1M Ono ISLA 2015 Sept28 - 30 2915
Masa Ono M Jaworski R Kaita T K Gray Y Hirooka and the NSTX-U research team
Liquid Lithium Applications for Solving Challenging Fusion Reactor Issues and NSTX-U Contributions
ISLA-4 Granada SpainSeptember 28 ndash 30 2015
2M Ono ISLA 2015 Sept28 - 30 2915
bull Introduction ndash Lithium can improve plasma performance but may solve some of the reactor technology challenges
bull Compatibility of lithium with reactor
bull Three major fusion reactor technology issuesndash Solving divertor heat flux issue Basic idea of the radiative
liquid lithium divertor concept
ndash Dust generation - lithium loop
ndash Controlling tritium inventory issue ndash cold trap
bull Summary
Outline
3M Ono ISLA 2015 Sept28 - 30 2915
bull NSTX tested applications of lithium in diverted H-mode tokamak configuration- Electron energy confinement improvement for improved plasma
performance (see for example R Maingi at this symposium)- Broader pressure and current profile for improved MHD stability- ELM control through edge electron pressure profile modification- Reduction in H-mode power threshold - Lower edge density and impurity control benefited rf heating and non-
inductive tokamak start-up- Lithium is an effective hydrogendeuterium pump - Very low lithium core dilution even with heavy lithium divertor application- Lithium improved NSTX operational efficiencies
NSTX experimental results suggest potential benefits for near-term and longer term tokamakST fusion development path
Lithium Improves H-mode Performance via Strong Pumping
Yet lithium does not appear to contaminate the plasma core
4M Ono ISLA 2015 Sept28 - 30 2915 4
Divertor heat load is very challenging for fusion reactors steady-state as well as transient ones
bull Unmitigated steady-state heat flux may exceed 40 MWm2 in ITER size 1GW-e power plant
bull Unmitigated ELM heat flux could reach 1 GWm2 bull Divertor PFCs can be only serviced maybe only once a year or twohellip
bull No solution exists for solid metal PFCs which continuously erode deteriorate and even melthellip
bull Liquid lithium PFCs looks attractive due to renewable surfaces and tolerance to transient events
5M Ono ISLA 2015 Sept28 - 30 2915 5
Steady state surface heat removal maybe limited to ~ 5 MWm2 solid or liquid metal PFCshellip
Tobita K et al 2009 Nucl Fusion 49 075029
bull Solid-based divertor PFC steady-state heat handling capability maybe limited to ~ 5 MWm2 for lt 1200degC PFC temperature with gt300 degC cooling temperature
bull Even liquid lithium based PFCs may be challenging handle steady-state ~ 5 MWm2 to keep PFC surface temperature to le 500 degC
M Jowarski et al at ISLA-3
Need to handle high heat flux gt 5 MWm2 volumetrically
6M Ono ISLA 2015 Sept28 - 30 2915
a)
b)
c)
d)
bull 2 identical shots (No ELMs)ndash Ip = 08 MA Pnbi ~ 4 MW
ndash high δ fexp ~ 20
bull 2 pre-discharge lithium depositionsndash 150 mg 141255
ndash 300 mg 138240bull Tsurf at the outer strike point stays below
400deg C for 300 mg of Lindash Peaks around 800deg C for 150 mg
bull Results in a heat flux that never peaks above 3 MWm2 with heavy lithium evaporation
bull No LLD surface damage observed
Lithiated graphite
T Gray NF 2014
Clear reduction in NSTX divertor surface temperature and heat flux with increased lithium evaporation
H Kugel FEampD 2012
NSTX-U can perform detailed assessment of Li radiation with LITER
7M Ono ISLA 2015 Sept28 - 30 2915
Lithium Provides Several Layers of Protection
Vaporization Ionization Radiation
7
Divertor side wall
LLD Tray
Li Injection (ARLLD)~ 100 MJmole
DivertorEntrance
Power and particle flux
Li Vapor Shielding
Li Radiative Cooling (RLLD)~ 100 MJmole
Li Vaporization (150 kJ mole)
Li Ionization1st ionization ndash 05 MJ mole 2nd ionization ndash 73 MJ mole 3rd ionization ndash 118 MJ mole
M Jaworski
Radial Transport Charge Exchange
Loss
T Abram
This talk emphasis
F Scotti VA Soukhanovskii et al NF 2013
TD Rognlien et al PoP 2002
8M Ono ISLA 2015 Sept28 - 30 2915
Divertor side wall
RLLD Tray
Active Injection of LL as First Line of Defense
Li injection as needed via feed-back control
Li Injection
DivertorEntrance
Power and particle flux
8
D Mansfield FEampD 2010
Lithium aerosol is introduced by a ldquodroperrdquo at the plasma edge and the ionized lithium tends to flow toward the divertor plate along the field line
Li Aerosol in NSTX
Li granular injector for NSTX-U
R Lunsford at this symposium
Li Radiative Mantle
Li ionized with Z = 2 and flows toward divertor
at Cs2
Cs2
R Goldston NF 2012
Li granular injector on NSTX-U will provide important data on ARLLD
9M Ono ISLA 2015 Sept28 - 30 2915
The Li radiation power per one atom and one electron in coronal-quilibrium (net = infinity) and non-equilibrium regimesS V Mirnov et al Plasma Phys Control Fusion (2006)
Assumed radiation
level in the modeling
calculation for RLLD
Coronal-Equilibrium Value
Strong (~x100) Li Radiation Level Over Coronal Eq
Low particle confinement could increase radiation in divertor
Divertor Heat and Particle Flux
Li paths
LLD Tray
t ~ 100 ms
9
Radiation ~ N-Lit N-Li~ Li-inj t Radiation ~ Li-inj ~ 100 MJmole
10M Ono ISLA 2015 Sept28 - 30 2915
Radiative Liquid Lithium Divertor Proposed Handle divertor heat load volumetrically (3D vs 2D)
M Ono NF 2013 FEampD 2014
10
Y Hirooka at this conference
Flowing LL Particle Pumping Surfaces
Li+
Li++
Li+++
Li0
Heat Exchanger
B0
Divertor Heat and Particles Flux
Liquid Lithium (LL) ~ 1 lsec for pumping dust removal
LL Purification System to remove tritium impurities and dust
Li Evap Ionization (RLLD)~ few molesec
Li Radiative Mantle
Li wall coating condensation
Li path
Reduced Divertor Heat and Particle
Flux
Particle pumping by Li
coated wall
Divertor Strike Point
RLLD ARLLD Lithium provides low recycling radiative divertor
Active LL Injection (ARLLD)~ few molesec
11M Ono ISLA 2015 Sept28 - 30 2915 11
Concerns for lithium in reactor applicationbull Lithium evaporation is too
high in reactor PFC temperatures of ~ 600 degC LL needs to be le 450degC
bull Lithium can trap tritium and make the tritium inventory issues worse
bull Lithium is volatile and unsafe
bull Lithium is corrosive
LL Surface Temp (degC)
Log N-Li m2-s Lithium Evaporation Rate
IFMIF International Fusion Materials Irradiation Facility
H Kondo et al FEampD (2012)
LL operating
range Reactor FW temperature
12M Ono ISLA 2015 Sept28 - 30 2915
High Temperature First Wallbull High electrical conversion bull Cleaner wall ndash lower T inventorybull There are ideas to use lithium for the
first allhellip
Lower RLLD Operating Temperaturebull Prevents excessive Li vaporization
pressure bull Cooler divertor provides natural
collection (pumping) surfaces for entire reactor chamber
bull May permit use of iron based material for substrates and structural material
bull Reduces Li corrosive issuesbull Provides safer LL utilization
First Wall BlanketAt 500degC ndash 700degC
000000000000
Core ReactingPlasma
Edge Plasma
Scrape Off Layer
Flowing LLD Tray 200 ndash 500 degC
Closed RLLD
LL Out LL InLL In
12
Compatibility with liquid lithium with a hot reactor first wall RLLD configuration permits operation at lower T lt 450 degC
13M Ono ISLA 2015 Sept28 - 30 2915 13
Liquid lithium could also solve long-standing fusion reactor technology challenges ndash dust generation and T inventory
bull Erosion redeposition from plasma sputtering and disruptions including dust and flake generation
bull Tritium retention and removal Dust could further aggravate tritium inventory issues
G Federici C H Skinner et al NF 111308820011113088
Solution Liquid lithium loop
IFMIFEVEDA RLLD LoopTotal LL amount 25 t 05 tFlow rate 50 ls lt 1 lsOperation 25 days Steady-stateTImpurity lt 001 lt1 Li target under the
IFMIF conditions (15 ms 10minus3 Pa 250 degC)H Kondo et al FEampD (2014)
M Jaworki et al for NSTX-U at this symposium
14M Ono ISLA 2015 Sept28 - 30 2915
Dust Generation Likely a Serious Issue for ReactorHowever nature and quantity of dust generation
unknown
14
LLCirculation
Pump
Divertor Heat and Particle Flux
LL 1 ls
Back to RLLDARLLD
Dust particle
filter
Tritiumimpurity removal loop
Purified LL
Dustparticle filters are located below divertor and dust are carried to filter by gravity action
bull Each dustparticle filters when fulll drained of LL and removedbull Removed filter processed to recover trapped tritium
15M Ono ISLA 2015 Sept28 - 30 2915
Cold Trap Could Remove T D H and O Cold trap can be regenerated at higher
temperatures
15
K Natesan JNM 1983
bull At 200 degC hydrogen can be reduced toward 01 levelbull Oxygen is also effectively reduced with cold trapbull Nitrogen would require separate hot nitrogen trap
Nearly ~ 10 in solubility
16M Ono ISLA 2015 Sept28 - 30 2915
Realtime Tritium Recovery Needed~ 05 gsec of tritium must be recovered in real
time
16
Tritium Recycling
TritiumSeparater
Deuterium ampOther impurities as
well as dust
T ndash 05 gs
T D H O
LLCold Trap
LLCold Trap
01 TTo RLLDARLLD
Parallel paths to enable regeneration while operation
Drain liquid lithium before regeneration
Multiple filters to enable regeneration
Valves and pumps not shown
200degC
1 TFrom dustparticle filter loop
01 lsec of 1 T LL can carry 05 gs of T
17M Ono ISLA 2015 Sept28 - 30 2915
Tritium Inventory Control in Fusion Power PlantTotal site inventory maybe ~ 50 days or ~ 20 kg
17
M Nishikawa FST 2010
bull 1 (by weight) tritium concentration LL contains ~ 5 g of T l
bull LL inside VV may contain 100 l of LL or 05 kg for RLLDARLLD
bull LL in LL-loop before and in cold traps (~ 1) may contain 500 l of LL or 25 kg
bull LL after cold traps (~ 01) may contain 500 l of LL or 025kg
bull Total tritium inventory in RLLDALLD may contains 325 kg of T which is about 8 days ltlt 50 days
LL system may be compatible with the fusion reactor power plant tritium inventory requirements
18M Ono ISLA 2015 Sept28 - 30 2915
NSTX-U Construction complete First Plasma on August 10 2015
HHFW System
1st NBI
2nd NBI
NSTX-U
MPTS Exit Flight Tube
19M Ono ISLA 2015 Sept28 - 30 2915
LITERs
Comprehensive Lithium Boundary Physics ToolsBoronization Lithium Evaporators Granule Injector High Z tiles
Lithium Evaporator (LITERs)
Upward Li evaporator
High Z Tiles
T-bar mount
Castellations
Granule injector (GI) for ELM pacing
Rotating Impeller
Successfully tested on EAST and DIII-DGranules Li B4C Cf ~ up to 500 Hz
dTMB Gas Cabinet
Boronization System
Granular Reservoir
Electron beam for flash evaporation
crucible
FY 2016
FY 2016
20M Ono ISLA 2015 Sept28 - 30 2915
Enhanced Capability for Lithium PMI ResearchMulti-Institutional Contributions
ORNL
Lithium CHERS
Divertor ImagingSpectrometer
Dual-band fast IR Camera
Two fast 2D visible and IR cameras with full divertor coverage
Li I
C II
MAPP probe for between-shots surface analysis ndash Tested in LTX
LLNL ORNL UT-K
LLNL
Divertor fast pressure gauges
ORNL
Divertor fast eroding thermocouples
R Kaita at this symposium
21M Ono ISLA 2015 Sept28 - 30 2915
bull Lithium was observed to improve fusion plasma performance
bull Radiative LL Divertor (RLLD) and Active version of RLLD (ARLLD) are proposed to solve divertor heat flux issues
bull More experimental data needed to assess effectiveness of lithium radiation (lithium granular injection in NSTX-U planned)
bull Compatibility issues of lithium with fusion reactor were examined
bull Dustparticles are collected under divertor by a set of filters mainly by the gravity action
bull Tritium is removed in real time with a set of cold traps
bull Tritium inventory issue maybe manageable
bull NSTX-U is now starting to support lithium program (M Jaworski)
Summary Lithium could solve several critical reactor issues
2M Ono ISLA 2015 Sept28 - 30 2915
bull Introduction ndash Lithium can improve plasma performance but may solve some of the reactor technology challenges
bull Compatibility of lithium with reactor
bull Three major fusion reactor technology issuesndash Solving divertor heat flux issue Basic idea of the radiative
liquid lithium divertor concept
ndash Dust generation - lithium loop
ndash Controlling tritium inventory issue ndash cold trap
bull Summary
Outline
3M Ono ISLA 2015 Sept28 - 30 2915
bull NSTX tested applications of lithium in diverted H-mode tokamak configuration- Electron energy confinement improvement for improved plasma
performance (see for example R Maingi at this symposium)- Broader pressure and current profile for improved MHD stability- ELM control through edge electron pressure profile modification- Reduction in H-mode power threshold - Lower edge density and impurity control benefited rf heating and non-
inductive tokamak start-up- Lithium is an effective hydrogendeuterium pump - Very low lithium core dilution even with heavy lithium divertor application- Lithium improved NSTX operational efficiencies
NSTX experimental results suggest potential benefits for near-term and longer term tokamakST fusion development path
Lithium Improves H-mode Performance via Strong Pumping
Yet lithium does not appear to contaminate the plasma core
4M Ono ISLA 2015 Sept28 - 30 2915 4
Divertor heat load is very challenging for fusion reactors steady-state as well as transient ones
bull Unmitigated steady-state heat flux may exceed 40 MWm2 in ITER size 1GW-e power plant
bull Unmitigated ELM heat flux could reach 1 GWm2 bull Divertor PFCs can be only serviced maybe only once a year or twohellip
bull No solution exists for solid metal PFCs which continuously erode deteriorate and even melthellip
bull Liquid lithium PFCs looks attractive due to renewable surfaces and tolerance to transient events
5M Ono ISLA 2015 Sept28 - 30 2915 5
Steady state surface heat removal maybe limited to ~ 5 MWm2 solid or liquid metal PFCshellip
Tobita K et al 2009 Nucl Fusion 49 075029
bull Solid-based divertor PFC steady-state heat handling capability maybe limited to ~ 5 MWm2 for lt 1200degC PFC temperature with gt300 degC cooling temperature
bull Even liquid lithium based PFCs may be challenging handle steady-state ~ 5 MWm2 to keep PFC surface temperature to le 500 degC
M Jowarski et al at ISLA-3
Need to handle high heat flux gt 5 MWm2 volumetrically
6M Ono ISLA 2015 Sept28 - 30 2915
a)
b)
c)
d)
bull 2 identical shots (No ELMs)ndash Ip = 08 MA Pnbi ~ 4 MW
ndash high δ fexp ~ 20
bull 2 pre-discharge lithium depositionsndash 150 mg 141255
ndash 300 mg 138240bull Tsurf at the outer strike point stays below
400deg C for 300 mg of Lindash Peaks around 800deg C for 150 mg
bull Results in a heat flux that never peaks above 3 MWm2 with heavy lithium evaporation
bull No LLD surface damage observed
Lithiated graphite
T Gray NF 2014
Clear reduction in NSTX divertor surface temperature and heat flux with increased lithium evaporation
H Kugel FEampD 2012
NSTX-U can perform detailed assessment of Li radiation with LITER
7M Ono ISLA 2015 Sept28 - 30 2915
Lithium Provides Several Layers of Protection
Vaporization Ionization Radiation
7
Divertor side wall
LLD Tray
Li Injection (ARLLD)~ 100 MJmole
DivertorEntrance
Power and particle flux
Li Vapor Shielding
Li Radiative Cooling (RLLD)~ 100 MJmole
Li Vaporization (150 kJ mole)
Li Ionization1st ionization ndash 05 MJ mole 2nd ionization ndash 73 MJ mole 3rd ionization ndash 118 MJ mole
M Jaworski
Radial Transport Charge Exchange
Loss
T Abram
This talk emphasis
F Scotti VA Soukhanovskii et al NF 2013
TD Rognlien et al PoP 2002
8M Ono ISLA 2015 Sept28 - 30 2915
Divertor side wall
RLLD Tray
Active Injection of LL as First Line of Defense
Li injection as needed via feed-back control
Li Injection
DivertorEntrance
Power and particle flux
8
D Mansfield FEampD 2010
Lithium aerosol is introduced by a ldquodroperrdquo at the plasma edge and the ionized lithium tends to flow toward the divertor plate along the field line
