巻号一覧
後続誌
34 巻, 3 号
選択された号の論文の5件中1～5を表示しています
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秋山 守, 星野 力, 清水 彰直, 宮 健三, 高橋 博, 岩田 修一, 矢川 元基, 中川 雅俊, 近藤 駿介1992 年 34 巻 3 号 p. 193-226
発行日: 1992/03/30
公開日: 2010/01/08
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斯波 正誼, 石田 泰一, 芳賀 暢, 井上 修二, 仁紫 明人, 児玉 城司, 三竹 晉, 平野 光將, 宮口 公秀, 飯嶋 敏哲1992 年 34 巻 3 号 p. 227-238
発行日: 1992/03/30
公開日: 2011/02/17
ジャーナル フリーThe regulatory authorities need in the licensing process to examine the licensee's safety analysis by analyzing by themselves some events independently. For this purpose, Japan Institute of Nuclear Safety (JINS) was established in Nuclear Power Engineering Center (NUPEC) in 1980. Since then, JINS has been preparing, improving and developing safety analysis codes, and applied them to audit calculations for nuclear power plants (NPP) and fuel cycle facilities (FCF). Further, JINS is conducting the probabilistic safety assessment (PSA) with the aim to complement the deterministic safety assessment.
This review describes the development at JINS of safety anlysis techniques for NPP (Chap. II) and FCF (Chap. III), of the PSA (Chap. IV) and of environmental dose assessment (Chap. V). Most of the codes have been completed to be applicable for safety examination by the regulatory authorities.抄録全体を表示PDF形式でダウンロード (7183K) -
小原 徹, Milton C. EDLUND1992 年 34 巻 3 号 p. 256-258
発行日: 1992/03/30
公開日: 2011/02/17
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古田 一雄, 堀 慎一郎, 近藤 駿介1992 年 34 巻 3 号 p. 259-265
発行日: 1992/03/30
公開日: 2011/02/17
ジャーナル フリーAn architecture to support nuclear power plant operators for monitoring abnormal symptoms has been proposed based on the techniques of knowledge engineering, and the feasibility of a plant monitoring support system was investigated. The purpose of the support system is to present the operators with useful information so that they can make correct judgment at an early and subtle stage of abnormal plant conditions. In the architecture proposed, abductive reasoning is performed to search for causal events and deductive one to predict consequential events using the knowledge representing plant components as frames and those representing causal relations as production rules. A method to deal with uncertainties in each type of reasoning has been adopted, and it is used to rank several hypotheses of causal events and to assess the importance of plant parameters for monitoring. A prototype system was developed, and its usefulness was tested using a case of failure in a recirculation pump of a BWR plant.抄録全体を表示PDF形式でダウンロード (2369K) -
佐藤 千之助, 車田 亮, 川又 清弘, 鈴木 信幸, 金子 光信, 福田 幸朔1992 年 34 巻 3 号 p. 266-276
発行日: 1992/03/30
公開日: 2011/02/17
ジャーナル フリーTo simulate the nuclear fuel for the High Temperature Engineering Testing Reactor (HTTR), fuel compact models using SiC-kernel coated particles instead of UO2-kernel coated particles were prepared under the same conditions as those for the real fuel compact. The mechanical and fracture mechanics properties were studied at room temperature. The thermal shock resistance and fracture toughness for thermal stresses of the fuel compact were experimentally assessed by means of arc discharge heating applied at a central area of the disk specimens. These model specimens were then neutron irradiated in the Japan Material Testing Reactor (JMTR) for fluences up to 1.7×1025n/mm2 (E>29fJ) at 900°C±50°C. The effects of irradiation on a series of fracture mechanical properties were evaluated and compared with the cases of graphite IG-110 used as the core materials in the HTTR.抄録全体を表示PDF形式でダウンロード (16456K)
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