Monday 27 October 2014 - Elsevier...Monday 27 October 2014 07:30-08:45 Registration | Grand allroom...

The Nuclear Materials Conference, 2014| Oral Program

Monday 27 October 2014 07:30-08:45 Registration | Grand Ballroom Foyer

08:45-09:05 Opening Ceremony | Grand Ballroom D&E

09:05-09:15 Conference Welcome: L.K. Mansur, Chairman of Editors, Journal of Nuclear Materials | Grand Ballroom D&E

09:15-10:00 Robert Cahn Award Lecture: Dr. Claudio Ronchi | Grand Ballroom D&E

10:00-10:40 Plenary Speaker - Masaki Kurata, Japan Atomic Energy Agency, Japan | Grand Ballroom D&E

10:40-11:10 Coffee Break

Track 1 - Grand Ballroom A,B&C Track 2 - Grand Ballroom D&E Track 3 - Mangrove & Citrus Track 4 - Waters Edge Ballroom

11:10-12:35 Behavior of materials during severe accidents/accident tolerant fuels | Chair: Takanari Ogata | Grand Ballroom A,B&C

Sponsored by:

Structural and functional materials for fission and fusion reactors Chair: Lizhen Tan | Grand Ballroom D&E

Neutron irradiation fuels behavior/pie/advanced instrumentation and characterization/stored fuel behavior Chair: Vincenzo Rondinella | Mangrove & Citrus

Structural materials modeling and simulations Chair: Phillip D. Edmonson | Waters Edge Ballroom

11:10-11:20 Track 1 Intro Takanari Ogata, CRIEPI, Japan

Track 2 Intro Lizhen Tan, Oak Ridge National Laboratory, USA

Track 3 Intro Vincenzo Rondinella, ITU, EU, Germany

Track 4 Intro Phillip D. Edmonson, University of Oxford, UK

11:20-11:45 [O1.01] High temperature steam oxidation performance of candidate materials for accident tolerant fuel cladding B.A. Pint*, K.A. Terrani, J.R. Keiser, L.L. Snead, Oak Ridge National Laboratory, USA

[O2.01] Characterization and comparison of atomic displacement and gas production rates in various power and materials test reactors L. Walters*

1, S.R. Douglas

3, L.R.

Greenwood2, J. Pencer

1, T. Leung

1, M.

Griffiths1,

1Atomic Energy of Canada

Limited, Canada, 2Pacific Northwest

National Laboratory, USA, 3Retired from

Atomic Energy of Canada Limited, Canada

[O3.01] Revisiting the mechanisms of high burn-up structure formation in oxide nuclear fuel V.G. Baranov

1, A.V. Lunev*

1, A.V.

Tenishev1, V.F. Reutov

2, M.G.

Isaenkova1,

1National Research Nuclear

University, Russia, 2

Joint Institute for Nuclear Research, Russia

[O4.01] Radiation-induced mixing between metals of low solid solubility L. Zhang, M.J. Demkowicz*, Massachusetts Institute of Technology, USA

11:45-12:10 [O1.02] High-temperature oxidation of Zircaloy-4 in steam-nitrogen mixtures M. Steinbrück*, F. Oliveira da Silva, H.J.

[O2.02] Development of ODS FeCrAl ferritic alloys for fusion reactor applications D.T. Hoelzer*, K.A. Unocic, B.A. Pint, Oak

[O3.02] Strain relaxation in He implanted UO2 polycrystals under thermal treatment: An in-situ XRD study

[O4.02] Correlating magnetic characterization and material degradation of reactor structural materials through mesoscale phase field

Seifert, Karlsruhe Institute of Technology, Germany

Ridge National Laboratory, USA H. Palancher*1, R. Kachnaoui

1, R. Belin

1, C.

Sabathier1, J.C. Richaud

1, G. Martin

1, G.

Carlot1, H. Rouquette

1, A. Richard

1, E.

Castelier1,

1CEA, St. Paul Lez Durance

Cedex, France, 2

Institut Pprime, France,

3CNRS/UPR3079 CEMHTI, France,

4Electricité de France (EDF), France,

5CEA,

Grenoble Cedex, France

modeling Y.L. Li*

1, S.Y. Hu

1, J.S. Mccloy

2, P.

Ramuhalli1, W.L. Jiang

1, J.D. Suter

1, C.H.

Henager1, B. Johnson

1,

1Pacific Northwest

National Laboratory, USA, 2

Washington State University, USA

12:10-12:35 [O1.03] A conceptual model of nitridation process in the Zr-O-N system during air oxidation S. Park*

1, L. Fernandez-Moguel

1, M.

Steinbrück2, J. Birchley

1,

1Paul Scherrer

Institute, Switzerland, 2

Karlsruhe Institute of Technology, Germany

[O2.03] Current status of advanced radiation resistant oxide dispersion strengthened steel (ARROS) development for the core structural components of future nuclear systems in KAERI T.K. Kim*, S. Noh, S.H. Kang, Korea Atomic Energy Research Institute, Republic of Korea

[O3.03] UO2 structural modifications under swift heavy ion irradiation: Impact on fission gas release Y. Pipon*

1, N. Bérerd

1, N. Moncoffre

1, G.

Victor1, B. Marchand

1 ,4, L. Raimbault

2, C.

Garnier3, C. Delafoy

3,

1University of Lyon,

France, 2

Ecole des Mines de Paris, France,

3AREVA, France,

4University of Helsinki,

Finland

[O4.03] Development of an atomistically informed equation of state for helium in iron R.E. Stoller*, Y.N. Osetskiy, Oak Ridge National Laboratory, USA

12:35-13:35 Lunch Break | Grand Ballroom F&G and Grand Ballroom Foyer

13:35-14:15 Plenary Speaker - Steven J. Zinkle, ORNL, USA | Grand Ballroom D&E

14:15-14:20 Time to change rooms

Track 1 Continued | Grand Ballroom A,B&C

Sponsored by:

Track 2 Continued | Grand Ballroom D&E

Track 3 Continued | Mangrove & Citrus Track 4 Continued | Waters Edge Ballroom

14:20-14:45 [O1.04] Accident tolerant fuel cladding for LWRs P. Xu*, J. Mazzoccoli, E. Lahoda, Westinghouse Electric Company, USA

[O2.04] Novel composite materials for innovative design of high-heat-flux components of fusion reactors J.H. You*

1, A. Brendel

2, A. Herrmann

3, S.

Kimmig2, C. Linsmeier

4, J. Riesch

1, A.

