Poster Programme - elsevier.com · 4th Nuclear Materials Conference I Poster Programme A. Boulle*1,...

4th

Nuclear Materials Conference I Poster Programme

Poster Programme

Poster Session 1

Monday 7th November 2016 17:50-19:20

[P1.01] Validation Status of Multifunction Model for BWR Core Degradation on DF-4, QUENCH-06 and CORA experiments T. Okawa*, T. Nakajima, Regulatory Standard and Research Department, Secretariat of Nuclear Regulation Authority (S/NRA/R), Japan

[P1.02] Molecular dynamics simulations of high energy cascade in ordered alloys : defect production and subcascade division J-P. Crocombette*, L. Van Brutzel, D. Simeone, L. Luneville, CEA Saclay, Université Paris-Saclay, France

[P1.03] Drying Characteristics Of Simulated Debris In a Pretreatment Process For Dry Storage A. Nakayoshi*

1 ,2, S. Suzuki

1 ,2, N. Okamura

1 ,2, M. Watanabe

1 ,2, K. Koizumi

1 ,2,

1Japan atomic energy

agency, Japan, 2

International Research Institute for Nuclear Decommissioning, Japan

[P1.04] Annealing and creep behaviour at high temperature of a stabilised austenitic steel for Gen-IV nuclear power plants L. Mateus Freire*

1, 2, E. Piozin

1, A. Courcelle

1, A-F. Gourgues

2, T. Guilbert

1,

1CEA, France,

2PSL

Research University, France

[P1.05] Micro x-ray diffraction study on irradiated metallic fuels Y-S. Youn*

1, Y-S. Park

1, J-Y. Kim

1 ,2, Y-K. Ha

1,

1Korea Atomic Energy Research Institute, Republic of

Korea, 2

University of Science & Technology, Republic of Korea

[P1.06] Anisotropic Creep Behavior of Multi-pass Welded Joint of the Modified 9%CrMoV Steel F.Z. Xuan*, B. Yang, East China University of Science and Technology, China

[P1.07] Constraint effect on the creep fracture toughness of a Cr-Mo-V steel J.P. Tan*, F.Z. Xuan, G.Z. Wang, S.T. Tu, East China University of Science and Technology, China

[P1.08] Characterization of melt-solidified (U,Gd,Zr)O2-x as simulated corium debris K. Morimoto*

1 ,2, S. Hirooka

1 ,2, M. Akashi

1 ,2, M. Watanabe

1 ,2,

1Japan Atomic Energy Agency, Japan,

2International Research Institute for Nuclear Decommissioning, Japan

[P1.09] Intermediate results of HALDEN irradiation test of micro-cell UO2 pellet D.J. Kim*, K.S. Kim, J.H. Kim, J.S. Oh, J.H. Yang, Y.H. Koo, Korea Atomic Energy Research Institute, Republic of Korea

[P1.10] Study of the correlation between fuel engineering properties and point defects Y. MA*

1, P. Garcia

1, L. Desgranges

1, G. Baldinozzi

2, H.E. Fischer

3, D. Simeone

2,

1CEA CADARACHE,

France, 2

CEA Gif-sur-Yvette, France, 3

ILL Grenoble, France

[P1.11] Ultra-high temperature tensile properties of ODS steel cladding for evaluating severe accident Y. Yano*

1, T. Tanno

1, S. Ohtsuka

1, H. Oka

1, T. Inoue

1, S. Kato

1, T. Furukawa

1, T. Uwaba

1, T. Kaito

1, S.

Ukai2,


2Hokkaido university, Japan

[P1.12] Stability of various oxide particles in oxide dispersion strengthened (ODS) steels above 1473K N. Oono*

1, S. Ukai

1, T. Kaito

2, S. Ohtsuka

2, T. Torimaru

3, K. Sakamoto

3, S. Hayashi

4, A.

Kimura5,

1Hokkaido University, Japan,


3Nippon Nuclear Fuel

Development, Co., Ltd., Japan, 4

Tokyo Institute of Technology, Japan, 5

Kyoto University, Japan

[P1.13] Computational description of nanoscale precipitate in microalloyed steel during deformation based on finite element analysis L.J. Hu*, Q.F. Zhang, K. Liu, H.Y. Dong, Y.P. Xie, Shanghai University, China

[P1.14] Phase stability behavior in heavy ion-irradiated F/M steel HT9 C. Zheng

1, M.A. Auger

2, D. Kaoumi*

1,

1North Carolina State University, USA,

2University of Oxford, UK

[P1.15] Observation of molten CsI behavior on yttria-stabilized zirconia single crystals

4th


H. Ishii*1, K. Kurosaki

1 ,2, Y. Murakami

3, Y. Ohishi

1, H. Muta

1, M. Uno

3, S. Yamanaka

1 ,3,

1Osaka

University, Japan, 2

JST, PRESTO, Japan, 3

University of Fukui, Japan

[P1.16] Effects of boron on revaporization of iodine and cesium compounds in a severe accident condition S. Miwa*, M. Shinada, M. Osaka, Y. Maruyama, Japan Atomic Energy Agency, Japan

[P1.17] On-chip irradiation creep testing of copper films P. Lapouge

1, M. Coulombier

2, F. Onimus*

1, T. Pardoen

2, J-P. Raskin

2, Y. Bréchet

3,

1CEA, France,

2Université catholique de Louvain, Belgium,

3INPG, France

[P1.18] Radiation damage of refractory high-entropy alloys D.M. King

1 ,2, S.C. Middleburgh*

3, G. Thorogood

2, M. Blackford

2, M. Ionescu

2, G.R. Lumpkin

2, L.

Edwards2, M.B. Cortie

1,

1University of Technology Sydney, NSW 2007, Australia,

22ANSTO, Lucas

Heights, NSW 2234, Australia, 3

Westinghouse Electric Sweden AB, SE-721 63 Västerås, Sweden

[P1.19] A novel method for recording flow curves in proton irradiated material A.D. Smith*

1, M. Preuss

1, P.J. Withers

1, K. Wilford

2,

1University of Manchester, UK,

2Rolls-Royce plc,

UK

[P1.20] Assessment of stainless steel cladding behaviour under LOCA scenario using modified fuel performance code C. Giovedi*

1, A. Abe

2, D.S. Gomes

2, A.T. Silva

2, M.R. Martins

1,

1University of São Paulo, Brazil,

2Nuclear and Energy Research Institute, Brazil

[P1.21] Manufacturing options for uranium silicide accident tolerant fuel D.T. Goddard*, P. Durham, J.I. Paul, R. Logsdon, E.P. Vernon, D.P. Mathers, National Nuclear Laboratory, UK

[P1.22] Evaluation on oxidation behavior of nanocrystalline CrN deposited Zr-4 alloys at high temperature C-W. Shen*, K-P. Chang, F-Y. Ouyang, National Tsing Hua University, Taiwan

[P1.23] High temperature creep properties of ODS steel cladding for evaluating severe accident S. Kato

1, T. Furukawa*

1, Y. Yano

1, T. Tanno

1, S. Ohtsuka

1, T. Inoue

1, H. Oka

1, T. Kaito

1, S. Ukai

2, A.

Kimura3, S. Hayashi

4, T. Torimaru

5,


2Hokkaido University,

Japan, 3

Kyoto University, Japan, 4


Nippon Nuclear Fuel Development Co. Ltd., Japan

[P1.24] Phases and morphology in the simulated MCCI products prepared by arc melting method M. Takano*, A. Onozawa, A. Sudo, Japan Atomic Energy Agency, Japan

[P1.25] Experimental studies on Cs chemisorption on reactor structural materials and their behaviour at high temperature F.G. Di Lemma*, K. Nakajima, S. Yamashita, M. Osaka, JAEA, Japan

[P1.26] Characterization of Y2Ti2O7 as a coating material for fuel claddings Y. Seto*

1, H. Muta

1, Y. Ohishi

1, K. Kurosaki

1, S. Yamanaka

1 ,2, K. Sakamoto

3,

1Osaka university, Japan,

2Fukui university, Japan,

3Nippon Nuclear Fuel Development, Japan

[P1.27] The manufacture and characterisation of uranium oxide fuel containing silicon carbide and molybdenum for improved in-reactor performance and increased accident tolerance. J. Buckley*, J. Turner, T. Abram, University of Manchester, UK

[P1.28] Syntheses and characterizations of uranium carbide targets for new intense radioactive beams at ALTO J. Guillot*, B. Roussière, N. Barré-Boscher, S. Tusseau-Nenez, Université Paris Saclay, France

[P1.29] Determination of the local porosity and Young's modulus in irradiated uranium dioxide by high frequency acoustic microscopy M. Marchetti*

1 ,2, D. Laux

2 ,3, F. Cappia

1 ,4, T. Wiss

1, P. Van Uffelen

1, V.V. Rondinella

1, G. Despaux

2

,3,

1European Commission - Joint Research Centre - Institute for Transuranium Elements, Germany,

2University of Montpellier, France,

3CNRS, IES, France,

4Technische Universität München, Germany

[P1.30] Transient burst properties of ODS steel cladding for evaluating severe accident T. Inoue*

1, Y. Sekio

1, S. Ohtsuka

1, Y. Yano

1, T. Tanno

1, H. Oka

1, T. Furukawa

1, T. Kaito

1, T. Torimaru

2,

S. Hayashi3, A. Kimura

4, S. Ukai

5,


2Nuclear Fuel Development,

Japan, 3



Hokkaido University, Japan

[P1.31] Advanced X-ray Diffraction Techniques for the Study of the Microstructure of Irradiated Materials

4th


A. Boulle*1, M. Souilah

1, A. Debelle

2, H. Palancher

3, F. Garrido

2, P. Goudeau

4,

1SPCTS, CNRS,

Université de Limoges, France, 2

CSNSM, Univ. Paris-Sud, CNRS/IN2P3, France, 3

CEA, DEN, DEC, France,

4Institut Pprime, CNRS, Université de Poitiers-ENSMA, France

[P1.32] Quantification of αʹ precipitation in neutron-irradiated Fe-Cr-Al model alloys utilizing complementary SANS & APT techniques S.A. Briggs

1, P.D. Edmondson

2, K.G. Field*

2, Y. Yamamoto

2, K.C. Littrell

2, C.R. Daily

2, K.

