巻号一覧
後続誌
2 巻, 4 号
選択された号の論文の7件中1～7を表示しています
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主としてコールダーホール改良型発電炉の分割制御方式について武田 充司1960 年 2 巻 4 号 p. 175-181
発行日: 1960/04/30
公開日: 2009/02/12
ジャーナル フリーIn the core of a large power reactor the shape of neutron flux distribution tends to be distorted in transient behavior. Especially in the core with positive temperature coefficient, such as the improved Calder Hall type reactor, the distortion becomes unstable to result in divergence or oscillation. In order to control such a reactor the spatial control system should be provided such that control rods are locally divided into several groups and each group of control rods is independently moved to control the local reactivity. Therefore, the kinetic analysis of such a reactor requires the new method which can describe the time behavior of neutron flux shape and temperature distribution in the core. In this paper the author proposes a new method using the mode transfer functions which are determined corresponding to spatial eigenfunctiors. Applying this method the spatial kinetic analysis can be resolved into each mode kinetic analysis without any spatial consideration.抄録全体を表示PDF形式でダウンロード (375K) -
加地 郁夫, 小沢 保知1960 年 2 巻 4 号 p. 182-189
発行日: 1960/04/30
公開日: 2009/03/27
ジャーナル フリーThe possible occurrence of plasma instabilities has increased the necessity of further investigation on plasma oscillations since the Second International Conference in Geneva. Though a number of paper has already been presented, there still remain lots of unsolved problems.
In this paper detailed considerations were made against the dispersion equations of potential function and of velocity distribution function respectively.
Several new dispersion relations were derived and tabulated each for amplified, continuous and damped plasma oscillations.抄録全体を表示PDF形式でダウンロード (449K) -
ウラン燃料要素に関する研究, (6)武谷 清昭, 市川 逵夫1960 年 2 巻 4 号 p. 190-195
発行日: 1960/04/30
公開日: 2009/02/12
ジャーナル フリーTo develop the fuel element for Japan Research Reactor-3, the properties of uranium fuel rod fabricated into 10m/m in diameter, are studied, and a part of the results has. already been reported in this journal. The effect of β-treatment on uranium fuel rod were studied from the points of thermal cycling growth coefficient, thermal expansion coefficient, hardness and microstructure, which has been reported in the reference. The effect of β-treatment on the texture of the same uranium fuel rod, as was used in the previous study is reported this time. As the preparation of the pole figure of a uranium fuel rod is very troublesome, inverse pole figure method has been prefered, to describe the texture of the specimen.
(001) projection of α uranium is used in this inverse pole figure. Intensities of the diffractions from 22 planes of a specimen have been measured by G.E. diffractometer and they are used for calculation. Inverse pole figures of β-treated uranium rods rolled at 300° and 600°C respectively have also been made. From the results, β-treatment at 720°C has been found to have better effect on the texture of uranium rod than that at 680°C; more homogenous distribution of crystallographic planes could be obtained, which is, therefore, the reason why β-treatment at 720°C will give smaller thermal cycling coefficient. The more homogenous is the distribution of the planes in the β-treated specimen, the smaller thermal cycling coefficient can be obtained.抄録全体を表示PDF形式でダウンロード (2267K) -
Francis T. Miles, Jr., 吉田 正男1960 年 2 巻 4 号 p. 196-201
発行日: 1960/04/30
公開日: 2009/02/12
ジャーナル フリーアメリカ原子力委員会ブルックヘーブン研究所原子力工学部次長Francis T. Miles, Jr. 博士が,原研の招聘で来日されたのを機会に, 4月1日原研主催の講演会が西堀栄三郎氏の座長で開催された。本稿は当日の通訳吉田正男氏により抄訳されたものである。抄録全体を表示PDF形式でダウンロード (1726K) -
松田 俊彦1960 年 2 巻 4 号 p. 202-212
発行日: 1960/04/30
公開日: 2009/03/27
ジャーナル フリーDuring the world-round trip from June to September in 1959, the author observed the recent tendency of the treatments of radioactive liquid wastes in Europe and U.S.A. The conclusions are as follows:
(1) Low level wastes (<10-4μc/ml) is mainly treated by the chemical coagulation, quite economically.
(2) The evaporation method is applied to medium and high level wastes and the methods of coagulation and ion-exchange are used as auxiliary treatments.
(3) It is urgent to settle the best procedure to treat high level wastes.
(4) We must be careful to adapt these foreign technics directly for our treatment, because we have different and complicated conditions, i.e. narrow territory, dense population, many calamities and special sensibilities of people hating radioactivity. We must acquire more budget for these sorts of plants and equipments in order to assure our coming progress in atomic age.抄録全体を表示PDF形式でダウンロード (1828K) -
石森 富太郎1960 年 2 巻 4 号 p. 213-217
発行日: 1960/04/30
公開日: 2009/02/12
ジャーナル フリーPDF形式でダウンロード (229K) -
1960 年 2 巻 4 号 p. 218-219
発行日: 1960/04/30
公開日: 2009/02/12
ジャーナル フリーPDF形式でダウンロード (129K)
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