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Okada, Shota; Murakami, Masashi; Kochiyama, Mami; Izumo, Sari; Sakai, Akihiro
JAEA-Testing 2022-002, 66 Pages, 2022/08
JAEA-Testing-2022-002.pdf:2.46MB
Japan Atomic Energy Agency is an implementing organization of burial disposal for low-level radioactive waste generated from research, industrial and medical facilities in Japan. Radioactivity concentrations of the waste are essential information for design of the disposal facility and for licensing process. A lot of the waste subjected to the burial disposal is arising from dismantling of nuclear facilities. Radioactive Wastes Disposal enter has therefore discussed a procedure to evaluate the radioactivity concentrations by theoretical calculation for waste arising from the dismantling of the research reactors facilities and summarized the common procedure. The procedure includes evaluation of radioactive inventory by activation calculation, validation of the calculation results, and determination of the disposal classification as well as organization of the data on total radioactivity and maximum radioactivity concentration for each classification. For the evaluation of radioactive inventory, neutron flux and energy spectra are calculated at each region in the reactor facility using two- or three-dimensional neutron transport code. The activation calculation is then conducted for 140 nuclides using the results of neutron transport calculation and an activation calculation code. The recommended codes in this report for neutron transport calculation are two-dimensional discrete ordinate code DORT, three-dimensional discrete ordinate code TORT, or Monte Carlo codes MCNP and PHITS, and for activation calculation is ORIGEN-S. Other recommendation of cross-section libraries and calculation conditions are also indicated in this report. In the course of the establishment of the procedure, Radioactive Wastes Disposal Center has discussed the commonly available procedure at meetings. It has periodically held to exchange information with external operators which have research reactor facilities. The procedure will properly be reviewed and be revised by reflecting future situ
Murakami, Masashi; Hoshino, Yuzuru; Nakatani, Takayoshi; Sugaya, Toshikatsu; Fukumura, Nobuo*; Sanda, Toshio*; Sakai, Akihiro
JAEA-Technology 2019-003, 50 Pages, 2019/06
JAEA-Technology-2019-003.pdf:4.42MB
Toward the establishment of a common approach to determine the radioactivity concentrations in dismantling wastes arising from research reactors, radionuclide concentrations in the reactor structure materials of aluminum, carbon steel, shield concrete, and graphite of TRIGA Mark II reactor at Rikkyo University, Japan, were evaluated with both radiochemical analysis and theoretical calculation. The measured nuclides by the radiochemical analysis were 
H, 
Co, and 
Ni in aluminum, H, Co, Ni, and 
Eu in carbon steel, H, Co, and Eu in shield concrete, and H, 
C, Co, Ni, and Eu in graphite. Neutron-flux distributions and neutron-induced activities were computed with DORT and ORIGEN-ARP codes, respectively. Using the results of material composition analysis, radioactivity concentrations were conservatively predicted with good accuracy except for graphite material.
Tsuchiya, Kunihiko; Nagao, Yoshiharu
Kinzoku, 86(10), p.893 - 899, 2016/10
no abstracts in English
Tsuji, Hirokazu; Miya, Kenzo*
Nucl. Eng. Des., 155, p.527 - 546, 1995/00
Times Cited Count：1 Percentile：16.76(Nuclear Science & Technology)no abstracts in English
Tsuji, Hirokazu; Miya, Kenzo*
Nucl. Eng. Des., 155, p.547 - 557, 1995/00
Times Cited Count：2 Percentile：28.65(Nuclear Science & Technology)no abstracts in English
Tsuji, Hirokazu; Miya, Kenzo*
Preprints of the Post SMiRT Seminar No. ll on Construction Codes and Engineering, p.3.4-1 - 3.4-19, 1991/08
no abstracts in English
Tsuji, Hirokazu; Miya, Kenzo*
Preprints of the Post SMiRT Seminar No. ll on Construction Codes and Engineering, p.3.4-20 - 3.4-39, 1991/08
no abstracts in English
Tsuji, Hirokazu; ; Nakajima, Hajime
JAERI-M 90-191, 126 Pages, 1990/11
no abstracts in English
Shimomura, Yusuke; Kochiyama, Mami; Haraga, Tomoko; Ishimori, Kenichiro; Kameo, Yutaka
no journal, ,
no abstracts in English
Hayashi, Hirokazu; Izumo, Sari; Nakata, Hisakazu; Tsuji, Tomoyuki; Amazawa, Hiroya; Sakai, Akihiro
no journal, ,
no abstracts in English
Hayashi, Hirokazu
no journal, ,
In the seminar on evaluating the radioactivity of wastes subject to near surface pit and trench disposal, the lecturer will report on the study of a common method for evaluating the radioactivity of wastes from research facilities in JAEA, as one of the method for confirmation related to waste package by the regulator.