Sridharan1,

1University of Wisconsin-Madison, USA,

2Oak Ridge National Laboratory, USA

[P1.33] Analysis of dislocation channeling in irradiated bcc materials using a crystal plasticity finite element framework A. Patra*

1, D.L. McDowell

2,

1Los Alamos National Laboratory, USA,

2Georgia Institute of Technology,

USA

[P1.34] Irradiation Embrittlement Analysis of A508-3 Steel in China Y. Lin*, W. Yang, Z.F. Tong, China Institute of Atomic Energy, China

[P1.35] Helium Effects on Void Swelling in RAFM steel for Fusion Application: Reaction Rate Theory Analysis Y.W. Watanabe*

1, K.M. Morishita

2, M.A. Ando

1, H.T. Tanigawa

1,

1National Institutes for Quantum

and Radiological Science and Technology, Japan, 2

Institute of Advanced Energy, Kyoto University, Japan

[P1.36] Grazing incident X-ray diffraction study of the synergy effect of irradiation and corrosion in Ni based alloy C. Yu*, J. Hou, R. Xie, Shanghai Institute of Applied Physics, China

[P1.37] Thermophysical properties of Ag-In liquid alloys T. Kondo*

1, Y. Ohishi

1, H. Muta

1, K. Kurosaki

1, S. Yamanaka

1 ,2,

1Osaka University, Japan,

2Fukui

University, Japan

[P1.38] Mechanical and thermal properties of bulk ZrSiO4 F. Nakamori*

1, Y. Ohishi

1, H. Muta

1, K. Kurosaki

1, K. Fukumoto

2, S. Yamanaka

1 ,2,

1Osaka University,

Japan, 2

University of Fukui, Japan

[P1.39] Mechanical Properties of Urania-Zirconia Solid Solutions withTetragonal and Monoclinic Structures H. Ikeuchi*

1 ,2, K. Yano

1 ,2, H. Ogino

1 ,2, J. Matsunaga

4 ,3,


2International Research Institute for Nuclear Decommissioning, Japan,


Development Co.Ltd, Japan, 4

Global Nuclear Fuel-Japan Co. Ltd, Japan

[P1.40] Molecular dynamics study on thermal-physical properties of liquid lead-17lithium alloy Y. Gao*

1, G. Raos

2, C. Cavallotti

1, M. Takahashi

2,

1Tokyo Institute of Technology, Japan,

2Politecnico

di Milano, Italy

[P1.41] The SPHERE irradiation experiment: comparison of irradiation performance of pellets and sphere-pac ma-bearing driver fuel S. van Til*

1, P.R. Hania

1, A.V. Fedorov

1, E. D'Agata

2, A. Cambriani

3, D. Freis

3, F. Delage

4,

1NRG, The

Netherlands, 2

JRC-IET, The Netherlands, 3

JRC-ITU, Germany, 4

CEA, France

[P1.42] Thermophysical Properties of Al2O3-ZrO2Molten Materials Measured by Aerodynamic Levitation Y. Ohishi*

1, F. Nakamori

1, H. Muta

1, K. Kurosaki

1, S. Yamanaka

1 ,2, F. Kargl

3,


2University of Fukui, Japan,

3German Aerospace Center (DLR e. V.), Germany

[P1.43] Evaluation of microstructural and mechanical changes in Zr-Nb alloys irradiated by high energy C ion irradiation H.L. Yang*

1, S. Kano

1, Y. Matsukawa

2, Z.G. Duan

2, H. Abe

1,

1The University of Tokyo, Japan,

2Tohoku

University, Japan

[P1.44] Characterization by APT and TEM of Xe nano-bubbles in CeO2 C. Perrin-Pellegrino

1 ,4, M. Dumont*

1 ,4, M.F. Keita

1, T. Neisius

1 ,5, G. Carlot

3, P. Maugis

1 ,4,

1Aix-

Marseille University, France, 2

CNRS, France, 3

CEA, France, 4

IM2NP, France, 5

CIMPACA, France

[P1.45] Thermal conductivity of Zr-Fe liquid alloy Y. Daijo*

1, Y. Ohishi

1, T. Kondo

1, H. Muta

1, K. Kurosaki

1, S. Yamanaka

1 ,2,


2University of Fukui, Japan

4th


[P1.46] Silicide/silicate coatings on zirconium alloys for improving the high temperature corrosion resistance B. Sartowska*

1, W. Starosta

1, M. Barlak

2, L. Walis

1, M. Milkowska

1,

1Institute of Nuclear Chemistry

and Technology, Poland, 2

National Institute for Nuclear Research, Poland

[P1.47] Phase Change of The Suimulated MCCI Debris at High Temperatures under Reductive and Oxidative Atmospheres N. Sato*

1, D. Akiyama

1, A. Kirishima

1, T. Sasaki

2,

1Tohoku University, Japan,

2Kyoto University, Japan

[P1.48] Phase state estimation of metallic inclusions in simulated corium debris M. Akashi*

1 ,2, K. Morimoto

1 ,2,


2International Research

Institute for Nuclear Decommissioning, Japan

[P1.49] Investigating the potential of MAX phases as accident tolerant fuel (ATF) cladding T. Galvin*

1, N.C. Hyatt

1, W.M. Rainforth

1, I.M. Reaney

1, D. Shepherd

2,

1University of Sheffield, UK,

2National Nuclear Laboratory, UK

[P1.50] Effects of injected interstitials and of the surface during 10 MeV Fe ion irradiation in 304 austenitic steels B. Michaut

1, J. Malaplate

1, T. Jourdan*

2, A. Renault-Laborne

1, F. Sefta

3, B. Décamps

4,

1CEA - DEN-

Service de Recherches Métallurgiques Appliquées, France, 2

CEA - DEN-Service de Recherches de Métallurgie Physique, France,

3EDF R&D, France,

4CNRS- CSNSM, France

[P1.51] Nanoscale-structures and magnetic properties of neutron and ion irradiated Fe-Cr binary alloys Y. Kamada*

1, T. Kabutomori

1, J.N. Mohapatra

1, S. Kobayashi

1, H. Watanabe

2,

1Iwate University,

Japan, 2

Kyushu University, Japan

[P1.52] Vacancy formation in oxidised zirconium J. Heikinheimo*, S. Ortner, I. Makkonen, J. Kujala, F. Tuomisto, Aalto University, Finland

[P1.53] Mn, Ni and Cu segregation in Fe using scalable parallel Monte Carlo algorithm M.I. Pascuet

1 ,2, E. Martinez

3, L. Malerba*

2,

1CONICET, Argentina,

2SCK-CEN, Belgium,

3LANL, USA

[P1.54] Tritium permeability in FeCrAl-ODS ferritic steel without oxide scales K. Sakamoto*

1, M. Hirai

1, K. Goto

2, T. Otsuka

2, S. Yamashita

3,

1Nippon Nuclear Fuel Development

Co., Ltd., Japan, 2

Kyushu University, Japan, 3

Japan Atomic Energy Agency, Japan

[P1.55] Oxygen effect on steam oxidation resistance of Zr-added FeCrAl-ODS steels at 1473 K S. Ukai*

1, Y. Shizukawa

1, N. Oono

1, S. Hayashi

2, K. Sakamoto

3, T. Torimaru

3, T. Kaito

4, S. Ohtsuka

4, A.

Kimura5,


2Tokyo Institute of Technology, Japan,


Development Co. Ltd., Japan, 4

Japan Atomic Energy Agency, Japan, 5

Kyoto University, Japan

[P1.56] Application of a material constitutive model for austenitic stainless steels to an irradiated hexagonal block P. Glabeck*

1 ,2, A. Barbu

3, D. Brimbal

1, S. Chapuliot

1, M. Coret

2, K. Fleurisson

1, L. Fournier

1, L.

Stainier2,

1Areva NP, France,

2Ecole Centrale de Nantes, France,

3Alain Barbu Consultant, France

[P1.57] High-temperature steam oxidation of FeCrAl-ODS ferritic steels up to 1673 K K. Sakamoto*

1, T. Torimaru

1, S. Ukai

2, N. Oono

2, T. Kaito

3, A. Kimura

4, S. Hayashi

5,

1Nippon Nuclear

Fuel Development Co., Ltd., Japan, 2

Hokkaido Univ., Japan, 3

Japan Atomic Energy Agency, Japan,

4Kyoto Univ., Japan,

5Tokyo Institute of Technology, Japan

[P1.58] Influence of concrete inhomogeneity on radiation shielding properties calculated using Monte Carlo simulations D.B. Tefelski

1, T. Piotrowski*

1, M. Mazgaj

1, K. Tyminska

2, M.A. Gryzinski

2, P. Wlodarczyk

1,

1Warsaw

University of Technology, Poland, 2

National Centre for Nuclear Research, Poland

[P1.59] The effects of applying stress on defect formation process in face-centred-cubic metals Y. Yang*, T. Okita, M. Itakura, University of tokyo, Japan

[P1.60] Behaviour of a self-interstitial-atom dislocation loop in the periphery of an edge dislocation and its dependence on stacking fault energy in face-centred-cubic metals S. Hayakawa*

1, T. Okita

1, M. Aichi

1, M. Itakura

2,

1The University of Tokyo, Japan,

2Japan Atomic

Energy Agency, Japan

[P1.61] Molecular dynamics study of the He properties in the Fe-Ni-Cr alloys A. Jelea, Institut de Radioprotection et de Sûreté Nucléaire (IRSN), France

4th


[P1.62] Development of Erosion Evaluation Model Based on a Thermo-Chemical Reaction between Molten Debris and Refractory Material S. Matsushita*, M. Nojima, Y. Maruno, Hitachi, Ltd., Japan

[P1.63] Thermal ageing behaviour of aluminium containing duplex stainless steels, possible accident resistant fuel cladding materials H. Kim*, J.W. Heo, S. Hong, C. Jang, KAIST, Republic of Korea

[P1.64] Internal stresses and structural evolutions in Zr alloys during oxidation at high temperature and subsequent cooling R. Guillou

1, M. Le Saux

1, J.C. Brachet*

1, T. Guilbert

1, D. Menut

1, C. Toffolon-Maclet

1, D.

Thiaudière2,

1DEN-Service de Recherches Métallurgiques Appliquées (SRMA), CEA, Université Paris-

Saclay, F-91191, Gif-sur-Yvette, France, France, 2

Synchrotron SOLEIL, Gif-sur-Yvette, France, France

[P1.65] Molecular dynamics simulations to evaluate the effects of stacking fault energy on the interaction between a screw dislocation and a self-interstitial-atom type Frank loop in FCC metals T. Okita*

1, Y. Hayashi

1, K. Doihara

1, K. Suzuki

1, M. Itakura

2,

1the University of Tokyo, Japan,

2Japan

Atomic Energy Agency, Japan

[P1.66] Transport process and radiation swelling modeling in TiN/a-Si3N4 nanocomposite V.V. Uglov*

1 ,2, G.E. Remnev

2, I.V. Safronov

1 ,3, N.N. Dorozhkin

1, N.T. Kvasov

1 ,2, V.I. Shymanski

1 ,2, E.

