Compliance measures at the Radioactive Waste Treatment Facilities at the Nuclear Science Research Institute; Aseismic reinforcement of the Radioactive Waste Treatment Facility No. 3, Waste Size Reduction and Storage Facility, and Waste Volume Reduction Facility

Iketani, Shotaro; Suzuki, Takeshi; Yokobori, Tomohiko; Sugawara, Satoshi; Yokota, Akira; Kikuchi, Genta; Muraguchi, Yoshinori; Kitahara, Masaru; Seya, Manato; Kurosawa, Tsuyoshi; et al.

JAEA-Technology 2025-001, 169 Pages, 2025/08

JAEA-Technology-2025-001.pdf:14.22MB

The radioactive waste treatment facilities at the Nuclear Science Research Institute includes the Radioactive Waste Treatment Facility No. 3, Waste Size Reduction and Storage Facility, and Waste Volume Reduction Facility. These three facilities come under the purview of the Act on the Regulation of Nuclear Source Material, Nuclear Fuel Material and Reactors, and are included under Class C of the act based on the seismic requirements specified in the Act. We assessed the seismic capacity of these three radioactive waste treatment facilities based on the current Building Standards Act, to verify whether they comply with the new regulatory requirements enforced by the Nuclear Regulation Authority (NRA) in the aftermath of the 2011 nuclear accident at the Fukushima Daiichi Nuclear Power Station operated by the Tokyo Electric Power Company. We found that the allowable stress of a few structural members used in the construction of the facilities did not meet the regulatory requirements. After studying the approval granted by the NRA for the construction plans, including the design and construction methods (design and construction plans) of the three facilities on March 5, 2021, we made aseismic reinforcement at these facilities between 2021 and 2022. This report presents an overview of the seismic design of these facilities and an outline of the aseismic reinforcement conducted, management system existing, safety measures adopted, and the preoperational inspections conducted at these facilities.

In-situ dismantling of the liquid waste storage tank LV-1 in the JRTF; The Dismantling preparation work

Yokozuka, Yuta; Sunaoshi, Mizuho*; Fujikura, Toshiki; Suzuki, Shota; Muraguchi, Yoshinori; Handa, Yuichi; Mimura, Ryuji; Terunuma, Akihiro

JAEA-Technology 2020-017, 56 Pages, 2021/01

JAEA-Technology-2020-017.pdf:7.88MB

JAEA has dismantled equipment and instrument in the JAERI's Reprocessing Test Facility (JRTF) since 1996 as a part of its decommissioning. Starting in JFY 2007, in the annex building B which stored liquid waste generated in wet reprocessing tests, the liquid waste storage tank LV-1 installed in the LV-1 room of the first basement was dismantled with the in situ dismantling method. The dismantling preparation work is described in this report. Data on manpower, radiation control, and waste in the preparation work were collected, and its work efficiency was analyzed.

JRTF decommissioning project; Evaluation of project management data concerning dismantling activities of glove boxes, 1

Muraguchi, Yoshinori; Kanayama, Fumihiko; Usui, Hideo; Izumo, Sari; Tachibana, Mitsuo

JAEA-Technology 2012-035, 69 Pages, 2012/12

JAEA-Technology-2012-035.pdf:4.96MB

Dismantling activities of equipment in JAERI's Reprocessing Test Facility (JRTF) used for wet reprocessing test started from 1996. Glove boxes and hoods installed in the main building were dismantled preferentially for securing temporary place of dismantled waste and dismantling tools by dismantling activities. Of these, 8 glove boxes (glove box group) were installed in room 232 of the main building. The glove box group was dismantled by setting up a large plastic enclosure (greenhouse) for work efficiency. In this report, dismantling procedure and actual data obtained from dismantling activity were arranged about dismantling activity of glove box group of room 232 in 1996. About dismantling activity of glove box group, manpower of the basic work items extracted by classifying into common work items and independent work items were analyzed. In addition, calculation equation was examined concerning dismantling of glove boxes.

In-situ dismantling of the liquid waste storage tank LV-1 in JRTF, 5; Removal of the radioactive residue and decontamination in LV-1

Nakashio, Nobuyuki; Muraguchi, Yoshinori; Mimura, Ryuji; Nemoto, Koichi; Shiraishi, Kunio

no journal, , 

no abstracts in English

In-situ dismantling of the liquid waste storage tank LV-1 in JRTF, 9; Cutting of water jacket and legs of the LV-1 tank

Yokozuka, Yuta; Mimura, Ryuji; Fujikura, Toshiki; Muraguchi, Yoshinori; Nemoto, Koichi; Shida, Shigeo

no journal, , 

no abstracts in English

In-situ dismantling of the liquid waste storage tank LV-1 in JRTF, 2; Preparatory works before dismantling

Muraguchi, Yoshinori; Mimura, Ryuji; Nakashio, Nobuyuki; Nemoto, Koichi; Shiraishi, Kunio; Tachibana, Mitsuo

no journal, , 

For the purpose of the development of technology for dismantling and decontamination at the high dose area, dismantling method is applied for the liquid waste storage tank (LV-1) which is in the concrete cell at the JRTF. This report describes about the outline of preparatory works before dismantling and the data obtained from its works.

Treatment of the radioactive metallic waste at the Advanced Volume Reduction Facilities

Nakayama, Yoshihiko; Yoshida, Yoshihiro; Muraguchi, Yoshinori; Ishihara, Keisuke; Yokobori, Tomohiko; Sudo, Tomoyuki

no journal, , 

no abstracts in English