巻号一覧
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39 巻, 11 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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一政 祐輔, 野口 宏, 武田 洋, 齊藤 眞弘, 百島 則幸, 久松 俊一, 一政 満子, 天野 光, 新 麻里子, 横山 須美, 大平 ...1997 年 39 巻 11 号 p. 914-942
発行日: 1997/11/30
公開日: 2009/03/31
ジャーナル フリーPDF形式でダウンロード (29207K) -
班目 春樹, 村尾 良夫, 中島 伸也, 村松 壽晴, 稲田 文夫, 田中 伸和, 中尾 俊次, 宮野 廣, 須藤 亮, 堀 慶一, 上野 ...1997 年 39 巻 11 号 p. 943-956
発行日: 1997/11/30
公開日: 2009/03/31
ジャーナル フリーThermal-hydraulics governs mechanical load and environmental condition of structural materials, thus a quantitative understanding of thermal-hydraulic behavior is of real importance to a correct estimate of many kinds of plant aging processes. The current status of thermal-hydraulics for prediction of plant aging is summarized and subjects for future research are discussed.抄録全体を表示PDF形式でダウンロード (28271K) -
野村 末雄1997 年 39 巻 11 号 p. 962-963
発行日: 1997/11/30
公開日: 2009/03/31
ジャーナル フリーPDF形式でダウンロード (2606K) -
遠隔操作型スモールパンチ試験装置の開発近江 正男, 齋藤 順市, 大岡 紀一, 実川 資朗, 菱沼 章道, 海野 明1997 年 39 巻 11 号 p. 966-974
発行日: 1997/11/30
公開日: 2009/03/31
ジャーナル フリーAn accelerator-driven deuterium-lithium (d-Li) stripping reaction-type neutron source, such as the International Fusion Materials Irradiation Facility (IFMIF) planned by the International Energy Agency is recognized as one of the most promising facility to obtain test environments of high-energy neutrons for fusion reactor materials development. The limitation on the available irradiation volume of the irradiation facility requires the development of the small specimen test techniques (SSTT). Application of SSTT to evaluate the degradation of various components in the light water reactor for the life extension is expected to be also quite beneficial.
A remote-controlled testing machine for the Small Punch (SP) and miniaturized tensile tests was developed at the hot laboratory of the Japan Materials Testing Reactor (JMTR). The machine is designed for testing at temperatures ranging between 93 and 1, 123K to evaluate the temperature dependence of the strength of materials including the embrittlement at low temperatures and the softening at elevated temperatures. The tests are performed in a vacuum or in an inert gas environment.
The machine has been installed in a hot cell and is being used for the round robin test program of the SP test method. The round robin test program is planned to identify the capability of the test method and to establish a standard test procedure. The configuration and the specifications of the test machine are introduced and the results of the SP tests are also shown.抄録全体を表示PDF形式でダウンロード (18622K) -
林 秀行, 一宮 正和, 永沼 正行1997 年 39 巻 11 号 p. 975-985
発行日: 1997/11/30
公開日: 2009/03/31
ジャーナル フリーA conceptual design study on a 1, 300MWe class FBR of loop type using sodium bonded mixed nitride fuel was performed from the viewpoint of the enhancement of passive safety. Spectrum-Adjusted Core concept that shifted neutron spectrum to low energy side by adding zirconium hydride was adopted to enlarge the negative Doppler reactivity feedback for the purpose of passive shutdown at ULOF. Integrity of plant system at transients was also examined under long flow coast down condition. It has been found that the large FBR concept with enhanced passive safety characteristics has sufficient feasibility for commercialization and the increase of the capital cost concerning passive safety is not a burden.抄録全体を表示PDF形式でダウンロード (23248K) -
宮崎 邦夫, 国谷 治郎, 諏訪 正輝, 越石 正人, 白木 智美1997 年 39 巻 11 号 p. 986-991
発行日: 1997/11/30
公開日: 2009/03/31
ジャーナル フリーIn order to reduce radiation exposure in nuclear plants (ABWR), Co free wear resistant alloys for rollers in FMCRD (Fine Motion Control Rod Drive) were investigated. Microstructures of conventional Ni-base alloy (WPM) and Co-base alloy were compared to get hints for improving the wear resistance of Ni-base alloys, and a developing conception, dispersing large size Cr carbides into soft Ni matrix, was obtained. The conception was confirmed to be valid by sintered Ni alloys. And then, cast Ni alloys in which less material defect could be expected than sintered Ni alloys were prepared to examine the wear and impact properties. It was known that 1.92.1C-30Cr-Ni(mass%) cast alloys showed much higher wear resistance than those of WPM and Co-base Alloy in high temperature water of 288°C, and that the absorbed energy in sharpy impact test of the cast Ni alloys was more than two times larger than those of WPM and Co-Alloy 3.抄録全体を表示PDF形式でダウンロード (12415K) -
1997 年 39 巻 11 号 p. 992-993
発行日: 1997/11/30
公開日: 2009/03/31
ジャーナル フリーPDF形式でダウンロード (231K) -
1997 年 39 巻 11 号 p. 993
発行日: 1997年
公開日: 2009/03/31
ジャーナル フリーPDF形式でダウンロード (88K)
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