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9 巻, 1 号
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飯田 嘉宏, 小林 清志, 熊谷 伸一1967 年 9 巻 1 号 p. 2-7
発行日: 1967/01/30
公開日: 2009/03/31
ジャーナル フリーThe void fraction is one of the most important factors in the study of twophase flow. There are many methods for measuring this value, but few provide accurate results for the local void fraction. In the present paper, an attempt is made to find a method of accurately determining the local void fraction. The detector is composed of a probe and a plate electrode, and detects the difference in electrical conductivity between the liquid and gas phases between two electrodes. The void fraction can be expressed by the ratio between the time during which the probe is occupied by the gas phase and the total measuring time. Actually, the void fraction is found by using a signal generator and an electronic counter. Experiments were made to study the influence of the probe on the flowing bubbles. The measured values by this method agreed well with the values from other methods. Finally, this method was applied to measure the distribution of void fraction along a cross section of a channel, as illustrated in the Figs. 7 and 8.抄録全体を表示PDF形式でダウンロード (5609K) -
天野 文雄1967 年 9 巻 1 号 p. 7-15
発行日: 1967/01/30
公開日: 2009/03/31
ジャーナル フリーThis report describes a theoretical analysis of pulsed neutron experiments on the SHE (Semi-Homogeneous Critical Assembly in the Japan Atomic Energy Research Institute). Analysis of experiments has been performed on the following problems, using the time-dependent, two-group diffusion theory neglecting delayed neutrons.
(1) Comparison between measured and calculated values representing the effectiveness of gray control rods.
(2) Relation between the spatial harmonic contamination and the manner in which the reactor system is made subcritical.
(3) How to decide the relative positions of neutron source and detector to minimize the harmonic effects.
(4) Evaluation of error resulting from higher harmonics with a single-mode fitting method based on the response of a single detector.抄録全体を表示PDF形式でダウンロード (2807K) -
能沢 正雄1967 年 9 巻 1 号 p. 16-24
発行日: 1967/01/30
公開日: 2009/03/31
ジャーナル フリーThis is a brief summary of a design study undertaken in the Japan Atomic Energy Research Institute on a 1, 000 MWe sodium-cooled fast reactor.
The following conditions were adopted as the design targets: Good breeding ratio in the reactor core; small positive reactivity of sodium void in the central channel of the core; 2-zoned power flattening by optimizing the core material composition, reasonable maximum clad temperature for cladding.
PuO2-UO2 mixed oxide was chosen as fuel material. A rotating core concept was considered for refueling. A total breeding ratio of 1.44 was obtained. A doubling time of about 9 years is possible with this design. A rough estimate of power cost gives a value of 1.48 yen/kWh.抄録全体を表示PDF形式でダウンロード (8668K) -
桂木 学, 松岡 謙一, 深井 佑造1967 年 9 巻 1 号 p. 25-34
発行日: 1967/01/30
公開日: 2009/03/31
ジャーナル フリーPDF形式でダウンロード (891K) -
洲崎 輝雄1967 年 9 巻 1 号 p. 35-36
発行日: 1967/01/30
公開日: 2009/03/31
ジャーナル フリーPDF形式でダウンロード (204K)
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