Role of Fusion Energy in the 21 st Century Farrokh Najmabadi Prof. of Electrical Engineering...
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Transcript of Role of Fusion Energy in the 21 st Century Farrokh Najmabadi Prof. of Electrical Engineering...
Role of Fusion Energy in the 21st Century
Farrokh NajmabadiProf. of Electrical EngineeringDirector of Center for Energy ResearchUC San Diego
Lehigh UniversityPhysics Department ColloquiumApril 26, 2012
UCSD Center for Energy Research
Staff 90 Graduate Students (PhD) 25 Paid Student Researchers (non-Degree) 15 Annual Research Funding (09-10) $8.5M* Number of Active Grants (09-10) 49
Staff 90 Graduate Students (PhD) 25 Paid Student Researchers (non-Degree) 15 Annual Research Funding (09-10) $8.5M* Number of Active Grants (09-10) 49
Total Funding received (06-10) $40M Number of Journal publications (06-10) 262 Number of Conference papers (06-10) 163 Professional Society Awards 12
Total Funding received (06-10) $40M Number of Journal publications (06-10) 262 Number of Conference papers (06-10) 163 Professional Society Awards 12
Plasma Physics & Fusion Energy Solar Energy (renewable) forecasting & integration Fuel Cells
Plasma Physics & Fusion Energy Solar Energy (renewable) forecasting & integration Fuel Cells
The Energy Challenge
Scale:1 EJ = 1018 J = 24 Mtoe1TW = 31.5 EJ/yearWorld energy use ~ 450 EJ/year
~ 14 TW
With industrialization of emerging nations, energy use is expected to grow ~ 4 fold in this century (average 1.6% annual growth rate)
With industrialization of emerging nations, energy use is expected to grow ~ 4 fold in this century (average 1.6% annual growth rate)
0
50
100
150
200
250
300
350
400
0 5,000 10,000 15,000 20,000 25,000 30,000 35,000 40,000
GDP per capita (PPP, $2000)
Prim
ary
Ener
gy p
er c
api
ta (G
J)
US
Australia
Russia
BrazilChina
India
S. Korea
Mexico
Ireland
Greece
France
UKJapan
Malaysia
Energy use increases with Economic Development
Data from IEA World Energy Outlook 2006
Quality of Life is strongly correlated to energy use.
Typical goals: HDI of 0.9 at 3 toe per capita for developing countries. For all developing countries to reach this point, would need world energy
use to double with today’s population, or increase 2.6 fold with the 8.1 billion expected in 2030.
Typical goals: HDI of 0.9 at 3 toe per capita for developing countries. For all developing countries to reach this point, would need world energy
use to double with today’s population, or increase 2.6 fold with the 8.1 billion expected in 2030.
HDI: (index reflecting life expectancy at birth + adult literacy & school enrolment + GNP (PPP) per capita)
World Primary Energy Demand is expect to grow substantially
Wor
ld E
nerg
y D
eman
d (M
toe)
Data from IAE World Energy Outlook 2006 Reference (Red) and Alternative (Blue) scenarios.
World population is projected to grow from 6.4B (2004) to 8.1B (2030). Scenarios are very sensitive to assumption about China.
Data from IAE World Energy Outlook 2006 Reference (Red) and Alternative (Blue) scenarios.
World population is projected to grow from 6.4B (2004) to 8.1B (2030). Scenarios are very sensitive to assumption about China.
Energy supply will be dominated by fossil fuels for the foreseeable future
0
2,000
4,000
6,000
8,000
10,000
12,000
14,000
16,000
18,000
1980 2004 2010 2015 2030
MtoeOtherRenewables
Biomass &waste
Hydro
Nuclear
Gas
Oil
Coal
’04 – ’30 Annual Growth
Rate (%)
Total
6.5
1.3
2.0
0.7
2.0
1.3
1.8
1.6
Source: IEA World Energy Outlook 2006 (Reference Case), Business as Usual (BAU) case
Technologies to meet the energy challenge do not exist
Improved efficiency and lower demand Huge scope but demand has always risen faster due to long turn-over
time.
Renewables Intermittency, cost, environmental impact.
Carbon sequestration Requires handling large amounts of C (Emissions to 2050
=2000Gtonne CO2)
Fission Fuel cycle and waste disposal
Fusion Probably a large contributor in the 2nd half of the century
Improved efficiency and lower demand Huge scope but demand has always risen faster due to long turn-over
time.
