日本原子力学会誌

新しい原子核の探究

中井浩二

1974 年 16 巻 12 号 p. 605-613
発行日: 1974/12/30
公開日: 2009/04/21

DOIhttps://doi.org/10.3327/jaesj.16.605

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有限要素法におけるモデル化と原子力工学

矢川元基

1974 年 16 巻 12 号 p. 614-620
発行日: 1974/12/30
公開日: 2009/04/21

DOIhttps://doi.org/10.3327/jaesj.16.614

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42. 気体状α放射能測定用内部ガス充填型電離箱の壁効果

モンテカルロ計算

舘野徹, 池辺幸正, 下道国

1974 年 16 巻 12 号 p. 626-631
発行日: 1974/12/30
公開日: 2009/04/21

DOIhttps://doi.org/10.3327/jaesj.16.626

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In measuring the ionization current due to gaseous α-radioactive sources with an ionization chamber, we must make correction to compensate the reduction of current due to the wall effect, which is absent when the current is measured with a wall-less ionization chamber.
In this report, we calculate the wall effect by Monte Carlo calculation on two types of ionization chambers-the parallel plate chamber (electrode distance: 0.5-30cm) and the cylindrical chamber (radius: 4, 6, 8, 12cm, length: 10-80cm)-and for several gaseous α-radioactive sources-Rn, Tn, ThA, etc., 4.196-8.785 MeV. The results obtained are presented graphically, and they agree approximately with experiment and with the Monte Carlo calculation undertaken by other workers.

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602. 長期サイクルの物量に及ぼす炉型特性の影響,(II)

高速炉の増殖特性と導入年遅れの影響

古橋晃

1974 年 16 巻 12 号 p. 632-639
発行日: 1974/12/30
公開日: 2009/04/21

DOIhttps://doi.org/10.3327/jaesj.16.632

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Material requirements in the long-term fuel cycle, such as the cumulative demand for natural U and separative work, are analyzed under two different growth-rates anticipated for nuclear generating capacity in Japan. In this second report, the analysis still covers only a simple system consisting of light water reactors and fast breeders, but the breeding characteristics of the fast reactors are changed parametrically, and the timing of the first FBR installation also is varied in the range of 1986-1996 and beyond.
The cumulative demand for natural U prior to attainment of the self-suppporting Pu breeding cycle is empirically represented by a simple function of breeder characteristics. To give an indication of the possible fuel saving with a reduced projection of the nuclear installations, a typical case is analyzed, in which the anticipated capacity of such installations is toned down after the year 2000.
The importance of the time delay in commencing re-use of discharged Pu is discussed. The delay exerts a large influence on the material requirements, if the installation capacity is assumed to grow rapidly. A simple consideration is presented concerning the limitation on the growth-rate of breeder capacity imposed as a result of this time delay.

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