Li Aerosol in NSTX
Li granular injector for NSTX-U
R Lunsford at this symposium
Li Radiative Mantle
Li ionized with Z = 2 and flows toward divertor
at Cs2
Cs2
R Goldston NF 2012
Li granular injector on NSTX-U will provide important data on ARLLD
9M Ono ISLA 2015 Sept28 - 30 2915
The Li radiation power per one atom and one electron in coronal-quilibrium (net = infinity) and non-equilibrium regimesS V Mirnov et al Plasma Phys Control Fusion (2006)
Assumed radiation
level in the modeling
calculation for RLLD
Coronal-Equilibrium Value
Strong (~x100) Li Radiation Level Over Coronal Eq
Low particle confinement could increase radiation in divertor
Divertor Heat and Particle Flux
Li paths
LLD Tray
t ~ 100 ms
9
Radiation ~ N-Lit N-Li~ Li-inj t Radiation ~ Li-inj ~ 100 MJmole
10M Ono ISLA 2015 Sept28 - 30 2915
Radiative Liquid Lithium Divertor Proposed Handle divertor heat load volumetrically (3D vs 2D)
M Ono NF 2013 FEampD 2014
10
Y Hirooka at this conference
Flowing LL Particle Pumping Surfaces
Li+
Li++
Li+++
Li0
Heat Exchanger
B0
Divertor Heat and Particles Flux
Liquid Lithium (LL) ~ 1 lsec for pumping dust removal
LL Purification System to remove tritium impurities and dust
Li Evap Ionization (RLLD)~ few molesec
Li Radiative Mantle
Li wall coating condensation
Li path
Reduced Divertor Heat and Particle
Flux
Particle pumping by Li
coated wall
Divertor Strike Point
RLLD ARLLD Lithium provides low recycling radiative divertor
Active LL Injection (ARLLD)~ few molesec
11M Ono ISLA 2015 Sept28 - 30 2915 11
Concerns for lithium in reactor applicationbull Lithium evaporation is too
high in reactor PFC temperatures of ~ 600 degC LL needs to be le 450degC
bull Lithium can trap tritium and make the tritium inventory issues worse
bull Lithium is volatile and unsafe
bull Lithium is corrosive
LL Surface Temp (degC)
Log N-Li m2-s Lithium Evaporation Rate
IFMIF International Fusion Materials Irradiation Facility
H Kondo et al FEampD (2012)
LL operating
range Reactor FW temperature
12M Ono ISLA 2015 Sept28 - 30 2915
High Temperature First Wallbull High electrical conversion bull Cleaner wall ndash lower T inventorybull There are ideas to use lithium for the
first allhellip
Lower RLLD Operating Temperaturebull Prevents excessive Li vaporization
pressure bull Cooler divertor provides natural
collection (pumping) surfaces for entire reactor chamber
bull May permit use of iron based material for substrates and structural material
bull Reduces Li corrosive issuesbull Provides safer LL utilization
First Wall BlanketAt 500degC ndash 700degC
000000000000
Core ReactingPlasma
Edge Plasma
Scrape Off Layer
Flowing LLD Tray 200 ndash 500 degC
Closed RLLD
LL Out LL InLL In
12
Compatibility with liquid lithium with a hot reactor first wall RLLD configuration permits operation at lower T lt 450 degC
13M Ono ISLA 2015 Sept28 - 30 2915 13
Liquid lithium could also solve long-standing fusion reactor technology challenges ndash dust generation and T inventory
bull Erosion redeposition from plasma sputtering and disruptions including dust and flake generation
bull Tritium retention and removal Dust could further aggravate tritium inventory issues
G Federici C H Skinner et al NF 111308820011113088
Solution Liquid lithium loop
IFMIFEVEDA RLLD LoopTotal LL amount 25 t 05 tFlow rate 50 ls lt 1 lsOperation 25 days Steady-stateTImpurity lt 001 lt1 Li target under the
IFMIF conditions (15 ms 10minus3 Pa 250 degC)H Kondo et al FEampD (2014)
M Jaworki et al for NSTX-U at this symposium
14M Ono ISLA 2015 Sept28 - 30 2915
Dust Generation Likely a Serious Issue for ReactorHowever nature and quantity of dust generation
unknown
14
LLCirculation
Pump
Divertor Heat and Particle Flux
LL 1 ls
Back to RLLDARLLD
Dust particle
filter
Tritiumimpurity removal loop
Purified LL
Dustparticle filters are located below divertor and dust are carried to filter by gravity action
bull Each dustparticle filters when fulll drained of LL and removedbull Removed filter processed to recover trapped tritium
15M Ono ISLA 2015 Sept28 - 30 2915
Cold Trap Could Remove T D H and O Cold trap can be regenerated at higher
temperatures
15
K Natesan JNM 1983
bull At 200 degC hydrogen can be reduced toward 01 levelbull Oxygen is also effectively reduced with cold trapbull Nitrogen would require separate hot nitrogen trap
Nearly ~ 10 in solubility
16M Ono ISLA 2015 Sept28 - 30 2915
Realtime Tritium Recovery Needed~ 05 gsec of tritium must be recovered in real
time
16
Tritium Recycling
TritiumSeparater
Deuterium ampOther impurities as
well as dust
T ndash 05 gs
T D H O
LLCold Trap
LLCold Trap
01 TTo RLLDARLLD
Parallel paths to enable regeneration while operation
Drain liquid lithium before regeneration
Multiple filters to enable regeneration
Valves and pumps not shown
200degC
1 TFrom dustparticle filter loop
01 lsec of 1 T LL can carry 05 gs of T
17M Ono ISLA 2015 Sept28 - 30 2915
Tritium Inventory Control in Fusion Power PlantTotal site inventory maybe ~ 50 days or ~ 20 kg
17
M Nishikawa FST 2010
bull 1 (by weight) tritium concentration LL contains ~ 5 g of T l
bull LL inside VV may contain 100 l of LL or 05 kg for RLLDARLLD
bull LL in LL-loop before and in cold traps (~ 1) may contain 500 l of LL or 25 kg
bull LL after cold traps (~ 01) may contain 500 l of LL or 025kg
bull Total tritium inventory in RLLDALLD may contains 325 kg of T which is about 8 days ltlt 50 days
LL system may be compatible with the fusion reactor power plant tritium inventory requirements
18M Ono ISLA 2015 Sept28 - 30 2915
NSTX-U Construction complete First Plasma on August 10 2015
HHFW System
1st NBI
2nd NBI
NSTX-U
MPTS Exit Flight Tube
19M Ono ISLA 2015 Sept28 - 30 2915
LITERs
Comprehensive Lithium Boundary Physics ToolsBoronization Lithium Evaporators Granule Injector High Z tiles
Lithium Evaporator (LITERs)
Upward Li evaporator
High Z Tiles
T-bar mount
Castellations
Granule injector (GI) for ELM pacing
Rotating Impeller
Successfully tested on EAST and DIII-DGranules Li B4C Cf ~ up to 500 Hz
dTMB Gas Cabinet
Boronization System
Granular Reservoir
Electron beam for flash evaporation
crucible
FY 2016
FY 2016
20M Ono ISLA 2015 Sept28 - 30 2915
Enhanced Capability for Lithium PMI ResearchMulti-Institutional Contributions
ORNL
Lithium CHERS
Divertor ImagingSpectrometer
Dual-band fast IR Camera
Two fast 2D visible and IR cameras with full divertor coverage
Li I
C II
MAPP probe for between-shots surface analysis ndash Tested in LTX
LLNL ORNL UT-K
LLNL
Divertor fast pressure gauges
ORNL
Divertor fast eroding thermocouples
R Kaita at this symposium
21M Ono ISLA 2015 Sept28 - 30 2915
bull Lithium was observed to improve fusion plasma performance
bull Radiative LL Divertor (RLLD) and Active version of RLLD (ARLLD) are proposed to solve divertor heat flux issues
bull More experimental data needed to assess effectiveness of lithium radiation (lithium granular injection in NSTX-U planned)
bull Compatibility issues of lithium with fusion reactor were examined
bull Dustparticles are collected under divertor by a set of filters mainly by the gravity action
bull Tritium is removed in real time with a set of cold traps
bull Tritium inventory issue maybe manageable
bull NSTX-U is now starting to support lithium program (M Jaworski)
Summary Lithium could solve several critical reactor issues
3M Ono ISLA 2015 Sept28 - 30 2915
bull NSTX tested applications of lithium in diverted H-mode tokamak configuration- Electron energy confinement improvement for improved plasma
performance (see for example R Maingi at this symposium)- Broader pressure and current profile for improved MHD stability- ELM control through edge electron pressure profile modification- Reduction in H-mode power threshold - Lower edge density and impurity control benefited rf heating and non-
inductive tokamak start-up- Lithium is an effective hydrogendeuterium pump - Very low lithium core dilution even with heavy lithium divertor application- Lithium improved NSTX operational efficiencies
NSTX experimental results suggest potential benefits for near-term and longer term tokamakST fusion development path
Lithium Improves H-mode Performance via Strong Pumping
Yet lithium does not appear to contaminate the plasma core
4M Ono ISLA 2015 Sept28 - 30 2915 4
Divertor heat load is very challenging for fusion reactors steady-state as well as transient ones
bull Unmitigated steady-state heat flux may exceed 40 MWm2 in ITER size 1GW-e power plant
bull Unmitigated ELM heat flux could reach 1 GWm2 bull Divertor PFCs can be only serviced maybe only once a year or twohellip
bull No solution exists for solid metal PFCs which continuously erode deteriorate and even melthellip
bull Liquid lithium PFCs looks attractive due to renewable surfaces and tolerance to transient events
5M Ono ISLA 2015 Sept28 - 30 2915 5
Steady state surface heat removal maybe limited to ~ 5 MWm2 solid or liquid metal PFCshellip
Tobita K et al 2009 Nucl Fusion 49 075029
bull Solid-based divertor PFC steady-state heat handling capability maybe limited to ~ 5 MWm2 for lt 1200degC PFC temperature with gt300 degC cooling temperature
bull Even liquid lithium based PFCs may be challenging handle steady-state ~ 5 MWm2 to keep PFC surface temperature to le 500 degC
M Jowarski et al at ISLA-3
Need to handle high heat flux gt 5 MWm2 volumetrically
6M Ono ISLA 2015 Sept28 - 30 2915
a)
b)
c)
d)
bull 2 identical shots (No ELMs)ndash Ip = 08 MA Pnbi ~ 4 MW
ndash high δ fexp ~ 20
bull 2 pre-discharge lithium depositionsndash 150 mg 141255
ndash 300 mg 138240bull Tsurf at the outer strike point stays below
400deg C for 300 mg of Lindash Peaks around 800deg C for 150 mg
bull Results in a heat flux that never peaks above 3 MWm2 with heavy lithium evaporation
bull No LLD surface damage observed
Lithiated graphite
T Gray NF 2014
Clear reduction in NSTX divertor surface temperature and heat flux with increased lithium evaporation
H Kugel FEampD 2012
NSTX-U can perform detailed assessment of Li radiation with LITER
7M Ono ISLA 2015 Sept28 - 30 2915
Lithium Provides Several Layers of Protection
Vaporization Ionization Radiation
7
Divertor side wall
LLD Tray
Li Injection (ARLLD)~ 100 MJmole
DivertorEntrance
Power and particle flux
Li Vapor Shielding
Li Radiative Cooling (RLLD)~ 100 MJmole
Li Vaporization (150 kJ mole)
Li Ionization1st ionization ndash 05 MJ mole 2nd ionization ndash 73 MJ mole 3rd ionization ndash 118 MJ mole
M Jaworski
Radial Transport Charge Exchange
Loss
T Abram
This talk emphasis
F Scotti VA Soukhanovskii et al NF 2013
TD Rognlien et al PoP 2002
8M Ono ISLA 2015 Sept28 - 30 2915
Divertor side wall
RLLD Tray
Active Injection of LL as First Line of Defense
Li injection as needed via feed-back control
Li Injection
DivertorEntrance
Power and particle flux
8
D Mansfield FEampD 2010
Lithium aerosol is introduced by a ldquodroperrdquo at the plasma edge and the ionized lithium tends to flow toward the divertor plate along the field line
Li Aerosol in NSTX
Li granular injector for NSTX-U
R Lunsford at this symposium
Li Radiative Mantle
Li ionized with Z = 2 and flows toward divertor
at Cs2
Cs2
R Goldston NF 2012
Li granular injector on NSTX-U will provide important data on ARLLD
9M Ono ISLA 2015 Sept28 - 30 2915
The Li radiation power per one atom and one electron in coronal-quilibrium (net = infinity) and non-equilibrium regimesS V Mirnov et al Plasma Phys Control Fusion (2006)
Assumed radiation
level in the modeling
calculation for RLLD
Coronal-Equilibrium Value
Strong (~x100) Li Radiation Level Over Coronal Eq
Low particle confinement could increase radiation in divertor
Divertor Heat and Particle Flux
Li paths
LLD Tray
t ~ 100 ms
9
Radiation ~ N-Lit N-Li~ Li-inj t Radiation ~ Li-inj ~ 100 MJmole
10M Ono ISLA 2015 Sept28 - 30 2915
Radiative Liquid Lithium Divertor Proposed Handle divertor heat load volumetrically (3D vs 2D)
M Ono NF 2013 FEampD 2014
10
Y Hirooka at this conference
Flowing LL Particle Pumping Surfaces
Li+
Li++
Li+++
Li0
Heat Exchanger
B0
Divertor Heat and Particles Flux
Liquid Lithium (LL) ~ 1 lsec for pumping dust removal
LL Purification System to remove tritium impurities and dust
Li Evap Ionization (RLLD)~ few molesec
Li Radiative Mantle
Li wall coating condensation
Li path
Reduced Divertor Heat and Particle
Flux
Particle pumping by Li
coated wall
Divertor Strike Point
RLLD ARLLD Lithium provides low recycling radiative divertor
Active LL Injection (ARLLD)~ few molesec
11M Ono ISLA 2015 Sept28 - 30 2915 11
Concerns for lithium in reactor applicationbull Lithium evaporation is too
high in reactor PFC temperatures of ~ 600 degC LL needs to be le 450degC
bull Lithium can trap tritium and make the tritium inventory issues worse
bull Lithium is volatile and unsafe
bull Lithium is corrosive
LL Surface Temp (degC)
Log N-Li m2-s Lithium Evaporation Rate
IFMIF International Fusion Materials Irradiation Facility
H Kondo et al FEampD (2012)
LL operating
range Reactor FW temperature
12M Ono ISLA 2015 Sept28 - 30 2915
High Temperature First Wallbull High electrical conversion bull Cleaner wall ndash lower T inventorybull There are ideas to use lithium for the
first allhellip
Lower RLLD Operating Temperaturebull Prevents excessive Li vaporization
pressure bull Cooler divertor provides natural
collection (pumping) surfaces for entire reactor chamber
bull May permit use of iron based material for substrates and structural material
bull Reduces Li corrosive issuesbull Provides safer LL utilization
First Wall BlanketAt 500degC ndash 700degC
000000000000
Core ReactingPlasma
Edge Plasma
Scrape Off Layer
Flowing LLD Tray 200 ndash 500 degC
Closed RLLD
LL Out LL InLL In
12
Compatibility with liquid lithium with a hot reactor first wall RLLD configuration permits operation at lower T lt 450 degC
13M Ono ISLA 2015 Sept28 - 30 2915 13
Liquid lithium could also solve long-standing fusion reactor technology challenges ndash dust generation and T inventory
bull Erosion redeposition from plasma sputtering and disruptions including dust and flake generation
bull Tritium retention and removal Dust could further aggravate tritium inventory issues
G Federici C H Skinner et al NF 111308820011113088
Solution Liquid lithium loop
IFMIFEVEDA RLLD LoopTotal LL amount 25 t 05 tFlow rate 50 ls lt 1 lsOperation 25 days Steady-stateTImpurity lt 001 lt1 Li target under the
IFMIF conditions (15 ms 10minus3 Pa 250 degC)H Kondo et al FEampD (2014)
M Jaworki et al for NSTX-U at this symposium
14M Ono ISLA 2015 Sept28 - 30 2915
Dust Generation Likely a Serious Issue for ReactorHowever nature and quantity of dust generation
unknown
14
LLCirculation
Pump
Divertor Heat and Particle Flux
LL 1 ls
Back to RLLDARLLD
Dust particle
filter
Tritiumimpurity removal loop
Purified LL
Dustparticle filters are located below divertor and dust are carried to filter by gravity action
bull Each dustparticle filters when fulll drained of LL and removedbull Removed filter processed to recover trapped tritium
15M Ono ISLA 2015 Sept28 - 30 2915
Cold Trap Could Remove T D H and O Cold trap can be regenerated at higher
temperatures
15
K Natesan JNM 1983
bull At 200 degC hydrogen can be reduced toward 01 levelbull Oxygen is also effectively reduced with cold trapbull Nitrogen would require separate hot nitrogen trap
Nearly ~ 10 in solubility
16M Ono ISLA 2015 Sept28 - 30 2915
Realtime Tritium Recovery Needed~ 05 gsec of tritium must be recovered in real
time
16
Tritium Recycling
TritiumSeparater
Deuterium ampOther impurities as
well as dust
T ndash 05 gs
T D H O
LLCold Trap
LLCold Trap
01 TTo RLLDARLLD
Parallel paths to enable regeneration while operation
Drain liquid lithium before regeneration