Demir4,

1Belarusian State University, Belarus,

2Tomsk Polytechnic University, Russia,

3Research

Institute for Nuclear Problems of Belarusian State University, Belarus, 4

Istanbul Technical University, Turkey

[P1.67] Fe/Cr phase decomposition behaviour of FeCrAl-ODS ferritic steels A. Kimura*

1, Z. Zhang

1, P. Song

1, W. Han

1, K. Yabuuchi

1, P. Dou

1, S. Ukai

2, N. Oono

2, S. Hayashi

3, T.

Kaito4, T. Torimaru

5,

1Kyoto University, Japan,


3Tokyo Institute of

Technology, Japan, 4


Nuclear Fuel Development, Japan

[P1.68] Diffusion study after swift heavy ion irradiation of indium implanted in glassy carbon E.G. Njoroge*

1, C.C. Theron

1, T.T. Thulane

1, J.B. Malherbe

1, V.A. Skuratov

2, E. Wendler

3,

1University

of Pretoria, South Africa, 2

Joint Institute for Nuclear Research, Russia, 3

Institut für Festkörperphysik, Friedrich-Schiller-Universität Jena, Germany

[P1.69] A new look on irradiated fuels at the CEA Cadarache I. ZACHARIE-AUBRUN*

1, T. BLAY

1, C. CISZAK

1, C. CAGNA

1, S. CHALAL

2,

1CEA, France,

2CARL ZEISS,

France

[P1.70] Annealing of SiC implanted at room temperature after swift heavy ion irradiation at room temperature and 500 °C T.T. Hlatshwayo, J.H. O’Connell, V.A. Skuratov*, E. Wendler, E.G. Njoroge, M. Mlambo, J.B. Malherbe, University of Pretoria, South Africa

[P1.71] Parameter free DFT+U method for efficient modelling of nuclear materials G. Beridze*

1, P.M. Kowalski

1, Y. Li

1, E. Alekseev

1, B. Xiao

2, P. Kegler

1, R. Baker

3, G.L. Murphy

4, B.J.

Kennedy4, D. Bosbach

1,

1Forschungszentrum Juelich, Germany,

2Helmholtz-Zentrum Dresden-

Rossendorf, Germany, 3

University of Dublin, Ireland, 4

University of Sydney, Australia

[P1.72] Computer simulations of radiation damage and defect recombination kinetics in sapphire A.I. Popov*

1, Y. Zhukovskii

1, E. Kotomin

1, A. Platonenko

1, S. Piskunov

1, V. Kuzovkov

1, A. Lushchik

2, R.

Vila3,

1Institute of Solid State Physics, University of Latvia,8 Kengaraga, Riga, Latvia,

2Institute of

Physics, University of Tartu, W.Ostwald Str. 1, 50411 Tartu, Estonia, 3

CIEMAT, Av Complutense 40, 28040 Madrid, Spain

[P1.73] Diffusion Of Implanted Europium In Glassy Carbon M.F. Kenari*, O.S. Odutemowo, J.M. Nel, J.B. Malherbe, T.T. Thulani, University of Pretoria, South Africa

[P1.74] Radiation effects in high-temperature YBCO superconductors with high energy protons for space radiation environments S. Wang*

1, F. Li

1, X. Le

1, L. Jiang

2, X. Ou

2,

1Beihang University, China,

2Beijing Institute of Spacecraft

Engineering Environment, China

[P1.75] Effects of ion irradiation on the magnetic properties of austenitic stainless steels for use in

4th


Tokamak fusion reactors T. Davis

2, C. Cooper

2, B.J. Connolly*

1 ,2,


2University of Birmingham, UK

[P1.76] Effect of substrate surface preparation on corrosion performance of multilayer (TiN, TiAlN) coatings E. Alat*

1, A.T. Motta

1, R.J. Comstock

2, J.M. Partezana

2, D.E. Wolfe

1,

1The Pennsylvania State

University, USA, 2

Westinghouse Electric Co., USA

[P1.77] High Temperature Oxidation Behavior of Liquid Phase Sintered Silicon Carbide Ceramics during Hydrothermal Exposure K.Y. Lim*

1, Y.S. Na

1, S.J. Lee

1, Y.W. Kim

2, W.J. Kim

3,

1KEPCO Nuclear Fuel, Republic of Korea,

2University of Seoul, Republic of Korea,

3KAERI, Republic of Korea

[P1.78] Intergranular stress distributions in polycrystalline aggregates of irradiated stainless steel J. Hure

1, S. El Shawish*

2, L. Cizelj

2, B. Tanguy

1,

1CEA, France,

2Jožef Stefan Institute, Slovenia

[P1.79] Investigating the effect of in-situ proton irradiation on the microstructure of zirconium oxide F. Baxter*

1, A. Garner

1, P. Frankell

1, A. Cole-Baker

2, M. Preuss

1,


2Rolls-Royce Plc, UK

[P1.80] High Temperature Steam Oxidation Behavior of Accident-Tolerant FeCrAl and FeCr Cladding Alloys B.A. Pint*, K.A. Unocic, Y. Yamamoto, K.A. Terrani, Oak Ridge National Laboratory, USA

[P1.81] Small-angle neutron scattering characterisation of radiation induced precipitation of RPV steels: effect of copper alloying additions and ion irradiation temperature S. Samothrakitis

2, C. Cooper

2, M. Laver

2, B.J. Connolly*

1 ,2,

1Univerity of Manchester, UK,

2University

of Birmingham, UK

[P1.82] Vaporization and deposition of cesium dimolybdate on Platinum in humid condition T.M.D. DO*

1, S. SUJATANOND

2, T. OGAWA

1 ,3,

1Nagaoka University of Technology, Japan,

2Thammasat University, Thailand,

3Japan Atomic Energy Agency, Japan

[P1.83] Spatially Resolved Measurement of Thermal Transport in Nuclear Fuels M. Khafizov*

1, Y. Wang

1, V. Chauhan

1, M.F. Riyad

1, D.H. Hurley

2,

1The Ohio State University, USA,

2Idaho National Laboratory, USA

[P1.84] Preliminary study on the tribological compatibility of surface-treated spacer grids for accident-tolerant fuel Y-H. Lee, D-J. Park*, I-H. Kim, H-G. Kim, J-H. Yang, Korea Atomic Energy Research Institute, Republic of Korea

[P1.85] Application of selective area laser deposition to the manufacture of SiC-SiC composite nuclear fuel cladding R. Neall*

1, T.J. Abram

1, M. Goodfellow

2,


2Rolls Royce Ltd, UK

[P1.86] Thermodynamic modelling of Cr-Nb-Sn-Zr system P. Lafaye*

1 ,2, J.C. Crivello

2, C. Toffolon

1, J.M. Joubert

2,

1CEA Saclay, France,

2CNRS, France

[P1.87] On the applicability of correlation empirical formula between tensile strength and hardness in irradiated Zr-based alloys S. Kano*

1, H.L. Yang

2, K. Murakami

2, H. Abe

2,

1Department of Nuclear Engineering and

management, Japan, 2

Department of Nuclear Engineering, Japan

[P1.88] Combining spatially resolved electron energy loss spectroscopy experiments with atomistic simulations to determine helium density in nanometric bubbles M-L. David, J. Dérès, M-F. Beaufort, L. Pizzagalli*, Institut Pprime, France

[P1.89] Effect of heavy ion irradiation on thermodynamically equilibrium Zr-Excel alloy H. YU

1, J. Liang

1 ,3, Z. Yao*

1, M. Kirk

2, M. Daymond

1,

1Department of Mechanical and Materials

Engineering, Queen’s University, Canada, 2

Material Science division, Argonne National Laboratory, USA,

3College of Science, Guangxi University for Nationalities, China

[P1.90] Investigation of the oxidation behaviour of thorium- uranium mixed oxides under controlled oxidation experiments M. Saoudi*

1, J.R. Hayes

2, A.P. Grosvenor

2, J. Mouris

1, T. Do

1,

1Canadian Nuclear Laboratories Limited

(CNL), Chalk River, Ontario, Canada, 2

Department of Chemistry, University of Saskatchewan, Saskatoon, Canada

4th


[P1.91] X-ray absorption spectroscopy and advanced microscopy study of fission products in SiC from irradiated TRISO fuel R.L. Seibert

1, C.M. Parish

2, P.D. Edmondson

2, K.A. Terrani*

2, J. Terry

1,

1Illinois Institute of

Technology, USA, 2

Oak Ridge National Laboratory, USA

[P1.92] First approach of the ability to pressing and sintering of lanthanide oxides with controlled morphology S. Chaigne*

1 ,2, A. Maître

1, R. Boulesteix

1, B. Arab-Chapelet

2, T. Delahaye

2,

1Laboratoire Science des

procédés Céramiques et de Traitements de Surface, UMR CNRS 7315, 12 rue Atlantis, 87068 Limoges, France,

2Laboratoire de Conversion des Actinides et de Radiolyse, CEA MARCOULE, 30207 Bagnols-

sur-cèze, France

[P1.93] Experimental assessment of solid/liquid equilibria in corium subsystems by laser heating L. Soldi

1 ,2, S. Mastromarino

1 ,3, D. Robba

1, L. Luzzi

2, A. Ciccioli

4, D. Bottomley

1, A. Seibert

1, E. Kassim

1,

D. Prieur1, D. Manara*

1,

1European Commission, Germany,

2Politecnico di Milano, Italy,

3Delft

University of Technology, The Netherlands, 4

Università La Sapienza, Italy

[P1.94] The effect of carbon (C) ion irradiation on the electrical properties of copper (Cu) film P.P. Wang

1, J.L. Du

1, E.G. Fu*

1, X.J. Wang

2,

1State Key Laboratory of Nuclear Physics and Technology,

Peking University, China, 2

State Key Laboratory of Advanced Optical Communication Systems and Networks, Peking University, China

[P1.95] TGA-QMS-water vapor measurements of zircaloy and steel E. Post*

1, T. Choucroun

1,

1NETZSCH Geraetebau GmbH, Germany,

2NETZSCH Geraetebau GmbH

Analyses & Tests, France

[P1.96] An X-ray diffraction study of the neutron irradiation effects on nuclear graphite Y.H. Jin*

1 ,2, Z. Zhou

4, K. Yoshida

2, Z.C. Li

1, T. Maruyama

1, T. Yano

2,

1State Key Lab of New Ceramic

and Fine Processing, Key Laboratory of Advanced Materials (MOE), School of Materials Science & Engineering, Tsinghua University, Beijing 100084, China,

2Laboratory for Advanced Nuclear Energy,

Tokyo Institute of Technology, 2-12-1, O-okayama, Meguro-ku, Tokyo 152-8550, Japan, 3