Renewables Intermittency, cost, environmental impact.
Carbon sequestration Requires handling large amounts of C (Emissions to 2050
=2000Gtonne CO2)
Fission Fuel cycle and waste disposal
Fusion Probably a large contributor in the 2nd half of the century
Energy Challenge: A Summary
Large increases in energy use is expected.
IEA world Energy Outlook indicate that it will require increased use of fossil fuels Air pollution & Global Warming Will run out sooner or later
Limiting CO2 to 550ppm by 2050 is an ambitious goal. USDOE: “The technology to generate this amount of emission-free
power does not exist.” IEA report: “Achieving a truly sustainable energy system will call for
radical breakthroughs that alter how we produce and use energy.”
Public funding of energy research is down 50% since 1980 (in real term). World energy R&D expenditure is 0.25% of energy market of $4.5 trillion.
Large increases in energy use is expected.
IEA world Energy Outlook indicate that it will require increased use of fossil fuels Air pollution & Global Warming Will run out sooner or later
Limiting CO2 to 550ppm by 2050 is an ambitious goal. USDOE: “The technology to generate this amount of emission-free
power does not exist.” IEA report: “Achieving a truly sustainable energy system will call for
radical breakthroughs that alter how we produce and use energy.”
Public funding of energy research is down 50% since 1980 (in real term). World energy R&D expenditure is 0.25% of energy market of $4.5 trillion.
Most of public energy expenditures is in the form of subsidies
Coal44.5%
Oil and gas30%
Fusion 1.5%
Fission 6%
Renewables18%
Energy Subsides (€28B) and R&D (€2B) in the EU
Source : EEA, Energy subsidies in the European Union: A brief overview, 2004. Fusion and fission are displayed separately using the IEA government-R&D data base and EURATOM 6th framework programme dataSlide from C. Llewellyn Smith, UKAEA
Fission (seeking a significant fraction of World Energy Consumption of 14TW)
Nuclear power is already a large contributor to world energy supply
Nuclear power provide 8% of world total energy demand (20% of US electricity)
Operating reactors in 31 countries 438 nuclear plants generating 353 GWe Half of reactors in US, Japan, and France 104 reactor is US, 69 in France
30 New plants in 12 countries under construction
Nuclear power provide 8% of world total energy demand (20% of US electricity)
Operating reactors in 31 countries 438 nuclear plants generating 353 GWe Half of reactors in US, Japan, and France 104 reactor is US, 69 in France
30 New plants in 12 countries under construction
1990 1994 2000 2001 20020
200
400
600
800
1000
US
Nuc
lear
Ele
ctric
ity (
GW
h) No new plant in US for more than two decades
Increased production due to higher availability 30% of US electricity growth Equivalent to 25 1GW plantsExtended license for many plants
No new plant in US for more than two decades
Increased production due to higher availability 30% of US electricity growth Equivalent to 25 1GW plantsExtended license for many plants
Evolution of Fission Reactors
Challenges to Long-term viability of fission
Economics: Reduced costs Reduced financial risk (especially licensing/construction time)
Safety Protection from core damage (reduce likelihood) Eliminate offsite radioactive release potential
Sustainability Efficient fuel utilization Waste minimization and management Non-proliferation
Economics: Reduced costs Reduced financial risk (especially licensing/construction time)
Safety Protection from core damage (reduce likelihood) Eliminate offsite radioactive release potential
Sustainability Efficient fuel utilization Waste minimization and management Non-proliferation
Reprocessing and Transmutation Gen IV Reactors Reprocessing and Transmutation Gen IV Reactors
Fusion: Looking into the future
ARIES-AT tokamak Power plant
Brining a Star to Earth
DT fusion has the largest cross section and lowest temperature (~100M oC). But, it is still a high-temperature plasma!
Plasma should be surrounded by a Li-containing blanket to generate T. Or, DT fusion turns its waste (neutrons) into fuel!
Through careful design, only a small fraction of neutrons are absorbed in structure and induce radioactivity.
For liquid coolant/breeders (e.g., Li, LiPb), most of fusion energy is directly deposited in the coolant simplifying energy recovery
Practically no resource limit (1011 TWy D; 104 (108) TWy 6Li)
DT fusion has the largest cross section and lowest temperature (~100M oC). But, it is still a high-temperature plasma!