Multiple filters to enable regeneration
Valves and pumps not shown
200degC
1 TFrom dustparticle filter loop
01 lsec of 1 T LL can carry 05 gs of T
17M Ono ISLA 2015 Sept28 - 30 2915
Tritium Inventory Control in Fusion Power PlantTotal site inventory maybe ~ 50 days or ~ 20 kg
17
M Nishikawa FST 2010
bull 1 (by weight) tritium concentration LL contains ~ 5 g of T l
bull LL inside VV may contain 100 l of LL or 05 kg for RLLDARLLD
bull LL in LL-loop before and in cold traps (~ 1) may contain 500 l of LL or 25 kg
bull LL after cold traps (~ 01) may contain 500 l of LL or 025kg
bull Total tritium inventory in RLLDALLD may contains 325 kg of T which is about 8 days ltlt 50 days
LL system may be compatible with the fusion reactor power plant tritium inventory requirements
18M Ono ISLA 2015 Sept28 - 30 2915
NSTX-U Construction complete First Plasma on August 10 2015
HHFW System
1st NBI
2nd NBI
NSTX-U
MPTS Exit Flight Tube
19M Ono ISLA 2015 Sept28 - 30 2915
LITERs
Comprehensive Lithium Boundary Physics ToolsBoronization Lithium Evaporators Granule Injector High Z tiles
Lithium Evaporator (LITERs)
Upward Li evaporator
High Z Tiles
T-bar mount
Castellations
Granule injector (GI) for ELM pacing
Rotating Impeller
Successfully tested on EAST and DIII-DGranules Li B4C Cf ~ up to 500 Hz
dTMB Gas Cabinet
Boronization System
Granular Reservoir
Electron beam for flash evaporation
crucible
FY 2016
FY 2016
20M Ono ISLA 2015 Sept28 - 30 2915
Enhanced Capability for Lithium PMI ResearchMulti-Institutional Contributions
ORNL
Lithium CHERS
Divertor ImagingSpectrometer
Dual-band fast IR Camera
Two fast 2D visible and IR cameras with full divertor coverage
Li I
C II
MAPP probe for between-shots surface analysis ndash Tested in LTX
LLNL ORNL UT-K
LLNL
Divertor fast pressure gauges
ORNL
Divertor fast eroding thermocouples
R Kaita at this symposium
21M Ono ISLA 2015 Sept28 - 30 2915
bull Lithium was observed to improve fusion plasma performance
bull Radiative LL Divertor (RLLD) and Active version of RLLD (ARLLD) are proposed to solve divertor heat flux issues
bull More experimental data needed to assess effectiveness of lithium radiation (lithium granular injection in NSTX-U planned)
bull Compatibility issues of lithium with fusion reactor were examined
bull Dustparticles are collected under divertor by a set of filters mainly by the gravity action
bull Tritium is removed in real time with a set of cold traps
bull Tritium inventory issue maybe manageable
bull NSTX-U is now starting to support lithium program (M Jaworski)
Summary Lithium could solve several critical reactor issues
4M Ono ISLA 2015 Sept28 - 30 2915 4
Divertor heat load is very challenging for fusion reactors steady-state as well as transient ones
bull Unmitigated steady-state heat flux may exceed 40 MWm2 in ITER size 1GW-e power plant
bull Unmitigated ELM heat flux could reach 1 GWm2 bull Divertor PFCs can be only serviced maybe only once a year or twohellip
bull No solution exists for solid metal PFCs which continuously erode deteriorate and even melthellip
bull Liquid lithium PFCs looks attractive due to renewable surfaces and tolerance to transient events
5M Ono ISLA 2015 Sept28 - 30 2915 5
Steady state surface heat removal maybe limited to ~ 5 MWm2 solid or liquid metal PFCshellip
Tobita K et al 2009 Nucl Fusion 49 075029
bull Solid-based divertor PFC steady-state heat handling capability maybe limited to ~ 5 MWm2 for lt 1200degC PFC temperature with gt300 degC cooling temperature
bull Even liquid lithium based PFCs may be challenging handle steady-state ~ 5 MWm2 to keep PFC surface temperature to le 500 degC
M Jowarski et al at ISLA-3
Need to handle high heat flux gt 5 MWm2 volumetrically
6M Ono ISLA 2015 Sept28 - 30 2915
a)
b)
c)
d)
bull 2 identical shots (No ELMs)ndash Ip = 08 MA Pnbi ~ 4 MW
ndash high δ fexp ~ 20
bull 2 pre-discharge lithium depositionsndash 150 mg 141255
ndash 300 mg 138240bull Tsurf at the outer strike point stays below
400deg C for 300 mg of Lindash Peaks around 800deg C for 150 mg
bull Results in a heat flux that never peaks above 3 MWm2 with heavy lithium evaporation
bull No LLD surface damage observed
Lithiated graphite
T Gray NF 2014
Clear reduction in NSTX divertor surface temperature and heat flux with increased lithium evaporation
H Kugel FEampD 2012
NSTX-U can perform detailed assessment of Li radiation with LITER
7M Ono ISLA 2015 Sept28 - 30 2915
Lithium Provides Several Layers of Protection
Vaporization Ionization Radiation
7
Divertor side wall
LLD Tray
Li Injection (ARLLD)~ 100 MJmole
DivertorEntrance
Power and particle flux
Li Vapor Shielding
Li Radiative Cooling (RLLD)~ 100 MJmole
Li Vaporization (150 kJ mole)
Li Ionization1st ionization ndash 05 MJ mole 2nd ionization ndash 73 MJ mole 3rd ionization ndash 118 MJ mole
M Jaworski
Radial Transport Charge Exchange
Loss
T Abram
This talk emphasis
F Scotti VA Soukhanovskii et al NF 2013
TD Rognlien et al PoP 2002
8M Ono ISLA 2015 Sept28 - 30 2915
Divertor side wall
RLLD Tray
Active Injection of LL as First Line of Defense
Li injection as needed via feed-back control
Li Injection
DivertorEntrance
Power and particle flux
8
D Mansfield FEampD 2010
Lithium aerosol is introduced by a ldquodroperrdquo at the plasma edge and the ionized lithium tends to flow toward the divertor plate along the field line
Li Aerosol in NSTX
Li granular injector for NSTX-U
R Lunsford at this symposium
Li Radiative Mantle
Li ionized with Z = 2 and flows toward divertor
at Cs2
Cs2
R Goldston NF 2012
Li granular injector on NSTX-U will provide important data on ARLLD
9M Ono ISLA 2015 Sept28 - 30 2915
The Li radiation power per one atom and one electron in coronal-quilibrium (net = infinity) and non-equilibrium regimesS V Mirnov et al Plasma Phys Control Fusion (2006)
Assumed radiation
level in the modeling
calculation for RLLD
Coronal-Equilibrium Value
Strong (~x100) Li Radiation Level Over Coronal Eq
Low particle confinement could increase radiation in divertor
Divertor Heat and Particle Flux
Li paths
LLD Tray
t ~ 100 ms
9
Radiation ~ N-Lit N-Li~ Li-inj t Radiation ~ Li-inj ~ 100 MJmole
10M Ono ISLA 2015 Sept28 - 30 2915
Radiative Liquid Lithium Divertor Proposed Handle divertor heat load volumetrically (3D vs 2D)
M Ono NF 2013 FEampD 2014
10
Y Hirooka at this conference
Flowing LL Particle Pumping Surfaces
Li+
Li++
Li+++
Li0
Heat Exchanger
B0
Divertor Heat and Particles Flux
Liquid Lithium (LL) ~ 1 lsec for pumping dust removal
LL Purification System to remove tritium impurities and dust
Li Evap Ionization (RLLD)~ few molesec
Li Radiative Mantle
Li wall coating condensation
Li path
Reduced Divertor Heat and Particle
Flux
Particle pumping by Li
coated wall
Divertor Strike Point
RLLD ARLLD Lithium provides low recycling radiative divertor
Active LL Injection (ARLLD)~ few molesec
11M Ono ISLA 2015 Sept28 - 30 2915 11
Concerns for lithium in reactor applicationbull Lithium evaporation is too
high in reactor PFC temperatures of ~ 600 degC LL needs to be le 450degC
bull Lithium can trap tritium and make the tritium inventory issues worse
bull Lithium is volatile and unsafe
bull Lithium is corrosive
LL Surface Temp (degC)
Log N-Li m2-s Lithium Evaporation Rate
IFMIF International Fusion Materials Irradiation Facility
H Kondo et al FEampD (2012)
LL operating
range Reactor FW temperature
12M Ono ISLA 2015 Sept28 - 30 2915
High Temperature First Wallbull High electrical conversion bull Cleaner wall ndash lower T inventorybull There are ideas to use lithium for the
first allhellip
Lower RLLD Operating Temperaturebull Prevents excessive Li vaporization
pressure bull Cooler divertor provides natural
collection (pumping) surfaces for entire reactor chamber
bull May permit use of iron based material for substrates and structural material
bull Reduces Li corrosive issuesbull Provides safer LL utilization
First Wall BlanketAt 500degC ndash 700degC
000000000000
Core ReactingPlasma
Edge Plasma
Scrape Off Layer
Flowing LLD Tray 200 ndash 500 degC
Closed RLLD
LL Out LL InLL In
12
Compatibility with liquid lithium with a hot reactor first wall RLLD configuration permits operation at lower T lt 450 degC
13M Ono ISLA 2015 Sept28 - 30 2915 13
Liquid lithium could also solve long-standing fusion reactor technology challenges ndash dust generation and T inventory
bull Erosion redeposition from plasma sputtering and disruptions including dust and flake generation
bull Tritium retention and removal Dust could further aggravate tritium inventory issues
G Federici C H Skinner et al NF 111308820011113088
Solution Liquid lithium loop
IFMIFEVEDA RLLD LoopTotal LL amount 25 t 05 tFlow rate 50 ls lt 1 lsOperation 25 days Steady-stateTImpurity lt 001 lt1 Li target under the
IFMIF conditions (15 ms 10minus3 Pa 250 degC)H Kondo et al FEampD (2014)
M Jaworki et al for NSTX-U at this symposium
14M Ono ISLA 2015 Sept28 - 30 2915
Dust Generation Likely a Serious Issue for ReactorHowever nature and quantity of dust generation
unknown
14
LLCirculation
Pump
Divertor Heat and Particle Flux
LL 1 ls
Back to RLLDARLLD
Dust particle
filter
Tritiumimpurity removal loop
Purified LL
Dustparticle filters are located below divertor and dust are carried to filter by gravity action
bull Each dustparticle filters when fulll drained of LL and removedbull Removed filter processed to recover trapped tritium
15M Ono ISLA 2015 Sept28 - 30 2915
Cold Trap Could Remove T D H and O Cold trap can be regenerated at higher
temperatures
15
K Natesan JNM 1983
bull At 200 degC hydrogen can be reduced toward 01 levelbull Oxygen is also effectively reduced with cold trapbull Nitrogen would require separate hot nitrogen trap
Nearly ~ 10 in solubility
16M Ono ISLA 2015 Sept28 - 30 2915
Realtime Tritium Recovery Needed~ 05 gsec of tritium must be recovered in real
time
16
Tritium Recycling
TritiumSeparater
Deuterium ampOther impurities as
well as dust
T ndash 05 gs
T D H O
LLCold Trap
LLCold Trap
01 TTo RLLDARLLD
Parallel paths to enable regeneration while operation
Drain liquid lithium before regeneration
Multiple filters to enable regeneration
Valves and pumps not shown
200degC
1 TFrom dustparticle filter loop
01 lsec of 1 T LL can carry 05 gs of T
17M Ono ISLA 2015 Sept28 - 30 2915
Tritium Inventory Control in Fusion Power PlantTotal site inventory maybe ~ 50 days or ~ 20 kg
17
M Nishikawa FST 2010
bull 1 (by weight) tritium concentration LL contains ~ 5 g of T l
bull LL inside VV may contain 100 l of LL or 05 kg for RLLDARLLD
bull LL in LL-loop before and in cold traps (~ 1) may contain 500 l of LL or 25 kg
bull LL after cold traps (~ 01) may contain 500 l of LL or 025kg
bull Total tritium inventory in RLLDALLD may contains 325 kg of T which is about 8 days ltlt 50 days
LL system may be compatible with the fusion reactor power plant tritium inventory requirements
18M Ono ISLA 2015 Sept28 - 30 2915
NSTX-U Construction complete First Plasma on August 10 2015
HHFW System
1st NBI
2nd NBI
NSTX-U
MPTS Exit Flight Tube
19M Ono ISLA 2015 Sept28 - 30 2915
LITERs
Comprehensive Lithium Boundary Physics ToolsBoronization Lithium Evaporators Granule Injector High Z tiles
Lithium Evaporator (LITERs)
Upward Li evaporator
High Z Tiles
T-bar mount
Castellations
Granule injector (GI) for ELM pacing
Rotating Impeller
Successfully tested on EAST and DIII-DGranules Li B4C Cf ~ up to 500 Hz
dTMB Gas Cabinet
Boronization System
Granular Reservoir
Electron beam for flash evaporation
crucible
FY 2016
FY 2016
20M Ono ISLA 2015 Sept28 - 30 2915
Enhanced Capability for Lithium PMI ResearchMulti-Institutional Contributions
ORNL
Lithium CHERS
Divertor ImagingSpectrometer
Dual-band fast IR Camera
Two fast 2D visible and IR cameras with full divertor coverage
Li I
C II
MAPP probe for between-shots surface analysis ndash Tested in LTX
LLNL ORNL UT-K
LLNL
Divertor fast pressure gauges
ORNL
Divertor fast eroding thermocouples
R Kaita at this symposium
21M Ono ISLA 2015 Sept28 - 30 2915
bull Lithium was observed to improve fusion plasma performance
bull Radiative LL Divertor (RLLD) and Active version of RLLD (ARLLD) are proposed to solve divertor heat flux issues
bull More experimental data needed to assess effectiveness of lithium radiation (lithium granular injection in NSTX-U planned)
bull Compatibility issues of lithium with fusion reactor were examined
bull Dustparticles are collected under divertor by a set of filters mainly by the gravity action
bull Tritium is removed in real time with a set of cold traps
bull Tritium inventory issue maybe manageable
bull NSTX-U is now starting to support lithium program (M Jaworski)
Summary Lithium could solve several critical reactor issues
5M Ono ISLA 2015 Sept28 - 30 2915 5
Steady state surface heat removal maybe limited to ~ 5 MWm2 solid or liquid metal PFCshellip
Tobita K et al 2009 Nucl Fusion 49 075029
bull Solid-based divertor PFC steady-state heat handling capability maybe limited to ~ 5 MWm2 for lt 1200degC PFC temperature with gt300 degC cooling temperature
bull Even liquid lithium based PFCs may be challenging handle steady-state ~ 5 MWm2 to keep PFC surface temperature to le 500 degC
M Jowarski et al at ISLA-3
Need to handle high heat flux gt 5 MWm2 volumetrically
6M Ono ISLA 2015 Sept28 - 30 2915
a)
b)
c)
d)
bull 2 identical shots (No ELMs)ndash Ip = 08 MA Pnbi ~ 4 MW
ndash high δ fexp ~ 20
bull 2 pre-discharge lithium depositionsndash 150 mg 141255
ndash 300 mg 138240bull Tsurf at the outer strike point stays below
400deg C for 300 mg of Lindash Peaks around 800deg C for 150 mg
bull Results in a heat flux that never peaks above 3 MWm2 with heavy lithium evaporation
bull No LLD surface damage observed
Lithiated graphite
T Gray NF 2014
Clear reduction in NSTX divertor surface temperature and heat flux with increased lithium evaporation
H Kugel FEampD 2012
NSTX-U can perform detailed assessment of Li radiation with LITER
7M Ono ISLA 2015 Sept28 - 30 2915
Lithium Provides Several Layers of Protection
Vaporization Ionization Radiation
7
Divertor side wall
LLD Tray
Li Injection (ARLLD)~ 100 MJmole
DivertorEntrance
Power and particle flux
Li Vapor Shielding
Li Radiative Cooling (RLLD)~ 100 MJmole
Li Vaporization (150 kJ mole)
Li Ionization1st ionization ndash 05 MJ mole 2nd ionization ndash 73 MJ mole 3rd ionization ndash 118 MJ mole
M Jaworski
Radial Transport Charge Exchange
Loss
T Abram
This talk emphasis
F Scotti VA Soukhanovskii et al NF 2013
TD Rognlien et al PoP 2002
8M Ono ISLA 2015 Sept28 - 30 2915
Divertor side wall
RLLD Tray
Active Injection of LL as First Line of Defense
Li injection as needed via feed-back control
Li Injection
DivertorEntrance
Power and particle flux
8
D Mansfield FEampD 2010
Lithium aerosol is introduced by a ldquodroperrdquo at the plasma edge and the ionized lithium tends to flow toward the divertor plate along the field line
Li Aerosol in NSTX
Li granular injector for NSTX-U
R Lunsford at this symposium
Li Radiative Mantle
Li ionized with Z = 2 and flows toward divertor
at Cs2
Cs2
R Goldston NF 2012
Li granular injector on NSTX-U will provide important data on ARLLD
9M Ono ISLA 2015 Sept28 - 30 2915
The Li radiation power per one atom and one electron in coronal-quilibrium (net = infinity) and non-equilibrium regimesS V Mirnov et al Plasma Phys Control Fusion (2006)
Assumed radiation
level in the modeling
calculation for RLLD
Coronal-Equilibrium Value
Strong (~x100) Li Radiation Level Over Coronal Eq
Low particle confinement could increase radiation in divertor
Divertor Heat and Particle Flux
Li paths
LLD Tray
t ~ 100 ms
9
Radiation ~ N-Lit N-Li~ Li-inj t Radiation ~ Li-inj ~ 100 MJmole
10M Ono ISLA 2015 Sept28 - 30 2915
Radiative Liquid Lithium Divertor Proposed Handle divertor heat load volumetrically (3D vs 2D)