Institute of Nuclear and New Energy Technology, Tsinghua University, Beijing (100084), China,

4Delft University

of Technology, Faculty of Applied Sciences, Mekelweg 15, 2629 JB Delft, The Netherlands

[P1.97] Microstructural Changes in Irradiated U-7Mo/Al Alloy MatRiX Dispersion Fuel During Exposure to Temperatures up To 500˚C D. Keiser, Jr., J. Gan, J. Jue, B. Miller, A. Robinson, J. Madden, F. Rice, J. Cole*, Idaho National Laboratory, USA

Poster Session 2 Tuesday 8th November 2016

16:20-17:50

[P2.01] Synchrotron x-ray diffraction study of ZrH dissolution and precipitation kinetics in Zr-2.5%Nb O.V. Shiman*

1, M. Daymond

1, E. Tulk

2,

1Queen’s University, Canada,

2Kinectrics Inc., Canada

[P2.02] Defects, microstructures tailoring and properties of ZrC ceramics for advanced nuclear systems X.G. Wang, Shanghai Institute of Ceramics, Chinese Academy of Sciences, China

[P2.03] Study of carbide composites and their interfaces for Generation IV nuclear reactors T. kwamman*

1, K. Abrams

1, M. Rainforth

1, K. Whittle

2,

1University of Sheffield, UK,

2University of

Liverpool, UK

[P2.04] Investigation of gas bubble nucleation and growth behaviours in a Xe ion implanted single crystal Mo D. Yun*

1, J. Rest

2, Y. Du

1, Y. Gao

1,

1Xi'an Jiaotong University, China,

2Argonne National Laboratory,

USA

[P2.05] The synthesis and analysis of WxTaTiVCr alloys for high temperature and plasma facing applications O.A. Waseem*, S.S. Kim, S.H. Hong, H.J. Ryu, Korea Advanced Institute of Science and Technology,

4th


Republic of Korea

[P2.06] Computation of stacking fault energies in uranium dioxide using variable charge empirical potentials A. Soulié*

1, J-P. Crocombette

1, F. Garrido

2,

1CEA-SRMP, Gif-sur-Yvette, France,

2UPS-CSNSM, Orsay,

France

[P2.07] Pulse modulation spraying technology to produce ceramics materials for fusion and fission reactor B. Gutman, Nassau Community College, USA

[P2.08] Preparation of tritium permeation barrier consisting of titanium by pack cementation method Y. Wang*, D. Liu, S. Feng, Y. Zhang, T. Ouyang, X. Fang, J. Suo, Huazhong University of Science and Technology, China

[P2.09] Evolution of Oxides and Carbides in Oxide Dispersion Strengthened Alloy 617 at Elevated Temperatures and Their Effect on Tensile Properties Y.B. Chun*

1, X. Mao

2, C.H. Han

1, J. Jang

1,

1Korea Atomic Energy Research Institute, Republic of Korea,

2Institute of Nulcear Energy Safety Technology, China

[P2.10] Use of 3D laue spectroscopy to study oxide induced strains and stresses in zircaloy-4 B.M. Ensor*

1, A.T. Motta

1, D.J. Spengler

2, J.R. Seidensticker

2, R. Bajaj

2, W. Liu

3, R. Barabash

4,

1The

Pennsylvania State University, USA, 2

Bechtel Marine Propulsion Corporation, USA, 3

Argonne National Laboratory, USA,

4Oak Ridge National Laboratory, USA

[P2.11] Three scales simulations of MOX fuel rods behaviour under irradiation R. Masson*

1, M.B. Seck

2, A. Boulore

1, V. Blanc

1, L. Noirot

1, R. Largenton

3, M. Garajeu

2,

1CEA, France,

2LMA-CNRS, France,

3EDF, France

[P2.12] Development of tritium permeation barrier coating on RAFM steel for CN HCCB TBM in CIAE Y. Xiaoming*, Y. Hongguang, Z. Qin, Z. Weiwei, China Institute of Atomic Energy, China

[P2.13] Oxidation and surface segregation of chromium and silicon in Fe-Cr-Si alloys studied by Mössbauer and X-ray photoelectron spectroscopy R. Idczak*, K. Idczak, R. Konieczny, University of Wroclaw, Poland

[P2.14] Precipitation of grain boundary carbides in Inconel Alloys 600 and 690 after grain boundary engineering H. Li*, S. Xia, W.Q. Liu, B.X. Zhou, Shanghai University, China

[P2.15] The cause of enhanced resistance to primary water stress corrosion cracking of thermally treated Alloys 600/690 over solution-annealed ones Y-S. Kim*, S-S. Kim, Korea Atomic Energy Reseracch Institute, Republic of Korea

[P2.16] Creep crack growth behavior of CLAM steel at 500°C and 550°C Y.Y. Zhao*, G. Xu, B. Huang, S.J. Liu, Q.Y. Huang, Key Laboratory of Neutronics and Radiation Safety, Institute of Nuclear Energy Safety Technology, Chinese Academy of Science, China

[P2.17] Etched surface of CVTD Single Crystal Tungsten Coating after Serving at High Temperature H.T. Huang*, J.P. Zheng, Y.F. Wei, China Institute of Atomic Energy, China

[P2.18] Fabrication and Characterization of Advanced Radiation Resistant ODS Steel Components for Next Generation Nuclear Systems S. Noh*, S.H. Kang, T.K. Kim, Korea Atomic Energy Research Institute, Republic of Korea

[P2.19] Miniaturised creep testing of structural materials for fusion reactors M. Gorley*

1, B. Wynne

1 ,2, E. Surrey

1,

1UK Atomic Energy Authority, UK,

2Sheffield University, UK

[P2.20] Damage characterization of displacement cascades in (U,Pu)O2 fuels by MD simulations H. Balboa*, L. Van Brutzel, CEA, France

[P2.21] Thermodynamic Calculations in Multi-physics Nuclear Fuel Codes M.H.A. Piro*

1, S. Simunovic

2, M.J. Welland

1, T.M. Besmann

3,

1Canadian Nuclear Laboratories,

Canada, 2

Oak Ridge National Laboratory, USA, 3

University of South Carolina, USA

[P2.22] Development of 3D finite element module for simulation of pellet-cladding mechanical interaction H.C. KIM*

1, Y.S. YANG

1, S.K. SEO

2,

1Korea Atomic Energy Research Institute, Republic of Korea,

2Korea Advanced Institute of Science and Technology, Republic of Korea

[P2.23] Hydrogen diffusivity in oxide layers of Zr-alloy formed in air and steam

4th


T. Kato*1, I. Takagi

1, K. Sakamoto

2, M. Aomi

3,

1Kyoto University Graduate, Japan,

2Nippon Nuclear

Fuel Development, Co. Ltd., Japan, 3

Global Nuclear Fuel Japan. Co. Ltd., Japan

[P2.24] Recent progress of beryllides R&D as advanced neutron multipliers for DEMO fusion reactors M. Nakamichi*, J-H. Kim, National Institutes for Quantum and Radiological Science and Technology, Japan

[P2.25] Assessment of the evolution of fuel thermal conductivity in metallic U-19Pu-10Zr fuels with burnup via a finite-element based computer simulation Y. Gao*, Y. Du, J. Liu, W. Sun, B. Zhang, D. Yun, Xi'an Jiaotong University, China

[P2.26] Investigation on Ti3SiC2 Interphase Coated by Eletrophoretic Deposition in SiCf/SiC Composite H-G. Lee*, D.J. Kim, J.Y. Park, W-J. Kim, Korea Atomic Energy Research Institute, Republic of Korea

[P2.27] Finite element modelling of pellet-clad interaction in nuclear fuel T.A. Haynes*, M.R. Wenman, Imperial College London, UK

[P2.28] Nanoindentation of Zr, ZrO2 and ZrO2/Zr by molecular dynamics simulation Z. Lu

1, A. Chernatynskiy

2, M.J. Noordhoek

3, S.B. Sinnott

4, S.R. Phillpot*

1,

1University of Florida, USA,

2Missouri University of Science and Technology, USA,

3University of South Carolina, USA,

4Pennsylvania State University, USA

[P2.29] Mechanical property degradation due to thermal aging in cast austenitic stainless steels T.S. Byun*

1, T.G. Lach

1, Y. Yang

2, C. Jang

3,

1Pacific Northwest National Laboratory, USA,

2Oak Ridge

National Laboratory, USA, 3

Korea Advanced Institute and Technology, Republic of Korea

[P2.30] Deformation-Induced Martensitic Transformation in 304 Stainless Steel using In-situ and Ex-situ TEM characterization D. Kaoumi*

1, J. Liu

1, F.L. Paul

2,

1North Carolina State University, USA,

2Phelma, France

[P2.31] Influence of milling atmosphere on precipitation behavior in MA/ODS ferritic steels N.Y. Iwata*

1, S. Noh

2, Y. Ha

3, A. Kimura

4,

1MSE, National Institute of Technology, Kurume College,

Fukuoka, Japan, 2

Korea Atomic Energy Research Institute, Daejeon, Republic of Korea, 3

Nuclear Safety Research Center, Japan Atomic Energy Agency, Ibaraki, Japan,

4Institute of Advanced Energy,

Kyoto University, Kyoto, Japan

[P2.32] Fabrication and characterizations of crushed titanium-beryllium intermetallic compounds J-H. Kim*, M. Nakamichi, National Institutes for Quantum and Radiological Science and Technology, QST, Japan

[P2.33] Microstructural study of 15-15 Ti stabilized stainless steel SFR fuel cladding H.K. Namburi*

1, R. Delville

2, P. Halodova

1, D. Marusakova

1, P. Bublikova

1,

1Centrum výzkumu Rež s.

r. o, Czech Republic, 2

SCK•CEN, Belgium

[P2.34] Fuel cladding microstructure under LOCA conditions J. Krejci*

2, V. Vrtilkova

1, J. Kabatova

1, A. Pribyl

1, P. Gajdos

1, D. Rada

1, J. Sustr

1,

1UJP Praha a.s., Nad

Kamínkou 1345, 156 10 Praha - Zbraslav, Czech Republic, 2

FNSPE, CTU in Prague, Department of Nuclear Reactors, V Holešovičkách 2, 180 00 Prague, Czech Republic

[P2.35] Modeling of the effective elastic behavior of nanoporous materials with spherical and ellipsoidal in shape bubbles: application to irradiated uranium dioxide X. HALLER

1 ,2, Y. MONERIE*

3 ,2, S. PAGANO

3 ,2, P-G. VINCENT

1 ,2,

1Institut de Radioprotection et de

Sûreté Nucléaire, France, 2

Laboratoire de Micromécanique et Intégrité des Structures, IRSN-CNRS-UM, France,

3Laboratoire de Mécanique et Génie Civil, Université de Montpellier, CNRS, France

