1 Nuclear Energy Division Materials for Generation IV Nuclear Reactors Cargese, Sept. 24 – Oct. 6, 2007 Outlook on Gen IV Nuclear Systems and related Materials R&D Challenges - Goals for innovative reactor systems - Requirements for structural materials: generic and specific - Synergies, crosscutting R&D areas and modelling - Significance of international collaboration Frank Carré and Pascal Yvon CEA – Nuclear Energy Division
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Outlook on Gen IV Nuclear Systems and related Materials R&D Challenges
Outlook on Gen IV Nuclear Systems and related Materials R&D Challenges Goals for innovative reactor systems - Requirements for structural materials: generic and specific - Synergies, crosscutting R&D areas and modelling - Significance of international collaboration Frank Carré and Pascal Yvon - PowerPoint PPT Presentation
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1Nuclear Energy Division Materials for Generation IV Nuclear ReactorsCargese, Sept. 24 – Oct. 6, 2007
Outlook on Gen IV Nuclear Systems and related Materials R&D Challenges
- Goals for innovative reactor systems- Requirements for structural materials: generic and specific
- Synergies, crosscutting R&D areas and modelling- Significance of international collaboration
Type of nuclear materials Detection, technical difficulty, cost, time…
Strategies for a flexible management of actinides in Gen IV fast neutron systems.
Implementation depending on international standards and national optimization criteria (economics & waste).
6Nuclear Energy Division Materials for Generation IV Nuclear ReactorsCargese, Sept. 24 – Oct. 6, 2007
Technical challenges & Leading physical phenomena
60-year lifetime
Fast neutron damage (fuel and core materials) Effect of irradiation on microstructure, phase instability, precipitation Swelling growth, hardening, embrittlement Effect on tensile properties (yield strength, UTS, elongation…) Irradiation creep and creep rupture properties Hydrogen and helium embrittlement
High temperature resistance (SFR > 550°C, V/HTR > 850-950°C) Effect on tensile properties (yield strength, UTS, elongation…) High temperature embrittlement Effect on creep rupture properties Creep fatigue interaction Fracture toughness
Corrosion resistance (primary coolant, power conversion, H2 production) Corrosion and stress-corrosion cracking (IGSCC, IASCC, hydrogen cracking & chemical compatibility…)
Requirements for materials in future nuclear systems (1/2)
7Nuclear Energy Division Materials for Generation IV Nuclear ReactorsCargese, Sept. 24 – Oct. 6, 2007
Additional requirements
Material availability and cost
Fabricability, joining technology
In service inspection Non destructive examination techniques
Safety approach and licensing Codes and design methods
R&D effort needed to establish or complement mechanical design rules and standards
Decommissioning and waste management
Requirements for materials in future nuclear systems (2/2)
8Nuclear Energy Division Materials for Generation IV Nuclear ReactorsCargese, Sept. 24 – Oct. 6, 2007
Structural materials for Innovative Reactor Systems
SFR GFR LFR VHTR SCWR MSR Fusion
CoolantT (°C)
Liquid Na few
bars
He, 70 bars480-850
Lead alloys
550-800
He, 70 bars
600-1000
Water280-55024 MPa
Molten salt
500-720
He, 80 b300-480
Pb-17Li 480-700
Core Structures
Wrapper F/M
steels
Cladding AFMA
F/M ODS
Fuel & core
structures
SiCf-SiC composite
Target, Window Cladding
F/M steels ODS
CoreGraphite
Control rodsC/C
SiC/SiC
Cladding & core
structures
Ni basedAlloys &
F/M steels
Core structure
Graphite
Hastelloy
First wallBlanket
F/M steelsODS
SiCf-SiC
Temp. °C 390-700 600-1200 350-480 600-1600 350-620 700-800 500-625
DoseCladding 200 dpa
60/90 dpa
Cladding ~100 dpa
ADS/Target~100 dpa
7/25 dpa~ 100 dpa
+ 10 ppmHe/dpa+ 45 ppmH/dpa
Other components
IHX or turbine
Ni alloys
IHX or turbine
Ni alloys
9Nuclear Energy Division Materials for Generation IV Nuclear ReactorsCargese, Sept. 24 – Oct. 6, 2007
A new generation of sodium cooledFast Reactors
Reduced investment cost Simplified design, system innovations(Pool/Loop design, ISIR – SC CO2 PCS)
Towards more passive safety features+ Better managt of severe accidents
Integral recycling of actinidesRemote fabrication of TRU fuel
SFR Steering
Committee
U.S.A.U.S.A.JapanJapan
FranceFrance
South KoreaSouth KoreaEuratom Euratom countriescountries
10Nuclear Energy Division Materials for Generation IV Nuclear ReactorsCargese, Sept. 24 – Oct. 6, 2007
SFR Primary system
New 9-12%Cr F/M steel vs Advanced AusteniticGood physical and thermal properties, dilatation, low costBetter creep resistance (T91, T92 (Fe-9Cr-xW-V-N…))
Compactness, mass reduction of components DBTT but Improved toughness Weldability (%Cr dependent) Good compatibility with sodium impurities (C, O, N)(Demonstrated in Phénix 2ry system & Steam generator + 150 000 h Irradiation experiments of T91 & ODS (SuperNova))
Compact component and system designs (piping, IHX…)
Potential margin for temperature increase (< 600°C) (especially if using a gas turbine power conversion system)
Allowable departure from the negligible creep regime?
