巻号一覧
後続誌
24 巻, 10 号
選択された号の論文の11件中1～11を表示しています
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松本 元一1982 年 24 巻 10 号 p. 744-748
発行日: 1982/10/30
公開日: 2009/04/21
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宇尾 光治, 飯吉 厚夫1982 年 24 巻 10 号 p. 749-758
発行日: 1982/10/30
公開日: 2010/01/08
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五十嵐 健治, 武村 祥夫1982 年 24 巻 10 号 p. 759-763
発行日: 1982/10/30
公開日: 2009/04/21
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佐藤 健二1982 年 24 巻 10 号 p. 764-769
発行日: 1982/10/30
公開日: 2010/01/08
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遊佐 英夫, 菊池 恂, 堀内 進, 林 勝1982 年 24 巻 10 号 p. 770-774
発行日: 1982/10/30
公開日: 2009/04/21
ジャーナル フリーNew volume reduction systems, which treat most of nuclear power plant radioactive wastes including liquids and sludges, have been developed and they are ready for commercial use. The main feature of the system is that mixed wastes having different chemical and physical characteristics can be treated by one unit. This report describes the outline of the system, mathematical simulation models to estimate the operational characteristics of the key components, on-line computer control system using these models, and packaging technique for the long term storage of the wastes.抄録全体を表示PDF形式でダウンロード (358K) -
1982 年 24 巻 10 号 p. 774
発行日: 1982年
公開日: 2010/01/08
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桜井 勉, 高橋 昭, 藤沢 銀治, 横山 淳1982 年 24 巻 10 号 p. 775-782
発行日: 1982/10/30
公開日: 2010/01/08
ジャーナル フリーThe Kr fixation studies carried out in the world have been reviewed from the viewpoint of the long term storage of 85Kr. (1) The ion implantation-sputtering process (UK, USA and West Germany) is excellent in Kr loading, and the Kr is heat-resistant in the matrix. Increasing the efficiency of implantation is an important problem to be solved. (2) The zeolite encapsulation (USA, West Germnay and Japan) has given favorable results concerning both Kr loading and heatresistance of the fixed Kr. It would be necessary for its practical use to reduce the Kr pressure on encapsulation. (3) The current clathrate process (West Germany) is expensive, because it needs large quantities of Pt. A study is underway in order to replace the Pt with a cheaper metal. (4) The chemical fixation of Kr, proposed by the present authors, makes it possible to encapsulate Kr into zeolites at low temperatures and pressures. The process must be modified to increase Kr loading.
Of these, the zeolite encapsulation is being developed towar s technical scale experiments, while the others are in the stage of laboratory scale experiments.抄録全体を表示PDF形式でダウンロード (653K) -
高橋 酉藏1982 年 24 巻 10 号 p. 783-785
発行日: 1982/10/30
公開日: 2009/04/21
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名取 久秀, 金戸 邦和, 大輝 茂1982 年 24 巻 10 号 p. 792-802
発行日: 1982/10/30
公開日: 2009/04/21
ジャーナル フリーAn on-line core performance evaluation system ATROPOS has been developed in order to carry out safe and efficient reactor operation of "FUGEN" (a heavy water moderated, boiling light water cooled, pressure tube type reactor). This system offers detailed and useful information on such items of core performance as core thermal power, power distribution and thermal operation limits.
The power distribution is calculated first by using a three-dimensional nodal coupling model, employing such process data as control rod position and 10B concentration in the D2O moderator. Then the calculated power distribution is corrected by local power monitor readings.
An axial one-dimensional nodal coupling model, which considers radial power distribution, and a localized three-dimensional nodal coupling model are used to predict the core thermal power and the power distribution for the region surrounding the control rods respectively, within a short time in advance of control rod operation.
The methods employed in this system are verified by comparison with start-up test data from the FUGEN initial core. The estimated power distribution and channel flow agree with values measured by the power calibration monitor and with channel flow converted from measured values of pressure drop, within 3 and 5% respectively, in their root mean square values. The difference in core thermal power between the predicted value and the value measured by the total power monitor is about 1% for control rod operation.抄録全体を表示PDF形式でダウンロード (863K) -
秋山 雅胤, 古田 一雄, 井田 俊雄, 坂田 薫, 安 成弘1982 年 24 巻 10 号 p. 803-816
発行日: 1982/10/30
公開日: 2009/04/21
ジャーナル フリーBeta decay heat released from fission products (FPs) has been measured for fast-neutron fissions of 235U, 239Pu and 233U using the radiation spectrometry method. The sample irradiations were for 10, 60 and 300s (10 and 100s for 233U) in the fast neutron source reactor YAYOI of the University of Tokyo. Spectral data for β-ray were obtained at post-irradiation time intervals ranging 11-26, 000s using a plastic scintillation detector combined with a transmission type proportional counter to eliminate γ-ray effects. The data were processed to the form of β-energy release rates per fission for each set of time-interval parameters. The standard representation of the decay heat following fission pulse (in cooling times ranging 19-24, 000s) was provided from the β-energy release rates. The experimental uncertainties (1σ) of the decay heat data were within 5%.
The present results are compared with three summation calculations using JNDC, TASAKA and ENDF/B-IV FP decay data libraries, and with other experimental resul s. As the results of these comparisons, it appears that the values calculated using JNDC FP decay data library agree very well with the measured values.抄録全体を表示PDF形式でダウンロード (1062K) -
仲戸川 哲人, 益田 福三, 川西 康平, 礒野 正道1982 年 24 巻 10 号 p. 817-825
発行日: 1982/10/30
公開日: 2009/04/21
ジャーナル フリーAn experimental study on impingement steam jet was performed as one of the efforts to establish evaluation methods for effects caused by jet under the postulated pipe rupture accident in the nuclear power plant.
Steam jet ejected from a nozzle into the atmosphere is vertically impinged on the flat ptate. Nozzle reaction, jet impingement force and impingement pressure distribution were measured over a wide range of impingement distance. Employed nozzles are circles and ellipses. The steam conditions are steady-state and dry saturated, and the maximum pressure is 4.5MPa.
From the data of nozzle reaction and impingement force, these are mutually equal and are proportional to the initial stagnant pressure. And from this data, the thrust coefficient for each nozzle were calculated. Based on the data of impingement pressure distribution, the jet is roughly divided iato three regions according to the characteristics of distribution in both cases of circular and elliptical nozzles. In addition, in the case of ircular nozzle, locations where the pattern of distribution changes distinctly depend on the location of Mach disk. In the case of elliptical nozzle, expansion on the minor axis is remarkably greater than on the major axis, particularly near the nozzle exit.抄録全体を表示PDF形式でダウンロード (559K)
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