[P2.36] Analysis of the stress-strain state effect of the zirconium alloy claddings on the distribution of hydrides G.V. Kulakov

1, A.V. Vatulin

1, Y.V. Konovalov*

1, A.A. Kosaurov

1, M.M. Peregud

1, E.A. Korotchenko

1,

V.Y. Shishin2, A.A. Sheldyakov

2,

1Stock Company «A.A. Bochvar High-Technology Research Institute

of Inorganic Materials» (SC VNIINM), Russia, 2

Stock Company «State Scientific Center of Russian Federation - Research Institute of Atomic Reactors» (SC RIAR), Russia

[P2.37] The effect of displacement damage and temperature on the trapping of deuterium implanted into SiC P. Muñoz*, I. García-Cortés, F.J. Sánchez, A. Moroño, M. Malo, E.R. Hodgson, National Fusion Laboratory, CIEMAT, Spain

4th


[P2.38] Investigation of HIP temperature effect on microstructure and mechanical properties of 14Cr-ODS steels by synchrotron radiation and TEM R. XIE*, Z. LU, C.Y. LU, X.Y. DING, C.M. LIU, Northeastern University, China

[P2.39] Effect of Cu/Bi/Fe/Ge co-addition on the corrosion resistance of Zr-1Nb-0.15Fe alloy M.Y. Yao*

1 ,2, X.T. Wu

1 ,2, J. Huang

1 ,2, J.L. Zhang

1 ,2, X. Liang

1 ,2, J.C. Peng

1 ,2, Q. Li

1 ,2,

1Institute of

Materials, Shanghai University, Shanghai 200072,, China, 2

Laboratory for Microstructures, Shanghai University, Shanghai 200444,, China

[P2.40] Microstructural characterization and deformation studies of an industrial scale alloy 690 electro-slag remelted ingot M. Wang*, M.S. Zhang, Z.H. Du, X.C. Hao, K. Liu, Chinese Academy of Sciences, China

[P2.41] Irradiation capsule for testing of anti-permeation and anti-corrosion protective coatings for the European DEMO breeding blanket project P. Stupka, T. Melichar, J. Soltes, L. Vala*, Centrum vyzkumu Rez s.r.o., Czech Republic

[P2.42] An efficient energy remainder criterion for intra-granular diffusion calculations: improving the polypole-1 algorithm D. Pizzocri

1, G. Pastore

2, T. Barani*

1, S. Lorenzi

1, L. Luzzi

1,

1Politecnico di Milano, Italy,

2Idaho

National Laboratory, USA

[P2.43] Observations on the steel T91 under constant load in PbBi eutectic F. Di Gabriele*, A. Hojna, J. Lorincik, P. Halodova, CVR, Czech Republic

[P2.44] Effect of HIP temperature on microstructure and tensile properties of 9Cr-ODS steels produced by atomized alloys powders R. XIE*, Z. LU, C.Y. LU, X.Y. DING, C.M. LIU, Northeastern University, China

[P2.45] Lattice Expansion by Intrinsic Defects in Uranium by Molecular Dynamics Simulation Y. Li

1 ,2, A. Chernatynskiy

3, J. Kennedy

4, S. Sinnott

5, S. Phillpot*

1,

1University of Florida, USA,

2Sun Yat-

sen University, China, 3

Missouri University of Science and Technology, USA, 4

Idaho National Laboratory, USA,

5Pennsylvania State University, USA

[P2.46] Laser welding of P91 and EUROFER97 steels for fusion reactor coolant pipes S. Kirk*

1, W. Suder

2, K. Keogh

1,

11United Kingdom Atomic Energy Authority, UK,

2Cranfield

University, UK

[P2.47] The atomistic simulation of pressure-induced phase transition in uranium mononitride V.I. Tseplyaev*

1 ,2, S.V. Starikov

1 ,2,

1Moscow Institute of Physics and Technology, Russia,

2Joint

Institute for High Temperatures of the Russian Academy of Sciences, Russia

[P2.48] Investigation of susceptibility of A533B steel to temper embrittlement M.A. Sokolov*

1, B.A. Gurovich

2, E.A. Kuleshova

2, Z.V. Bukina

2, A.S. Frolov

2, D.A. Maltsev

2, S.V.

Fedotova2,

1Oak Ridge National Laboratory, USA,

2NRC "Kurchatov Institute", Russia

[P2.49] EBSD analysis of A-EDC tested Zr-Nb alloy H. Muta*

1, Z. Zishou

2, Y. Matsukawa

2, Y. Shinohara

3, H. Abe

4, Y. Ohishi

1, K. Kurosaki

1, S.

Yamanaka1,



3NDC, Japan,

4The University of

Tokyo, Japan

[P2.50] Deformation behaviour of F82H reduced activation martensiric steel during compression tests T. Nagasaka*

1, T. Tanaka

1, T. Muroga

1, A. Sagara

1, R. Kasada

2, H. Tanigawa

3, H. Sakasegawa

3, M.

Ando3,

1National Institute for Fusion Science, Japan,

2Institute of Advanced Energy, Kyoto University,

Japan, 3

National Institutes for Quantum and Radiological Science and Technology, Japan

[P2.51] Effects of oxide particles on He-trapping in ODS ferritic steels P. Song*, A. Kimura, K. Yabuuchi, Kyoto University, Japan

[P2.52] Helium implanted fullerene films on ODS steel plates D. Morrall*, K. Yabuuchi, A. Kimura, Kyoto University, Japan

[P2.53] Microstructure and mechanical properties of Zr hydrides R. Nishikane*

1, H. Muta

1, Y. Ohishi

1, K. Kurosaki

1, S. Yamanaka

1 ,2, K. Sakamoto

3, J. Matsunaga

3 ,5, S.

Harjo4, T. Kawasaki

4,

1Osaka university, Japan,

2University of Fukui, Japan,

3NFD, Japan,

4JAEA, Japan,

5GNF-J, Japan

[P2.54] The effect of post weld heat treatments on the mechanical properties and microstructure of

4th


welded austenitic stainless steel J.H. Jang*, D.H. Jang, D.G. Nam, B.J. Kim, Korea Institute of Industrial Technology, Republic of Korea

[P2.55] The effect of single and double quenching heat treatments on the mechanical properties of low alloy steel J.S. Kim*, K.P. Kim, H.S. Moon, D.G. Nam, B.J. Kim, Korea Institute of Industrial Technology, Republic of Korea

[P2.56] Influence of the milling conditions on the microstructure and mechanical properties of Oxide Dispersion Strengthened Steels M. Loyer-Prost*, F. Legendre, L. Chaffron, CEA, France

[P2.57] Thermal Aging Effect Analysis on Microstructure of17-4PH Martensitic Stainless Steel Valves for Nuclear Power Plant B. Bai*

1, C.Y. Zhang

1, J.S. Wang

2, H.X. Wang

1, Z.F. Tong

1, Q.X. Lv

2, W. Yang

1,

1China Institute of

Atomic Energy, China, 2

Daya Bay Nuclear Power Operations and Management Co., Ltd., China

[P2.58] Effect of pre-deformation on microstructures, hardness, and magnetic properties of thermally-aged Fe-Cr binary alloys Y. Kamada*

1, M. Je

1, J.N. Mohapatra

1, T. Murakami

1, S. Kobayashi

1, H. Watanabe

2,

1Iwate University,

Japan, 2

Kyushu University, Japan

[P2.59] Quantitative guidelines for the development of a fuel pin thermo-mechanic safety-informed design-oriented tool for HLM cooled reactors F. Lodi*

1, J. Wallenius

2, G. Grasso

3, M. Sumini

1,

1University of Bologna - DIN, Italy,

2KTH - Reactor

Physics Division, Sweden, 3

ENEA - FSN-SICNUC-PSSN, Italy

[P2.60] Development of charge-variable interatomic potential based on second moment tight-binding model: Application to a molecular dynamics study of Mo behavior in UO2. D. Mbongo*

1, D. Ducher

1, D. Dubourg

1, R. Tetot

2,

1Institut de Radioprotection et de Sûreté

Nucléaire, France, 2

Université Paris-Sud, France

[P2.61] Current status of design, R&D toward ADS target irradiation facility, TEF-T N. Okubo*, S. Saito, H. Obayashi, T. Sasa, Japan Atomic Energy Agency, Japan

[P2.62] DFT study of UB2 for use in nuclear power applications P.A. Burr*

1, S.C. Middleburgh

2, R. Holmes

3,

1University of New South Wales, Australia,

2Westinghouse Electric Sweden AB, Sweden,

3Australian Nuclear Science and Technology

Organisation, Australia

[P2.63] Ab initio modelling of silicide nuclear fuels: Handling metastable states A. Claisse*, M. Pierre, P. Olsson, KTH - Royal Institute of Technology, Sweden

[P2.64] A DFT+U study of the actinide nitride series: metastable states, electronic and elastic properties A. Claisse*, P. Olsson, KTH - Royal Institute of Technology, Sweden

[P2.65] Incorporation and migration mechanisms of molybdenum in the stoichiometric and hyper-stoichiometric uranium dioxide L. Sarrasin*

1, N. Moncoffre

1, Y. Pipon

1 ,2, C. Gaillard

1, N. Bérerd

1 ,2, R. Ducher

3, R.

Dubourg3,

1Université de Lyon, CNRS/IN2P3, Université Lyon 1, Institut de Physique Nucléaire, 69622

Villeurbanne, France, 2

Université de Lyon, Université Lyon 1, IUT Lyon 1, 69622 Villeurbanne, France,

3Institut de Radioprotection et Sureté Nucléaire, BP3 13115 St. Paul Lez-Durance, France

[P2.66] Effect of stress on microstructural evolution in U-Mo/Al dispersion fuel Y.S. Kim*

1, G.Y. Jeong

1,

1ANL, USA,

2UNIST, USA

[P2.67] Nanoceramic alumina coatings for future nuclear reactors M. Vanazzi*

1, F. Garcia Ferré

1, F. Di Fonzo

1, S. Bassini

2, M. Utili

2, M. Beghi

3,

1Center for Nano Science

and Technology - IIT, Italy, 2

ENEA C.R. Brasimone, Italy, 3

Dipartimento di Energia, Politecnico di Milano, Italy

[P2.68] Manufacturing Technology And Properties Of Ceramic Pebbles For Breeding Blanket R. Lo Frano*

1, M. Puccini

1, A. Maggini

1, D. Aquaro

1, S. Vitolo

1, N. Forgione

1, S. De Santis

2, M.

