Workshop on Structural Materials for Innovative Nuclear Systems (SMINS)

in co-operation with the International Atomic Energy Agency


Karlsruhe, Germany

 

Hosted by

4-6 June 2007

 

Forschungszentrum Karlsruhe Logo

 

Materials research is a field of growing relevance for innovative nuclear systems, such as Generation IV reactors, critical and sub-critical transmutation systems and fusion devices. For these different systems, structural materials are selected or developed taking into account the specificities of their foreseen operational environment. However, material development projects share the common feature of requiring cross-cutting research programmes and advanced experimental and simulation facilities to characterise and evaluate the performance of the selected materials. This workshop aimed at stimulating an exchange of information on current material research programmes for different innovative nuclear systems in order to identify and develop potential synergies. The workshop, organised in co-operation with the International Atomic Energy Agency (IAEA), was hosted by Forschungszentrum Karlsruhe (FZK) and attracted some 120 participants.


Programme

 

Welcome addresses

W. Tromm (FZK)
F. Mompean (OECD NEA)
C. Fazio (FZK)


Overview papers (Chair: W. Tromm, FZK)


Inozentsev (IAEA): ADVANCED MATERIALS DEVELOPMENT AND FUEL PERFORMANCE ANALYSIS IN THE IAEA FOR THE NUCLEAR ENERGY SECTOR
Van Goethem (EC): EURATOM RDDD IN INNOVATIVE REACTOR SYSTEMS AND FUEL CYCLES


Session 1: Keynote lectures (Session chairs: W. Tromm, FZK and G. van Goethem, EC)

Carré (CEA): INNOVATIVE REACTOR SYSTEMS AND REQUIREMENTS FOR STRUCTURAL MATERIALS
Sekimura (University of Tokyo): TRANSFER OF KNOWLEDGE ON DATABASE ON MATERIAL ISSUES FROM AGED LWRS TO FUTURE REACTORS
Zinkle (ORNL): SYNERGIES BETWEEN FUSION AND INNOVATIVE FISSION SYSTEMS FOR STRUCTURAL MATERIALS R&D
Allen (University of Wisconsin): FUNDAMENTAL RESEARCH: MODELLING, MICROSTRUCTURES, RADIATION DAMAGE AND UNDERSTANDING OF IRRADIATION DATA
Möslang (FZK): EXISTING AND FUTURE IRRADIATION FACILITIES: THEIR AVAILABILITY AND ACCESS


Session 2: Gas cooled systems (Session chairs: W. Hoffelner, PSI and B. J. Marsden, University of Manchester)


Hittner: AN INDUSTRIAL POINT OF VIEW ON R&D NEEDS FOR HTR MATERIALS AND COMPONENTS
Snead: COMPOSITES FOR NUCLEAR CORE APPLICATION AT TEMPERATURES ABOVE 800°C
Heggie: BUCKLE, RUCK AND TUCK - THE RESPONSE OF GRAPHITE TO IRRADIATION
van der Laan: GRAPHITES AND COMPOSITES IRRADIATIONS FOR GAS COOLED REACTOR CORE STRUCTURES
Hoffelner: MATERIAL RESEARCH FOR VHTR DESIGN CODES
Burlet: EVALUATION OF NICKEL-BASE MATERIALS FOR VHTR PRIMARY CIRCUIT AND HEAT EXCHANGER
Hähner: MECHANICAL PERFORMANCE OF HTR TURBINE MATERIALS AFTER PRE-EXPOSURE TO CORROSIVE ENVIRONMENTS
Blanchet: AN UNCERTAINTY ASSESSMENT TECHNIQUE FOR MATERIALS BEHAVIOUR IN ADVANCED FAST REACTORS
Hoffmann / Roos: STRUCTURAL MATERIALS CONCEPTS FOR NUCLEAR POWER PLANTS
Buckthorpe: MATERIAL REQUIREMENTS FOR THE VERY HIGH TEMPERATURE REACTOR – RESULTS AND PROGRESS WITHIN THE RAPHAEL-IP


Session 3: Liquid metal cooled systems (Session Chairs: P. Yvon,CEA and C. Kato, JAEA)


