巻号一覧
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25 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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土屋 毎雄1983 年 25 巻 5 号 p. 320-328
発行日: 1983/05/30
公開日: 2009/04/21
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香山 晃, 井形 直弘1983 年 25 巻 5 号 p. 329-336
発行日: 1983/05/30
公開日: 2009/04/21
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石榑 顕吉, 大沢 安隆, 内田 俊介1983 年 25 巻 5 号 p. 337-343
発行日: 1983/05/30
公開日: 2009/04/21
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木村 一治, 山室 信弘, 渡辺 昇, 田中 茂也, 中原 康明, 朝岡 卓見, 浅見 明, 安 成弘, 石川 義和, 石野 栞, 加藤 義 ...1983 年 25 巻 5 号 p. 344-355
発行日: 1983/05/30
公開日: 2009/04/21
ジャーナル フリーTwo types of neutron emitting and breeding target systems were considered, those consisting mainly of heavy metals and molten salt containing fertile material like Th or U. Their performance studies have been made applying a computational procedure for hadron transport incorporated with high energy fission. Structural models of molten salt reactor system are presented for the future studies. Review is made of the neutron nuclear data in the energy range of tens-thousand MeV. Surveys have been also made for accelerators to supply sufficient protons to the target. These studies suggest three types of accelerators which will match each phase of the development and also be useful as themselves: (1) intense proton synchrotron like "GEMINI" now under study at KEK, (2) intermediate scale proton linac for the engineering study, (3) high power proton linac for the demonstration accelerator breeder system.抄録全体を表示PDF形式でダウンロード (869K) -
金田 久, 志村 重孝, 鈴木 克彦, 北沢 俊一1983 年 25 巻 5 号 p. 356-365
発行日: 1983/05/30
公開日: 2009/04/21
ジャーナル フリーThe new computerized system has introduced to improve function of radiation protection for those who enter the radiation control area, by dealing with measurement of radiation dose, check of personal qualification, resistration of working condition and statistical treatment of these data.
This system uses combined TLD, "TL BADGE", as a radiation detection sensor, instead of conventional pocket dosimeter and film badge. TL BADGE reading instrument are installed at the entrance to the control area and at working areas. The data of radiation dose, personal qualification etc. read by the reading instrument are transmitted directly to the computer system, which compiles and transacts these data. This system is consisted of three minicomputers, double memory files, CRTs for effective data search and display and floppy disks as a medium for registration, etc. Thus the computer system improves its reliability and the maintenanceability of data, being capable of automatical transaction of a great amount of data quckly.
This report describes: Concept of using computer system, System outline, Measurement of radiation dose and Operational functions.抄録全体を表示PDF形式でダウンロード (2344K) -
池谷 元伺, 三木 俊克1983 年 25 巻 5 号 p. 370-371
発行日: 1983/05/30
公開日: 2009/04/21
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桜井 文雄, 新保 利定1983 年 25 巻 5 号 p. 372-382
発行日: 1983/05/30
公開日: 2009/04/21
ジャーナル フリーThe neutron fluence above 1.0MeV or 0.1MeV is routinely reported as the fast neutron irradiation dose value for materials irradiation experiments in the Japan Materials Testing Reactor (JMTR). The radiation damage of materials is, however, affected by not only the amount of the neutron fluence but also the neutron energy spectrum. Therefore, in the radiation damage studies of materials the neutron irradiation dose values should be expressed in the exposure parameter containing the information of the neutron energy spectrum.
This report describes some exposure parameters such as displacement per atom and damage fluence, and correlations between these parameters and the neutron fluence above 1.0MeV in the JMTR. These parameters have deep connection with changes in the physical properties of materials under neutron irradiation.
The neutron irradiation dose values in the JMTR can be evaluated in some kinds of exposure parameters containing the information of the neutron energy spectrum from the neutron flunce above 1.0MeV measured by using the 54Fe(n, p)54Mn monitor.抄録全体を表示PDF形式でダウンロード (643K) -
配管とレストレントとのクリアランスの影響植田 脩三, 栗原 良一, 磯崎 敏邦, 宮崎 則幸, 加藤 六郎, 宮園 昭八郎, 斎藤 和男1983 年 25 巻 5 号 p. 383-393
発行日: 1983/05/30
公開日: 2010/03/08
ジャーナル フリーThis paper describes results of the experimental and analytical research concerning a phenomenon of pipe whipping and behavior of restraints to limit the pipe movement in the postulated loss-of-coolant accident of BWR nuclear power plants.
The test pipe, which was made of Type 304 stainless steel, was 114.3mm in diameter and 8.6mm in thickness. Four restraints of U-type were used. The rod of the restraint which was made of Type 304 stainless steel, was 8mm in diameter. The overhang length between the pipe exit and the restraints was 400mm. The clearances between the pipe and the restraint were 30, 50 and 100mm. In all the experiments the restraints limited the pipe movement. The residual restraint strain was less than the elongation of this material. The peak value of the pipe strain occurred near the restraints due to the rotation of the pipe after the impact. This value was less than the elongation of the pipe material.
Calculations of the restraint strain, restraint force and the impact time were peformed using the general purpose finite element program ADINA. The trend of the calculated results was in agreement with that of the experimental results.抄録全体を表示PDF形式でダウンロード (3791K)
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