巻号一覧
後続誌
34 巻, 12 号
選択された号の論文の7件中1～7を表示しています
- |<
- <
- 1
- >
- >|
-
竹田 辰興, 永嶺 謙忠, 山崎 泰規, 門野 良典, 石田 勝彦, 上村 正康, 山崎 良成, 水本 元治1992 年 34 巻 12 号 p. 1098-1107
発行日: 1992/12/30
公開日: 2010/04/19
ジャーナル フリーPDF形式でダウンロード (2801K) -
中山 良一, 竹原 健, 杉山 栄, 林 哲司, 蜂須賀 良明, 小林 光男, 岩金 孝信, 稲本 康, 亀井 光仁, 佐藤 多秀1992 年 34 巻 12 号 p. 1108-1115
発行日: 1992/12/30
公開日: 2010/04/19
ジャーナル フリーPDF形式でダウンロード (11488K) -
桝田 藤夫, 小野 良樹, 木下 詳一郎, 岩見 裕1992 年 34 巻 12 号 p. 1116-1120
発行日: 1992/12/30
公開日: 2010/04/19
ジャーナル フリーA document describing technical meaning of safety related terms for advanced nuclear plants was issued in September 1991 by IAEA. This document presents technical description of fundamental terms such as "Inherent safety" and "Grace period" and introduces consensus attained in IAEA Technical Committee Meeting and Consultants Meetings. The authors present Japanese translation of this document in order to be widely understood among Japanese engineers and scientists.抄録全体を表示PDF形式でダウンロード (409K) -
動的および静的条件下での違い大貫 敏彦, 村上 隆, 佐藤 努, 磯部 博志1992 年 34 巻 12 号 p. 1139-1142
発行日: 1992/12/30
公開日: 2010/04/19
ジャーナル フリーPDF形式でダウンロード (2861K) -
三田地 紘史, 下田 隆行, 古川 和男, 鈴木 孝司1992 年 34 巻 12 号 p. 1143-1150
発行日: 1992/12/30
公開日: 2010/04/19
ジャーナル フリーIn the design of a small molten salt power reactor, one of the important problems is the heat deposition in graphite moderators, which are irradiated with high energy γ-ray and neutron flux. To remove the deposited heat adequately, fuel salt should be distributed appropriately in the reactor core.
A numerical study was carried out in this paper, and the main concern was about the temperature distributions in the graphite moderator elements and the fuel salt. The velocity distribution of fuel salt in the reactor core was increased in proportion to the heat generation distribution which was given from the preceding neutronic design study. The heat conduction equation with appropriate boundary conditions was solved by finite element method to simulate heat transmission process in the graphite moderators. It was revealed that the maximum temperature of about 1, 150K appeared in the graphite element in the blanket. The maximum temperature gradient of about 4K/mm appeared in the element in the inner core (core I). It was also estimated that the velocity of fuel salt was about 1.0m/s in the core I, and 0.1m/s in the blanket. The thermal design study represented in this paper suggested that the heat deposition would not cause severe restrictions to construct and to run the small molten-salt power reactor.抄録全体を表示PDF形式でダウンロード (3029K) -
吉村 忍, 矢川 元基, 飯田 式彦, 渡士 克己, 藤岡 照高, 植田 浩義, 宇野 哲老, 宇野 昌嘉, 北条 公延, 植田 脩三1992 年 34 巻 12 号 p. 1151-1160
発行日: 1992/12/30
公開日: 2010/04/19
ジャーナル フリーThis paper is concerned with roundrobin analyses of probabilistic fracture mechanics (PFM) problems of aged structures and materials using seven codes.
Analyzed here is a plate with a semi-elliptical surface crack subjected to multiple cyclic tensile and bending stresses. A depth and an aspect ratio of the surface crack are assumed to be probabilistic variables. Probability calculations are performed by using Importance Sampling or Stratified Sampling Monte Carlo methods. Material properties are chosen from the Marshall report, ASME Code Section XI and the experiments of the LE-subcommittee of JWES (Japan Welding Engineering Society), while loadings are determined referring to design loading conditions of pressurized water reactors (PWR).
At first, one unique problem which is named Fundamental Problem is analyzed by all the codes to examine accuracy of PFM analyses. Secondly discussions are made on aging effects of fracture toughness, which are caused due to thermal aging and neutron irradiation, on failure probabilities. Finally life extension simulations based on the PFM analysis are presented.抄録全体を表示PDF形式でダウンロード (5066K) -
竹下 健二, 松本 史朗, 熊谷 幹郎, 古閑 二郎, 高島 洋一1992 年 34 巻 12 号 p. 1161-1165
発行日: 1992/12/30
公開日: 2010/04/19
ジャーナル フリーHydrophobic adsorbents, which consist of porous styrene-divinylbenzene copolymer (SDB) impregnated with silver, were developed for the removal of iodine from the dissolver off-gas (DOG). The adsorption of iodine in a simulated off-gas including iodine, NOx and water vapor was examined by use of an adsorption column packed with the hydrophobic adsorbents.
Silver impregnation methods using organic solutions were proposed. By use of dioxan and butylamine, which can swell the SDB easily, silver nitrate and metallic silver were uniformly distributed in the SDB particles.
The breakthrough of iodine was not influenced by the presence of NOx and water vapor. For a macroporous SDB with the pore volume of 1.59ml/g-SDB and the average pore diameter of 500Å, impregnated with metallic silver at silver content of 28wt%, a high adsorption capacity of 0.14g-I2/cm3-adsorbent was obtained, compared to that of a commercial adsorbent, AgNO3-impregnated silica gel. The impregnated silver was utilized about 91% for the iodine adsorption.抄録全体を表示PDF形式でダウンロード (5789K)
- |<
- <
- 1
- >
- >|