The Nuclear Materials Conference, 2016 – Oral Program · The Nuclear Materials Conference, 2016 – Oral Program . Sunday 6 November 2016 18:30-20:00 Registration | Room: Joffre

The Nuclear Materials Conference, 2016 – Oral Program

Sunday 6 November 2016 18:30-20:00 Registration | Room: Joffre 1 (Level 1)

Monday 7 November 2016 07:30-08:45 Registration | Room: Joffre 1 (Level 1) 08:45-08:55 Welcome and Introduction | Room: Pasteur (Entrance Level 1) 08:55-09:15 Welcome Frank Carré, CEA, France| Room: Pasteur (Entrance Level 1) 09:15:09:30 Introduction - Gary Was, Editor in Chief of JNM | Room: Pasteur (Entrance Level 1) 09:30-10:10 Robert Cahn Award Lecture: Dr. Srikumar Banerjee, Bhabha Atomic Research Centre in Mumbai, India | Room: Pasteur (Entrance Level 1) 10:10-10:30 Coffee Break | Room: Joffre 1 (Level 1) 10:30-11:10 [PS1] Thermal properties and defect chemistry in nonstoichiometric (U,Pu)O2 | Room: Pasteur (Entrance Level 1)

Masato Kato, JAEA, Japan 11:10-11:15 Time to change rooms 11:15-11:20 Track 2- Structural and

Functional Materials for Fission and Fusion reactors Intro Session Chair: Arthur T. Motta, Mark Daymond, Jean Henry Room: Pasteur (Entrance Level 1)

Track 5- Behavior of Materials during Severe Accidents and Accident Tolerant Fuels Intro Session Chair: Mikhail Veshchunov, Masaki Kurata, Jean-Christophe Brachet Sponsored by Westinghouse

Room: Joffre CD (Level 1)

Track 4- Modelling and Simulation of Structural Materials Intro Session Chair: Pascal Bellon, Thomas Jourdan, Maria Jose Caturla Room: Barthez (Level 2)

Track 7- Characterization of Irradiated Materials and Nuclear Fuels Intro Session Chair: Ann Leenaers, Masahiko Ohsaka, Heather Chichester Room: Sully 3 (Level 1)

Track 8- Materials for the Nuclear Fuel Cycle Intro Session Chair: Stéphane Gin, James Neeway, Ondrej Benes Room: Joffre 5 (Level 1)

11:20-11:45 [O2.01] Nanostructure of titanium alloy Ti-Al-V-Zr and its response on long term thermal aging and ion irradiation A.A. Nikitin*1, S.V. Rogozhkin1, A.A. Vasiliev1, I.A. Schatslivaya2, J. Wagner3 et al, 1Kurchatov Institute, Russia, 2Central Research Institute of Structural Materials “Prometey”, Russia, 3Karlsruhe Institute of Technology, Germany

[O5.01] IAEA activities in the area of Nuclear Power Reactor Fuel Engineering M. Veshchunov, IAEA, Austria

[O4.01] KMC simulation of cluster nucleation in metals during irradiation K. Morishita*, T. Nakasuji, X. Ruan, Kyoto University, Japan

[O7.01] Overview of the U. S. Nuclear Science User Facilities (NSUF) J.R. Kennedy, Idaho National Laboratory, USA

[O8.01] Radiation effects on graphene-oxide hybrid materials D.C. Castley*, U.G.K. Wegst Dartmouth College, USA

11:45-12:10 [O2.02] Atom probe tomography and transmission electron microscope analysis of peak-aged Al-Mg-Si-Cu alloys K. Buchanan, K. Colas*, J. Ribis, A. Lopez, J. Garnier, CEA, Université Paris-Saclay, France

[O5.02] Analytical modelling of an unprotected transient overpower in sodium-cooled fast reactors K.H. Herbreteau*1, N.M. Marie1, F.B. Bertrand1, J.S. Seiler1, P.R. Rubiolo2 1CEA, France, 2CNRS, France

[O4.02] OKMC simulation of absorption kinetics of point defects by dislocations and defect clusters D. Carpentier*1, T. Jourdan1, Y. Le Bouar2, M-C. Marinica1, 1CEA Saclay, France, 2LEM, CNRS-ONERA, France

[O7.02] Postirradiation examination on metallic fuel tests in the AFC-2 series J.M. Harp, L. Capriotti*, H.J.M. Chichester, P.G. Medvedev Idaho National Laboratory, USA

[O8.02] New layered materials for radionuclide retention D. Alby*, C. Charnay, B. Prélot, J. Zajac, M. Héran, Université Montpellier, France

12:10-12:35 [O2.03] Investigation of long term thermal ageing effects on mechanical and microstructural

[O5.03] Release behavior of radionuclides from MOX fuels irradiated in a fast reactor during

[O4.03] Dynamics of interaction between point defects and dislocations in bcc iron using

[O7.03] TRABANT: Post-irradiation studies of a high power FR-MOX-irradiation in the

[O8.03] Treatment of irradiated nuclear graphite in LiCl KCl eutectic

properties of VVER-440 RPV steel M. Kolluri*1, A. Kryukov5,1, A.J. Magielsen1, P. Hähner1, V. Petrosyan3, G. Sevikyan4, Z. Szaraz2, 1Nuclear Research & consultancy Group (NRG), The Netherlands, 2Joint Research Centre - Institute for Energy and Transport, The Netherlands, 3Armenian Scientific Research Institute for Nuclear Plant Operation (ARMATOM), Armenia, 4Armenian Nuclear Power Plant (ANPP), Armenia, 5Scientific and Engineering Centre for Nuclear and Radiation Safety, Russia

heating tests K. Tanaka*1, I. Sato2, T. Onishi1, T. Ishikawa1, T. Hirosawa1, K. Katsuyama1, H. Seino1, S. Ohno1, H. Hamada1, D. Tokoro3 et al 1Japan Atomic Energy Agency, Japan, 2Tokyo Institute of Technology, Japan, 3Inspection Development Company, Japan

SEAKMC simulations H. Xu*, L. Casillas-Trujillo The University of Tennessee, USA

HFR S. van Til*1, A.V. Fedorov1, P.R. Hania1, R. Moss2, D. Staicu3, J. Somers3, N. Chauvin4, 1NRG, The Netherlands, 2JRC-IET, The Netherlands, 3JRC-ITU, Germany, 4CEA, France

T. Grebennikova*, C.A. Sharrad, A. Jones, R. Worth, H. Lambert, R. Foster, A. Theodosiou University of Manchester, UK

12:35-13:35 Lunch Break | Room: Joffre 1 (Level 1) 13:35-14:15 [PS2] Materials for the Material Testing Jules Horowitz Reactor | Room: Pasteur (Entrance Level 1)

Jérôme Garnier, CEA, France 14:15-14:20 Time to change rooms Track 2 Continued | Session

Chair: Arthur T. Motta, Mark Daymond, Jean Henry Room: Pasteur (Entrance Level 1)

Track 5 Continued | Session Chair: Mikhail Veshchunov, Masaki Kurata, Jean-Christophe Brachet Room: Joffre CD (Level 1)

Track 4 Continued | Session Chair: Pascal Bellon, Thomas Jourdan, Maria Jose Caturla Room: Barthez (Level 2)

Track 7 Continued | Session Chair: Ann Leenaers, Masahiko Ohsaka, Heather Chichester Room: Sully 3 (Level 1)

Track 8 Continued Session Chair: Stéphane Gin, James Neeway, Ondrej Benes Room: Joffre 5 (Level 1)

14:20-14:55 [T2.INV01] Radiation induced damage in Ni based superalloy X-750 from fast and thermal neurtons Zhongwen Yao, Queen’s University, Canada

[T5.INV01] Challenges and Outcomes from prototypic corium experiments within the European SAFEST consortium Christophe Journeau, CEA, France

[T4.INV01] Self-consistent mean field diffusion theory applied to the modeling of Fe-based alloys under irradiation Maylise Nastar , CEA, France

[T7.INV01] Irradiated fuel characterization and testing for in- and out of reactor safety applications Vincenzo Rondinella, ITU, Germany

[T8.INV01] Overview of the current safety assessment of HLW in Japan Seiichiro Mitsui, JAEA, Japan

14:55-15:20 [O2.04] Thermal and irradiation-enhanced ordering in Ni-Cr alloys of varying stoichiometry J.D. Tucker*1, F. Teng1, E. Marquis2, M.G. Burke3, 1Oregon State University, USA, 2University of Michigan, USA, 3University of Manchester, UK

[O5.04] Accident tolerant fuel development within Westinghouse - Present and future developments S.C. Middleburgh*1, P. Xu2, J. Partezana2, L. Cai2, D. Eaves3, S. Ray2, E.J. Lahoda2, 1Westinghouse Electric Sweden AB, Sweden, 2Westinghouse Electric Company LLC, USA, 3Westinghouse Springfields Ltd., UK

