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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.
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
Isozaki, Toshihiko; Tsutagi, Koichi; Shirato, Yoji; Nakazawa, Yutaka; Kake, Yasuhiro; Furukawa, Shinichi
no journal, ,
no abstracts in English
Morimoto, Yasuyuki; Tanaka, Yoshio; Takahashi, Nobuo; Tokuyasu, Takashi; Sugitsue, Noritake
no journal, ,
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*
no journal, ,
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
no journal, ,
no abstracts in English
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.
Yamada, Fumiaki; Araki, Kosuke*
no journal, ,
There was not the influence that Monju system startup tests data gave to numerical analysis of large pipe break in primary heat transfer system concerned from comparison actual plant base analysis and before conservative base analysis.
Nagai, Ryoji; Hajima, Ryoichi; Nishimori, Nobuyuki
no journal, ,
no abstracts in English
Yoshida, Hiroyuki; Suzuki, Takayuki*; Takase, Kazuyuki; Ikuta, Ryuhei*; Koizumi, Yasuo*
no journal, ,
no abstracts in English
Ikuta, Ryuhei*; Koizumi, Yasuo*; Yoshida, Hiroyuki; Takase, Kazuyuki
no journal, ,
no abstracts in English
Aoyama, Yasuo; Komuro, Michiyasu; Seki, Masakazu; Izawa, Kazuhiko; Sono, Hiroki; Ogawa, Kazuhiko; Yanagisawa, Hiroshi; Miyoshi, Yoshinori
no journal, ,
no abstracts in English
Takano, Masahide; Yamagishi, Isao; Akabori, Mitsuo; Minato, Kazuo; Yoshioka, Masahiro*; Ochi, Eiji*; Fukui, Toshiki*; Komamine, Satoshi*
no journal, ,
no abstracts in English
Morihira, Masayuki; Mizusako, Fumiki*; Tsuboi, Yasushi*
no journal, ,
A feasibility study for oxygen getter options is conducted in JAEA to reduce cladding inner corrosion of FBR MOX fuels to attain high burn-up. Investigation of oxygen getter loading options for pellet type MOX fuels as well as evaluation results of oxidation behavior of the candidate materials are reported.
Miwa, Shuhei; Usuki, Toshiyuki; Sato, Isamu; Hirosawa, Takashi; Tanaka, Kosuke; Osaka, Masahiko; Seki, Takayuki*; Kashimura, Naoki*
no journal, ,
no abstracts in English
Suzuki, Mitsuru
no journal, ,
no abstracts in English