Structure Materials for Innovat - OECD Nuclear Energy Agency

445 Pages·012.46 MB·English

by  coll.

Nuclear Science
2012
S
tructural Materials for
Innovative Nuclear Systems
(SMINS-2)
Workshop Proceedings
Daejon, Republic of Korea
31 August-3 September 2010
NEA

Nuclear Science ISBN 978-92-64-99209-2
Structural Materials for Innovative Nuclear Systems
(SMINS-2)
Workshop Proceedings, Daejon, Republic of Korea
31 August-3 September 2010
© OECD 2012
NEA No. 6896

NUCLEAR ENERGY AGENCY
ORGANISATION FOR ECONOMIC CO-OPERATION AND DEVELOPMENT
ORGANISATION FOR ECONOMIC CO-OPERATION AND DEVELOPMENT
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NUCLEAR ENERGY AGENCY
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Cover picture credits: China Institute of Atomic Energy; KAERI.
FOREWORD
Foreword
Materials research is a field of growing relevance for innovative nuclear systems, such
as Generation IV reactors, critical and subcritical transmutation systems and fusion
devices. For these different systems, structural materials are selected or developed taking
into account the specificities of their foreseen operational environment. However,
material development projects require both cross-cutting research programmes and
advanced experimental/simulation facilities in order to characterise and evaluate the
performance of the selected materials.
Since 2007, the OECD Nuclear Energy Agency (NEA) has begun organising a series of
workshops on Structural Materials for Innovative Nuclear Systems (SMINS). The objective
of these workshops is to stimulate an exchange of information on current materials
research programmes for different innovative nuclear systems with a view to identifying
and developing potential synergies. The first workshop was organised in Karlsruhe,
Germany in 2007.
The second workshop was organised on 31 August−3 September 2010 in Daejon,
Republic of Korea. It was hosted by the Korea Atomic Energy Research Institute (KAERI)
and co-sponsored by the European Commission (EC) and the International Atomic Energy
Agency (IAEA). A total of 78 papers were presented during the oral and poster sessions.
These proceedings include all the papers presented at the second workshop. The
opinions expressed are those of the authors only, and do not necessarily reflect the views
of the NEA, any national authority or any other international organisation.

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STRUCTURAL MATERIALS FOR INNOVATIVE NUCLEAR SYSTEMS (SMINS-2), ISBN 978-92-64-99209-2, © OECD 2012
ACKNOWLEDGEMENTS
Acknowledgements
The OECD Nuclear Energy Agency (NEA) is grateful to the Korea Atomic Energy
Research Institute (KAERI) for hosting the second Workshop on Structural Materials for
Innovative Nuclear Systems (SMINS). The Agency also extends its gratitude to the
European Commission (EC) and the International Atomic Energy Agency (IAEA) for their
co-operation.

