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JAEA Reports

Study on waste acceptance criteria for waste packages destined for near surface disposal containing radioactive waste from research, industrial and medical facilities; Minimization of the amounts of scattering radionuclides caused by dropping impact

Nakata, Hisakazu; Okada, Shota; Amazawa, Hiroya; Sakai, Akihiro

JAEA-Technology 2023-021, 31 Pages, 2024/01

JAEA-Technology-2023-021.pdf:2.53MB

Radioactive waste packages, which Japan Atomic Energy Agency (JAEA) plans to dispose of, must meet the technical criteria specified by the Order of Nuclear Regulation Authority. One criteria is newly specified in 2019 such that it shall be impact resistant performance so as to be few in quantity of radionuclides released from the waste package in case of dropping from the maximum height assumed in the disposal process. Then, JAEA needs to prove the compliance of the waste package with the technical criteria by estimating the leakage of radionuclides. In this report, the amounts of scattering materials inside two waste packages caused by dropping impact from 8m height was estimated by numerical analysis, providing the ratio of the amounts of scattering materials to the weight of the waste package. The analysis objects were 1m$$^{3}$$ cube container-filled and solidified waste package containing metal waste, which are expected to emplace into a vault-type disposal facility. Some considerations relating to the production method of the waste package using 1m$$^{3}$$ cubic container and its waste acceptance criteria are provided on the basis of the drop analysis in this report.

Journal Articles

Development of waste acceptance criteria and current challenges relating to the disposal project of LLW generated in research, medical and industrial facilities

Nakata, Hisakazu; Amazawa, Hiroya; Izumo, Sari; Okada, Shota; Sakai, Akihiro

Dekomisshoningu Giho, (58), p.10 - 23, 2018/09

Low level radioactive wastes are generated in the research and development of the nuclear energy, medical and industrial use of radioisotope except NPP in Japan. The disposal of wastes arising from NPP has already been implemented while not the one for wastes from research institutes etc. Japan Atomic Energy Agency therefore has been assigned an implementing organization for the disposal legally in 2008 in order to promote the disposal program as quickly and firmly as possible. Since then, JAEA has conducted their activity relating to the disposal facility design on generic site conditions and developing Waste Acceptance Criteria for LLW from research institutes. This report summarizes the WAC and current challenges.

JAEA Reports

None

Toyohara, Masumitsu*; Hirayama, Fumio*; Tamura, Toshiyuki*; Fukazawa, Takuji*; Igarashi, Noboru*

PNC TJ8164 96-010, 213 Pages, 1996/03

PNC-TJ8164-96-010.pdf:7.49MB

no abstracts in English

Oral presentation

Oral presentation

Disposal project of LLW generated in research, medical and industrial facilities; Investigation of method filling voids in waste for trench disposal

Nakata, Hisakazu; Izumo, Sari; Amazawa, Hiroya; Sakai, Akihiro

no journal, , 

JAEA is working toward the establishment of disposal facilities for waste from research facilities in Japan, in accordance with the Law and the government's basic policy (2008). For burial disposal, it is necessary to make burial waste that meet the acceptance criteria for safety. This report presents the results of tests conducted to confirm the method meeting the waste acceptance criteria for voids as for trench disposal.

Oral presentation

Disposal project of LLW generated in research, medical and industrial facilities; Evaluation of radioactivity concentration corresponding to dose criterion

Saito, Tatsuo; Sugaya, Toshikatsu; Sakai, Akihiro; Kamei, Gento

no journal, , 

In Japan, low-level radioactive wastes generated from research institutes, universities and medical institutions are continuously stored without being buried. Therefore, the Japan Atomic Energy Agency (JAEA) has been an implementation body of the burial project of the radioactive wastes from research facilities. In this report, the characteristics of the wastes and the conceptional design of the JAEA burial facilities are introduced, and the current status of the study on the radioactivity concentrations corresponding to dose criterion for trench disposal and pit disposal is also presented.

Oral presentation

Development of measurement method for methane gas generation volume due to decomposition of combustible materials disposed of in trench disposal facilities

Nakamura, Mizuki; Sato, Junya; Nakata, Hisakazu; Sakai, Akihiro; Osugi, Takeshi

no journal, , 

no abstracts in English

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