Zivelonghi1, H. Greuner

1,

1Max-Planck-

Institut für Plasmaphysik, Germany,

2MTU Aero Engines GmbH, Germany,

3Helmholtz-Gemeinschaft, Germany,

4Forschungszentrum Jülich, Germany

[O3.04] Three-dimensional microstructure evolution in UO2: Comparison between HEDM experiments and POTTS model R. Pokharel*, D.W. Brown, Los Alamos National Laboratory, USA

[O4.04] The role of lattice deffects on segregation/precipitation behavior of a dilute Fe-Cu-Mn-Ni alloy: A phase-field approach S.B. Biner*, Y.F. Zhang, Idaho National Laboratory, USA

14:45-15:10 [O1.05] Chemistry and mechanics of alternative LWR clad T.M. Besmann*, M.K. Ferber, H.T. Lin, Oak Ridge National Laboratory, USA

[O2.05] The effects of tantalum addition on the microtexture and mechanical behavior of tungsten for ITER applications E. Tejado*

1 ,2, P.A. Carvalho

3 ,4, A.

Muñoz5, J.Y. Pastor

1,

1Universidad

Politécnica de Madrid, Spain, 2

Centro

[O3.05] Thermal spikes and energetic recoils in the grey phase and uranium dioxide M.J. Qin*

1, E. Kuo

1, S.C. Middleburgh

1,

G.R. Lumpkin1, M.W.D. Cooper

2,

1ANSTO,

Australia, 2

Imperial College London, UK

[O4.05] Formation and stability of Y-V-O-enriched nanoclusters in Fe-based alloys H. Zhao*

1, C-L. Fu

2, Y. Gan

1, D. Yun

3, D.

Hoelzer2,

1Clemson University, USA,

2Oak

Ridge National Laboratory, USA, 3

Argonne National Laboratory, USA

Nacional de Investigaciones Metalúrgicas (CENIM-CSIC), Spain,

3Instituto de Ciência e Engenharia de

Materiais e Superfícies, Portugal,

4Instituto Superior Técnico, Portugal,

5Universidad Carlos III, Spain

15:10-15:35 [O1.06] Tribological behaviors of cladding candidates for accident tolerant fuels Y.H. Lee*

1, T.S. Byun

2, Y.H. Koo

1,

1Korea

Atomic Energy Research Institute, Republic of Korea,

2Oak Ridge National

Laboratory, USA

[O2.06] Development of Fe-based composite materials for diverter by sintering with carbon nanofiber N. Hashimoto*

1, A. Kakitsuji

2, T.

Imanishi2,

1Hokkaido University, Japan,

2TASC, Japan

[O3.06] Microstructural development in U-Mo alloys irradiated to high fission density D. Keiser, Jr.*, J. Jue, J. Gan, B. Miller, A. Robinson, P. Medvedev, Idaho National Laboratory, USA

[O4.06] TBA

15:35-16:00 [O1.07] Experimental and computational examination of burst for alternative cladding materials under LOCA conditions K.A. Terrani*, T.S. Byun, B.A. Pint, Oak Ridge National Laboratory, USA

[O2.07] Synthesis and characterisation of ZrCxNy ceramics via carbothermic reduction-nitridation R. Harrison*, O. Ridd, D.D. Jayaseelan, W.E. Lee, Imperial College London, UK

[O3.07] Post-Irradiation examinations on Am-bearing FR blanket fuel irradiated at well-defined temperatures P.R. Hania*

1, S. Bejaoui

2, E. D'Agata

3, G.K.

Menard1, A.V. Fedorov

1, S. van Til

1, A.J.

van Lierop1, F. Delage

2,

1NRG, The

Netherlands, 2

CEA, France, 3

JRC, The Netherlands

[O4.07] He embrittlement at grain boundary of bcc transition metals: Systematic study T. Suzudo*, M. Yamaguchi, Japan Atomic Energy Agency, Japan

16:00-16:30 Coffee Break | Grand Ballroom F&G and Grand Ballroom Foyer


Sponsored by:



16:30-16:55 [O1.08] Effect of boron vapour on transport behaviour of deposited CsI during the heating test simulating a BWR severe accident condition I. Sato*, T. Onishi, K. Tanaka, M. Iwasaki, S. Koyama, Japan Atomic Energy Agency, Japan

[O2.08] Zirconium metal Li ceramic cermet development (PNNL-SA-102664) L.M. Bagaasen*, B.R. Johnson, R.O. Gates, J.S. Hardy, D.J. Senor, Pacific Northwest National Laboratory, USA

[O3.08] Interaction of metallic nuclear fuel with Fe-based cladding A. Aitkaliyeva*, J.W. Madden, J.R. Kennedy, J.I. Cole, Idaho National Laboratory, USA

[O4.08] Preferential Cu segregation at extended defects: An atomistic study Y.F. Zhang*, X.M. Bai, M.R. Tonks, S.B. Biner, Idaho National Lab, USA

16:55-17:20 [O1.09] Failure evaluation analysis of reactor pressure vessel lower head in BWR due to severe accident Y. Kaji*, J. Katsuyama, Y. Yamaguchi, Y. Nemoto, Y. Abe, F. Nagase, Japan Atomic Energy Agency, Japan

[O2.09] Evolution of microstructure in 15Cr-15Ni austenitic steel cladding tubes obtained by HPTR cold pilgering L. Courtin*

1, S. Bosonnet

1, D. Bossu

1, B.

Kedjar2, D. Eyidi

2, P. Olier

1, M.

Tabarant1, L. Thilly

2,

1CEA Saclay,

[O3.09] Helium bubble/void evolution in nanocrystalline RAFM steel under post-irradiation thermal annealing W.B. Liu, C. Zhang*, Z.G. Yang, Tsinghua University, China

[O4.09] Simulation for temperature dependence of irradiation-induced grain-boundary phosphorus segregation using first-principles-based rate theory model K. Ebihara*, T. Suzudo, M. Yamaguchi, Y. Nishiyama, Japan Atomic Energy Agency,

France, 2

Institut Pprime, France Japan

17:20-17:45 [O1.10] Ion plated Cr coating for the corrosion resistance of Zr cladding J.H. Park*, E.J. Kim, Y.I. Jung, D.J. Park, H.G. Kim, Y.H. Koo, Korea Atomic Energy Research Institute, Republic of Korea

[O2.10] Martensitic transformation in Eurofer-97 and ODS-Eurofer steels: A comparative study V.B. Oliveira

1, K.D. Zilnyk

1, H.R.Z. Sandim*

1,

A. Möslang2, D. Raabe

3,

1University of Sao

Paulo, Brazil, 2

Karlsruher Institut für Technologie, Germany,

3Max-Planck Institut

für Eisenforschung, Germany

[O3.10] Fractography Examination of Ex-Service Inconel X-750 CANDU Spacers C.D. Judge, C. Mayhew*, M. Wright, Atomic Energy of Canada Limited, Canada

