日本原子力学会誌
Online ISSN : 2186-5256
Print ISSN : 0004-7120
ISSN-L : 0004-7120
29 巻, 5 号
選択された号の論文の9件中1~9を表示しています
  • 大輝 茂, 金子 淳, 川原 敏夫, 松本 光雄
    1987 年 29 巻 5 号 p. 368-384
    発行日: 1987/05/30
    公開日: 2009/04/21
    ジャーナル フリー
  • 秋元 正幸, 平野 雅司, 成合 英樹
    1987 年 29 巻 5 号 p. 385-391
    発行日: 1987/05/30
    公開日: 2010/03/08
    ジャーナル フリー
  • 岩崎 博
    1987 年 29 巻 5 号 p. 392-399
    発行日: 1987/05/30
    公開日: 2010/01/08
    ジャーナル フリー
  • 古屋 廣高
    1987 年 29 巻 5 号 p. 400-405
    発行日: 1987/05/30
    公開日: 2009/04/21
    ジャーナル フリー
  • 西村 正彦
    1987 年 29 巻 5 号 p. 406-407
    発行日: 1987/05/30
    公開日: 2009/04/21
    ジャーナル フリー
  • 有田 節男, 一ノ瀬 祐治, 北浦 渉
    1987 年 29 巻 5 号 p. 420-427
    発行日: 1987/05/30
    公開日: 2010/03/08
    ジャーナル フリー
    In an instrumentation and surveillance system of a large power plant, it is critical to transmit integrated information within a limited transmission capacity. This report proposes a new transmission system capable of doing this. The system features three new techniques; to transmit information with a high priority preferentially, to control full motion image and frame repetition transmission by using priority levels, and to use priority of the information in packet length control. The priority is assigned dynamically, corresponding to the status of the plant. This transmission system can efficiently transmit surveillance information from images produced by an industrial television camera (ITVC), operational process information measured at the plant, maintenance information for diagnosing the integrity of controllers, and voice information for operator communications. Transmission experiments using image information demonstrate the effectiveness of the system.
  • 基本的流動特性
    植田 公雄, 藤村 亮, 中野 才治, 平島 浩, 久保田 雄, 服部 禎男, 伊藤 力生, 平塚 法夫
    1987 年 29 巻 5 号 p. 428-435
    発行日: 1987/05/30
    公開日: 2009/04/21
    ジャーナル フリー
    A slab-type, large-scale fluidized bed reactor has been proposed as a means to obtain an adequate heat transfer area satisfying the limit of critical safe size, for use in the denitration reaction of highly enriched U. More specifically, with respect to the reactor, 120-mm wide, 1, 900-mm long, 4, 000-mm high, capable of 4% U enrichment, 3 t-U/d, examinations were conducted of its fundamental fluidization characteristics and the characteristics thus obtained showed that the reactor can be used with no ploblem and in a more stable manner than the conventional cylindrical reactor. The results are as follows:
    (1) It was found possible to approximate the reactor's fluidization initiation gas rate to the values obtainable by Babu's and Leva's formulas.
    (2) It was shown that the bed expansion can be approximated to 0.65 as calculated by Babu's formula.
    (3) Kato's formula can be applied, with some modifications, to the calculation of the bubble size in the fluidized bed.
    (4) An empirical formula was established for measuring the height of "jumping" particles, which is necessary in designing the reactor.
    (5) It was also found that the slab-type fluidized bed reactor operates with much less slugging and in a more stable manner than the cylindrical reactor.
  • 武田 邦彦, 山下 博久, 佐々木 光永
    1987 年 29 巻 5 号 p. 436-444
    発行日: 1987/05/30
    公開日: 2009/04/21
    ジャーナル フリー
    A detailed study on the adsorbability of uranium complexes on ion-exchanger, especially on the average charge ν and standard reduction potential strength Δμ0 of adsorbed uranium complexes, has been carried out. The new equations of chemical equilibria have been derived by which ν and Δμ0 can be calculated from experimental results. The distributions of uranium complexes in solutions at high ionic strengths and high temperatures were estimated and the standard reduction potentials calculated with the distributions were compared with ones obtained experimentally. On the basis of the above predictive analysis and observed values of ν and Δμ0, it was revealed that ν increased with increasing Cl-concentration or with an elevation of temperature and that ν had a great effect on Δμ0. The Δμ0 was also found to be varied to a small extent in the range of ν more than 2.5 of absolute value. The combined condition of the value of ν around 2.0 and a rather high temperature was favorable in order to strongly adsorb U (VI) complexes.
  • 竹下 健二, 北本 朝史
    1987 年 29 巻 5 号 p. 445-455
    発行日: 1987/05/30
    公開日: 2010/01/08
    ジャーナル フリー
    The separation rate of carbon isotope by a counter-current column was studied in details by the experimental procedures for DBA-octane system.
    The isotope exchange reaction went through two successive steps, in which the concentration of CO2 dissolved into working solution showed the important roles as an intermediate factor. The first step was the isotope exchange between CO2 gas and CO2 dissolved by physical absorption, and the second step was the isotope exchange between CO2 dissolved by physical absorption and carbamic acid. The overall exchange rate of 13C was evaluated by these two rate coefficients and the variation of concentration of CO2 dissolved. The rate controlling factor changed with the variation of temperature and DBA concentration. The rate was controlled by the first step at temperatures lower than 0°C, however it was controlled by the second step at higher temperatures.
    Two rate coefficients were united to an overall capacity coefficient Kfl, which was newly defined in this paper. This factor would be helpful for the evaluation of separation performances of counter-current column at lower temperatures and/or higher pressures.
feedback
Top