M Ono NF 2013 FEampD 2014
10
Y Hirooka at this conference
Flowing LL Particle Pumping Surfaces
Li+
Li++
Li+++
Li0
Heat Exchanger
B0
Divertor Heat and Particles Flux
Liquid Lithium (LL) ~ 1 lsec for pumping dust removal
LL Purification System to remove tritium impurities and dust
Li Evap Ionization (RLLD)~ few molesec
Li Radiative Mantle
Li wall coating condensation
Li path
Reduced Divertor Heat and Particle
Flux
Particle pumping by Li
coated wall
Divertor Strike Point
RLLD ARLLD Lithium provides low recycling radiative divertor
Active LL Injection (ARLLD)~ few molesec
11M Ono ISLA 2015 Sept28 - 30 2915 11
Concerns for lithium in reactor applicationbull Lithium evaporation is too
high in reactor PFC temperatures of ~ 600 degC LL needs to be le 450degC
bull Lithium can trap tritium and make the tritium inventory issues worse
bull Lithium is volatile and unsafe
bull Lithium is corrosive
LL Surface Temp (degC)
Log N-Li m2-s Lithium Evaporation Rate
IFMIF International Fusion Materials Irradiation Facility
H Kondo et al FEampD (2012)
LL operating
range Reactor FW temperature
12M Ono ISLA 2015 Sept28 - 30 2915
High Temperature First Wallbull High electrical conversion bull Cleaner wall ndash lower T inventorybull There are ideas to use lithium for the
first allhellip
Lower RLLD Operating Temperaturebull Prevents excessive Li vaporization
pressure bull Cooler divertor provides natural
collection (pumping) surfaces for entire reactor chamber
bull May permit use of iron based material for substrates and structural material
bull Reduces Li corrosive issuesbull Provides safer LL utilization
First Wall BlanketAt 500degC ndash 700degC
000000000000
Core ReactingPlasma
Edge Plasma
Scrape Off Layer
Flowing LLD Tray 200 ndash 500 degC
Closed RLLD
LL Out LL InLL In
12
Compatibility with liquid lithium with a hot reactor first wall RLLD configuration permits operation at lower T lt 450 degC
13M Ono ISLA 2015 Sept28 - 30 2915 13
Liquid lithium could also solve long-standing fusion reactor technology challenges ndash dust generation and T inventory
bull Erosion redeposition from plasma sputtering and disruptions including dust and flake generation
bull Tritium retention and removal Dust could further aggravate tritium inventory issues
G Federici C H Skinner et al NF 111308820011113088
Solution Liquid lithium loop
IFMIFEVEDA RLLD LoopTotal LL amount 25 t 05 tFlow rate 50 ls lt 1 lsOperation 25 days Steady-stateTImpurity lt 001 lt1 Li target under the
IFMIF conditions (15 ms 10minus3 Pa 250 degC)H Kondo et al FEampD (2014)
M Jaworki et al for NSTX-U at this symposium
14M Ono ISLA 2015 Sept28 - 30 2915
Dust Generation Likely a Serious Issue for ReactorHowever nature and quantity of dust generation
unknown
14
LLCirculation
Pump
Divertor Heat and Particle Flux
LL 1 ls
Back to RLLDARLLD
Dust particle
filter
Tritiumimpurity removal loop
Purified LL
Dustparticle filters are located below divertor and dust are carried to filter by gravity action
bull Each dustparticle filters when fulll drained of LL and removedbull Removed filter processed to recover trapped tritium
15M Ono ISLA 2015 Sept28 - 30 2915
Cold Trap Could Remove T D H and O Cold trap can be regenerated at higher
temperatures
15
K Natesan JNM 1983
bull At 200 degC hydrogen can be reduced toward 01 levelbull Oxygen is also effectively reduced with cold trapbull Nitrogen would require separate hot nitrogen trap
Nearly ~ 10 in solubility
16M Ono ISLA 2015 Sept28 - 30 2915
Realtime Tritium Recovery Needed~ 05 gsec of tritium must be recovered in real
time
16
Tritium Recycling
TritiumSeparater
Deuterium ampOther impurities as
well as dust
T ndash 05 gs
T D H O
LLCold Trap
LLCold Trap
01 TTo RLLDARLLD
Parallel paths to enable regeneration while operation
Drain liquid lithium before regeneration
Multiple filters to enable regeneration
Valves and pumps not shown
200degC
1 TFrom dustparticle filter loop
01 lsec of 1 T LL can carry 05 gs of T
17M Ono ISLA 2015 Sept28 - 30 2915
Tritium Inventory Control in Fusion Power PlantTotal site inventory maybe ~ 50 days or ~ 20 kg
17
M Nishikawa FST 2010
bull 1 (by weight) tritium concentration LL contains ~ 5 g of T l
bull LL inside VV may contain 100 l of LL or 05 kg for RLLDARLLD
bull LL in LL-loop before and in cold traps (~ 1) may contain 500 l of LL or 25 kg
bull LL after cold traps (~ 01) may contain 500 l of LL or 025kg
bull Total tritium inventory in RLLDALLD may contains 325 kg of T which is about 8 days ltlt 50 days
LL system may be compatible with the fusion reactor power plant tritium inventory requirements
18M Ono ISLA 2015 Sept28 - 30 2915
NSTX-U Construction complete First Plasma on August 10 2015
HHFW System
1st NBI
2nd NBI
NSTX-U
MPTS Exit Flight Tube
19M Ono ISLA 2015 Sept28 - 30 2915
LITERs
Comprehensive Lithium Boundary Physics ToolsBoronization Lithium Evaporators Granule Injector High Z tiles
Lithium Evaporator (LITERs)
Upward Li evaporator
High Z Tiles
T-bar mount
Castellations
Granule injector (GI) for ELM pacing
Rotating Impeller
Successfully tested on EAST and DIII-DGranules Li B4C Cf ~ up to 500 Hz
dTMB Gas Cabinet
Boronization System
Granular Reservoir
Electron beam for flash evaporation
crucible
FY 2016
FY 2016
20M Ono ISLA 2015 Sept28 - 30 2915
Enhanced Capability for Lithium PMI ResearchMulti-Institutional Contributions
ORNL
Lithium CHERS
Divertor ImagingSpectrometer
Dual-band fast IR Camera
Two fast 2D visible and IR cameras with full divertor coverage
Li I
C II
MAPP probe for between-shots surface analysis ndash Tested in LTX
LLNL ORNL UT-K
LLNL
Divertor fast pressure gauges
ORNL
Divertor fast eroding thermocouples
R Kaita at this symposium
21M Ono ISLA 2015 Sept28 - 30 2915
bull Lithium was observed to improve fusion plasma performance
bull Radiative LL Divertor (RLLD) and Active version of RLLD (ARLLD) are proposed to solve divertor heat flux issues
bull More experimental data needed to assess effectiveness of lithium radiation (lithium granular injection in NSTX-U planned)
bull Compatibility issues of lithium with fusion reactor were examined
bull Dustparticles are collected under divertor by a set of filters mainly by the gravity action
bull Tritium is removed in real time with a set of cold traps
bull Tritium inventory issue maybe manageable
bull NSTX-U is now starting to support lithium program (M Jaworski)
Summary Lithium could solve several critical reactor issues
6M Ono ISLA 2015 Sept28 - 30 2915
a)
b)
c)
d)
bull 2 identical shots (No ELMs)ndash Ip = 08 MA Pnbi ~ 4 MW
ndash high δ fexp ~ 20
bull 2 pre-discharge lithium depositionsndash 150 mg 141255
ndash 300 mg 138240bull Tsurf at the outer strike point stays below
400deg C for 300 mg of Lindash Peaks around 800deg C for 150 mg
bull Results in a heat flux that never peaks above 3 MWm2 with heavy lithium evaporation
bull No LLD surface damage observed
Lithiated graphite
T Gray NF 2014
Clear reduction in NSTX divertor surface temperature and heat flux with increased lithium evaporation
H Kugel FEampD 2012
NSTX-U can perform detailed assessment of Li radiation with LITER
7M Ono ISLA 2015 Sept28 - 30 2915
Lithium Provides Several Layers of Protection
Vaporization Ionization Radiation
7
Divertor side wall
LLD Tray
Li Injection (ARLLD)~ 100 MJmole
DivertorEntrance
Power and particle flux
Li Vapor Shielding
Li Radiative Cooling (RLLD)~ 100 MJmole
Li Vaporization (150 kJ mole)
Li Ionization1st ionization ndash 05 MJ mole 2nd ionization ndash 73 MJ mole 3rd ionization ndash 118 MJ mole
M Jaworski
Radial Transport Charge Exchange
Loss
T Abram
This talk emphasis
F Scotti VA Soukhanovskii et al NF 2013
TD Rognlien et al PoP 2002
8M Ono ISLA 2015 Sept28 - 30 2915
Divertor side wall
RLLD Tray
Active Injection of LL as First Line of Defense
Li injection as needed via feed-back control
Li Injection
DivertorEntrance
Power and particle flux
8
D Mansfield FEampD 2010
Lithium aerosol is introduced by a ldquodroperrdquo at the plasma edge and the ionized lithium tends to flow toward the divertor plate along the field line
Li Aerosol in NSTX
Li granular injector for NSTX-U
R Lunsford at this symposium
Li Radiative Mantle
Li ionized with Z = 2 and flows toward divertor
at Cs2
Cs2
R Goldston NF 2012
Li granular injector on NSTX-U will provide important data on ARLLD
9M Ono ISLA 2015 Sept28 - 30 2915
The Li radiation power per one atom and one electron in coronal-quilibrium (net = infinity) and non-equilibrium regimesS V Mirnov et al Plasma Phys Control Fusion (2006)
Assumed radiation
level in the modeling
calculation for RLLD
Coronal-Equilibrium Value
Strong (~x100) Li Radiation Level Over Coronal Eq
Low particle confinement could increase radiation in divertor
Divertor Heat and Particle Flux
Li paths
LLD Tray
t ~ 100 ms
9
Radiation ~ N-Lit N-Li~ Li-inj t Radiation ~ Li-inj ~ 100 MJmole
10M Ono ISLA 2015 Sept28 - 30 2915
Radiative Liquid Lithium Divertor Proposed Handle divertor heat load volumetrically (3D vs 2D)
M Ono NF 2013 FEampD 2014
10
Y Hirooka at this conference
Flowing LL Particle Pumping Surfaces
Li+
Li++
Li+++
Li0
Heat Exchanger
B0
Divertor Heat and Particles Flux
Liquid Lithium (LL) ~ 1 lsec for pumping dust removal
LL Purification System to remove tritium impurities and dust
Li Evap Ionization (RLLD)~ few molesec
Li Radiative Mantle
Li wall coating condensation
Li path
Reduced Divertor Heat and Particle
Flux
Particle pumping by Li
coated wall
Divertor Strike Point
RLLD ARLLD Lithium provides low recycling radiative divertor
Active LL Injection (ARLLD)~ few molesec
11M Ono ISLA 2015 Sept28 - 30 2915 11
Concerns for lithium in reactor applicationbull Lithium evaporation is too
high in reactor PFC temperatures of ~ 600 degC LL needs to be le 450degC
bull Lithium can trap tritium and make the tritium inventory issues worse
bull Lithium is volatile and unsafe
bull Lithium is corrosive
LL Surface Temp (degC)
Log N-Li m2-s Lithium Evaporation Rate
IFMIF International Fusion Materials Irradiation Facility
H Kondo et al FEampD (2012)
LL operating
range Reactor FW temperature
12M Ono ISLA 2015 Sept28 - 30 2915
High Temperature First Wallbull High electrical conversion bull Cleaner wall ndash lower T inventorybull There are ideas to use lithium for the
first allhellip
Lower RLLD Operating Temperaturebull Prevents excessive Li vaporization
pressure bull Cooler divertor provides natural
collection (pumping) surfaces for entire reactor chamber
bull May permit use of iron based material for substrates and structural material
bull Reduces Li corrosive issuesbull Provides safer LL utilization
First Wall BlanketAt 500degC ndash 700degC
000000000000
Core ReactingPlasma
Edge Plasma
Scrape Off Layer
Flowing LLD Tray 200 ndash 500 degC
Closed RLLD
LL Out LL InLL In
12
Compatibility with liquid lithium with a hot reactor first wall RLLD configuration permits operation at lower T lt 450 degC
13M Ono ISLA 2015 Sept28 - 30 2915 13
Liquid lithium could also solve long-standing fusion reactor technology challenges ndash dust generation and T inventory
bull Erosion redeposition from plasma sputtering and disruptions including dust and flake generation
bull Tritium retention and removal Dust could further aggravate tritium inventory issues
G Federici C H Skinner et al NF 111308820011113088
Solution Liquid lithium loop
IFMIFEVEDA RLLD LoopTotal LL amount 25 t 05 tFlow rate 50 ls lt 1 lsOperation 25 days Steady-stateTImpurity lt 001 lt1 Li target under the
IFMIF conditions (15 ms 10minus3 Pa 250 degC)H Kondo et al FEampD (2014)
M Jaworki et al for NSTX-U at this symposium
14M Ono ISLA 2015 Sept28 - 30 2915
Dust Generation Likely a Serious Issue for ReactorHowever nature and quantity of dust generation
unknown
14
LLCirculation
Pump
Divertor Heat and Particle Flux
LL 1 ls
Back to RLLDARLLD
Dust particle
filter
Tritiumimpurity removal loop
Purified LL
Dustparticle filters are located below divertor and dust are carried to filter by gravity action
bull Each dustparticle filters when fulll drained of LL and removedbull Removed filter processed to recover trapped tritium
15M Ono ISLA 2015 Sept28 - 30 2915
Cold Trap Could Remove T D H and O Cold trap can be regenerated at higher
temperatures
15
K Natesan JNM 1983
bull At 200 degC hydrogen can be reduced toward 01 levelbull Oxygen is also effectively reduced with cold trapbull Nitrogen would require separate hot nitrogen trap
Nearly ~ 10 in solubility
16M Ono ISLA 2015 Sept28 - 30 2915
Realtime Tritium Recovery Needed~ 05 gsec of tritium must be recovered in real
time
16
Tritium Recycling
TritiumSeparater
Deuterium ampOther impurities as
well as dust
T ndash 05 gs
T D H O
LLCold Trap
LLCold Trap
01 TTo RLLDARLLD
Parallel paths to enable regeneration while operation
Drain liquid lithium before regeneration
Multiple filters to enable regeneration
Valves and pumps not shown
200degC
1 TFrom dustparticle filter loop
01 lsec of 1 T LL can carry 05 gs of T
17M Ono ISLA 2015 Sept28 - 30 2915
Tritium Inventory Control in Fusion Power PlantTotal site inventory maybe ~ 50 days or ~ 20 kg
17
M Nishikawa FST 2010
bull 1 (by weight) tritium concentration LL contains ~ 5 g of T l
bull LL inside VV may contain 100 l of LL or 05 kg for RLLDARLLD
bull LL in LL-loop before and in cold traps (~ 1) may contain 500 l of LL or 25 kg
bull LL after cold traps (~ 01) may contain 500 l of LL or 025kg
bull Total tritium inventory in RLLDALLD may contains 325 kg of T which is about 8 days ltlt 50 days
LL system may be compatible with the fusion reactor power plant tritium inventory requirements
18M Ono ISLA 2015 Sept28 - 30 2915
NSTX-U Construction complete First Plasma on August 10 2015
HHFW System
1st NBI
2nd NBI
NSTX-U
MPTS Exit Flight Tube
19M Ono ISLA 2015 Sept28 - 30 2915
LITERs
Comprehensive Lithium Boundary Physics ToolsBoronization Lithium Evaporators Granule Injector High Z tiles
Lithium Evaporator (LITERs)
Upward Li evaporator
High Z Tiles
T-bar mount
Castellations
Granule injector (GI) for ELM pacing
Rotating Impeller
Successfully tested on EAST and DIII-DGranules Li B4C Cf ~ up to 500 Hz
dTMB Gas Cabinet
Boronization System
Granular Reservoir
Electron beam for flash evaporation
crucible
FY 2016
FY 2016
20M Ono ISLA 2015 Sept28 - 30 2915
Enhanced Capability for Lithium PMI ResearchMulti-Institutional Contributions
ORNL
Lithium CHERS
Divertor ImagingSpectrometer
Dual-band fast IR Camera
Two fast 2D visible and IR cameras with full divertor coverage
Li I
C II
MAPP probe for between-shots surface analysis ndash Tested in LTX
LLNL ORNL UT-K
LLNL
Divertor fast pressure gauges
ORNL
Divertor fast eroding thermocouples
R Kaita at this symposium
21M Ono ISLA 2015 Sept28 - 30 2915
bull Lithium was observed to improve fusion plasma performance
bull Radiative LL Divertor (RLLD) and Active version of RLLD (ARLLD) are proposed to solve divertor heat flux issues
bull More experimental data needed to assess effectiveness of lithium radiation (lithium granular injection in NSTX-U planned)
bull Compatibility issues of lithium with fusion reactor were examined
bull Dustparticles are collected under divertor by a set of filters mainly by the gravity action
bull Tritium is removed in real time with a set of cold traps
bull Tritium inventory issue maybe manageable
bull NSTX-U is now starting to support lithium program (M Jaworski)
Summary Lithium could solve several critical reactor issues
7M Ono ISLA 2015 Sept28 - 30 2915
Lithium Provides Several Layers of Protection
Vaporization Ionization Radiation
7
Divertor side wall
LLD Tray
Li Injection (ARLLD)~ 100 MJmole
DivertorEntrance
Power and particle flux
Li Vapor Shielding
Li Radiative Cooling (RLLD)~ 100 MJmole
Li Vaporization (150 kJ mole)
Li Ionization1st ionization ndash 05 MJ mole 2nd ionization ndash 73 MJ mole 3rd ionization ndash 118 MJ mole
