Update of fire receiver panel (The Waste Safety Testing Facility)

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.

Application of the spectral determination method to liquid scintillation spectra

Oshima, Masumi*; Goto, Jun*; Hayakawa, Takehito*; Shinohara, Hirofumi*; Suzuki, Katsuyuki*; Sano, Yuichi*; Asai, Masato; Haraga, Tomoko

Journal of Nuclear Science and Technology, 61(7), p.871 - 882, 2024/07

https://doi.org/10.1080/00223131.2023.2282552

Previously we reported a simple algorithmic method of spectral determination method (SDM), which is based on the first principle that a -ray spectrum obtained for a sample is a linear superposition of individual spectra of the radioactive nuclides included in the sample and demonstrated that the method is valid for -ray determination. Here we apply it to the spectra obtained by liquid scintillation counter (LSC). In LSC measurements quenching is generally observed and we at first developed its correction method to standard spectra. The SDM code reported in the previous investigation is used to analyze the LSC spectra. Based on the analyses done by using the measured spectra, we concluded that the SDM method is valid in the LSC spectra similarly to the -ray spectra studied in the previous investigation.

Optimization in granulation conditions for adsorbent of extraction chromatography

Hasegawa, Kenta; Goto, Ichiro*; Miyazaki, Yasunori; Ambai, Hiromu; Watanabe, So; Watanabe, Masayuki; Sano, Yuichi; Takeuchi, Masayuki

Mechanical Engineering Journal (Internet), 11(2), p.23-00407_1 - 23-00407_8, 2024/04

https://doi.org/10.1299/mej.23-00407

Utilization of gamma ray irradiation at the WASTEF Facility

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.

Low reactivity of stoichiometric FeS with hydrogen at high-pressure and high-temperature conditions

Takano, Masahiro*; Kagi, Hiroyuki*; Mori, Yuichiro*; Aoki, Katsutoshi*; Kakizawa, Sho*; Sano, Asami; Iizuka-Oku, Riko*; Tsuchiya, Taku*

Journal of Mineralogical and Petrological Sciences (Internet), 119(1), p.240122_1 - 240122_9, 2024/00

https://doi.org/10.2465/jmps.240122

Hydrogenation of iron sulfide (FeS) under high-pressure and high-temperature conditions has attracted attention because hydrogen and sulfur are promising candidates as light elements in the cores of the Earth and other terrestrial planets. In earlier reports describing the hydrogenation of FeS, the chemical compositions of starting materials were not fully clarified. This study reports in-situ neutron and X-ray diffraction measurements under high-pressure and high-temperature conditions of an Fe-S-H system using a stochiometric Fe1.000S (troilite) as a starting material. The occupancies determined were significantly lower than those reported from earlier studies, indicating that the hydrogenation of FeS can be affected strongly by the stoichiometry of iron sulfide.

Competitive distribution of europium and samarium based on reaction rate-limiting process in nitrilotriacetamide extractant-impregnated polymer-coated silica particles

Miyagawa, Akihisa*; Hayashi, Naoki*; Iwamoto, Hibiki*; Arai, Tsuyoshi*; Nagatomo, Shigenori*; Miyazaki, Yasunori; Hasegawa, Kenta; Sano, Yuichi; Nakatani, Kiyoharu*

Bulletin of the Chemical Society of Japan, 96(9), p.1019 - 1025, 2023/09

https://doi.org/10.1246/bcsj.20230142

In the present study, we have elucidated the mass transfer mechanism of Eu(III) and Sm(III) in the solution with these ions in single nitrilotriacetamide (NTA) extractant-impregnated polymer-coated silica particle. The rate-limiting process of mass transfer was the reaction process of ions with NTA molecules, in which the NO ions were not involved, which was consistent with that obtained in single ion distribution system.

Kinetic mass transfer behavior of Eu(III) in nitrilotriacetamide-impregnated polymer-coated silica particles

Miyagawa, Akihisa*; Hayashi, Naoki*; Kuzure, Yoshiaki*; Takahashi, Takumi*; Iwamoto, Hibiki*; Arai, Tsuyoshi*; Nagatomo, Shigenori*; Miyazaki, Yasunori; Hasegawa, Kenta; Sano, Yuichi; et al.

Bulletin of the Chemical Society of Japan, 96(7), p.671 - 676, 2023/07

https://doi.org/10.1246/bcsj.20230087

We investigated the distribution mechanism of Eu(III) in a single polymer-coated silica particle including nitrilotriacetamide (NTA) extractants known as HONTA and TOD2EHNTA. The present study provides a valuable approach for the evaluation and enhancement of the functionality of "single extractant-impregnated polymer-coated silica particle".

Development of engineering scale extraction chromatography separation system, 1; Overview of developments in engineering scale system

Watanabe, So; Takahatake, Yoko; Hasegawa, Kenta; Goto, Ichiro*; Miyazaki, Yasunori; Watanabe, Masayuki; Sano, Yuichi; Takeuchi, Masayuki

Proceedings of 30th International Conference on Nuclear Engineering (ICONE30) (Internet), 6 Pages, 2023/05

Kinetics and mechanism of Eu(III) transfer in tributyl phosphate microdroplet/HNO aqueous solution system revealed by fluorescence microspectroscopy

Miyagawa, Akihisa*; Kusano, Yuka*; Nagatomo, Shigenori*; Sano, Yuichi; Nakatani, Kiyoharu*

Analytical Sciences, 38(7), p.955 - 961, 2022/07

https://doi.org/10.1007/s44211-022-00117-3

In this study, we reveal an Eu(III) extraction mechanism at the interface between HNO and tributyl phosphate (TBP) solutions using fluorescence microspectroscopy. The mass transfer rate constant at the interface is obtained from the analysis of fluorescence intensity changes during the forward and backward extractions at various HNO and TBP concentrations to investigate the reaction mechanism. This result indicates that one nitrate ion reacts with Eu(III) at the interface, whereas TBP molecules are not involved in the interfacial reaction, which is different from the results obtained using the NaNO solution in our previous study. We demonstrate that the chemical species of Eu(III) complex with nitrate ion and TBP in the aqueous solution play an important role for the extraction mechanism.

Sodium-cooled Fast Reactors

Ohshima, Hiroyuki; Morishita, Masaki*; Aizawa, Kosuke; Ando, Masanori; Ashida, Takashi; Chikazawa, Yoshitaka; Doda, Norihiro; Enuma, Yasuhiro; Ezure, Toshiki; Fukano, Yoshitaka; et al.

Sodium-cooled Fast Reactors; JSME Series in Thermal and Nuclear Power Generation, Vol.3, 631 Pages, 2022/07

https://shop.elsevier.com/books/sodium-cooled-fast-reactors/morishita/978-0-12-824076-2

This book is a collection of the past experience of design, construction, and operation of two reactors, the latest knowledge and technology for SFR designs, and the future prospects of SFR development in Japan. It is intended to provide the perspective and the relevant knowledge to enable readers to become more familiar with SFR technology.