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Journal Articles

Treatment technology of highly radioactive solid waste generated by experimental tests and sample analysis in reprocessing facilities

Goto, Yuichi; Inada, Satoshi; Kuno, Takehiko; Mori, Eito*

Nihon Hozen Gakkai Dai-16-Kai Gakujutsu Koenkai Yoshishu, p.221 - 224, 2019/07

Test equipment, containers, and analytical wastes, generated by experiments using spent fuel pieces in hot cell of Operation Testing Laboratory and by analysis of highly active liquid wastes in hot analytical cell line of Tokai Reprocessing Plant, are treated as highly radioactive solid wastes. These wastes are stored in specific shielded containers called waste cask and then transport to the storage facility. The treatment of these highly radioactive solid wastes have been carried out for 40 years with upgrading waste taking out system and transportation device. As a results, automation of several procedures have been achieved utilizing conventional equipment, and work efficiency and safety have been improved.

JAEA Reports

Differential pressure analysis for ventilation filter by smoke under fire accident with CELVA-1D

Watanabe, Koji; Tashiro, Shinsuke; Abe, Hitoshi; Takada, Junichi; Morita, Yasuji

JAERI-Tech 2004-029, 48 Pages, 2004/03

JAERI-Tech-2004-029.pdf:3.19MB

In a part of building ventilating installation of a nuclear fuel facility, a reprocessing plant for example, the pre-filters are adopted as one of the ventilation filters. In a fire accident, it is supposed that, because of the pre-filter clogging by large smoke, its differential pressure ($$Delta$$p) is evolved up to the value at its breakage. Therefore, in regard to maintaining the confinement of radioactive materials, it is important to predict the time course of $$Delta$$p of the pre-filter accurately. In the current study, it was assumed that the empirical equation for the DF of the pre-filter as function of smoke particle diameter (SPD), between 0.7-2 $$mu$$m, could be applied to estimating its DF for SPD above 2 $$mu$$m. Under this assumption, the time corresponding to its $$Delta$$p at its breakage, calculated by CELVA-1D, was agreed well with the experimental result.

Journal Articles

New critical facilities toward their first criticality, STACY and TRACY in NUCEF

Tonoike, Kotaro; Izawa, Naoki; Okazaki, Shuji; Sugikawa, Susumu; Takeshita, Isao; *

ICNC 95: 5th Int. Conf. on Nuclear Criticality Safety,Vol. II, 0, p.10.25 - 10.32, 1995/00

no abstracts in English

Journal Articles

Fault tree analysis of system anomaly leading to red oil explosion in plutonium evaporator

Nomura, Yasushi; R.Leicht*; P.Ashton*

Journal of Nuclear Science and Technology, 31(8), p.850 - 860, 1994/08

 Times Cited Count:4 Percentile:57.35(Nuclear Science & Technology)

no abstracts in English

Journal Articles

NUCEF project and its expected contribution to safety assessment

Yanagisawa, Hiroshi; Takeshita, Isao; Nomura, Masayuki; ; Tsujino, Takeshi

Proc. of the CSNI Specialist Meeting on Safety and Risk Assessment in Fuel Cycle Facilities, p.461 - 470, 1991/00

no abstracts in English

Oral presentation

Development of treatment for low radioactive effluent in Tokai Reprocessing Plant, 13; Full-scale experiment of cement based encapsulation

Yamashita, Masaaki; Sato, Fuminori; Horiguchi, Kenichi; Kojima, Junji; Sakai, Etsuo*; Atarashi, Daiki*; Kadota, Hirofumi*

no journal, , 

no abstracts in English

Oral presentation

Development of treatment for low radioactive effluent in Tokai Reprocessing Plant, 11; Development plan and outline of cement based encapsulation

Sato, Fuminori; Horiguchi, Kenichi; Yamashita, Masaaki; Kojima, Junji

no journal, , 

no abstracts in English

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