Synergies between Fission and Fusion Nuclear Systems:
Common R&D Issues and Possible Cooperation
Frank Carré
Program Director for Future Nuclear Energy Systems
CEA/Nuclear Energy Division
[email protected]
Nuclear Energy Division
Post-FISA Workshop – Luxembourg, march 16, 2006
Commonalities between Fission and Fusion Research
1
Materials considered for Tokamak large components
Breeding Blankets (DEMO è Reactor)
TF coils
blanket
manifolds
7
a
d
2
g
1
10
Blanket
module
q Tritium breeder materials: LiPbeu, Li2TiO2, Li4SiO4
(+ beyond EU: Li 2O, Li)
f
4
3
8
9
q Structural materials: Eurofer, Eurofer ODS,
SiCf/SiC (+ beyond EU: other M/FS, V alloys)
c
5
6
upper
ports
b
11
shield
e
h
divertor
plates
central
ports
vacuum
vessel
lower
ports
q Functionnal materials: Be (neutron multiplier),
permeation barrier & corrosion, electric insulators
in SiCf/SiC, shielding PP (W)
q Coolants: He, LiPbeu (+ beyond EU: Li, water SP)
R&D needs (measurements &
improvements)
Divertor (DEMO è Reactor)
q Structural materials: W alloys, Eurofer
(+ interface in C), Eurofer ODS, SiCf/SiC
(+ brasage?) (+ beyond EU: other M/FS, V alloys)
q Shielding materials: ceramic or W tiles
q Coolants: He, pressurized water, LiPbeu
(+ beyond EU: Li)
Nuclear Energy Division
ü Behaviour under irradiation (mechanical,
thermal, neutronic, electrical, …)
ü Irradiation behaviour
ü Modelling
ü Compatibility between materials
ü Fabrication (ex.: CIC, particle bed..)
ü Assembly (ex.: interface, weldings…)
ü Low long term activation
Post-FISA Workshop – Luxembourg, march 16, 2006
Commonalities between Fission and Fusion Research
2
HELOKA Loop for Fission-Fusion Systems Development
HELOKA (FZK-Karlsruhe): an helium test loop planned to be used for long
term R & D in the frame of the European Nuclear Fusion Program and for Gas
Cooled Reactors development for Fission Applications
Operating conditions
Filter
Flow rate: 2kg/s
Economizer
TBM
Cooler
(HT)
Pressure: 10 MPa
Temperature: 550°C
Test Blanket Module
IHX
vessel
Reactor
Vessel
Test
section
Heater
Cooler
(LT)
Crossduct
Vessel
Water
Cooling
Circulator
Test Divertor Module
Fission - 2007- 2015: (VHTR/GFR) 1/5
Fusion - 2007- 2020: Program of ITER
Hot gas duct thermo-mechanical studies,
generic helium technology, blower and
magnetic bearings testing, instrumentation
breeding blanket and divertor development,
components (pump, heat exchanger of the
ITER Helium cooling systems)
Nuclear Energy Division
Post-FISA Workshop – Luxembourg, march 16, 2006
Commonalities between Fission and Fusion Research
3
Synergistic R&D Issues between Fission and Fusion (1/2)
Ø Nuclear design code system
Neutronics (n, ? transport), 14 MeV n à (n, 2n), (n, a), decay heat
§ Thermal-hydraulics, thermo-mechanics…(FW components, blanket
thermal mgt)
§ Coupled calculations
à Fusion extends the range of applications
of Fission system design codes
§
Ø High temperature materials & system technology
§
§
§
§
§
§
Ceramics and composites (C-C, SiCf-SiC…)
Advanced ferritic & martensitic steels (9Cr), low activation steel
Oxide dispersion strengthened steel (ODS)
Helium system technology (Heloka, Helite…)
Lead alloy system technology (PbBi, PbLi…)
Codification of mechanical design rules
à Sharing experiments
(irradiation, characterization, manufacturing in loop tests, …)
Nuclear Energy Division
Post-FISA Workshop – Luxembourg, march 16, 2006
Commonalities between Fission and Fusion Research
4
Synergistic R&D Issues between Fission and Fusion (2/2)
ØSafety approach
§ Adaptation of Fission safety demonstration to Fusion experimental devices
§ Safety case of ITER and DEMO (confinement of tritium, decay heat removal…)
Ø In service inspection, maintenance and dismantling
§ Remote inspection, maintenance and repair of large structures
§ Remote dismantling and waste management
Ø Increased
synergies for the Fusion DEMO reactor
§ Optimization of blanket design for energy and tritium production
§ Demonstration of full tritium breeding and recovery
§ Production of initial tritium load
ØBasic research
§ Materials science & modelling (neutron damage, corrosion…), (ODS, ceramics)
§ Nuclear data
§ Chemical separation processes
Nuclear Energy Division
Post-FISA Workshop – Luxembourg, march 16, 2006
Commonalities between Fission and Fusion Research
5
Synergistic R&D Issues between Fission and Fusion (2/2)
Ø Safety approach
§ Adaptation of Fission safety demonstration to Fusion experimental devices
§ Safety case of ITER and DEMO (confinement of tritium, decay heat removal…)
Ø In service inspection, maintenance and dismantling
§ Remote inspection, maintenance and repair of large structures
§ Remote dismantling and waste management
Ø Increased
synergies for the Fusion DEMO reactor
§ Optimization of blanket design for energy and tritium production
§ Demonstration of full tritium breeding and recovery
§ Production of initial tritium load
Ø Education in nuclear physics and engineering
§ Attraction of young scientists in the fields of nuclear energy
§ Stimulation of education and training in nuclear physics and engineering
Nuclear Energy Division
Post-FISA Workshop – Luxembourg, march 16, 2006
Commonalities between Fission and Fusion Research
6
Possible cooperation between Fission and Fusion
Ø Initiatives of organizations involved in both F&F
§ Nuclear design code system
§ Structural materials development (joint irradiations in MTRs, PIE…)
§ Nuclear system technology (Heloka helium test loop…)
Ø Actions of the EU R&D FP6 relevant to both F&F
§
§
§
§
PERFECT – Irradiation damage on reactor components
EXTREMAT – Materials in extreme conditions
HOTLAB – Infrastructure for Fission & radiation protection research
MTH + I3 – Crosscutting research on nuclear safety, waste and material
Ø Towards
a “Fission Technology Platform” in FP7?
§ Organization parallel to that of Fusion governed by the EFDA
§ Consistent R&D on Fission systems of interest to Europe
§ Fast neutron systems with closed fuel cycles
§ V/High temperature systems & hydrogen
§ Innovations for ALWRs
§ Adequate training & maintaining/renewing R&D infrastructures
§ More balanced partnership with large nuclear countries (USA, Japan…)
§ Increased capacity for experimental & prototype reactors in Europe
Nuclear Energy Division
Post-FISA Workshop – Luxembourg, march 16, 2006
Commonalities between Fission and Fusion Research
7
Sustainable Nuclear Fission Technology Platform (SNF -TP)
LWR
(current & Gen -3)
Competitiveness
and Safety
Optimization
VHTR
Process Heat,
Electricity & H2
Materials & Fuel Development
Reactor Design & Safety
Training and R&D Infrastructures
Fuel Cycle and Waste Processes
System Integration
(Economy, non proliferation …)
Fast Neutron
Systems & Closed
Fuel Cycle
Critical Reactors
ADS
Nuclear Energy Division
Geological Disposal
Technologies,
design, safety
assessment
Post-FISA Workshop – Luxembourg, march 16, 2006 2
Commonalities between Fission and Fusion Research
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