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Structural Materials for Innovative Nuclear Systems (SMINS-2): Workshop Proceedings, Daejon, Republic of Korea, 31 August-3 September 2010

Structural Materials for Innovative Nuclear Systems (SMINS-2): Workshop Proceedings, Daejon, Republic of Korea, 31 August-3 September 2010

Organisation for Economic Co-operation and Development; NEA

Materials research is a field of growing relevance for innovative nuclear systems, such as Generation IV reactors, critical and sub-critical transmutation systems and fusion devices. For these different systems, structural materials are selected or developed taking into account the pecificities of their foreseen operational environment. Since 2007, the OECD Nuclear Energy Agency (NEA) has begun organising a series of workshops on Structural Materials for Innovative Nuclear Systems (SMINS) in order to provide a forum to exchange information on current materials research programmes for different innovative nuclear systems. These proceedings include the papers of the second workshop (SMINS-2) which was held in Daejon, Republic of Korea on 31 August-3 September 2010, and hosted by the Korea Atomic Energy Research Institute (KAERI)

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Published Paris: OECD Publishing, 2012

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Statement of responsibility: Organisation for Economic Co-operation and Development and NEA
ISBN: 926499209X, 9789264992092
Physical Description: 1 online resource
Other Number: 10.1787/9789264992092-en
Series: Nuclear Science,
Subject: Nuclear Energy
Series Title: Nuclear Science,


