Choice of Coolants for DEMO-FNS Fusion-Fission Hybrid Facility · • Fusion-fission hybrid...

B.V. Kuteev et al., Zvenigorod-2011, Russia, 14-18 February, 2011

Choice of Coolants for DEMO-FNS

Fusion-Fission Hybrid Facility

Kurchatov Nuclear Technologies Complex

Tokamak Research Unit

1)B.V. Kuteev, 1)V.I. Khripunov, 2)I.V. Danilov,2)A.V. Razmerov,1)Yu.S. Shpanskiy

1)NRC Kurchatov Institute, 1 Academician Kurchatov Sq., Moscow, 123182, Russia

2)JSC “NIKIET”, 2/8 Malaya Krasnoselskaya Str., 107140 Moscow Russia

E-mail : [email protected]

NATIONAL RESEARCH CENTRE

KURCHATOV INSTITUTE

НАЦИОНАЛЬНЫЙ ИССЛЕДОВАТЕЛЬСКИЙ

ЦЕНТР «КУРЧАТОВСКИЙ ИНСТИТУТ»

B.V. Kuteev, 3-5 July, 2017, Coolants-1-st TM, IAEA, Vienna, Austria


• Russian Strategy for Magnetic Fusion is developing by NRC

Kurchatov Institute and national research institutions under

auspices of the State Corporation “Rosatom” (2007 - 2060)

• The Strategy developing is aimed at provision of Fusion as a

new Energy source with unlimited resources, attractive ecology

and safety by 2060, Hybrid Systems as transmuter and breeder

by 2050, Early fusion-fission applications ASAP

• Fusion-Fission hybrid systems with Fusion Neutron Sources are

included in the National Fusion Program up to 2035 as

perspective devices for fission fuel production, nuclide

processing and basic research

Introduction

2 B.V. Kuteev, 3-5 July, 2017, Coolants-1-st TM, IAEA, Vienna, Austria


• n20 – plasma density in 1020 m-3

• TkeV – plasma temperature in keV

• tE – energy confinement time in s

• kg – Kurchatov neutron yield in g/day

• tSS – steady state operation time in y

• C – capacity factor

Fusion for World’s Future

Breakeven/Ignition

Q = PFusion/PAH

proportional to the Tripple product

Controlled Fusion

Kg = n20 TkeV tE kg tSS C

Transition from Modern Tokamaks to PROTO -> 12 orders of Kurchatov factor Kg

Facility n20 TkeV tE kg tSS C Q Kg

JET 1 10 0.3 0.35 3.5x10-7 0.1 1 3x10-8

NIF 1012 0.2 2x10-11 10-8 10-6 0.1 0.015 4x10-15

ITER 1 10 3.5 25 10-4 0.25 10 2x 10-2

FNS-ST 1 2 0.05 0.2 1 0.3 0.2 6x10-3

DEMO-FNS 1 4 0.3 2 1 0.3 1 7x10-1

DEMO 1 15 5 50 1 0.5 25 2x103

PROTO 1 15 6 150 1 0.8 30 1x104



Strategy 2013 for Fusion-Fission development in Russia

2015 2030 2050

T-15 ITER DEMO PROTO

DEMO-FNS

Test beds for enabling

technologies

CHP

Test beds for molten salt

technologies

Burning Plasma Physics

Nuclear physics and technology

Nuclear technologies of new generation

Hybrid Fusion

E.Velikhov, FEC-25

B.Kuteev et al. NF 2015



Major facilities on the path to Industrial Hybrid Plant

• Magnetic system• Vacuum vessel• Divertor• Blanket• Remote handling• Heating and current

drive• Fueling and

pumping• Diagnostics• Safety• Molten salts

Pilot Hybrid Plant construction by 2030 P=500 MWt, Qeng ~1

Steady State Technologies

•Materials

SSO&MS Globus-M3 FNS-ST DEMO-FNS

DT neutrons MS blankets

•Hybrid Tech•Integration

центральный столб обмотки тороидального магнитного поля вакуумная камера плазменный шнур опорная структура

