巻号一覧
後続誌
17 巻, 8 号
選択された号の論文の8件中1～8を表示しています
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村田 寿典, 遊佐 英夫1975 年 17 巻 8 号 p. 392-397
発行日: 1975/08/30
公開日: 2010/01/08
ジャーナル フリーPDF形式でダウンロード (386K) -
核燃料・炉材料等分析委員会の活動を中心として辻村 重男1975 年 17 巻 8 号 p. 398-403
発行日: 1975/08/30
公開日: 2011/02/17
ジャーナル フリーProgress in analytical chemistry associated with atomic energy is reviewed with particular emphasis on the activity of the Committee on Analytical Chemistry of Nuclear Fuels and Reactor Materials, Japan Atomic Energy Research Institute.
Analytical methods for the determination of impurities and of constituents contained in nuclear fuels such as uranium metal, uranium oxide and uranium carbides as well as in reactor materials such as zircaloy, sodium and high temperature alloy were examined through comparison of the analytical results obtained by different laboratories. The Committee also prepared reference samples of uranium, zircaloy and high temperature alloys.抄録全体を表示PDF形式でダウンロード (427K) -
清瀬 量平, 関口 善之, 宮本 不二男, 丸山 正倫, 九十九 清彦, 西堀 俊雄, 北原 義久, 松本 徳太郎, 中田 啓, 斎藤 親, ...1975 年 17 巻 8 号 p. 404-413
発行日: 1975/08/30
公開日: 2011/02/17
ジャーナル フリーThis report includes a summarized version of a design standard proposed by the Research Committee on Standards for Criticality Alarm Systems, which was organized in the Atomic Energy Society of Japan in October, 1973 and which terminated its activities in March, 1975. Some additional information on criticality alarm systems are included, such as the basic characteristics of criticality accidents, examples of criticality alarm systems installed in Japanese, as well as in some foreign nuclear fuel facilities, functional checks and tests of criticality alarm systems, and a survey of relevant standards already proposed and used in U.S.A., U.K. and other countries. The proposed standard incorporates reliability considerations and a criticality accident to be assumed in designing criticality alarm systems.抄録全体を表示PDF形式でダウンロード (643K) -
1975 年 17 巻 8 号 p. 414-419
発行日: 1975/08/30
公開日: 2011/02/17
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「欧文誌」投稿者のために吉田 正男1975 年 17 巻 8 号 p. 427-428
発行日: 1975/08/30
公開日: 2011/02/17
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安 成弘, 佐藤 禎1975 年 17 巻 8 号 p. 429-431
発行日: 1975/08/30
公開日: 2011/02/17
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星 龍夫1975 年 17 巻 8 号 p. 432-438
発行日: 1975/08/30
公開日: 2011/02/17
ジャーナル フリーIn order to facilitate the calculation of energy utilization efficiency in gamma-irradiators a method for approximate calculation was established considering that: (1) The energy utilization efficiency is defined by the product of geometrical and absorption efficiencies; (2) The geometrical efficiency depends on the shape of both the γ-ray source and the surface of the irradiated material and their relative positions; (3) The absorption efficiency mainly depends on the maximum and the minimum penetration lengths of γ-rays in the irradiated material when the irradiator is designed so that energy of γ-rays is effectively absorbed in the irradiated material. In this approximation the geometrical efficiency is easily determined by combining the geometrical efficiencies for a case where the shapes of both γ-ray source and surface of the irradiated material are simulated by simplified approximations, and the absorption efficiency is easily determined by an approximative formula which does not depend on the shape of either γ-ray source or surface of the irradiated material. In a cylindrical material with line source at the center, the energy utilization efficiency obtained by this method agrees with the exact value to within ±4%.抄録全体を表示PDF形式でダウンロード (403K) -
宮 健三, 橋本 光男, 岡村 和夫, 安藤 良夫1975 年 17 巻 8 号 p. 439-446
発行日: 1975/08/30
公開日: 2011/02/17
ジャーナル フリーIt is of great interest to establish a method for analyzing the transient thermal contact problem of fuel and cladding with use made of the Finite Element Method. Such a method is presented, which deals with transient temperature distributions in fuel and cladding assumed to be in contact with each other. The general matrix equation is composed of matrix equations for fuel and cladding, the two matrix equations being then coupled by the boundary conditions at the interface.
On the one hand, dynamic operation of the University of Tokyo Reactor [YAYOI] has been successfully performed as a preliminary step to pulsed operation. Measurements were made of the transient temperature on the cladding surface. Some of measured results were analyzed by means of the Finite Element Method, as a result of which an insight was gained on the transient temperature distribution in the fuel and cladding produced during the dynamic operation of [YAYOI]. The information thus obtained should serve usefully in the safety analysis of the dynamic operation in respect of cladding integrity.抄録全体を表示PDF形式でダウンロード (421K)
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