Asayama: DEVELOPMENT OF STRUCTURAL MATERIALS FOR JAPANESE DEMONSTRATION FAST BREEDER REACTOR
Maloy: FAST REACTOR MATERIALS DEVELOPMENT AND TESTING FOR THE GNEP PROGRAM
Almazouzi: MATERIALS ISSUES IN ACCELERATOR DRIVEN SYSTEMS
Busby / Zinkle: RADIATION-INDUCED SEGREGATION IN ADVANCED REACTOR STRUCTURAL MATERIALS
Kimura: SUPER ODS STEEL RESEARCH AND DEVELOPMENT
Obara: INFLUENCE OF NORMALIZING TEMPERATURE ON MX PRECIPITATION BEHAVIOR IN HIGH CHROMIUM STEEL
Nikitina: DEVELOPMENT OF ODS FERRITIC-MARTENSITIC STEELS FOR INNOVATIVE NUCLEAR FAST BREEDER REACTORS
Dai: AN OVERVIEW OF MECHANICAL PROPERTIES AND MICROSTRUCTURE OF FERRITIC / MARTENSITIC STEELS AFTER IRRADIATION IN SINQ TARGETS
Valsakumar: VOID SWELLING AND DEFECT PROCESSES IN Ti MODIFIED STEELS USING ACCELERATOR IRRADIATION
Weissenburger: FeCrAlY COATINGS MODIFIED WITH A PULSED ELECTRON BEAM (GESA) USED AS CORROSION BARRIER FOR CLADDINGS IN LEAD ALLOYS


Session 4: Fusion, high power accelerator targets and other fission reactor systems (LWR, SCWR, MSR) (Session chairs: L. Heikinheimo, VTT and D. Gomez Briceño, CIEMAT)



Teysseyre: ASSESSING SCC AND IASCC FOR APPLICATION TO THE SCWR CONCEPT
Gomez-Briceño: OXIDATION AND STRESS CORROSION CRACKING OF STAINLESS STEELS IN SCWRs
Novotny: SCC TESTS OF AISI 304 AND 316L TYPE STAINLESS STEELS IN SCW CONDITIONS
Tan / Allen: MICROSTRUCTURAL INFLUENCE ON THE CORROSION BEHAVIOR OF STRUCTURAL MATERIALS FOR NUCLEAR SYSTEMS
Kalinin: DEVELOPMENT OF STRUCTURAL DESIGN CRITERIA FOR INTERNALS OF LWR
Li: INFLUENCE OF STACKING FAULT ENERGY (SFE) ON THE DEFORMATION MODE OF STAINLESS STEELS
Tavassoli: EVOLUTION OF STRUCTURAL MATERIALS IN NUCLEAR REACTORS
Dietz: QUALIFICATION OF STRUCTURAL MATERIALS FOR REACTOR SYSTEMS


Session 5: Fundamental research (Session Chairs: A. Almazouzi, SCK-CEN and S. Maloy, LANL)