Aringhieri2,

1DICI - University of Pisa, Italy,

2Industrie Bitossi S. p. A, Italy

[P2.69] Latest progress on structural materials for advanced reactors in FDS team Q.H. Huang, Institute of Nuclear Energy Safety Technology, Chinese Academy of Sciences, China

4th


[P2.70] Unusual mechanical behavior of Ni50Nb10Zr15Ti15Pt7.2Cu2.5 metallic glass induced by ion irradiation Y.H. Qiu

1, J.L. Du

1, E.G. Fu*

1, L. Shao

2,

1Peking University, China,

2Texas A&M University, USA

[P2.71] Atomistic simulation of defects formation and structure transitions in U-Mo alloys at swift heavy ion irradiation L.N. Kolotova*

1 ,2, S.V. Starikov

1,

1Joint Institute for High Temperatures of the Russian Academy of

Sciences, Russia, 2

Moscow Institute of Physics and Technology, Russia

[P2.72] Fuel performance analysis of FeCrAl cladding during LWR operation R.T. Sweet

1, K.A. Terrani

2, B.D. Wirth*

1 ,2,

1Universit of Tennessee, USA,

2Oak Ridge National

Laboratory, USA

[P2.73] Improvement of the 12% Cr ferritic-martensitic steel corrosion resistance by means of high-temperature pulsed plasma flows processing P.S. Dzhumaev*

1, V.L. Yakushin

1, B.A. Kalin

1, M.V. Leontieva-Smirnova

1 ,2, I.A. Naumenko

2, V.I.

Polskiy1, O.V. Emelyanova

1,

1National Research Nuclear University MEPhI (Moscow Engineering

Physics Institute), Russia, 2

Stock Company «A.A. Bochvar High-technology Research Institute of Inorganic Materials», Russia

[P2.74] Cluster dynamics model for the hydride precipitation kinetics in zirconium cladding D. Xu*, H. Xiao, University of Tennessee, USA

[P2.75] Thermoelectric power and magnetic hysteresis loop measurements on thermally aged high chromium martensitic steel Y. Kamada*, T. Sato, M. Murakami, S. Kobayashi, Iwate University, Japan

[P2.76] Description of diffusion in U-Mo alloys from the molecular dynamics simulations T.S. Kostuchenko*

1 ,2, A.Y. Kuksin

1 ,2,

1Moscow Institute of Physics and Technology, Russia,

2Joint

Institute for High Temperatures of the Russian Academy of Sciences, Russia

[P2.77] Preliminary consideration of crack initiation in ferritic martensitic steel T91 in Pb F. Di Gabriele*, A. Hojna, M. Chocholousek, J. Lorincik, CVR, Czech Republic

[P2.78] Oxide particles dissolution and precipitation in spark-plasma sintered and cold deformed ODS chromium steel B.A. Tarasov*, M.S. Tarasova, M.A. Saveliev, I.I. Konovalov, National Research Nuclear University MEPhI (Moscow Engineering Physics Institute), Russia

[P2.79] Development of a shell model for grain boundary porosity A.A. Prudil, M.J. Welland, M. Piro*, Canadian Nuclear Laboratories, Canada

[P2.80] Thermal properties of W-Ti-Hf prepared by mechanical alloying B. Nevrlá*, M. Vilémová, F. Lukáč, IPP CAS CR, Czech Republic

[P2.81] Phase field modeling of grain growth in uranium dioxide incorporating anisotropic grain boundary energies E.D. Hansen*

1, T.J. Harbison

1, J.M. Carmack

2, J.S. Tolliver

1, J.M. Bradley

1, Y. Zhang

3,

1Brigham Young

University-Idaho, USA, 2

University of Arkansas, USA, 3

Idaho National Laboratory, USA

[P2.82] Influence of alloying elements on thermal and mechanical properties of tungsten M. Vilémová*, B. Nevrlá, F. Lukáč, T. Chráska, Institute of Plasma Physics AS CR, v.v.i., Czech Republic

[P2.83] Development of oxide layer coated Zr-based alloys as accident tolerant fuel cladding: Trial assessment on a corrosive basis Z.G. Duan*

1, H.L. Yang

2, Y. Satoh

1, K. Murakami

2, S. Kano

2, H. Abe

2,


2The

University of Tokyo, Japan

[P2.84] Effects of annealing temperature on nanoscale particles in oxide dispersion strengthened Fe-15Cr alloy powders with Ti and Zr additions H.J. Xu, Z. Lu*, C.M. Liu, Northeastern University, China

[P2.85] Oscar-Na: a new code for simulating corrosion product contamination in sodium fast reactors J-B. Genin, L. Brissonneau*, T. Gilardi, CEA DEN, France

[P2.86] Microstructure of yttria doped ceria as a function of oxalate co-precipitation synthesis conditions L. Brissonneau*, A. Mathieu, B. Tormos, A. Martin-Garin, CEA DEN, France

4th


[P2.87] Phase field modelling of intergranular gas bubble evolution in irradiated U-7Mo alloy L.Y. Liang, Z.G. Mei, A.M. Yacout*, Argonne National Lab, USA

[P2.88] Multidimensional modelling options in the BISON fuel performance code J.D. Hales*, B.W. Spencer, R.L. Williamson, Idaho National Laboratory, USA

[P2.89] Anharmonic effects in vacancy diffusion rate calculations: bcc U and Mo K.S. Fidanyan*

1 ,2, V.V. Stegailov

1,

1Joint Institute for High Temperatures of the Russian Academy of

Sciences, Russia, 2

Moscow Institute of Physics and Technology, Russia

[P2.90] Thermal/Cold Spray of Mechanically Alloyed F/M-ODS Steel Powder S.H. Kang*

1, D-Y. Park

2, B-K. Choi

1, S. Noh

1, J. Jang

1, T.K. Kim

1,

1Korea Atomic Energy Research

Institute, Republic of Korea, 2

COSMOS Metallizing Co, Republic of Korea

Poster Session 3 Wednesday 9th November 2016

16:30-18:00

[P3.01] Study on neutron and gamma-ray interaction properties with cobalt-free martensite steel M.M. Eissa

1, S.U. El-Kameesy*

2, M.M. Kassab

3, A. Abdel-Latif

3,

1Central Metallurgical research and

Development Institute, Egypt, 2

Faculty of Science, Ain Shams University, Egypt, 3

Faculty of Engineering, Fayoum University, Egypt

[P3.02] Sodium infiltration studies in irradiated metallic fuel using surrogate material L.S. Bhadrinarayanan*, S. Muthusaravanan, B. Malarvizhi, D. Ponraju, B.K. Nashine, P. Selvaraj, Indira Gandhi Centre for Atomic Research, Kalpakkam, India

[P3.03] Semi-destructive testing methods SPT and ABIT used for evaluation of mechanical properties of irradiated NPP's materials P. Petelová*, R. Kopriva, M. Falcník, I. Eliášová, ÚJV Rež, a. s., Czech Republic

[P3.04] Influence of neutron irradiation on mechanical behavior of CuCrZr alloy and CuCrZr/316L stainless steels joints for the First Wall panels of the ITER M. Kolluri*

1, A.J. Magielsen

1, H. Nolles

1, T. Bakker

1, A. Kovács

2, S. Heikkinen

3, S. Wikman

3, F.

Zacchia3, R. Eaton

4, V. Barabash

4,

1Nuclear Research & consultancy Group (NRG), The Netherlands,

2MTA-EK, Hungary,

3Fusion for Energy, Spain,

4ITER International Organization, France

[P3.05] In-reactor investigation of the composite UO2-BeO fuel: background, results and perspectives M.A. McGrath

1, B.Y. Volkov*

1, Y. Russin

2,

1Institute for Energy Technology, Norway,

2JSC "UMP",

Kazakhstan

[P3.06] The effects of particle size on the characteristics of uranium dioxide pellets produced via spark plasma sintering (SPS) J.D. Turner*, J. Buckley, M.J.J. Schmidt, T. Abram, The University of Manchester, UK

[P3.07] Decontamination of radioactive waste: Caesium extraction by functionalized carbon nanotubes. H. draouil*, L. alvarez, J. cambedezou, université de tunis, Tunisia

[P3.08] Performance guarantee tests with a thermal diffusivity light flash apparatus in order to characterize nuclear fuels C. Duguay*, V. Eltchian, M. Soulon, CEA, DEN, DEC, Cadarache F-13108 Saint-Paul-lez-Durance, France

[P3.09] Yttria stabilised zirconia as a simulant for uranium oxide during spark plasma sintering M.J.J. Schmidt*, J.D. Turner, J. Buckley, T. Abram, The University of Manchester, UK

[P3.10] Swelling, creep and embrittlement of D9 stainless steel cladding and duct in two FFTF driver fuel assemblies at high neutron exposures F.A. Garner*

1, B.J. Makenas

2, S.A. Chastain

2,

1Texas A&M University, USA,

2retired, USA

[P3.11] Fabrication and Characterization of Metallic Fuel Slugs for Sodium-cooled Fast Reactor Using Recycled Fuel Scraps K.H. Kim*, S.J. Ha, S.W. Kuk, J.Y. Park, C.B. Lee, Korea Atomic Energy Research Institute, Republic of Korea

[P3.12] 3He NMR measurements on palladium samples aged under tritium

4th


M. Segard*1, T. Charpentier

2, M. Moskura

2, S. Challet

1, A. Fabre

1,

1CEA, centre de Valduc, France,

2NIMBE - UMR CEA-CNRS 3685, France

[P3.13] Characterization of (U,Gd)O2 nanoparticles synthesized by a low temperature method A.L. Soldati

1 ,2, A. Fernandez Zuvich*

1, I. Gana Watkins

1, H. Zolotucho

1, M. Prado

1 ,2,

1Centro Atómico

Bariloche, Comisión Nacional de Energía Atómica, Argentina, 2

Consejo Nacional de Investigaciones Científicas y Técnicas, Argentina

[P3.14] Thermal conductivity and thermal stress of UO2-Mo micro-cell fuel pellets H.S. Lee

1, D-J. Kim

2, J.H. Yang

2, Y-H. Koo

2, D.R. Kim*

1,

1Hanyang University, Republic of Korea,

2Korea

Atomic Energy Research Institute, Republic of Korea

[P3.15] Improvement of swelling resistance of advanced ODS alloys by combining the suppression effects of both dispersoids and tempered martensite phase L. Shao*

1, T.Y. Chen

1, J. Gigax

1, L. Price

1, S. Ukai

2, F.A. Garner

1,

1Texas A&M University, USA,

2Hokkaido University, Japan

[P3.16] An auto-catalytic mechanism to model the fission gas release between 500°C and 800°C on UO2 irradiated fuel G. Brindelle*

1 ,2, G. Baldinozzi

2, H. Capdevila

1, L. Desgranges

1, Y. Pontillon

1,

1CEA DEN/DEC, France,

2CNRS, SPMS, LRC CARMEN, France

[P3.17] Oxygen depth profiling by resonant backscattering of Ti6-Al-4V alloy oxidized by ion implantation S. Nsengiyumva

1, M. Topic*

2, L. Pichon

3, C.M. Comrie

4, C. Mtshali

5,

1Rhodes University, South Africa,

2iThemba LABS, South Africa,

3Institute Pprime, France,

4iThemba LABS, South Africa,

5iThemba LABS,

South Africa

[P3.18] The main principles of irradiated dispersion type fuel “uranium dioxide + aluminium alloy” behaviour G.V. Kulakov*

1, Y.V. Konovalov

1, A.V. Vatulin

1, V.Y. Shishin

2, A.A. Sheldyakov

2,

1Stock Company «A.A.

