巻号一覧
後続誌
27 巻, 1 号
選択された号の論文の9件中1～9を表示しています
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中島 秀紀1985 年 27 巻 1 号 p. 2-8
発行日: 1985/01/30
公開日: 2010/01/08
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中嶋 秀夫, 島本 進1985 年 27 巻 1 号 p. 9-14
発行日: 1985/01/30
公開日: 2010/01/08
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舘野 淳1985 年 27 巻 1 号 p. 15-20
発行日: 1985/01/30
公開日: 2009/04/21
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秋元 正幸, 田辺 文也, 鴻坂 厚夫1985 年 27 巻 1 号 p. 21-29
発行日: 1985/01/30
公開日: 2009/04/21
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金子 義彦, 秋濃 藤義1985 年 27 巻 1 号 p. 30-38
発行日: 1985/01/30
公開日: 2010/03/08
ジャーナル フリーReactor ghysics research activities in Japan related to Very High Temperature Reactor (VHTR) for multipurpose usage are briefly summarized. Neutronic core design accuracy required for the experimental VHTR is made clear at first, and description is given on the nuclear data compilation and the neutronic calculation code development. For experimental works, after a review on the results of the reactor physics experiments ever done an SHE (Semi-Homogeneous Experiment) at Japan Atomic Energy Research Institute, reconstruction program of the critical assembly is presented aiming at performing a detailed mock-up experiment of the experimental VHTR loaded with low enriched uranium coated particle fuels. At last, improvement of the neutronic calculational accuracy attained through comparison between calculation and experiment is illustrated and some future problems are point out.抄録全体を表示PDF形式でダウンロード (681K) -
大輝 茂, 松本 光雄, 白山 新平, 田井 一郎1985 年 27 巻 1 号 p. 39-48
発行日: 1985/01/30
公開日: 2010/01/08
ジャーナル フリーIn the Prototype Heavy Water Reactor "Fugen", Zircaloy-2 is used as in-core structural material for neutron economy. In-core neutron detectors for the Local Power Monitor are placed in heavy water moderator of 50°C. Such "Fugen" in-core conditions bring a high level thermal neutron flux environment, which burns away the neutron conversion material (235U) in the detector more rapidly compared to that of the light water reactors. Therefore, it was strongly required to realize a neutron detector which could work for a long time under such environment.
To resolve this unexperienced subject, the authors started to develop an advanced in-core neutron detector for "Fugen" by adopting various technologies, The developed neutron detectors have smart structures and excellent characteristics such as (1) light weight structure to avoid gas displacement due to γ-heating, (2) structure of assembling detectors in a Zircaloy-2 tube, (3) wide range and linear current measuring performance and (4) long life performance by the use of mixed uranium (235U+234U). This kind of in-core neutron detector is now in the reactor core of "Fugen" nuclear power plant and is contributing to the high-efficient reactor operation.抄録全体を表示PDF形式でダウンロード (657K) -
小林 健介, 堀井 英雄, 石神 努, 千葉 猛美1985 年 27 巻 1 号 p. 56-65
発行日: 1985/01/30
公開日: 2009/04/21
ジャーナル フリーA sensitivity analysis of thermal hydraulic response in containment during a 'station blackout' (the loss of all AC power) accident at Browns Ferry unit one plant was performed with the computer code MARCH 1.0. In the analysis, the plant station batteries were assumed to be available for 4h after the initiation of the accident. The thermal hydraulic response in the containment was calculated by varying several input data for MARCH 1.0 independently and the deviation among calculated results were investigated.
The sensitivity analysis showed that (a) the containment would fail due to the overtemperature without any operator actions for plant recovery, which would be strongly dependent on the model of the debris-concrete interaction and the input parameters for specifying the containment failure modes in MARCH 1.0, (b) a core melting temperature and an amount of water left in a primary system at the end of the meltdown were identified as important parameters which influenced the time of the containment failure, and (c) experimental works regarding the parameters mentioned above could be recommended.抄録全体を表示PDF形式でダウンロード (797K) -
菊地 賢司, 根本 政明, 蕪木 英雄, 佐野川 好母, 川口 勝之, 小野 重治1985 年 27 巻 1 号 p. 66-77
発行日: 1985/01/30
公開日: 2009/04/21
ジャーナル フリーRelative sliding or bumping of structural elements during the operation of a very high-temperature gas-cooled reactor (VHTR), which has been developed by the Japan Atomic Energy Research Institute, are to be caused supposedly by thermal expansion, flow-induced vibration, seismic forces etc. Appropriate measures, therefore, must be taken in order to prevent abnormal wear, seizing or failure of these structural elements.
The friction and wear characteristics of Ni-based heat-resisting alloy (Hastelloy X-R), which is now thought to be one of the promising candidate materials for VHTR structures, and several ceramic materials by which the surfaces of Hastelloy X-R are to be coated, were studied in 1, 000°C and 0.2-4.1MPa He gas environment.
The followings are the conclusions derived from the present experiment:
(1) The friction coefficient of Hastelloy X-R against itself decreased with increasing O2 gas partial pressure within 3kPa in the He gas environment.
(2) The mutual transfer of material elements occurred when the material combination was Hastelloy X-R against ZrO2 coating.
(3) The friction and wear characteristics of ZrO2 and TiC coatings against themselves were stable.抄録全体を表示PDF形式でダウンロード (8326K) -
加藤 隆夫, 下 道国, 池辺 幸正1985 年 27 巻 1 号 p. 78-85
発行日: 1985/01/30
公開日: 2009/04/21
ジャーナル フリーMeasurements of concentrations of radon and its short-lived decay products were carried out in two vessels in which radon gases were contained, a tunnel and two rooms. The volume/surface ratio of the vessel and/or room ranged from 0.1 to 4.0m. The results of measurements gave the rate constant for wall deposition and the deposition velocity of unattached RaA atoms to be 10-1, 000h-1 and 0.5-2.5cm·s-1, respectively. The apparent diffusion coefficient of unattached RaA atoms was also estimated to be 10cmcm2·s-1. It was clarified that the rate constant for wall deposition and deposition velocity increased with the rate of room ventilation.抄録全体を表示PDF形式でダウンロード (543K)
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