M Jaworski
Radial Transport Charge Exchange
Loss
T Abram
This talk emphasis
F Scotti VA Soukhanovskii et al NF 2013
TD Rognlien et al PoP 2002
8M Ono ISLA 2015 Sept28 - 30 2915
Divertor side wall
RLLD Tray
Active Injection of LL as First Line of Defense
Li injection as needed via feed-back control
Li Injection
DivertorEntrance
Power and particle flux
8
D Mansfield FEampD 2010
Lithium aerosol is introduced by a ldquodroperrdquo at the plasma edge and the ionized lithium tends to flow toward the divertor plate along the field line
Li Aerosol in NSTX
Li granular injector for NSTX-U
R Lunsford at this symposium
Li Radiative Mantle
Li ionized with Z = 2 and flows toward divertor
at Cs2
Cs2
R Goldston NF 2012
Li granular injector on NSTX-U will provide important data on ARLLD
9M Ono ISLA 2015 Sept28 - 30 2915
The Li radiation power per one atom and one electron in coronal-quilibrium (net = infinity) and non-equilibrium regimesS V Mirnov et al Plasma Phys Control Fusion (2006)
Assumed radiation
level in the modeling
calculation for RLLD
Coronal-Equilibrium Value
Strong (~x100) Li Radiation Level Over Coronal Eq
Low particle confinement could increase radiation in divertor
Divertor Heat and Particle Flux
Li paths
LLD Tray
t ~ 100 ms
9
Radiation ~ N-Lit N-Li~ Li-inj t Radiation ~ Li-inj ~ 100 MJmole
10M Ono ISLA 2015 Sept28 - 30 2915
Radiative Liquid Lithium Divertor Proposed Handle divertor heat load volumetrically (3D vs 2D)
M Ono NF 2013 FEampD 2014
10
Y Hirooka at this conference
Flowing LL Particle Pumping Surfaces
Li+
Li++
Li+++
Li0
Heat Exchanger
B0
Divertor Heat and Particles Flux
Liquid Lithium (LL) ~ 1 lsec for pumping dust removal
LL Purification System to remove tritium impurities and dust
Li Evap Ionization (RLLD)~ few molesec
Li Radiative Mantle
Li wall coating condensation
Li path
Reduced Divertor Heat and Particle
Flux
Particle pumping by Li
coated wall
Divertor Strike Point
RLLD ARLLD Lithium provides low recycling radiative divertor
Active LL Injection (ARLLD)~ few molesec
11M Ono ISLA 2015 Sept28 - 30 2915 11
Concerns for lithium in reactor applicationbull Lithium evaporation is too
high in reactor PFC temperatures of ~ 600 degC LL needs to be le 450degC
bull Lithium can trap tritium and make the tritium inventory issues worse
bull Lithium is volatile and unsafe
bull Lithium is corrosive
LL Surface Temp (degC)
Log N-Li m2-s Lithium Evaporation Rate
IFMIF International Fusion Materials Irradiation Facility
H Kondo et al FEampD (2012)
LL operating
range Reactor FW temperature
12M Ono ISLA 2015 Sept28 - 30 2915
High Temperature First Wallbull High electrical conversion bull Cleaner wall ndash lower T inventorybull There are ideas to use lithium for the
first allhellip
Lower RLLD Operating Temperaturebull Prevents excessive Li vaporization
pressure bull Cooler divertor provides natural
collection (pumping) surfaces for entire reactor chamber
bull May permit use of iron based material for substrates and structural material
bull Reduces Li corrosive issuesbull Provides safer LL utilization
First Wall BlanketAt 500degC ndash 700degC
000000000000
Core ReactingPlasma
Edge Plasma
Scrape Off Layer
Flowing LLD Tray 200 ndash 500 degC
Closed RLLD
LL Out LL InLL In
12
Compatibility with liquid lithium with a hot reactor first wall RLLD configuration permits operation at lower T lt 450 degC
13M Ono ISLA 2015 Sept28 - 30 2915 13
Liquid lithium could also solve long-standing fusion reactor technology challenges ndash dust generation and T inventory
bull Erosion redeposition from plasma sputtering and disruptions including dust and flake generation
bull Tritium retention and removal Dust could further aggravate tritium inventory issues
G Federici C H Skinner et al NF 111308820011113088
Solution Liquid lithium loop
IFMIFEVEDA RLLD LoopTotal LL amount 25 t 05 tFlow rate 50 ls lt 1 lsOperation 25 days Steady-stateTImpurity lt 001 lt1 Li target under the
IFMIF conditions (15 ms 10minus3 Pa 250 degC)H Kondo et al FEampD (2014)
M Jaworki et al for NSTX-U at this symposium
14M Ono ISLA 2015 Sept28 - 30 2915
Dust Generation Likely a Serious Issue for ReactorHowever nature and quantity of dust generation
unknown
14
LLCirculation
Pump
Divertor Heat and Particle Flux
LL 1 ls
Back to RLLDARLLD
Dust particle
filter
Tritiumimpurity removal loop
Purified LL
Dustparticle filters are located below divertor and dust are carried to filter by gravity action
bull Each dustparticle filters when fulll drained of LL and removedbull Removed filter processed to recover trapped tritium
15M Ono ISLA 2015 Sept28 - 30 2915
Cold Trap Could Remove T D H and O Cold trap can be regenerated at higher
temperatures
15
K Natesan JNM 1983
bull At 200 degC hydrogen can be reduced toward 01 levelbull Oxygen is also effectively reduced with cold trapbull Nitrogen would require separate hot nitrogen trap
Nearly ~ 10 in solubility
16M Ono ISLA 2015 Sept28 - 30 2915
Realtime Tritium Recovery Needed~ 05 gsec of tritium must be recovered in real
time
16
Tritium Recycling
TritiumSeparater
Deuterium ampOther impurities as
well as dust
T ndash 05 gs
T D H O
LLCold Trap
LLCold Trap
01 TTo RLLDARLLD
Parallel paths to enable regeneration while operation
Drain liquid lithium before regeneration
Multiple filters to enable regeneration
Valves and pumps not shown
200degC
1 TFrom dustparticle filter loop
01 lsec of 1 T LL can carry 05 gs of T
17M Ono ISLA 2015 Sept28 - 30 2915
Tritium Inventory Control in Fusion Power PlantTotal site inventory maybe ~ 50 days or ~ 20 kg
17
M Nishikawa FST 2010
bull 1 (by weight) tritium concentration LL contains ~ 5 g of T l
bull LL inside VV may contain 100 l of LL or 05 kg for RLLDARLLD
bull LL in LL-loop before and in cold traps (~ 1) may contain 500 l of LL or 25 kg
bull LL after cold traps (~ 01) may contain 500 l of LL or 025kg
bull Total tritium inventory in RLLDALLD may contains 325 kg of T which is about 8 days ltlt 50 days
LL system may be compatible with the fusion reactor power plant tritium inventory requirements
18M Ono ISLA 2015 Sept28 - 30 2915
NSTX-U Construction complete First Plasma on August 10 2015
HHFW System
1st NBI
2nd NBI
NSTX-U
MPTS Exit Flight Tube
19M Ono ISLA 2015 Sept28 - 30 2915
LITERs
Comprehensive Lithium Boundary Physics ToolsBoronization Lithium Evaporators Granule Injector High Z tiles
Lithium Evaporator (LITERs)
Upward Li evaporator
High Z Tiles
T-bar mount
Castellations
Granule injector (GI) for ELM pacing
Rotating Impeller
Successfully tested on EAST and DIII-DGranules Li B4C Cf ~ up to 500 Hz
dTMB Gas Cabinet
Boronization System
Granular Reservoir
Electron beam for flash evaporation
crucible
FY 2016
FY 2016
20M Ono ISLA 2015 Sept28 - 30 2915
Enhanced Capability for Lithium PMI ResearchMulti-Institutional Contributions
ORNL
Lithium CHERS
Divertor ImagingSpectrometer
Dual-band fast IR Camera
Two fast 2D visible and IR cameras with full divertor coverage
Li I
C II
MAPP probe for between-shots surface analysis ndash Tested in LTX
LLNL ORNL UT-K
LLNL
Divertor fast pressure gauges
ORNL
Divertor fast eroding thermocouples
R Kaita at this symposium
21M Ono ISLA 2015 Sept28 - 30 2915
bull Lithium was observed to improve fusion plasma performance
bull Radiative LL Divertor (RLLD) and Active version of RLLD (ARLLD) are proposed to solve divertor heat flux issues
bull More experimental data needed to assess effectiveness of lithium radiation (lithium granular injection in NSTX-U planned)
bull Compatibility issues of lithium with fusion reactor were examined
bull Dustparticles are collected under divertor by a set of filters mainly by the gravity action
bull Tritium is removed in real time with a set of cold traps
bull Tritium inventory issue maybe manageable
bull NSTX-U is now starting to support lithium program (M Jaworski)
Summary Lithium could solve several critical reactor issues
8M Ono ISLA 2015 Sept28 - 30 2915
Divertor side wall
RLLD Tray
Active Injection of LL as First Line of Defense
Li injection as needed via feed-back control
Li Injection
DivertorEntrance
Power and particle flux
8
D Mansfield FEampD 2010
Lithium aerosol is introduced by a ldquodroperrdquo at the plasma edge and the ionized lithium tends to flow toward the divertor plate along the field line
Li Aerosol in NSTX
Li granular injector for NSTX-U
R Lunsford at this symposium
Li Radiative Mantle
Li ionized with Z = 2 and flows toward divertor
at Cs2
Cs2
R Goldston NF 2012
Li granular injector on NSTX-U will provide important data on ARLLD
9M Ono ISLA 2015 Sept28 - 30 2915
The Li radiation power per one atom and one electron in coronal-quilibrium (net = infinity) and non-equilibrium regimesS V Mirnov et al Plasma Phys Control Fusion (2006)
Assumed radiation
level in the modeling
calculation for RLLD
Coronal-Equilibrium Value
Strong (~x100) Li Radiation Level Over Coronal Eq
Low particle confinement could increase radiation in divertor
Divertor Heat and Particle Flux
Li paths
LLD Tray
t ~ 100 ms
9
Radiation ~ N-Lit N-Li~ Li-inj t Radiation ~ Li-inj ~ 100 MJmole
10M Ono ISLA 2015 Sept28 - 30 2915
Radiative Liquid Lithium Divertor Proposed Handle divertor heat load volumetrically (3D vs 2D)
M Ono NF 2013 FEampD 2014
10
Y Hirooka at this conference
Flowing LL Particle Pumping Surfaces
Li+
Li++
Li+++
Li0
Heat Exchanger
B0
Divertor Heat and Particles Flux
Liquid Lithium (LL) ~ 1 lsec for pumping dust removal
LL Purification System to remove tritium impurities and dust
Li Evap Ionization (RLLD)~ few molesec
Li Radiative Mantle
Li wall coating condensation
Li path
Reduced Divertor Heat and Particle
Flux
Particle pumping by Li
coated wall
Divertor Strike Point
RLLD ARLLD Lithium provides low recycling radiative divertor
Active LL Injection (ARLLD)~ few molesec
11M Ono ISLA 2015 Sept28 - 30 2915 11
Concerns for lithium in reactor applicationbull Lithium evaporation is too
high in reactor PFC temperatures of ~ 600 degC LL needs to be le 450degC
bull Lithium can trap tritium and make the tritium inventory issues worse
bull Lithium is volatile and unsafe
bull Lithium is corrosive
LL Surface Temp (degC)
Log N-Li m2-s Lithium Evaporation Rate
IFMIF International Fusion Materials Irradiation Facility
H Kondo et al FEampD (2012)
LL operating
range Reactor FW temperature
12M Ono ISLA 2015 Sept28 - 30 2915
High Temperature First Wallbull High electrical conversion bull Cleaner wall ndash lower T inventorybull There are ideas to use lithium for the
first allhellip
Lower RLLD Operating Temperaturebull Prevents excessive Li vaporization
pressure bull Cooler divertor provides natural
collection (pumping) surfaces for entire reactor chamber
bull May permit use of iron based material for substrates and structural material
bull Reduces Li corrosive issuesbull Provides safer LL utilization
First Wall BlanketAt 500degC ndash 700degC
000000000000
Core ReactingPlasma
Edge Plasma
Scrape Off Layer
Flowing LLD Tray 200 ndash 500 degC
Closed RLLD
LL Out LL InLL In
12
Compatibility with liquid lithium with a hot reactor first wall RLLD configuration permits operation at lower T lt 450 degC
13M Ono ISLA 2015 Sept28 - 30 2915 13
Liquid lithium could also solve long-standing fusion reactor technology challenges ndash dust generation and T inventory
bull Erosion redeposition from plasma sputtering and disruptions including dust and flake generation
bull Tritium retention and removal Dust could further aggravate tritium inventory issues
G Federici C H Skinner et al NF 111308820011113088
Solution Liquid lithium loop
IFMIFEVEDA RLLD LoopTotal LL amount 25 t 05 tFlow rate 50 ls lt 1 lsOperation 25 days Steady-stateTImpurity lt 001 lt1 Li target under the
IFMIF conditions (15 ms 10minus3 Pa 250 degC)H Kondo et al FEampD (2014)
M Jaworki et al for NSTX-U at this symposium
14M Ono ISLA 2015 Sept28 - 30 2915
Dust Generation Likely a Serious Issue for ReactorHowever nature and quantity of dust generation
unknown
14
LLCirculation
Pump
Divertor Heat and Particle Flux
LL 1 ls
Back to RLLDARLLD
Dust particle
filter
Tritiumimpurity removal loop
Purified LL
Dustparticle filters are located below divertor and dust are carried to filter by gravity action
bull Each dustparticle filters when fulll drained of LL and removedbull Removed filter processed to recover trapped tritium
15M Ono ISLA 2015 Sept28 - 30 2915
Cold Trap Could Remove T D H and O Cold trap can be regenerated at higher
temperatures
15
K Natesan JNM 1983
bull At 200 degC hydrogen can be reduced toward 01 levelbull Oxygen is also effectively reduced with cold trapbull Nitrogen would require separate hot nitrogen trap
Nearly ~ 10 in solubility
16M Ono ISLA 2015 Sept28 - 30 2915
Realtime Tritium Recovery Needed~ 05 gsec of tritium must be recovered in real
time
16
Tritium Recycling
TritiumSeparater
Deuterium ampOther impurities as
well as dust
T ndash 05 gs
T D H O
LLCold Trap
LLCold Trap
01 TTo RLLDARLLD
Parallel paths to enable regeneration while operation
Drain liquid lithium before regeneration
Multiple filters to enable regeneration
Valves and pumps not shown
200degC
1 TFrom dustparticle filter loop
01 lsec of 1 T LL can carry 05 gs of T
17M Ono ISLA 2015 Sept28 - 30 2915
Tritium Inventory Control in Fusion Power PlantTotal site inventory maybe ~ 50 days or ~ 20 kg
17
M Nishikawa FST 2010
bull 1 (by weight) tritium concentration LL contains ~ 5 g of T l
bull LL inside VV may contain 100 l of LL or 05 kg for RLLDARLLD
bull LL in LL-loop before and in cold traps (~ 1) may contain 500 l of LL or 25 kg
bull LL after cold traps (~ 01) may contain 500 l of LL or 025kg
bull Total tritium inventory in RLLDALLD may contains 325 kg of T which is about 8 days ltlt 50 days
LL system may be compatible with the fusion reactor power plant tritium inventory requirements
18M Ono ISLA 2015 Sept28 - 30 2915
NSTX-U Construction complete First Plasma on August 10 2015
HHFW System
1st NBI
2nd NBI
NSTX-U
MPTS Exit Flight Tube
19M Ono ISLA 2015 Sept28 - 30 2915
LITERs
Comprehensive Lithium Boundary Physics ToolsBoronization Lithium Evaporators Granule Injector High Z tiles
Lithium Evaporator (LITERs)
Upward Li evaporator
High Z Tiles
T-bar mount
Castellations
Granule injector (GI) for ELM pacing
Rotating Impeller
Successfully tested on EAST and DIII-DGranules Li B4C Cf ~ up to 500 Hz
dTMB Gas Cabinet
Boronization System
Granular Reservoir
Electron beam for flash evaporation
crucible
FY 2016
FY 2016
20M Ono ISLA 2015 Sept28 - 30 2915
Enhanced Capability for Lithium PMI ResearchMulti-Institutional Contributions
ORNL
Lithium CHERS
Divertor ImagingSpectrometer
Dual-band fast IR Camera
Two fast 2D visible and IR cameras with full divertor coverage
Li I
C II
MAPP probe for between-shots surface analysis ndash Tested in LTX
LLNL ORNL UT-K
LLNL
Divertor fast pressure gauges
ORNL
Divertor fast eroding thermocouples
R Kaita at this symposium
21M Ono ISLA 2015 Sept28 - 30 2915
bull Lithium was observed to improve fusion plasma performance
bull Radiative LL Divertor (RLLD) and Active version of RLLD (ARLLD) are proposed to solve divertor heat flux issues
bull More experimental data needed to assess effectiveness of lithium radiation (lithium granular injection in NSTX-U planned)
bull Compatibility issues of lithium with fusion reactor were examined
bull Dustparticles are collected under divertor by a set of filters mainly by the gravity action
bull Tritium is removed in real time with a set of cold traps
bull Tritium inventory issue maybe manageable
bull NSTX-U is now starting to support lithium program (M Jaworski)
Summary Lithium could solve several critical reactor issues
9M Ono ISLA 2015 Sept28 - 30 2915