Bochvar High-Technology Research Institute of Inorganic Materials» (SC VNIINM), Russia, 2

Stock Company «State Scientific Center of Russian Federation - Research Institute of Atomic Reactors» (SC RIAR), Russia

[P3.19] Formation of alpha prime phase in ion-irradiated Fe-12Cr alloys Z. Jiao, F. Gao, G.S. Was*, University of Michigan, USA

[P3.20] Thermal conductivity analysis of uranium dioxide solid solution N. Kato*

1, H. Muta

1, K. Tanaka

2, T. Matsuda

3, Y. Ohishi

1, K. Kurosaki

1, S. Yamanaka

1,

1Osaka



Japan Fine Ceramics Center, Japan

[P3.21] Resistance to temperature of stearates used as lubricants for the manufacturing of fast reactor fuels J. Garcia

2, A.C. Robisson*

1, J. Martinez

2, R. Rambier

1, F. Garel

1, P. Matheron

1, F. Audubert

1,

1CEA

Cadarache, France, 2

CEA Marcoule, France

[P3.22] Crystal orientation dependence of ion-irradiation hardening in tungsten single crystal E. Hasenhuetl*, Z. Zhang, K. Yabuuchi, A. Kimura, Kyoto University, Japan

[P3.23] Experimental investigation of the liquidus surface in Ag-Cd-In ternary system K. Gajavalli*

1, P. Benigni

2, J. Rogez

2, G. Mikaelian

2, A. Decreton

1, M. Barrachin

1, E. Fischer

3,

1Institut

de Radioprotection et Sureté Nucléaire, France, 2

IM2NP, UMR7334, CNRS, Aix-Marseille Université, France,

3Université Grenoble Alpes, CMTC, SIMAP, France

[P3.24] Stoichiometry deviation in the accident tolerant fuel candidate U3Si2 S.C. Middleburgh*

1, R.W. Grimes

2, E.J. Lahoda

3, P. Xu

3, C.R. Stanek

4, D.A.

Andersson4,

1Westinghouse Electric Sweden AB, Sweden,

2Imperial College London, U.K, UK,

3Westinghouse Electric Company LLC, USA,

4Los Alamos National Laboratory, USA

[P3.25] Mortars under gamma irradiation: from cements hydrates to waste nuclear coating L. Acher*

1, J. Haas

1, A. Dannoux-Papin

1, F. Frizon

1, F. Dunstetter

1 ,2, M-N. De Noirfontaine

2,

1CEA,

France, 2

Laboratoire des solides irradiés, Ecole Polytechnique, France

[P3.26] UO2 extended defect kinetic change under ion irradiation/implantation using TEM characterization C. Onofri*

1, C. Sabathier

1, C. Bachelet

2, C. Baumier

2, M. Legros

2,

1CEA, France,

2CNRS, France

4th


[P3.27] Irradiation temperature influence on structure and radiation embrittlement of RPV steel B.A. Gurovich, E.A. Kuleshova, A.S. Frolov, S.V. Fedotova, D.A. Maltsev, E.V. Krikun, D.A. Zhurko, Z. Bukina*, National Research Center "Kurchatov Institute", Russia

[P3.28] Radiation tolerance of Cr-Ta multi-layered coatings M. Loyer-Prost*

1, M. Sall

1, A. Billard

2, H. Khodja

1,

1CEA, France,

2UTBM, France

[P3.29] Structure of ZrN/SiNx multilayers irradiated by helium ions V.V. Uglov*

1 ,2, G. Abadias

3, S.V. Zlotski

1, M. Marteau

3, I.A. Saladukhin

1, A. Janse van Vuuren

4, J.

O’Connell4, S. Vlasenko

1, A. Benediktovitch

1,


2Tomsk

Polytechnic University, Russia, 3

Institut Pprime, France, 4

Centre for HRTEM, South Africa

[P3.30] Microwave sintering of nuclear ceramics J. Croquesel*

1, S. Pillon

1, F. Valdivieso

2, S. Saunier

2,

1CEA Marcoule, France,

2Ecole des Mines de

Saint Etienne, France

[P3.31] Enthalpy increment measurements on U-15 wt.% Cr alloy using inverse drop calorimetry R. Santhosh*

1, S. Raju

2, S. Saroja

1 ,2,

1Homi Bhabha National Institute,Indira Gandhi Centre for

Atomic Research, Kalpakkam, India, 2

Indira Gandhi Centre for Atomic Research, Kalpakkam, India

[P3.32] Hydrothermal treatment to make crack-free ThO2 microspheres using external gelation process P. WANG, C. YAN, H. HUANG, F-X. WANG, C-Q. CHAO, Z-Y. ZHU, J. LIN*, Center for Thorium Molten Salt Reactor System, Shanghai Institute of Applied Physics, Chinese of Applied Physics, China

[P3.33] Effect of irradiation by hydrogen atoms and ions of hydrogen and argon plasma on hydrogen transport through the surface oxide layer of zirconium A.E. Evsin*

1, L.B. Begrambekov

1, A.I. Gumarov

2, A.S. Kaplevsky

1, N.F. Kashapov

2, A.G. Luchkin

2, L.R.

Tagirov2, I.R. Vakhitov

2, I.V. Yanilkin

2,

1National Research Nuclear University MEPhI, Russia,

2Kazan

Federal University, Russia

[P3.34] Microstructure evolution and thermal property change in heavy ion irradiated zirconium diboride J.T. Graham*, C.H. Castano, Missouri University of Science & Technology, USA

[P3.35] Radiation induced hardenig of A533B under neutorn irradiation H.W. Watanabe*

1, T.T. Tnaka

1, Y.K. Kamada

2,

1RIAM, Kyushu univ.,, Japan,

2Iwate univ.,, Japan

[P3.36] A first-principles study on thermal conductivity of actinide dioxides H. Nakamura*, M. Machida, Japan Atomic Energy Agency, Japan

[P3.37] Void swelling behavior of multi-ion irradiated F82H M. Ando*, H. Tanigawa, H. Kurotaki, National Institutes for Quantum and Radiological Science and Technology, Japan

[P3.38] Origin and consequences of silicate glass passivation by surface layers S. GIN, CEA, France

[P3.39] Irradiation hardening of reduced activation ferritic/martensitic steels irradiated with Fe3+

and He+:

comparison with pure Fe and Fe-8Cr model alloy H. Kanai*

1, K. Yabuuchi

2, A. Kimura

2, M. Ando

3, H. Tanigawa

3,

1Graduate School of Energy Science,


Institute of Advanced Energy, Kyoto University, Japan, 3

National Institutes for Quantum and Radiological Science and Technology, Japan

[P3.40] Irradiation Defects in UO2 leached in oxidizing water:An in-situ Raman study R. Mohun

1, L. Desgranges*

1, M. Magnin

1, C. Jegou

1, A. Canizares

2, P. Simon

2,

1CEA,DEN, France,

2CNRS, France

[P3.41] Corrosion behavior of ODS steels with several chromium contents in hot nitric acid solutions T. Tanno*, M. Takeuchi, S. Ohtsuka, T. Kaito, Japan Atomic Energy Agency, Japan

[P3.42] Spinel nitrides for fusion applications E. Feldbach*

1 ,2, A. Kanaev

2, A. Zerr

2,

1University of Tartu, Estonia,

2CNRS, Université Paris 13, France

[P3.43] Study of gamma irradiation effects in fusion reactor optical components I. Garcia-Cortes*

1, M. Malo

1, A. Moroño

1, E.R. Hodgson

1, P. Valdivieso

1, P. Muñoz

1, A. Gusarov

1, L.

Vermeeren1,

1National Fusion Laboratory, CIEMAT, 28040 Madrid, Spain,

2Technology Division,

CIEMAT, 28040 Madrid, Spain, 3

SCK·CEN Boeretang 200, Mol 2400, Belgium

[P3.44] Thermodynamic Database of UO2-ZrO2-Al2O3-CaO-SiO2 System based on Cell Model M. Kurata*

1, N. Shirasu

1, K. Kawakami

2,

1JAEA, Japan,

2NSSMC, Japan

4th


[P3.45] Deuterium permeation at 250 ºC during 1.8 MeV electron irradiation for alumina coated Eurofer T. Hernández*, E.R. Hodgson, M. Malo, A. Maroño, CIEMAT, Spain

[P3.46] Influence of substrate-gas inlet gap on morphology and microstructure of zirconium carbide coatings grown by chemical vapour deposition S. Biira*

1 ,2, B.A.B. Alawad

1, H. Bissett

3, J.T. Nel

3, T.T. Hlatshwayo

1, P.L. Crouse

1, J.B.

Malherbe1,

1University of Pretoria, South Africa,

2Busitema University, Uganda,

3The South African

Nuclear Energy Corporation (Necsa), South Africa

[P3.47] Crystal structures of oxide layers formed by water corrosion of pure zirconium, hydride zirconium and Zircaloy-4 under deep geological repository conditions for nuclear wastes T. Otsuka*

1 ,6, K. Hashizume

1, O. Kato

2, T. Tateishi

3, Y. Ikeda

4, S. Yoshida

5, T. Sakuragi

5,

1Kyushu


Kobe Steel, Ltd, Japan, 3

Kobelco Research Institute, Inc., Japan, 4

Nippon Steel & Sumikin Technology, Japan,

5Radioactive Waste Management Funding and Research Center, Japan,

6Kindai University, Japan

[P3.48] Oxidation of Uranium Nitride in Air and Steam Environments K.D. Johnson*, S. Uygur, D.A. Lopes, Kungliga Tekniska Högskolan, Sweden

[P3.49] Thermodynamic segregation of C and O impurities in uranium nitride fuel D.A. Lopes

1, T. Chuler

2, A. Claisse*

1, P. Olsson

1,

1KTH - Kungliga Tekniska Högskolan, Sweden,

2University of Illinois, USA

[P3.50] Apparatus for accelerated IASCC testing using simultaneous proton irradiation and tensile loading E. Metsanurk*, M. Klintenberg, Uppsala University, Sweden

[P3.51] Blister formation in zirconium and silicon nitrides multilayers V.V. Uglov*

1 ,2, G. Abadias

3, N.T. Kvasov

1, S.V. Zlotski

1, M. Marteau

3, I.A. Saladukhin

1, V.I. Shymanski

1

,2, N.N. Cherenda

1 ,2, J. Moffat

4,


2Tomsk Polytechnic University,

Russia, 3

Institut Pprime, France, 4

Asylum Research an Oxford Instruments company, UK

[P3.52] Experimental evidence of oxygen thermo-migration in PWR UO2 fuels during power ramps using in-situ oxido-reduction indicators C. Riglet-Martial*, J. Sercombe, J. Lamontagne, J. Noirot, I. Roure, T. Blay, L. Desgranges, CEA, DEN, DEC, France

[P3.53] Migration mechanisms of molybdenum in the stoichiometric and hyper-stoichiometric uranium dioxide L. Sarrasin*

1, N. Moncoffre

1, Y. Pipon

1 ,2, C. Gaillard

1, N. Bérerd

1 ,2, R. Ducher

3, R. Dubourg

3, D.

