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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 60Co 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.
Yamashita, Naoki; Aoyama, Takahito; Kato, Chiaki; Sano, Naruto; Tagami, Susumu
JAEA-Technology 2023-028, 22 Pages, 2024/03
JAEA-Technology-2023-028.pdf:1.9MB
At the Fukushima Daiichi Nuclear Power Station (1F), which is currently undergoing decommissioning, there is growing interest in the effects of radiation-emitting radionuclides such as 
Sr and 
Cs on the structural integrity. In particular, the corrosion behavior of carbon steel, which is used in many parts of 1F, is known to change depending on metal cations in solution, but the effects of Sr and Cs on corrosion are not yet understood. In addition, it is important to investigate the distribution of Sr and Cs in the rust layer in order to understand the corrosion behavior, but the method has not yet been established. In this study, a glove box was prepared to conduct corrosion tests of carbon steel in NaCl containing Sr and Cs in the glove box. In addition, in order to clarify the influence of Sr and Cs, which exist as metal cations in the solution, on the corrosion behavior of carbon steel, we attempted to establish a detection method for radioactive materials in the rust layer using an imaging plate.
Yamashita, Naoki; Irisawa, Eriko; Kato, Chiaki; Sano, Naruto; Tagami, Susumu
JAEA-Technology 2022-035, 29 Pages, 2023/03
JAEA-Technology-2022-035.pdf:2.54MB
In the treatment process of the current commercial reprocessing plant (Rokkasho Reprocessing Plant), the high-level liquid waste concentrator is the equipment that treats the most corrosive solution. In the high-level liquid waste concentrator, the extracted liquid waste after separation of uranium and plutonium is heated, concentrated, and reduced in volume. Therefore, the amount of gamma- rays emitted from fission products and the concentration of corrosive metal ion species such as neptunium-237 (
Np) are the highest in the reprocessing process, and the amount of corrosion in the high-level liquid waste concentrate canner is expected to be large. In this study, in order to clarify the effect of gamma-rays on the corrosion reaction of stainless steel in nitric acid solutions containing Np from the electrochemical viewpoint, the corrosion test apparatus for heat transfer surfaces in an airtight concrete cell at the Waste Safety TEsting Facility (WASTEF) of Nuclear Science Research Institute was modified to enable electrochemical measurements under gamma-ray irradiation. The effect of gamma-rays on the corrosion reaction taking place on the stainless steel surface was discussed from the electrochemical test results obtained. As a result, changes in the immersion potentials of stainless steel and the polarization curves due to chemical species caused by radiolysis of gamma-ray irradiation were confirmed.
Sano, Naruto; Yamashita, Naoki; Hoshino, Kazutoyo*; Tsukada, Manabu*; Sawauchi, Fumiya*; Otake, Yoshinori; Ichise, Kenichi; Tagami, Susumu
JAEA-Technology 2022-034, 47 Pages, 2023/03
JAEA-Technology-2022-034.pdf:2.81MB
The Waste Safety Testing Facility (WASTEF) was established in 1982 as an experimental facility for long-term storage of solidified high-level radioactive waste generated in the reprocessing of spent light water reactor fuel and the subsequent safety assessment of geological disposal. It is a historic facility that started operation in 1982. This facility consists of 5 concrete cells, 1 lead cell, 6 glove boxes, and 7 hoods, and is a large-scale facility that can use nuclear fuel materials including uranium and plutonium and radioactive isotopes including TRU. In this facility, research and development requested by the research department is carried out in the Hot Material Examination Section. In addition, patrol inspections, self-inspections, etc. are also carried out as maintenance management based on safety regulations. This report summarizes the overview of WASTEF facilities, the results of operation, maintenance and management work in FY2021, and the future outlook.
Tagami, Susumu; Shimizu, Osamu; Sano, Naruto; Imaizumi, Akiko; Tobita, Hiroshi; Nagasaki, Yosuke; Kurobane, Shiro
JAEA-Review 2010-079, 90 Pages, 2011/03
JAEA-Review-2010-079.pdf:3.02MB
The Back-end Cycle Key Elements Research Facility (BECKY) was installed in the Nuclear Fuel Cycle Safety Engineering Research Facility (NUCEF) in 1994 for the safety and basic studies of the nuclear fuel cycle and radioactive waste. BECKY consists of three alpha/
concrete cells, three alpha/ steel cells, thirty glove boxes and twenty hoods. Operation, maintenance and management are in execution based on the operational safety programs. And we also execute application about amendment of the permission and approval for the purpose of support R&D. This report describes the operation, maintenance and management from April 1, 2005 to March 31, 2010 for the purpose of keeping the performance of BECKY.
Tagami, Susumu; Sano, Naruto; Otobe, Haruyoshi; Akabori, Mitsuo; Kurobane, Shiro
JAEA-Technology 2010-034, 65 Pages, 2010/10
JAEA-Technology-2010-034.pdf:3.56MB
An experimental facility called the Module for TRU High Temperature Chemistry (TRU-HITEC) was installed in the Back-end Cycle Key Elements Research Facility (BECKY) of the Nuclear Fuel Cycle Safety Engineering Research Facility (NUCEF) in February, 2003. The main purpose of this facility is to perform the basic studies of the behavior the transuranium elements (TRU) in pyrochemical reprocessing and oxide fuels. Hot-experiment started in December, 2004. TRU-HITEC consists of three 
/ cells and a glove box. This is the only facility in the country as large-scale facilities maintained a high purity argon gas atmosphere. The experience gained through the maintenance and improvement is useful also for the maintenance of similar designed facility. This report describes the maintenance method and improvement for the purpose of keeping the performance of TRU-HITEC.
Takano, Masahide; Tagami, Susumu; Minato, Kazuo; Kozaki, Tamotsu*; Sato, Seichi*
Journal of Alloys and Compounds, 439(1-2), p.215 - 220, 2007/07
Times Cited Count：16 Percentile：64.42(Chemistry, Physical)ZrN is a possible candidate for the diluent material of the nitride fuel containing minor actinides. In the present study, the lattice thermal expansions of ZrN, DyN and (Dy,Zr)N solid solutions were measured by high temperature XRD, as the analogous fuel material. The average linear thermal expansion coefficients of these nitrides increased from 7.86
10
to 9.5410 K
with increasing Dy fraction. On the analogy with the results on the composition dependence of the thermal expansion coefficients, the preferable effect of ZrN as the diluent material is suggested.
Tc generated from natural-Mo(n,)
Mo, 4; Analysis in the verification test of the producing process of Tc milked from a highly radioactive MoSonoda, Takashi; Umeda, Miki; Tagami, Susumu; Kurobane, Shiro; Miyoshi, Yoshinori; Tanaka, Atsushi*; Ishikawa, Koji*; Tsuguchi, Akira*; Tatenuma, Katsuyoshi*
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no abstracts in English
Irisawa, Eriko; Kato, Chiaki; Yamashita, Naoki; Sano, Naruto; Tagami, Susumu
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no abstracts in English
Irisawa, Eriko; Kato, Chiaki; Yamashita, Naoki; Sano, Naruto; Tagami, Susumu
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