[O4.10] Evaluation of advanced displacement cross-sections for the major EUROFER constituents based on an atomistic modelling approach A. Konobeyev*, U. Fischer, P. Pereslavtsev, Karlsruhe Institute of Technology, Germany

17:45-18:45 Welcome Reception | Grand Ballroom F&G and Grand Ballroom Foyer

Tuesday 28 October 2014 09:00-09:40 Plenary Speaker - Jerome Lamontagne, CEA, France | Grand Ballroom D&E



Sponsored by:



09:45-10:10 [O1.11] Advanced ODS FeCrAl alloys as accident tolerant fuel cladding S. Dryepondt*, K.A. Unocic, D.T. Hoelzer, T.S. Byun, B.A. Pint, Oak Ridge National Laboratory, USA

[O2.11] Basic and applied R&D for materials optimization and innovation for present and future challenges in nuclear energy C. Gallé, CEA, France

[O3.11] Extended storage effects on spent fuel properties V.V. Rondinella*, T.A.G. Wiss, D. Papaioannou, R. Nasyrow, European Commission, Joint Research Centre, Institute for Transuranium Elements, Germany

[O4.11] Mechanistic modeling of the creep fracture of HT9 steel A. Karahan, Argonne National Laboratory, USA

10:10-10:35 [O1.12] Microstructural characterization of the oxide layer formed on FeCrAl alloy during normal operation and accident conditions D.J. Park*, J.Y. Park, H.G. Kim, Y.I. Jeong, J.H. Park, Y.H. Koo, Korea Atomic Energy Research Institute, Republic of Korea

[O2.12] Effect of thermal treatment and microstructure on helium retention behaviour in V-based materials: TEM and SIMS characterisation S. Gorondy Novak*

1, F. Prima

2, F.

Jomard3, H. Lefaix-

Jeuland1,

1Commissariat à l'énergie

Atomique et aux énergies Alternatives, France,

2Chimie ParisTech, France,

3University of Versailles Saint-Quentin-

en-Yvelines, France

[O3.12] Chemical behaviour of a nuclear-grade magnesium alloy during storage T.P. Majchrowski*

1, J.A. Anderson

1, C.

Rhodes2, R.P.K. Wells

1,

1University of

Aberdeen, UK, 2

Nuclear Decommissioning Authority, UK

[O4.12] A metallurgical-mechanical model to describe the behaviour at high temperature of EM10 for generation IV fast-reactor applications A. Courcelle*, P. Gavoille, M. Le Flem, CEA, France

10:35-11:00 [O1.13] Mechanical properties and microstructural evolution of model accident tolerant FeCrAl alloys after LWR-Relevant neutron irradiation K.G. Field

1, X. Hu

2, K. Littrell

1, Y.

[O2.13] Effect of tempering on the microstructure, electrical and magnetic properties of Eurofer 97 steel M.J.R. Sandim*

1, F.U. Farrão

1, V.B.

Oliveira1, E.H. Bredda

1, A.D. Santos

2,

[O3.13] Influence of light ions irradiation of the oxide layer on the oxidation rate of zircaloy-4 alloy R. Verlet*

1, M. Tupin

1, G. Baldacchino

2, K.

Wolski3,

1CEA DEN, France,

2CEA DSM,

[O4.13] Integrity analysis of upper guide structure support flange K.H. Lee*, M.J. Jhung, Korea Institute of Nuclear Safety, Republic of Korea

Yamamoto1, L.L. Snead*

1,

1Oak Ridge


University of Tennessee, USA

C.A.M. dos Santos1, H.R.Z.

Sandim1,

1Escola de Engenharia de

Lorena-University of Sao Paulo, Brazil,

2Instituto de Física - University of Sao

Paulo, Brazil

France, 3

ENSMSE, France



Sponsored by:



11:30-11:55 [O1.14] Properties and performance of uranium-silicide compounds for potential light water reactor applications A.T. Nelson*, J.T. White, D.D. Byler, J.T. Dunwoody, K.J. McClellan, LANL, USA

[O2.14] Stability of MX precipitates in ferritic alloys under Fe

2+ ion and neutron

irradiations L. Tan*

1, K.G. Field

1, L.L. Snead

1, G.S.

Was2,

1Oak Ridge National Laboratory,

USA, 2

University of Michigan, USA

[O3.14] Advanced TEM techniques for characterisation of neutron and proton irradiation damage in Zr alloy Zircaloy-2 A. Harte*

1, E. Francis

1, M. Topping

1, T.

Seymour1, P. Frankel

1, L. Hallstadius

2, J.

Romero3, D. Jadernas

4, M.

Preuss1,

1University of Manchester, UK,

2Westinghouse Electric Vasteras, Sweden,

3Westinghouse Electric Company, Sweden,

4Studsvik Nuclear, Sweden

[O4.14] Molecular dynamics simulations to evaluate the effects of stacking fault energy on the interaction between an edge dislocation and an SIA loop in FCC metals K. Asari

1, K. Nishio

1, T. Okita*

1, S. Fujita

1, M.

Itakura2,

1The University of Tokyo, Japan,

2Japan Atomic Energy Agency, Japan

11:55-12:20 [O1.15] Mixing of uranium dioxide and hafnium at high temperature: Potential application to mitigate criticality risks in fast reactors C. Journeau*

1, P. Fouquart

1, V.

Marteau2, P. Allegri

2, O. Dugne

2,

1CEA

Cadarache, 2

CEA Marcoule, France

[O2.15] Role of helium and temperature on high dose swelling behavior in ion irradiated HT9 steel G.S. Was*, E. Getto, Z. Jiao, A. Monterrosa, K. Sun, University of Michigan, USA

[O3.15] Synchrotron micro-diffraction study of a 9-cycles cladding: Contribution to the metal/oxide interface characterization in Zircaloy-2 M. Chollet*, G. Kuri, J. Bertsch, S. Abolhassani, D. Grolimund, Paul Scherrer Institute, Switzerland

[O4.15] The study of irradiation damage and evolution of radiation-induced defects in Mo with MD and OKMC simulation approaches G.Y. Wu

1, N.W. Hu

1, H.Q. Deng*

1, S.F. Xiao

1,

P. Huai2, W.Y. Hu

1,

1Hunan University,

China, 2

Chinese Academy of Sciences, China

12:20-12:45 [O1.16] Transient benchmarking of advanced In-Pin metallic fuel performance models A. Karahan, Argonne National Laboratory, USA

[O2.16] Characterization of a high-Ni RPV weld after irradiation at wide range of neutron fluences and fluxes M.A. Sokolov*

1, G.R. Odette

2, R.K.

Nanstad1, W.L. Server

3, M.K.