Investment 1$B 0.1$B 1$B 5$B

10$B

100$B

Commercial Hybrid Plant construction by 2040 P=3 GWt, Qeng

~6.5 P=1.3 GWe, P=1.1 GWn, MA=1t/y, FN=1.1 t/y or T=14 kg/y



FEC-26Yu.S. Shpanskiy et al. FIP/O7-4Status of DEMO-FNS

Development

NATIONAL RESEARCH CENTER

KURCHATOV INSTITUTE

НАЦИОНАЛЬНЫЙ ИССЛЕДОВАТЕЛЬСКИЙ ЦЕНТР

«КУРЧАТОВСКИЙ ИНСТИТУТ»

• Fusion-fission hybrid facility based on

superconducting tokamak DEMO-FNS is

developed in Russia for integrated

commissioning steady-state and nuclear

fusion technologies at the power level up to

40 MW for fusion and 400 MW for fission.

Aspect ratio R/a, m 3.2/1

Toroidal magnetic field 5 T

Electron/ion

Temperature, keV 11.5/10.7

Beta normalized βN 2.1

Plasma current Ipl, 5 MA

Neutron yield GN 1.3·1019/s

Neutral injection power 36 MW

ECR heating power 6 MW

Discharge time 5000 h

Capacity factor 0.3

Life time 30 years

Consumed/

generated power 200 MW

• Facility is considered in RF as the

main source of technological and

nuclear science information that

complement the ITER research results

in the fields of burning plasma physics

and control.



FNS-ST, DEMO-FNS and ITER parameters

Device Parameters FNS-ST DEMO-FNS ITER

Major radius R, m 0.5 2.75 – 3.2 6.2

DT-fusion option Beam driven fusion Beam driven and

thermonuclear fusion

~50:50%

Thermonuclear

fusion

~100%

Heat transfer from alphas to plasma no yes/2 yes

Divertor configuration DN DN SN

Toroidal field at the VV center, T 1.5 5 5.3

Fusion power, MW 1 - 3 30 - 40 500

Auxiliary heating power PAUX, МВт ~ 8 - 10 30 - 40 50 - 150

Fusion energy gain factor Q ~ 0.2 ~ 1 ~ 10

Shielding at high field side, m No shield > 60 cm 100 – 120 cm

Type of magnetic system Cu alloys LTS LTS

Neutron loading Гn, MW/m2 0.2 0.2 0.5

Neutron fluence, MWy/m2 ~ 2 ~ 2 0.3

NATIONAL RESEARCH CENTRE

KURCHATOV INSTITUTE

НАЦИОНАЛЬНЫЙ ИССЛЕДОВАТЕЛЬСКИЙ ЦЕНТР

«КУРЧАТОВСКИЙ ИНСТИТУТ»



Structural and Functional Materials of the Hybrid Concept –key issue

Structural materials:austenitic steels 12Х18Н10Т (SS316)

ЧC-68ЭК-164

Nickel alloys Hastelloy

Vanadium alloys V-(4-9)Cr-(0.1-8)W-(1-2Zr)

V-4Cr-4Ti

Materials for Magnetic System CuCuCrZrNb3SnNbTiMgB2

Insulators MgAl2O4ghPolyimid

8

Reduced 14 MeV-neutron loading <0.2 MW/m2

makes possible implementation of existing materials



Coolants are starting point for designing the Hybrid Concept

9

System Loads T-range,

K

Potential coolants/Materials

Water Heavy

Water

Water-

Steam

Mixture

Organic

Coolant

s

He S-CO2 Liquid

Metals

Molte

n Salts

First Wall 5 MW/m2 300-500 + - - - - + - -

Divertor 10 MW/m2 350-500 + - - - - + - -

Vacuum

Vessel0.2 MW/m2 300-470 + - - - - - - -

Active Core 85 kW/l <550 ∓ + ±* - - + - -

T-Breeding

Blanket0.5 kW/l <600 - + - - + + ± -

Fissile

Breeding

Blanket

1 kW/l <550 - - - - + - +

Li-circulation ~1/h <600 + - - - - + - -

Magnets and

Thermal

Shield

~20 kW

at 4 K4-80 - - - - + - - -

*) symbol ± - rather "yes" than "no"; symbol ∓ - rather "no" than "yes"

