巻号一覧
後続誌
35 巻, 10 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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松岡 伸吾1993 年 35 巻 10 号 p. 864-873
発行日: 1993/10/30
公開日: 2010/04/19
ジャーナル フリーPDF形式でダウンロード (707K) -
その環境科学的意味岩倉 哲男1993 年 35 巻 10 号 p. 874-879
発行日: 1993/10/30
公開日: 2010/04/19
ジャーナル フリーPDF形式でダウンロード (402K) -
藤高 和信1993 年 35 巻 10 号 p. 880-884
発行日: 1993/10/30
公開日: 2010/04/19
ジャーナル フリーPDF形式でダウンロード (4934K) -
福本 貞義1993 年 35 巻 10 号 p. 885-890
発行日: 1993/10/30
公開日: 2010/04/19
ジャーナル フリーPDF形式でダウンロード (2713K) -
「核融合プラズマ材料工学」研究専門委員会1993 年 35 巻 10 号 p. 899-904
発行日: 1993/10/30
公開日: 2010/04/19
ジャーナル フリーThis report describes the activities of Research Committee on Plasma and Fusion Reactor Materials, Atomic Energy Society of Japan, during the period of April, 1989 to March, 1993.
The committee reviewed and discussed on the present status of (1) plasma facing materials, (2) development of structure materials of ITER and DEMO, and (3) low activation materials including ferritic steel, vanadium alloy and other materials.抄録全体を表示PDF形式でダウンロード (438K) -
森谷 渕1993 年 35 巻 10 号 p. 905-915
発行日: 1993/10/30
公開日: 2010/04/19
ジャーナル フリーThe safety of CIS and Eastern Europe Nuclear Power Plants is a serious concern throughout the world. The features of design and operation of the Soviet PWR (VVER) have been recently revealed. This paper is to introduce the technical characteristics, together with the issues and background of safety countermeasures for the operating VVER. The reference data is taken mainly from IAEA technical documents.
The safety of VVER-440/V-230 plants is a major concern, since these plants do not possess enough safeguards against fire, redundancy of ECCS, embrittlement of reactor pressure vessels and plant operational management. Therefore, an urgent response to secure safety features is strongly anticipated, based upon international practice and principles.
In order to establish safety features for CIS and Eastern Europe NPPs, international cooperation has been progressed utilizing multiple frameworks; such as G-7, G-24, ECC, IAEA, OECD and WANO. Among them, IAEA has made considerable contributions by making design reviews of NPPs in those countries after 1990. Japan is also participating on cooperative activities through organization of training programs in Japan for nuclear specialists from those countries and the dispatch of specialists.抄録全体を表示PDF形式でダウンロード (735K) -
柴田 勝之, 磯崎 敏邦, 植田 脩三, 栗原 良一, 鬼沢 邦雄, 鴻坂 厚夫1993 年 35 巻 10 号 p. 923-939
発行日: 1993/10/30
公開日: 2010/04/19
ジャーナル フリーUpon request by the Science and Technology Agency of Japanese Government, the Japan Atomic Energy Research Institute has conducted Piping Reliability Test Program to demonstrate the safety and reliability of light water reactor primary pipings. In this report, the results of the program are summarized. In the test program, pipe fatigue tests, Leak-Before-Break (LBB) verification tests and pipe rupture tests were carried out to examine the integrity of pipings, to verify the LBB concept and to demonstrate the effectiveness of the protective measures against jet impingement and pipe whip under pipe rupture event, respectively. In the pipe fatigue tests, a procedure to predict the fatigue crack growth was developed and the integrity of piping during plant service life was demonstrated. In the LBB verification tests, pipe fracture tests and leak rate tests were performed using cracked pipes. Based on the test results, LBB in the primary pipings was demonstrated. In the pipe rupture tests, the influence of jet impingement on the target plate and the interaction between whipping pipe and restraint were investigated. Using the test results, the effect of jet impingement and the effectiveness of pipe whip restraints were demonstrated.抄録全体を表示PDF形式でダウンロード (14142K)
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