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Sono, Hiroki
Robutsuri No Kenkyu (Internet), (78), 12 Pages, 2025/03
The Static Experiment Critical Facility (STACY) was renovated from a "solution fuel reactor" to a "reactor using fuel rods and light water moderator", and restarted operation on August 2, 2024, after a hiatus of 13 years and 8 months. During that time, it took 8 years and 11 months to obtain its permission and approval, 3 years and 1 month for its construction, and 4 months for pre-operation inspections on the reactor performance. This article reports on the history of STACY from its birth to its restart of operation, as well as its future utilization.
Maruyama, Shuhei
Robutsuri No Kenkyu (Internet), (78), 7 Pages, 2025/03
no abstracts in English
Watanabe, Tomoaki
Robutsuri No Kenkyu (Internet), (77), 3 Pages, 2024/06
no abstracts in English
Tada, Kenichi
Robutsuri No Kenkyu (Internet), (77), 6 Pages, 2024/06
The author participated in the international conference on reactor physics (Physor2024) held in San Francisco, U.S.A. from April 21 to 24, 2024. This article shows the overview of two workshops, i.e., the demonstration of the multi-physics platform Kraken at VTT and MOOSE at INL, the overview of two sections, i.e., "Data Methods, Code Validation" and "Multi-Physics Reactor Simulations and Validation", and the author's impressions of the conference.
Gunji, Satoshi
Robutsuri No Kenkyu (Internet), (77), 11 Pages, 2024/06
I participated in the international reactor physics conference PHYSOR2024 and summarized the overview and impressions of the conference.
Fujita, Tatsuya
Robutsuri No Kenkyu (Internet), (77), 4 Pages, 2024/06
This is a report on the International Conference on Reactor Physics (PHYSOR2024) held in April 2024. In the "Robutsuri-No-Kenkyu," a newsletter of the Reactor Physics Division in the Atomic Energy Society of Japan, participation reports are written from the viewpoints of university professors and students, vendor engineers, and research institute researchers. This report describes the contents of the research presentations at this international conference from the perspective of the research institute researcher.
Tada, Kenichi
Robutsuri No Kenkyu (Internet), (75), 13 Pages, 2023/03
In addition to nuclear data processing, FRENDY has various functions such as editing nuclear data and plotting cross section data. This document introduces these functions.
Okita, Shoichiro
Robutsuri No Kenkyu (Internet), (75), 3 Pages, 2023/03
This paper is a report on the International Conference on Physics of Reactors 2022 (PHYSOR2022), held in Pittsburgh, USA, from 15-19 May 2022.
Kondo, Ryoichi
Robutsuri No Kenkyu (Internet), (75), 3 Pages, 2023/03
The author received the encouragement award from the reactor physics division of the atomic energy society of Japan. The research on the RSE (Resonance calculation using energy Spectrum Expansion) method, which is the subject of the award, is described for the bulletin of the reactor physics division.
Tada, Kenichi
Robutsuri No Kenkyu (Internet), (73), 5 Pages, 2021/03
This report is overview of FRENDY training course held in Oct. 2020. This report gives speaker's impressions.
Katano, Ryota
Robutsuri No Kenkyu (Internet), (71), 3 Pages, 2019/02
no abstracts in English
Tada, Kenichi
Robutsuri No Kenkyu (Internet), (71), 13 Pages, 2019/02
The nuclear data processing is very important to connect between the evaluated nuclear data library and the particle transport calculation code. However, many nuclear engineers do not know well about the nuclear data processing. This paper describes the overview of nuclear data processing and our nuclear data processing code FRENDY. This paper also lists references about the nuclear data processing.
Yokoyama, Kenji
Robutsuri No Kenkyu (Internet), (70), 12 Pages, 2018/04
no abstracts in English
Tada, Kenichi; Hagura, Naoto*
Robutsuri No Kenkyu (Internet), (67), 105 Pages, 2015/03
In 2014 AESJ autumn meeting, the session, that the title name is current condition and future status of the human resources for the reactor physics field, was presented. In this session, the employment status was investigated and the questionnaire was desigined. In this paper, the detail result of the emplyment status and the questionnaire was described.
Suyama, Kenya
Robutsuri No Kenkyu (Internet), (66), p.11 - 14, 2014/03
The development of an original nuclear data processing code has been recognized as the most important issue in Japan. This report describes the background information on the development of it carried out in JAEA.
Iwamoto, Yosuke; Iwamoto, Hiroki; Harada, Masahide; Niita, Koji*; Sawai, Tomotsugu
Robutsuri No Kenkyu (Internet), (65), p.1 - 3, 2013/03
The displacement cross sections for common structural materials were calculated using the radiation damage model in PHITS. The displacement cross sections with the defect production efficiency gave good agreement with experimental data. For application to the DPA calculations at 400 MeV proton and 40 MeV deuteron, calculated cross sections were folded into calculated particle fluxes in PHITS. Thus the PHITS including the displacement cross sections can be useful to calculate the DPA values in materials used at accelerator facilities that will be exposed to intense primary and secondary particle irradiation. It will also be useful at fission and fusion reactor facilities.
Suyama, Kenya
Robutsuri No Kenkyu (Internet), (64), 18 Pages, 2012/03
In order to take required countermeasure to the Fukushima Dai-ichi NPPs accident after the 2011 off the Pacific coast of Tohoku Earthquake, we had evaluated the radioactivity existing in the reactor cores of the Fukushima Dai-ichi NPPs (i.e. inventory calculation). This report describes the outline of the inventory calculation for that accident and the status of the assay data of spent nuclear fuel for severe accident evaluation.
Suzuki, Takayuki
Robutsuri No Kenkyu, (63), p.2_1 - 2_9, 2011/03
Prototype fast breeder reactor Monju restarted in May, 2010. The result of the first step of its System Start up Test (Core Confirmation Test) is reported. In this test, major core characteristics including criticality, control rod worth and isothermal temperature coefficient were measured. JAEA's calculation method developed for commercial reactor has good accuracy in the analysis of this test.
Usami, Shin
Robutsuri No Kenkyu, (58), p.37 - 39, 2006/02
no abstracts in English
Nakakawa, Masayuki
Robutsuri No Kenkyu, (51), p.47 - 51, 2000/12
no abstracts in English
