巻号一覧
後続誌
34 巻, 8 号
選択された号の論文の6件中1～6を表示しています
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川瀬 洋一1992 年 34 巻 8 号 p. 720-726
発行日: 1992/08/30
公開日: 2010/04/19
ジャーナル フリーPDF形式でダウンロード (3131K) -
青木 芳朗1992 年 34 巻 8 号 p. 727-732
発行日: 1992/08/30
公開日: 2010/04/19
ジャーナル フリーPDF形式でダウンロード (475K) -
森島 信弘1992 年 34 巻 8 号 p. 739-745
発行日: 1992/08/30
公開日: 2010/04/19
ジャーナル フリーA series of NEACRP benchmark tests on reactor noise analysis is reviewed, mainly referring to summary reports presented at the Benchmark Meetings in Tokyo in 1981, Dijon in 1984, Munich in 1987 and Delft in 1990. Progress in methods of reactor noise analysis is notable, especially for computation of noise descriptors, estimation of physical parameters on BWR, PWR and FBR, anomaly detection and system identification. The present review summarizes the results of the tests and recent advance in multivariate autoregressive modeling.抄録全体を表示PDF形式でダウンロード (2561K) -
白山 新平, 関 英治, 田井 一郎, 遠藤 順政, 伊東 敏明, 佐藤 増雄1992 年 34 巻 8 号 p. 754-762
発行日: 1992/08/30
公開日: 2010/04/19
ジャーナル フリーAn electrical circuit which separate the signal current using input filters has been developed for a wide range neutron flux monitoring system.
In general, a wide range neutron flux monitoring system is for measuring signals from a single neutron detector using a pulse counting method and a Campbell method simultaneously. Therefore, it is difficult to design a suitable signal processing circuit for both measurements. <Br>The developed system employs two filters different in their characteristics and placed in parallel at the input stage of the preamplifiers. The filters separate the detector signals into two frequency ranges which are then amplified. It becomes possible by processing the signals into a pulse system and a Campbell system with the individual amplifiers in this way to enlarge the impedance of the first stage amplifier in the Campbell system without being influenced by the pulse counting unit which requires a low input impedance. Thus, the signal-to-noise characteristic can be improved, and a more accurate measurement can be obtained.
As a result, the system including a neutron detector has been developed and tested in an experimental reactor. The obtained overlap between the pulse system and the Campbell system was 2.3 decades, on the basis of a 0.8% maximum measurement error.抄録全体を表示PDF形式でダウンロード (376K) -
清水 俊一, 桜井 昭次, 高岡 和, 兼本 茂, 福富 茂樹1992 年 34 巻 8 号 p. 763-775
発行日: 1992/08/30
公開日: 2010/04/19
ジャーナル フリーInspection and maintenance planning in nuclear power plants is conducted by decision making based on experts' collective consensus. However, since a great deal of time and effort is required to reach a consensus among expert judgments, the establishment of effective decision making methods is necessary. Therefore, the authors developed a method for supporting collective decision making, based on a combination of three types of decision making methods; the Characteristic Diagram method, Interpretive Structural Modeling method, and the Analytic Hierarchy Process method. The proposed method enables us to determine the evaluation criteria systematically for collective decision making, and also allows extracting collective decisions using simplified questionaires. The proposed method can support reaching a consensus of groups effectively through the evaluation of collective decision structural models and their characteristics.
In this paper, the effectiveness of the proposed method was demonstrated through its application to the decision making problem concerning whether or not the improved ultrasonic testing equipment should be adopted at nuclear power plants.抄録全体を表示PDF形式でダウンロード (2757K) -
新谷 文將, 岩村 公道, 大久保 努, 秋本 肇, 村尾 良夫1992 年 34 巻 8 号 p. 776-786
発行日: 1992/08/30
公開日: 2010/04/19
ジャーナル フリーA conceptual design of a double-flat-core type high conversion pressurized water reactor (HCPWR) has been developed at the Japan Atomic Energy Research Institute to improve fuel utilization. In thermal-hydraulic feasibility studies of the proposed concept, major six events such as large and small break LOCAs have been analyzed with the best estimate code REFLA/TRAC. This paper describes the results of control rod ejection accident analyses as a part of the series of analyses. The calculations were performed according to the licensing analysis on current PWRs. The calculated results showed that the proposed concept had larger safety margines than current PWRs. Therefore, the proposed concept is considered to be feasible from a view point of safety analysis of control rod cruster ejection accident. It is seen that the large safety margine of the proposed concept is originated from smaller excess reactivity, smaller maximum linear heat generation rate and smaller rod worth per a control rod than those of current PWRs.抄録全体を表示PDF形式でダウンロード (4418K)
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