New materials for sodium fast reactors (1/2)
11Nuclear Energy Division Materials for Generation IV Nuclear ReactorsCargese, Sept. 24 – Oct. 6, 2007
J.L. Séran, A. Alamo, A. Maillard, H. Touron, J.C. Brachet, P. Dubuisson, O. Rabouille J. Nucl. Mater. 212-215 (1994) 588-593.
Great stability of fracture properties 9% Cr Martensitic steels
Swelling of advanced austenitic steels and ferrito-martensitic steels
used as fuel cladding in Phenix
14Nuclear Energy Division Materials for Generation IV Nuclear ReactorsCargese, Sept. 24 – Oct. 6, 2007
Safety enhancement of Fast Reactor core
Low reactivity sodium void effect high BU coreLarge diameter fuel pin with thin spacer wireODS cladding for low swelling(Experiments in Phenix (Supernova, Matrix1&2) + in Joyo)
15-15 Ti lot CE
15-15 Ti bas C
12-25 Ti N915-25 bas Ti
15-25 Ti Nb DS5
15-25 Ti Nb DS4
16-25 Ti Nb V TS2
-5
0
5
10
15
400 450 500 550
-5
0
5
10
15
400 450 500 550
-5
0
5
10
15
400 450 500 550
-5
0
5
10
15
400 450 500 550
MA 957 MA 956
V/V%
T °C
15-15 Ti lot CE
15-15 Ti bas C
12-25 Ti N915-25 bas Ti
15-25 Ti Nb DS5
15-25 Ti Nb DS4
16-25 Ti Nb V TS2
-5
0
5
10
15
400 450 500 550
-5
0
5
10
15
400 450 500 550
-5
0
5
10
15
400 450 500 550
-5
0
5
10
15
400 450 500 550
MA 957 MA 956
V/V%
T °C
COEX COCA
MOX fuel fabrica-tion from co-precipita-ted UPu solution from the COEX process To be first tested in Phenix (Copix expt)
Various recycling modes of minor actinides in Fast Reactors: Homogeneous (~2% MA): GACID Heterogeneous in blanket (10-20% MA): Curios, Amboine2-Joyo expts
15Nuclear Energy Division Materials for Generation IV Nuclear ReactorsCargese, Sept. 24 – Oct. 6, 2007
A novel type of Gas-cooled Fast Reactor: an alternative to the Sodium Fast Reactor, and a sustainable version of the VHTR
Robust heat resisting fuel (<1600°C) 1200 MWe – THe ~ 850 °C - Cogeneration of electricity, H2, synfuel, process heat Safe management of cooling accidents Potential for integral recycling of Actinides
26Nuclear Energy Division Materials for Generation IV Nuclear ReactorsCargese, Sept. 24 – Oct. 6, 2007
Materials science and new materials are key for optimizing 2nd & 3rd
generation LWRs as well as to meet 4th nuclear systems’ objectives :> 2040: Fast reactors with a closed fuel cycle (SFR, GFR, LFR)~2025-30: High temperature reactors (V/HTR) for process heat (H2…)More prospective nuclear systems (SCWR, MSR)
Incremental progress and breakthroughs are sought on a wide span of structural materials for fuel claddings, core structures, reactor cooling systems & components (RPV, IHX, SG…), power conversion systems (electricity, H2…):
Innovative Reactor Systems & Requirements for Structural Materials
Summary (1/2)
27Nuclear Energy Division Materials for Generation IV Nuclear ReactorsCargese, Sept. 24 – Oct. 6, 2007
Increased role of Materials science (analytical research and modelling) for a more predictive R&D towards aimed materials properties
Metals Ceramics Fuels
International cooperation to increase and share R&D work and achieve breakthroughs for 21st century nuclear power systemsFederate national programs into a consistent international roadmap
Enhancing R&D and technology demonstrations (Gen IV, EU FP7…)Databases of materials propertiesMulti-scale modelling of materials & fuelsSynergies between Fission and Fusion materials
Progressing towards harmonized international standardsMechanical design rules and standards, CodificationSafety, non-proliferation, physical protection…
Innovative Reactor Systems & Requirements for Structural Materials