[O4.04] Improved object kinetic Monte Carlo model for quasi-atomistic simulation of iron-chromium alloys P. Castrillo*1, I. Dopico2, I. Martin-Bragado2, F.J. Rodriguez-Martinez1, J.F. Castejón-Mochón1, A.M. Hernandez1 1UCAM, Catholic University of Murcia, Spain, 2IMDEA Materials Institute, Spain

[O7.04] TEM characterization : Comparison between an in-reactor irradiated fuel and an ion-implanted fresh fuel C. Sabathier*1, C. Onofri1, O. Dieste Blanco2, T. Wiss2, C. Bachelet3, C. Baumier3, H. Palancher1, M. Legros4 1CEA,DEN,DEC, France, 2Institute for Transuranium Elements, Germany, 3CNRS/IN2P3,Paris Saclay University, France, 4CNRS/CEMES, Paul Sabatier University, France

[O8.04] The metal nuclear fuel with controlled porosity for fast breeder reactors D.P. Shornikov*, B.A. Tarasov, S.N. Nikitin, National Research Nuclear University MEPhI (Moscow Engineering Physics Institute), Russia

15:20-15:45 [O2.05] Characterization of alloy 800H irradiated by neutrons and ions to 16.6 dpa C.J. Ulmer1, J.J.H. Lim2, E.R. Anderson3, E. Marquis3, M.G.

[O5.05] Evaluation of the behavior of Cr-coated M5® cladding in nominal and accidental conditions J. Bischoff*1, C. Vauglin1, P. Barberis1, D. Perche1, B. Guerin1, D. Duthoo1, J-

[O4.05] Microstructure evolution under irradiation in model alloys for reactor pressure vessel steels: A novel object kinetic Monte Carlo

[O7.05] Smaller, faster, better: applying advanced microscopy to irradiated fuels and materials C.M. Parish*1, P.D. Edmondson1, R.L. Seibert2, T.J. Gerczak1, Y.

[O8.05] Thermogravimetric Study of Fluorination of Uranium and Zirconium Oxides by Fluorine for Fuel Debris Treatment N. Sato*1, A. Kirishima1, T.

Burke2, K.G. Field4, A.T. Motta*1 1The Pennsylvania State University, USA, 2University of Manchester, UK, 3University of Michigan, USA, 4Oak Ridge National Laboratory, USA

C. Brachet2, 1AREVA NP, France, 2CEA, France

approach L. Malerba*1, N. Castin1, M. Chiapetto1, C.S. Becquart2, C. Domain3, L. Messina4, P. Olsson5 1SCK-CEN, Belgium, 2U. Lille I, France, 3EDF R&D, France, 4CEA Saclay, France, 5KTH Stockholm, Sweden

Katoh1, K.A. Terrani1, 1Oak Ridge National Laboratory, USA, 2Illinois Institute of Technology, USA

Fukasawa2, 1Tohoku University, Japan, 2Hitachi-GE Nuclear Energy, Japan

15:45-16:10 [O2.06] Thermal recovery and strain rate sensitivity of helium irradiated Inconel 800H and AISI 310 Alloys F. Nie*, R.J. Klassen University of Western Ontario, Canada

[O5.06] Mechanical properties of TiN and TiAlN type coatings proposed for accident tolerant fuels I. Bhamji*1, D. Wolfe2, A. Motta2, P. Withers1, M. Preuss1, 1University of Manchester, UK, 2Pennsylvania State University, USA

[O4.06] Magnetism induced Ni surface segregation in Fe-Ni Alloys M. Sansa*1,2, A. Dhouib1,3, G. Tréglia2, F. Ribeiro4, 1University, Tunisia, 2CNRS, France, 3University, Saudi Arabia, 4IRSN, France

[O7.06] Dislocation loops in proton irradiated UO2 and CeO2 J. Pakarinen*1, L. He2, S. Conradson3, M. Khafizov4, T.R. Allen2, 1Belgian Nuclear Research Centre (SCK-CEN), Belgium, 2Idaho National Laboratory, USA, 3Institute Josef Stefan, Slovenia, 4Ohio State University, USA

[O8.06] Uranium nitride compacts by high voltage electro discharge consolidation M.S. Tarasova, National Research Nuclear University MEPhI (Moscow Engineering Physics Institute), Russia

16:10-16:35 Coffee Break | Room: Joffre 1 (Level 1) Track 2 Continued | Session



Track 4 Continued | Session Chair: Pascal Bellon, Thomas Jourdan, Maria Jose Caturla Room: Barthez (Level 2)



16:35-17:00 [O2.07] In Situ Investigation of Load Allocation in Ni-Mo-Cr Alloy With High Energy X-Ray C. Yu1, J. Liang1, Z. Nie2, Y. Ren3, R. Xie*1, 1Shanghai Institute of Applied Physics, China, 2Beijing Institute of Technology, China, 3Argonne Natioanl Lab, USA

[O5.07] Behaviour of ion irradiated chromium coatings on Zircaloy-4 substrate A. Wu*, J. Ribis, J.C. Brachet, E. Clouet, B. Arnal, E. Rouesne, S. Urvoy, J. Roubaud, Y. Serruys, F. Lepretre, CEA, France

[O4.07] Fast, vacancy-free climb of dislocation loops in bcc metals T.D. Swinburne*1, K. Arakawa2, H. Mori3, H. Yasdua3, M. Isshiki4, K. Mimura4, M. Uchikoshi4, S.L. Dudarev1, 1Culham Centre For Fusion Energy, UK, 2Shimane University, Japan, 3Osaka University, Japan, 4Tohoku University, Japan

[O7.07] In situ raman spectroscopy: A technique to investigate the nuclear material modifications under ion beam irradiation G. Gutierrez*1, S. Miro1, E. Bordas1, F. Leprêtre1, Y. Serruys1, C. Onofri1, L. Thomé2, F. Garrido2, A. Debelle2, G. Sattonnay2 et al 1CEA, France, 2Centre de Sciences Nucléaires et de Sciences de la Matière, France

[O8.07] A new approach for the determination of diffusion coefficients of lanthanides lower oxidation states and the intervalence charge transfer in molten salts S.A. Kuznetsov*1, M. Gaune-Escard2, 1Institute of Chemistry Kola Science Centre RAS, Russia, 2CNRS UMR, France

17:00-17:25 [O2.08] The effect of temperature on the preferential intergranular oxidation susceptibility of Alloy 600 G. Bertali*1, G. Burke1, F. Scenini1, N. Huin2, 1University of Manchester, UK, 2Areva NP, France

[O5.08] Assessment of high-temperature steam oxidation behavior of Zircaloy-4 with Ti2AlC coating deposited by magnetron sputtering C. Tang*, M. Stueber, M. Steinbrueck, M. Grosse, S. Ulrich, H.J. Seifert, Karlsruhe Institute of Technology, Germany

[O4.08] Modeling defect cluster evolution in irradiated structural materials B.D. Wirth*, A. Kohnert, D. Xu University of Tennessee, USA

[O7.08] Observing dislocation loop growth in stainless steels by additional irradiation at elevated temperature D.Y. Chen*1, K. Murakami1, K. Dohi2, K. Nishida2, N. Soneda2, Z.C. Li3, L. Liu1, N. Sekimura1, 1The University of Tokyo, Japan, 2Central Research Institute of Electric Power Industry, Japan, 3Tsinghua University, China

[O8.08] Uranium solubility in a molten reductive glass P. Chevreux*1, L. Tissandier2, S. Bahl3, A. Laplace1, E. Deloule2 1CEA, France, 2CRPG-CNRS, France, 3KIT, Germany

17:25-17:50 [O2.09] Oxide evolution on x-750 ni alloy in simulated bwr environment S. Tuzi*1, K. Göransson2, S.M.H.

