Zobrazeno 1 - 10
of 26
pro vyhledávání: '"Shinya Kosaka"'
Publikováno v:
Journal of Nuclear Science and Technology. 55:756-780
In order to achieve highly accurate resonance calculations with short computation time , a new ultra-fine-group resonance calculation method is developed. The ultra-fine-group method has a limitati...
Publikováno v:
Journal of Nuclear Science and Technology. 55:41-65
A unified resonance self-shielding method, which can treat general sub-divided fuel regions, is developed for lattice physics calculations in reactor physics field. In a past study, a hybrid resona...
Autor:
D. Verrier, Hisatomo Murakami, Edouard Hourcade, Laurent Costes, Gilles Rodriguez, Koichi Higurashi, Haruo Mochida, Yoshio Shimakawa, Franck Dechelette, Koichi Kurita, Kazuhiro Oyama, Benoit Perrin, David Plancq, Frédéric Chanteclair, Nobuyuki Ishikawa, Bernard Carluec, Shigeo Ohki, Frederic Serre, Jean-François Dirat, Marie-Sophie Chenaud, Kazuya Koyama, Christophe Venard, Hidemasa Yamano, Kazuya Takano, Jean-Marie Hamy, Shigenobu Kubo, Toru Iitsuka, Frédéric Varaine, Yumi Yamada, Shinya Kosaka, Fumiaki Kaneko, Ryo Shimizu, Takayuki Ozawa, Masaaki Tanaka
Publikováno v:
EPJ N-Nuclear Sciences & Technologies
EPJ N-Nuclear Sciences & Technologies, 2021, 7, pp.15. ⟨10.1051/epjn/2021014⟩
EPJ N-Nuclear Sciences & Technologies, EDP Sciences, 2021, 7, pp.15. ⟨10.1051/epjn/2021014⟩
EPJ Nuclear Sciences & Technologies, Vol 7, p 15 (2021)
EPJ N-Nuclear Sciences & Technologies, 2021, 7, pp.15. ⟨10.1051/epjn/2021014⟩
EPJ N-Nuclear Sciences & Technologies, EDP Sciences, 2021, 7, pp.15. ⟨10.1051/epjn/2021014⟩
EPJ Nuclear Sciences & Technologies, Vol 7, p 15 (2021)
International audience; In the frame of the France-Japan agreement on nuclear collaboration, a bilateral collaboration agreement on nuclear energy was signed on March 21st, 2017, including a topic dedicated to Sodium-cooled Fast Reactor (SFR). This a
Publikováno v:
Journal of Nuclear Science and Technology. 53:842-869
A new hybrid resonance self-shielding treatment method in reactor physics field is developed by integrating equivalence theory and ultra-fine-group slowing-down calculation from the theoretical point of view. In the conventional equivalence theory, s
Publikováno v:
Volume 3: Thermal-Hydraulics.
Mitsubishi Heavy Industries, Ltd. (MHI) has developed the safety analysis code system, MCOBRA/RELAP5-GOTHIC, for large break LOCA, small break LOCA and containment integrity analyses of PWR. The code system contains three codes, MCOBRA code, M-RELAP5
Autor:
Shinya Kosaka, Tatsuya Fujita, Kenichiro Nozaki, Tomohiro Endo, Akio Yamamoto, Go Hirano, Kenichi Tada
Publikováno v:
Journal of Nuclear Science and Technology. 49:689-707
An optimization approach to establish an appropriate multi-group energy structure for boiling water reactor (BWR) pin-by-pin fine mesh core analysis is proposed. In the present approach, the number of energy groups of cross sections is successively r
Autor:
Shinya Kosaka, Go Hirano, Tatsuya Fujita, Kenichiro Nozaki, Tomohiro Endo, Akio Yamamoto, Kenichi Tada
Publikováno v:
Journal of Nuclear Science and Technology. 48:1437-1452
Three-dimensional pin-by-pin core analysis is considered to be a candidate for the next-generation BWR core calculation method. In our previous study, the applicability of the transport and burnup calculations for a three-dimensional pin-by-pin BWR c
Publikováno v:
Annals of Nuclear Energy. 37:22-27
The pin-by-pin fine mesh BWR core analysis code SUBARU has been developed as a next-generation BWR core analysis code. SUBARU is based on the SP3 theory and the response matrix method is used for flux calculations. The SP3 theory consists of the 0th
Publikováno v:
AIP Conference Proceedings.
This paper introduces recent improvements for reactor physics codes in Mitsubishi Heavy Industries, Ltd(MHI). MHI has developed a new neutronics design code system Galaxy/Cosmo-S(GCS) for PWR core analysis. After TEPCO’s Fukushima Daiichi accident,
Publikováno v:
Annals of Nuclear Energy. 33:1315-1321
The anisotropic scattering effect to keff is studied for UO2 and MOX fueled BWR assemblies. The anisotropic scattering effect increases the assembly k∞ by 0.44% Δk for the UO2 assembly with 0% void fraction, and by 0.21% Δk for the MOX assembly w