  1. Executive summary 11 OPENING SESSION. Chair: J.H. Hong, M-S. Yang��17 -KAERI welcome address, Y-J. Choi�19 -NEA welcome address 21 PLENARY SESSION I. Chairs: T. Allen, J-Y. Park 23 -Summary of international design needs for advanced reactors by J-H. Chang, D.H. Hahn�25 -Novel pathways for improving nuclear reactor structural materials performance�by S. Zinkle��27 Session I: Metal − VHTR Environmental Effects and High-temperature Properties: Chairs: F. Balbaud-Célérier, S. Kislitsin 29 -VHTR materials issues by W.R. Corwin�31 -Environmental effects of nickel-based superalloys on mechanical properties for VHTR applications�by C-H. Jang, D. Kim, D. Kim, I. Sah, M. Kim, W-S. Ryu, D.J. Yoon��33 -Optimisation of Ni-based Alloy 617 by K. Maile, E. Roos, A. Klenk, M. Hoffmann��39 -Fracture toughness of two advanced structural alloys�by M.A. Sokolov��53 -High-temperature fracture toughness of Inconel 617 by R.K. Nanstad, M.A. Sokolov, R.N. Wright��55 -Oxidation behaviour of Alloy 617 during ageing at various temperatures�by Y-D. Kim, T-S. Jo, J-H. Lim, J-Y. Park��57 Session II: Ceramics-composite: Chairs: C. Fazio, W.J. Kim�59 -Development of SiC f/SiC composite for innovative structural materials by J.Y. Park, W.J. Kim�61 -Irradiation-induced property change of C/C composite for application of control rod elements of very-high-temperature reactor (VHTR) by T. Shibata, J. Sumita, T. Takagi, T. Makita, K. Sawa, E. Kunimoto�69 -Behaviour of irradiated boron carbide by T. Donomae, K. Maeda�79 -Study of heavy ions irradiation on structure of triple titanium nitride basis coating�by S. Kislitsin, K. Kadyrzhanov, V. Uglov, D. Rusalski, G. Abadias, S. Dub��87 -Diffusion of silver in zirconium carbide inside tristructural-isotropic nuclear fuel�by Y-K. Yang, T. Gerczak, D. Morgan, I. Szlufarska, S-T. Kim, T. Allen��89 Session III: Metal − Materials Compatibility − Molten Salt and Sodium: Chair: Y. Dai 99 -Alloys compatibility with selected molten salt environments for molten salt fast reactor breeders and burners by V. Ignatiev, A. Surenkov�101 -Investigation on the compatibility of weldments of main component materials with sodium in the Chinese experimental fast breeder reactor (CEFR) by B. Long, Y. Xu, J. Zhang, H. Li, D. Zhang��121 PLENARY SESSION�II . Chairs: Ph. Dubuisson, W.W. Kim 131 -Innovative fuels state-of-the-art assessment by K.O. Pasamehmetoglu, Ph. Dubuisson�133 -Super ODS steels R&D for fuel cladding of advanced nuclear systems�by�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���135 Session IV: Metal − Materials Compatibility − LFR Corrosion. Chairs: M. Toloczko, S. Ukai 149 -Corrosion of structural materials in nuclear systems involving liquid metals by F. Balbaud-Celerier, L. Martinelli, F. Gabriel�151 -Effect of temperature and strain rate on the fracture toughness of T91 steel in lead-bismuth eutectic environment by G. Coen�153 -Effect of welding on corrosion properties of ferritic-martensitic steels in liquid lead-bismuth�by A. Pramutadi, A. Mustari, M. Takahashi��155 -Development of alumina forming ferritic steels for lead-bismuth eutecticcooled applications by I-S. Hwang, J. Lim, S-G. Lee�165 -Corrosion barrier development using electron beams for application in lead alloys with focus on recent creep to rupture tests by A. Weisenburger, A. Jianu, A. Heinzel, M. DelGiacco, G. Muller, V.D. Markov, A.D. Kastanov��175 -Development of aluminium powder alloy coating for innovative nuclear systems with lead-bismuth by Y. Kurata, H. Sato, H. Yokota, T. Suzuki�177 Session V: Fundamental − Radiation Effects. Chairs: G.J. Ackland, J. Wallenius 189 -ODS ferritic-martensitic alloys for sodium fast reactor fuel pin cladding by Ph. Dubuisson, Y. de Carlan, V. Garat, M. Blat�191 -Materials issues in cladding and duct reactor materials by S.A. Maloy, M. Toloczko, J. Cole, T.S. Byun�193 -Radiation response of super ODS steels for fuel cladding of advanced nuclear systems by�R. Kasada, J.H. Lee, A. Kimura, T. Okuda, M. Inoue, S. Ukai, S. Ohnuki, T. Fujisawa, F. Abe��195 -Formation of dislocation loops at the onset of plasticity during single crystal nanoindentation by C. Shin, Y. Osetsky, R. Stoller, J. Kwon�201 Session VI: General. Chair: S.S. Hwang 203 -Developing advanced nuclear structural materials for use in high-radiation environments: An Australian perspective by L. Edwards�205 -Development of materials for nuclear fusion reactors: Summary of the 14th International Conference on Fusion Reactor Materials�by T. Shikama, T. Muroga��207 -Structural materials research in the Swedish GENIUS Project by J. Wallenius, N. Sandberg, P. Szakalos, A. Nordlund�209 PLENARY SESSION�III. Chairs: S. Zinkle, C.H. Jang 211 -Binding of impurities in austenitic iron: An� ab initio study�by G.J. Ackland, T.P.C Klaver, D.J. Hepburn�213 -Fission-fusion cross-cutting issues related to structural materials by F. Tavassoli�223 Session VII: Novel Materials − Nano-structured Materials. Chairs: A. Kimura, J.S. Jang 225 -Structural control and high-temperature strength of 9 Cr ODS steels by S. Ukai, R. Miyata, S. Hayashi, K. Tanaka, T. Kaito, S. Ohtsuka�227 -Development of cladding materials: Past and present experience�by C. Fazio, J. Knebel��237 -Advances in the development of core and out-of-core structural materials for sodium-cooled fast reactors�by M.D. Mathew, T. Jayakumar, B. Raj��251 Session