In-situ dismantling of the liquid waste storage tank in the decommissioning program of the JRTF

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

Proceedings of 23rd International Conference on Nuclear Engineering (ICONE-23) (DVD-ROM), 5 Pages, 2015/05

The JAERI's Reprocessing Test Facility (JRTF) was the first engineering-scale reprocessing facility constructed in Japan. The JRTF was operated from 1968 to 1969 to reprocess spent fuels from the Japan Research Reactor No.3 (JRR-3). As a result of the operation (total 3 runs) by PUREX process, 200 g of highly purified plutonium (Pu) were extracted. In this operation, about 70 m of liquid waste was generated and part of this waste, which including Pu, with relatively high radioactivity, was stored in six large tanks. After shutdown of the facility, the JRTF decommissioning program was started in 1990 to develop decommissioning technologies and to obtain experiences and data on dismantling of fuel cycle facilities. Liquid waste in the tanks was treated from 1982 to 1998. Dismantling of tanks started in 2002. The tanks were installed in narrow concrete cells and inside of the cell was high dose area. Dismantling method for the tank is important factor to decide manpower and time for dismantlement. In this paper, in-situ dismantling of the liquid waste storage tank and its preparation work are discussed.

Fabrication of U-Pu-Zr metallic fuel elements for the irradiation test at experimental fast test reactor Joyo

Nakamura, Kinya*; Ogata, Takanari*; Kikuchi, Hironobu; Iwai, Takashi; Nakajima, Kunihisa; Kato, Tetsuya*; Arai, Yasuo; Uozumi, Koichi*; Hijikata, Takatoshi*; Koyama, Tadafumi*; et al.

Nihon Genshiryoku Gakkai Wabun Rombunshi, 10(4), p.245 - 256, 2011/12

https://doi.org/10.3327/taesj.J10.038

Sodium-bonded metallic fuel elements were fabricated for the first time in Japan for the irradiation test in the experimental fast test reactor JOYO. U-20Pu-10Zr fuel slugs of 200 mm in length and approximately 5 mm in diameter were fabricated in a small-scale injection casting furnace. Each fuel slug was loaded into the ferritic martenstic stainless steel (PNC-FMS) cladding tube with the sodium thermal bond, thermal insulator and reflector in a helium gas atmosphere glove box. After top-end plug welding to the cladding tube and heat treatment of the welding area, each fuel element was subjected to the sodium bonding process. After the inspection such as element length, gas plenum length and helium-leak tightness, six metallic fuel elements are transported to the JOYO site for the coming irradiation test.

Three dimensional atomic image of TlInSe by X-ray fluorescence holography

Mimura, Kojiro*; Hosokawa, Shinya*; Happo, Naohisa*; Hu, W.; Hayashi, Koichi*; Wakita, Kazuki*; Ishii, Hirofumi*; Yoshimura, Masato*; Jeyakanthan, J.*; Mamedov, N.*

e-Journal of Surface Science and Nanotechnology (Internet), 9, p.273 - 276, 2011/07

https://doi.org/10.1380/ejssnt.2011.273

Dose response of a gel dosimeter measured by various modalities

Yamanashi, Koichi*; Fujibuchi, Toshio*; Kawamura, Taku*; Hiroki, Akihiro; Yamashita, Shinichi; Nagasawa, Naotsugu; Taguchi, Mitsumasa; Mimura, Koichi*; Ushiba, Hiroaki*

no journal, , 

no abstracts in English

In-situ dismantling of the liquid waste storage tank LV-1 in JRTF, 1; An Outline of the dismantling program

Nakashio, Nobuyuki; Mimura, Ryuji; Muraguchi, Yoshinori; Nemoto, Koichi; Shiraishi, Kunio; Tachibana, Mitsuo; Kubota, Shintaro; Kawagoshi, Hiroshi

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 the outline of the program for dismantling of the LV-1.

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, 6; Evaluation of the removal procedure of the radioactive residue in LV-1

Kubota, Shintaro; Tachibana, Mitsuo; Mimura, Ryuji; Nemoto, Koichi; Shiraishi, Kunio

no journal, , 

no abstracts in English

In-situ dismantling of the liquid waste storage tank LV-1 in the JRTF, 8; Cutting of lower part of the LV-1 tank

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

no journal, , 

no abstracts in English

Study of pelletizing and sintering technologies of secondary wastes produced from contaminated water treatment, 1; Overview of the wastes and the sintering technology

Sato, Junya; Suzuki, Shinji*; Kato, Jun; Sakakibara, Tetsuro; Nakazawa, Osamu; Meguro, Yoshihiro; Ueda, Hiroshi*; Kurosaki, Fumio*; Yoneyama, Takashi*; Matsukura, Minoru*; et al.

no journal, , 

no abstracts in English

Study of pelletizing and sintering technologies of secondary wastes produced from contaminated water treatment, 3; Leach test of sintered pellets

Mori, Koichi*; Komori, Hideyuki*; Kitami, Katsunobu*; Sato, Junya; Nakazawa, Osamu; Meguro, Yoshihiro; Ueda, Hiroshi*; Kurosaki, Fumio*; Matsukura, Minoru*; Mimura, Hitoshi*

no journal, , 

no abstracts in English