Miller1,

1Oak Ridge National

Laboratory, USA, 2

University of California, Santa Barbara, USA,

3ATI

Conculting, USA

[O3.16] Impact of applied stress on c-component loops in recrystallized zirconium alloys: Experimental approach and cluster dynamics modelling N. Gharbi*

1, F. Onimus

1, T. Jourdan

1, D.

Gilbon1, J.P. Mardon

2, X. Feaugas

3,

1CEA,

France, 2

AREVA NP, France, 3

University of La Rochelle, France

[O4.16] Peroxide defect formation in grey phase perovskites S.C. Middleburgh*

1, I. Karatchevsteva

1, Z.

Zhang1, M.J. Qin

1, G.R. Lumpkin

1, P.A.

Burr1 ,2

, R.W. Grimes2, B.J. Kennedy

3, E.

Reynolds3,

1ANSTO, Australia,

2Imperial

College London, UK, 3

University of Sydney, Australia


13:45-14:25 Plenary Speaker - Steve Fitzgerald , Oxford University, UK | Grand Ballroom D&E

14:25-14:30 Time to Change Rooms

14:30-16:15 Thermodynamics and thermophysics of nuclear fuel materials Chair: Christine Gueneau | Grand Ballroom A,B&C

Track 2 Continued Radiation stability of complex microstructures (ion irradiation) Chair: Yanwen Zhang | Mangrove & Citrus

Materials modeling and simulation of nuclear fuels Chair: Marius Stan | Waters Edge Ballroom

14:30-14:35 Track 5 Intro Christine Gueneau, CEA, France

Track 6 Intro Yanwen Zhang, University of Tennessee, USA

Track 8 Intro Marius Stan, Argonne National Laboratory, USA




14:35-15:00 [O5.01] The OECD-NEA project “thermodynamics of advanced fuels-international database” C. Guéneau

1, N. Dupin

2, T.M.

Besmann*3, M. Kurata

4, S. Gossé

1,

P.E.A. Turchi5, D.H. Barber

6, M.H.A.

Piro6, E.C. Corcoran

7, J.C.

Dumas1,

1Commissariat à l'Énergie

Atomique et aux Énergies Alternative, France,

2Nathalie Dupin Calcul

Thermodynamique, France, 3

ORNL, USA,

4Japan Atomic Energy Agency, Japan,

5LLNL, USA,

6AECL Chalk River, Canada,

7Royal Military College of Canada,

Canada, 8

University of Ontario Institute of Technology, Canada,

9NRG, The

Netherlands, 10

Korean Atomic Energy Research Institute, Republic of Korea,

11Central Research Institute of Electric

Power Industry, Japan, 12

INL, USA,

13OECD-Nuclear Energy Agency, France

[O2.17] Effects of neutron irradiation on commercial MAX-phase ceramics Y. Katoh*

1, C. Shih

1, C.M. Parish

1, L.L.

Snead1, S.J. Zinkle

1 ,2, T. Toyama

3, T.

Shikama3,

1Oak Ridge National

Laboratory, USA, 2

University of Tennessee, USA,

3Tohoku University,

Japan

[O6.01] Ionization-induced self-healing of defects and collision damage in silicon carbide W.J. Weber*

1 ,2, R. Sachan

2, O.H.

Pakarinen2, M.L. Crespillo

1, P. Liu

1, H.

Xue1, Y. Zhang

2 ,1,

1University of

Tennessee, USA, 2

Oak Ridge National Laboratory, USA

[O8.01] A radial fission rate distribution model for innovative nuclear fuel designs A.J. Mieloszyk*, M.S. Kazimi, Massachusetts Institute of Technology, USA

15:00-15:25 [O5.02] The role of Ab Initio in building up a physics-based thermodynamic database for nuclear fuel materials P.E.A. Turchi*, A.P. Perron, A.I. Landa, P.A. Söderlind, Lawrenece Livermore National Laboratory, USA

[O2.18] The structural damage evolutions of MAX phases induced by Au irradiation C.X. Wang*1, T.F. Yang1, J.R. Xiao1, S.S. Liu1, J.M. Xue1, Q. Huang2, J.Y. Wang3, J.J. Kai4, Y.G. Wang1, 1Peking University, China, 2Ningbo Institute of Material Technology and Engineering, Chinese Academy of Sciences, China, 3Shenyang National Laboratory for Materials Science, Chinese Academy of Sciences, China,

4National Tsing Hua University, Taiwan

[O6.02] Radiation effects in perovskites in fission and fusion contexts K.R. Whittle*

1, S. Lawson

1, A.S. Gandy

1,

P.D. Edmondson2,

1University of Sheffield,

UK, 2

University of Oxford, UK

[O8.02] Minor actinide bearing blanket manufacturing press and associated material studies for compaction cycle optimization J-P. Bayle*, V. Reynaud, CEA, France

15:25-15:50 [O5.03] Thermodynamic description of the (U-Pu-O-Cs-I-Te-Mo) system for the volatile fission products modelling in SFR irradiated fuel J.C. Dumas*

1, T.N. Pham Thi

1, V.

Bouineau1, N. Dupin

2, C. Guéneau

3, S.

Gossé3, P. Benigni

4, P. Maugis

4, J.

Rogez4,

1Centre de Cadarache, France,

2Calcul Thermo, France,

3Centre de

Saclay, France, 4

Aix-Marseille University, France

[O2.19] High performance SiC/SiC pipes/tubes by new prototype continuous NITE process J.S. Park*

1, N. Nakazato

1, H. Nisimura

2,

D. Hayasaka2, H. Kishimoto

1, A.

Kohyama1,

1Muroran Institute of

Technology, Japan, 2

Graduate School of Engineering, Japan

[O6.03] In-situ and ex-situ characterization of ion-irradiation effects on third generation SiC fibers: Correlation between microstructure and properties J. Huguet-Garcia*, A. Jankowiak, S. Miro, D. Gosset, Y. Serruys, J.M. Costantini, CEA Saclay, France

[O8.03] Sensitivity studies examining current TRISO material property correlations for high-fluence applications J.J. Powers*

1, B.D. Wirth

1 ,2,

1Oak Ridge


University of Tennessee, USA

15:50-16:15 [O5.04] Thermodynamic assessments of U-M-O systems, where M=lanthanide, Th, or Y J.W. McMurray*

1 ,2, T.M. Besmann

1, S.

Voit1, D. Shin

1, B.W. Slone

3,

1Oak Ridge


The University of Tennessee, USA,

3California

Institute of Technology, USA

[O2.20] Swelling of SiC and SiCf/SiC as advanced nuclear structural materials after low temperature neutron irradiation M.I. Idris*

1 ,2, T. Yano

1, K. Yoshida

1, M.