Plasma should be surrounded by a Li-containing blanket to generate T. Or, DT fusion turns its waste (neutrons) into fuel!
Through careful design, only a small fraction of neutrons are absorbed in structure and induce radioactivity.
For liquid coolant/breeders (e.g., Li, LiPb), most of fusion energy is directly deposited in the coolant simplifying energy recovery
Practically no resource limit (1011 TWy D; 104 (108) TWy 6Li)
D + 6Li 2 4He + 3.5 MeV (Plasma) + 17 MeV (Blanket)
D + T 4He (3.5 MeV) + n (14 MeV)
n + 6Li 4He (2 MeV) + T (2.7 MeV)nT
Fusion Energy Requirements:
Confining the plasma so that alpha particles sustain fusion burn Lawson Criteria: ntE ~ 1021 s/m3
Heating the plasma for fusion reactions to occur to 100 Million oC (routinely done in present experiments)
Optimizing plasma confinement device to minimize the cost Smaller devices Cheaper systems, e.g., lower-field magnets (MFE) or lower-
power lasers (IFE)
Extracting the fusion power and breeding tritium Co-existence of a hot plasma with material interface Developing power extraction technology that can operate in
fusion environment
Confining the plasma so that alpha particles sustain fusion burn Lawson Criteria: ntE ~ 1021 s/m3
Heating the plasma for fusion reactions to occur to 100 Million oC (routinely done in present experiments)
Optimizing plasma confinement device to minimize the cost Smaller devices Cheaper systems, e.g., lower-field magnets (MFE) or lower-
power lasers (IFE)
Extracting the fusion power and breeding tritium Co-existence of a hot plasma with material interface Developing power extraction technology that can operate in
fusion environment
Two Approaches to Fusion Power – 1) Inertial Fusion
Inertial Fusion Energy (IFE) Fast implosion of high-density DT capsules by laser or particle beams
(~30 fold radial convergence, heating to fusion temperature). A DT burn front is generated, fusing ~1/3 of fuel (to be demonstrated in
National Ignition Facility in Lawrence Livermore National Lab). Several ~300 MJ explosions per second with large gain (fusion
power/input power).
Inertial Fusion Energy (IFE) Fast implosion of high-density DT capsules by laser or particle beams
(~30 fold radial convergence, heating to fusion temperature). A DT burn front is generated, fusing ~1/3 of fuel (to be demonstrated in
National Ignition Facility in Lawrence Livermore National Lab). Several ~300 MJ explosions per second with large gain (fusion
power/input power).
Two Approaches to Fusion Power –2) Magnetic Fusion
Rest of the Talk is focused on MFE Rest of the Talk is focused on MFE
Magnetic Fusion Energy (MFE) Particles confined within a “toroidal magnetic bottle” for 10’s km
and 100’s of collisions per fusion event. Strong magnetic pressure (100’s atm) to confine a low density but
high pressure (10’s atm) plasma. At sufficient plasma pressure and “confinement time”, the 4He
power deposited in the plasma sustains fusion condition.
Magnetic Fusion Energy (MFE) Particles confined within a “toroidal magnetic bottle” for 10’s km
and 100’s of collisions per fusion event. Strong magnetic pressure (100’s atm) to confine a low density but
high pressure (10’s atm) plasma. At sufficient plasma pressure and “confinement time”, the 4He
power deposited in the plasma sustains fusion condition.
Plasma behavior is dominated by “collective” effects
Pressure balance (equilibrium) does not guaranty stability. Example: Interchange stability
Pressure balance (equilibrium) does not guaranty stability. Example: Interchange stability
Impossible to design a “toroidal magnetic bottle” with good curvatures everywhere.
Fortunately, because of high speed of particles, an “averaged” good curvature is sufficient.
Impossible to design a “toroidal magnetic bottle” with good curvatures everywhere.
Fortunately, because of high speed of particles, an “averaged” good curvature is sufficient.
