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

• Liquid Lithium Applications for Solving Challenging Fusion Reac
• Slide 2
• Slide 3
• Slide 4
• Slide 5
• Slide 6
• Slide 7
• Slide 8
• Slide 9
• Slide 10
• Slide 11
• Slide 12
• Slide 13
• Slide 14
• Slide 15
• Slide 16
• Slide 17
• Slide 18
• Slide 19
• Slide 20
• Slide 21

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

• Liquid Lithium Applications for Solving Challenging Fusion Reac
• Slide 2
• Slide 3
• Slide 4
• Slide 5
• Slide 6
• Slide 7
• Slide 8
• Slide 9
• Slide 10
• Slide 11
• Slide 12
• Slide 13
• Slide 14
• Slide 15
• Slide 16
• Slide 17
• Slide 18
• Slide 19
• Slide 20
• Slide 21

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

• Liquid Lithium Applications for Solving Challenging Fusion Reac
• Slide 2
• Slide 3
• Slide 4
• Slide 5
• Slide 6
• Slide 7
• Slide 8
• Slide 9
• Slide 10
• Slide 11
• Slide 12
• Slide 13
• Slide 14
• Slide 15
• Slide 16
• Slide 17
• Slide 18
• Slide 19
• Slide 20
• Slide 21

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

• Liquid Lithium Applications for Solving Challenging Fusion Reac
• Slide 2
• Slide 3
• Slide 4
• Slide 5
• Slide 6
• Slide 7
• Slide 8
• Slide 9
• Slide 10
• Slide 11
• Slide 12
• Slide 13
• Slide 14
• Slide 15
• Slide 16
• Slide 17
• Slide 18
• Slide 19
• Slide 20
• Slide 21

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

• Liquid Lithium Applications for Solving Challenging Fusion Reac
• Slide 2
• Slide 3
• Slide 4
• Slide 5
• Slide 6
• Slide 7
• Slide 8
• Slide 9
• Slide 10
• Slide 11
• Slide 12
• Slide 13
• Slide 14
• Slide 15
• Slide 16
• Slide 17
• Slide 18
• Slide 19
• Slide 20
• Slide 21

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

• Liquid Lithium Applications for Solving Challenging Fusion Reac
• Slide 2
• Slide 3
• Slide 4
• Slide 5
• Slide 6
• Slide 7
• Slide 8
• Slide 9
• Slide 10
• Slide 11
• Slide 12
• Slide 13
• Slide 14
• Slide 15
• Slide 16
• Slide 17
• Slide 18
• Slide 19
• Slide 20
• Slide 21

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

• Liquid Lithium Applications for Solving Challenging Fusion Reac
• Slide 2
• Slide 3
• Slide 4
• Slide 5
• Slide 6
• Slide 7
• Slide 8
• Slide 9
• Slide 10
• Slide 11
• Slide 12
• Slide 13
• Slide 14
• Slide 15
• Slide 16
• Slide 17
• Slide 18
• Slide 19
• Slide 20
• Slide 21

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

• Liquid Lithium Applications for Solving Challenging Fusion Reac
• Slide 2
• Slide 3
• Slide 4
• Slide 5
• Slide 6
• Slide 7
• Slide 8
• Slide 9
• Slide 10
• Slide 11
• Slide 12
• Slide 13
• Slide 14
• Slide 15
• Slide 16
• Slide 17
• Slide 18
• Slide 19
• Slide 20
• Slide 21

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

• Liquid Lithium Applications for Solving Challenging Fusion Reac
• Slide 2
• Slide 3
• Slide 4
• Slide 5
• Slide 6
• Slide 7
• Slide 8
• Slide 9
• Slide 10
• Slide 11
• Slide 12
• Slide 13
• Slide 14
• Slide 15
• Slide 16
• Slide 17
• Slide 18
• Slide 19
• Slide 20
• Slide 21

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

• Liquid Lithium Applications for Solving Challenging Fusion Reac
• Slide 2
• Slide 3
• Slide 4
• Slide 5
• Slide 6
• Slide 7
• Slide 8
• Slide 9
• Slide 10
• Slide 11
• Slide 12
• Slide 13
• Slide 14
• Slide 15
• Slide 16
• Slide 17
• Slide 18
• Slide 19
• Slide 20
• Slide 21