Imai1,

1Tokyo Institute of Technology,

Japan, 2

The National University of Malaysia, Malaysia

[O6.04] Radiation stability studies on hollandite phase for nuclear waste immobilization M. Tang*

1, J. Amoroso

2, J. Marra

2, P.

Tumurugoti3, S.K. Sundaram

3, K.

Brinkman4,

1Los Alamos National

Laboratory, USA, 2

Savannah River National Laboratory, USA,

3Alfred

University, USA, 4

Clemson University, USA

[O8.04] Multiscale simulation of hydride behavior in nuclear fuel cladding during irradiation and long-term interim storage R.L. Williamson*, J.D. Hales, S.R. Novascone, B.W. Spencer, M.R. Tonks, Y. Zhang, Idaho National Laboratory, USA

16:15-17:45 Poster Session 1 & Coffee Break (Refreshments will be served from 16:10 until 16:40) | Grand Ballroom F&G

Wednesday 29 October 2014 09:10-09:50 Plenary Speaker – Rudy Konings, ITU, EU, Germany | Grand Ballroom D&E





09:55-10:20 [O5.05] Thermochemical studies in RE-Cd (RE: Ce, Pr, Nd, Sm, Eu) systems S. Ghosh*, R. Ganesan, R. Sridharan, T. Gnanasekaran, Indira Gandhi Centre for Atomic Research, India

[O2.21] Fracture characteristics of neutron-irradiated ferritic-martensitic steels in ductile-brittle transition region T.S. Byun*

1, T.A. Saleh

2, S.A. Maloy

2,

G.R. Odette3,

1Oak Ridge National

Laboratory, USA, 2

Los Alamos National Laboratory, USA,

3University of

California, USA

[O6.05] Relationship of void swelling and dispersoid stability in various ODS ferritic-martensitic alloys irradiated with self-ions to very high dpa levels F.A. Garner*

1, L. Shao

2, S. Ukai

3, M.B.

Toloczko4, V. Voyevodin

5, V. Bryk

5, O.

Borodin5, D. Hoelzer

6,

1Radiation Effects

Consulting, USA, 2

Texas A&M University, USA,

3Hokkaido University, Japan,

4Pacific

Northwest National Laboratory, USA,

5Kharkov Institute of Physics and

Technology, Ukraine, 6

ORNL, USA

[O8.05] Fuel performance modeling using microstructure rather than burnup via multiscale modeling and simulation M.R. Tonks*

1, Y. Zhang

1, Z. Bai

1, D.

Andersson2, C. Stanek

2, R.

Williamson1,

1Idaho National Laboratory,

USA, 2

Los Alamos National Laboratory, USA

10:20-10:45 [O5.06] Electronical and structural changes induced by the incorporation of Am into conventional fuels D. Prieur*

1, U. Carvajal-Nunez

1, F.

[O2.22] TBA

[O6.06] Kinetics versus thermodynamics in materials modelling: The case of the di-vacancy in iron and tungsten F. Djurabekova*

1, L. Malerba

2, P. Olsson

3,

[O8.06] Main features of the thermo-mechanical fuel code ALCYONE 1.4 V. Marelle*, P. Goldbronn, J. Sercombe, G. Jomard, B. Michel, V. Blanc, J. Julien, CEA,

Lebreton2, P. Martin

2, T. Delahaye

2, D.

Manara1, D. Staicu

1, A.C. Scheinost

3, T.

Vitova4, J. Somers

1,

1Institute for

Transuranium Elements, Germany,

2Commisariat à l'énergie Atomique,

France, 3

Helmholtz Zentrum Dresden Rossendorf, Germany,

4Institut für

Nukleare Entsorgung, Germany

R. Passianot4, K. Heinola

5,

1University of

Helsinki, Finland, 2

SCK-CEN Mol, Belgium,

3KTH, Sweden,

4CAC-CNEA and CONICET,

Argentina, 5

Culham Centre for Fusion Energy, UK

France

10:45-11:10 [O5.07] Thermodynamic assessment of Mo-Pd-Rh-Ru fission products precipitating in nuclear waste glasses S. Bordier*

1, S. Gossé

1, J. Rogez

2, S.

Schuller1,

1Commissariat à l’Energie

Atomique et aux Energies Alternatives, France,

2Universités d'Aix-Marseille,

France

[O2.23] Fracture of irradiated tungsten at low and intermediate irradiation temperature L.L. Snead*, T.S. Byun, N.A.P. Kiran Kumar, Oak Ridge National Laboratory, USA

[O6.07] Effect of heavy ion irradiation on microstructural evolution in CF8 cast austenitic stainless steel W.Y. Chen*

1 ,2, M. Li

1, M. Kirk

1, P. Baldo

1,

T. Lian3,

1Argonne National Laboratory,

USA, 2

University of Illinois at Urbana-Champaign, USA,

3Electric Power Research

Institute, USA

[O8.07] Role of microstructure on fuel performance: Macroscale insights from atomic-resolution simulations S.R. Phillpot*, A. Goyal, T-W. Chiang, B. Deng, Y. Li, M.J. Noordhoek, A. Chernatynskiy, S.B. Sinnott, University of Florida, USA





11:40-12:05 [O5.08] Thermodynamic evaluation of phase change behavior of MCCI products under estimated Fukushima-daiichi nuclear power plant conditions T. Kitagaki*, K. Yano, N. Kaji, T. Washiya, Japan Atomic Energy Agency, Japan

[O2.24] Brittle tungsten becomes tough: Pseudo-ductility in tungsten fibre-reinforced tungsten composites J. Riesch*

1, T. Höschen

1, S. Wurster

2, J-

H. You1, C. Linsmeier

3, R. Neu

1 ,4,

1Max-

Planck-Insitute für Plasmaphysik, Germany,

2Department of Materials

Physics, Montanuniversität Leoben, Austria,

3Forschungszentrum Jülich

GmbH, Germany, 4

Technische Universität München, Germany

[O6.08] Electron microscopy and spectroscopy for the study of helium cavities and radiation damage in oxide-dispersion-strengthened steels V. Badjeck*

1, M. Walls

1, E. Meslin

2, A.

Bhattacharya2 ,3

, L. Chaffron2,

1Université

Paris-Sud, France, 2

DEN/DMN/SRMA, CEA Saclay, France,

3CSNSM/IN2P3/CNRS,

Université Paris-Sud, France

[O8.08] Development and application of the SVECHA code to analysis of Zry cladding internal oxidation and secondary hydriding under LOCA conditions M.S. Veshchunov*, V.E. Shestak, Nuclear Safety Institute (IBRAE), Russian Academy of Sciences, Russia

12:05-12:30 [O5.09] Thermodynamics of Zr-H system S.C. Lumley

1 ,2, S.T. Murphy

1, P.A. Burr

1 ,3, A.