Outside part of torus inside part of torusFluid Interchange Instability
Tokamak is the most successful concept for plasma confinement
R=1.7 m
DIII-D, General AtomicsLargest US tokamak
Many other configurations possible depending on the value and profile of “q” and how it is generated (internally or externally)
Many other configurations possible depending on the value and profile of “q” and how it is generated (internally or externally)
T3 Tokamak achieved the first high temperature (10 M oC) plasma
R=1 m
0.06 MAPlasma Current
JET is currently the largest tokamak in the world
R=3 m
ITER Burning plasma experiment (under construction)
R=6 m
Progress in plasma confinement has been impressive
500 MW of fusion Power for 300s
Construction has started in France
500 MW of fusion Power for 300s
Construction has started in France
Fu
sio
n t
rip
le p
rod
uct
n (
102
1 m
-3) t(
s) T
(ke
V)
ITER Burning plasma experiment
Large amount of fusion power has also been produced
ITER Burning plasma experiment
DT Experiments
DD Experiments
Fusion Energy Requirements:
Confining the plasma so that alpha particles sustain fusion burn Lawson Criteria: ntE ~ 1021 s/m3
Heating the plasma for fusion reactions to occur to 100 Million oC (routinely done in present experiments)
Optimizing plasma confinement device to minimize the cost Smaller devices Cheaper systems, e.g., lower-field magnets (MFE) or lower-
power lasers (IFE)
Extracting the fusion power and breeding tritium Developing power extraction technology that can operate in fusion
environment Co-existence of a hot plasma with material interface
Confining the plasma so that alpha particles sustain fusion burn Lawson Criteria: ntE ~ 1021 s/m3
Heating the plasma for fusion reactions to occur to 100 Million oC (routinely done in present experiments)
Optimizing plasma confinement device to minimize the cost Smaller devices Cheaper systems, e.g., lower-field magnets (MFE) or lower-
power lasers (IFE)
Extracting the fusion power and breeding tritium Developing power extraction technology that can operate in fusion
environment Co-existence of a hot plasma with material interface
ITER and Satellite tokamaks (e.g., JT60-SU in Japan) should demonstrate operation of a fusion plasma (and its support technologies) at the power plant scale.
ITER Device History
1988-1990 EU, Japan, USSR, and US conducted the Conceptual Design Activity
1992 Engineering Design Activity (EDA) Started
1998 Initial EDA ended. US urged rescoring to reduce cost
1998 US withdraws from ITER at Congressional Direction. EU, Japan, RF pursue a lower cost design
2001 EDA ends
2003 US, Korea, and China join ITER
2006 Agreement on ITER Site
2009 Construction of long-lead time components started
2017? First Plasma
2026? Full power DT experiments
1988-1990 EU, Japan, USSR, and US conducted the Conceptual Design Activity
1992 Engineering Design Activity (EDA) Started
1998 Initial EDA ended. US urged rescoring to reduce cost
1998 US withdraws from ITER at Congressional Direction. EU, Japan, RF pursue a lower cost design
2001 EDA ends
2003 US, Korea, and China join ITER
2006 Agreement on ITER Site
2009 Construction of long-lead time components started
2017? First Plasma
2026? Full power DT experiments
We have made tremendous progress in optimizing fusion plasmas
Substantial improvement in plasma performance though optimization of plasma shape, profiles, and feedback.
Achieving plasma stability at high plasma pressure.
Achieving improved plasma confinement through suppression of plasma turbulence, the “transport barrier.”
Progress toward steady-state operation through minimization of power needed to maintain plasma current through profile control.
Controlling the boundary layer between plasma and vessel wall to avoid localized particle and heat loads.
Substantial improvement in plasma performance though optimization of plasma shape, profiles, and feedback.
Achieving plasma stability at high plasma pressure.
Achieving improved plasma confinement through suppression of plasma turbulence, the “transport barrier.”
Progress toward steady-state operation through minimization of power needed to maintain plasma current through profile control.
Controlling the boundary layer between plasma and vessel wall to avoid localized particle and heat loads.
ITER and satellite tokamaks will provide the necessary data for a fusion power plant
DIII-D DIII-D ITERSimultaneous Max Baseline ARIES-AT
Major toroidal radius (m) 1.7 1.7 6.2 5.2Plasma Current (MA) 2.25 3.0 15 13Magnetic field (T) 2 2 5.3 6.0Electron temperature (keV) 7.5* 16* 8.9** 18**Ion Temperature (keV) 18* 27* 8.1** 18**Density (1020 m-3) 1.0* 1.7* 1.0** 2.2**Confinement time (s) 0.4 0.5 3.7 1.7Normalized confinement, H89 4.5 4.5 2 2.7b (plasma/magnetic pressure) 6.7% 13% 2.5% 9.2%Normalized b 3.9 6.0 1.8 5.4Fusion Power (MW) 500 1,755Pulse length 300 S.S.