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STRUCTURAL MATERIALS FOR INNOVATIVE NUCLEAR SYSTEMS (SMINS-2), ISBN 978-92-64-99209-2, © OECD 2012
TABLE OF CONTENTS
Table of contents
Executive summary ....................................................................................................................... 11
Opening Session ............................................................................................................................. 17
Chair: J.H. Hong
M-S. Yang
KAERI welcome address ...................................................................................................... 19
Y-J. Choi
NEA welcome address ......................................................................................................... 21
Plenary Session I ............................................................................................................................ 23
Chairs: T. Allen, J-Y. Park
J-H. Chang, D.H. Hahn
Summary of international design needs for advanced reactors ................................... 25
S. Zinkle
Novel pathways for improving nuclear reactor
structural materials performance ...................................................................................... 27
Session I: Metal − VHTR Environmental Effects and
High-temperature Properties ....................................................................................................... 29
Chairs: F. Balbaud-Célérier, S. Kislitsin
W.R. Corwin
VHTR materials issues ......................................................................................................... 31
C-H. Jang, D. Kim, D. Kim, I. Sah, M. Kim, W-S. Ryu, D.J. Yoon
Environmental effects of nickel-based superalloys on mechanical properties
for VHTR applications .......................................................................................................... 33
K. Maile, E. Roos, A. Klenk, M. Hoffmann
Optimisation of Ni-based Alloy 617 ................................................................................... 39
M.A. Sokolov
Fracture toughness of two advanced structural alloys ................................................... 53
R.K. Nanstad, M.A. Sokolov, R.N. Wright
High-temperature fracture toughness of Inconel 617 ..................................................... 55
Y-D. Kim, T-S. Jo, J-H. Lim, J-Y. Park
Oxidation behaviour of Alloy 617 during ageing
at various temperatures ...................................................................................................... 57
Session II: Ceramics-composite .................................................................................................. 59
Chairs: C. Fazio, W.J. Kim
J.Y. Park, W.J. Kim
Development of SiCf/SiC composite for innovative
structural materials ............................................................................................................. 61
T. Shibata, J. Sumita, T. Takagi, T. Makita, K. Sawa, E. Kunimoto
Irradiation-induced property change of C/C composite for application of
control rod elements of very-high-temperature reactor (VHTR) ................................... 69
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TABLE OF CONTENTS
T. Donomae, K. Maeda
Behaviour of irradiated boron carbide .............................................................................. 79
S. Kislitsin, K. Kadyrzhanov, V. Uglov, D. Rusalski, G. Abadias, S. Dub
Study of heavy ions irradiation on structure of
triple titanium nitride basis coating .................................................................................. 87
Y-K. Yang, T. Gerczak, D. Morgan, I. Szlufarska, S-T. Kim, T. Allen
Diffusion of silver in zirconium carbide
inside tristructural-isotropic nuclear fuel ........................................................................ 89
Session III: Metal − Materials Compatibility − Molten Salt and Sodium ............................. 99
Chair: Y. Dai
V. Ignatiev, A. Surenkov
Alloys compatibility with selected molten salt environments for molten salt
fast reactor breeders and burners .................................................................................... 101
B. Long, Y. Xu, J. Zhang, H. Li, D. Zhang
Investigation on the compatibility of weldments of main component materials
with sodium in the Chinese experimental fast breeder reactor (CEFR)..........................1 21
Plenary Session II ......................................................................................................................... 131
Chairs: Ph. Dubuisson, W.W. Kim
K.O. Pasamehmetoglu, Ph. Dubuisson
Innovative fuels state-of-the-art assessment ................................................................ 133
A. Kimura, R. Kasada, N. Iwata, J. Isselin, P. Dou, J.H. Lee, T. Okuda, M. Inoue,
S. Ukai, S. Ohnuki, H. Sano, T. Fujisawa, F. Abe
Super ODS steels R&D for fuel cladding of advanced nuclear systems ..................... 135
Session IV: Metal − Materials Compatibility − LFR Corrosion.............................................. 149
Chairs: M. Toloczko, S. Ukai
F. Balbaud-Célérier, L. Martinelli, F. Gabriel
Corrosion of structural materials in nuclear systems involving liquid metals ......... 151
G. Coen
Effect of temperature and strain rate on the fracture toughness of T91 steel in
lead-bismuth eutectic environment ................................................................................ 153
A. Pramutadi, A. Mustari, M. Takahashi
Effect of welding on corrosion properties of ferritic-martensitic steels in liquid
lead-bismuth ....................................................................................................................... 155
I-S. Hwang, J. Lim, S-G. Lee
Development of alumina forming ferritic steels for lead-bismuth eutectic-
cooled applications ............................................................................................................ 165
A. Weisenburger, A. Jianu, A. Heinzel, M. DelGiacco, G. Müller, V.D. Markov,
A.D. Kastanov
Corrosion barrier development using electron beams for application in lead
alloys with focus on recent creep to rupture tests ........................................................ 175
Y. Kurata, H. Sato, H. Yokota, T. Suzuki
Development of aluminium powder alloy coating for innovative nuclear
systems with lead-bismuth .............................................................................................. 177
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STRUCTURAL MATERIALS FOR INNOVATIVE NUCLEAR SYSTEMS (SMINS-2), ISBN 978-92-64-99209-2, © OECD 2012
TABLE OF CONTENTS
Session V: Fundamental − Radiation Effects ........................................................................... 189
Chairs: G.J. Ackland, J. Wallenius
Ph. Dubuisson, Y. de Carlan, V. Garat, M. Blat
ODS ferritic-martensitic alloys for sodium fast reactor
fuel pin cladding ................................................................................................................. 191
S.A. Maloy, M. Toloczko, J. Cole, T.S. Byun
Materials issues in cladding and duct reactor materials .............................................. 193
R. Kasada, J.H. Lee, A. Kimura, T. Okuda, M. Inoue, S. Ukai, S. Ohnuki,
T. Fujisawa, F. Abe
Radiation response of super ODS steels for fuel cladding
of advanced nuclear systems ........................................................................................... 195
C. Shin, Y. Osetsky, R. Stoller, J. Kwon
Formation of dislocation loops at the onset of plasticity during
single crystal nanoindentation ........................................................................................2 01
Session VI: General ...................................................................................................................... 203
Chair: S.S. Hwang
L. Edwards
Developing advanced nuclear structural materials for use in high-radiation
environments: An Australian perspective ...................................................................... 205
T. Shikama, T. Muroga
Development of materials for nuclear fusion reactors: Summary of the
14th International Conference on Fusion Reactor Materials ......................................... 207
J. Wallenius, N. Sandberg, P. Szakalos, A. Nordlund
Structural materials research in the Swedish GENIUS Project .................................... 209
Plenary Session III ........................................................................................................................ 211
Chairs: S. Zinkle, C.H. Jang
G.J. Ackland, T.P.C Klaver, D.J. Hepburn
Binding of impurities in austenitic iron: An ab initio study .......................................... 213
F. Tavassoli
Fission-fusion cross-cutting issues related to structural materials ...........................2 23
Session VII: Novel Materials − Nano-structured Materials .................................................. 225
Chairs: A. Kimura, J.S. Jang
S. Ukai, R. Miyata, S. Hayashi, K. Tanaka, T. Kaito, S. Ohtsuka
Structural control and high-temperature strength of 9 Cr ODS steels ....................... 227
C. Fazio, J. Knebel
Development of cladding materials: Past and present experience ............................. 237
M.D. Mathew, T. Jayakumar, B. Raj
Advances in the development of core and out-of-core structural materials for
sodium-cooled fast reactors ............................................................................................. 251
Session VIII: Fundamental Radiation Effects − Helium Effect .............................................. 261
Chairs: R. Nanstad, S-H. Chi
Y. Dai
Challenges of structural materials for applications
in spallation targets of ADS .............................................................................................. 263
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TABLE OF CONTENTS
C. Heintze, E. Altstadt, F. Bergner, M. Hernández Mayoral, M. Xie, U. Birkenheuer
Hardening and microstructure of neutron- and ion-irradiated
Fe-Cr alloys .......................................................................................................................... 265
G-H. Kim, K. Shiba, T. Sawai, I. Ioka, K. Kiuchi, J. Nakayama
Microstructural evolution and void swelling in extra high purity
Ni-based superalloy under multi-ion irradiation .......................................................... 273
S. Obara, T. Wakai, T. Asayama, Y. Yamada, T. Nakazawa, M. Yamazaki,
H. Hongo
Effects of heat treatments on long-term creep properties of
9Cr-W-Mo-V-Nb steel ........................................................................................................ 281

