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Journal Articles

Rules for flaw interaction for subsurface flaws in operating pressurized vessels; Technical basis of code case N-877

Lacroix, V.*; Dulieu, P.*; Blasset, S.*; Tiete, R.*; Li, Y.; Hasegawa, Kunio; Bamford, W.*; Udyawar, A.*

Proceedings of 2018 ASME Pressure Vessels and Piping Conference (PVP 2018), 10 Pages, 2018/07

JAEA Reports

Status of international cooperation in nuclear technology on testing/research reactors between JAEA and INP-NNC

Kawamura, Hiroshi; Chakrov, P.*; Tsuchiya, Kunihiko; Gizatulin, S.*; Takemoto, Noriyuki; Chakrova, Y.*; Kimura, Akihiro; Ludmila, C.*; Tanimoto, Masataka; Asset, S.*; et al.

JAEA-Review 2011-042, 46 Pages, 2012/02

JAEA-Review-2011-042.pdf:2.69MB

Based on the implementing agreement between National Nuclear Center of the Republic of Kazakhstan (NNC) and the Japan Atomic Energy Agency (JAEA) for the Nuclear Technology on Testing/Research Reactors in the cooperation in Nuclear Energy Research and Development in Nuclear Energy and Technology, four specific topics of cooperation (STC) have been carried out from June, 2009. Four STCs are as follows; (1) STC No.II-1: International Standard of Instrumentation, (2) STC No.II-2: Irradiation Technology of RI Production, (3) STC No.II-3: Lifetime Expansion of Beryllium Reflector, (4) STC No.II-4: Irradiation Technology for NTD-Si. The information exchange, personal exchange and cooperation experiments are carried out under these STCs. The status in the field of nuclear technology on testing/research reactors in the implementing arrangement is summarized, and future plans of these specific topics of cooperation are described in this report.

Oral presentation

Collaboration with Republic of Kazakhstan regarding development of HTGR, 3; Collaboration of development of oxidation-resistant graphite material for HTGR

Shibata, Taiju; Sumita, Junya; Nagata, Hiroshi; Saito, Takashi; Tsuchiya, Kunihiko; Sakaba, Nariaki; Osaki, Hiroki*; Kato, Hideki*; Fujitsuka, Kunihiro*; Muto, Takenori*; et al.

no journal, , 

no abstracts in English

Oral presentation

Collaboration with Republic of Kazakhstan regarding development of HTGR, 2; Collaboration of irradiation performance of HTGR fuel

Ueta, Shohei; Mizutani, Yoshitaka; Sakaba, Nariaki; Furihata, Noboru*; Honda, Masaki*; Asset, S.*; Gizatulin, S.*; Chakrov, P.*

no journal, , 

A capsule irradiation test with the high temperature gas-cooled reactor (HTGR) fuel by WWR-K in the Institute of Nuclear Physics of the Republic of Kazakhstan (INP) is being carried out. The HTGR fuel specimens were newly designed at the target burnup of 100 GWd/t. A plan of the irradiation test and results on evaluation of the integrity of the HTGR fuel specimen based on fission gas (FP) release rate under the irradiation are reported.

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