DIII-D DIII-D ITERSimultaneous Max Baseline ARIES-AT
Major toroidal radius (m) 1.7 1.7 6.2 5.2Plasma Current (MA) 2.25 3.0 15 13Magnetic field (T) 2 2 5.3 6.0Electron temperature (keV) 7.5* 16* 8.9** 18**Ion Temperature (keV) 18* 27* 8.1** 18**Density (1020 m-3) 1.0* 1.7* 1.0** 2.2**Confinement time (s) 0.4 0.5 3.7 1.7Normalized confinement, H89 4.5 4.5 2 2.7b (plasma/magnetic pressure) 6.7% 13% 2.5% 9.2%Normalized b 3.9 6.0 1.8 5.4Fusion Power (MW) 500 1,755Pulse length 300 S.S.
* Peak value, **Average Value
Fusion Energy Requirements:
Confining the plasma so that alpha particles sustain fusion burn Lawson Criteria: ntE ~ 1021 s/m3
Heating the plasma for fusion reactions to occur to 100 Million oC (routinely done in present experiments)
Optimizing plasma confinement device to minimize the cost Smaller devices Cheaper systems, e.g., lower-field magnets (MFE) or lower-power
lasers (IFE)
Extracting the fusion power and breeding tritium Developing power extraction technology that can operate in
fusion environment Co-existence of a hot plasma with material interface
Confining the plasma so that alpha particles sustain fusion burn Lawson Criteria: ntE ~ 1021 s/m3
Heating the plasma for fusion reactions to occur to 100 Million oC (routinely done in present experiments)
Optimizing plasma confinement device to minimize the cost Smaller devices Cheaper systems, e.g., lower-field magnets (MFE) or lower-power
lasers (IFE)
Extracting the fusion power and breeding tritium Developing power extraction technology that can operate in
fusion environment Co-existence of a hot plasma with material interface
First wall and blanket System is subject to a harsh environment
Environment:
Surface heat flux (due to X-ray and ions)
First wall erosion by ions.
Radiation damage by neutrons (e.g. structural material)
Volumetric heating by neutrons in the blanket.
MHD effects
Functions:
Tritium breeding management
Maximize power recovery and coolant outlet temperature for maximum thermal efficiency
Constraints:
Simple manufacturing technique
Safety (low afterheat and activity)
Environment:
Surface heat flux (due to X-ray and ions)
First wall erosion by ions.
Radiation damage by neutrons (e.g. structural material)
Volumetric heating by neutrons in the blanket.
MHD effects
Functions:
Tritium breeding management
Maximize power recovery and coolant outlet temperature for maximum thermal efficiency
Constraints:
Simple manufacturing technique
Safety (low afterheat and activity)
Outboard blanket & first wall
x rayNeutronsions
New structural material should be developed for fusion application
Fe-9Cr steels: builds upon 9Cr-1Mo industrial experience and materials database (9-12 Cr ODS steels are a higher temperature future option) SiC/SiC: High risk, high performance option (early in its development path) W alloys: High performance option for PFCs (early in its development path)
Fe-9Cr steels: builds upon 9Cr-1Mo industrial experience and materials database (9-12 Cr ODS steels are a higher temperature future option) SiC/SiC: High risk, high performance option (early in its development path) W alloys: High performance option for PFCs (early in its development path)
Irradiation leads to a operating temperature window for material
Additional considerations such as He embrittlement and chemical compatibility may impose further restrictions on operating window
Additional considerations such as He embrittlement and chemical compatibility may impose further restrictions on operating window
Radiation embrittlement
Thermal creep
Zinkle and Ghoniem, Fusion Engr. Des. 49-50 (2000) 709
Carnot=1-Treject/Thigh
Structural Material Operating Temperature Windows: 10-50 dpa
Several blanket Concepts have been developed
Simple, low pressure design with SiC structure and LiPb coolant and breeder.
Innovative design leads to high LiPb outlet temperature (~1,100oC) while keeping SiC structure temperature below 1,000oC leading to a high thermal efficiency of ~ 60%.
Simple, low pressure design with SiC structure and LiPb coolant and breeder.
Innovative design leads to high LiPb outlet temperature (~1,100oC) while keeping SiC structure temperature below 1,000oC leading to a high thermal efficiency of ~ 60%.
