Annual report on the effluent control of low level liquid waste in Nuclear Fuel Cycle Engineering Laboratories FY2018

Nakano, Masanao; Fujii, Tomoko; Nagaoka, Mika; Inoue, Kazumi; Koike, Yuko; Yamada, Ryohei; Yoshii, Hideki*; Otani, Kazunori*; Hiyama, Yoshinori*; Kikuchi, Masaaki*; et al.

JAEA-Review 2019-045, 120 Pages, 2020/03

JAEA-Review-2019-045.pdf:2.54MB

Based on the regulations (the safety regulation of Tokai Reprocessing Plant, the safety regulation of nuclear fuel material usage facilities, the radiation safety rule, the regulation about prevention from radiation hazards due to radioisotopes, which are related with the nuclear regulatory acts, the local agreement concerning with safety and environment conservation around nuclear facilities, the water pollution control law, and by law of Ibaraki Prefecture), the effluent control of liquid waste discharged from the Nuclear Fuel Cycle Engineering Laboratories of Japan Atomic Energy Agency has been performed. This report describes the effluent control results of the liquid waste in the fiscal year 2018. In this period, the concentrations and the quantities of the radioactivity in liquid waste discharged from the reprocessing plant, the plutonium fuel fabrication facilities, and the other nuclear fuel material usage facilities were much lower than the limits authorized by the above regulations.

Modification of vacuum plasma sprayed tungsten coating on reduced activation ferritic/martensitic steels by friction stir processing

Tanigawa, Hiroyasu; Ozawa, Kazumi; Morisada, Yoshiaki*; Noh, S.*; Fujii, Hidetoshi*

Fusion Engineering and Design, 98-99, p.2080 - 2084, 2015/10

https://doi.org/10.1016/j.fusengdes.2015.04.059

The vacuum plasma spray (VPS) technique has been investigated as the most practical method to form Tungsten (W) layer as a plasma facing material in fusion devices. The issues are the thermal conductivity and the strength of VPS-W, i.e., the thermal conductivity of VPS-W were significantly lower than that of the bulk W, and the hardness of VPS-W is much less than that of the bulk W. These are mainly caused by the porous structure of VPS-W. In order to solve these issues, friction stir processing (FPS) was applied on VPS-W in this study. It was suggested that FSP can contribute to significant improvement both in mechanical and thermal properties of VPS-W coating.

Chemical evolution of amino acid induced by soft X-ray with synchrotron radiation

Kaneko, Fusae*; Tanaka, Masahito*; Narita, Satoru*; Kitada, Tomo*; Matsui, Takahiro*; Nakagawa, Kazumichi*; Agui, Akane; Fujii, Kentaro; Yokoya, Akinari

Journal of Electron Spectroscopy and Related Phenomena, 144-147, p.291 - 294, 2005/06

https://doi.org/10.1016/j.elspec.2005.01.233

no abstracts in English

Feasibility Study on Commercialization of Fast Breeder Reactor Cycle Systems Interim Report of Phase II; Technical Study Report for Reactor Plant Systems

Konomura, Mamoru; Ogawa, Takashi; Okano, Yasushi; Yamaguchi, Hiroyuki; Murakami, Tsutomu; Takaki, Naoyuki; Nishiguchi, Youhei; Sugino, Kazuteru; Naganuma, Masayuki; Hishida, Masahiko; et al.

JNC TN9400 2004-035, 2071 Pages, 2004/06

JNC-TN9400-2004-035.pdf:76.42MB

The attractive concepts for Sodium-, lead-bismuth-, helium- and water-cooled FBRs have been created through using typical plant features and employing advanced technologies. Efforts on evaluating technological prospects of feasibility have been paid for these concepts. Also, it was comfirmed if these concepts satisfy design requierments of capability and performance presumed in the feasibilty study on commertialization of Fast Breeder Reactor Systems. As results, it was concluded that the selection of sodium-cooled reactor was most rational for practical use of FBR technologies in 2015.

Modification of vacuum plasma sprayed tungsten coating by friction stir processing

Tanigawa, Hiroyasu; Ozawa, Kazumi; Morisada, Yoshiaki*; Fujii, Hidetoshi*; Noh, S.*

no journal, , 

no abstracts in English

Effect of tungstate inhibitor and molybdate-containing mixed phosphate-based inhibitor on corrosion of PCV steel in diluted sea water, 2

Kaneko, Tetsuji*; Tanaka, Norihiko*; Kawaharada, Yoshiyuki*; Fujii, Kazumi*; Iwanami, Masaru*; Ishioka, Shinichi*; Yokoyama, Yutaka*; Umehara, Ryuji*; Kato, Chiaki; Ueno, Fumiyoshi; et al.

no journal, , 

no abstracts in English

Effect of later added inhibitors of the steel corrosion in the diluted artificial seawater under -ray irradiation

Kato, Chiaki; Sato, Tomonori; Ueno, Fumiyoshi; Kaneko, Tetsuji*; Tanaka, Norihiko*; Kawaharada, Yoshiyuki*; Fujii, Kazumi*; Iwanami, Masaru*; Ishioka, Shinichi*; Yokoyama, Yutaka*; et al.

no journal, , 

no abstracts in English

Evaluation of effect of corrosion inhibitors on reactor core spray pipe steel in flowing diluted sea water

Yokoyama, Yutaka*; Umehara, Ryuji*; Kaneko, Tetsuji*; Tanaka, Norihiko*; Kawaharada, Yoshiyuki*; Fujii, Kazumi*; Iwanami, Masaru*; Ishioka, Shinichi*; Kato, Chiaki; Ueno, Fumiyoshi; et al.

no journal, , 

no abstracts in English

Research and development project on irradiation damage management technology for structural materials of long-life nuclear plant, 6; Evalaution of irradiation damage indicators due to reactor neutron irradiation and cyclotron helium implantation, etc

Wakai, Eiichi; Takada, Fumiki; Kato, Yoshiaki; Kato, Shoichi; Hirade, Tetsuya; Takaya, Shigeru; Matsui, Yoshinori; Fujii, Kimio; Aoto, Kazumi; Nogami, Shuhei*; et al.

no journal, , 

no abstracts in English

Effect of tungstate inhibitor and molybdate-containing mixed phosphate-based inhibitor on corrosion of PCV steel in diluted sea water

Kaneko, Tetsuji*; Tanaka, Norihiko*; Kawaharada, Yoshiyuki*; Fujii, Kazumi*; Iwanami, Masaru*; Ishioka, Shinichi*; Yokoyama, Yutaka*; Umehara, Ryuji*; Kato, Chiaki; Ueno, Fumiyoshi; et al.

no journal, , 

no abstracts in English