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Nakazato, Wataru*; Taninaka, Hiroshi
Nihon Genshiryoku Gakkai-Shi ATOMO
, 54(1), p.68 - 69, 2012/01
no abstracts in English
Sugino, Kazuteru; Nakazato, Wataru*; Moriwaki, Hiroyuki*
no journal, ,
JENDL-4.0 is planned to be applied to the core neutronics design for next generation FBRs. In order to improve the accuracy and reliability of the neutronics core design, reflection of the accumulated integral data is essential, which are obtained in critical facility experiments and power reactor tests. Additionally, the specific method of reflection should be prudently selected based on the comparison in advantages and disadvantages from the various points of view. The present study shows the general consistency between the calculation data of experiments/tests and the covariance data of cross-sections by comparing the prediction accuracies of neutronics core design using the combinations of several core design methods and uncertainty evaluation methods based on the constant set with JENDL-4.0.
Sugino, Kazuteru; Ohgama, Kazuya; Nakazato, Wataru*; Moriwaki, Hiroyuki*
no journal, ,
Towards realizations of the demonstration reactor in around 2025 and the commercialized reactor in around 2050, a investigation on the conceptual core design of the sodium-cooled fast reactor (JSFR: Japan Sodium-cooled Fast Reactor) is under going. This paper presents the elavuation of the core design prediction accuracy based on the studies related to the latest nuclear data.
Oki, Shigeo; Kugo, Teruhiko; Nakazato, Wataru*; Moriwaki, Hiroyuki*
no journal, ,
no abstracts in English
Oki, Shigeo; Kugo, Teruhiko; Nakazato, Wataru*; Moriwaki, Hiroyuki*
no journal, ,
no abstracts in English
Nakazato, Wataru*; Kan, Taro*; Oki, Shigeo
no journal, ,
no abstracts in English
Takano, Kazuya; Taninaka, Hiroshi; Maruyama, Shuhei; Kuwagaki, Kazuki; Oki, Shigeo; Kan, Taro*; Nakazato, Wataru*; Oshima, Takumi*; Fukuchi, Ikuo*; Koike, Hiroki*; et al.
no journal, ,
As a part of the international collaboration between France and Japan for the development of sodium-cooled fast reactors (SFRs) since 2020, VVUQ on neutronics and shielding design methods for fast reactors has been jointly studied and the methods and effects on prediction accuracy improvements have been assessed. The Japan-France joint experimental database, numerical benchmark problems, and VVUQ methods obtained through this cooperation will be an important knowledge for obtaining a licensing approval for neutronics design and shielding design of future SFRs for demonstration and commercialization.