巻号一覧
後続誌
15 巻, 10 号
選択された号の論文の6件中1～6を表示しています
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わが国における核データ活動との関連塚田 甲子男1973 年 15 巻 10 号 p. 641-646
発行日: 1973/10/30
公開日: 2010/04/19
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三井田 純一, 石塚 信, 荒 克之, 市川 逵生, 佐藤 一男1973 年 15 巻 10 号 p. 647-660
発行日: 1973/10/30
公開日: 2010/04/19
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平野 武彦1973 年 15 巻 10 号 p. 661-666
発行日: 1973/10/30
公開日: 2010/04/19
ジャーナル フリーA review is presented, which summarizes both experimental and theoretical studies reported during the nine-year period 1964-73 on pumping methods for lasers using nuclear reactions either with or without electrical discharge (Nuclear Pumped Lasers or else Direct Nuclear Pumped Lasers). In much of the reported experimental work, the 10B(n, α)7Li and 3He (n, p)3H nuclear reactions have been utilized as source for high energy heavy particles with neutron fluxes ranging from 108 to 1017n/cmcm2·sec. Most of the theoretical work has been focused on the calculation of threshold neutron flux requirements for noble gases or CO2 lasers. The threshold estimates fall in the range 1.2×109-1018n/cmcm2·sec on 10B. A theoretical model was proposed by Guyot et al. which predicts the behavior of the metastable densities in noble-gas plasmas created by nuclear radiations. The present author is now undertaking jointly with Shipman a study of the electron energy distribution function in nuclear pumped lasers using the combined Boltzmann-Fokker-Planck equation.抄録全体を表示PDF形式でダウンロード (343K) -
日米科学セミナー報告菅野 昌義1973 年 15 巻 10 号 p. 667-676
発行日: 1973/10/30
公開日: 2010/04/19
ジャーナル フリーA review is presented on the U.S.-Japanese Cooperative Seminar entitled "Thermodynamics and Phase Relations of Nuclear Materials", held at Ames Laboratory, U.S. AEC, Iowa State University, July 9-12, 1973. Summary proceedings of the seminar and a comprehensive description of the topics discussed are reported.
On the total of 7 sessions held, 2 sessions, in which 6 papers were presented, were devoted primarily to theoretical and experimental methods including Engel-Brewer's theory, vaporization studies, heat capacity measurements and electromotive force measurements.
The 5 other sessions, in which 14 papers were presented, dealt with the phase relations and the thermodynamic properties of various materials, as well as the thermodynamics of fused salts and liquid metal solutions.抄録全体を表示PDF形式でダウンロード (1518K) -
大塚 徳勝, 山本 忠利1973 年 15 巻 10 号 p. 681-692
発行日: 1973/10/30
公開日: 2010/04/19
ジャーナル フリーIrradiation facilities using 85Kr as radiation source have been devised for producing chemical reactions in liquid phase. For this purpose, the 85Kr gas is dispersed uniformly in the liquid phase containing the reactants, so that the 85Kr gas and the reactants come into direct contact with each other. The paper presents a description of such a facility, together with its performance, and the technical problems encountered in the designing and manufacturing stages (particularly, for the prevention of 85Kr gas leakage, and for the removal and recovery of 85Kr gas dissolved in the liquid reactants). Safety considerations are also discussed. Some typical experimental results are reported.
Irradiation experiments were performed in a reaction vessel of 1l capacity charged with 300Ci of 85Kr. It was observed that the maximum dose rate reaches 1.8×104 rad/hr, and that the radioactive concentration after removal of the 85Kr gas dissolved in the solution diminishes to a level below 10-5μCi/g. From these results, it is concluded that it should be quite practical to use 85Kr gas as a radiation source for chemical reaction in liquid phase.抄録全体を表示PDF形式でダウンロード (851K) -
流れに沿う状態変化と臨界流の理論安達 公道1973 年 15 巻 10 号 p. 693-701
発行日: 1973/10/30
公開日: 2010/04/19
ジャーナル フリーThe author has proposed a new theoretical method for analyzing two-phase flashing flow. Two independent energy equations were used, one related to the unit flowing weight of the two-phase mixture and the other to its unit existing weight. This method can be applied to any one-component, two-phase flow, from subcritical to supercritical, provided the following basic assumptions are satisfied:
(1) One-dimensional flow, (2) Steady flow, (3) Adiabatic flow,
(4) Gravity force is negligible, (5) Thermally saturated flow.
Two-phase critical flow can be determined as a maximum weight velocity flow, corresponding to the conditions dictated by the high pressure reservoir tank. Numerical calculations of critical parameters show good agreement with the experimental values.抄録全体を表示PDF形式でダウンロード (476K)
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