[O5.09] Fabrication of Zr fuel cladding with oxidation resistant coating layer and its behavior under loss-of-coolant accident condition

[O4.09] Spatially-dependent rate theory model for the radiation-induced swelling in RAFM steels M.J. Zheng*, J.W. Fu, M. Jiang,

[O7.09] Clustering in a low Cu, high Ni RPV weld K.E. Lindgren*1, K. Stiller1, P. Efsing2, M. Thuvander1

[O8.09] Experimental study on tellurium corrosion of nickel - molybdenum alloys with ternary molten salt fluorides of lithium,

Rahman1, S.G. Eriksson1, F. Liu1, M. Thuvander1, J. Chen1,3, K. Stiller1, 1Chalmers University of Technology, Sweden, 2Westinghouse Electric Sweden AB, Sweden, 3Studsvik Nuclear AB, Sweden

D.J. Park*, H.G. Kim, Y.I. Jung, J.H. Park, J.H. Yang, Y.H. Koo, Korea Atomic Energy Research Institute, Republic of Korea

W.Y. Ding, J.P. Xin, S.Y. Hu, Q.Y. Huang, Institute of Nuclear Energy Safety Technology, China

1Chalmers University of Technology, Sweden, 2Vattenfall Ringhals AB, Sweden

beryllium and uranium V. Ignatiev*, A. Surenkov, I. Gnidoi, V. Uglov NRC “Kurchatov Institute”, Russia

17:50-19:20 Poster Session 1 (Refreshments will be served) | Room: Joffre 1 (Level 1)

Tuesday 8 November 2016

09:00-09:40 [PS3] Modelling Reactor Fuel Material Behavior Based on Microstructure Rather Than Burn-Up | Room: Pasteur (Entrance Level 1) Michael Tonks, INL, USA

09:40-09:45 Time to change rooms Track 2 Continued | Session



Track 6- Radiation Damage Processes in Materials and Complex Microstructures Intro Session Chair: Kazuhiro Yasuda, Aurélien Debelle, Maik K. Lang Room: Sully 2 (Level 1)



09:45-10:10 [O2.10] Effects of microstructure and irradiation conditions on tritium release from LiAlO2 D.J. Senor*1, W.G. Luscher1, K.K. Clayton2, 1Pacific Northwest National Laboratory, USA, 2Idaho National Laboratory, USA

[O5.10] Effects of neutron irradiation on nuclear grade SiC/SiC composites in LWR-relevant conditions Y. Katoh*1, T. Koyanagi1, K.A. Terrani1, M.A. Snead1, L.L. Snead2, K. Yueh3, 1Oak Ridge National Laboratory, USA, 2Massachusetts Institute of Technology, USA, 3Electric Power Research Institute, USA

[O6.01] Multi-scale simulation of the experimental responseof ion-irradiated zirconium carbide J-P. Crocombette*1, S. Pellegrino1, A. Debelle2, P. Trocellier1, L. Thomé2 1CEA Saclay, Université Paris-Saclay, France, 2Université Paris-Sud, France

[O7.10] Influence of the strain rate on the microstructure of UO2 poly crystals deformed during compression tests, at 1500°C M. Ben Saada*1,2, N. Gey2, X. Iltis1, A. Miard1, P. Garcia1, B. Beausir2, N. Maloufi2, 1CEA Cadarache, France, 2Université de Lorraine, France

[O8.10] Dimple-patterned Polymeric Microsphere for the Removal of Uranium in Nuclear Wastes J.I. Park*, Y.S. Youn, B. Kang, Y.K. Ha, Korea Atomic Energy Research Institute, Republic of Korea

10:10-10:35 [O2.11] Near zero tritium permeation through Al2O3 diffusion barrier coatings D. Iadicicco*1, F. Garcìa Ferré1, M. Vanazzi1,2, M. Utili3, F. Di Fonzo1, 1Istituto Italiano di Tecnologia, Italy, 2Politecnico di Milano, Italy, 3ENEA, Italy

[O5.11] Development of SiC-SiC composite accident tolerant fuel cladding C. Deck*1, H. Khalifa1, G. Jacobsen1, J. Sheeder1, J. Zhang1, C. Bacalski1, J. Stone1, C. Shih1, G. Vasudevamurthy1, E. Lahoda2 et al 1General Atomics, USA, 2Westinghouse Electric Company LLC, USA

[O6.02] The suitability of MAX phases for nuclear applications determined by proton irradiation and autoclave testing J. Ward*1, P. Frankel1, P. Withers1, D. Stewart3, M. Barsoum2, M. Preuss1 1University of Manchester, UK, 2Drexel University, USA, 3Rolls-Royce plc, UK

O7.11] From cladding oxidation to fuel-clad strong bonding in PWR fuel rods: Investigation of the fuel-clad interface evolution by morphological structural and elementray analyses C. Ciszak*1, L. Fayette1, S. Miro2, I. Zacharie-Aubrun1, S. Chalal3, K. Hanifi1, P. Bienvenu1, S. Schultig1, S. Chevalier4, 1CEA Cadarache, France, 2CEA Marcoule, France, 3Carl Zeiss, France, 4Université de Bourgogne, France

[O8.11] Developing waste-based inorganic polymers for radioactive waste encapsulation: A leaching study N. Vandevenne*1, B. Mast1, E. Thijssen1, G. Reggers1, R. Carleer1, T. Croymans-Plaghki1, Y. Pontikes2, S. Schreurs1, W. Schroeyers1 1Hasselt University, Belgium, 2KU Leuven, Belgium

10:35-11:00 [O2.12] LIBERTI- A new irradiation experiment design for in-pile tritium release and irradiation of Lithium ceramics and beryllium alloys in the High Flux Reactor Petten

[O5.12] Role of irradiation-induced defects on hydrothermal corrosion of SiC S. Kondo*, S. Mouri, T. Hinoki Kyoto University, Japan

[O6.03] Quantifying Disorder in Irradiated Crystals:A Statistical Approach of the Amorphization Process in SiC A. Boulle*1, A. Debelle1 1SPCTS, CNRS, Université de

[O7.12] Synchrotron X-ray diffraction investigations on strains in the oxide layer of an irradiated Zircaloy fuel cladding M. Chollet*1, S. Valance2, G. Stein1, D. Grolimund1, S.

[O8.12] Evolving solid/liquid interface during the dissolution of uranium based dioxide solid solutions : role chemical, structural and microstructural parameters

A.J. Magielsen*1,3, G. de Jong1,3, D. Boomstra1,3, F. Charpin1,3, G. Uitslag1,3, R. Knitter2, P. Vladimirov2, M. Kolb2, V. Chakin2, M. Zmitko2 et al, 1KIT, Germany, 2F4E, Spain, 3NRG, The Netherlands

Limoges, France, 2CSNSM, Univ. Paris-Sud, CNRS/IN2P3, France

Abolhassani1, M. Martin1, G. Kuri1, J. Bertsch1, 1Paul Scherrer Institute, Switzerland, 2CEA Cadarache, France

N. Dacheux*1, F. Tocino2, T. Cordara2, L. Claparede1, S. Szenknect2, J. Ravaux3, A. Mesbah3, 1ICSM/University of Montpellier, France, 2ICSM/CEA, France, 3ICSM/CNRS, France



Track 1- Thermodynamics and Thermal Properties of Nuclear Fuels Intro | Session Chair: Stéphane Gossé, Emily Corcoran, Dario Manara | Room: Joffre CD (Level 1)

Track 6 Continued | Session Chair: Kazuhiro Yasuda, Aurélien Debelle, Maik K. Lang Room: Sully 2 (Level 1)

Track 3- Modelling and Simulation of Nuclear Fuels Intro | Session Chair: Simon Phillpot, Markus Piro, Renaud Masson Room: Sully 3 (Level 1)

Track 4 Continued Session Chair: Pascal Bellon, Thomas Jourdan, Maria Jose Caturla Room: Joffre 5 (Level 1)

11:30-11:55 [O2.13] Unprecedented radiation endurance in oxide nanoceramic coatings F. García Ferré1, A. Mairov2, L. Ceseracciu1, Y. Serruys3, F. Lepretre3, M.G. Beghi4, K. Sridharan2, F. Di Fonzo1, M. Vanazzi*1, 1Istituto Italiano di Tecnologia, Italy, 2University of Wisconsin-Madison, USA, 3CEA/DEN/SRMP/JANNUS, France, 4Politecnico di Milano, Italy

[O1.01] Determination of point defect characteristics of uranium based, non-stoichiometric oxide fuels from electrical property measurements P. Garcia*1, Y. Ma1, A. Miard1, P. Matheron1, B. Dorado1 1CEA,DEN,DEC, France, 2CEA,DIF, France

[O6.04] Hydrogen Diffusion and Microstructural Evolution in H+ and He+ Ion-Implanted Gamma-LiAlO2 W. Jiang*1, D.J. Senor1, L. Shao2 1Pacific Northwest National Laboratory, USA, 2Texas A&M University, USA

[O3.01] Modelling behaviour of U3Si2 under light water reactor conditions K.A. Gamble1, K.E. Metzger2, Y. Miao3, A.M. Yacout3, J.D. Hales*1 1Idaho National Laboratory, USA, 2University of South Carolina, USA, 3Argonne National Laboratory, USA

[O4.10] Molecular dynamics simulations of the onset of plasticity in zirconium in relation to hydrides formation W. Szewc1,3, S. Brochard1,3, E. Clouet2, L. Pizzagalli*1,3 1CNRS, France, 2CEA, France, 3Université de Poitiers, France