Poster Session ............................................................................................................................... 297
Chairs: T. Allen, J-Y. Park
Session I: Fundamental − Irradiation ....................................................................................... 299
Chairs: J-H. Kwon, G-G. Lee, C-S. Shin
J-H. Kwon, G-G. Lee, C-S. Shin
Multi-scale modelling approach to the estimation of radiation hardening of
stainless steels in LWR and SFR environments ............................................................. 301
S-H. Kim, W-S. Ryu, Y-W. Kim
A study on the change of impact properties by neutron irradiation
in modified 9Cr–1Mo steel ................................................................................................. 303
K. Field, A. Certain, Y. Yang, T. Allen
Radiation response of ferritic/martensitic cladding steels .......................................... 305
J-H. Yoon, S-H. Kim, D-S. Kim, B-S. Lee, W-S. Ryu
Irradiation-induced shifts in master curve reference temperature of
ferritic/martensitic steels and welds ............................................................................... 307
D-W. Kim, S-H. Kim, W-S. Ryu
Mechanical properties of welded and irradiated 9Cr-1Mo-1W steel .......................... 309
G.G. Lee, J.H. Kwon
Computer simulation on the isochronal annealing of irradiated Fe using the
kinetic Monte Carlo method ............................................................................................. 313
W.G. Kim, S.N. Yin, G.G. Lee, J.Y. Park, Y.W. Kim
Creep properties in air and helium environments of Alloy 617
For a VHTR ........................................................................................................................... 315
Session II: Metal-Compatibility ................................................................................................. 317
Chairs: D.Y. Ku, M.Y. Ahn, I.K. Yu, S. Cho, H.G. Lee, K.J. Jung
D.Y. Ku, M.Y. Ahn, I.K. Yu, S. Cho, H.G. Lee, K.J. Jung
Thermal fatigue and thermal ageing test of low activation ferrite/martensitic
steel for helium-cooled solid breeder TBM ..................................................................... 319
X. Fu, B. Long, J. Zhang, F. Chu, Y. Xu, A. Gessi
Corrosion behaviour of 316LN in static liquid lead-bismuth eutectic ........................ 321
J. Zhang, X. Fu, B. Long, F. Chu, Y. Xu, A. Gessi
Compatibility of CLAM steel 9Cr2WVTa with flowing lead.......................................... 323
D. Kim, I. Sah, C. Jang
Ageing effects of nickel-based superalloys on mechanical properties for VHTR
applications ......................................................................................................................... 325
D. Kim, I. Sah, C. Jang
Effects of carburisation and decarburisation on the mechanical properties of
nickel-based superalloys for VHTR applications ...........................................................3 29
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STRUCTURAL MATERIALS FOR INNOVATIVE NUCLEAR SYSTEMS (SMINS-2), ISBN 978-92-64-99209-2, © OECD 2012