choice of coolants for demo-fns fusion-fission hybrid facility · • fusion-fission hybrid...
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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
B.V. Kuteev et al., Zvenigorod-2011, Russia, 14-18 February, 2011
• 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
B.V. Kuteev et al., Zvenigorod-2011, Russia, 14-18 February, 2011
• 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
3 B.V. Kuteev, 3-5 July, 2017, Coolants-1-st TM, IAEA, Vienna, Austria
B.V. Kuteev et al., Zvenigorod-2011, Russia, 14-18 February, 2011
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
4 B.V. Kuteev, 3-5 July, 2017, Coolants-1-st TM, IAEA, Vienna, Austria
B.V. Kuteev et al., Zvenigorod-2011, Russia, 14-18 February, 2011
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
5 B.V. Kuteev, 3-5 July, 2017, Coolants-1-st TM, IAEA, Vienna, Austria
B.V. Kuteev et al., Zvenigorod-2011, Russia, 14-18 February, 2011
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.
6 B.V. Kuteev, 3-5 July, 2017, Coolants-1-st TM, IAEA, Vienna, Austria
B.V. Kuteev et al., Zvenigorod-2011, Russia, 14-18 February, 2011
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»
7 B.V. Kuteev, 3-5 July, 2017, Coolants-1-st TM, IAEA, Vienna, Austria
B.V. Kuteev et al., Zvenigorod-2011, Russia, 14-18 February, 2011
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
B.V. Kuteev, 3-5 July, 2017, Coolants-1-st TM, IAEA, Vienna, Austria
B.V. Kuteev et al., Zvenigorod-2011, Russia, 14-18 February, 2011
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
B.V. Kuteev, 3-5 July, 2017, Coolants-1-st TM, IAEA, Vienna, Austria
B.V. Kuteev et al., Zvenigorod-2011, Russia, 14-18 February, 2011
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
B.V. Kuteev, 3-5 July, 2017, Coolants-1-st TM, IAEA, Vienna, Austria
B.V. Kuteev et al., Zvenigorod-2011, Russia, 14-18 February, 2011
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”
B.V. Kuteev, 3-5 July, 2017, Coolants-1-st TM, IAEA, Vienna, Austria
B.V. Kuteev et al., Zvenigorod-2011, Russia, 14-18 February, 2011
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
B.V. Kuteev, 3-5 July, 2017, Coolants-1-st TM, IAEA, Vienna, Austria
B.V. Kuteev et al., Zvenigorod-2011, Russia, 14-18 February, 2011
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
B.V. Kuteev, 3-5 July, 2017, Coolants-1-st TM, IAEA, Vienna, Austria
B.V. Kuteev et al., Zvenigorod-2011, Russia, 14-18 February, 2011
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
B.V. Kuteev, 3-5 July, 2017, Coolants-1-st TM, IAEA, Vienna, Austria
B.V. Kuteev et al., Zvenigorod-2011, Russia, 14-18 February, 2011
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
15 B.V. Kuteev, 3-5 July, 2017, Coolants-1-st TM, IAEA, Vienna, Austria
B.V. Kuteev et al., Zvenigorod-2011, Russia, 14-18 February, 2011
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
B.V. Kuteev, 3-5 July, 2017, Coolants-1-st TM, IAEA, Vienna, Austria
B.V. Kuteev et al., Zvenigorod-2011, Russia, 14-18 February, 2011
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
B.V. Kuteev, 3-5 July, 2017, Coolants-1-st TM, IAEA, Vienna, Austria
B.V. Kuteev et al., Zvenigorod-2011, Russia, 14-18 February, 2011
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
B.V. Kuteev, 3-5 July, 2017, Coolants-1-st TM, IAEA, Vienna, Austria
B.V. Kuteev et al., Zvenigorod-2011, Russia, 14-18 February, 2011
Specific afterheat in coolants after irradiation during 1 FPY
in combined fusion-fission spectra
19 B.V. Kuteev, 3-5 July, 2017, Coolants-1-st TM, IAEA, Vienna, Austria
H2O, CO2 and D2O have the lowest afterheat characteristics
B.V. Kuteev et al., Zvenigorod-2011, Russia, 14-18 February, 2011
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
B.V. Kuteev, 3-5 July, 2017, Coolants-1-st TM, IAEA, Vienna, Austria
B.V. Kuteev et al., Zvenigorod-2011, Russia, 14-18 February, 2011
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
B.V. Kuteev, 3-5 July, 2017, Coolants-1-st TM, IAEA, Vienna, Austria
B.V. Kuteev et al., Zvenigorod-2011, Russia, 14-18 February, 2011
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
B.V. Kuteev, 3-5 July, 2017, Coolants-1-st TM, IAEA, Vienna, Austria