11:55-12:20 [O2.14] Investigation of PVD coatings for nuclear applications: High temperature steam exposure testing J. Rabe*1, K. Daub2, H. Nordin2, R. Van Nieuwenhove1, T.M. Karlsen1, R. Szőke1, 1Institute for Energy Technology, Norway, 2Canadian Nuclear Laboratories, Canada

[O1.02] Oxygen self and chemical diffusion coefficients in (U, Pu)O2 M. Watanabe*1, M. Kato1, T. Sunaoshi2, 1Japan Atomic Energy Agency, Japan, 2Inspection Development Company, Japan

[O6.05] About the relevance of multi-beam irradiations to simulate the radiation aging of nuclear glass S. Peuget*5, A.H. Mir5, T. Charpentier1, L. Martel2, J. Somers2, S. Miro3, Y. Serruys3, M. Toulemonde4, S. Bouffard4, C. Jegou5, 1Université Paris-Saclay, France, 2Institute for Transuranium Elements (ITU), Germany, 3Laboratoire JANNUS, France, 4CIMAP-GANIL (CEA-CNRS-ENSICAEN-Univ. Caen), France, 5Laboratoire d’Étude des Matériaux et Procédés Actif, France

[O3.02] Fission Gas Behavior in U3Si2 at LWR Conditions Y. Miao1, K.A. Gamble2, D. Andersson3, Z.G. Mei1, A.M. Yacout*1, 1Argonne National Laboratory, USA, 2Idaho National Laboratory, USA, 3Argonne National Laboratory, USA

[O4.11] Embrittlement of nuclear claddings by hydrides: A Tight-Binding approach P. Eyméoud*1, F. Ribeiro1, A. Charaf Eddin2, G. Tréglia2 1IRSN, France, 2CINaM-CNRS, France

12:20-12:45 [O2.15] Microstructural and micromechanical characterization of SiC-SiC fiber composites for fuel cladding applications

[O1.03] The effect of Am on oxygen potential of MOX fuel at high temperatures T. Matsumoto*1, M. Kato1, K. Morimoto1, T. Sunaoshi2

[O6.06] Electron radiation damage in complex ceramic oxides, of the calcium silicate type M-N. de Noirfontaine1, M.

[O3.03] Density functional theory investigation of defect and fission gas diffusion in U3Si2 D.A. Andersson, Los Alamos National Laboratory, USA

[O4.12] Coupled crystal plasticity-finite element modeling of irradiation growth and creep in Zircaloy-2 A. Patra*, C. Tome, Los Alamos

Y. Zayachuk*1, D. Armstrong1, S.G. Roberts1,2, C. Deck3, P. Hosemann4, 1University of Oxford, UK, 2Culham Centre for Fusion Energy, UK, 3General Atomics, USA, 4University of California, Berkeley, USA

1Japan Atomic Energy Agency, Japan, 2Inspection development company, Japan

Courtial1,2, F. Dunstetter1, M. Signes-Frehel1, G. Wang3, M. Walls4, D. Gorse-Pomonti*1 1Ecole Polytechnique CEA CNRS Université Paris-Saclay, France, 2Université d'Artois, France, 3CNRS Université Paris-Diderot, France, 4CNRS Université Paris-Sud, France

National Laboratory, USA

12:45-13:45 Lunch Break | Room: Joffre 1 (Level 1) 13:45-14:25 [PS4] Integrated models for fusion reactor materials | Room: Pasteur (Entrance Level 1)

Sergei Dudarev, Culham Centre for Fusion Energy, UK 14:25-14:30 Time to change rooms 14:30-16:20 Track 2 Continued (14:40-16:20)

Session Chair: Arthur T. Motta, Mark Daymond, Jean Henry Room: Pasteur (Entrance Level 1)

Track 1 Continued | Session Chair: Stéphane Gossé, Emily Corcoran, Dario Manara Room: Joffre CD (Level 1)


Track 3 Continued | Session Chair: Simon Phillpot, Markus Piro, Renaud Masson Room: Sully 3 (Level 1)

Track 4 Continued | Session Chair: Pascal Bellon, Thomas Jourdan, Maria Jose Caturla Room: Joffre 5 (Level 1)

14:30-15:05 [O2.16] Characterization of oxide particles of Zr-added FeCrAl-ODS ferritic steels A. Kimura*, T. Takuya, P. Song, W. Han, K. Yabuuchi, P. Dou Kyoto University, Japan

[T1.INV01] Energetics of Trivalent Substitutional Elements Actinide Dioxides: Combined Computational and Experimental Investigations Mark Asta, UC Berkeley, USA

[T6.INV01] Nanostructured Materials- Radiation Interaction and Fuel Performance Modeling Jie Lian, Rensselaer Polytechnic Institute, USA

[T3.INV01] The way forward for fuel performance modelling - an overview of options Paul van Uffelen, ITU, Germany

[T4.INV02] New perspectives for non-adiabatic ion-electron interactions as unveiled by time dependent density functional theory Alfredo Caro, LANL, USA

15:05-15:30 [O2.17] Fine oxide dispersion and the evolution of ultrafine grained structure of austenitic oxide dispersion strengthened steel J. Jang*1, X. Mao1,2, C. Han1, S. Kang1, T. Kim1, 1KAERI, Republic of Korea, 2INEST, China

[O1.04] Thermodynamic investigations on rare earth uranates M. Sahu*, S. Dash, Bhabha Atomic Research centre, India

[O6.07] Investigation of the formation mechanisms of the high burnup structure in the spent nuclear fuel ‒ experimental simulation by in situ transmission electron microscopy experiment with ion beams Y. Haddad*, F. Garrido, A. Gentils, L. Delauche CSNSM, Univ Paris-Sud, CNRS/IN2P3, Université Paris-Saclay, France

[O3.04] First-principles modelling of point defects in (U,Pu)O2 MOX fuel M. Freyss*, M. Bertolus, I. Cheik Njifon, Y. Li, L. Shi CEA, France

[O4.13] Design of radiation resistant alloys T. SCHULER, P. Bellon*, D.R. Trinkle, University of Illinois at Urbana Champaign, USA

15:30-15:55 [O2.18] Synthesis of pyrochlore Y2Ti2O7 by high energy ball milling of Y2O3 and TiO2 powders E. Simondon*1, P.F. Giroux1, L. Chaffron1, P. Castany2, T. Gloriant2, 1Université Paris-Saclay, France, 2INSA Rennes, France

[O1.05] First-principles molecular dynamics study of high-temperature properties of thorium dioxide M. Machida*, H. Nakamura Japan Atomic Energy Agency, Japan

[O6.08] Quantification of irradiation induced defects in UO2 using Raman and positron annihilation spectroscopies L. Desgranges*1, R. Mohun1, S. Miro1, C. Jegou1, F. Duval2, A. Canizares2, P. Simon2, P. Desgardin2, M.F. Barthe2, B. Boizot1, 1CEA,DEN, France, 2CNRS, France

[O3.05] Numerical simulations and modeling of the effective plastic flow surface of a biporous material with pressurized intergranular bubbles: Application to irradiated uranium dioxide G. BOITTIN1, P-G. VINCENT*1,2, H. MOULINEC3, M. GARAJEU3 1Institut de Radioprotection et de Sûreté Nucléaire, France, 2Laboratoire de Micromécanique et Intégrité des Structures, IRSN-

[O4.14] The helium behaviours in vanadium studied with molecular dynamics simulations N.W. Hu, H.Q. Deng*, S.F. Xiao, W.Y. Hu, Hunan University, China

CNRS-UM, France, 3Laboratoire de Mécanique et d’Acoustique, CNRS, France

15:55-16:20 TBC- [O2.19] Mechanisms of Particle Coarsening and Phase Transformation in Oxide Dispersion Strengthened Steels During Friction Stir Welding K.E. Knipling*1, B.W. Baker2, D.K. Schreiber3, 1U. S. Naval Research Laboratory, USA, 2U. S. Naval Academy, USA, 3Pacific Northwest National Laboratory, USA

[O1.06] Valence states and local structure of lanthanide doped nuclear fuels R. BES*1, J. PAKARINEN2, S. CONRADSON3, A. BAENA2, J. HEIKINHEIMO1, M. VERWERFT2, F. TUOMISTO1,1Aalto University, Finland, 2SCK-CEN, Belgium, 3Jozef Stefan Institute, Slovenia

[O6.09] Small angle x-ray scattering investigations of defect structure in ceria irradiated with swift heavy ions S. Yoshioka*1, K. Tsuruta1, K. Yasuda1, S. Matsumura1, T. Horide2, N. Ishikawa3 1Kyushu University, Japan, 2Kyushu Institut of Technology, Japan, 3Japan Atom Energy Agency, Japan

