日本原子力学会誌
Online ISSN : 2186-5256
Print ISSN : 0004-7120
ISSN-L : 0004-7120
11 巻, 3 号
選択された号の論文の6件中1~6を表示しています
  • 中村 治人, 山林 尚道
    1969 年 11 巻 3 号 p. 134-137
    発行日: 1969/03/30
    公開日: 2010/04/19
    ジャーナル フリー
    Electorolytically purified manganese metal was used as target material for the production of 56Mn by (n, γ) reaction. The impurities were first roughly determined by nondestructively measuring their radioactivities after irradiation, and then precisely by combining chemical separation with activation analysis. Antimony, chromium, scandium and europium were found present, to the extent of a few ppm or lower.
    In addition, 54Mn produced by 55Mn(n, 2n) 54Mn reaction with fast neutrons was also detected. In order to estimate the production rate of this 54Mn, the activation cross section of this nuclear reaction was estimaied from the activities of 54Mn in a manganese target irradiated in one of the hollow fuel elements of JRR-2. It was estimated to be 0.19mb which roughly agreed with the value of 0.16mb obtained by Roy et al. (1960).
    Radiochemical impurities in the 56Mn produced in the Japan Atomic Energy Research Institute were estimated from the values obtained above and the irradiation conditions used for the production. It was found that the product is 99.999% radiochemically pure 56Mn.
  • 活性炭へのヨウ素およびヨウ化メチルの吸着
    村田 寿典, 神谷 九二男
    1969 年 11 巻 3 号 p. 138-143
    発行日: 1969/03/30
    公開日: 2010/04/19
    ジャーナル フリー
    In order to obtain adsorption data for iodine and methyliodide at low partial pressures, helium gas containing iodine or methyliodide was passed through a small activated carbon bed, and the amount of iodine and methyliodide adsorbed was measured. The specific adsorption of both iodine and methyl iodide at temperatures from 50° to 400°C was determined, together with the rate of desorption and the amounts irreversibly adsorbed.
    From these results it was found that the rate of adsorption can be, expressed by the equation given by Bangham, and the isotherms by that of Freundlich. The differential heats of adsorption were obtained through the use of Clausius-Clapeyron's equation.
  • 宮坂 駿一, 金森 善彦, 福島 穣, 山田 毅
    1969 年 11 巻 3 号 p. 144-149
    発行日: 1969/03/30
    公開日: 2010/04/19
    ジャーナル フリー
    This study has been performed as part of a series of mock-up tests undertaken in relation to the shielding design for the first Japanese nuclear propelled ship. The subject is reactor γ-ray leakage through a part of the shielding forming the junction between 15cm thick lead and 75cm thick concrete slabs, with the lead wall abutting at right angles against the side of the concrete shielding. The experimental results are expressed as functions of slit width, beam incident angle and point of observation. The observed data are compared with calculations based on ray-analysis for penetration components, and on single scattering method for streaming components.
  • 原研JPDRおよびTCAを用いて
    村主 進, 松浦 祥次郎
    1969 年 11 巻 3 号 p. 150-157
    発行日: 1969/03/30
    公開日: 2010/04/19
    ジャーナル フリー
    The recycled utilization of Pu produced in light water reactors is expected to become a prominent problem in the period from 1975 to 1990. While Pu utilization in light water reactors has been confirmed to be technically feasible in basic principle, practical application will still require prior solution of a number of problems. Of such problems, the most important in the domain related to reactor core characteristics include the accurate evaluation of the reaction rate in the fuel rod and of the power distribution in irregular lattices, as well as burnup systematics. Further detailed and accurate measurements and analyses must be performed on these problems through examination of burnup histories. A series of experimental and analytical studies using JPDR (Japan Power Demonstration Reactor) and TCA (Tank-type Critical Assembly) at the Japan Atomic Energy Research Institute is being planned for gaining information on the characteristics of PuO2-UO2 fuel assemblies and core, and as preliminary tests on fuels to precede their practical utilization in large power reactors.
  • 古川 和男, 高橋 正男, 木谷 進, 岩本 多実, 二瓶 勲, 亀井 満
    1969 年 11 巻 3 号 p. 158-171
    発行日: 1969/03/30
    公開日: 2010/04/19
    ジャーナル フリー
  • 村主 進, 三井田 純一
    1969 年 11 巻 3 号 p. 172-183
    発行日: 1969/03/30
    公開日: 2010/04/19
    ジャーナル フリー
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