Dual coolant with a self-cooled PbLi zone, He-cooled RAFS structure and SiC insert
Dual coolant with a self-cooled PbLi zone, He-cooled RAFS structure and SiC insert
Flow configuration allows for a coolant outlet temperature to be higher than maximum structure temperature
Flow configuration allows for a coolant outlet temperature to be higher than maximum structure temperature
Design leads to a LiPb Outlet Temperature of 1,100oC While Keeping SiC Temperature Below 1,000oC
• Two-pass PbLi flow, first pass to cool SiCf/SiC box second pass to superheat PbLi
q''plasma
Pb-17Li
q'''LiPb
Out
q''back
vback
vFW
Poloidal
Radial
Inner Channel
First Wall Channel
SiC/SiCFirst Wall SiC/SiC Inner Wall
700
800
900
1000
1100
1200800
900
1000
1100
1200
1
2
3
4
5
6
00.020.040.060.080.1
00.020.040.060.080.1
Radial distance (m)
Poloidaldistance(m)
SiC/SiC
Pb-17Li
Bottom
Top
PbLi Outlet Temp. = 1100 °C
Max. SiC/PbLi Interf. Temp. = 994 °C
Max. SiC/SiC Temp. = 996°C
PbLi Inlet Temp. = 764 °C
Managing the plasma material interface is challenging
Alpha power and alpha ash has to eventually leave the plasma
Particle and energy flux on the material surrounding the plasma
Modern tokomaks use divertors: Closed flux surfaces containing hot core
plasma Open flux surfaces containing cold
plasma diverted away from the first wall. Particle flux on the first wall is reduced,
heat flux on the first wall is mainly due to radiation (bremsstrahlung, synchrotron, etc.)
Alpha ash is pumped out in the divertor region
High heat and particle fluxes on the divertor plates.
Alpha power and alpha ash has to eventually leave the plasma
Particle and energy flux on the material surrounding the plasma
Modern tokomaks use divertors: Closed flux surfaces containing hot core
plasma Open flux surfaces containing cold
plasma diverted away from the first wall. Particle flux on the first wall is reduced,
heat flux on the first wall is mainly due to radiation (bremsstrahlung, synchrotron, etc.)
Alpha ash is pumped out in the divertor region
High heat and particle fluxes on the divertor plates.
First Wall
Confined plasma
Separatrix
Edge Plasma
Divertor plates
Flux surface
Several Gad-cooled W divertor Concepts has been produced.
EU finger: 2.6 cm diameter Impinging multi-jet cooling Allowable heat flux >10 MW/m2
~535,000 units for a power plant
Plate: 20 cm x 100 cm Impinging slot-jet cooling Allowable heat flux ~10 MW/m2
~750 units for a power plant
Re (/104)
Nu
p / N
u
Mass flow rate [g/s]
Pp
* / P *
Nominal operating condition
Thermal hydraulic experiments confirm very high heat transfer for slot jet cooling
H > 50 kW/(m2K) is possible
Thermal hydraulic experiments confirm very high heat transfer for slot jet cooling
H > 50 kW/(m2K) is possible
The ARIES-AT utilizes an efficient superconducting magnet design
On-axis toroidal field: 6 T Peak field at TF coil: 11.4 T
TF Structure: Caps and straps support loads without inter-coil structure;
On-axis toroidal field: 6 T Peak field at TF coil: 11.4 T
TF Structure: Caps and straps support loads without inter-coil structure;
Superconducting Material Either LTC superconductor (Nb3Sn and
NbTi) or HTC Structural Plates with grooves for winding
only the conductor.
Superconducting Material Either LTC superconductor (Nb3Sn and
NbTi) or HTC Structural Plates with grooves for winding
only the conductor.
10-7
10-6
10-5
10-4
10-3
10-2
10-1
100
101
104 105 106 107 108 109 1010 1011
ARIES-STARIES-RS
Act
ivit
y (C
i/W th
)
Time Following Shutdown (s)
1 mo 1 y 100 y1 d
After 100 years, only 10,000 Curies of radioactivity remain in the585 tonne ARIES-RS fusion core.
After 100 years, only 10,000 Curies of radioactivity remain in the585 tonne ARIES-RS fusion core.
SiC composites lead to a very low activation and afterheat.
All components of ARIES-AT qualify for Class-C disposal under NRC and Fetter Limits. 90% of components qualify for Class-A waste.