[O3.06] Modeling oxygen redistribution and volatile fission product transport in germinal v2 using open calphad software K. Samuelsson*1, J-C. Dumas2, C. Guéneau3, N. Dupin4, B. Sundman5 1KTH Royal Institute of Technology Sweden, 2DEN/DEC – Centre de Cadarache, France, 3DEN/DANS/DPC – Centre de Saclay, France, 4Calcul Thermo, France, 5Centre de Saclay, France

[O4.15] Simulation of atomic structure in the neighbourhood of nanovoids and void growth rates in cubic metals A.V. Nazarov*1,2, A.A. Mikheev3, A.G. Zaluzhnyi1,2, 1National research nuclear university MEPhI, Russia, 2SSC RF Institute for Theoretical and Experimental Physics, Russia, 3Moscow State University of Design and Technology, Russia


17:55-19:30 Cocktail Reception | Room: Joffre 1 (Level 1)

Wednesday 9 November 2016

09:00-09:40 [PS5] The underlying philosophy and the progress towards development of accident tolerant fuels for LWRs | Room: Pasteur (Entrance Level 1) Kurt A. Terrani, ORNL, USA

09:40-09:45 Time to change rooms 09:45-09:55 Track 2 Continued | Session


Track 3 Continued | Session Chair: Simon Phillpot, Markus Piro, Renaud Masson | Room: Joffre CD (Level 1)

Track 4 Continued | Session Chair: Pascal Bellon, Thomas Jourdan, Maria Jose Caturla Room: Sully 2 (Level 1)


Track 5 Continued Session Chair: Mikhail Veshchunov, Masaki Kurata, Jean-Christophe Brachet Room: Joffre 5 (Level 1)

09:55-10:20 [O2.20] Synchrotron investigation of strain anisotropy in Zr hydrides during in situ precipitation C. Leclere*1, A. Ambard2, A. Legris3, M. Preuss4, F. Ribeiro1 1IRSN, France, 2EDF, France, 3Université de Lille 1, France, 4University of Manchester, UK

[O3.07] Study of rare gases behavior in uranium dioxide M. Gerardin*1, E. Gilabert2, D. Horlait2, M-F. Barthe3, P. Desgardin3, G. Carlot1, C. Sabathier1 1CEA Cadarache, France, 2Centre d'Etudes Nucléaires de Bordeaux Gradignan, France, 3Conditions Extrêmes et Matériaux Haute Température et Irradiation, France

[O4.16] Interstitial diffusion of Fe and Cr in Zr alloys P.A. Burr*1, A. Jain2, D.R. Trinkle2 1University of New South Wales, Australia, 2University of Illinois, USA

[O7.13] Effects of ion irradiation and dissolved hydrogen on corrosion in 316 stainless steel K. Murakami*1, K. Fujimoto2,3, D.Y. Chen1, K. Sakima2, T. Kobayashi2, T. Iwai4, N. Sekimura1 1The University of Tokyo, Japan, 2Mitsubishi Heavy Industries, Japan, 3Nuclear Development Corporation, Japan, 4Yamagata University, Japan

[O5.13] Thermal conductivity of simulated and real corium A. Seibert*1, D. Staicu1, D. Bottomley1, M. Cologna1, E. Kassim1, V. Tyrpekl2, T. Wiss1, R. Konings1, V.V. Rondinella1, J. Somers1, 1European Commission Joint Research Centre – Institute for Transuranium Elements, Germany, 2SCK•CEN, Department of Fuel Materials Analysis, Belgium

10:20-10:45 [O2.21] Hydride accelerated corrosion in Zircaloy-4 B. Ensor*1, A. Lucente1, M. Frederick1, A. Motta1 1Penn State University, USA, 2Bechtel Marine Propulsion Corporation, USA

[O3.08] Intragranular bubble impact on nuclear fuel thermomechanical properties F. Ribeiro*1, M. Colbert1, J. Arayro1, G. Tréglia2, 1IRSN, France, 2CNRS, France

[O4.17] Investigation of self-diffusion and phase transitions in Zr-Nb binary system performed with a novel interatomic potential D.E. Smirnova*, S.V. Starikov, I.S. Gordeev, Joint institute for high temperatures of RAS, Russia

[O7.14] Helium effects on Matrix and Grain Boundary Cohesion by using Instrumented Nano-Indentor I. Villacampa*1, J.C. Chen1, P. Spätig1, H.P. Seifert1, F. Duval2 1Paul Scherrer Institute, Switzerland, 2CEMHTI/CNRS Unicersité d’Orléans, France

[O5.14] Experimental and thermodynamic calculations results on corium subsystems in a pressurized water reactor A. Quaini*, C. Guéneau, B. Lindahl, S. Gossé, CEA Saclay, France

10:45-11:10 [O2.22 ] Transmission electron [O3.09] Molecular dynamics [O4.18] Modelling the influence [O7.15] Microstructural [O5.15] Characterization of core

microscopy analysis on oxidation of Nb precipitates in Zr-Nb alloys subjected to water corrosion Y. Matsukawa*1, S. Kitayama1, K. Murakami2, H.L. Yang2, K. Yoshida1, Y. Shinohara3, H. Muta4, T. Toyama1, S. Yamanaka4, H. Abe2 et al 1Tohoku University, Japan, 2The University of Tokyo, Japan, 3NDC, Japan, 4Osaka University, Japan, 5Kyushu University, Japan

simulation of thermal transport in UO2 with intrinsic defects and fission products C.R. Stanek, M.W.D. Cooper, D.A. Andersson*, X.Y. Liu Los Alamos National Laboratory, USA

of alloying additions on the behaviour of zirconium alloys B.D.C. Bell1, S.T. Murphy2, P.A. Burr3, J.M. Partezana4, R.W. Grimes1, M.R. Wenman*1 1Imperial College London, UK, 2University College London, UK, 3University of New South Wales, Australia, 4Westinghouse Electric Company, USA

characterization to assess the atypical embrittlement of an irradiated pressure vessel steel containing a large amount of hydrogen flakes S. De Vroey*1, B. Marini2, E. De Bruycker1, J. Stubbe1, P. Absil1, S. Goedseels1, 1EngieLab Laborelec, Belgium, 2Université Paris-Saclay, Belgium

melt/concrete interface region examined by light-concentrating heating technique A. Sudo*, M. Takano, A. Onozawa Japan Atomic Energy Agency, Japan



Track 3 Continued | Session Chair: Simon Phillpot, Markus Piro, Renaud Masson | Room: Joffre CD (Level 1)

Track 4 Continued | Session Chair: Pascal Bellon, Thomas Jourdan, Maria Jose Caturla Room: Sully 2 (Level 1)



11:40-12:05 [O2.23] Hydrogen plasma irradiation as an accelerated test of resistance to hydrogenation of light-water reactor materials L.B. Begrambekov*, A.E. Evsin, A.S. Kaplevsky, National Research Nuclear University MEPhI, Russia

[O3.10] Towards multiscale modelling of collective dislocation motion in uranium dioxide A.V. Lunev*, S.V. Starikov, A.Y. Kuksin Joint Institute for High Temperatures of the Russian Academy of Sciences, Russia

[O4.19] Oxygen atom diffusion in strained α-zirconium W. Xiao*, Y. Li State Nuclear Power Research Institute, China

[O7.16] Microstructure evolution in titanium stabilized Fe-15Ni-15Cr under ion irradiations at high temperature and high doses M. Kountchou*1,2, A. Courcelle1, B. Radiguet2, P. Pareige2 1Université Paris-Saclay, France, 2Université et INSA de Rouen, France

[O5.16] Investigation of Zy-4 cladding embrittlement mechanisms under simulated LOCA conditions R. Thieurmel*1,2, E. Pouillier1, A. Parrot1, A-F. Gourgues-Lorenzon2, J. Besson2, 1EDF R&D, France, 2Mines ParisTech, France

12:05-12:30 [O2.24] Stress corrosion cracking of SUS316L stainless steel in hydrogen dissolved hot pressurized water Y-J. Huang*, A. Kimura Kyoto University, Japan

[O3.11] Radiation induced fission gas diffusion in UO2 M.W.D. Cooper*1, C.R. Stanek1, J.A. Turnbull2, D.A. Andersson1, B.P. Uberuaga1, 1Materials Science and Technology Division, Los Alamos National Laboratory, USA, 2Independent Consultant, UK

[O4.20] Oxidation kinetics and hydrogen pickup mechanism in zirconium alloys A. Couet*1, A.T. Motta2 1University of Wisconsin-Madison, USA, 2Penn State University, USA

[O7.17] Quantification of Morphology of Zr-Hydride Precipitates for Evaluation of High-Burnup Cladding Mechanical Property A. Yamauchi*, K. Ogata, K. Kitano Secretariat of Nuclear Regulation Authority, Japan

