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Yamada, Susumu; Itakura, Mitsuhiro; Okumura, Masahiko; Machida, Masahiko
no journal, ,
no abstracts in English
Maeda, Toshikatsu; Omori, Hiroyuki; Sakamaki, Keiko
no journal, ,
no abstracts in English
Yoshida, Hiroyuki; Nagatake, Taku; Takase, Kazuyuki; Kaneko, Akiko*; Monji, Hideaki*; Abe, Yutaka*
no journal, ,
no abstracts in English
Yamashita, Susumu; Takase, Kazuyuki; Yoshida, Hiroyuki
no journal, ,
In the Fukushima accidents, fuel assemblies which were installed in the reactors were reached a high temperature by stop of the core cooling system with a power station black-out. As a result, it is considered that the core degradation has been introduced because the melting of the fuel rods occurred and the melting behavior was expanded. In order to elucidate a progress of the melting phenomena in the reactor core, a numerical simulation code which can be precisely evaluated the melting phenomena is required. Then, the melting behavior of the fuel assemblies in the reactor core was analyzed numerically using the three-dimensional multi-phase thermal-hydraulic simulation code. In the presentation, the numerical results on the melting behavior of molten debris including heating source and not have it which suppose Uranium fuel and reactor core internals.
Suzuki, Takayuki; Yoshida, Hiroyuki; Nagase, Fumihisa; Abe, Yutaka*; Kaneko, Akiko*
no journal, ,
no abstracts in English
Sakurai, Takeshi; Yabuuchi, Yukiko; Arai, Nobuyoshi; Sawada, Makoto; Yamashita, Kiyonobu; Sato, Nobuyuki; Torata, Shinichiro; Kanaizuka, Seiichi; Nakamura, Kazuyuki
no journal, ,
Outline of the Instructor Training Program, which is contracted with MEXT, for ten countries in Asia, and status of the Follow-up Training Course, which is one of the three major courses and conducted in Asian countries, will be reported.
Takase, Kazuyuki; Misawa, Takeharu; Yoshida, Hiroyuki; Mori, Hideo*; Ezato, Koichiro
no journal, ,
no abstracts in English
Zaima, Naoki; Nakatsuka, Yoshiaki; Nakashima, Shinichi; Kureta, Masatoshi; Ozu, Akira; Takase, Misao
no journal, ,
The passive assay system based on (
,n) neutron counting generated from alpha-ray for uranium bearing wastes drums had been developed. The passive neutron assay system is, therefore it has been inevitable its scarce neutron response and chemical form dependence. Therefore the improvements for detection response and less matrix dependence have also been started. The new measurements systems are equipped helium-3 counters, 14 MeV neutron generator and concrete shielding. The trials for accumulating data used uranium sources have also been started successfully.
Horiguchi, Naoki*; Abe, Yutaka*; Yoshida, Hiroyuki; Kaneko, Akiko*; Uesawa, Shinichiro*
no journal, ,
no abstracts in English
Daido, Hiroyuki
no journal, ,
no abstracts in English
Ito, Hiromichi; Kawahara, Hirotaka; Takamatsu, Misao; Toyoshi, Akira*; Sakao, Ryuta*; Murata, Chotaro*
no journal, ,
no abstracts in English
Okura, Takehisa; Feistenauer, P.*; Meisenberg, O.*; Shinonaga, Taeko*; Tschiersch, J.*
no journal, ,
The atmospheric radioactivity monitoring at Nuclear Science Research Institute, following the Fukushima accident was reviewed in this study. Comparison with measurement result of the filters at Helmholz Zentrum Muenchen (Germay) was made in order to discuss how to make an estimate of background under contaminated circumstance soon after the accident. Values of each other for samples with important level to estimate internal exposure was consistent; this points to that the adopted method to estimate background was appropriate. But some of samples with relative lower level were incompatible with each other. Penetration of radiocesium aerosols through HE-40TA was discussed with size distribution of radiocesium aerosols and characteristics of HE-40TA. Size distributions of radiocesium aerosols were evaluated experimentally, separated from HE-40TA and collected into a cascade impactor. The penetration was estimated by about 1% - 5%.
Yokoyama, Kaoru; Sugitsue, Noritake; Ohara, Yoshiyuki; Takeda, Hiroshi*; Rong, D.*; Yanase, Shinichiro*; Kuwagi, Kenya*; Takami, Toshihiro*; Hyakutake, Toru*
no journal, ,
Some disaster wastes polluted with the radioactive cesium diffused in the accident of the Fukushima Daiichi Nuclear Power Plant are incinerated in the refuse incineration plant. It is thought that cesium is not emitted outside since cesium is coagulated to the refuse incineration ash and trapped by a bag filter or an electric dust collector. Therefore, we report the results of analysis of the cesium concentration and specific surface area of the ash, for the evaluation of the status of adherence to the incinerated ash of cesium.
Yokoyama, Kaoru; Sugitsue, Noritake; Ohara, Yoshiyuki; Takeda, Hiroshi*; Rong, D.*; Yanase, Shinichiro*; Kuwagi, Kenya*; Takami, Toshihiro*; Hyakutake, Toru*
no journal, ,
Some disaster wastes polluted with the radioactive cesium diffused in the accident of the Fukushima Daiichi Nuclear Power Plant are incinerated in the refuse incineration plant. It is thought that cesium is not emitted outside since cesium is coagulated to the refuse incineration ash and trapped by a bag filter or an electric dust collector. Therefore, we report on simulation results incorporating the adhesion model of cesium in the combustion model of waste.
Suzuki, Kazuhiro; Motooka, Takafumi; Tsukada, Takashi; Terakawa, Yuto; Ichise, Kenichi; Numata, Masami; Kikuchi, Hiroyuki
no journal, ,
no abstracts in English
Haraga, Tomoko; Hishinuma, Yukio*; Kaneta, Yui*; Ishimori, Kenichiro; Takahashi, Kuniaki
no journal, ,
no abstracts in English
Ozu, Akira; Nakamura, Tatsuya; Takase, Misao; Kurata, Noritaka; Haruyama, Mitsuo; Soyama, Kazuhiko; Kureta, Masatoshi; Seya, Michio
no journal, ,
no abstracts in English
Tsunashima, Yasumichi; Shimazaki, Masao; Ohashi, Yusuke; Tanaka, Yoshio; Nomura, Mitsuo
no journal, ,
The operation waste of uranium conversion plant and uranium enrichment plant is called sludge, and contains many fluoride which is deleterious material. For disposal, elution of fluoride is a problem. Moreover, sludge contains many calcium sulfate and we are anxious about expansion of cement solidification object by superfluous generation ofettringite. Therefore, we report solidification and the leaching property of the cement solidification object of the sludge containing many fluoride. Moreover, we report solidification and the leaching property of sludge using magnesium oxide solidification material as a method of controlling elution and expansion of fluoride.
Amano, Yuki; Amamiya, Hiroki; Murakami, Hiroaki; Iwatsuki, Teruki; Terashima, Motoki; Mizuno, Takashi; Kirishima, Akira*; Kuno, Atsushi*; Sasaki, Takayuki*; Kubota, Takumi*; et al.
no journal, ,
no abstracts in English
Hata, Haruhi; Yokoyama, Kaoru; Tanaka, Yoshio; Ohara, Yoshiyuki; Sugitsue, Noritake
no journal, ,
For decommission of uranium handling facilities, it is important to characterize the details of the facilities, which are the distribution of nuclide, the existence of hazardous waste and so on. The report suggests classification method based on the nuclide composition by using principal component analysis.