Massoud / Domain: PREDICTION OF IRRADIATION DAMAGE EFFECTS BY MULTI-SCALE MODELLING: EURATOM 6TH FRAMEWORK INTEGRATED PROJECT PERFECT
Domain / Olsson: DENSITY FUNCTIONAL CALCULATIONS OF STRUCTURES AND DYNAMICS OF DEFECTS IN FE AND NI ALLOYS
Vincent / Becquart: SIMULATION OF THE MICROSTRUCTURAL EVOLUTION UNDER IRRADIATION OF DILUTE Fe-CuNiMnSi ALLOYS BY ATOMIC KINETIC MONTE CARLO MODEL BASED ON AB INITIO DATA
Malerba: UNDERSTANDING RADIATION DAMAGE IN FE-CR ALLOYS
Wirth: FUNDAMENTAL INVESTIGATION OF POINT DEFECT INTERACTIONS IN FE-CR ALLOYS
Monnet: THERMODYNAMICAL ANALYSES OF MOLECULAR SIMULATIONS OF DISLOCATION-DEFECT INTERACTIONS: SIMULATIONS AT 0K
Takahashi / Ghoniem: A NEW COMPUTATIONAL METHOD FOR STUDIES OF 3-D DISLOCATION-PRECIPITATE INTERACTIONS IN REACTOR STEELS
Ryazanov: EFFECT OF NEUTRON FLUX AND IRRADIATION TEMPERATURE ON RADIATION SWELLING OF AUSTENITIC STEELS AT HIGH NEUTRON DOSES OF FAST REACTOR BN- 350 OPERATIONS
Chen: IRRADIATION CREEP AND MICROSTRUCTURAL CHANGES IN AN ODS FERRITIC STEEL WITH HELIUM IMPLANTATION UNDER STRESS
Gaude-Fugarolas: ON THE THEORETICAL DEVELOPMENT OF NEW CREEP RESISTANT ALLOYS AND THEIR EMPIRICAL VALIDATION
Berre: MODELLING OF NUCLEAR GRADE GRAPHITE USING X-RAY TOMOGRAPHY DATA
Hernandez-Mayoral / Caturla: BASIC EXPERIMENTS FOR UNDERSTANDING MICROSTRUCTURE EVOLUTION UNDER IRRADIATION : TEM AND KMC CHARACTERISATION OF IRRADIATED PURE IRON
Bergner: COMBINED TEM, PAS AND SANS INVESTIGATION OF NEUTRON-IRRADIATED PURE IRON
Pouchon: SYNCHROTRON LIGHT TECHNIQUES FOR THE INVESTIGATION OF ADVANCED NUCLEAR REACTOR STRUCTURAL MATERIALS
Heifets / van Uffelen: FIRST-PRINCIPLES MODELING OF DEFECTS IN ADVANCED NUCLEAR FUELS


Summary Session (Session Chairs: C. Fazio, FZK and F. Mompean, OECD NEA): Session summaries by Session co-chairs


Session 1
Session 2 (B. Marsden) , Session 2 (W. Hoffelner)
Session 3
Session 4
Session 5
Workshop Summary (C. Fazio, FZK)
General discussion: Synergies, perspectives and conclusions