[O5.17] High temperature oxidation behavior of zirconium alloy with nanostructured oxide layer in steam environment Y.J. Park*, J.W. Kim, S.O. Cho KAIST, Republic of Korea

12:30-12:55 [O2.25] Mechanical properties of recrystallized and stress-relieved Zircaloy-4 cladding tubes under biaxial stress conditions T. Mihara*, Y. Udagawa, M. Amaya, Japan Atomic Energy Agency, Japan

[O3.12] Atomic scale insights on the microstructure evolution of urania under irradiation A. Chartier*1, L. Van Brutzel1, C. Onofri1,2, C. Sabathier1,2 1CEA, DEN, DPC, France, 2CEA,DEN, DEC, France

[O4.21] Beryllium segregation and transport to basal and prismatic zirconium surfaces by first principles A. Jain*, D.R. Trinkle Univ. Illinois, Urbana-Champaign, USA

[O7.18] Post-irradiation Raman spectroscopy of fine-grained nuclear graphite A.A. Campbell*1, Y. Katoh1, M.A. Snead1, M.J. Lance1, K. Takizawa2 1Oak Ridge National Laboratory, USA, 2Tokai Carbon Co., Ltd., Japan

TBC- [O5.18] Behavior of the fission products (FPs) and fuel microstructure during the severe accident semi-analytical tests Vercors 2, 3 and 5 A. De Bremaecker*1, A. Leenaers1, M. Verwerft1, M. Barrachin2, R. Dubourg2, R. Ducher2 1SCK.CEN, Belgium, 2IRSN, France

12:55-13:55 Lunch Break | Room: Joffre 1 (Level 1) 13:55-14:35 [PS6] Material Modification and Nanostructuring by Swift Heavy Ions | Room: Pasteur (Entrance Level 1)

Norito Ishikawa, JAEA, Japan 14:35-14:40 Time to change rooms

Track 2 Continued | Session Chair: Arthur T. Motta, Mark Daymond, Jean Henry Room: Pasteur (Entrance Level 1)

Track 1 Continued | Session Chair: Stéphane Gossé, Emily Corcoran, Dario Manara | Room: Joffre CD (Level 1)




14:40-15:15 [T2.INV02] Effect of Ion-Irradiation Induced Defects on Dislocation Dynamics in Ni-based Alloy Using In-Situ TEM Pr. Djamel Kaoumi , University of South Carolina, USA

[T1.INV02] The peculiar chemistry of the nuclear fuel-sodium coolant interaction Anna Smith, Univ. Delft, The Netherlands

[T6.INV02] Phase transformation Induced by Irradiation in Complex Oxides Gaël Sattonnay, University Paris Sud, France

[T7.INV02] Microstructure and fuel performance analysis of U-Mo dispersion fuel irradiated at HANARO Ho Jin Ryu , Korea Advanced Institute of Science and Technology, Korea

[T5.INV02] Progress of R&D and remaining subjects on materials degradation in severe accidents Fumi Nagase, JAEA, Japan

15:15-15:40 [O2.26] Study of deformation mechanisms of zirconium alloys under and after irradiation M. Gaumé*1,2, F. Onimus1, F. Mompiou2, L. Dupuy1, S. Jublot-Leclerc3, 1CEA Saclay, France, 2CEMES, CNRS, France, 3CSNSM Orsay, France

[O1.07] Variability in YSZ and UO2 pellets produced via spark plasma sintering (SPS) J.D. Turner*, J. Buckley, M.J.J. Schmidt, T. Abram, The University of Manchester, UK

[O6.10] X-ray diffraction study of the Y2Ti2O7 pyrochlore disordering sequence under irradiation A. Soulié*1,2, D. Menut2, J-P. Crocombette1, A. Chartier3, J-L. Béchade1,2, N. Sellami4, G. Sattonnay5, I. Monnet6 1Université Paris-Saclay, France, 2CEA, DEN, Service de Recherches de Métallurgie Appliqué, Université Paris-Saclay, France, 3CEA, DEN, Service de la Corrosion et du Comportement des Matériaux dans leur Environnement, Université Paris-Saclay, France, 4Univ. Paris Sud, ICMMO-SP2M, France, 5Univ. Paris-Sud, France, 6 Université de Caen, France

[O7.19] Hot-cell materials properties testing to support development and qualification of U-10Mo LEU monolithic fuel J.I. Cole*, B.H. Rabin, J.A. Smith, C.L. Scott, B.C. Benefiel, E.D. Larsen, P.R. Lind, D.A. Sell Idaho National Laboratory, USA

[O5.19] SPS: A Unique Synthesis Tool For Safety of Nuclear Fuel Studies M. Cologna*1, M. Holzhäuser1, K. Popa1, V. Tyrpekl1, J-F. Vigier1, D. Salvato1,2, L. Luzzi2, D. Staicu1, E. De Bona1, G.D. Sorarù1, J. Somers1, T. Wangle1 et al 1EC JRC-ITU, Germany, 2Politecnico di Milano, Italy, 3Università di Trento, Italy

15:40-16:05 [O2.27] Understanding co-evolution of microstructure features in self ion irradiated HT9 to 650 dpa E. Getto*, G. Vancoevering, K. Sun, Z. Jiao, G.S. Was University of Michigan, USA

[O1.08] High temperature thermo- physical properties of UO2 T. Pavlov*1,2, L. Vlahovic1, D. Staicu1, R.J.M. Konings1, R.W. Grimes2, M.R. Wenman2 1Institute for Transuranium Elements, Germany, 2Imperial College London, UK

[O6.11] Temperature dependence of the radiation tolerance of nanocrystalline pyrochlores A2Ti2O7 (A = Gd, Ho and Lu) Y.Q. Wang*1, J. Wen1,2, C. Sun1, P.P. Dholabhai1, Y. Xia2, M. Tang1, D. Chen1, D.Y. Yang2, Y.H. Li2, B.P. Uberuaga1, 1Los Alamos National Laboratory, USA, 2Lanzhou University, China

[O7.20] Three dimensional synchrotron x-ray characterization of nuclear fuels M.A. Okuniewski*1,2, J. Hunter3, H. Sharma4, P. Kenesei4, R. Pokharel3, J-S. Park4, J. Almer4, A. Aitkaliyeva2, J. Harp2, B. Miller2 et al, 1Purdue University, USA, 2Idaho National Laboratory, USA, 3Los Alamos National Laboratory, USA, 4Argonne National Laboratory, USA

[O5.20] Use of novel high-density composite fuels for use in light water reactor application J.T. White1, A.W. Travis2, R. Pokharel1, J.T. Dunwoody1, A.T. Nelson*1, 1Los Alamos National Laboratory, USA, 2University of California, Irvine, USA

16:05-16:30 [O2.28] Mechanical and microstructural properties of neutron irradiated Fe-Cr-C alloys M.J. Konstantinovic*, W. Van Renterghem, M. Lambrecht, M.

[O1.09] In situ study of the first stage of MO2 (M = Ce, Th, U) microspheres sintering N. Clavier*1, G.I. Nkou Bouala1, J. Léchelle2, N. Dacheux1, R. Podor1

[O6.12] Thermo-physical properties of boron carbide under irradiation in fast neutron reactors D. Gosset*1,2, B. Kryger1, J.P.

[O7.21] A new tool for the PIE The high-resolution powder diffractometer of the MARS beamline at Synchrotron Soleil dedicated for the radioactive

[O5.21] Radiation tolerance of model, engineering grade, and commercial FeCrAl alloys K.G. Field*1, S.A. Briggs2, K.C. Littrell1, P.D. Edmondson1, M.N.

