日本原子力学会誌
Online ISSN : 2186-5256
Print ISSN : 0004-7120
ISSN-L : 0004-7120
10 巻, 9 号
選択された号の論文の6件中1~6を表示しています
  • 前田 秀, 津田 順司, 萩 洋伍
    1968 年 10 巻 9 号 p. 478-487
    発行日: 1968/09/30
    公開日: 2010/04/19
    ジャーナル フリー
    This report presents the results of hybrid computer model studies performed to determine the transient characteristics of a self-pressurized water reactor plant. The plant has a hydrogen overpressure mechanism, with a steam dome on the top of the vessel in lieu of a separate pressurizer. It is the principal objective of the report to analyze the transient conditions inside this steam dome which characterizes the plant.
    For this analysis we have treated non-condensing processes with four gas conditions (adiabatic mixed gas; isoentropic, isoenthalpic and saturated steam), as well as various condensing processes, with particular reference to condensing processes with saturated steam and with limited condensation. The method of computation adopted describes the two processes of compression and expansion under a single unified system.
    The method is applicable to other non-condensing gas overpressure mechanisms, to ordinary self-pressurized reactor plants, and to conventional PWR pressurizer analysis. A hybrid computer (ordinary analog computer connected with the digital computer HITAC 2010) was used for the characteristics computation. Some examples are given of the results obtained.
  • 宮坂 駿一, 金森 善彦, 福島 穰, 山田 毅
    1968 年 10 巻 9 号 p. 488-495
    発行日: 1968/09/30
    公開日: 2010/04/19
    ジャーナル フリー
    In continuation of a series ot mockup tests for the first Japanese nuclear ship, reactor γ-ray leakage through a double-bend two-dimensiond passage in a leqd slab was experimentally studied. This zig-zag slit channel is recognized to be an effective device against γ-ray leakqge at shield seams. Such leakage may occur through straight passages with normally incident γ-rays, or else with oblique incidence, in the form of streaming.
    In the case of zig-zag channel, it should be noted that there exist certain incident angles at which the shielding effect is morkedly impaired. The components of penetration calculated by ray-analysis method have been compared with experimental results. The existence of a slit in a lead slab increases scattered γ-rays, which are localized near the shield surface, but which spread widely with increasing distance from wall.
  • 清瀬 量平
    1968 年 10 巻 9 号 p. 496-501
    発行日: 1968/09/30
    公開日: 2010/04/19
    ジャーナル フリー
    The burnup performance of various power reactor types, including gas-cooled graphite moderated, light-water moderated, heavy-water moderated and fast breeder reactors, are discussed in conjunction with fuel management schemes applicable to these reactor types.
    A review is presented covering the progress made in studies on burnup analysis of power reactors, and need is felt for further studies in domains such as burnup and fuel management codes, mathematical models useful for burnup or fuel cycle optimization, and experimental methods of burnup determination.
  • 萩野谷 徹
    1968 年 10 巻 9 号 p. 502-506
    発行日: 1968/09/30
    公開日: 2010/04/19
    ジャーナル フリー
    The development of safeguards techniques increases importance with the widening practical application of nuclear power generation. This was early recognized in the United States and Great Britain, where active research and development of such techniques have been under way. An ad hoc committee on the subject established in the U.S. AEC submitted their repor in March 1967, and a Symposium on Safeguards Techniques was held at ANL in june 1967. The IAEA sponsored in August 1967, a panel on safeguards techniques.
    The most effective manner of applyhg safeguards measures is to cover the entire fuel cycle, with inspections conducted on the key points of the fuel cycle. The success of such a procedure would depend on improvements in available safeguards technique.
    Developments in this domain must be pursued along two lines-instrumentation and systems. In every case, the strategic point is the reprocessing plant and not the nuclear reactor itself.
  • 日本学術会議原子力特別委員会研究部会
    1968 年 10 巻 9 号 p. 507-510
    発行日: 1968/09/30
    公開日: 2010/04/19
    ジャーナル フリー
  • 近藤 正春, 団野 皓文, 飯塚 義助, 清水 治通
    1968 年 10 巻 9 号 p. 511-521
    発行日: 1968/09/30
    公開日: 2010/04/19
    ジャーナル フリー
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