The Li radiation power per one atom and one electron in coronal-quilibrium (net = infinity) and non-equilibrium regimesS V Mirnov et al Plasma Phys Control Fusion (2006)
Assumed radiation
level in the modeling
calculation for RLLD
Coronal-Equilibrium Value
Strong (~x100) Li Radiation Level Over Coronal Eq
Low particle confinement could increase radiation in divertor
Divertor Heat and Particle Flux
Li paths
LLD Tray
t ~ 100 ms
9
Radiation ~ N-Lit N-Li~ Li-inj t Radiation ~ Li-inj ~ 100 MJmole
10M Ono ISLA 2015 Sept28 - 30 2915
Radiative Liquid Lithium Divertor Proposed Handle divertor heat load volumetrically (3D vs 2D)
M Ono NF 2013 FEampD 2014
10
Y Hirooka at this conference
Flowing LL Particle Pumping Surfaces
Li+
Li++
Li+++
Li0
Heat Exchanger
B0
Divertor Heat and Particles Flux
Liquid Lithium (LL) ~ 1 lsec for pumping dust removal
LL Purification System to remove tritium impurities and dust
Li Evap Ionization (RLLD)~ few molesec
Li Radiative Mantle
Li wall coating condensation
Li path
Reduced Divertor Heat and Particle
Flux
Particle pumping by Li
coated wall
Divertor Strike Point
RLLD ARLLD Lithium provides low recycling radiative divertor
Active LL Injection (ARLLD)~ few molesec
11M Ono ISLA 2015 Sept28 - 30 2915 11
Concerns for lithium in reactor applicationbull Lithium evaporation is too
high in reactor PFC temperatures of ~ 600 degC LL needs to be le 450degC
bull Lithium can trap tritium and make the tritium inventory issues worse
bull Lithium is volatile and unsafe
bull Lithium is corrosive
LL Surface Temp (degC)
Log N-Li m2-s Lithium Evaporation Rate
IFMIF International Fusion Materials Irradiation Facility
H Kondo et al FEampD (2012)
LL operating
range Reactor FW temperature
12M Ono ISLA 2015 Sept28 - 30 2915
High Temperature First Wallbull High electrical conversion bull Cleaner wall ndash lower T inventorybull There are ideas to use lithium for the
first allhellip
Lower RLLD Operating Temperaturebull Prevents excessive Li vaporization
pressure bull Cooler divertor provides natural
collection (pumping) surfaces for entire reactor chamber
bull May permit use of iron based material for substrates and structural material
bull Reduces Li corrosive issuesbull Provides safer LL utilization
First Wall BlanketAt 500degC ndash 700degC
000000000000
Core ReactingPlasma
Edge Plasma
Scrape Off Layer
Flowing LLD Tray 200 ndash 500 degC
Closed RLLD
LL Out LL InLL In
12
Compatibility with liquid lithium with a hot reactor first wall RLLD configuration permits operation at lower T lt 450 degC
13M Ono ISLA 2015 Sept28 - 30 2915 13
Liquid lithium could also solve long-standing fusion reactor technology challenges ndash dust generation and T inventory
bull Erosion redeposition from plasma sputtering and disruptions including dust and flake generation
bull Tritium retention and removal Dust could further aggravate tritium inventory issues
G Federici C H Skinner et al NF 111308820011113088
Solution Liquid lithium loop
IFMIFEVEDA RLLD LoopTotal LL amount 25 t 05 tFlow rate 50 ls lt 1 lsOperation 25 days Steady-stateTImpurity lt 001 lt1 Li target under the
IFMIF conditions (15 ms 10minus3 Pa 250 degC)H Kondo et al FEampD (2014)
M Jaworki et al for NSTX-U at this symposium
14M Ono ISLA 2015 Sept28 - 30 2915
Dust Generation Likely a Serious Issue for ReactorHowever nature and quantity of dust generation
unknown
14
LLCirculation
Pump
Divertor Heat and Particle Flux
LL 1 ls
Back to RLLDARLLD
Dust particle
filter
Tritiumimpurity removal loop
Purified LL
Dustparticle filters are located below divertor and dust are carried to filter by gravity action
bull Each dustparticle filters when fulll drained of LL and removedbull Removed filter processed to recover trapped tritium
15M Ono ISLA 2015 Sept28 - 30 2915
Cold Trap Could Remove T D H and O Cold trap can be regenerated at higher
temperatures
15
K Natesan JNM 1983
bull At 200 degC hydrogen can be reduced toward 01 levelbull Oxygen is also effectively reduced with cold trapbull Nitrogen would require separate hot nitrogen trap
Nearly ~ 10 in solubility
16M Ono ISLA 2015 Sept28 - 30 2915
Realtime Tritium Recovery Needed~ 05 gsec of tritium must be recovered in real
time
16
Tritium Recycling
TritiumSeparater
Deuterium ampOther impurities as
well as dust
T ndash 05 gs
T D H O
LLCold Trap
LLCold Trap
01 TTo RLLDARLLD
Parallel paths to enable regeneration while operation
Drain liquid lithium before regeneration
Multiple filters to enable regeneration
Valves and pumps not shown
200degC
1 TFrom dustparticle filter loop
01 lsec of 1 T LL can carry 05 gs of T
17M Ono ISLA 2015 Sept28 - 30 2915
Tritium Inventory Control in Fusion Power PlantTotal site inventory maybe ~ 50 days or ~ 20 kg
17
M Nishikawa FST 2010
bull 1 (by weight) tritium concentration LL contains ~ 5 g of T l
bull LL inside VV may contain 100 l of LL or 05 kg for RLLDARLLD
bull LL in LL-loop before and in cold traps (~ 1) may contain 500 l of LL or 25 kg
bull LL after cold traps (~ 01) may contain 500 l of LL or 025kg
bull Total tritium inventory in RLLDALLD may contains 325 kg of T which is about 8 days ltlt 50 days
LL system may be compatible with the fusion reactor power plant tritium inventory requirements
18M Ono ISLA 2015 Sept28 - 30 2915
NSTX-U Construction complete First Plasma on August 10 2015
HHFW System
1st NBI
2nd NBI
NSTX-U
MPTS Exit Flight Tube
19M Ono ISLA 2015 Sept28 - 30 2915
LITERs
Comprehensive Lithium Boundary Physics ToolsBoronization Lithium Evaporators Granule Injector High Z tiles
Lithium Evaporator (LITERs)
Upward Li evaporator
High Z Tiles
T-bar mount
Castellations
Granule injector (GI) for ELM pacing
Rotating Impeller
Successfully tested on EAST and DIII-DGranules Li B4C Cf ~ up to 500 Hz
dTMB Gas Cabinet
Boronization System
Granular Reservoir
Electron beam for flash evaporation
crucible
FY 2016
FY 2016
20M Ono ISLA 2015 Sept28 - 30 2915
Enhanced Capability for Lithium PMI ResearchMulti-Institutional Contributions
ORNL
Lithium CHERS
Divertor ImagingSpectrometer
Dual-band fast IR Camera
Two fast 2D visible and IR cameras with full divertor coverage
Li I
C II
MAPP probe for between-shots surface analysis ndash Tested in LTX
LLNL ORNL UT-K
LLNL
Divertor fast pressure gauges
ORNL
Divertor fast eroding thermocouples
R Kaita at this symposium
21M Ono ISLA 2015 Sept28 - 30 2915
bull Lithium was observed to improve fusion plasma performance
bull Radiative LL Divertor (RLLD) and Active version of RLLD (ARLLD) are proposed to solve divertor heat flux issues
bull More experimental data needed to assess effectiveness of lithium radiation (lithium granular injection in NSTX-U planned)
bull Compatibility issues of lithium with fusion reactor were examined
bull Dustparticles are collected under divertor by a set of filters mainly by the gravity action
bull Tritium is removed in real time with a set of cold traps
bull Tritium inventory issue maybe manageable
bull NSTX-U is now starting to support lithium program (M Jaworski)
Summary Lithium could solve several critical reactor issues
10M Ono ISLA 2015 Sept28 - 30 2915
Radiative Liquid Lithium Divertor Proposed Handle divertor heat load volumetrically (3D vs 2D)
M Ono NF 2013 FEampD 2014
10
Y Hirooka at this conference
Flowing LL Particle Pumping Surfaces
Li+
Li++
Li+++
Li0
Heat Exchanger
B0
Divertor Heat and Particles Flux
Liquid Lithium (LL) ~ 1 lsec for pumping dust removal
LL Purification System to remove tritium impurities and dust
Li Evap Ionization (RLLD)~ few molesec
Li Radiative Mantle
Li wall coating condensation
Li path
Reduced Divertor Heat and Particle
Flux
Particle pumping by Li
coated wall
Divertor Strike Point
RLLD ARLLD Lithium provides low recycling radiative divertor
Active LL Injection (ARLLD)~ few molesec
11M Ono ISLA 2015 Sept28 - 30 2915 11
Concerns for lithium in reactor applicationbull Lithium evaporation is too
high in reactor PFC temperatures of ~ 600 degC LL needs to be le 450degC
bull Lithium can trap tritium and make the tritium inventory issues worse
bull Lithium is volatile and unsafe
bull Lithium is corrosive
LL Surface Temp (degC)
Log N-Li m2-s Lithium Evaporation Rate
IFMIF International Fusion Materials Irradiation Facility
H Kondo et al FEampD (2012)
LL operating
range Reactor FW temperature
12M Ono ISLA 2015 Sept28 - 30 2915
High Temperature First Wallbull High electrical conversion bull Cleaner wall ndash lower T inventorybull There are ideas to use lithium for the
first allhellip
Lower RLLD Operating Temperaturebull Prevents excessive Li vaporization
pressure bull Cooler divertor provides natural
collection (pumping) surfaces for entire reactor chamber
bull May permit use of iron based material for substrates and structural material
bull Reduces Li corrosive issuesbull Provides safer LL utilization
First Wall BlanketAt 500degC ndash 700degC
000000000000
Core ReactingPlasma
Edge Plasma
Scrape Off Layer
Flowing LLD Tray 200 ndash 500 degC
Closed RLLD
LL Out LL InLL In
12
Compatibility with liquid lithium with a hot reactor first wall RLLD configuration permits operation at lower T lt 450 degC
13M Ono ISLA 2015 Sept28 - 30 2915 13
Liquid lithium could also solve long-standing fusion reactor technology challenges ndash dust generation and T inventory
bull Erosion redeposition from plasma sputtering and disruptions including dust and flake generation
bull Tritium retention and removal Dust could further aggravate tritium inventory issues
G Federici C H Skinner et al NF 111308820011113088
Solution Liquid lithium loop
IFMIFEVEDA RLLD LoopTotal LL amount 25 t 05 tFlow rate 50 ls lt 1 lsOperation 25 days Steady-stateTImpurity lt 001 lt1 Li target under the
IFMIF conditions (15 ms 10minus3 Pa 250 degC)H Kondo et al FEampD (2014)
M Jaworki et al for NSTX-U at this symposium
14M Ono ISLA 2015 Sept28 - 30 2915
Dust Generation Likely a Serious Issue for ReactorHowever nature and quantity of dust generation
unknown
14
LLCirculation
Pump
Divertor Heat and Particle Flux
LL 1 ls
Back to RLLDARLLD
Dust particle
filter
Tritiumimpurity removal loop
Purified LL
Dustparticle filters are located below divertor and dust are carried to filter by gravity action
bull Each dustparticle filters when fulll drained of LL and removedbull Removed filter processed to recover trapped tritium
15M Ono ISLA 2015 Sept28 - 30 2915
Cold Trap Could Remove T D H and O Cold trap can be regenerated at higher
temperatures
15
K Natesan JNM 1983
bull At 200 degC hydrogen can be reduced toward 01 levelbull Oxygen is also effectively reduced with cold trapbull Nitrogen would require separate hot nitrogen trap
Nearly ~ 10 in solubility
16M Ono ISLA 2015 Sept28 - 30 2915
Realtime Tritium Recovery Needed~ 05 gsec of tritium must be recovered in real
time
16
Tritium Recycling
TritiumSeparater
Deuterium ampOther impurities as
well as dust
T ndash 05 gs
T D H O
LLCold Trap
LLCold Trap
01 TTo RLLDARLLD
Parallel paths to enable regeneration while operation
Drain liquid lithium before regeneration
Multiple filters to enable regeneration
Valves and pumps not shown
200degC
1 TFrom dustparticle filter loop
01 lsec of 1 T LL can carry 05 gs of T
17M Ono ISLA 2015 Sept28 - 30 2915
Tritium Inventory Control in Fusion Power PlantTotal site inventory maybe ~ 50 days or ~ 20 kg
17
M Nishikawa FST 2010
bull 1 (by weight) tritium concentration LL contains ~ 5 g of T l
bull LL inside VV may contain 100 l of LL or 05 kg for RLLDARLLD
bull LL in LL-loop before and in cold traps (~ 1) may contain 500 l of LL or 25 kg
bull LL after cold traps (~ 01) may contain 500 l of LL or 025kg
bull Total tritium inventory in RLLDALLD may contains 325 kg of T which is about 8 days ltlt 50 days
LL system may be compatible with the fusion reactor power plant tritium inventory requirements
18M Ono ISLA 2015 Sept28 - 30 2915
NSTX-U Construction complete First Plasma on August 10 2015
HHFW System
1st NBI
2nd NBI
NSTX-U
MPTS Exit Flight Tube
19M Ono ISLA 2015 Sept28 - 30 2915
LITERs
Comprehensive Lithium Boundary Physics ToolsBoronization Lithium Evaporators Granule Injector High Z tiles
Lithium Evaporator (LITERs)
Upward Li evaporator
High Z Tiles
T-bar mount
Castellations
Granule injector (GI) for ELM pacing
Rotating Impeller
Successfully tested on EAST and DIII-DGranules Li B4C Cf ~ up to 500 Hz
dTMB Gas Cabinet
Boronization System
Granular Reservoir
Electron beam for flash evaporation
crucible
FY 2016
FY 2016
20M Ono ISLA 2015 Sept28 - 30 2915
Enhanced Capability for Lithium PMI ResearchMulti-Institutional Contributions
ORNL
Lithium CHERS
Divertor ImagingSpectrometer
Dual-band fast IR Camera
Two fast 2D visible and IR cameras with full divertor coverage
Li I
C II
MAPP probe for between-shots surface analysis ndash Tested in LTX
LLNL ORNL UT-K
LLNL
Divertor fast pressure gauges
ORNL
Divertor fast eroding thermocouples
R Kaita at this symposium
21M Ono ISLA 2015 Sept28 - 30 2915
bull Lithium was observed to improve fusion plasma performance
bull Radiative LL Divertor (RLLD) and Active version of RLLD (ARLLD) are proposed to solve divertor heat flux issues
bull More experimental data needed to assess effectiveness of lithium radiation (lithium granular injection in NSTX-U planned)
bull Compatibility issues of lithium with fusion reactor were examined
bull Dustparticles are collected under divertor by a set of filters mainly by the gravity action
bull Tritium is removed in real time with a set of cold traps
bull Tritium inventory issue maybe manageable
bull NSTX-U is now starting to support lithium program (M Jaworski)
Summary Lithium could solve several critical reactor issues
11M Ono ISLA 2015 Sept28 - 30 2915 11
Concerns for lithium in reactor applicationbull Lithium evaporation is too
high in reactor PFC temperatures of ~ 600 degC LL needs to be le 450degC
bull Lithium can trap tritium and make the tritium inventory issues worse
bull Lithium is volatile and unsafe
bull Lithium is corrosive
LL Surface Temp (degC)
Log N-Li m2-s Lithium Evaporation Rate
IFMIF International Fusion Materials Irradiation Facility
H Kondo et al FEampD (2012)
LL operating
range Reactor FW temperature
12M Ono ISLA 2015 Sept28 - 30 2915
High Temperature First Wallbull High electrical conversion bull Cleaner wall ndash lower T inventorybull There are ideas to use lithium for the
first allhellip
Lower RLLD Operating Temperaturebull Prevents excessive Li vaporization
pressure bull Cooler divertor provides natural
collection (pumping) surfaces for entire reactor chamber
bull May permit use of iron based material for substrates and structural material
bull Reduces Li corrosive issuesbull Provides safer LL utilization
First Wall BlanketAt 500degC ndash 700degC
000000000000
Core ReactingPlasma
Edge Plasma
Scrape Off Layer
Flowing LLD Tray 200 ndash 500 degC
Closed RLLD
LL Out LL InLL In
12
Compatibility with liquid lithium with a hot reactor first wall RLLD configuration permits operation at lower T lt 450 degC
13M Ono ISLA 2015 Sept28 - 30 2915 13
Liquid lithium could also solve long-standing fusion reactor technology challenges ndash dust generation and T inventory
bull Erosion redeposition from plasma sputtering and disruptions including dust and flake generation
bull Tritium retention and removal Dust could further aggravate tritium inventory issues
G Federici C H Skinner et al NF 111308820011113088
Solution Liquid lithium loop
IFMIFEVEDA RLLD LoopTotal LL amount 25 t 05 tFlow rate 50 ls lt 1 lsOperation 25 days Steady-stateTImpurity lt 001 lt1 Li target under the
IFMIF conditions (15 ms 10minus3 Pa 250 degC)H Kondo et al FEampD (2014)
M Jaworki et al for NSTX-U at this symposium
14M Ono ISLA 2015 Sept28 - 30 2915
Dust Generation Likely a Serious Issue for ReactorHowever nature and quantity of dust generation
unknown
14
LLCirculation
Pump
Divertor Heat and Particle Flux
LL 1 ls
