巻号一覧
後続誌
15 巻, 5 号
選択された号の論文の7件中1～7を表示しています
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Nuclex '72に参加して柴田 二三男1973 年 15 巻 5 号 p. 285-294
発行日: 1973/05/30
公開日: 2010/04/19
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欧米の現状を中心に近藤 達男1973 年 15 巻 5 号 p. 295-304
発行日: 1973/05/30
公開日: 2010/04/19
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中野 忠典, 八木 英司1973 年 15 巻 5 号 p. 305-311
発行日: 1973/05/30
公開日: 2010/04/19
ジャーナル フリーA He gas test loop was constructed, to contribute to the development of the HTR.
The loop was successfully operated for 110 hr at a flow rate of 3.3g/sec under 1, 000°C temperature and 40kg/cmcm2·g pressure. This loop is composed of a circulator, regenerative exchanger, electric heater, cooler, pressure tank and piping.
The circulator is of diaphragm type, while the double tube arrangement is adopted for the regenerative exchanger, piping exposed to high temperature, and the cooler.
The He temperature is raised by passing through Ta tube elements heated electrically. Operation of the loop enabled as to fulfil most of the initial objectives. But the endurance and aging deterioration of the heater elements have yet to be confirmed. We have also left aside for future solution the problem of effectively contr olling the purity of the He gas.抄録全体を表示PDF形式でダウンロード (383K) -
兵藤 知典, 竹内 清, 中田 正也, 宮坂 駿一, 金森 善彦, 東原 義治, 梅田 巌, 木村 逸郎, 山越 寿夫, 高橋 善昭, 古田 ...1973 年 15 巻 5 号 p. 312-321
発行日: 1973/05/30
公開日: 2010/04/19
ジャーナル フリーThis is a report on the activities of the Research Committee on Neutron Shielding (Apr. 1970-Mar. 1973), Atomic Energy Society of Japan. The Committee studied the present status and problems in Japan and the trends in foreign countries in such fields as neutron reactor shielding, including transport calculations, duct streaming, spectroscopy, shielding optimization and cross sections for shielding calculations. Three working groups established in the Committee-Neutron Transport, Duct Streaming and Cross Section for Shielding-undertook such activities as (a) calculations of the five benchmark problems for testing computational methods in neutron transport, (b) a survey of theoretical and experimental approaches to duct streaming, and (c) intercomparison of nuclear data for particular nuclides related to shielding in data libraries such as ENDF/B-I, III, KFK-120 and -750.抄録全体を表示PDF形式でダウンロード (753K) -
安藤 良夫, D.G.H. LATZKO, 藤村 理人, 宮園 昭八郎1973 年 15 巻 5 号 p. 322-327
発行日: 1973/05/30
公開日: 2010/04/19
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青木 英人1973 年 15 巻 5 号 p. 332-337
発行日: 1973/05/30
公開日: 2010/04/19
ジャーナル フリーThis report deals with the transient analysis of a fast reactor power generating station with once-through type steam generator, and with the design of the plant control system. The feature of the analytical model is a one-dimensional distributed parameter model of the steam generator. The validity of the model is examined by a calculation of the pump failure transient of the secondary sodium flow. This is followed by a study of three kinds of partial load operation characteristics. The possibility of feed-forward control has been considered, for the purpose of obtaining better plant response to changes in load demand. The plant control system has been designed with account taken of the results of the above preliminary studies, and the plant responses have been calculated for changes of plant power setting.抄録全体を表示PDF形式でダウンロード (320K) -
炉雑音解析法に基づく装荷燃料燃焼度の推定法斎藤 慶一1973 年 15 巻 5 号 p. 338-347
発行日: 1973/05/30
公開日: 2010/04/19
ジャーナル フリーHigh power operation of nuclear reactors depletes the nuclear fuel and accumulates fission products (F.P.'s) in the fuel. Almost all the F.P.'s are unstable and emit γ and/or β in the course of their transmutation. Their total energy varies depending on the fuel depletion and on the time elapsed after the production of the F.P.'s. When the power reactors are shut down, the decay heat plays the role of heat source, the emmision rate of which do not have, however, a deterministic but has rather a stochastic nature.
The fluctuating heat source gives rise to fluctuations in the temperature of the core material. When the dirty core is restarted and operated at relatively low power level, the fluctuations in neutrons, and in the high-energy photons emitted upon nuclear fission, as well as the temperature noise are caused primarily by the fluctuations in the decay heat. There is a possibility of obtaining some information on the magnitude of the decay heat through noise analysis of the high-energy photons or of the temperature. The present paper examines theoretically the stochastic nature of the decay heat and its relation to the fluctuations in temperature, neutrons and prompt gammas. It should be of interest to perform experiments with use made of the present new method of deter- mining the decay heat and/or the in-core fuel depletion.抄録全体を表示PDF形式でダウンロード (637K)
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