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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.
Maeda, Toshikatsu; Omori, Hiroyuki*
no journal, ,
no abstracts in English
activity under highly alkaline conditionsSawaguchi, Takuma; Kadowaki, Mitsushi*; Mukai, Masayuki; Tsukada, Manabu; Maeda, Toshikatsu; Tanaka, Tadao
no journal, ,
no abstracts in English
Tsukada, Manabu; Kadowaki, Mitsushi*; Mukai, Masayuki; Sawaguchi, Takuma; Kataoka, Masaharu; Maeda, Toshikatsu; Tanaka, Tadao
no journal, ,
no abstracts in English
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.
Mizuno, Mineo; Sudo, Katsuo; Takeuchi, Kentaro; Okita, Takatoshi; Kihara, Yoshiyuki
no journal, ,
The short process is considered to be a main concept which has high feasibility in Fast Reactor Cycle Technology Development (FaCT). In this study, a small-scale fabrication test was carried out to investigate characteristic of MOX pellet made of granulated MOX powder blended with dry-route recycle powder, for the first time, as a basic test concern with the short process. As the results, it was found that the sintered density of the pellet clearly depends on the preparing conditions and content of recycle powder. The results is intended to be utilized in the investigation of engineering-scale test conditions.
Komoto, Norio; Sasaki, Hirofumi; Kawata, Tsuyoshi; Taki, Kiyotaka; Kinoshita, Shigemi*
no journal, ,
no abstracts in English
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
Kunimaru, Takanori; Hama, Katsuhiro; Ogata, Nobuhisa; Sato, Toshinori; Saegusa, Hiromitsu; Tsuruta, Tadahiko; Takeuchi, Ryuji; Matsuoka, Toshiyuki; Mizuno, Takashi
no journal, ,
no abstracts in English
Onishi, Takashi; Osaka, Masahiko; Miwa, Shuhei; Obayashi, Hiroshi; Sekino, Hirotaka*; Kirishima, Akira*; Sato, Nobuaki*
no journal, ,
As a demonstration of nuclear fuel reprocessing by sulfurization reaction, voloxidation, selective sulfurization and selective dissolution of simulated spent nuclear fuel pellet fabricated from U, Pu, Am and non-radioactive FP were conducted. As results, dissolution rate of each elements were obtained and behavior of MA and FP were investigated.
Maekawa, Keisuke; Inagaki, Manabu*; Tanaka, Tatsuya*; Hashimoto, Shuji*; Matsuo, Shigeaki*
no journal, ,
no abstracts in English
Sugiyama, Katsuteru*; Noguchi, Hiroki; Takegami, Hiroaki; Onuki, Kaoru; Kaneko, Akiko*; Abe, Yutaka*
no journal, ,
The Japan Atomic Energy Agency has been conducting R&D on thermo-chemical IS process, which is one of most attractive water-splitting hydrogen production methods using nuclear heat of a high temperature gas-cooled reactor. The present study concerns with development of IS process equipment utilizing direct contact heat exchanger (DCHX). The application of DCHX to the sulfuric acid decomposition step of IS process has been proposed such that the decomposed gas contacts with the sulfuric acid solution supplied from the Bunsen reaction step. The concept is very attractive in terms of the development of compact and efficient sulfuric acid concentrator. However, little is known on the behavior of sulfuric acid in the DCHX, which is required for the equipment design. Therefore, we considered an experimental acquisition of essential design parameter of the DCHX, the gas-phase mass transfer coefficient.
Morikawa, Keita; Kunimaru, Takanori
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no abstracts in English
Sato, Shinichiro; Sai, Hitoshi*; Oshima, Takeshi; Imaizumi, Mitsuru*; Shimazaki, Kazunori*; Kondo, Michio*
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*
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no abstracts in English
Nakazaki, Katsutoshi; Takaya, Akikazu; Kato, Junya; Kobayashi, Masahiro; Matsumura, Tadayuki; Niitsuma, Koichi; Fujiwara, Koji
no journal, ,
no abstracts in English
Takemoto, Noriyuki; Imaizumi, Tomomi; Nagao, Yoshiharu
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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.