Chroneos4, P.R. Chard-Tuckey

2, R.W. Grimes

1,

M.R. Wenman*1,

1Imperial College London,

UK, 2

Defence Academy, UK, 3

Australian Nuclear Science and Technology Organisation, Australia,

4The Open

University, UK

[O2.25] Effects of thermal aging at 650 and 750°C on fracture toughness of Inconel 617 R.K. Nanstad*, X. Chen, M.A. Sokolov, Oak Ridge National Laboratory, USA

[O6.09] Effects of high-temperature heavy-ion irradiation in helium-implanted nano-engineered silicon carbide C.H. Chen*

1, Y. Zhang

2 ,1, E.G. Fu

3, Y.Q.

Wang4, M.L. Crespillo

1, S. Shannon

5, W.J.

Weber1 ,2

, 1University of Tennessee, USA,

2Oak Ridge National Laboratory, USA,

3Peking University, China,

4Los Alamos


North Carolina State University, USA

[O8.09] Joint modelling of fission gas transport and creep fracture in nuclear fuels M. Ovaska*, M.J. Alava, Aalto University, Finland

12:30-12:55 [O5.10] Contribution to the description of the absorber rod behavior in severe accident conditions: An experimental investigation of the Ag-Zr phase diagram A. Decreton*

1, P. Benigni

2, M. Lomello-

Tafin3, A. Janghorban

3, M. Barrachin

1, J.

Rogez2,

1IRSN, France,

2IM2NP, France,

3SYMME, France

[O2.26] In-situ TEM observation of dynamic interaction between dislocation and cavity in BCC metals in tensile deformation K. Tougou*, K. Fukumoto, K. Nogiwa, T. Onitsuka, A. Shikata, U. Kawase, University of Fukui, Japan

[O6.10] Irradiation behavior study of U-Mo/Al dispersion fuel with high energy Xe B. Yei*, D. Yun, K. Mo, W. Mohamed, Y.S. Kim, G. Hofman, J. Fortner, M. Pellin, A. Yacout, Argonne National Lab, USA

[O8.10] Open-porosity based inter-granular fission gas release model for fuel performance codes A. Claisse*

1, P. van Uffelen

1,

1KTH, Sweden,

2JRC-ITU, Germany


13:55-14:35 Plenary Speaker - Kai Nordlund, University of Helsinki, Finland | Grand Ballroom D&E

14:35-14:40 Time to change rooms Track 4 Continued

14:40-15:05 [O5.11] Thermodynamic study on the in-vessel corium system U-Pu-Zr-Fe-O A. Quaini*

1 ,5, C. Guéneau

1, S. Gossé

1, T.

Alpettaz1, A. Chocard

2, E. Brackx

2, R.

Belin3, D. Manara

4, F. Hodaj

5,

1CEA

Saclay, France, 2

CEA Marcoule, France,

3Cea Cadarache, France,

4European

ommission - Institut for Transuranium Elements, Germany,

5INP Grenoble,

France

[O2.27] Study of thin oxide layers of autoclave corrosion coupons of zircaloy-4 using synchrotron radiation diffraction and fluorescence B. Ensor*

1, A. Motta

1, R. Bajaj

2, J.

Seidensticker2, D. Spengler

3, Z. Cai

4, W.

Liu4,

1Penn State University, USA,

2Bettis

Atomic Power Laboratory, USA, 3

Knolls Atomic Power Laboratory, USA,

4Argonne National Laboratory, USA

[O6.11] Ion-induced microstructural changes at 500-600 dpa of a novel 12Cr ferritic-martensitic ODS alloy T.Y. Chen*

1, J. Jonathan

1, C.C. Wei

1, J.

Wang1, E. Aydogan

1, L. Price

1, D. Chen

1,

X.M. Wang1, L. Shao

2, S. Ukai

3,

1Texas

A&M University, USA, 2

Hokkaido University, Japan,

3University of Florida,

USA, 4

Radiation Effects Consulting, USA

[O4.17] Clustering of Fe and Cr in Zr alloys P.A. Burr*

1 ,2, M.R. Wenman

1, R.W.

Grimes1,

1Imperial College London, UK,

2Australian Nuclear Science and Technology

Organisation, Australia

15:05-15:30 [O5.12] Thermal expansion measurement of (U,Pu)O2-x in oxygen partial pressure controlled atmosphere M. Kato*

1, Y. Ikusawa

1, T. Sunaoshi

2, K.

McClellan3, A. Nelson

3,

1Japan Atomic

Energy Agency, Japan, 2

Inspection Development Company, Japan,

3Los

Alamos National Laboratories, USA

[O2.28] Evolution of alloying element distribution in Zircaloy-2 fuel cladding during in-reactor exposure G. Sundell*, M. Thuvander, H-O. Andrén, Chalmers University of Technology, Sweden

[O6.12] Timescales of natural recovery of alpha-decay-induced damage in UO2 Y. Eyal, Technion-Israel Institute of Technology, Israel

[O4.18] The effect of Sn on the properties of the oxide layer of Zr-based alloys B.D.C. Bell*

1, S.T. Murphy

1, P.A. Burr

1 ,2,

R.W. Grimes1, M.R. Wenman

1,

1Imperial

College London, UK, 2

Australian Nuclear Science and Technology Organisation, Australia

15:30-15:55 [O5.13] High temperature thermochemistry of (U,Pu)O2 MOx fuel with Hf absorbersApplication to severe accidents in SFR S. Gossé*

1, S. Chatain

1, T. Alpettaz

1, C.

Guéneau1, N. Dupin

2, E. Brackx

3,

1CEA -

Centre de Saclay, France, 2

Calcul Thermodynamique, France,

3CEA -

Centre de Marcoule, France

[O2.29] Microstructure and mechanical properties of Zircaloy-4 claddings hydrogenated at temperatures between 900 and 1200 K A. Pshenichnikov, J. Stuckert*, M. Walter, Karlsruhe Institute of Technology (KIT), Germany

[O6.13] Characterization of nuclear reactor materials using synchrotron radiation M. Li*

1, J. Almer

1, E. Benda

1, Y. Chen

1, D.

Hoelzer2, S. Maloy

3, A. Mashayekhi

1, Y.

Miao4, J. Park

1, L. Tan

2,

1ANL, USA,

2ORNL,

USA, 3

LANL, USA, 4

UIUC, USA, 5

IIT, USA,

6University of Florida, USA

[O4.19] A new tight-binding inter-atomic potential for zirconium hydrides precipitation modelling A. Dufresne*

1 ,2, F. Ribeiro

2, G.

