June 14-15, 2005/ARR1

Status of ARIES-CS Power Core Engineering

A. René Raffray University of California, San Diego

ARIES Meeting

UW

June 14-15, 2005

June 14-15, 2005/ARR2

Major Focus of Engineering Effort During Phase II(from last meeting)

1. Divertor design and analysis

2. Detailed design and analysis of dual coolant concept with a self-cooled Pb-17Li zone and He-cooled RAFS structure: • Modular concept first (port-based maintenance) • Field-period based maintenance concept next

3. Coil cross-section (including insulation + structural support)• Do we need to do structural analysis?

4. Integration with credible details about design of different components, maintenance and ancillary equipment for both maintenance schemes.

1. Divertor design and analysis

2. Detailed design and analysis of dual coolant concept with a self-cooled Pb-17Li zone and He-cooled RAFS structure: • Modular concept first (port-based maintenance) • Field-period based maintenance concept next

3. Coil cross-section (including insulation + structural support)• Do we need to do structural analysis?

4. Integration with credible details about design of different components, maintenance and ancillary equipment for both maintenance schemes.

June 14-15, 2005/ARR3

Action Items for Phase II (from previous meetings)

1. Run LOCA/LOFA case with low contact resistance between blanket and hot shield (UW)

2. Check effect of local radial conductance in blanket and between shield and vacuum vessel (UW)

3. Do we need to consider any other accident scenario? (INEL/UW) LOVA4. Structural analysis of coil support to have a better definition of required

thickness for cases with separate coil structure for each field period (MIT)5. Details of module attachment and replacement (choice between “single”

module maintenance or “series” module maintenance) (FNTC/UCSD)6. Port maintenance including all pipes and lines (realistic 3-D layout including

accommodation of all penetrations) (UCSD) Details of module design and thermal-hydraulic analysis for dual coolant design coupled to Brayton power cycle(FNTC/UCSD)

7. Coolant lines coupling to the heat exchanger (choice of HX material, e.g. W-coated FS vs. refractory alloy such as niobium alloy) (FNTC/UCSD/INEL)

8. Tritium extraction system for Pb-17Li + tritium inventories (FNTC/UCSD/INEL)

9. How high can we push the Pb-17Li/FS interface temperature based on corrosion limits? (FNTC/UCSD)

10. External vacuum vessel design (thickness and configuration) (FNTC/UCSD)11. Divertor design and analysis (T. Ihli/UCSD)

1. Run LOCA/LOFA case with low contact resistance between blanket and hot shield (UW)

2. Check effect of local radial conductance in blanket and between shield and vacuum vessel (UW)

3. Do we need to consider any other accident scenario? (INEL/UW) LOVA4. Structural analysis of coil support to have a better definition of required

thickness for cases with separate coil structure for each field period (MIT)5. Details of module attachment and replacement (choice between “single”

module maintenance or “series” module maintenance) (FNTC/UCSD)6. Port maintenance including all pipes and lines (realistic 3-D layout including

accommodation of all penetrations) (UCSD) Details of module design and thermal-hydraulic analysis for dual coolant design coupled to Brayton power cycle(FNTC/UCSD)

7. Coolant lines coupling to the heat exchanger (choice of HX material, e.g. W-coated FS vs. refractory alloy such as niobium alloy) (FNTC/UCSD/INEL)

8. Tritium extraction system for Pb-17Li + tritium inventories (FNTC/UCSD/INEL)

9. How high can we push the Pb-17Li/FS interface temperature based on corrosion limits? (FNTC/UCSD)

10. External vacuum vessel design (thickness and configuration) (FNTC/UCSD)11. Divertor design and analysis (T. Ihli/UCSD)

June 14-15, 2005/ARR4

~15 mm

W alloy outer tube

W alloy inner cartridge

He coolant inlet and outlet

Graded transition between W and ODS FS

W armor

~100-150 mm

Divertor Study• Major focus of ARIES Phase-II effort (Good Progress)

- Physics modeling to better assess divertor location and heat loads- Engineering effort to evolve a suitable design to accommodate a max. q’’ of at least 10 MW/m2.- Productive collaboration with FZK

• Build on the W cap design and explore possibility of a new mid-size configuration with good q’’ accommodation potential, reasonably simple (and credible) manufacturing and assembly procedures, and which could be well integrated in the CS reactor design. - "T-tube" configuration (~10 cm) - Cooling with discrete or continuous jets- Consistent CFD analysis results from Georgia Tech. and FZK

• Design introduced at ISFNT-7, to be described in more detail at SOFE and in journal publication.

