Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Maeda, Toshikatsu; Bamba, Tsunetaka*; Omori, Hiroyuki; Yamaguchi, Tetsuji
no journal, ,
no abstracts in English
Tanaka, Yoshio; Hata, Haruhi; Yokoyama, Kaoru; Tokuyasu, Takashi; Kaneda, Koji; 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 mainly shows the character of distribution of uranium and its isotopes.
rayTanaka, Yoshio; Hata, Haruhi; Yokoyama, Kaoru; Tokuyasu, Takashi; Kaneda, Koji; Sugitsue, Noritake
no journal, ,
This report shows the classification method into NU group or RU group by passive ray assay. Moreover, we discuss the practicality of the method.
Yokoyama, Kaoru; Sugitsue, Noritake; Suzuki, Yasuo*; Muroi, Masayuki*; Nakatsuka, Yoshiaki; Ishii, Kazuto*
no journal, ,
The computational technique using the ray of two energies emitted from 
U progeny nuclide (
Pa) was developed to determine uranium quantity in heterogeneous waste. In this study, the relative error and detection limit evaluation results using the simulated wastes are reported.
Seki, Masayuki; Kihara, Yoshiyuki; Tsukada, Tatsuya*; Motoki, Kazuhiko*; Hirako, Kazuhito*
no journal, ,
no abstracts in English
Nishihara, Kenji; Iwamura, Takamichi*; Akie, Hiroshi; Shirasu, Noriko
no journal, ,
Use of Rock-like oxide (ROX) fuel is proposed for the purpose of reduction of plutonium amount in the case of gradually stopping nuclear power generation without introducing fast breeder reactors. In this study, the mass flow and repository of three scenarios that is once-through, Pu-thermal and ROX, was analysed. As the result, amount and attractiveness as nuclear weapon of Pu was decreased in the ROX scenario in comparison with the once-through scenario, although the repository size was not reduced.
Yamano, Hidemasa; Sakai, Takaaki; Kurisaka, Kenichi
no journal, ,
The characteristics of fast reactor safety is that it has passive safety function such as natural circulation heat removal. Hence, it is necessary to evaluate the reliability of the passive safety function and to estimate probability of the functional failure in order to perform level 1 PSA on a plant. This paper reports sensitivity analysis and failure probability evaluation in 2011 to construct failure probability evaluation methodology on natural circulation decay heat removal.
Ishigaki, Masahiro; Watanabe, Tadashi*; Takeda, Takeshi; Nakamura, Hideo
no journal, ,
no abstracts in English
Nogiwa, Kimihiro; Onitsuka, Takashi; Takeuchi, Tomoaki; Abe, Teruyoshi; Sakakibara, Yasuhide; Horie, Kaoru; Nakamura, Takahisa
no journal, ,
no abstracts in English
Aizawa, Kosuke; Chikazawa, Yoshitaka; Oki, Shigeo
no journal, ,
A selector-valve mechanism is adopted for its failed-fuel detection and location (FFDL) system in the previous sodium-cooled large reactors. However, there is a concern about maintenence of samplin pipes. Therefore, applicability evaluation of tagging-gas failed fuel detection and location system was investigated in this study.
Meiliza, Y.; Oki, Shigeo; Kawashima, Katsuyuki; Okubo, Tsutomu
no journal, ,
Ishizuka, Akihiro; Nozaki, Tatsuo; Kokubun, Yuji; Okubo, Koichi; Torii, Tatsuo; Takata, Takushi*; Kume, Kyo*; Hasegawa, Takashi*; Sugita, Takeshi*
no journal, ,
The assessment methods of types and distributions of a radioactivity unexpectedly released to atmosphere from nuclear power plants have been studied with a help of examination of data measured by -ray detectors at several radiation monitoring equipments. The principle was verified with a -ray source in room, and an existing nuclear power station was simulated as an application example.
Takata, Takushi*; Ishizuka, Akihiro; Nozaki, Tatsuo; Kokubun, Yuji; Okubo, Koichi; Torii, Tatsuo; Kume, Kyo*; Otani, Nobuo*; Hasegawa, Takashi*
no journal, ,
The assessment methods of a radioactivity distribution unexpectedly released to atmosphere from nuclear power plants have been studied using a single channel analyzing technique. A combination of this single channel analyzing technique and a detector sensitive to a solid angle of an incident -ray was examined to assess the same purpose.
Kojima, Kensuke; Okumura, Keisuke; Arita, Yuji*
no journal, ,
Dry processing is assumed for reprocessing of minor actinide mixed metal fuels discharged from fast reactors. In wet processing, spent fuel composition has been measured by a method of sampling fuel solution. However, the method is difficult for dry processing to be applied. Thus, a new method is required for dry processing. The new method was considered as predicting nuclide inventories from measured isotopic ratio of fission products of noble gas accumulated in plenum region of fuel rod with use of correlations between the inventories and the isotopic ratio. In order to evaluate the correlations, burn-up calculations were carried out for various configurations based on FaCT core with the metal fuels. Using the calculated data, correlation functions were newly formulated. As results of applying isotopic ratios 
Kr/
Kr and 
Xe/
Xe to the functions, the predicted inventories show good agreement with those of burn-up calculations for major 21 nuclides.
irradiationIto, Yoshiyuki; Saito, Yasuo; Susa, Shunsuke*; Mimura, Hitoshi*
no journal, ,
no abstracts in English
Manabe, Kentaro; Sato, Kaoru; Endo, Akira
no journal, ,
no abstracts in English
Hoshino, Takanori; Yano, Kimihiko; Kaji, Naoya; Washiya, Tadahiro; Fukasawa, Tetsuo*; Ohara, Hiroshi*
no journal, ,
no abstracts in English
Yano, Kimihiko; Hoshino, Takanori; Kaji, Naoya; Washiya, Tadahiro; Fukasawa, Tetsuo*; Ohara, Hiroshi*
no journal, ,
A part of study on the management of fuel debris in unit 1-3 at Fukushima Dai-ichi Nuclear Power Station, it is suggested that solubilization of fuel debris for nitric acid by solution treatment with UO. It was experimentally confirmed that this process made insoluble (U,Zr)O, one of the major components, be dissoluble.
Tsuda, Shuichi; Tsutsumi, Masahiro; Yoshida, Tadayoshi; Saito, Kimiaki
no journal, ,
The spectrum-dose conversion operators (hereafter, G(E) function) for a CsI(Tl) scintillation counter used in environmental dose monitoring was calculated based on the response functions obtained by a Monte Carlo simulation code, MCNP5. The G(E) functions were evaluated for ambient dose, H*(10). It is found that the calculated values of H*(10) deduced by the G(E) functions agree with those of H*(10) determined in the calibration fields in JAEA within 2% in the case of irradiations by a Csesium-137, a radium-226 and a cobalt-60 source, by the measurements using a scintillation counter whose crystal size is 13 
13 20 mm
.
Irisawa, Keita; Osone, Osamu; Meguro, Yoshihiro
no journal, ,
no abstracts in English