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Journal Articles

Release of radioactive materials from simulated high level liquid waste at boiling accident in reprocessing plant

Tashiro, Shinsuke; Uchiyama, Gunzo; Amano, Yuki; Abe, Hitoshi; Yamane, Yuichi; Yoshida, Kazuo

Nuclear Technology, 190(2), p.207 - 213, 2015/05

 Times Cited Count:8 Percentile:51.03(Nuclear Science & Technology)

The release behavior of radioactive materials from high active liquid waste (HALW) has been investigated under boiling accident conditions. Results of the experiment using a nonradioactive simulated HALW found Ru to be a volatile element under the accident conditions and to be released into the gas phase in the form of both mist and gas. The Ru release rate and the apparent Ru volatilization rate constant were obtained under the boiling conditions of simulated HALW. The other fission product elements such as Cs were found to be nonvolatile and to be released into the gasphase in the form of mist. The mist size distribution near the surface of the simulated HALW in the reactor vessel was found to range from 0.05 to 20 $$mu$$m with a peak diameter of $$sim$$ 2 $$mu$$m.

Journal Articles

State-of-the-art report on nuclear aerosols

Allelein, H.-J.*; Auvinen, A.*; Ball, J.*; G$"u$ntay, S.*; Herranz, L. E.*; Hidaka, Akihide; Jones, A. V.*; Kissane, M.*; Powers, D.*; Weber, G.*

NEA/CSNI/R(2009)5, 388 Pages, 2009/12

JAEA Reports

Proceedings of the 24th NSRR Technical Review Meeting; Tokyo, November 13-14, 2000

Fuel Safety Research Laboratory

JAERI-Conf 2001-010, 303 Pages, 2001/09

JAERI-Conf-2001-010.pdf:59.22MB

The 24th NSRR Technical Review Meeting was held at Tranomon Pastoral, Tokyo, on November 13 and 14, 2000. The purpose of the meeting was to present and discuss the recent progress of the NSRR program and other LWR fuel safety researches at JAERI. Twenty-one papers, including five by foreign institutes, were presented and discussed regarding fuel behavior during normal operation, reactivity initiated accident (RIA) and loss-of-coolant accident (LOCA) and FP release behavior during severe accident. The meeting was a great help in planning future research and promoting research cooperation. This proceeding contains the papers presented in the meeting.

Journal Articles

Findings from CSARP; Cooperative severe accident research program

Sugimoto, Jun; Hashimoto, Kazuichiro*; Yamano, Norihiro; Hidaka, Akihide; Maruyama, Yu; Uetsuka, Hiroshi; Fuketa, Toyoshi; Nakamura, Takehiko; Soda, Kunihisa; Katanishi, Shoji*

Nihon Genshiryoku Gakkai-Shi, 39(2), p.123 - 134, 1997/02

 Times Cited Count:0 Percentile:0.01(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Severe accident research activities in Japan

Sugimoto, Jun

Heat and Mass Transfer in Severe Nuclear Reactor Accidents, 0, p.462 - 477, 1996/00

no abstracts in English

JAEA Reports

Verification of computer code FPRETAIN with respect to RIA data from SPERT and PBF experiments

Y.-H.Heo*; Yanagisawa, Kazuaki

JAERI-M 92-195, 19 Pages, 1992/12

JAERI-M-92-195.pdf:0.47MB

no abstracts in English

Journal Articles

Behavior of iodine-131 during rinsing in-pile loop with demineralized water after fission product release experiment

Yamamoto, Katsumune; ; Okagawa, Seigo; Yokouchi, Iichiro;

Journal of Nuclear Science and Technology, 17(1), p.67 - 76, 1980/00

 Times Cited Count:1 Percentile:22.79(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Outline and currect research status on coated particle fuels

Iwamoto, K.

Nihon Genshiryoku Gakkai-Shi, 15(2), p.86 - 101, 1973/02

 Times Cited Count:0

no abstracts in English

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