Tréglia1,

1Aix-Marseille University, France,

2IRSN, PSN, SEMIA, LPTM, Cadarache,

France

15:55-16:20 [O5.14] Optimization of the conversion of uranium dioxide to uranium nitride through a carbothermic reduction

[O2.30] Emulation of biaxial creep behaviour of zircaloy-4 cladding for interim dry storage of light-water reactor spent

[O6.14] The National synchrotron light source-II – A new facility for materials characterization

[O4.20] Non-linear creep rate dependence on neutron flux in Zr-2.5Nb pressure tubing G.A. Bickel*, M. Griffiths, S.A. Donohue, A.

process A.J. Parkison*, A.T. Nelson, J.T. Dunwoody, K.J. McClellan, Los Alamos National Laboratory, USA

fuel K.C. Lan*1, Z.D. Kriz

1, Y. Miao

1, X.

Liu1, K. Mo

2, H.M. Tung

3, B. Fox

4, M.

Russo4, J.F. Stubbins

1,

1University of

Illinois at Urbana Champaign, USA,

2Argonne National Laboratory, USA,

3Institute of Nuclear Energy Research,

Taiwan, 4

Mensor, USA

L.E. Ecker*, D.J. Sprouster, S.K. Gill, E. Dooryhee, Brookhaven National Laboratory, USA

Buyers, AECL-Chalk River Laboratories, Canada

16:20-17:50 Poster Session 2 & Coffee Break (Refreshments will be served from 16:20 until 16:50) | Grand Ballroom F&G

Thursday 30 October 2014 08:30-09:10 Plenary Speaker - David Holcomb, ORNL, USA | Grand Ballroom D&E

09:10-10:30 Track 5 Continued | Grand Ballroom A,B&C


Molten salts for nuclear applications Chair: Kumar Sridharin | Mangrove & Citrus

Track 8 Continued | Waters Edge Ballroom

09:10-09:15 Track 7 Intro Kumar Sridharin, University of Wisconsin, USA

09:15-09:40 [O5.15] Modelling of irradiation of annular U-10Zr fuel in the ATR using BISON and comparison with post-irradiation examination results P.G. Medvedev, INL, USA

[O2.31] Corrosion behaviour of reference materials exposed to Pb, after fast neutrons irradiation in the BOR60 reactor, up to 16DpA A. Gessi*

1, P. Agostini

1, S.

Eremin2,

1ENEA, Italy,

2RIAR, Russia

[O7.01] High temperature corrosion of structural materials in molten fluoride salt G. Zheng*

1, B. Kelleher

1, G. Cao

1, M.

Anderson1, K. Sridharan

1, T.

Allen2,

1University of Wisconsin-Madison,

USA, 2

Idaho National Laboratory, USA

[O8.11] Computational evaluation of the thermal behaviour of U-Mo/Al and U-Mo/Mg research reactor fuels M.H.A. Piro*, B.W. Leitch, N. Wang, Chalk River Laboratories, Canada

09:40-10:05 [O5.16] Phase diagram investigation on Bi-Fe-O ternary system A.V. Meera*, R. Ganesan, T. Gnanasekaran, Indira Gandhi Centre for Atomic Research, India

[O2.32] Effect of reactive elements in Fe10Cr4Al alloys exposed to liquid lead up to one year J. Ejenstam*, P. Szakalos, KTH Royal Institute of Technology, Sweden

[O7.02] Investigating the corrosion and radiation damageof Ni-based alloys for fluoride molten salt applications R.L. Holmes*, H. Zhu, T. Palmer, I. karatchevtseva, E.R. Vance, D. Gregg, T. Hanley, Australian Nuclear Science and Technology Organisation, Australia

[O8.12] Calculations of effective thermal conductivity of U-Mo metallic fuels with distributed Xe gas bubbles S.Y. Hu*, A.M. Casella, C.A. Lavender, D.E. Burkes, Pacific Northwest National Laboratory, USA

10:05-10:30 [O5.17] Subsolidus phase relations in U-T-Al (T= Ti, Zr), ternary systems C. Moussa*

1, O. Tougait

2, M. Pasturel

1,

H. Noel1, B. Stepnik

3,

1CNRS, France,

2University of Rennes1, France,

3AREVA,

France

[O2.33] Investigation of synergetic influence of lead bismuth eutectic (LBE) and neutron irradiation on the tensile properties of the base and weld materials for accelerator driven systems M. Kolluri*, J. Degmova, A.J. Magielsen, Nuclear Research and Consultancy Group, The Netherlands

[O7.03] Enhanced molten salt corrosion in hastelloy N by dissimilar material interactions at high temperature J. Hou*, H. Ai, G.J. Yu, Shanghai Institute of Applied Physics, China

[O8.13] The effects of U-Mo particle - Al matrix interaction on the deformation of U-Mo/Al dispersion fuel during irradiation H.J. Ryu*

1, Y.S. Kim

1,

1Korea Advanced

Institute of Science and Technology, Republic of Korea,

2Argonne National

Laboratory, USA


11:00-11:25 [O5.18] The UC2-x - carbon eutectic: A laser heating study

[O2.34] A review of iodine-induced stress corrosion cracking research pertinent

[O7.04] Corrosion results on Ni alloys by molten alkali salts measured with a special TGA

[O8.14] Atomistic simulations of phonon properties in UO2A. Chernatynskiy*

1, B.

D. Manara*, K. Boboridis, S. Morel, F. De Bruycker, European Commission Joint Research Centre, Germany

to BWR, PWR and CANDU reactors M.H.A. Piro*

1, A. Douchant

1, C. Judge

1,

R.W. Revie2, M. Wright

1,

1Chalk River

Laboratories, Canada, 2

Consultant, Canada

sample carrier E. Post*

1, B. Fidler

1,

1NETZSCH

Geraetebau GmbH, Germany, 2

NETZSCH Instruments, USA

Deng1, J.W.L. Pang

2, B.C. Larson

2, S.R.

Phillpot1,

1University of Florida, USA,

2ORNL, USA

11:25-11:50 [O5.19] Phase-field simulation of reaction diffusion behaviour on UO2/Zr diffusion couple Y. Nishida*

1, Y. Tsukada

1, T. Koyama

1, M.

Kurata2,

1Nagoya Institute of

Technology, Japan, 2

Japan Atomic Energy Agency, Japan

[O2.35] Chloride-Induced transgranular stress corrosion cracking of 304L austenitic stainless steel G.G. Scatigno*, F. Giuliani, M.P. Ryan, M.R. Wenman, Imperial College London, UK

[O7.05]

TBA

[O8.15] A First-Principles study on heat capacity of actinide dioxides H. Nakamura*, M. Machida, Japan Atomic Energy Agency, Japan

11:50-12:15 [O5.20] Interdiffusion and reaction between U-10wt.%Zr and Fe-Cr-Ni alloys Y. Park*

1, K. Huang

1, K.R. Coffey

1, Y.H.