Compatibility of coolants with multiple enabling fusion and fission

technologies is challenging



Challenges for coolants of DEMO-FNS enabling systems

10

System Loads T-range,

K

Design concerns

First Wall 5 MW/m2 300-500 Large area ~200 m2 with the thermal loading located at arbitrary place

Divertor 10 MW/m2 350-500 Extremal heat loading localized nearby divertor strike points

Vacuum

Vessel0.2 MW/m2 300-470 Internal pressure limited by 20 bars

Active Core 85 kW/l <550 Fast neutron spectra, close packing of fuel rods, remote handling, afterheat

T-Breeding

Blanket0.5 kW/l <600 High temperature for T-extraction

Fissile

Breeding

Blanket

1 kW/l <550 Continuous nuclide processing, soft neutron spectra

Li-circulation ~1/h <600 Fire safety, control of temperature fields

Magnets and

Thermal

Shield

~20 kW

at 4 K4-80 Magnetically and thermally induced stresses



First Wall and Divertor H2O, D2O

Concerns

Heat sink material

corrosion CuCrZr

Compatibility with Li

under accidents

Heat transfer crisis

under local loading

Softer neutron

spectra

Zones of concern

Heat sink – water

coolant interface

at T>150 C

V.Yu. Sergeev et al.

Nucl. Fusion (2015)

55

11

Pros

Well developed

Experimentally

tested

B-field compatible

1 - cassette case,

2 – heat removal panel,

3 - internal panel

4 - external panel

5 - internal reflector,

6 - external reflector

7 - collectors,

8 – Dome,

9 - supporting device with

hinge

10 - standpipe with coolant,

11 - drain pipe with a

coolant,

12 - gripper arm

Divertor is double null and

consists of 36 independent

cassettes

Trend – “closed

configuration”



First Wall and Divertor S-CO2

First Wall mock-up with pressurized water coolant

Concerns

High pressure ~80 bar

High heat flux tests

Local heat transfer

Dissociation at high

temperature ??

V.Yu. Sergeev et al.

Nucl. Fusion (2015)

55

Successful operation at the heat load up to 10 MW/m2 up to 500 thermal cycles

12

Pros

Well developed

Experimentally

tested in reactors

B-field compatible

Li compatible

Higher

temperatures

1

2

5

4

3



Vacuum Vessel Coolant

VV with low pressure 20 bar water coolant

Concerns

Hydrogen generation

by neutrons

Interaction with boron

steel of neutron

shield

Activation near LTS

and electronics

Zones of concern

Steel– water

coolant interface

Pipes near LTS

B. Kuteev et al.

Nucl. Fusion (2017)

57 Close to ITER technology, minimal problems

13

Pros

well developed

experimentally

tested



Electromagnetic system of DEMO-FNS

14

General view of EMS

Superconducting electromagnetic

system (EMS) of DEMO-FNS

includes:

Toroidal field coils (TFC) -18 units

Central solenoid (CS) sectioned

Poloidal field coils (PFC) 4 pairs

Correction coils (CC) 3 groups, 18

units

Vertical control coils – 2 units

HTS current leads

materials:

Nb3Sn, NbTi, HTS,

SS, Cu-alloys

Polyimide insulator

He-coolant



Blanket of DEMO-FNSFunctions: transmutation of minor actinides (MA) and self-sufficient

tritium breeding

Coolants: H2O, H2O+steam, S-CO2 , He – choice is steel needed

1 - module case;

2 – subrcitical active core;

3 – T-breeding zone (ceramic

breeder) Li4SiO4;

4 - coolant inlet collector;

5 - coolant outlet collector;

6 – inlet He-gas collector;

7 – outlet He-gas collector

Nuclide Mass fraction, %

Np237 44.5

Am241 48.6

Am242m 0.04

Am243 6.1

Cm243 0.02

Cm244 0.74

Initial composition of the MA mixture

(total weight ~ 40 ton)

0.8 m



Neutron spectra in the first wall region

16

Neutron spectra in the first wall regionfrom DT-fusion neutron source in plasma chamberand fission neutron source in a subcritical blanket,normalized the DT-neutron wall loading of 0.2 MW/m2 and neutron multiplication factor M=20

