巻号一覧
後続誌
24 巻, 3 号
選択された号の論文の7件中1～7を表示しています
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現状と問題点中沢 正治, 関口 晃1982 年 24 巻 3 号 p. 166-174
発行日: 1982/03/30
公開日: 2010/01/08
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島田 将之1982 年 24 巻 3 号 p. 175-181
発行日: 1982/03/30
公開日: 2010/01/08
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環境シミュレーション試験和達 嘉樹, 山本 忠利, 武部 慎一, 大貫 敏彦, 鷲尾 方一, 原田 芳金, 斎藤 和明1982 年 24 巻 3 号 p. 182-187
発行日: 1982/03/30
公開日: 2009/04/21
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弘田 実弥, 篠原 慶邦, 斎藤 慶一, 黒田 義輝, 福西 宏有, 西原 英晃, 藤田 祐志, 角田 十三男, 田村 誠司, 須田 信英1982 年 24 巻 3 号 p. 188-198
発行日: 1982/03/30
公開日: 2009/04/21
ジャーナル フリーRecent progress in safety-related applications of reactor noise analysis is reviewed, mainly referring to various papers presented at the Third Specialists' Meeting on Reactor Noise (SMORN-III) held in Tokyo in 1981. Advances in application of autoregressive model, coherence analysis and pattern recognition technique are significant since SMORN-II in 1977. Development of reactor diagnosis systems based on noise analysis is in progress. Practical experiences in the safety-related applications to power plants are being accumulated. Advances in quantitative monitoring of vibration of internal structures in PWR and diagnosis of core stability and control system characteristics in BWR are notable. Acoustic methods are also improved to detect sodium boiling in LMFBR. The Reactor Noise Analysis Benchmark Test performed by Japan in connection with SMORN-III is successful so that it is possible to proceed to the second stage of the benchmark test.抄録全体を表示PDF形式でダウンロード (1005K) -
森 竜二1982 年 24 巻 3 号 p. 199-205
発行日: 1982/03/30
公開日: 2009/04/21
ジャーナル フリーSince the Japan Atomic Energy Research Institute and Nippon Nuclear Fuel Development Co. hot laboratories are located far off from the port which can handle spent fuel shipping casks, it is necessary to use a trailer-mounted cask which can be transported by public roads, bridges and intersections for the transportation of spent fuel specimens to these hot laboratories.
Model NH-25 shipping cask was designed, manufactured and qualification tested to meet Japanese regulations and was officially registered as a BM type cask. The NH-25 cask accomodates two BWR fuel assemblies, one PWR assembly or one ATR fuel assembly using interchangeable inner containers. The cask weight is 29.2t. The cask has three concentric stainless steel shells. Gamma shielding is lead cast between the inner shell and the intermediate shell. Neutron shielding consists of ethylene-glycol-aqueous solution layer formed between the intermediate shell and the outer shell.
The NH-25 cask now has been in operation for 2.5 yr. It was used for the transportation of spent fuel assemblies from six LWR power plants to the port on shipping cask carrier "Hinouramaru" on the sea, as well as from the port to the hot laboratory on a trailer. The capability of safe handling and transporting of spent fuel assemblies has been well demonstrated.抄録全体を表示PDF形式でダウンロード (604K) -
山崎 莞じ, 土井 敏詳, 泉 正行, 長岡 幸夫, 岸 勝一, 加藤 監治, 木口 高志, 小林 節雄, 水野 雄弘1982 年 24 巻 3 号 p. 217-227
発行日: 1982/03/30
公開日: 2010/01/08
ジャーナル フリーAnomalous condition monitoring apparatus for BWR plants is developed, by which the operators can grasp easily and correctly the plant operating conditions.
The anomalous condition monitoring apparatus consists of the plant diagnosis system, the summary status display and the system status monitor. The plant diagnosis system detects performance changes of the plant subsystems such as pressure control system. The summary status display is designed for grasping the whole plant situation at a glance. The system status monitor enables the operators to monitor intensively the operating condition of many components.
The performances of the summary status display and the system status monitor are tested by using signals, which are generated by superimposing the output signals of a dynamic simulator on the process data at normal operation recorded at a commercial BWR plant. The results of the performance tests show that they give correctly monitoring information according to the plant operating conditions. The performance of the plant diagnosis has been already confirmed in the commercial BWR plant.
The anomalous condition monitoring technique developed here, is to be useful implement not only for nuclear power plants, but also for fossil power plants and other industrial plants.抄録全体を表示PDF形式でダウンロード (4297K) -
三村 均, 菅野 卓治1982 年 24 巻 3 号 p. 228-236
発行日: 1982/03/30
公開日: 2010/01/08
ジャーナル フリーThe recrystallization of Cs and Sr form of synthetic mordenites (CsSM and SrSM) at high temperature has been studied by means of X-ray powder diffraction, thermal analysis and density measurement. Synthetic mordenite (Cs loading≥70%) calcined at 1, 200°C recrystallized to cesium aluminosilicate (CsAlSi5O12) and it crystallized rapidly at higher temperature. The density of calcined CsSM considerably increased above 1, 200°C, corresponding to the variation in X-ray diffraction patterns. SrSM recrystallized to SrAl2Si2O8 (Tric.) and SiO2 (β-cristobalite and α-quartz) above 1, 100°C, then its maximum density was observed at 1, 100°C.
The leachability of Cs from calcined CsSM decreased with an increase in calcining temperature. The amount of Cs leached into the water (pH 3-6, 25-100°C) from the CsSM calcined above 1, 200°C was below the detection limit of atomic absorption analysis; hence the leaching rate proposed by IAEA was evaluated to be less than 10-9 g/cmcm2·d. A decrease in the Cs loading yielded a decrease in the leachability of Cs. The leachability of Sr decreased with an increase in calcining temperature, and the leaching of Sr from the SrSM calcined above 1, 100°C into the water of pH 4-6 was below the detection limit.抄録全体を表示PDF形式でダウンロード (668K)
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