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JAEA Reports

Study on the evaluation method to determine the radioactivity concentration in radioactive waste on Oarai Research and Development Institute (FY2019)

Asakura, Kazuki; Shimomura, Yusuke; Donomae, Yasushi; Abe, Kazuyuki; Kitamura, Ryoichi

JAEA-Review 2020-015, 66 Pages, 2020/09

JAEA-Review-2020-015.pdf:4.27MB

The disposal of radioactive waste from the research facility need to calculated from the radioactivity concentration that based on variously nuclear fuels and materials. In Japan Atomic Energy Oarai Research and Development Institute, the study on considering disposal is being advanced among the facilities which generate radioactive waste as well as the facilities which process radioactive waste. This report summarizes a study result in FY2019 about the evaluation method to determine the radioactivity concentration in radioactive waste on Oarai Research and Development Institute.

Journal Articles

Current status of low level radioactive wastes generated from research, industrial and medical

Sakamoto, Yoshiaki

Genshiryoku Bakkuendo Kenkyu (CD-ROM), 26(2), p.127 - 132, 2019/12

JAEA has promoted near surface disposal project for low-level radioactive wastes generated from research, industrial and medical facilities after receiving project approval from the government in 2009. This kind of low level radioactive wastes which were arising from the 1940s are still keeping in each storage buildings. For immediate treatment and disposal of the wastes, technical issue and commercialization of the disposal project are studied by JAEA. The outline of current status of the disposal project of JAEA and some approach to push forward rational treatment and disposal system are presented.

Journal Articles

Approach for the treatment and disposal of dismantling waste (Research reactor)

Sakamoto, Yoshiaki

Genshiryoku Bakkuendo Kenkyu (CD-ROM), 24(2), p.141 - 146, 2017/12

Some research reactors are under decommissioning or preparation for application of decommissioning license for regulation authority in our country. The reasonable treatment and disposal of dismantling waste is important for decommissioning of research reactors. Therefore, in this paper, JAEA's approach of the treatment and disposal of dismantling waste was introduced from the point of view of disposal of low level radioactive waste arising from research, industrial and medical facilities.

Oral presentation

Design study for impermeable function of trench disposal facility for very low level waste generated from research, industrial and medical facilities

Sakai, Akihiro; Nakata, Hisakazu; Amazawa, Hiroya; Kurosawa, Ryohei*; Sato, Makoto*; Kitamura, Yoichi*

no journal, , 

We consider that very low level waste slightly including chemical toxicity material among radioactive waste generated from research, industrial and medical facilities is disposed of in trench disposal facility which is equipped with impermeable layers. We studied the impermeable system which has high performance to prevent the radioactive material from leaching out of waste layer taking into account the combination of geomembrane liners and low permeable materials.

Oral presentation

Challenges for management of radioactively contaminated wastes and volume reduction and reuse/recycling of removed soil derived from the activities for environmental remediation after the Fukushima Daiichi Nuclear Power Station accident; Cost evaluation method for the disposal of low level radioactive waste

Nakata, Hisakazu; Sakai, Akihiro; Amazawa, Hiroya; Sakamoto, Yoshiaki

no journal, , 

Removed soil except those that may be reusable/recyclable would be finally disposed of. A general view is obtained in regards to a disposal concept of low level radioactive wastes generated from research, industrial and medical facilities, for the purpose of contributing to designing final disposal facilities of removed soil. It is analyzed to investigate the issues related to cost evaluation in order to reasonably carry out that design, referring to a cost evaluation methodology applied to a trench-type disposal facility, which has been planned by JAEA, with impermeable layers.

Oral presentation

Development of confirmation methods of waste packages to radioactive wastes generated from research facilities, 2; Construction of radiochemical analytical scheme for metal samples

Shimomura, Yusuke; Kochiyama, Mami; Haraga, Tomoko; Ishimori, Kenichiro; Kameo, Yutaka

no journal, , 

no abstracts in English

Oral presentation

Development of confirmation methods of waste packages to radioactive wastes generated from research facilities, 3; Study of common evaluation method to determine the radioactivity concentration

Hayashi, Hirokazu; Izumo, Sari; Nakata, Hisakazu; Tsuji, Tomoyuki; Amazawa, Hiroya; Sakai, Akihiro

no journal, , 

no abstracts in English

Oral presentation

Oral presentation

Development of confirmation methods of waste packages to radioactive wastes generated from research facilities, 1; Development plan for confirmation methods of waste packages for near surface disposal

Izumo, Sari; Hayashi, Hirokazu; Nakata, Hisakazu; Kameo, Yutaka; Amazawa, Hiroya; Sakai, Akihiro

no journal, , 

no abstracts in English

Oral presentation

Plan and technical development status of disposal of low-level radioactive waste generated from research facilities

Sakai, Akihiro

no journal, , 

Plan of disposal of LLW generated from research facilities and recent topics of technical development of the disposal are explained. At first, regarding the radioactivity evaluation of waste, a study about the reduction of the number of important nuclides by the method that enhances the safety functions of the trench disposal facility is introduced. The installation of impermeable layers and sorption layers in order to reduce the leaching of nuclides and the installation of a cover structure with resistance to human intrusion into the waste layer are examined as the safety functions. Then, regarding the design and operation of trench disposal facilities, a measure that increase the slope angle of the cover soil beforehand is explained in order to prevent the cover soil from settlement caused by voids in the waste containers at the trench disposal facility. We will continue to study the specific design of trench disposal facilities to realize the measures to these issues.

Oral presentation

Waste acceptance criteria for near surface disposal project of low-level radioactive wastes generated in research, industrial and medical facilities

Nakata, Hisakazu

no journal, , 

Low level radioactive wastes are generated from the research and development of the nuclear energy, medical and industrial use of radioisotope in Japan. Almost all the wastes are still in storage without conditioning and/or treatment suitable for final disposal. The total amount of the waste is estimated approximately 590,000 drums. In order to promote the disposal project for the waste generated from both JAEA and others, JAEA has become its implementing organization in 2008. Since then, JAEA carried out preliminary design of near surface disposal facilities under generic site conditions and estimated the total project cost to accommodate the waste quantity to be required; 750,000 drums. In addition, site selection plans and technical studies in designing disposal facilities are also being discussed. In this report, it explains technical studies relating to Waste Acceptance Criteria for supporting appropriate waste conditioning and its planned implementation by the generators.

11 (Records 1-11 displayed on this page)
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