• Major focus of ARIES Phase-II effort (Good Progress)- Physics modeling to better assess divertor location and heat loads- Engineering effort to evolve a suitable design to accommodate a max. q’’ of at least 10 MW/m2.- Productive collaboration with FZK

• Build on the W cap design and explore possibility of a new mid-size configuration with good q’’ accommodation potential, reasonably simple (and credible) manufacturing and assembly procedures, and which could be well integrated in the CS reactor design. - "T-tube" configuration (~10 cm) - Cooling with discrete or continuous jets- Consistent CFD analysis results from Georgia Tech. and FZK

• Design introduced at ISFNT-7, to be described in more detail at SOFE and in journal publication.

June 14-15, 2005/ARR5

Coil Structural Analysis

• Need structural analysis of coil support to have a better definition of required thickness for cases with separate coil structure for each field period (MIT)

• Steady-state case (no disruption). Need force definition based on coil current and stress analysis

• Lack of progress - UCSD action item

• Need structural analysis of coil support to have a better definition of required thickness for cases with separate coil structure for each field period (MIT)

• Steady-state case (no disruption). Need force definition based on coil current and stress analysis

• Lack of progress - UCSD action item

June 14-15, 2005/ARR6

Ancillary Equipment

• Tritium extraction and recovery method

• Heat exchanger design and material choice - Connection to blanket structural material - Compatibility with Pb-17Li at a temperature of up to ~700-800°C- Ni?

• Can benefit from effort on ITER test module, which can be updated and applied to our blanket configuration (B. Merrill)

• Tritium extraction and recovery method

• Heat exchanger design and material choice - Connection to blanket structural material - Compatibility with Pb-17Li at a temperature of up to ~700-800°C- Ni?

• Can benefit from effort on ITER test module, which can be updated and applied to our blanket configuration (B. Merrill)

June 14-15, 2005/ARR7

Dual Coolant Module Design

• Updated design and cooling configuration for dual-coolant blanket modular concept.

• Thermal-hydraulic analysis of blanket coupled to Brayton cycle (further optimization).

• Maintenance of DC concept requires pipe cutting behind module.- In-bore or outside access for pipe cutting and rewelding- Visit of K. Ioki and F. Elio in March (ITER JCT) for discussion

- Pipe cutting and welding from outside commercially available- Some concern about space tightness in bottom of chamber for

manoeuvring articulated boom.

• Latest progress summarized at ISFNT-7.

• Updated design and cooling configuration for dual-coolant blanket modular concept.

• Thermal-hydraulic analysis of blanket coupled to Brayton cycle (further optimization).

• Maintenance of DC concept requires pipe cutting behind module.- In-bore or outside access for pipe cutting and rewelding- Visit of K. Ioki and F. Elio in March (ITER JCT) for discussion

- Pipe cutting and welding from outside commercially available- Some concern about space tightness in bottom of chamber for

manoeuvring articulated boom.

• Latest progress summarized at ISFNT-7.

June 14-15, 2005/ARR8

Dual Coolant Blanket Module Redesigned for Simpler More Effective Coolant Routing

• SiC insulator lining Pb-17 Li channel for thermal and electrical insulation to maximize TPb-17 Li and

minimize MHD P while accommodating compatibility limit TFS/Pb-17Li <500°C

• SiC insulator lining Pb-17 Li channel for thermal and electrical insulation to maximize TPb-17 Li and

minimize MHD P while accommodating compatibility limit TFS/Pb-17Li <500°C

Bulk Pb-17Li

He-Cooled Ferritic Steel Wall

SiC Insulator

Slow-Moving Thin Pb-17Li Layer

• 8 MPa He to cool FW toroidally and box

• Slow flowing (<10 cm/s) Pb-17Li in inner channels

• RAFS used (Tmax<550°C)

June 14-15, 2005/ARR9

Initial Parametric Study of Pb-17Li/He DC Blanket Coupled to a Brayton Cycle through as HX

• Brayton Cycle with a single expansion stage and 3-stage compression assumed

• For an insulator conductance of 200 W/m2-K, cycle~ 0.4 for n = 5 MW/m2 and cycle~ 0.43 for n = 3 MW/m2

• Can we do better (e.g. use ODS-FS in FW to increase the FS temp. limit; and assume a higher Pb-17Li/FS compatibility limit)?

• Brayton Cycle with a single expansion stage and 3-stage compression assumed

• For an insulator conductance of 200 W/m2-K, cycle~ 0.4 for n = 5 MW/m2 and cycle~ 0.43 for n = 3 MW/m2

• Can we do better (e.g. use ODS-FS in FW to increase the FS temp. limit; and assume a higher Pb-17Li/FS compatibility limit)?

