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Hatakeyama, Yuichi; Hirai, Koki; Ikegami, Yuta*; Sano, Naruto; Tomita, Takeshi; Usami, Koji; Tagami, Susumu
JAEA-Technology 2024-020, 33 Pages, 2025/03
JAEA-Technology-2024-020.pdf:2.21MB
The Waste Safety Testing Facility (WASTEF) is a facility that began operation in December 1982 with the aim of conducting safety testing research on the long-term storage and subsequent geological disposal of high-level radioactive waste generated by the reprocessing of spent fuel. This facility is composed of five concrete cells, one lead cell, six glove boxes, and seven hoods, and is a large-scale facility capable of using nuclear fuel materials including uranium and plutonium, as well as radioisotopes such as neptunium and americium. The facility is equipped with an automatic fire alarm system for the entire building in accordance with the Fire Service Act and regulations on technical standards for facilities used. This is an important aspect of safety management, and it is required that the equipment be sufficiently sound and reliable. However, after more than 30 years of use since its installation, the fire receiving panel, one of the components of the automatic fire alarm system, has deteriorated significantly. Furthermore, many of the parts used have been discontinued and are no longer available, making it difficult to procure them, making it difficult to maintain the equipment's performance. Therefore, in order to ensure the safe and stable operation of WASTEF, the fire receiving panel was updated. This report summarizes the update of the fire receiving panel among the automatic fire alarm equipment that was implemented in FY2022.
Hayashizaki, Kohei; Hirooka, Shun; Yamada, Tadahisa*; Sunaoshi, Takeo*; Murakami, Tatsutoshi; Saito, Kosuke
Ceramics (Internet), 8(1), p.24_1 - 24_12, 2025/03
Sano, Naruto; Yamashita, Naoki; Watanabe, Masaya; Tsukada, Manabu*; Hoshino, Kazutoyo*; Hirai, Koki; Ikegami, Yuta*; Tashiro, Shinsuke; Yoshida, Ryoichiro; Hatakeyama, Yuichi; et al.
JAEA-Technology 2023-029, 36 Pages, 2024/03
JAEA-Technology-2023-029.pdf:2.47MB
At the Waste Safety Testing Facility (WASTEF), the gamma ray irradiation device "Gamma Cell 220" was relocated from the 4th Research Building of the Nuclear Science Research Institute in FY2019, and the use of gamma ray irradiation has begun. Initially, Fuel Cycle Safety Research Group, Fuel Cycle Safety Research Division, Nuclear Safety Research Center, Sector of Nuclear Safety Research and Emergency Preparedness, the owner of this device, conducted the tests as the main user, but since 2022, other users, including those outside the organization, have started using it. The gamma ray irradiation device "Gamma Cell 220" is manufactured by Nordion International Inc. in Canada. Since it was purchased in 1989, the built-in 
Co radiation source has been updated once, and safety research related to nuclear fuel cycles, etc. It is still used for this purpose to this day. This report summarizes the equipment overview of the gamma ray irradiation device "Gamma Cell 220", its permits and licenses at WASTEF, usage status, maintenance and inspection, and future prospects.
Cantarel, V.; Motooka, Takafumi; Yamagishi, Isao
JAEA-Review 2017-014, 36 Pages, 2017/06
JAEA-Review-2017-014.pdf:3.37MB
After a necessary decay time, the zeolites used for the water decontamination will eventually be conditioned for their long-term storage. Geopolymer is considered as a potential matrix to manage radioactive cesium and strontium containing waste. For such applications, a correct comprehension of the binder structure, its macroscopic properties, its interactions with the waste and the physico-chemical phenomena occurring in the waste form is needed to be able to judge of the soundness and viability of the material. Although the geopolymer is a young binder, a lot of research has been carried out over the last fifty years and our understanding of this matrix and its potential applications is progressing fast. This review aims at gathering the actual knowledge on geopolymer studies about geopolymer composites, geopolymer as a confinement matrix for nuclear wastes and geopolymer under irradiation. This information will finally provide guidance for the future studies and experiments.
Department of Hot Laboratories
JAERI-Review 2001-044, 95 Pages, 2001/12
JAERI-Review-2001-044.pdf:6.55MB
no abstracts in English
Motooka, Takafumi; Terakado, Shogo; Koya, Toshio; Hamada, Shozo; Kiuchi, Kiyoshi
JAERI-Tech 2001-023, 29 Pages, 2001/03
JAERI-Tech-2001-023.pdf:2.21MB
no abstracts in English
Department of Hot Laboratories
JAERI-Review 2000-015, 113 Pages, 2000/09
JAERI-Review-2000-015.pdf:6.09MB
no abstracts in English
Department of Hot Laboratories
JAERI-Review 99-026, p.118 - 0, 1999/11
JAERI-Review-99-026.pdf:9.93MB
no abstracts in English
Department of Hot Laboratories
JAERI-Review 98-023, 97 Pages, 1998/12
JAERI-Review-98-023.pdf:5.35MB
no abstracts in English
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JAERI-M 93-016, p.58 - 63, 1993/02
no abstracts in English
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JAERI-M 86-131, 104 Pages, 1986/09
no abstracts in English
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JAERI-M 85-090, 77 Pages, 1985/07
no abstracts in English
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JAERI-M 84-133, 91 Pages, 1984/06
no abstracts in English
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JAERI-M 83-076, 74 Pages, 1983/06
no abstracts in English
Hata, Kuniki; Okada, Yuji; Ha, Yoosung; Ushijima, Hiroki; Mitsui, Kento; Fuyushima, Takumi; Ishijima, Yasuhiro; Nio, Daisuke; Watanabe, Masaya; Katsuyama, Jinya
no journal, ,
no abstracts in English
Watanabe, Masaya; Ha, Yoosung; Matsumoto, Naoya*; Hoshino, Kazutoyo*; Sano, Naruto; Tagami, Susumu; Usami, Koji; Hata, Kuniki; Chimi, Yasuhiro
no journal, ,
no abstracts in English