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

• Liquid Lithium Applications for Solving Challenging Fusion Reac
• Slide 2
• Slide 3
• Slide 4
• Slide 5
• Slide 6
• Slide 7
• Slide 8
• Slide 9
• Slide 10
• Slide 11
• Slide 12
• Slide 13
• Slide 14
• Slide 15
• Slide 16
• Slide 17
• Slide 18
• Slide 19
• Slide 20
• Slide 21

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

• Liquid Lithium Applications for Solving Challenging Fusion Reac
• Slide 2
• Slide 3
• Slide 4
• Slide 5
• Slide 6
• Slide 7
• Slide 8
• Slide 9
• Slide 10
• Slide 11
• Slide 12
• Slide 13
• Slide 14
• Slide 15
• Slide 16
• Slide 17
• Slide 18
• Slide 19
• Slide 20
• Slide 21

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

• Liquid Lithium Applications for Solving Challenging Fusion Reac
• Slide 2
• Slide 3
• Slide 4
• Slide 5
• Slide 6
• Slide 7
• Slide 8
• Slide 9
• Slide 10
• Slide 11
• Slide 12
• Slide 13
• Slide 14
• Slide 15
• Slide 16
• Slide 17
• Slide 18
• Slide 19
• Slide 20
• Slide 21

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

• Liquid Lithium Applications for Solving Challenging Fusion Reac
• Slide 2
• Slide 3
• Slide 4
• Slide 5
• Slide 6
• Slide 7
• Slide 8
• Slide 9
• Slide 10
• Slide 11
• Slide 12
• Slide 13
• Slide 14
• Slide 15
• Slide 16
• Slide 17
• Slide 18
• Slide 19
• Slide 20
• Slide 21

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

• Liquid Lithium Applications for Solving Challenging Fusion Reac
• Slide 2
• Slide 3
• Slide 4
• Slide 5
• Slide 6
• Slide 7
• Slide 8
• Slide 9
• Slide 10
• Slide 11
• Slide 12
• Slide 13
• Slide 14
• Slide 15
• Slide 16
• Slide 17
• Slide 18
• Slide 19
• Slide 20
• Slide 21

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

• Liquid Lithium Applications for Solving Challenging Fusion Reac
• Slide 2
• Slide 3
• Slide 4
• Slide 5
• Slide 6
• Slide 7
• Slide 8
• Slide 9
• Slide 10
• Slide 11
• Slide 12
• Slide 13
• Slide 14
• Slide 15
• Slide 16
• Slide 17
• Slide 18
• Slide 19
• Slide 20
• Slide 21

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

• Liquid Lithium Applications for Solving Challenging Fusion Reac
• Slide 2
• Slide 3
• Slide 4
• Slide 5
• Slide 6
• Slide 7
• Slide 8
• Slide 9
• Slide 10
• Slide 11
• Slide 12
• Slide 13
• Slide 14
• Slide 15
• Slide 16
• Slide 17
• Slide 18
• Slide 19
• Slide 20
• Slide 21

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

• Liquid Lithium Applications for Solving Challenging Fusion Reac
• Slide 2
• Slide 3
• Slide 4
• Slide 5
• Slide 6
• Slide 7
• Slide 8
• Slide 9
• Slide 10
• Slide 11
• Slide 12
• Slide 13
• Slide 14
• Slide 15
• Slide 16
• Slide 17
• Slide 18
• Slide 19
• Slide 20
• Slide 21

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

• Liquid Lithium Applications for Solving Challenging Fusion Reac
• Slide 2
• Slide 3
• Slide 4
• Slide 5
• Slide 6
• Slide 7
• Slide 8
• Slide 9
• Slide 10
• Slide 11
• Slide 12
• Slide 13
• Slide 14
• Slide 15
• Slide 16
• Slide 17
• Slide 18
• Slide 19
• Slide 20
• Slide 21

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

• Liquid Lithium Applications for Solving Challenging Fusion Reac
• Slide 2
• Slide 3
• Slide 4
• Slide 5
• Slide 6
• Slide 7
• Slide 8
• Slide 9
• Slide 10
• Slide 11
• Slide 12
• Slide 13
• Slide 14
• Slide 15
• Slide 16
• Slide 17
• Slide 18
• Slide 19
• Slide 20
• Slide 21

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

• Liquid Lithium Applications for Solving Challenging Fusion Reac
• Slide 2
• Slide 3
• Slide 4
• Slide 5
• Slide 6
• Slide 7
• Slide 8
• Slide 9
• Slide 10
• Slide 11
• Slide 12
• Slide 13
• Slide 14
• Slide 15
• Slide 16
• Slide 17
• Slide 18
• Slide 19
• Slide 20
• Slide 21