Chiapetto, L. Malerba Studiecentrum voor Kernenergie/Centre d'Etude de l'Energie Nucl\'eaire (SCK.CEN), Belgium

1University Montpellier, France, 2CEA/DEN/DEC/SESC/LLCC, France

Bonal1,2, 1CEA, France, 2Université Paris-Saclay, France

samples S. Schlutig*3,1, P.L. Solari1, H. Hermange1, N. Jonquères2, D. Leterme2, R. Boullon2, J. Noirot3 1Synchrotron Soleil, France, 2CEA Saclay, France, 3CEA Cadarache, France

Gussev1, Y. Yamamoto1, R.H. Howard1, X. Hu1, K. Sridharan2 1Oak Ridge National Laboratory, USA, 2University of Wisconsin - Madison, USA


Thursday 10 November 2016

09:00-09:40 [PS7] Research Reactor fuel R&D in Europe: 15 years of UMo dispersion fuel development| Room: Pasteur (Entrance Level 1) Sven Van de Berghe, SCK•CEN, Belgium

09:40-09:45 Time to change rooms Track 2 Continued | Session






09:45-10:10 [O2.29] Predicting macroscopic material properties from microstructures for functional nuclear materials Ll.M. Evans*1,2, E. Surrey1, L. Margetts2, 1Culham Centre for Fusion Energy, UK, 2University of Manchester, UK

[O1.10] Thermodynamic investigation of the Cr-O-U and Cr-O-Zr systems B. Lindahl*, A. Quaini, S. Gossé, T. Alpettaz, S. Poissonnet, P. Bonnaillie, C. Guéneau CEA Université Paris-Saclay, France

[O6.13] On the importance of correlated defect recombination in radiation effects studies S.J. Zinkle*1,2, R.E. Stoller1 1University of Tennessee, USA, 2Oak Ridge National Lab, USA

[O3.13] Combine granular materials behavior and fluid interactions: an attempt to model fuel dispersal during LOCA transients L. Amarsid1,2, F. Perales3, J.M. Ricaud*3, 1Université de Montpellier, France, 2Centre National de la Recherche Scientifique, France, 3Institut de Radioprotection et Sûreté Nucléaire, France

[O8.13] Mineral-like ceramic materials as matrix for radwaste. Technology for their obtaining by SPS method E. Potanina*1, D. Mikhailov1, M. Tokarev1, A. Orlova1, M. Boldin2, O. Belkin2, N. Sakharov2, A. Nokhrin2 1Department of Solid State Chemistry, Lobachevsky state university of Nizhni Novgorod, National Research University, Russia, 2National Research University, Russia

10:10-10:35 [O2.30] Defect processes in beryllides, Be12X where X = Ti, V, Mo or W M.L. Jackson*1,2, P.A. Burr3, R.W. Grimes1,1Imperial College London, UK, 2Culham Centre for Fusion Energy, UK, 3Australian Nuclear Science and Technology Organisation, Australia

[O1.11] New insight on the MO2+x-M3O8 domain of U-Am-O phase diagram E. Epifano*, R. Vauchy, F. Lebreton, A. Joly, C. Guéneau, P.M. Martin, R. Belin CEA, France

[O6.14] Oxide and carbide nanoparticles in ODS alloys irradiated with heavy ions of fission fragment energy V.A. Skuratov*1,2, A.S. Sohatsky1, J.H. O'Connell4, K. Kornieieva1, J.H. Neethling4, A.D. Volkov5, M. Zdorovets6,7, 1JINR, Dubna, Russia, 2National Research Nuclear University MEPhI, Russia, 3Dubna State University, Russia, 4NMMU, South Africa, 5Nararbaev University, Kazakhstan, 6Institute of Nuclear Physics, Kazakhstan, 7Ural Federal University, Russia

[O3.14] Modelling the fuel failure behaviour with a micromechanical approach in the HBS area C. Esnoul*1, R. Largenton1, J-C. Michel2, B. Michel3, C. Petry1, A. Bouloré3, 1EDF R&D, France, 2Laboratoire Mecanique et d'Acoustique, France, 3CEA Cadarache, France

[O8.14] Observations on flash sintering of UO2 A.M. Raftery*1, J.G. Pereira da Silva2, D.D. Byler1, J.A. Valdez1, D.A. Andersson1, B.P. Uberuaga1, C.R. Stanek1, K.J. McClellan1 1Los Alamos National Laboratory, USA, 2Technical University of Hamburg, Germany

10:35-11:00 [O2.31] Diffusion and clusters formation of helium in implanted boron carbide

[O1.12] Thermodynamics of soluble fission products caesium and iodine in the Molten Salt Reactor

[O6.15] Microstructure evolution in clf-1 steel and fe-cr model alloys by ion irradiation

[O3.15] Multiscale modelling of delayed hydride cracking M. Patel*, D.S. Balint, M.R.

[O8.15] Nitridation of dysprosium and zirconium metals in liquid cadmium

V. Motte*1,3, D. Gosset1, S. Doriot1, G. Gutierrez1, T. Sauvage2, N. Moncoffre2 1CEA, Université Paris-Saclay, France, 2CNRS, France, 3Université Lyon 1, France

E. Capelli*1, O. Beneš2, N. Vozarova2, R.J.M. Konings1,2, A.L. Smith1, P.R. Hania3, 1Delft University of Technology, The Netherlands, 2European Commission, Joint Research Centre, Institute for Transuranium Elements, Germany, 3NRG, The Netherlands

S. Huang*, S. Zhou, X. Jiang, Y. Su, J. Zhao Key Laboratory of Materials Modification by Laser, Ion and Electron Beams (Dalian University of Technology), China

Wenman, A.P. Sutton Imperial College London, UK

T. Sato*1, H. Hayashi1, H. Nakamura2, T. Omori2 1Japan Atomic Energy Agency, Japan, 2Toshiba Corporation, Japan







11:30-11:55 [O2.32] Behaviour of pre-stressed 14 and 19Cr ODS steels exposed to liquid lead-bismuth A. Hojna*1, H. Hadraba2, F. Di Gabriele1, R. Husak2, L. Rozumova1, P. Bublikova1 1Centrum vyzkumu Rez, Czech Republic, 2Institute of Physics of Materials, Czech Republic

[O1.13] Experimental investigations in the U-rich region of the U-Pu phase diagram B.R. Westphal*, S.X. Li Idaho National Laboratory, USA

[O6.16] 3-dimentional self-ordering loop lattice in tungsten irradiated with iron ions Z.X. Zhang*, E. Hasenhuetl, K. Yabuuchi, A. Kimura Kyoto University, Japan

[O3.16] Validation of microstructural evolution in ceria as predicted by MARMOT code H. Maruyama, S. Sulekar, M. Mehr, N. Strombom, Y. Yang, J.C. Nino* University of Florida, USA

[O8.16] Fabrication and Radiation Stability of Vanadate Apatite Waste Form F. Lu*1, J. Zhou1, T. Yao2, J. Lian2 1Louisiana State University, USA, 2Rensselaer Polytechnic Institute, USA

11:55-12:20 [O2.33] Low cycle fatigue behavior of 15-15Ti at 550 ºC in vacuum and LBE environments J.W. Chen*, Q.S. Wu, J. Xu, H.P. Mei, S.J. Liu, Q.Y. Huang Key Laboratory of Neutronics and Radiation Safety, Institute of Nuclear Energy Safety Technology, Chinese Academy of Sciences, China

[O1.14] Experimental Investigation and Assessment of the Phase Equilibria in the U-Ga and U-Al-Ga Systems C. Moussa1, A. Berche2, J. Barbosa2, M. Pasturel1, O. Tougait*3,2, B. Stepnik4 1CNRS, France, 2Université de Rennes1, France, 3Université de Lille1, France, 4AREVA NP, France

[O6.17] Dual-ion irradiation to emulate neutron-irradiated microstructure in ferritic-martensitic alloy T91 Z. Jiao1, S. Taller1, G. Vancoevering1, G.S. Was*1, K. Field2, C. Parish2, G. Yeli3, M. Moody3, D. Xu4 1University of Michigan, USA, 2Oak Ridge National Laboratory, USA, 3University of Oxford, UK, 4University of Tennessee, USA

[O3.17] Thermodynamics and diffusivity of point defects in (u,pu)n: model from the atomistic simulations A.Y. Kuksin*1,2, D.E. Smirnova1, S.V. Starikov1,2, A.V. Yanilkin1,2 1Joint Institute for High Temperatures of the Russian Academy of Sciences, Russia, 2Moscow Institute of Physics and Technology, Russia

[O8.17] Experimental studies on palladium samples aged under tritium M. Segard*1, S. Challet1, A. Fabre1, E. Leroy3, V. Paul-Boncour3, T. Charpentier2 1CEA, centre de Valduc, France, 2NIMBE - UMR CEA-CNRS 3685, France, 3CMTR / ICMPE, CNRS UMR 7182, France

12:20-12:45 [O2.34] Compatibility evaluation of candidate structural materials with liquid lead-bismuth for China LEAd-based Research Reactor Z.Z. Jiang*, S. Gao, C.J. Li, Q.Y. Huang,Institute of Nuclear Energy Safety Technology, Chinese Academy of Science, China

[O1.15] Revisiting thermodynamics and kinetic diffusivities of U-Nb with uncertainty quantification based on Bayes's theorem T. Duong*, R. Arroyave Texas A&M University, USA

[O6.18] Effect of neutron irradiation on thermally-aged cast austenitic stainless steels S. Chen*, Y. Miyahara, A. Nomoto, K. Nishida Central Reasearch Institute of Electric Power Industry, Japan

