日本原子力学会誌
Online ISSN : 2186-5256
Print ISSN : 0004-7120
ISSN-L : 0004-7120
38 巻, 10 号
選択された号の論文の4件中1~4を表示しています
  • 下村 寛昭
    1996 年 38 巻 10 号 p. 803-813
    発行日: 1996/10/30
    公開日: 2010/01/08
    ジャーナル フリー
    The present paper points out the difference of the helium closed cycle gas turbine, which is a candidate of nuclear gas turbine, from the open cycle gas turbine and indicates its inherent problems on pressure ratio and specific speed owing to the use of helium as the working gas.
    The paper also clarifies the effects of external pressure losses on the thermal efficiency and output of the gas turbine besides, it indicates that the major reason of the German unsuccessful helium turbine owes to deterioration of the external efficiencies of compressor and turbine resulted from pressure losses and the use of helium itself.
    Besides above, the paper indicates the key idea on heat exchangers for the closed cycle gas turbine and design basis to solve the problems and finally offers new conception with nitrogen or air as the working gas that is changeable into open cycle gas turbine.
  • 木村 元比古, 石川 正朗, 岡野 秀晴, 尾崎 脩
    1996 年 38 巻 10 号 p. 826-833
    発行日: 1996/10/30
    公開日: 2010/01/08
    ジャーナル フリー
    Remote Operated Vehicle (ROV) is currently applied for visual inspection inside the reactor pressure vessel (RPV). To inspect wide area of the RPV and structures, compactness is required for the inspection vehicle as well as good driverability.
    This report describes the development of visual inspection submersible which was manufactured based on the gap between structures inside RPV and applied with the support system. It was proved to be very efficient measure to make the inspection period short. Also, radiation tolerant camera and manipulator for the vehicle has been developed.
  • 羽田 一彦, 柴田 大受, 西原 哲夫, 塩沢 周策
    1996 年 38 巻 10 号 p. 834-844
    発行日: 1996/10/30
    公開日: 2010/01/08
    ジャーナル フリー
    An HTGR-hydrogen production system should be designed to have stable controllability because of a large difference in thermal dynamics between reactor and hydrogen production system and such a control design concept should be universally applicable to a variety of hydrogen production processes by the use of nuclear heat from HTGR.
    A transient response analysis of an HTGR-steam reforming hydrogen production system showed that a steam generator installed in a helium circuit for cooling the nuclear reactor provides stable controllability of the total system, resulting in avoiding a reactor scram. A survey of control design-related characteristics among several hydrogen production processes revealed the similarity of endothermic chemical reactions by the use of high temperature heat and that steam is required as a reactant of the endothermic reaction or for preheating a reactant.
    Based on these findings, a system design concept with stable controllability and universal applicability was proposed to install a steam generator as a downstream cooler of an endothermic reactor in the helium circuit of an HTGR-hydrogen production system.
  • 加治 芳行, 井岡 郁夫, 深谷 清
    1996 年 38 巻 10 号 p. 845-854
    発行日: 1996/10/30
    公開日: 2009/04/21
    ジャーナル フリー
    An intermediate heat exchanger (IHX) for the High Temperature Engineering Test Reactor (HTTR) is an important component of the cooling system and it is important to confirm the structural integrity. Particularly, a connecting tube would be subjected to thermal stress caused by the difference of thermal expansion and temperature between the manifold and the helical tube and is under severe design condition which is used in over 900°C in normal operation.
    The structural integrity test of an in-scale model consisted of the manifold and the lower connecting tube of the IHX for the HTTR was carried out under accelerated condition of the normal operation.
    From the present study, the crack was observed to have grown through the wall of the tube in two heat transfer tubes. The coil portion and the lower elbow portion of the heat transfer tube slightly hung down and the lower connecting tube was inclined. Prediction of fracture life by using the elastic-creep analysis which used Garofalo type of the creep constitutive equation and the time fraction rule was very conservative as compared with the experimental fracture life.
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