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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
Nakamura, Kazuyuki; Ida, Mizuho; Kanemura, Takuji; Kondo, Hiroo; Niitsuma, Shigeto; Hirakawa, Yasushi; Furukawa, Tomohiro; Watanabe, Kazuyoshi; Horiike, Hiroshi; Terai, Takayuki*; et al.
no journal, ,
Three and half years has been passed from the start of IFMIF/EVEDA. In IFMIF/EVEDA, tasks for Lithium Target System consists of 5 validation tasks (LF1-5) and a design task (ED3), and are shared by Japan and Europe. Japan is covering the construction and operation of EVEDA Li Test Loop (LF1), diagnostics (LF2), purification system (LF4), remote handling system (LF5) and engineering design (ED3) with the contribution from universities. The present status of these tasks will be reported in the conference.
Terada, Kazushi*; Iwamoto, Nobuyuki
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.
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.
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.