VIII: Fundamental Radiation Effects − Helium Effect. Chairs: R. Nanstad, S-H. Chi 261 -Challenges of structural materials for applications in spallation targets of ADS by Y. Dai 263 -Hardening and microstructure of neutron- and ion-irradiated Fe-Cr alloys by C. Heintze, E. Altstadt, F. Bergner, M. Hernández Mayoral, M. Xie, U. Birkenheuer�265 -Microstructural evolution and void swelling in extra high purity Ni-based superalloy under multi-ion irradiation by G-H. Kim, K. Shiba, T. Sawai, I. Ioka, K. Kiuchi, J. Nakayama�273 -Effects of heat treatments on long-term creep properties of 9Cr-W-Mo-V-Nb steel by�S. Obara, T. Wakai, T. Asayama, Y. Yamada, T. Nakazawa, M. Yamazaki, H. Hongo��281 POSTER SESSIONS. Chairs: T. Allen, J-Y. Park 297 Session I: Fundamental − Irradiation. Chairs: J-H. Kwon, G-G. Lee, C-S. Shin��299 -Multi-scale modelling approach to the estimation of radiation hardening of stainless steels in LWR and SFR environments�by J-H. Kwon, G-G. Lee, C-S. Shin��301 -A study on the change of impact properties by neutron irradiation in modified 9Cr–1Mo steel�by S-H. Kim, W-S. Ryu, Y-W. Kim��303 -Radiation response of ferritic/martensitic cladding steels by K. Field, A. Certain, Y. Yang, T. Allen�305 -Irradiation-induced shifts in master curve reference temperature of ferritic/martensitic steels and welds�by J-H. Yoon, S-H. Kim, D-S. Kim, B-S. Lee, W-S. Ryu��307 -Mechanical properties of welded and irradiated 9Cr-1Mo-1W steel�by D-W. Kim, S-H. Kim, W-S. Ryu��309 -Computer simulation on the isochronal annealing of irradiated Fe using the kinetic Monte Carlo method by G.G. Lee, J.H. Kwon�313 -Creep properties in air and helium environments of Alloy 617 For a VHTR by W.G. Kim, S.N. Yin, G.G. Lee, J.Y. Park, Y.W. Kim�315 Session II: Metal-Compatibility. Chairs: D.Y. Ku, M.Y. Ahn, I.K. Yu, S. Cho, H.G. Lee, K.J. Jung� 317 -Thermal fatigue and thermal ageing test of low activation ferrite/martensitic steel for helium-cooled solid breeder TBM�by D.Y. Ku, M.Y. Ahn, I.K. Yu, S. Cho, H.G. Lee, K.J.
  2. Jung�319 -Corrosion behaviour of 316LN in static liquid lead-bismuth eutectic X. Fu, B. Long, J. Zhang, F. Chu, Y. Xu, A. Gessi� 321 -Compatibility of CLAM steel 9Cr2WVTa with flowing lead by J. Zhang, X. Fu, B. Long, F. Chu, Y. Xu, A. Gessi��323 -Ageing effects of nickel-based superalloys on mechanical properties for VHTR applications by D. Kim, I. Sah, C. Jang�325 -Effects of carburisation and decarburisation on the mechanical properties of nickel-based superalloys for VHTR applications by D. Kim, I. Sah, C. Jang�329 -Effect of He environment on the microstructure and creep properties of Inconel Alloy 617 at high temperature�by G.G Lee, D.J. Kim, W.G. Kim, J.Y. Park��331 -Hydrogen effect on nickel and nickel oxide phase transition at hydrogenated water environment by H-O. Nam, I-S. Hwan, K-H. Lee 333 Session III: Ceramic. Chairs: E-S. Kim, S-H. Chi, Y-W. Kim 343 -Fracture behaviour of nuclear-grade graphite for VHTR�by E-S. Kim, S-H. Chi, Y-W. Kim��345 -Property changes of nuclear grade Cf/C composite by oxidation by�J-Y. Park, C-H. Jung, W-J. Kim, J. Sumita, T. Shibata, K. Sawa, I. Fujita, T. Takagi, T. Makita��347 -Properties of SiC/SiCf fabricated by slurry infiltration by G-Y. Gil, N. Alfian, D-H. Yoon, W-J. Kim, J-Y. Park�349 -Low-temperature sintering of SiC using ternary aluminium carbides by S-H. Lee, H-D. Kim��351 -Determination of the theoretical density and Young’s modulus of ceramic ZrO2 doped with neutron absorbers by Z. He, Z.L. Pan�353 Session IV: Novel Materials Pathways. Chairs: N.Y. Iwata, T. Liu, R. Kasada, A. Kimura, T. Okuda, M. Inoue, S. Ukai, S. Ohnuki, T. Fujisawa, F. Abe 365 -Influence of processing parameters on the microstructure and Charpy impact properties of ODS ferritic steels�by�N.Y. Iwata, T. Liu, R. Kasada, A. Kimura, T. Okuda, M. Inoue, F. Abe, S. Ukai, S. Ohnuki, T. Fujisawa��367 -Preliminary results of grain refinement of ODS alloy by equal channel angular pressing�by J-S. Jang, M-H. Kim, C-H. Han, H-J. Ryu, X. Zhang, D. Foley, K.T. Hartwig�369 -Effect of different insert materials on transient liquid phase bonded ODS ferritic steels for advanced nuclear systems by S-H. Noh, R. Kasada, A. Kimura�371 -Fracture toughness and Charpy impact properties of cold-worked F82H steels�by B-J. Kim, R. Kasada, H. Tanigawa, A. Kimura��381 -Study of optimum composition of extra high purity Ni-Cr-W-Si alloy for advanced reprocessing plant�byI. Ioka, J. Suzuki, K. Kiuchi, J. Nakayama��391 -Effects of lower nitrogen and higher boron in ferritic/martensitic steels for a SFR fuel cladding by J-H. Baek, C.H. Han, J.H. Kim, T.K. Kim, W.G. Kim, S.H. Kim, C.B. Lee�401 -Hydrogen cracking of structural materials for innovative nuclear systems: Crack growth mechanism in metals by Y-S. Kim, S-S. Kim, D-W. Kim�403 -A spin-polarised potential for Fe with charge transfer by J. Wallenius, N. Sandberg, G. Ackland�405 Session V: General.�Chairs: A. Zeman, N. Dytlewski, V. Inozemtsev, G. Mank, F. Mulhauser, D. Ridikas, A. Stanculescu 407 -IAEA activities on co-ordinated research of structural materials for advanced reactor systems�by�A. Zeman, N. Dytlewski, G. Mank, F. Mulhauser, D. Ridikas, A. Stanculescu, V. Inozemtsev��409 -Contribution of ITER to research of internal component materials by C.S. Kim, V. Barabash, M. Merola, R. Raffray�417 Annex 1: List of participants 433