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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.
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
Takeuchi, Shinji; Kunimaru, Takanori; Ota, Kunio
no journal, ,
Hydraulic packer test (HT) has been carried out in the deep borehole investigations in the URL programs. Obtained results (transmissivity and flow model etc.) are used for the groundwater modeling/simulations etc. Therefore, quality of HT data is crucial for ensuring reliability of the modeling/simulation results. Thus quality management system for the HT from data acquisition has been established. The established system has been applied to the recent borehole investigations in the URL program and confirmed it's appropriateness.
Inoue, Toshihiko; Ogawa, Ryuichiro; Inoue, Masaki; Yoshitake, Tsunemitsu; Nishinoiri, Kenji
no journal, ,
no abstracts in English
Kaito, Yasuaki; Ashida, Takashi; Miyamoto, Kazuyuki; Ito, Hideaki
no journal, ,
no abstracts in English
Yamamoto, Tomohiko; Negishi, Kazuo*; Hara, Hiroyuki*
no journal, ,
The JSFR adopts SCCV for the improvement of quality and economic efficiency. For commercialization of JSFR, we have carried out the research and development of not only the study on SCCV structure and construction term at the site but also the material strength test and analysis. These series presentation show the results. In this presentation, the results of study on construction methods are shown.
Kato, Atsushi; Chikazawa, Yoshitaka; Obata, Hiroyuki*
no journal, ,
Japan Sodium-cooled Fast Reactor have been adopted a new concept of the fuel handling machine which enables a compact reactor vessel compared with a conventional one. This fuel handling machine have been developing in the FaCT project. This time, a seismic analysis at the design base seismic condition have been conducted. As a result, the fuel handling machine would not interfere the equipments around them at its seismic condition.
Itagaki, Wataru; Soga, Tomonori; Aoyama, Takafumi; Ogata, Takanari*; Nakamura, Kinya*
no journal, ,
no abstracts in English
Tanaka, Yoshio; Morimoto, Yasuyuki; Tokuyasu, Takashi; Takahashi, Nobuo; Sugitsue, Noritake
no journal, ,
In Ningyo-toge environmental engineering center started the decommissioning project of commercial-scale nuclear fuel facility in 2008. We worked on dismantling/removal of equipments in the radiation controlled area, and about 80 % were finished. Therefore, we arranged it systematically for dismantling work in work elements to need for the decommissioning project. The man-hour ratio of 3 work division was preparation 29 % and dismantlement 59 %, post-processing 12 %. The breakdown of each work division is preparations 14 processes and dismantlement 32, post-processing 11. At least 57 processes classifications are necessary for dismantling work. In addition, a man-hour ratio to need for post-processing was almost a constant in every result. On the other hand, the man-hour ratios of preparations and dismantling were classified in 3 groups.
Kushida, Noriyuki; Fujibayashi, Kenichi; Kureta, Masatoshi; Segawa, Mariko; Shinohara, Takenao; Takemiya, Hiroshi
no journal, ,
Center for Computational Science and E-systems of Japan Atomic Energy Agency has been developing elemental technologies for high-speed data analysis in order to achieve "On Site" data analysis. Recent huge experimental facilities provide tremendous amount of data, which is beyond traditional computers capability. Therefore we developed and applied novel parallel computing techniques. As a result, we achieved around 100 times speed-up in computation, and 10 times speed-up in data storage access than traditional computers.
Suzuki, Mitsuru
no journal, ,
no abstracts in English