Sohn1, B.H. Sencer

2, J.R.

Kennedy2,

1University of Central

Florida, USA, 2

Idaho National Laboratory, USA

[O2.36] The suitability of polysiloxane coatings for mitigating iodine-induced stress corrosion cracking of Zircaloy-4 fuel sheathing G.A. Ferrier*, M. Farahani, J. Metzler, P.K. Chan, E.C. Corcoran, Royal Military College of Canada, Canada

[O7.06] Development of the fluorine potential model for understanding materials corrosion on molten FLiBe B. Kelleher*, M. Anderson, K. Sridharan, University of Wisconsin, USA

[O8.16] Degradation of thermal conductivity of standard, Cr-doped and mixed oxide fuels with burn-up M.W.D. Cooper*

1, S.C. Middleburgh

2, M.L.

Fullarton2, M. Qin

2, G.R. Lumpkin

2, R.W.

Grimes1,

1Imperial College London, UK,

2Australian Nuclear and Science Technology

Organisation, Australia

12:15-12:40 [O5.21] Interdiffusion behaviour of Pu and Am in MOX fuels T. Matsumoto*

1, T. Arima

1, Y. Inagaki

1, K.

Idemitsu1, M. Kato

2, K. Morimoto

2, H.

Uno3, T. Tamura

3,

1Kyushu University,

Japan, 2

Japan Atomic Energy Agency, Japan,

3Inspection Development

Company, Japan

[O2.37] Investigation of the impact of coatings on corrosion and hydrogen uptake of nuclear components R. Van Nieuwenhove*

1, K. Daub

2, H.

Nordin2,

1Institute for Energy

Technology, Norway, 2

Atomic Energy of Canada Limited, Chalk River Laboratories, Canada

[O7.07] Assessment of the pyrochemical DOS process for the recovery of actinides from spent oxide fuels developed by the CEA E. Mendes*, J. Serp, T. Plet, M. Miguirditchian, CEA Marcoule, France

[O8.17] Atomic migration behaviour of Kr in uranium dioxide: Application of a diffusion model E. Vathonne

1, M. Freyss

1, D. Andersson

2,

C.R. Stanek2, M. Bertolus*

1,

1CEA, DEN,

France, 2

Los Alamos National Laboratory, USA





13:40-14:05 [O5.22] The interdiffusion of U-based materials with Al: Characterization of the layer growth C. Moussa*

1, J. Allenou

2 ,4, X. Iltis

2, M.

Pasturel1, H. Palancher

2, B. Stepnik

3, O.

Tougait4,

1CNRS, France,

2CEA, France,

3AREVA, France,

4University of Rennes1,

France

[O2.38] TBA

[O7.08] A comparative study of gaseous Cl2 and HCl for the recovery of actinides from actinide-aluminium alloys B. Claux*

1, L. Cassayre

1, R. Meier

1 ,2, R.

Malmbeck1, P. Soucek

1, J-P. Glatz

1, T.

Fanghänel1 ,2

, 1European Commission,

Germany, 2

Heidelberg University, Germany

[O8.18] Thermodynamic and kinetic study of ZrN as diffusion barrier for U-Mo dispersion fuel Z.G. Mei*, A.M. Yacout, Y.S. Kim, G.L. Hofman, M. Stan, B. Ye, Argonne National Lab, USA

14:05-14:30 [O5.23] Experimental investigation of chemical compatibility between UO2 fuel and SiC/SiC structural material J. Braun

1, T. Alpettaz

1, S. Chatain*

1, E.

Brackx2, C. Guéneau

1, C. Sauder

1, F.

Balbaud1,

1CEA Saclay, France,

2CEA

Marcoule, France

[O2.39] Impact of radiolytic corrosion on the release of

13C and

37Cl implanted into

nuclear graphite : Consequences for the behaviour of

14C and

36Cl in gas

cooled graphite moderated reactors N. Moncoffre*

1, N. Toulhoat

1 ,2, N.

Bérerd1 ,3

, Y. Pipon1 ,3

, G. Silbermann1 ,4

, A. Blondel

1 ,5, N. Galy

1, P. Sainsot

6, J.N.

Rouzaud7, D. Deldicque

7,

1Université de

Lyon, France, 2

Centre de Saclay, France,

3Université de Lyon, UCBL IUT A, France,

4DIE - Division Environnement, France,

5Agence nationale Pour La gestion des

Déchets Radioactifs, France, 6

Université de Lyon, CNRS, France,

7Laboratoire de

Géologie de l’Ecole Normale Supérieure, France

[O7.09] Fluorination behavior of uranium - zirconium oxide solid solution H. Matsuura*

1, A. Nezu

1, H. Akatsuka

1, N.

Sato2,

1Tokyo Institute of Technology,

Japan, 2

Tohoku University, Japan

[O8.19] Thermo-mechanical properties of thoria: A density functional studies B. Szpunar*, J. Szpunar, University of Saskatchewan, Canada

14:30-14:55 [O5.24] Oxidation behavior and some material properties of sintered (U,Zr)O2 specimens M. Takano*, T. Nishi, A. Sudo, Japan Atomic Energy Agency, Japan

[O2.40] Corrosion behaviours of SiC triplex tubes in the hydrogen-controlled PWR primary water conditions D. Kim*, H.G. Lee, J.Y. Park, W.J. Kim, Korea Atomic Energy Research Institute, Republic of Korea

[O7.10] Phase equilibria in LiCl-KCl-PrCl3 ternary system S. Ghosh*, R. Ganesan, R. Sridharan, T. Gnanasekaran, Indira Gandhi Centre for Atomic Research, India

[O8.20] Modeling ion beam heating and sample temperature by high energy heavy ion irradiation and comparison with experimental measurements D. Yun*, K. Mo, W. Mohamed, M. Pellin, A. Yacout, Argonne National Laboratory, USA


15:00-15:40 Plenary Speaker - Toru Ogawa, Nagaoka University of Technology, Japan | Grand Ballroom D&E

15:40-16:20 JNM Award Talk | Grand Ballroom D&E Thermodynamic modelling of advanced oxide and carbide nuclear fuels: Description of the U-Pu-O-C system C. Guéneau*

1, E. Moore

1, N. Dupin

2, B. Sundman

1, C. Martial

3,

1CEA Saclay, France,

2Calcul Thermo, France,

3CEA Cadarache, France

16:20-16:30 Closing Ceremony | Grand Ballroom D&E

End of Conference

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