1,E+06

1,E+07

1,E+08

1,E+09

1,E+10

1,E+11

1,E+12

1,E+13

1,E+14

1,E+15

1,E-07 1,E-06 1,E-05 1,E-04 1,E-03 1,E-02 1,E-01 1,E+00 1,E+01 1,E+02

n-F

lux

, cm

-2s-1

per

let

ha

rgy i

nte

rval

En, MeV

n(DT)+n(fiss)

0.2 MW/m2

M=20



Neutron and gamma-ray fluxes in the First Wall and neutron

fluence per one operation year from the combined fusion-fission

neutron source

17

The FW neutron fluence in terms of usually used the DT-neutron fluence is ~0.2 MWa/m2,

and in terms of the fast neutron fluence - 4.4x1021 cm-2 that is a factor of 2.2 higher

than from the DT-neutron source only.

V. Khripunov, Fusion Eng. Des. 109–111 (2016) 7–12

Fluxes Fluences

Neutron and gamma-Sources per 1 FPY All-to-

DT-n n-fission g-prompt All cm-2DT-source

Energy Region cm-2s-1 cm-2s-1 cm-2s-1 cm-2s-1 ratios

n-thermal (<0.4 eV) 7.4x1012 9.2x1013 9.9x1013 3.1x1021 13.4

DT-n (14.1 MeV) 1.2x1013 4.9 x105 1.2x1013 3.8x1020 1.0

n-fast (>0.1 MeV) 6.4x1013 7.6x1013 1.4x1014 4.4x1021 2.2

n-tot (>0 ) 1.3x1014 2.9x1014 4.2x1014 1.3x1022 3.3

gamma (~1.2 MeV) 3.8x1013 2.3x1014 1.8 x1013 2.8x1014 8.9x1021 7.4



Specific Coolant Activity after Irradiation during 1 FPY

18

(The fast neutron fluence ~4.4x1021 cm-2, the total neutron fluence ~1.3x1022 cm-2)

H2O and S-CO2 are low activated by T



Specific afterheat in coolants after irradiation during 1 FPY

in combined fusion-fission spectra


H2O, CO2 and D2O have the lowest afterheat characteristics


Specific Tritium Production in Coolants per 1 FPY (Neutron Fluence ~1.3 x 1022 cm-2) and Decay after Irradiation (T1/2=12.3 yr)

20

FLIBE and FLINAK with nature composition have highest T-breeding

Coolant Bq/kg g-T/ kg

H2O 2.4x108 6.8x10-7

D20 1.7x1011 4.8x10-4

S-CO2 6.9x108 1.9x10-6

FLIBE 1.1x1015 3.2

FLINA

K

8.6x1014 2.4

Sodium

(Na)

7.4x1010 2.1x10-4

1,E+05

1,E+06

1,E+07

1,E+08

1,E+09

1,E+10

1,E+11

1,E+12

1,E+13

1,E+14

1,E+15

1,E+16

1,E-02 1,E-01 1,E+00 1,E+01 1,E+02

Tri

tiu

m A

ctiv

iy,

Bq

/kg

Time after Irradiation, years

Na

D2O

S-CO2

H2O

FLINAK

FLIBE



Schematic diagram of the energy conversion

system using S-CO2

21

Pros

High efficiency of

energy

conversion

Multy-loop (1-3)

Medium presure

(80 bars)

Reduced size and

weight

Available gas

turbines

(100 MW in Russia)

I.G. Surovtsev et al.

Science and Education,

Bauman University

Publishing, 2013



Conclusions

22

• Development of DEMO-FNS device for testing of fusion and hybrid

technology is in progress being at the stage of transition from conceptual

to engineering design

• Sequentially, in 2013-2016 the designs of tokamak, hybrid blanket and

fusion and fission fuel cycles were integrated in the facility

• The project is based on available materials, however, it may support

development of new materials for fusion and testing of components

•Integration of fusion and fission technological systems in one design

with minimal set of coolants is under design activity.

•The water coolant, water-steam mixture and super-crytical CO2

are possible engineering solutions for DEMO-FNS

with a broad list of final products including

neutrons, energy, tritium and fissile nuclides


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Choice of Coolants for DEMO-FNS Fusion-Fission Hybrid Facility · • Fusion-fission hybrid...

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