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37 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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三枝 利有, 伊藤 千浩, 長野 浩司, 福田 佐登志, 山地 憲治1995 年 37 巻 8 号 p. 675-680
発行日: 1995/08/30
公開日: 2010/01/08
ジャーナル フリーわが国では,使用済燃料はエネルギー資源の備蓄として,再処理されるまでの間,適切に貯蔵・管理される。欧米では,直接処分または再処理までの間の貯蔵技術として,金属・コンクリートキャスク貯蔵,ボールト貯蔵横型サイロ貯蔵,等が開発されている。わが国では,金属キャスク貯蔵の許認可が得られている。今後は,使用済みの高燃焼度燃料やMOX燃料も貯蔵の対象となり,貯蔵コスト低減のための研究等が行われている。抄録全体を表示PDF形式でダウンロード (10417K) -
関本 博, 小原 徹, 大谷 暢夫1995 年 37 巻 8 号 p. 681-688
発行日: 1995/08/30
公開日: 2009/04/21
ジャーナル フリーThis report is presented on a reactor laboratory course for graduate students using large facilities in national laboratories in Japan. A reactor laboratory course is offered every summer since 1990 for all graduate students in the Nuclear Engineering Course in Tokyo Institute of Technology (TIT), where the students can choose one of the experiments prepared at Japan Atomic Energy Research Institute (JAERI), Power Reactor and Nuclear Fuel Development Corporation (PNC) and Research Reactor Institute, Kyoto University (KUR). Both JAERI and PNC belong to Science and Technology Agency (STA). This is the first university curriculum of nuclear engineering using the facilities owned by the STA laboratories. This type of collaboration is promoted in the new Long-Term Program for Research, Development and Utilization of Nuclear Energy adopted by Atomic Energy Commission. Most students taking this course reported that they could learn so much about reactor physics and engineering in this course and the experiment done in large laboratory was a Very good experience for them.抄録全体を表示PDF形式でダウンロード (2950K) -
柳瀬 信之, 関根 敬一1995 年 37 巻 8 号 p. 704-709
発行日: 1995/08/30
公開日: 2009/04/21
ジャーナル フリーApplicability of a Ge detector was studied for in situ measurements of γ-ray emitting radionuclides in water. A Ge detector was lowered into a large tank filled with the air, tap water, seawater, and seawater spiked with 137Cs and 60Co isotopes by turns to measure the γrays. The detection efficiency of the Ge detector in seawater was 0.030, 0.024 and 0.012cps/(photon/s·l) for the 662keV (137Cs), 1, 332keV (60Co) and 1, 462keV (40K) γ rays, respectively. The detection limits were 0.28 and 0.22Bq/l for 137Cs, 60Co in seawater, and 11Bq/l for 40K in tap water, respectively. It could be concluded that the Ge detector could be used not only for monitoring systems around nuclear facilities but also as an accidental release of radionucideS from nuclear power plant such as the Chernobyl one.抄録全体を表示PDF形式でダウンロード (6408K) -
井上 晃, 黒須 立雄, 青木 利昌, 二口 政信, 八木 誠, 師岡 慎一, 星出 明彦, 石塚 隆雄, 吉村 邦広, 吉田 博之, 光武 ...1995 年 37 巻 8 号 p. 710-720
発行日: 1995/08/30
公開日: 2010/03/08
ジャーナル フリーSteam void fraction measurement test in a BWR fuel assembly has been carried out to prove the current BWR void prediction method. This report describes the experimental apparatus, experimental data, and evaluation results.
The test was carried out in an out-of-pile test facility that can simulate the high pressure and high temperature conditions of BWRs. Water was used as a coolant. The void distribution in a BWR fuel assembly under BWR operating conditions was measured for the first time by an X-ray CT scanner, using an electrically heated test assembly which simulated a BWR fuel assembly on a full scale. Void fraction under steady and unsteady conditions was measured by an X-ray CT scanner and an X-ray densitometer.
In steady state void test, 476 data were obtained. These data were compared with the current BWR void prediction method. Unsteady void test data were evaluated with the unsteady analytical code.
It has been proved from these evaluation results that the verification of the current BWR void prediction method and unsteady analytical code has been accomplished.抄録全体を表示PDF形式でダウンロード (9510K) -
谷内 廣明1995 年 37 巻 8 号 p. 721-728
発行日: 1995/08/30
公開日: 2009/04/21
ジャーナル フリーA technique for Monte Carlo codes to obtain surface dose rate profiles of cask surfaces within a reasonable CPU time is presented in this paper. This technique does not use a huge number of actual small detectors defined by additional geometry input data, but uses imaginary detectors. To demonstrate this technique, SAS4 in the SCALE code system is chosen. The estimator is a surface crossing estimator (SXE).
The technique is very simple and easy. In the Monte Carlo calculation, the contribution to the dose by a particle across the surface estimator is stored separately according to the coordinate of the surface crossing point of the particle as if there were a series of small surface estimators. After the Monte Carlo calculation has been done, the post processing procedure is made to produce dose rate profiles at the cask surface using the data from a series of small surface estimators. The additional CPU time required for introducing the new technique to the original CPU time is very small.
The proposed technique using SXE is confirmed to be a very efficient and cost-saving method for getting dose rate profiles around a cask.抄録全体を表示PDF形式でダウンロード (1116K) -
古川 宏, 口村 啓二, 北村 正晴, 鷲尾 隆1995 年 37 巻 8 号 p. 729-739
発行日: 1995/08/30
公開日: 2010/03/08
ジャーナル フリーA general framework for future development of intelligent operator support systems in nuclear plants is proposed in this paper. The central idea in the framework is the decision-making through consensus among multiple agents, each conducting diagnosis on the basis of mutually different, i.e. diverse, principle by focusing dissimilar symptoms obtained from the plant. The applicability and credibility of the operator support system are expected to be significantly improved by implementing the proposed scheme. The effectiveness of diversification in symptom description independently of the effect of reasoning methods was mainly evaluated in this paper. A prototype system was developed for the subtask of fault diagnosis by multiple neural networks emulating the diagnostic agents. The advantage of the proposed framework, together with the related technique of symptom diversification and consensus, was clearly demonstrated through numerical evaluations simulating anomalies in a pressurized water reactor. The obtained results validate, at least to same extent, the present claim of combining multiple and diverse perspectives for reliable decision-making in high-hazard artifacts.抄録全体を表示PDF形式でダウンロード (4842K)
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