[O3.18] Simulations of void behaviour in UO2 using a phase-field model informed by equilibrium thermodynamics M.J. Welland, E.M. Tenuta, M.H.A. Piro*, Canadian Nuclear Laboratories, Canada

[O8.18] Aging embrittlement of spent nuclear fuels during long-term storage Y-S. Kim*1, K. Park2 1Korea Atomic Energy Reseracch Institute, Republic of Korea, 2Kyunghee University, Republic of Korea

12:45-13:45 Lunch Break | Room: Joffre 1 (Level 1) 13:45-14:25 [PS8] Spent nuclear fuel corrosion processes under long term interim storage and waste disposal conditions | Room: Pasteur (Entrance Level 1)

Christophe Jégou, CEA, France 14:25-14:30 Time to change rooms Track 2 Continued (14:40-16:20)

Session Chair: Arthur T. Motta, Track 1 Continued | Session Chair: Stéphane Gossé, Emily Corcoran,

Track 6 Continued (14:40-16:20) Session Chair: Kazuhiro Yasuda,

Track 3 Continued | Session Chair: Simon Phillpot, Markus

Track 8 Continued Session Chair: Stéphane Gin,

Mark Daymond, Jean Henry Room: Pasteur (Entrance Level 1)

Dario Manara (14:40-16:20) | Room: Joffre CD (Level 1)

Aurélien Debelle, Maik K. Lang Room: Sully 2 (Level 1)

Piro, Renaud Masson Room: Sully 3 (Level 1)

James Neeway, Ondrej Benes Room: Joffre 5 (Level 1)

14:30-15:05 [O2.35] 3D printing of 316L stainless steel for nuclear fusion application Y. Zhong*1, L-E. Rännar2, A. Koptyug2, S. Wikman3, L.F. Liu1, J. Olsen1, D.Q. Cui1, Z.J. Shen1 1Stockholm University, Sweden, 2Mid Sweden University, Sweden, 3Fusion for Energy, Spain

[O1.16] A method to estimate the standard entropy of mixed oxide compounds R.J.M. Konings*1, A.L. Smith2 1European Commission JRC-ITU, Germany, 2TU Delft, The Netherlands

[O6.19] Re-examination of ion irradiation as a credible tool to simulate neutron-induced void swelling F.A. Garner*1, J. Wang1, L. Shao1, M.B. Toloczko2, S.A. Maloy3, V.A. Pechenkin4, V.N. Voyevodin5 1Texas A&M University, USA, 2Pacific Northwest National Laboratory, USA, 3Los Alamos National Laboratory, USA, 4Institute of Physics and Power Engineering, Russia, 5Kharkov Institute of Physics and Technology, Ukraine

[T3.INV02] Simulation of fuel behaviour under irradiation: Basic research in support of the PLEIADES fuel performance codes Carole Valot, CEA, France

[T8.INV02] Molten salt electrochemistry for pyro processing of oxide fuel Pavel Soucek, ITU, Germany

15:05-15:30 [O2.36] Impact of stacking fault energy and ferrite content on strain hardening behavior of 316L stainless steel observed by in-situ time-of-flight neutron diffraction G. Meric de Bellefon*1, J-C. van Duysen2,3, K. Sridharan1 1University of Wisconsin, Madison, USA, 2EDF R&D, France, 3University of Tennessee, Knoxville, USA, 4University of Wisconsin Madison, USA

[O1.17] Thermochemical modeling of nuclear fuel and the effects of oxygen potential buffers H. Loukusa*, T. Ikonen, V. Valtavirta, V. Tulkki, VTT Technical Research Centre of Finland, Finland

[O6.20] Contribution of non-hardening mechanism into flux effect and radiation embrittlement of VVER-1000 RPV steels E.A. Kuleshova1,2, B.A. Gurovich1, Z.V. Bukina*1, D.A. Maltsev1, S.V. Fedotova1, A.S. Frolov1 1National Research Center, Kurchatov Institute, Russia, 2National Research Nuclear University MEPhI, Russia

[O3.19] Features of structure and phase transitions in pure uranium and u-mo alloys: atomistic simulation study S. Starikov*1,2, L. Kolotova1,2, A. Kuksin1,2, D. Smirnova1, V. Tseplyaev1,2 1Joint Institute for High Temperatures of the Russian Academy of Sciences, Russia, 2Moscow Institute of Physics and Technology, Russia

[O8.19] Corrosion of Ti3AlC2 MAX phase in molten LiCl-KCl eutectic D.J. Cooper*1, K.J. Abrams1, C.A. Jantzen1, H. Lambert1, T. Abram1, K.R. Whittle1, M.D. Ogden1, W.M. Rainforth1 1The University of Sheffield, UK, 2The University of Manchester, UK, 3The University of Liverpool, UK

15:30-15:55 [O2.37] Microstructural evolution of cold worked DIN 1.4970 (X10 CrNiMoTiB 15 15) steel after heat treatments at 600 and 800 °C N. Cautaerts*1,2, R. Delville1, E. Stergar1, D. Schryvers2, M. Verwerft1 1SCK-CEN, Belgium, 2University of Antwerp, Belgium

[O1.18] CALPHAD-based development of the “Thermodynamics of Advanced Fuels – International Database” (TAF-ID) C. Guéneau1, N. Dupin2, M. Bankhead3, T.M. Besmann*5, S. Gossé1, E. Corcoran6, J-C. Dumas1, R. Hania1, J.R. Kennedy14, M. Kurata7 et al, 1CEA, France, 2Calcul Thermodynamique, France, 3National Nuclear Laboratory, UK, 4NRG, The Netherlands, 5Univ. South Carolina, USA, 6Royal Military College of Canada, Canada, 7JAEA, Japan, 8KAERI, Republic of Korea, 9Canadian Nuclear Laboratories, Canada, 10CRIEPI, Japan, 11Delft Univ. of Technology, The Netherlands, 12Livemore National Laboratory, USA,

[O6.21] Behaviour of 14YWT nanostructured ferritic alloys under extremely high dose self ion irradiations E. Aydogan*1,2, N. Almirall3, J.G. Gigax2, L. Price2, D. Chen2, T. Chen2, O. Anderoglu1, S.A. Maloy1, L. Shao2, F.A. Garner2 et al, 1Los Alamos National Laboratory, USA, 2Texas A&M University, USA, 3University of California, Santa Barbara, USA, 4Case Western Reserve University, USA, 5Oak Ridge National Laboratory, USA

[O3.20] Phase-field simulation of the growth behaviour of reaction phases at UO2/β-Zr interface during heating process T. Ishikawa*1, Y. Tsukada2, T. Koyama2, M. Kurata3 1Nagoya Institute of Technology, Japan, 2Nagoya University, Japan, 3Japan Atomic Energy Agency (JAEA), Japan

[O8.20] Development of Helium Leak Detector for SCC of Welded Canister H. Takeda Central Research Institute of Electric Power Industry, Japan

13OECD/NEA, France, 14Idaho National Laboratory, USA

15:55-16:20 [O2.38] Sliding wear analysis of cobalt based alloys in nuclear reactor conditions: using experimental and finite element methods R. McCarron*1, D. Dini1, D. Stewart2, P. Shipway3 1Imperial College London, UK, 2Rolls Royce, UK, 3University of Nottingham, UK

[O1.19] Thermodynamic Modeling of Advanced Fuels and Cladding Compatibility M.J. Noordhoek*, T.M. Besmann University of South Carolina, USA

[O6.22] The role of dispersoids in determining the swelling resistance of various reactor structural alloys during ion irradiation to 500 dpa V. Voyevodin*1, A. Kalchenko1, Y. Kupriiyanova1, A. Nikitina2, M. Leonteva-Smirnova2, V. Ageev2, F. Garner3,4, M. Toloczko5, D. Hoeltzer6, S. Maloy7 1KIPT, Ukraine, 2Bochvar, Russia, 3MEPhI, Russia, 4Radiation Effects Consulting, USA, 5PNNL, USA, 6ORNL, USA, 7LANL, USA

[O3.21] Threshold displacement energy of alpha and gamma uranium B. Beeler*, Y. Zhang Idaho National Laboratory, USA

[O8.21] Electrochemistry of U and Th in several groups of ionic liquids M. Straka*, L. Szatmary UJV Rez, a.s., Czech Republic

16:20-16:25 Time to change rooms 16:25-17:05 JNM Award Invited Speaker-Bruce Pint | Room: Pasteur (Entrance Level 1) 17:05-17:30 NuMart Awards/Best Poster Awards/Young Researcher Awards/Closing Ceremony | Room: Pasteur (Entrance Level 1)

End of Conference

Documents

The Nuclear Materials Conference, 2016 – Oral Program · The Nuclear Materials Conference, 2016 – Oral Program . Sunday 6 November 2016 18:30-20:00 Registration | Room: Joffre