巻号一覧
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35 巻, 6 号
選択された号の論文の8件中1～8を表示しています
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福井 謙一1993 年 35 巻 6 号 p. 475-481
発行日: 1993/06/30
公開日: 2010/04/19
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安田 隆芳, 川崎 了, 越後谷 寛法, 木下 豊, 窪田 博行, 小西 隆男, 山中 庸靖1993 年 35 巻 6 号 p. 482-492
発行日: 1993/06/30
公開日: 2010/04/19
ジャーナル フリーThe studies on nodular corrosion formed on the outer surface of BWR fuel cladding tubes were reviewed. Main factors affecting the corrosion behavior were material and environmental conditions and combined effect. The effects of such material conditions as fabrication process, alloy elements, texture and surface treatment and environmental factors as neutron irradiation, thermo-hydrodynamic, water chemistry, purity of the coolant and contact with foreign metals on the corrosion phenomena were surveyed. Out-of-reactor corrosion test methods and models for the corrosion mechanism were also reviewed.
Suppression of the accumulated annealing temperature during tube reduction process improved the nodular corrosion resistance of Zircaloys. Improved resistance for the nodular corrosion was reported for the unirradiated Zircaloys with some additives. Detailed irradiation test under the BWR conditions is needed to confirm the trend. Concerning the environmental factors, boiling on the cladding surface due to heat flux reduces the nodular corrosion susceptibility, while oxidizing radical generated from dissolved oxygen accelerates the corrosion.
Concerning corrosion mechanisms, importance of such phenomena as the depleted zone of alloying elements in zirconium matrix, reduction of H+ to H2 in oxide layer, electrochemical property of precipitates, crystallographic anisotropy of oxidation rates were revealed.抄録全体を表示PDF形式でダウンロード (4538K) -
宇津呂 雄彦, 川端 祐司, 山口 晃, 吉城 肇1993 年 35 巻 6 号 p. 493-500
発行日: 1993/06/30
公開日: 2010/04/19
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竹内 浩, JT-60チーム1993 年 35 巻 6 号 p. 501-509
発行日: 1993/06/30
公開日: 2010/04/19
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梅田 巌1993 年 35 巻 6 号 p. 543-545
発行日: 1993/06/30
公開日: 2010/04/19
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日野 竜太郎, 宮本 喜晟1993 年 35 巻 6 号 p. 546-548
発行日: 1993/06/30
公開日: 2010/04/19
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石神 努, 小林 健介1993 年 35 巻 6 号 p. 549-560
発行日: 1993/06/30
公開日: 2010/04/19
ジャーナル フリーAs a part of the preparation of the database of calculated results on severe accident sequences for emergency preparedness at nuclear power plants, steam generator tube rupture initiated severe accident sequences at a reference two-loop PWR plant have been analyzed using the THALES/ART computer code. Estimation were made of the times of key events such as core uncovery, core melt and reactor vessel melt-through, and an amount of fission products released to the environment. The effects of recovery action on core integrity and the amount of environmental fission products released were studied with regard to the discussion on mitigation of or recovery from the accident by the feed and/or bleed operation in the primary and/or the secondary system. The analysis showed that (1) the ECCS has adequate capability of maintaining core integrity, and (2) the bleed operation in the primary system is effective to suppress the environmental fission products released even if the ECCS did not function.抄録全体を表示PDF形式でダウンロード (5288K) -
松川 誠, 堀江 知義, 堀池 寛, 二宮 博正, 閨谷 譲, 安東 俊郎, 九嶋 孝憲1993 年 35 巻 6 号 p. 561-573
発行日: 1993/06/30
公開日: 2010/04/19
ジャーナル フリーAn iterative non-linear stress analysis considering the thermal expansion and the dynamic effect of the poloidal field coil support in JT-60U tokamak are described. In the JT -60U design, the large electromagnetic forces and smaller space between the toroidal field coil and the vacuum vessel result in a marginal design of the poloidal field coil support structures with small safety margin. Moreover, the complicated geometry of the structure is not easily modeled into the finite elements in the stress analysis and the non-linear friction force applied from the poloidal field coils is difficult to represent realistically. To accurately analyze the deformation and the stress, an iterative method which can treat the friction force as nonlinear force is proposed and applied to the actual design analysis in JT-60U. The deformation calculated from the iterative method is approximately four times of the result in the case of conservative linear friction force. Simple dynamic analysis about the combination of the poloidal field coil, support and the vacuum vessel was carried out to evaluate the dynamic effect with plasma disruption. The results indicated that the serious dynamic resonance can not be expected.抄録全体を表示PDF形式でダウンロード (13596K)
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