Back to RLLDARLLD
Dust particle
filter
Tritiumimpurity removal loop
Purified LL
Dustparticle filters are located below divertor and dust are carried to filter by gravity action
bull Each dustparticle filters when fulll drained of LL and removedbull Removed filter processed to recover trapped tritium
15M Ono ISLA 2015 Sept28 - 30 2915
Cold Trap Could Remove T D H and O Cold trap can be regenerated at higher
temperatures
15
K Natesan JNM 1983
bull At 200 degC hydrogen can be reduced toward 01 levelbull Oxygen is also effectively reduced with cold trapbull Nitrogen would require separate hot nitrogen trap
Nearly ~ 10 in solubility
16M Ono ISLA 2015 Sept28 - 30 2915
Realtime Tritium Recovery Needed~ 05 gsec of tritium must be recovered in real
time
16
Tritium Recycling
TritiumSeparater
Deuterium ampOther impurities as
well as dust
T ndash 05 gs
T D H O
LLCold Trap
LLCold Trap
01 TTo RLLDARLLD
Parallel paths to enable regeneration while operation
Drain liquid lithium before regeneration
Multiple filters to enable regeneration
Valves and pumps not shown
200degC
1 TFrom dustparticle filter loop
01 lsec of 1 T LL can carry 05 gs of T
17M Ono ISLA 2015 Sept28 - 30 2915
Tritium Inventory Control in Fusion Power PlantTotal site inventory maybe ~ 50 days or ~ 20 kg
17
M Nishikawa FST 2010
bull 1 (by weight) tritium concentration LL contains ~ 5 g of T l
bull LL inside VV may contain 100 l of LL or 05 kg for RLLDARLLD
bull LL in LL-loop before and in cold traps (~ 1) may contain 500 l of LL or 25 kg
bull LL after cold traps (~ 01) may contain 500 l of LL or 025kg
bull Total tritium inventory in RLLDALLD may contains 325 kg of T which is about 8 days ltlt 50 days
LL system may be compatible with the fusion reactor power plant tritium inventory requirements
18M Ono ISLA 2015 Sept28 - 30 2915
NSTX-U Construction complete First Plasma on August 10 2015
HHFW System
1st NBI
2nd NBI
NSTX-U
MPTS Exit Flight Tube
19M Ono ISLA 2015 Sept28 - 30 2915
LITERs
Comprehensive Lithium Boundary Physics ToolsBoronization Lithium Evaporators Granule Injector High Z tiles
Lithium Evaporator (LITERs)
Upward Li evaporator
High Z Tiles
T-bar mount
Castellations
Granule injector (GI) for ELM pacing
Rotating Impeller
Successfully tested on EAST and DIII-DGranules Li B4C Cf ~ up to 500 Hz
dTMB Gas Cabinet
Boronization System
Granular Reservoir
Electron beam for flash evaporation
crucible
FY 2016
FY 2016
20M Ono ISLA 2015 Sept28 - 30 2915
Enhanced Capability for Lithium PMI ResearchMulti-Institutional Contributions
ORNL
Lithium CHERS
Divertor ImagingSpectrometer
Dual-band fast IR Camera
Two fast 2D visible and IR cameras with full divertor coverage
Li I
C II
MAPP probe for between-shots surface analysis ndash Tested in LTX
LLNL ORNL UT-K
LLNL
Divertor fast pressure gauges
ORNL
Divertor fast eroding thermocouples
R Kaita at this symposium
21M Ono ISLA 2015 Sept28 - 30 2915
bull Lithium was observed to improve fusion plasma performance
bull Radiative LL Divertor (RLLD) and Active version of RLLD (ARLLD) are proposed to solve divertor heat flux issues
bull More experimental data needed to assess effectiveness of lithium radiation (lithium granular injection in NSTX-U planned)
bull Compatibility issues of lithium with fusion reactor were examined
bull Dustparticles are collected under divertor by a set of filters mainly by the gravity action
bull Tritium is removed in real time with a set of cold traps
bull Tritium inventory issue maybe manageable
bull NSTX-U is now starting to support lithium program (M Jaworski)
Summary Lithium could solve several critical reactor issues
12M Ono ISLA 2015 Sept28 - 30 2915
High Temperature First Wallbull High electrical conversion bull Cleaner wall ndash lower T inventorybull There are ideas to use lithium for the
first allhellip
Lower RLLD Operating Temperaturebull Prevents excessive Li vaporization
pressure bull Cooler divertor provides natural
collection (pumping) surfaces for entire reactor chamber
bull May permit use of iron based material for substrates and structural material
bull Reduces Li corrosive issuesbull Provides safer LL utilization
First Wall BlanketAt 500degC ndash 700degC
000000000000
Core ReactingPlasma
Edge Plasma
Scrape Off Layer
Flowing LLD Tray 200 ndash 500 degC
Closed RLLD
LL Out LL InLL In
12
Compatibility with liquid lithium with a hot reactor first wall RLLD configuration permits operation at lower T lt 450 degC
13M Ono ISLA 2015 Sept28 - 30 2915 13
Liquid lithium could also solve long-standing fusion reactor technology challenges ndash dust generation and T inventory
bull Erosion redeposition from plasma sputtering and disruptions including dust and flake generation
bull Tritium retention and removal Dust could further aggravate tritium inventory issues
G Federici C H Skinner et al NF 111308820011113088
Solution Liquid lithium loop
IFMIFEVEDA RLLD LoopTotal LL amount 25 t 05 tFlow rate 50 ls lt 1 lsOperation 25 days Steady-stateTImpurity lt 001 lt1 Li target under the
IFMIF conditions (15 ms 10minus3 Pa 250 degC)H Kondo et al FEampD (2014)
M Jaworki et al for NSTX-U at this symposium
14M Ono ISLA 2015 Sept28 - 30 2915
Dust Generation Likely a Serious Issue for ReactorHowever nature and quantity of dust generation
unknown
14
LLCirculation
Pump
Divertor Heat and Particle Flux
LL 1 ls
Back to RLLDARLLD
Dust particle
filter
Tritiumimpurity removal loop
Purified LL
Dustparticle filters are located below divertor and dust are carried to filter by gravity action
bull Each dustparticle filters when fulll drained of LL and removedbull Removed filter processed to recover trapped tritium
15M Ono ISLA 2015 Sept28 - 30 2915
Cold Trap Could Remove T D H and O Cold trap can be regenerated at higher
temperatures
15
K Natesan JNM 1983
bull At 200 degC hydrogen can be reduced toward 01 levelbull Oxygen is also effectively reduced with cold trapbull Nitrogen would require separate hot nitrogen trap
Nearly ~ 10 in solubility
16M Ono ISLA 2015 Sept28 - 30 2915
Realtime Tritium Recovery Needed~ 05 gsec of tritium must be recovered in real
time
16
Tritium Recycling
TritiumSeparater
Deuterium ampOther impurities as
well as dust
T ndash 05 gs
T D H O
LLCold Trap
LLCold Trap
01 TTo RLLDARLLD
Parallel paths to enable regeneration while operation
Drain liquid lithium before regeneration
Multiple filters to enable regeneration
Valves and pumps not shown
200degC
1 TFrom dustparticle filter loop
01 lsec of 1 T LL can carry 05 gs of T
17M Ono ISLA 2015 Sept28 - 30 2915
Tritium Inventory Control in Fusion Power PlantTotal site inventory maybe ~ 50 days or ~ 20 kg
17
M Nishikawa FST 2010
bull 1 (by weight) tritium concentration LL contains ~ 5 g of T l
bull LL inside VV may contain 100 l of LL or 05 kg for RLLDARLLD
bull LL in LL-loop before and in cold traps (~ 1) may contain 500 l of LL or 25 kg
bull LL after cold traps (~ 01) may contain 500 l of LL or 025kg
bull Total tritium inventory in RLLDALLD may contains 325 kg of T which is about 8 days ltlt 50 days
LL system may be compatible with the fusion reactor power plant tritium inventory requirements
18M Ono ISLA 2015 Sept28 - 30 2915
NSTX-U Construction complete First Plasma on August 10 2015
HHFW System
1st NBI
2nd NBI
NSTX-U
MPTS Exit Flight Tube
19M Ono ISLA 2015 Sept28 - 30 2915
LITERs
Comprehensive Lithium Boundary Physics ToolsBoronization Lithium Evaporators Granule Injector High Z tiles
Lithium Evaporator (LITERs)
Upward Li evaporator
High Z Tiles
T-bar mount
Castellations
Granule injector (GI) for ELM pacing
Rotating Impeller
Successfully tested on EAST and DIII-DGranules Li B4C Cf ~ up to 500 Hz
dTMB Gas Cabinet
Boronization System
Granular Reservoir
Electron beam for flash evaporation
crucible
FY 2016
FY 2016
20M Ono ISLA 2015 Sept28 - 30 2915
Enhanced Capability for Lithium PMI ResearchMulti-Institutional Contributions
ORNL
Lithium CHERS
Divertor ImagingSpectrometer
Dual-band fast IR Camera
Two fast 2D visible and IR cameras with full divertor coverage
Li I
C II
MAPP probe for between-shots surface analysis ndash Tested in LTX
LLNL ORNL UT-K
LLNL
Divertor fast pressure gauges
ORNL
Divertor fast eroding thermocouples
R Kaita at this symposium
21M Ono ISLA 2015 Sept28 - 30 2915
bull Lithium was observed to improve fusion plasma performance
bull Radiative LL Divertor (RLLD) and Active version of RLLD (ARLLD) are proposed to solve divertor heat flux issues
bull More experimental data needed to assess effectiveness of lithium radiation (lithium granular injection in NSTX-U planned)
bull Compatibility issues of lithium with fusion reactor were examined
bull Dustparticles are collected under divertor by a set of filters mainly by the gravity action
bull Tritium is removed in real time with a set of cold traps
bull Tritium inventory issue maybe manageable
bull NSTX-U is now starting to support lithium program (M Jaworski)
Summary Lithium could solve several critical reactor issues
13M Ono ISLA 2015 Sept28 - 30 2915 13
Liquid lithium could also solve long-standing fusion reactor technology challenges ndash dust generation and T inventory
bull Erosion redeposition from plasma sputtering and disruptions including dust and flake generation
bull Tritium retention and removal Dust could further aggravate tritium inventory issues
G Federici C H Skinner et al NF 111308820011113088
Solution Liquid lithium loop
IFMIFEVEDA RLLD LoopTotal LL amount 25 t 05 tFlow rate 50 ls lt 1 lsOperation 25 days Steady-stateTImpurity lt 001 lt1 Li target under the
IFMIF conditions (15 ms 10minus3 Pa 250 degC)H Kondo et al FEampD (2014)
M Jaworki et al for NSTX-U at this symposium
14M Ono ISLA 2015 Sept28 - 30 2915
Dust Generation Likely a Serious Issue for ReactorHowever nature and quantity of dust generation
unknown
14
LLCirculation
Pump
Divertor Heat and Particle Flux
LL 1 ls
Back to RLLDARLLD
Dust particle
filter
Tritiumimpurity removal loop
Purified LL
Dustparticle filters are located below divertor and dust are carried to filter by gravity action
bull Each dustparticle filters when fulll drained of LL and removedbull Removed filter processed to recover trapped tritium
15M Ono ISLA 2015 Sept28 - 30 2915
Cold Trap Could Remove T D H and O Cold trap can be regenerated at higher
temperatures
15
K Natesan JNM 1983
bull At 200 degC hydrogen can be reduced toward 01 levelbull Oxygen is also effectively reduced with cold trapbull Nitrogen would require separate hot nitrogen trap
Nearly ~ 10 in solubility
16M Ono ISLA 2015 Sept28 - 30 2915
Realtime Tritium Recovery Needed~ 05 gsec of tritium must be recovered in real
time
16
Tritium Recycling
TritiumSeparater
Deuterium ampOther impurities as
well as dust
T ndash 05 gs
T D H O
LLCold Trap
LLCold Trap
01 TTo RLLDARLLD
Parallel paths to enable regeneration while operation
Drain liquid lithium before regeneration
Multiple filters to enable regeneration
Valves and pumps not shown
200degC
1 TFrom dustparticle filter loop
01 lsec of 1 T LL can carry 05 gs of T
17M Ono ISLA 2015 Sept28 - 30 2915
Tritium Inventory Control in Fusion Power PlantTotal site inventory maybe ~ 50 days or ~ 20 kg
17
M Nishikawa FST 2010
bull 1 (by weight) tritium concentration LL contains ~ 5 g of T l
bull LL inside VV may contain 100 l of LL or 05 kg for RLLDARLLD
bull LL in LL-loop before and in cold traps (~ 1) may contain 500 l of LL or 25 kg
bull LL after cold traps (~ 01) may contain 500 l of LL or 025kg
bull Total tritium inventory in RLLDALLD may contains 325 kg of T which is about 8 days ltlt 50 days
LL system may be compatible with the fusion reactor power plant tritium inventory requirements
18M Ono ISLA 2015 Sept28 - 30 2915
NSTX-U Construction complete First Plasma on August 10 2015
HHFW System
1st NBI
2nd NBI
NSTX-U
MPTS Exit Flight Tube
19M Ono ISLA 2015 Sept28 - 30 2915
LITERs
Comprehensive Lithium Boundary Physics ToolsBoronization Lithium Evaporators Granule Injector High Z tiles
Lithium Evaporator (LITERs)
Upward Li evaporator
High Z Tiles
T-bar mount
Castellations
Granule injector (GI) for ELM pacing
Rotating Impeller
Successfully tested on EAST and DIII-DGranules Li B4C Cf ~ up to 500 Hz
dTMB Gas Cabinet
Boronization System
Granular Reservoir
Electron beam for flash evaporation
crucible
FY 2016
FY 2016
20M Ono ISLA 2015 Sept28 - 30 2915
Enhanced Capability for Lithium PMI ResearchMulti-Institutional Contributions
ORNL
Lithium CHERS
Divertor ImagingSpectrometer
Dual-band fast IR Camera
Two fast 2D visible and IR cameras with full divertor coverage
Li I
C II
MAPP probe for between-shots surface analysis ndash Tested in LTX
LLNL ORNL UT-K
LLNL
Divertor fast pressure gauges
ORNL
Divertor fast eroding thermocouples
R Kaita at this symposium
21M Ono ISLA 2015 Sept28 - 30 2915
bull Lithium was observed to improve fusion plasma performance
bull Radiative LL Divertor (RLLD) and Active version of RLLD (ARLLD) are proposed to solve divertor heat flux issues
bull More experimental data needed to assess effectiveness of lithium radiation (lithium granular injection in NSTX-U planned)
bull Compatibility issues of lithium with fusion reactor were examined
bull Dustparticles are collected under divertor by a set of filters mainly by the gravity action
bull Tritium is removed in real time with a set of cold traps
bull Tritium inventory issue maybe manageable
bull NSTX-U is now starting to support lithium program (M Jaworski)
Summary Lithium could solve several critical reactor issues
14M Ono ISLA 2015 Sept28 - 30 2915
Dust Generation Likely a Serious Issue for ReactorHowever nature and quantity of dust generation
unknown
14
LLCirculation
Pump
Divertor Heat and Particle Flux
LL 1 ls
Back to RLLDARLLD
Dust particle
filter
Tritiumimpurity removal loop
Purified LL
Dustparticle filters are located below divertor and dust are carried to filter by gravity action
bull Each dustparticle filters when fulll drained of LL and removedbull Removed filter processed to recover trapped tritium
15M Ono ISLA 2015 Sept28 - 30 2915
Cold Trap Could Remove T D H and O Cold trap can be regenerated at higher
temperatures
15
K Natesan JNM 1983
bull At 200 degC hydrogen can be reduced toward 01 levelbull Oxygen is also effectively reduced with cold trapbull Nitrogen would require separate hot nitrogen trap
Nearly ~ 10 in solubility
16M Ono ISLA 2015 Sept28 - 30 2915
Realtime Tritium Recovery Needed~ 05 gsec of tritium must be recovered in real
time
16
Tritium Recycling
TritiumSeparater
Deuterium ampOther impurities as
well as dust
T ndash 05 gs
T D H O
LLCold Trap
LLCold Trap
01 TTo RLLDARLLD
Parallel paths to enable regeneration while operation
Drain liquid lithium before regeneration
Multiple filters to enable regeneration
Valves and pumps not shown
200degC
1 TFrom dustparticle filter loop
01 lsec of 1 T LL can carry 05 gs of T
17M Ono ISLA 2015 Sept28 - 30 2915
Tritium Inventory Control in Fusion Power PlantTotal site inventory maybe ~ 50 days or ~ 20 kg
17
M Nishikawa FST 2010
bull 1 (by weight) tritium concentration LL contains ~ 5 g of T l
bull LL inside VV may contain 100 l of LL or 05 kg for RLLDARLLD
bull LL in LL-loop before and in cold traps (~ 1) may contain 500 l of LL or 25 kg
bull LL after cold traps (~ 01) may contain 500 l of LL or 025kg
bull Total tritium inventory in RLLDALLD may contains 325 kg of T which is about 8 days ltlt 50 days
LL system may be compatible with the fusion reactor power plant tritium inventory requirements
18M Ono ISLA 2015 Sept28 - 30 2915
NSTX-U Construction complete First Plasma on August 10 2015
HHFW System
1st NBI
2nd NBI
NSTX-U
MPTS Exit Flight Tube
19M Ono ISLA 2015 Sept28 - 30 2915
LITERs
Comprehensive Lithium Boundary Physics ToolsBoronization Lithium Evaporators Granule Injector High Z tiles
Lithium Evaporator (LITERs)