Poster Sessions


Cabet: HIGH TEMPERATURE CORROSION RESISTANCE OF SOME VHTR CANDIDATE ALLOYS UNDER IMPURE HELIUM
Hofflener: MATERIALS MODELLING-A POSSIBLE DESIGN TOOL FOR ADVANCED NUCLEAR APPLICATIONS
Jang: CHARACTERIZATION OF OXIDATION AND OXIDE LAYERS OF NICKEL-BASE SUPERALLOYS AT HIGH TEMPERATURE
Kim: AN EXPERIMENTAL SURVEY ON MECHANICAL PROPERTY CHARACTERIZATIONS OF THE ION-IRRADIATED SILICON CARBIDE
Alamzouzi: EXPERIMENTAL VALIDATION OF THE MULTISCALE APPROACH TO MODEL THE IRRADIATION DAMAGE IN REACTOR PRESSURE VESSEL STEELS
Konys: NEW ASPECTS OF OXYGEN CONTROL IN LBE SYSTEMS
Soler-Crespo: CORROSION BEHAVIOUR OF STAINLESS STEELS IN LEAD-BISMUTH EUTECTIC AND LEAD. EXISTING EXPERIENCE AND NEEDS
Song: THE LEAD AND LBE CORROSION RESEARCH AT KAERI
Takahashi: PERFORMANCE OF OXYGEN SENSOR AND CORROSION OF SURFACE-COATED STEELS, CERAMICS AND REFRACTORY METALS IN HIGH TEMPERATURE LBE
van den Bosch: LIMETS 2: A HOT-CELL TEST SET-UP FOR LIQUID METAL EMBRITTLEMENT (LME) STUDIES IN LIQUID LEAD ALLOYS
Becquart: LIQUID METAL-ASSISTED FRACTURE OF THE T91 MARTENSITIC STEEL
Yeliseyeva/Tsisar: CONCEPTION OF OPERATION OF IN-SITU OXIDE COATINGS CONCERNING LIQUID METAL COOLING SYSTEMS
Di Marcello: MODELLING OF PELLET CLADDING INTERACTION DURING POWER RAMPS IN PWR RODS BY MEANS OF TRANSURANUS FUEL ROD ANALYSIS CODE
Konobeev: INVESTIGATION OF RADIATION DAMAGE RATES IN A LWR VESSEL USING RESULTS OF MOLECULAR DYNAMICS SIMULATIONS
Blokhim/Chernov: THE RF NUCLEAR DATA BASE AND ITS APPLICATION TO THE STRUCTURAL MATERIALS IN NEUTRON SPECTRA OF FISSION AND FUSION POWER REACTORS
Chernov: ACTIVATION AND RADIATION DAMAGE OF THE RF CORE STRUCTURAL MATERIALS IN THE FISSION AND FUSION REACTORS
Clark: MATERIALS DEMAND FOR FUSION POWER PLANTS: IAEA PROJECTS, INITIATIVES AND DATABASES
Kato: EFFECT OF NEPTUNIUM IONS ON CORROSION OF ULTRA LOW CARBON TYPE 304 STAINLESS STEEL IN NITRIC ACID SOLUTION
Krsjak: STRUCTURAL MATERIALS FOR FUSION TECHNOLOGIES STUDIED BY NON DESTRUCTIVE TECHNIQUE
Lambercht: THE INFLUENCE OF DIFFERENT CHEMICAL ELEMENTS IN THE HARDENING-EMBRITTLEMENT OF RPV-STEELS
Malerba: INTERATOMIC POTENTIALS CONSISTENT WITH THERMODYNAMICS
Olsson: AB INITIO STUDY OF CR INTERACTIONS WITH POINT DEFECTS IN BCC FE
Over: THE WEB-ENABLED MATERIALS DATABASE OF JRC-EC, A USEFUL TOOL FOR MANAGING EUROPEAN GEN IV MATERIALS DATA
Roma: A FIRST PRINCIPLES STUDY OF PALLADIUM IN SILICON CARBIDE
Ryazanov: MODELLING OF RADIATION SWELLING IN GRAPHITE AND SIC MATERIALS
Terentyev: MOBILITY OF INTERSTITIAL CLUSTERS AND DISLOCATION LOOPS IN FE-CR ALLOYS
Teysseyre: MATERIAL CHALLENGES FOR THE VHTR CONCEPT
Vladimirov: NEW INSIGHT ON THE PRODUCTION PROCESS OF RAFM ODS STEELS FOR NUCLEAR APPLICATIONS
Wirth: ATOMISTIC SIMULATIONS OF DISLOCATION INTERACTIONS WITH STACKING FAULT TETRAHEDRON

Proceedings

The proceedings of this workshop will be published as an NEA report.

International Scientific Advisory Committee

Al Mazouzi, Abderrahim

SCK.CEN Belgium

Allen, Todd

Univ. of Wisconsin USA

Billot, Philippe

CEA France

Bolt, Harald

IPP Germany

Burlet, Helene

CEA France

Corsi, Franco

ENEA Italy

Fazio, Concetta (Chair)

FZK Germany

Gomez Briceño, Dolores

CIEMAT Spain

Heikinheimo, Liisa

VTT Finland

Hoffelner, Wolfgang

PSI Switzerland

Horvath, Akos

KFKI Hungary

Inozemtsev, Victor

IAEA

Kato, Chiaki

JAEA Japan

Maloy, Stuart

LANL USA

Mank, GŁnter

IAEA

Mansur, L. K.

ORNL USA

Marsden, Barry J.

Univ. of Manchester UK

Massoud, Jean-Paul

EdF France

Moeslang, Anton

FZK Germany

Mompean, Federico (Secretary)

OECD NEA

Perlado, J. M.

Univ. Politecnica de Madrid Spain

Ryu, Woo-Seog

KAERI Republic of Korea

Tromm, Walter

FZK Germany

Van Goethem, Georges

CEC

Wallenius, Janne

KTH Sweden

Yvon, Pascal

CEA France

Last updated: 1 February 2008




Karlsruhe, Germany


Hosted by


4-6 June 2007


Forschungszentrum Karlsruhe Logo