巻号一覧
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37 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
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岡 芳明, 尾本 彰, 田畑 広明, 水町 渉, 守屋公 三明, 久木 田豊, 鈎孝 幸, 牧原 義明, 玉置 昌義, 村尾 良夫, 星 蔦 ...1995 年 37 巻 9 号 p. 766-795
発行日: 1995/09/30
公開日: 2009/04/21
ジャーナル フリー21世紀に予想される後進国での電力需要の急上昇および各国での労働力不足に対処するため,国内外で省力化と人にわかりやすい技術に基づく次世代軽水炉を開発するプロジェクトが進められている。このような状況を踏まえて,次世代軽水炉の開発そして研究状況,そこに使用されている新しい要素技術についてまとめておくことは,会員に最新の情報を提供するという観点から有意義である。本稿では,次世代BWR, PWRおよび他の軽水炉の開発・研究状況および新要素技術について述べる。抄録全体を表示PDF形式でダウンロード (21546K) -
岡本 眞實, 北島 正弘, 三橋 武文, 小林 慶規, 木内 清, 加納 茂機1995 年 37 巻 9 号 p. 796-806
発行日: 1995/09/30
公開日: 2010/01/08
ジャーナル フリーThe Nuclear Material Research in the Cross-Over Research on underlying technology of nuclear energy has been conducted since 1989 as one of the four branches of the Frontier Research Project of Japan. This report was planned to commemorate the first 5 years of the research and to allow the members of the Atomic Energy Society an opportunity to view the typical results obtained in the first 5 years and the objects of the second phase of the project. The researches have been carried out under the multi-collaboration systems (cross-over) among the 5 national institutions including JAERI and PNC, universities, industries and so on.抄録全体を表示PDF形式でダウンロード (5143K) -
佐藤 一男1995 年 37 巻 9 号 p. 807-810
発行日: 1995/09/30
公開日: 2009/04/21
ジャーナル フリーPDF形式でダウンロード (2578K) -
木下 光夫, 福崎 孝治, 丸山 博見, 佐野 広樹, 深沢 幸久, 松木 勉1995 年 37 巻 9 号 p. 844-853
発行日: 1995/09/30
公開日: 2010/01/08
ジャーナル フリーsystem to automatically generate re-startup plans for BWR plants has been developed. By including consideration of high speed re-startup after reactor shutdown, where xenon By including consideration of high speed re-startup after reactor shutdown, where xenon By including consideration of high speed re-startup after reactor shutdown, where xenon current reactor conditions.
For this purpose, not only BWR core managing expertise in a knowledge base, but also core simulation programs are used. To realize both higher accuracy and shorter computing time of core characteristics predictions by the simulation programs, the error tendency between the simulation results and actual plant data is learned using an artificial neural network. To make the plan for re-startup operation, first, allowable xenon concentrations and corresponding control rod patterns that satisfy thermal constraints at the rated power are estimated. Secondly, based on the estimation results, control rod withdrawal sequence, reactor power, control rod pattern and core flow rate for each time are determined.
A prototype system was developed to evaluate its performance. The system was capable of generating a plan automatically within 30min.抄録全体を表示PDF形式でダウンロード (2309K) -
石塚 隆雄1995 年 37 巻 9 号 p. 854-865
発行日: 1995/09/30
公開日: 2010/01/08
ジャーナル フリーIn the boiling water reactor safety assessment, core cooling is achieved if the core is flooded during loss of coolant accidents. It is important to accurately predict a position of water level during blowdown. The change of water level position is determined by the amount of the difference between the generated steam by depressurizing boiling and the steam flowing out from the water surface. Both the water level and void fraction are necessary to calculate the amout of steam flowing out from the water level correctly. However these data have been scarcely obtaind simultaneously in a same experiment. Both the water level and void fraction data have been obtained with the time process at the same time by the author et al. In this study, these blowdown data were used to calculate vapor velocities during blowdown. A vapor velocity correlation has been obtained by vapor velocity data under various fluid conditions.
This vapor velocity correlation has been used in the LEVELY code to calculate the fluid condition during blowdown. It was confirmed that the water level was accurately predicted by the LEVELY code using this vapor velocity correlation derived in this study.抄録全体を表示PDF形式でダウンロード (652K) -
饒 燕飛, 福田 研二, 金島 竜次, 上廣 勝信1995 年 37 巻 9 号 p. 866-875
発行日: 1995/09/30
公開日: 2009/04/21
ジャーナル フリーLinear stability analysis in the frequency domain is performed to reveal the basic mechanism of coupled nuclear/thermal instabilities in a boiling channel. It is found that the Ledinegg instability will not occur due to the influence of void-reactivity (VR) feedback. Ledinegg instability will not occur due to the influence of void-reactivity (VR) feedback. fuel-time constant τM are found to be the parameters determining the density-wave instability. It is found that the Fr number has a much stronger effect on the stability of the system when It is found that the Fr number has a much stronger effect on the stability of the system when the system. The result reveals that there exists a region in which the VR feedback loop is unstable, which has an obvious impact on the stability of the system. A dimensionless fuel-time-constant number is proposed, with which the stability boundary is better presented.抄録全体を表示PDF形式でダウンロード (531K)
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