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37 巻, 10 号
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石榑 顕吉, 服部 高久, 宮川 俊晴, 長尾 博之, 酒井 公雄, 高久 啓, 内田 俊介1995 年 37 巻 10 号 p. 898-906
発行日: 1995/10/30
公開日: 2010/01/08
ジャーナル フリー軽水炉の水化学技術は,冷却水と材料との相互作用を,主として冷却水の視点で取り扱う技術である。これまでの水化学の基礎研究の進歩とその成果の実機への適用の結果,我が国の軽水炉プラントの高信頼性,高稼動率そして低放射線被曝の実績に貢献してきた。しかし,この数年の間に新たな現象が顕在化し,それに対応して新たな技術進歩も見られた。本稿では,日本原子力学会「原子炉水化学」研究専門委員会(1991年4月-1995年3月)で検討してきた成果をまとめたもので,最近の軽水炉プラントにおける水化学管理の実績を示すと共に,特に,放射線照射下の高温水中,高温蒸気中の炉内構造材,燃料被覆材の物性と挙動,モニタリング技術,材料・機器の寿命評価法などに重点をおいて,技術の進歩と将来展望をレビューした。抄録全体を表示PDF形式でダウンロード (2793K) -
篠原 伸夫, 臼田 重和1995 年 37 巻 10 号 p. 907-913
発行日: 1995/10/30
公開日: 2009/04/21
ジャーナル フリー超アクチノイド元素の化学的性質を解明する研究は,合成できる核種が極めて短寿命でかつ微量であるため,迅速分離装置を使った数個程度の原子を対象とする化学であり,超アクチノイド元素に既存の周期律が適用できるか,相対論的効果はあるか,通常の化学と違うのか等々の興味ある分野である。本稿では,オンライン化学分離手法や104番および105番元素の化学的性質を中心に解説する。抄録全体を表示PDF形式でダウンロード (2318K) -
「次世代燃料」研究専門委員会1995 年 37 巻 10 号 p. 914-924
発行日: 1995/10/30
公開日: 2010/01/08
ジャーナル フリーThe Research Committee on Fuel in Next Century was established in the Atomic Energy discuss the development of nuclear fuels focusing on the plutonium utilization and the burn-up extension. The discussions in these meetings are summarized in this report. The outline of core and nuclear fuel designs on both BWR and PWR for the extended burn-up is introduced together with the plans of burn-up extension. Two typical phenomena under irradiation of the LWR fuels at high burn-up are discussed, which are the rim formation and the cladding corrosion. The irradiation behavior of Mixed Oxide (MOX) fuels in LWR is also discussed. Both cladding and fuel pellet have been developed for the burn-up extension, and the current status is shown here. A brief review of physical properties of MOX fuel is also made. The review also includes the fabrication technology of MOX fuel for thermal reactor in countries such as France, Belgium, United Kingdom and Germany.抄録全体を表示PDF形式でダウンロード (5666K) -
吉田 清, 西 正孝, 辻 博史, 佐々木 崇, 保川 幸雄, 塚本 英雄, 田戸 茂, 重中 顕, 住吉 幸博, 長谷川 満1995 年 37 巻 10 号 p. 938-947
発行日: 1995/10/30
公開日: 2009/04/21
ジャーナル フリーThere was a debate over whether a pancake-winding or layer-winding technique is more appropriate for the Central Solenoid (CS) coil for ITER superconducting magnet. The layerwinding CS has the advantage of homogeneous winding supporting the TF centering force without weak joints, but has many difficulties during manufacturing and quality control. On other hand, the pancake-winding has the advantage of better quality control during manufacturing and module testing but has difficulties with joints and feeders, and pipes located in the load path of the bucking force from the toroidal field coils. The compact joints, reinforcement by preformed amour, sharp bending, and double seals are applied to the designof pancake-winding CS coil and demonstrated by hardware developments. The pancake-winding CS coil by using modified existing technology is compatible with the bucking concept of the ITER magnet system.抄録全体を表示PDF形式でダウンロード (17587K) -
武田 哲明, 武仲 五月, 菱田 誠, 江森 恒一1995 年 37 巻 10 号 p. 948-958
発行日: 1995/10/30
公開日: 2009/04/21
ジャーナル フリーA primary pipe rupture accident is one of the design-basis accidents of the High-Temperature Engineering Test Reactor (HTTR), which is now under construction at Japan Atomic Energy Research Institute. When the primary pipe rupture accident occurs, air is expected to enter the reactor core from the breach and oxidize in-core graphite structures. During the accident a complicated multi-component gas flow is expected to occur in the reactor vessel. This report deals with experimental study on air ingress process in the 1st stage of the accident. The experiments are carried out with a test model simulating the HTGR. Temperature of the simulated reactor core is varied from about 400-1, 050°C.抄録全体を表示PDF形式でダウンロード (3244K) -
飯島 隆, 中嶌 良昭, 桜井 直人, 八木 郭之, 丹治 順一1995 年 37 巻 10 号 p. 959-970
発行日: 1995/10/30
公開日: 2009/04/21
ジャーナル フリーAlthough control performance of some fuzzy logic control systems in a nuclear power plant are analytically evaluated, there is no examples of the application to the actual plant. This is mainly because that it requires long time for careful tuning of parameters (membership functions) as compared with the case in conventional control system.
We have studied the application of fuzzy logic controller to the feedwater control system in the FUGEN advanced thermal reactor. In order to reduce the controller tuning time in the actual plant, we limited the operational region for fuzzy logic control and used a weight instead of membership functions as the tuning parameters. A schematic model of the feedwater system in the FUGEN is used for the study of the tuning method. Efficiency of the developed method was demonstrated by numerical simulation as well as by the application to FUGEN.
From the operational data of the actual plant, we confirmed the improvement of controllability by the fuzzy logic control system.抄録全体を表示PDF形式でダウンロード (662K)
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