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Katayama, Masaharu*; Takamatsu, Kuniyoshi; Sawa, Kazuhiro; Takagi, Naoyuki*; Ooka, Yasunori*; Yamasaki, Masatoshi*
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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.
Hata, Haruhi; Yokoyama, Kaoru; Sugitsue, Noritake; Hyakutake, Toru*; Muto, Akinori*; Sasakura, Mariko*; Minowa, Hirotsugu*; Suzuki, Kazuhiko*
no journal, ,
As a first step to elucidate the molecular mechanism of decontamination systems for iodine heptafluoride, uranium hexafluoride and the metal (iron), the possibility of physical adsorption and chemical reactions with uranium hexafluoride and uranium tetrafluoride (solid), we investigate the possibility of physical adsorption and chemical reactions of this. Therefore, the intermolecular of uranium hexafluorides, iron and uranium hexafluoride, uranium tetrafluoride and uranium hexafluoride (solid) and evaluated by molecular orbital method to the intermolecular potential between, based on this data, MD law adhesion mechanism was estimated by uranium hexafluoride.
Isozaki, Toshihiko; Tsutagi, Koichi; Shirato, Yoji; Nakazawa, Yutaka; Kake, Yasuhiro; Furukawa, Shinichi
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no abstracts in English
Morimoto, Yasuyuki; Tanaka, Yoshio; Takahashi, Nobuo; Tokuyasu, Takashi; Sugitsue, Noritake
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no abstracts in English
Nishimori, Nobuyuki; Nagai, Ryoji; Hajima, Ryoichi; Yamamoto, Masahiro*; Miyajima, Tsukasa*; Honda, Yosuke*; Kuriki, Masao*; Iijima, Hokuto*; Kuwahara, Makoto*; Okumi, Shoji*; et al.
no journal, ,
no abstracts in English
Ohara, Takaharu; Ikeda, Makinori; Morishita, Masaki; Miyazaki, Masashi; Shimada, Koji; Moriizumi, Makoto*
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no abstracts in English
Harada, Tatsuyuki*; Okafuji, Takashi*; Morishita, Masaki; Tsukimori, Kazuyuki
no journal, ,
no abstracts in English
Omae, Takahiro; Kato, Masaaki*; Kanayama, Haruyuki*; Morishita, Masaki
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no abstracts in English
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.
-ray NDA experiment at the Compact ERLHajima, Ryoichi; Hayakawa, Takehito; Seya, Michio; Kawata, Hiroshi*; Kobayashi, Yukinori*; Urakawa, Junji*
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no abstracts in English
-ray beams; Simulation of -ray generation and detectionHajima, Ryoichi; Hayakawa, Takehito; Kikuzawa, Nobuhiro
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no abstracts in English
Ikuta, Ryuhei*; Koizumi, Yasuo*; Yoshida, Hiroyuki; Takase, Kazuyuki
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no abstracts in English
Aoyama, Yasuo; Komuro, Michiyasu; Seki, Masakazu; Izawa, Kazuhiko; Sono, Hiroki; Ogawa, Kazuhiko; Yanagisawa, Hiroshi; Miyoshi, Yoshinori
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no abstracts in English
Sato, Toshinori; Saegusa, Hiromitsu; Hama, Katsuhiro; Ogata, Nobuhisa; Mikake, Shinichiro
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Japan Atomic Energy Agency has been conducting Mizunami Underground Research Laboratory (URL) Project aiming to establish a firm scientific basis for safe geological disposal including: establishing investigation techniques, analysis and assessment of the deep geological environment, and applicability assessment of engineering technologies for designing and constructing underground facilities. This report describes the construction status of the URL, the results of deep geological investigations carried out, and the future plan of this project.
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
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no abstracts in English
Nagai, Haruyasu; Kobayashi, Takuya; Tsuzuki, Katsunori; Terada, Hiroaki
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no abstracts in English
Koide, Masashi*; Saito, Takumi*; Nagasaki, Shinya*; Yamamoto, Yuhei; Mizuno, Takashi
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no abstracts in English
Sugino, Kazuteru; Ohgama, Kazuya; Nakazato, Wataru*; Moriwaki, Hiroyuki*
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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
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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.