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Iwamoto, Osamu
JAEA-Conf 2020-001, p.11 - 16, 2020/12
Katabuchi, Tatsuya*; Hori, Junichi*; Iwamoto, Nobuyuki; Iwamoto, Osamu; Kimura, Atsushi; Nakamura, Shoji; Shibahara, Yuji*; Terada, Kazushi*; Tosaka, Kenichi*; Endo, Shunsuke; et al.
JAEA-Conf 2020-001, p.5 - 9, 2020/12
Fukahori, Tokio
JAEA-Conf 2020-001, p.17 - 20, 2020/12
After 9 years from the accident at TEPCO Fukushima Daiichi Nuclear Power Station, the "on-site" research and development (R&D) situation has been changed into new phase. It can be considered from understanding to predicting by many direct and indirect measurements and analyses. In this presentation, nuclear data needs for 1F decommissioning are revisited according to these situation. The needs for accident evolution characteristics, criticality management, debris storage, waste management, etc. are considered with the view point of R&D on prediction what is going on and will be happened in each stage of decommissioning.
Nakashima, Hiroshi
JAEA-Conf 2020-001, p.69 - 74, 2020/12
J-PARC (Japan Proton Accelerator Research Complex) is a high-energy proton accelerator complex of the world's highest beam power. Because of its very high beam power and its high energy as well as the large-scale accelerator complex, we encountered some very difficult problems on radiation safety design. Various examinations and countermeasures were considered in order to overcome the difficulty. This paper introduces some of them. In addition, some new knowledge obtained during 10 years after completion are described.
Konno, Chikara
JAEA-Conf 2020-001, p.193 - 197, 2020/12
JENDL Activation Cross Section File for Nuclear Decommissioning 2017 (JENDL/AD-2017) was released in 2018. This file includes the data of neutron-induced nuclear reactions for 311 nuclides from 10
eV to 20 MeV. Thus a multi-group neutron activation cross-section library (MAXS/AD-2017) with the same format as MAXS-2015 by Dr. Okumura has been developed from JENDL/AD-2017 with PREPRO 2018 for activation calculations in nuclear facility decommissioning. MAXS/AD-2017 will be converted to ORIGEN libraries and be tested with the JPDR decommissioning data. Then MAXS/AD-2017 will be released.
Fukaya, Yuji; Goto, Minoru; Nakagawa, Shigeaki
JAEA-Conf 2020-001, p.27 - 32, 2020/12
Recently, HTGR attracts a particular attention due to the outstanding safety features especially after the Fukushima Daiichi nuclear disaster, and the R&D is significantly promoted. In this presentation, we introduce the R&D plan of HTGR and the activities related to reactor physics and nuclear data including an experiment by using KUCA. Furthermore, requirement for nuclear data from the HTGR design is discussed.
