巻号一覧
後続誌
23 巻, 5 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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松本 純一郎1981 年 23 巻 5 号 p. 303-309
発行日: 1981/05/30
公開日: 2009/04/21
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井上 晃次, 白方 敬章, 金城 勝哉, 池上 哲雄, 山本 正昭1981 年 23 巻 5 号 p. 310-317
発行日: 1981/05/30
公開日: 2009/04/21
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諸住 正太郎, 李 基淳1981 年 23 巻 5 号 p. 318-323
発行日: 1981/05/30
公開日: 2009/04/21
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柚原 俊一1981 年 23 巻 5 号 p. 324-337
発行日: 1981/05/30
公開日: 2010/01/08
ジャーナル フリーIn recent years, considerable progress has been made and experience has been obtained for material applicability in sodium-cooled fast breeder reactors.
In this report, materials, principal dimensions and sodium conditions for the reactor system components, which include fuel pin cladding, intermediate heat exchangers, steam generators and pipings, are reviewed with emphasis on the thin-walled, high temperature and high strength components. The corrosion, mechanical and tribological behavior in sodium of important materials used for the reactor components, such as Types 304 and 316 stainless steel and 21/4Cr-1Mo steel, are discussed on the basis of characteristic testing results. Furthermore, material requirements concerned with compatibility in sodium are summarized from this review and discussion.抄録全体を表示PDF形式でダウンロード (3805K) -
加藤 清, 戸沢 誠一, 前田 頌1981 年 23 巻 5 号 p. 338-341
発行日: 1981/05/30
公開日: 2009/04/21
ジャーナル フリーThis report summarized the survey on drum containers for radioactive wastes which were used at nuclear power plants and research institutes in Japan, with respect to the specifications such as structure and coating system. The containers investigated are full removable head steel drums (200l) specified by JIS Z 1600 (1977). The drums made of steel sheets of 1.6mm thickness are most widely used in nuclear facilities. These conventional drums are coated with melamine-alkyd resin paints on the outside and epoxy resin paints on the inside, after the surface treatment with zinc phosphate.抄録全体を表示PDF形式でダウンロード (240K) -
大内 正博1981 年 23 巻 5 号 p. 353-354
発行日: 1981/05/30
公開日: 2009/04/21
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山田 直之, 木口 高志, 別所 泰典, 土居 一順, 桜井 三紀夫1981 年 23 巻 5 号 p. 355-364
発行日: 1981/05/30
公開日: 2009/04/21
ジャーナル フリーThe change of core characteristics, especially power distribution, during daily load following operation of BWR, has been analyzed by a three-dimensional core simulator with xenon dynamics.
The change of power distribution has been classified into two types. The first is that the power of the upper part of the core exceeds the value at the standard distribution when power level returns to the high level from the low level, where the standard distribution is defined as the distribution for equilibrium xenon state at the rated power and flow. This type is termed "FH type". The second is that the power of the lower part of the core exceeds the value at the standard distribution, after several hours of operation at high power level. This type is termed "FL type". It has been found that in the FH type, the increase of power at the upper part of the core is mainly due to the change of the void fraction. On the other hand, the increase of power at the lower part of the core in the FL type has been found to be mainly caused by the change of xenon concentration.
The effects of parameters, such as high power level and low power level, which specify the daily load following pattern on both types of power distribution change, have been evaluated quantitatively.抄録全体を表示PDF形式でダウンロード (573K) -
本島 健次, 河村 文雄1981 年 23 巻 5 号 p. 365-369
発行日: 1981/05/30
公開日: 2009/04/21
ジャーナル フリーFundamental experiments on radio-cobalt ion removal characteristics of oxine impregnated activated charcoal in sodium sulfate solution were performed, in order to evaluate the applicability of this adsorbent to treat radioactive liquid waste which contained a large amount of salts.
The effects of sodium sulfate concentration, pH, cobalt ion concentration, type of carrier activated charcoal and coexistence ion (CO32-, Ca2+, Mg2+, Ni2+, Zn2+) were studied. Column experiments showed that cobalt ions could be removed selectively under the conditions of Na2SO4 concentration 0-20w/0 and pH 7.5-10. However removal effciency decreased as the acidity of the solution increased. As to the effect of coexistence ion, slightly decrease in the efficiency was observed under the presence of CO32-, Ca2+ and Mg2+ ions. However removal efficiency decreased as the presence of transition divalent metal ions, such as Ni2+ and Zn2+ ions. Cobalt removal efficiency is not influenced under the type of carrier activated charcoal. And cobalt ions could be removed selectively too in the Na2B4O7 solution.抄録全体を表示PDF形式でダウンロード (281K)
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