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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.
Tada, Hiroyuki*; Saito, Akira*; Nakaya, Atsushi*; Kumasaka, Hiroo*; Hayashi, Katsuhiko; Noguchi, Akira; Kishi, Hirokazu; Nakama, Shigeo
no journal, ,
Bending test of the segmental rings consist of staggered pieces of rocks bonded by low-pH mortar is conducted in order to identify the mechanical properties of rock segmental rings comparing with parallel arrangement. As a result, it was found that the maximum load was reached at 130 to 210 kN in the positive bending tests for staggered rock blocks, lower than 210 to 270 kN for rock blocks arranged in parallel. In the negative bending tests, on the other hand, the maximum load was reached at 30 to 40 kN, lower than a maximum load of 40 kN for the rock blocks arranged in parallel. The results thus varied. Cracks occurred along the interface between the rock block and mortar in the specimen for the blocks arranged in parallel. For the staggered rock blocks, cracks penetrated through the mortar and the rock block near the point of loading in the specimen. Thus, it was confirmed that cracking occurred in different manners.
Komoto, Norio; Sasaki, Hirofumi; Kawata, Tsuyoshi; Taki, Kiyotaka; Kinoshita, Shigemi*
no journal, ,
no abstracts in English
Nagai, Haruyasu; Kobayashi, Takuya; Tsuzuki, Katsunori; Terada, Hiroaki
no journal, ,
no abstracts in English
Kofuji, Hirohide; Sawada, Nobuyuki*; Sasaki, Kazuya*; Amamoto, Ippei; Myochin, Munetaka; Suzuki, Akihiro*; Terai, Takayuki*
no journal, ,
The phosphate conversion process has been studied for reuse of spent electrolyte generated from pyrochemical reprocessing. As the fundamental information of thermodynamic data, heat capacities of some kind of phosphate were measured and phosphate conversion reactions were discussed based on such thermodynamic data.
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
no journal, ,
no abstracts in English
Akaoka, Katsuaki; Maruyama, Yoichiro; Oba, Masaki; Miyabe, Masabumi; Wakaida, Ikuo
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no abstracts in English
ray and its scintillation propertiesSekiwa, Hideyuki*; Miyamoto, Miyuki*; Tokutake, Taichi*; Yoshikawa, Akira*; Yanagida, Takayuki*; Izaki, Kenji
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no abstracts in English
Osaka, Masahiko
no journal, ,
Discussion on aspects of the public acceptance of thorium fuel are reported. The discussion was made at "the working group on utilization of thorium fuel in LWR and FBR" chaired by Prof. S. Yamanaka of Osaka University. established in AESJ.
Ishikawa, Makoto; Iwai, Takehiko*; Numata, Kazuyuki*; Kugo, Teruhiko; Oki, Shigeo
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no abstracts in English
Am using ANNRIHarada, Hideo; Ota, Masayuki; Oshima, Masumi; Kitatani, Fumito; Kimura, Atsushi; Kin, Tadahiro; Koizumi, Mitsuo; Goko, Shinji; Toh, Yosuke; Nakamura, Shoji; et al.
no journal, ,
The Am(n,
)
Am cross section has been measured using the accurate neutron-nucleus reacion measurment instrument (ANNRI) installed at the material and life-science experimental facility (MLF)in J-PARC. The Ge spectrometer in the ANNRI was used for measuring the prompt -rays. Based on the measurements and analyses, the applicability of ANNRI to neutron capture cross section measurement was investigated.
Morimoto, Kyoichi; Kato, Masato; Ogasawara, Masahiro*
no journal, ,
In MOX fuel stored for long term, the defects induced by self-irradiation (alpha decay) increase with an increase of storage time, and consequently its thermal conductivities decrease by an accumulation of these defects. Some investigators showed that these defects were decreased or annihilated by heat treatment, and then the lattice parameter, thermal conductivity, etc of fuel were recovered. In this study, we prepared the specimens divided from MOX fuels stored for about fifteen years. We investigated a recovery behavior of the thermal conductivities of this specimen and evaluated this behavior as functions of heating temperature and heating time.
Ishikawa, Joji; Nakashio, Nobuyuki; Osugi, Takeshi; Iseda, Hirokatsu; Mizoguchi, Takafumi; Kozawa, Kazushige; Momma, Toshiyuki
no journal, ,
no abstracts in English
,n) cross sections for Se isotopes; The Selection of the strength functionKitatani, Fumito; Goko, Shinji*; Harada, Hideo; Akimune, Hidetoshi*; Utsunomiya, Hiroaki*; Toyokawa, Hiroyuki*; Yamada, Kawakatsu*
no journal, ,
no abstracts in English
Yokoyama, Kenji; Ishikawa, Makoto; Kugo, Teruhiko
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.