Mangin4, P. Simon

5, E. Arthur-Baidoo

1,

1Université de Lyon, CNRS/IN2P3, Université Lyon 1, Institut

de Physique Nucléaire, 69622 Villeurbanne, France, 2

Université de Lyon, Université Lyon 1, IUT Lyon 1, 69622 Villeurbanne, France,

3Institut de Radioprotection et Sureté Nucléaire, BP3 13115 St. Paul

Lez-Durance, France, 4

Université de Lorraine, Institut Jean Lamour, 54011 Nancy, France, 5

Université d'Orléans, F-45067 Orléans 2, France

[P3.54] Manufacture and characterisation of cerium silicide as a nuclear surrogate G.P. Phillips*, J.D. Turner, T.J. Abram, University of Manchester, UK

[P3.55] Assessing the feasibility for cerium metal to be used as a surrogate for uranium in U-Zr alloys H.E. Ragnauth*, J.D. Turner, T.J. Abram, The University of Manchester, UK

[P3.56] Effects of electronic stopping on the structure and accumulation of ion tracks in ceria K. Yasuda*

1, T. Nagaishi

1, S. Takaki

1 ,2, S. Yoshioka

1, S. Matsumura

1, N. Ishikawa

2,

1Kyushu University,

Japan, 2

JAEA, Japan

[P3.57] Effect of radiation on embrittlement and matrix Cu content of a RPV weld with different PWHT conditions M.A. Sokolov*

1, R.K. Nanstad

1, L.E. Ecker

2, D.J. Sprouster

2,

1Oak Ridge National Laboratory, USA,

2Brookhaven National Laboratory, USA

[P3.58] Diffusion of Xenon implanted in Glassy Carbon M.Y.A. Ismail*, J.B. Malherbe, T.T. Hlatshwayo, E.G. Njoroge, S. Biira, B.A.B. Alawad, O.S. Odutemowo, University of Pretoria, South Africa

[P3.59] Solubility prediction of fission products and cladding constituents in heavy liquid metals for the development of gen iv fast reactors

4th


M. Cerini*, E. Macerata, M. Giola, M. Mariani, Politecnico di Milano, Italy

[P3.60] Vitrification as a means of reworking problematic cemented wasteforms J.S. Clarke*, M.C. Stennett, C.L. Corkhill, N.C. Hyatt, University of Sheffield, UK

[P3.61] Experimental assessment of U(Cd)O2 preparation H. Hoffmann

1, I. Gana Watkins

1, A.L. Soldati*

1 ,2, M. Prado

1 ,2,

1Centro Atómico Bariloche, Comisión

Nacional de Energía Atómica, Argentina, 2

Consejo Nacional de Investigaciones Científicas y Técnicas, Argentina

[P3.62] Kinetic and microstructural studies of thermal decomposition in uranium nitrides A.V. Lunev*

1 ,2, V.V. Mikhalchik

2, A.V. Tenishev

2, V.G. Baranov

2,

1Joint Institute for High

Temperatures of the Russian Academy of Sciences, Russia, 2

National Research Nuclear University MEPhI (Moscow Engineering Physics Institute), Russia

[P3.63] Fuel fabrication and characterization of graphite matrix low enriched uranium fuel blocks for the TREAT reactor: a preliminary report E. Luther*

1, I. van Rooyen

2, A. Short

3, S. Niedzelak

3, C. Richardson

3, D. Navolio

3, A. Nelson

1, C. Stull

1,

B. Coryell2,

1Los Alamos National Laboratory, USA,

2Idaho National Laboratory, USA,

3BWXT, USA

[P3.64] Analysis of boron by EPMA in nuclear glass E. Brackx*

1, B. Pelloux

1, C. Merlet

2, O. Dugne

3, S. Schuller

1, E. Excoffier

1,


2University of Montpellier, France,

3CEA Cadarache, France

[P3.65] Effect of silicon on the thermal conductivity of aluminium T.W. Cho

1, G.Y. Jeong

1, C.M. Lee

1, K.H. Lee

2, D-S. Sohn*

1,

1Ulsan National Institute of Science and

Technology, Republic of Korea, 2

2Korea Atomic Energy Research Institute, Republic of Korea

[P3.66] A thermodynamic study of the fe-ni-te and ni-te systems for the evaluation of fission-product induced corrosion of fast neutron reactor steel cladding C-M. Arvhult*

1 ,2, C. Guéneau

2, S. Gossé

2, S. Poissonnet

2, D. Menut

2, M. Selleby

1,

1KTH Royal

Institute of Technology, Sweden, 2

CEA Saclay, France

[P3.67] Study of the 5f electronic states in U, Np, Pu and Am and (U,Pu) mixed oxides using high resolution XANES P.M. Martin

1, D. Prieur

2, R. Bès*

3, R. Belin

4, M. Strach

1, D. Manara

2, C. Valot

1, T. Vitova

5, T.

Prüßmann5, K. Dardenne

5,


2European Commission - Institute for

Transuranium Elements, Germany, 3

Aalto University, Finland, 4

CEA Cadarache, France, 5

Karlsruhe Institute of Technology - Institute for Nuclear Waste Disposal, Germany

[P3.68] Synthesis of an iron phosphate glass loaded with a complex nuclear waste mixture A. Djeridi*

1, N. Kamel

2, A. Benmounah

1, D. Moudir

2,

1Research Unit for Materials, Processes and

Environment, University M' Hamed Bouguara of Boumerdes, Boumerdès, Algeria, 2

Nuclear Research Centre of Algiers, Division of Nuclear Techniques, 2. Bd Frantz Fanon, P.O. Box:399, Alger-RP, Algiers, Algeria

[P3.69] Synthesis and characterization of Th-bearing rhabdophane-type compounds as precursors for cheralite wasteform D. Qin

1 ,2, A. Mesbah

1, N. Clavier*

1, C. Gausse

1, S. Szenknect

1, N. Dacheux

1,

1ICSM - UMR 5257

CEA/CNRS/ENSCM/Univ. Montpellier, France, 2

Sino-French Institute of Nuclear Engineering and Technology, China

[P3.70] Structural and thermophysical properties of SrU(PO4)2 and BaU(PO4)2 M. Keskar*, S. Sali, K. Krishnan, R. Phatak, B. Vats, S. Kannan, Bhabha Atomic Research centre, India

[P3.71] X-ray and Thermal Investigations of [(U0.3Th0.7)1-yLay]O2+x; (0 ≤ y ≤ 0.36) M. Keskar*, S.K. Sali, K. Krishnan, S. Kannan, Bhabha Atomic Research centre, India

[P3.72] Challenges and developments to investigate high temperature properties of molten salt reactor fuel O. Beneš*

1, R.J.M. Konings

1, P. Soucek

1, E. Capelli

2,

1EC-JRC, Germany,

2TU Delft, The Netherlands

[P3.73] Impact of segregated interstitials on structures and energies of grain boundaries in Mo. I.I. Novoselov*, A.V. Yanilkin, Dukhov Research Institute of Automatics, Russia

[P3.74] A facile and accurate preparation of pure UMoO6 E.C. Corcoran*, J. Scott, R.A. Barry, Royal Military College of Canada, Canada

4th


[P3.75] High temperature X-ray diffraction study of lattice thermal expansion of Pu1-zAmzO2 mixed oxides R. Vauchy*, A. Joly, C. Valot, DEN/DTEC/SECA/LCC, Marcoule, F-30207 Bagnols-sur-Cèze, France

[P3.76] Effects of alloying element in Zr alloys during ion irradiation H.W. Watanabe, RIAM,Kyuhu Univ.,, Japan

[P3.77] Electrochemistry of europium in ionic liquids with chloride and fluoride anions L. Szatmary*, M. Straka, UJV Rez, a.s., Czech Republic

[P3.78] Radiation effects in zirconium and silicon nitrides multilayers irradiated by xenon ions V.V. Uglov*

1 ,2, G. Abadias

3, S.V. Zlotski

1, A. Janse van Vuuren

4, J. O’Connell

4, V. Skuratov

5, J.H.

Neethling4,


2Tomsk Polytechnic University, Russia,

3Institut

Pprime, France, 4

Centre for HRTEM, South Africa, 5

Joint Institute for Nuclear Research, Russia

[P3.79] Parametrical study of the hydrothermal synthesis of PuSiO4 analogs: CeSiO4 and ThSiO4 P. Estevenon*

1, E. Welcomme

1, S. Szenknect

1, A. Mesbah

2, P. Moisy

1, N. Dacheux

3, C.

Poinssot1,

1CEA, France,

2CNRS, France,

3Université de Montpellier, France

[P3.80] Preparation, characterization and thermodynamics of formation of coffinite, USiO4. S. SZENKNECT

2, A. MESBAH

3, T. CORDARA

2, N. CLAVIER

3, C. POINSSOT

4, R.C. EWING

5, N.

DACHEUX*1,

1ICSM/University of Montpellier, France,

2ICSM/CEA, France,

3ICSM/CNRS, France,

4CEA,

France, 5

Standford University, USA

[P3.81] In-situ EDX and TEM observation of matrix and solute interactions on Y-Ti-O oxide particles in an austenitic stainless steel under 1MeV Kr

2+ high temperature irradiation

A.J. Brooks*1, Z. Yao

1, M.R. Daymond

1, M.A. Kirk

2, Z. Zhou

3, G. Zhang

3,

1Queen's University, Canada,

2Argonne National Lab, USA,

3University of Science and Technology Beijing, China

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