SiC composites lead to a very low activation and afterheat.
All components of ARIES-AT qualify for Class-C disposal under NRC and Fetter Limits. 90% of components qualify for Class-A waste.
Ferritic SteelVanadium
Radioactivity levels in fusion power plantsare very low and decay rapidly after shutdown
Level in Coal AshLevel in Coal Ash
Waste volume is not large
0
50
100
150
200
250
300
350
400
Blanket Shield VacuumVessel
Magnets Structure Cryostat
Cu
mu
lati
ve
Co
mp
ac
ted
Wa
ste
Vo
lum
e (
m3
)
1270 m3 of Waste is generated after 40 full-power year (FPY) of operation. Coolant is reused in other power plants 29 m3 every 4 years (component replacement), 993 m3 at end of service
Equivalent to ~ 30 m3 of waste per FPY Effective annual waste can be reduced by increasing plant service life.
1270 m3 of Waste is generated after 40 full-power year (FPY) of operation. Coolant is reused in other power plants 29 m3 every 4 years (component replacement), 993 m3 at end of service
Equivalent to ~ 30 m3 of waste per FPY Effective annual waste can be reduced by increasing plant service life.
0
200
400
600
800
1000
1200
1400
Class A Class C
Cumu
lative
Comp
acted
Was
te Vo
lume (
m3)
90% of waste qualifies for Class A disposal
90% of waste qualifies for Class A disposal
Advances in fusion science & technology has dramatically improved our vision of fusion power plants
Estimated Cost of Electricity (c/kWh)
0
2
4
6
8
10
12
14
Mid 80'sPhysics
Early 90'sPhysics
Late 90's Physics
AdvancedTechnology
Major radius (m)
0
1
2
3
4
5
6
7
8
9
10
Mid 80's Pulsar
Early 90'sARIES-I
Late 90'sARIES-RS
2000 ARIES-AT
In Summary, …
In a CO2 constrained world uncertainty abounds
No carbon-neutral commercial energy technology is available today. Carbon sequestration is the determining factor for fossil fuel electric
generation. A large investment in energy R&D is needed. A shift to a hydrogen economy or carbon-neutral syn-fuels is also
needed to allow continued use of liquid fuels for transportation. Problem cannot be solved by legislation or subsidy. We need technical
solutions. Technical Communities should be involved or considerable public resources
would be wasted The size of energy market ($1T annual sale, TW of power) is huge.
Solutions should fit this size market 100 Nuclear plants = 20% of electricity production $50B annual R&D represents 5% of energy sale
No carbon-neutral commercial energy technology is available today. Carbon sequestration is the determining factor for fossil fuel electric
generation. A large investment in energy R&D is needed. A shift to a hydrogen economy or carbon-neutral syn-fuels is also
needed to allow continued use of liquid fuels for transportation. Problem cannot be solved by legislation or subsidy. We need technical
solutions. Technical Communities should be involved or considerable public resources
would be wasted The size of energy market ($1T annual sale, TW of power) is huge.
Solutions should fit this size market 100 Nuclear plants = 20% of electricity production $50B annual R&D represents 5% of energy sale
Status of fusion power
Over 15 MW of fusion power is generated (JET, 1997) establishing “scientific feasibility” of fusion power Although fusion power < input power.
ITER will demonstrate “technical feasibility” of fusion power by generating copious amount of fusion power (500MW for 300s) with fusion power > 10 input power.
Tremendous progress in understanding plasmas has helped optimize plasma performance considerably. Vision of attractive fusion power plants exists.
Transformation of fusion into a power plant requires considerable R&D in material and fusion nuclear technologies (largely ignored or under-funded to date). This step, however, can be done in parallel with ITER
Large synergy between fusion nuclear technology R&D and Gen-IV.
Over 15 MW of fusion power is generated (JET, 1997) establishing “scientific feasibility” of fusion power Although fusion power < input power.
ITER will demonstrate “technical feasibility” of fusion power by generating copious amount of fusion power (500MW for 300s) with fusion power > 10 input power.
Tremendous progress in understanding plasmas has helped optimize plasma performance considerably. Vision of attractive fusion power plants exists.
Transformation of fusion into a power plant requires considerable R&D in material and fusion nuclear technologies (largely ignored or under-funded to date). This step, however, can be done in parallel with ITER
Large synergy between fusion nuclear technology R&D and Gen-IV.
Thank You