550

600

650

700

750

800

850

900

950

0 100 200 300 400 500 600 700 800 900 1000

He/Pb-17Li fract. power = 0.42/0.58

Tmax,Pb-17Li/FS

<500°C

Δ THX

=30°C

He Ppump

/Pthermal

<0.03

q''plasma

=0.5 MW/m2

Sandwich Insulator Region Effective Conductance (W/m2

-K )

Neutron wall load= 3 MW/m2

Neutron wall load= 5 MW/m2

0.35

0.40

0.45

0.50

0 200 400 600 800 1000

/ -17 . = 0.42/0.58He Pb Li fract power

q''plasma

=0.5 /MW m2

T, -17 /max Pb Li FS

<500° ; C He Ppump

/P thermal

<0.03

THX

=30°C

( /Sandwich Insulator Region Effective Conductance W m2

-K )

Neutron w :all load 3 /MW m2

; 5 /MW m2

T,FS FW

< 550°C

Bulk Pb-17Li

He-Cooled Ferritic Steel Wall

SiC Insulator

Slow-Moving Thin Pb-17Li Layer

June 14-15, 2005/ARR10

Further Optimization of DC Blanket Coupled to Brayton Cycle

• Are optimized parameter values reasonable?• Some advantage at reducing wall load: higher cycle eff., higher Pb-17Li temp. (could

be utilized for H2 production if so desired)• Cycle efficiency could be tweaked to exceed value corresponding to max. wall load by

considering also lower wall load module (but difficult)• Cycle eff. dependency on wall load should be considered in system study (update values

previously provided to Jim)

• Are optimized parameter values reasonable?• Some advantage at reducing wall load: higher cycle eff., higher Pb-17Li temp. (could

be utilized for H2 production if so desired)• Cycle efficiency could be tweaked to exceed value corresponding to max. wall load by

considering also lower wall load module (but difficult)• Cycle eff. dependency on wall load should be considered in system study (update values

previously provided to Jim)

0.35

0.40

0.45

0.50

0.55

0 1 2 3 4 5 6

/ -17 . = 0.42/0.58He Pb Li fract power

. . SiC ins eff conductance = 100 /W m

2

-K

T

, -17 /max Pb Li FS

<550° ; C P

pump

/P

elec

<0.05

T

,HX min

=30°C

. = 4 ( ) 3 ( )FW He channel dim cm rad x cm pol

( /Neutron Wall Load MW m

2

)

NWL q''

plasma

( /MW m

2

) ( /MW m

2

)

1 0.13

2 0.26

3 0.4

4 0.52

5 0.67

550

600

650

700

750

800

850

900

950

0 0.5 1 1.5 2 2.5 3 3.5 4 4.5 5

Neutron Wall Load (MW/m

2

)

Pb-17Li Outlet Temp.

Max. FW

FS Temp.Avg. FW FS Temp.

at T

max

location

He/Pb-17Li fract. power = 0.42/0.58

SiC ins. eff. conductance = 100 W/m

2

-K

T

max,Pb-17Li/FS

<550°C; P

pump

/P

elec

<0.05

Δ T

HX,min

=30°C

FW He channel dim.= 4 cm (rad) x 3 cm (pol)

June 14-15, 2005/ARR11

Different H2 Production Methods Exist -High Temperature Electrolysis Used as Example Here

Adapted from S. Herring’s May 15, 2002 presentation:”High Temperature Electrolysis Using Solid Oxide Fuel Cell Technology,” INEEL

H2 (g) + 1/2 O2 (g) = H2O (g)H = -241.8 kJ/mol

€

H2=

Energy out (ΔH)

Energy in (thermal)

June 14-15, 2005/ARR12

Possible Use of Dual Coolant Blanket for H2 Production + Power Generation

Adapted from S. Herring’s May 15, 2002 presentation:”High Temperature Electrolysis Using Solid Oxide Fuel Cell Technology,” INEEL

June 14-15, 2005/ARR13

Efficiency of High Temperature Electrolysis for H2 Production Using DC Blanket

H2 (g) + 1/2 O2 (g) = H2O (g)H = -241.8 kJ/mol

€

H2=

Energy out (ΔH)

Energy in (thermal)

Interesting possibility if so desired in the future

0.40

0.45

0.50

0.55

0.60

0 1 2 3 4 5 6

/ -17 . = 0.42/0.58He Pb Li fract power

. . SiC ins eff conductance = 100 /W m

2

-K

T

, -17 /max Pb Li FS

<550° ; C P

pump

/P

elec

<0.05

T

,HX min

=30°C

. = 4 ( ) 3 ( )FW He channel dim cm rad x cm pol

( /Neutron Wall Load MW m

2

)

NWL q''

plasma

( /MW m

2

) ( /MW m

2

)

1 0.13

2 0.26

3 0.4

4 0.52

5 0.67