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Seki, Masayuki; Kihara, Yoshiyuki; Hirako, Kazuhito*; Motoki, Kazuhiko*; Tsukada, Tatsuya*
no journal, ,
no abstracts in English
Zaima, Naoki; Nakashima, Shinichi; Kaneda, Koji; Kado, Kazumi
no journal, ,
We developed uranium mass assay systems for 200-litter wastes drums applied neutron and 
measurements by NDA method. In this intermediate report we will describe measurement systems and trial data. The systems are composed of the 16 pieces of helium-3 proportional counters for neutron detection and a large sized NaI(Tl) scintillation detector for -ray detection. The extensive testing trials using the calibrated uranium sources with different enrichment and some kinds of matrices in drums were performed. Through the one year testing the useful experiences of this system concerning neutron and -ray measurements for uranium mass were obtained. Almost all instruments and software were so good performance as is designed. As the next step we are going to schedule to try measurements for actual wastes that are stored in the Uranium Refining and Conversion Plant at Ningyo-toge, and put practical uses near future. Our research was accomplished with the support of Los Alamos National Laboratory.
Katayama, Masaharu*; Takamatsu, Kuniyoshi; Sawa, Kazuhiro; Takagi, Naoyuki*; Ooka, Yasunori*; Yamasaki, Masatoshi*
no journal, ,
As collaborative research project by Japan Atomic Energy Agency, Toyota Tsusho Corporation and Nuclear Fuel Industries, Ltd., new utilizations of HTGR and new R&D of a cooperative relationship between car industries and HTGR are presented. Specifically, we showed the results of feasibility study on material creation and new-type fuel utilization by using HTTR.
Yamada, Fumiaki; Araki, Kosuke*
no journal, ,
There was not the influence that Monju system startup tests data gave to numerical analysis of large pipe break in primary heat transfer system concerned from comparison actual plant base analysis and before conservative base analysis.
Nakayama, Hiromasa; Nagai, Haruyasu
no journal, ,
We perform Large-Eddy Simulations (LES) on turbulent flows and plume dispersions within and over regular arrays of cubic buildings with various roughness densities and investigate the influence of the building arrangement pattern on the characteristics of mean and fluctuation concentrations for the assessment of human health hazard from toxic substances and the safety analysis of flammable gas.
Okusa, Kyoichi; Muranaka, Makoto; Sotsu, Masutake; Kimura, Koichi
no journal, ,
The ultrasonic thermometer is installed on the piping of the secondary cooling system in Monju. The characteristic of the ultrasonic thermometer in case of the sodium temperature change was evaluated as the first stage of system startup test of Monju. The evaluated temperature by the ultrasonic thermometer agreed well with the thermocouple measurement in this condition.
Takeyasu, Shinji; Takebayashi, Hiroyuki; Watanabe, Kazunori*; Shimizu, Takenori
no journal, ,
no abstracts in English
Nagai, Ryoji; Hajima, Ryoichi; Nishimori, Nobuyuki
no journal, ,
no abstracts in English
Tanaka, Kosuke; Sato, Isamu; Hirosawa, Takashi; Seki, Takayuki*; Kashimura, Naoki*; Kurosaki, Ken*; Tokushima, Kazuyuki*; Muta, Hiroaki*; Oishi, Yuji*; Yamanaka, Shinsuke*
no journal, ,
Complex uranium or plutonium oxides with alkaline-earth metals were prepared by using conventional powder metallurgy and its thermophysical properties were evaluated.
Takano, Masahide; Yamagishi, Isao; Akabori, Mitsuo; Minato, Kazuo; Yoshioka, Masahiro*; Ochi, Eiji*; Fukui, Toshiki*; Komamine, Satoshi*
no journal, ,
no abstracts in English
Morihira, Masayuki; Mizusako, Fumiki*; Tsuboi, Yasushi*
no journal, ,
A feasibility study for oxygen getter options is conducted in JAEA to reduce cladding inner corrosion of FBR MOX fuels to attain high burn-up. Investigation of oxygen getter loading options for pellet type MOX fuels as well as evaluation results of oxidation behavior of the candidate materials are reported.
Miwa, Shuhei; Usuki, Toshiyuki; Sato, Isamu; Hirosawa, Takashi; Tanaka, Kosuke; Osaka, Masahiko; Seki, Takayuki*; Kashimura, Naoki*
no journal, ,
no abstracts in English
Amamoto, Ippei; Kofuji, Hirohide; Mitamura, Naoki*; Tsuzuki, Tatsuya*; Motohashi, Takumi*; Takasaki, Yasushi*; Shibayama, Atsushi*; Yano, Tetsuji*
no journal, ,
no abstracts in English
Kinase, Sakae; Homma, Toshimitsu
no journal, ,
no abstracts in English
Yanagisawa, Kazuaki
no journal, ,
A failure mechanism of preirradiated 14
14 type PWR fuel rod was studied. The test specimen at 42 MWd/kgU was segmented by the active column length of 0.12 m (STFR). It was loaded into the JMTR for load follow operation of 35 kW per m (20 min); 20 kW per m (10 min) up to the 300 cycles. The STFR was further pulsed at NSRR with the energy deposition of 118cal per gram and defected by the split mechanism. This failure was affected with burnup (BU), PCMI stress, the hoop stress caused by the transient FGR and the time. Because they are irrelevant to the type of the fuel rod, all LWR fuels preirradiated may be possible to fail by this mechanism.
Shibamoto, Yasuteru; Yonomoto, Taisuke; Maruyama, Yu
no journal, ,
no abstracts in English
Sato, Isamu; Katsuyama, Kozo; Arai, Yasuo
no journal, ,
To understand release behavior of He and fission gases from irradiated fuel, the quantities of He and fission gases accumulated in mixed oxide fuel irradiated in a fast reactor was measured to reveal retaining gas amounts per pin.
Koide, Masashi*; Saito, Takumi*; Nagasaki, Shinya*; Yamamoto, Yuhei; Mizuno, Takashi
no journal, ,
no abstracts in English
Sugino, Kazuteru; Ohgama, Kazuya; Nakazato, Wataru*; Moriwaki, Hiroyuki*
no journal, ,
Towards realizations of the demonstration reactor in around 2025 and the commercialized reactor in around 2050, a investigation on the conceptual core design of the sodium-cooled fast reactor (JSFR: Japan Sodium-cooled Fast Reactor) is under going. This paper presents the elavuation of the core design prediction accuracy based on the studies related to the latest nuclear data.
Suzuki, Mitsuru
no journal, ,
no abstracts in English