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13 巻, 12 号
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小森 卓二, 田村 修三, 吉田 博之, 郡司 勝文, 田村 公子1971 年 13 巻 12 号 p. 688-693
発行日: 1971/12/30
公開日: 2009/04/21
ジャーナル フリーThe mass spectrometric technique has been applied to the determination of burnup of an irradiated fuel of JRR-1 (20% 235U, uranyl sulfate solution). Three different methods were used, based respectively on uranium isotopic ratio, and on the measurement of stable fission-product neodymium and molybdenum. The isotopic ratios were measured with a surface ionization type mass spectrometer.
The uranium isotopic ratio method consists of the measurement of isotopic change of uranium before and after irradiation. in the neodymium and molybdenum methods, uranium and fission-products neodymium and molybdenum were determined by isotope dilution-mass spectrometry using natural uranium, 150Nd and 96Mo, respectively, as spikes. The burnup was calculated from the ratios of concentration reffered to uranium presented by neodymium and molybdenum. While chemical separation is essential prior to mass spectrometry, quantitative recovery of these three elements are not necessary. The results obtained by three methods are in good agreement, and the neodymium method was found to be best in sensitivity, precision and accuracy.抄録全体を表示PDF形式でダウンロード (387K) -
小林 朋文, 加藤 実穂子, 井上 孝太郎1971 年 13 巻 12 号 p. 694-703
発行日: 1971/12/30
公開日: 2010/01/08
ジャーナル フリーThe optimum design point of a fast reactor can be obtained only through a theoretical optimization process, because the complexity of the reactor and lack of accumulated experience in design and construction makes it difficult to optimize the design by experience or by intuition.
While the nonlinear programming technique would appear suitable for carrying out this optimization process, it is not easy to decide which algorithm should be adopted among the many that could be chosen and which differ largely from each other in characteristics.
This paper compares the various algorithms on the basis of results obtained from numerical experiments. A "Fast Reactor Design Optimization System" has been devised, based on a "Method of Approximated Programming" selected as the most suitable one.抄録全体を表示PDF形式でダウンロード (587K) -
江連 秀夫1971 年 13 巻 12 号 p. 704-718
発行日: 1971/12/30
公開日: 2009/04/21
ジャーナル フリーPower-up tests of Japan Power Demonstration Reactor with recirculation flow (JPDR-I) were carried out in Oct. 1963. It was operated at the enhanced level up to 4, 437 MWD/T and shut down in Sept. 1969. Many tests were carried during this operation. The resulting data are very useful for the understanding of the operational characteristics and verifying the 3-dimensional boiling water reactor model. For example, it was found that the position of control rods which had been logged the operation each hour reflected the history of burnup, and that also the temperature which the temperature coefficient had been zero increased with burnup. The reactor physical characteristics of JPDR-I differed between high and low power operations and these characteristics, together with the outline of reactor physical and hydrodynamic characteristics are outlined. As part of the studies on the measurements and analysis of burnup, a series of destructive and undestructive tests was carried out. The absolute γ-intensity of 137Cs and isotopes ratios of U and Pu were also measured.抄録全体を表示PDF形式でダウンロード (5127K) -
穴原 良司, 三島 良績, 青地 哲男, 今井 美材, 下川 純一, 望月 恵一, 中田 清兵衛, 野沢 俊弥, 堀 純郎, 安 成弘, 恒 ...1971 年 13 巻 12 号 p. 719-730
発行日: 1971/12/30
公開日: 2009/04/21
ジャーナル フリーPDF形式でダウンロード (1035K) -
山中 千代衛1971 年 13 巻 12 号 p. 731-732
発行日: 1971/12/30
公開日: 2009/04/21
ジャーナル フリーPDF形式でダウンロード (863K)
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