Upward Li evaporator
High Z Tiles
T-bar mount
Castellations
Granule injector (GI) for ELM pacing
Rotating Impeller
Successfully tested on EAST and DIII-DGranules Li B4C Cf ~ up to 500 Hz
dTMB Gas Cabinet
Boronization System
Granular Reservoir
Electron beam for flash evaporation
crucible
FY 2016
FY 2016
20M Ono ISLA 2015 Sept28 - 30 2915
Enhanced Capability for Lithium PMI ResearchMulti-Institutional Contributions
ORNL
Lithium CHERS
Divertor ImagingSpectrometer
Dual-band fast IR Camera
Two fast 2D visible and IR cameras with full divertor coverage
Li I
C II
MAPP probe for between-shots surface analysis ndash Tested in LTX
LLNL ORNL UT-K
LLNL
Divertor fast pressure gauges
ORNL
Divertor fast eroding thermocouples
R Kaita at this symposium
21M Ono ISLA 2015 Sept28 - 30 2915
bull Lithium was observed to improve fusion plasma performance
bull Radiative LL Divertor (RLLD) and Active version of RLLD (ARLLD) are proposed to solve divertor heat flux issues
bull More experimental data needed to assess effectiveness of lithium radiation (lithium granular injection in NSTX-U planned)
bull Compatibility issues of lithium with fusion reactor were examined
bull Dustparticles are collected under divertor by a set of filters mainly by the gravity action
bull Tritium is removed in real time with a set of cold traps
bull Tritium inventory issue maybe manageable
bull NSTX-U is now starting to support lithium program (M Jaworski)
Summary Lithium could solve several critical reactor issues
15M Ono ISLA 2015 Sept28 - 30 2915
Cold Trap Could Remove T D H and O Cold trap can be regenerated at higher
temperatures
15
K Natesan JNM 1983
bull At 200 degC hydrogen can be reduced toward 01 levelbull Oxygen is also effectively reduced with cold trapbull Nitrogen would require separate hot nitrogen trap
Nearly ~ 10 in solubility
16M Ono ISLA 2015 Sept28 - 30 2915
Realtime Tritium Recovery Needed~ 05 gsec of tritium must be recovered in real
time
16
Tritium Recycling
TritiumSeparater
Deuterium ampOther impurities as
well as dust
T ndash 05 gs
T D H O
LLCold Trap
LLCold Trap
01 TTo RLLDARLLD
Parallel paths to enable regeneration while operation
Drain liquid lithium before regeneration
Multiple filters to enable regeneration
Valves and pumps not shown
200degC
1 TFrom dustparticle filter loop
01 lsec of 1 T LL can carry 05 gs of T
17M Ono ISLA 2015 Sept28 - 30 2915
Tritium Inventory Control in Fusion Power PlantTotal site inventory maybe ~ 50 days or ~ 20 kg
17
M Nishikawa FST 2010
bull 1 (by weight) tritium concentration LL contains ~ 5 g of T l
bull LL inside VV may contain 100 l of LL or 05 kg for RLLDARLLD
bull LL in LL-loop before and in cold traps (~ 1) may contain 500 l of LL or 25 kg
bull LL after cold traps (~ 01) may contain 500 l of LL or 025kg
bull Total tritium inventory in RLLDALLD may contains 325 kg of T which is about 8 days ltlt 50 days
LL system may be compatible with the fusion reactor power plant tritium inventory requirements
18M Ono ISLA 2015 Sept28 - 30 2915
NSTX-U Construction complete First Plasma on August 10 2015
HHFW System
1st NBI
2nd NBI
NSTX-U
MPTS Exit Flight Tube
19M Ono ISLA 2015 Sept28 - 30 2915
LITERs
Comprehensive Lithium Boundary Physics ToolsBoronization Lithium Evaporators Granule Injector High Z tiles
Lithium Evaporator (LITERs)
Upward Li evaporator
High Z Tiles
T-bar mount
Castellations
Granule injector (GI) for ELM pacing
Rotating Impeller
Successfully tested on EAST and DIII-DGranules Li B4C Cf ~ up to 500 Hz
dTMB Gas Cabinet
Boronization System
Granular Reservoir
Electron beam for flash evaporation
crucible
FY 2016
FY 2016
20M Ono ISLA 2015 Sept28 - 30 2915
Enhanced Capability for Lithium PMI ResearchMulti-Institutional Contributions
ORNL
Lithium CHERS
Divertor ImagingSpectrometer
Dual-band fast IR Camera
Two fast 2D visible and IR cameras with full divertor coverage
Li I
C II
MAPP probe for between-shots surface analysis ndash Tested in LTX
LLNL ORNL UT-K
LLNL
Divertor fast pressure gauges
ORNL
Divertor fast eroding thermocouples
R Kaita at this symposium
21M Ono ISLA 2015 Sept28 - 30 2915
bull Lithium was observed to improve fusion plasma performance
bull Radiative LL Divertor (RLLD) and Active version of RLLD (ARLLD) are proposed to solve divertor heat flux issues
bull More experimental data needed to assess effectiveness of lithium radiation (lithium granular injection in NSTX-U planned)
bull Compatibility issues of lithium with fusion reactor were examined
bull Dustparticles are collected under divertor by a set of filters mainly by the gravity action
bull Tritium is removed in real time with a set of cold traps
bull Tritium inventory issue maybe manageable
bull NSTX-U is now starting to support lithium program (M Jaworski)
Summary Lithium could solve several critical reactor issues
16M Ono ISLA 2015 Sept28 - 30 2915
Realtime Tritium Recovery Needed~ 05 gsec of tritium must be recovered in real
time
16
Tritium Recycling
TritiumSeparater
Deuterium ampOther impurities as
well as dust
T ndash 05 gs
T D H O
LLCold Trap
LLCold Trap
01 TTo RLLDARLLD
Parallel paths to enable regeneration while operation
Drain liquid lithium before regeneration
Multiple filters to enable regeneration
Valves and pumps not shown
200degC
1 TFrom dustparticle filter loop
01 lsec of 1 T LL can carry 05 gs of T
17M Ono ISLA 2015 Sept28 - 30 2915
Tritium Inventory Control in Fusion Power PlantTotal site inventory maybe ~ 50 days or ~ 20 kg
17
M Nishikawa FST 2010
bull 1 (by weight) tritium concentration LL contains ~ 5 g of T l
bull LL inside VV may contain 100 l of LL or 05 kg for RLLDARLLD
bull LL in LL-loop before and in cold traps (~ 1) may contain 500 l of LL or 25 kg
bull LL after cold traps (~ 01) may contain 500 l of LL or 025kg
bull Total tritium inventory in RLLDALLD may contains 325 kg of T which is about 8 days ltlt 50 days
LL system may be compatible with the fusion reactor power plant tritium inventory requirements
18M Ono ISLA 2015 Sept28 - 30 2915
NSTX-U Construction complete First Plasma on August 10 2015
HHFW System
1st NBI
2nd NBI
NSTX-U
MPTS Exit Flight Tube
19M Ono ISLA 2015 Sept28 - 30 2915
LITERs
Comprehensive Lithium Boundary Physics ToolsBoronization Lithium Evaporators Granule Injector High Z tiles
Lithium Evaporator (LITERs)
Upward Li evaporator
High Z Tiles
T-bar mount
Castellations
Granule injector (GI) for ELM pacing
Rotating Impeller
Successfully tested on EAST and DIII-DGranules Li B4C Cf ~ up to 500 Hz
dTMB Gas Cabinet
Boronization System
Granular Reservoir
Electron beam for flash evaporation
crucible
FY 2016
FY 2016
20M Ono ISLA 2015 Sept28 - 30 2915
Enhanced Capability for Lithium PMI ResearchMulti-Institutional Contributions
ORNL
Lithium CHERS
Divertor ImagingSpectrometer
Dual-band fast IR Camera
Two fast 2D visible and IR cameras with full divertor coverage
Li I
C II
MAPP probe for between-shots surface analysis ndash Tested in LTX
LLNL ORNL UT-K
LLNL
Divertor fast pressure gauges
ORNL
Divertor fast eroding thermocouples
R Kaita at this symposium
21M Ono ISLA 2015 Sept28 - 30 2915
bull Lithium was observed to improve fusion plasma performance
bull Radiative LL Divertor (RLLD) and Active version of RLLD (ARLLD) are proposed to solve divertor heat flux issues
bull More experimental data needed to assess effectiveness of lithium radiation (lithium granular injection in NSTX-U planned)
bull Compatibility issues of lithium with fusion reactor were examined
bull Dustparticles are collected under divertor by a set of filters mainly by the gravity action
bull Tritium is removed in real time with a set of cold traps
bull Tritium inventory issue maybe manageable
bull NSTX-U is now starting to support lithium program (M Jaworski)
Summary Lithium could solve several critical reactor issues
17M Ono ISLA 2015 Sept28 - 30 2915
Tritium Inventory Control in Fusion Power PlantTotal site inventory maybe ~ 50 days or ~ 20 kg
17
M Nishikawa FST 2010
bull 1 (by weight) tritium concentration LL contains ~ 5 g of T l
bull LL inside VV may contain 100 l of LL or 05 kg for RLLDARLLD
bull LL in LL-loop before and in cold traps (~ 1) may contain 500 l of LL or 25 kg
bull LL after cold traps (~ 01) may contain 500 l of LL or 025kg
bull Total tritium inventory in RLLDALLD may contains 325 kg of T which is about 8 days ltlt 50 days
LL system may be compatible with the fusion reactor power plant tritium inventory requirements
18M Ono ISLA 2015 Sept28 - 30 2915
NSTX-U Construction complete First Plasma on August 10 2015
HHFW System
1st NBI
2nd NBI
NSTX-U
MPTS Exit Flight Tube
19M Ono ISLA 2015 Sept28 - 30 2915
LITERs
Comprehensive Lithium Boundary Physics ToolsBoronization Lithium Evaporators Granule Injector High Z tiles
Lithium Evaporator (LITERs)
Upward Li evaporator
High Z Tiles
T-bar mount
Castellations
Granule injector (GI) for ELM pacing
Rotating Impeller
Successfully tested on EAST and DIII-DGranules Li B4C Cf ~ up to 500 Hz
dTMB Gas Cabinet
Boronization System
Granular Reservoir
Electron beam for flash evaporation
crucible
FY 2016
FY 2016
20M Ono ISLA 2015 Sept28 - 30 2915
Enhanced Capability for Lithium PMI ResearchMulti-Institutional Contributions
ORNL
Lithium CHERS
Divertor ImagingSpectrometer
Dual-band fast IR Camera
Two fast 2D visible and IR cameras with full divertor coverage
Li I
C II
MAPP probe for between-shots surface analysis ndash Tested in LTX
LLNL ORNL UT-K
LLNL
Divertor fast pressure gauges
ORNL
Divertor fast eroding thermocouples
R Kaita at this symposium
21M Ono ISLA 2015 Sept28 - 30 2915
bull Lithium was observed to improve fusion plasma performance
bull Radiative LL Divertor (RLLD) and Active version of RLLD (ARLLD) are proposed to solve divertor heat flux issues
bull More experimental data needed to assess effectiveness of lithium radiation (lithium granular injection in NSTX-U planned)
bull Compatibility issues of lithium with fusion reactor were examined
bull Dustparticles are collected under divertor by a set of filters mainly by the gravity action
bull Tritium is removed in real time with a set of cold traps
bull Tritium inventory issue maybe manageable
bull NSTX-U is now starting to support lithium program (M Jaworski)
Summary Lithium could solve several critical reactor issues
18M Ono ISLA 2015 Sept28 - 30 2915
NSTX-U Construction complete First Plasma on August 10 2015
HHFW System
1st NBI
2nd NBI
NSTX-U
MPTS Exit Flight Tube
19M Ono ISLA 2015 Sept28 - 30 2915
LITERs
Comprehensive Lithium Boundary Physics ToolsBoronization Lithium Evaporators Granule Injector High Z tiles
Lithium Evaporator (LITERs)
Upward Li evaporator
High Z Tiles
T-bar mount
Castellations
Granule injector (GI) for ELM pacing
Rotating Impeller
Successfully tested on EAST and DIII-DGranules Li B4C Cf ~ up to 500 Hz
dTMB Gas Cabinet
Boronization System
Granular Reservoir
Electron beam for flash evaporation
crucible
FY 2016
FY 2016
20M Ono ISLA 2015 Sept28 - 30 2915
Enhanced Capability for Lithium PMI ResearchMulti-Institutional Contributions
ORNL
Lithium CHERS
Divertor ImagingSpectrometer
Dual-band fast IR Camera
Two fast 2D visible and IR cameras with full divertor coverage
Li I
C II
MAPP probe for between-shots surface analysis ndash Tested in LTX
LLNL ORNL UT-K
LLNL
Divertor fast pressure gauges
ORNL
Divertor fast eroding thermocouples
R Kaita at this symposium
21M Ono ISLA 2015 Sept28 - 30 2915
bull Lithium was observed to improve fusion plasma performance
bull Radiative LL Divertor (RLLD) and Active version of RLLD (ARLLD) are proposed to solve divertor heat flux issues
bull More experimental data needed to assess effectiveness of lithium radiation (lithium granular injection in NSTX-U planned)
bull Compatibility issues of lithium with fusion reactor were examined
bull Dustparticles are collected under divertor by a set of filters mainly by the gravity action
bull Tritium is removed in real time with a set of cold traps
bull Tritium inventory issue maybe manageable
bull NSTX-U is now starting to support lithium program (M Jaworski)
Summary Lithium could solve several critical reactor issues
19M Ono ISLA 2015 Sept28 - 30 2915
LITERs
Comprehensive Lithium Boundary Physics ToolsBoronization Lithium Evaporators Granule Injector High Z tiles
Lithium Evaporator (LITERs)
Upward Li evaporator
High Z Tiles
T-bar mount
Castellations
Granule injector (GI) for ELM pacing
Rotating Impeller
Successfully tested on EAST and DIII-DGranules Li B4C Cf ~ up to 500 Hz
dTMB Gas Cabinet
Boronization System
Granular Reservoir
Electron beam for flash evaporation
crucible
FY 2016
FY 2016
20M Ono ISLA 2015 Sept28 - 30 2915
Enhanced Capability for Lithium PMI ResearchMulti-Institutional Contributions
ORNL
Lithium CHERS
Divertor ImagingSpectrometer
Dual-band fast IR Camera
Two fast 2D visible and IR cameras with full divertor coverage
Li I
C II
MAPP probe for between-shots surface analysis ndash Tested in LTX
LLNL ORNL UT-K
LLNL
Divertor fast pressure gauges
ORNL
Divertor fast eroding thermocouples
R Kaita at this symposium
21M Ono ISLA 2015 Sept28 - 30 2915
bull Lithium was observed to improve fusion plasma performance
bull Radiative LL Divertor (RLLD) and Active version of RLLD (ARLLD) are proposed to solve divertor heat flux issues
bull More experimental data needed to assess effectiveness of lithium radiation (lithium granular injection in NSTX-U planned)
bull Compatibility issues of lithium with fusion reactor were examined
bull Dustparticles are collected under divertor by a set of filters mainly by the gravity action
bull Tritium is removed in real time with a set of cold traps
bull Tritium inventory issue maybe manageable
bull NSTX-U is now starting to support lithium program (M Jaworski)
Summary Lithium could solve several critical reactor issues
20M Ono ISLA 2015 Sept28 - 30 2915
Enhanced Capability for Lithium PMI ResearchMulti-Institutional Contributions
ORNL
Lithium CHERS
Divertor ImagingSpectrometer
Dual-band fast IR Camera
Two fast 2D visible and IR cameras with full divertor coverage
Li I
C II
MAPP probe for between-shots surface analysis ndash Tested in LTX
LLNL ORNL UT-K
LLNL
Divertor fast pressure gauges
ORNL
Divertor fast eroding thermocouples
R Kaita at this symposium
21M Ono ISLA 2015 Sept28 - 30 2915
bull Lithium was observed to improve fusion plasma performance
bull Radiative LL Divertor (RLLD) and Active version of RLLD (ARLLD) are proposed to solve divertor heat flux issues
bull More experimental data needed to assess effectiveness of lithium radiation (lithium granular injection in NSTX-U planned)
bull Compatibility issues of lithium with fusion reactor were examined
bull Dustparticles are collected under divertor by a set of filters mainly by the gravity action
bull Tritium is removed in real time with a set of cold traps
bull Tritium inventory issue maybe manageable
bull NSTX-U is now starting to support lithium program (M Jaworski)
Summary Lithium could solve several critical reactor issues
21M Ono ISLA 2015 Sept28 - 30 2915
bull Lithium was observed to improve fusion plasma performance
bull Radiative LL Divertor (RLLD) and Active version of RLLD (ARLLD) are proposed to solve divertor heat flux issues
bull More experimental data needed to assess effectiveness of lithium radiation (lithium granular injection in NSTX-U planned)
bull Compatibility issues of lithium with fusion reactor were examined
bull Dustparticles are collected under divertor by a set of filters mainly by the gravity action
bull Tritium is removed in real time with a set of cold traps
bull Tritium inventory issue maybe manageable
bull NSTX-U is now starting to support lithium program (M Jaworski)
Summary Lithium could solve several critical reactor issues
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