巻号一覧
32 巻 (1994)
- 6 号 p. 288-
- 5 号 p. 240-
- 4 号 p. 184-
- 3 号 p. 130-
- 2 号 p. 66-
- 1 号 p. 4-
前身誌
32 巻, 3 号
選択された号の論文の5件中1～5を表示しています
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金丸 修, 清水 勝, 宮崎 秀子, 八木 晃一1994 年 32 巻 3 号 p. 130-138
発行日: 1994/05/25
公開日: 2010/08/05
ジャーナル フリーIso-stress tests were conducted on carbon and low alloy steels of which long-term creep rupture data had been obtained in NRIM Creep Data Sheet program, in order to verify the avail ability of Iso-stress method for life prediction. Creep rupture curves of these steels showed an inverse-sigmoidal shape. When the stress of Iso-stress tests was higher than that corresponding to the inverse-sigmoidal shape, the life estimated on the basis of Larson-Miller relation agreed well with experimental long-term one. For the stresses lower than the stress of sigmoidal shape, the life estimated by Manson-Haferd relation agreed well with the experimental one. For the middle stress condition, where the behavior of sigmoidal shape had been observed, the lives predicted by both relations were over-estimated. This over-estimation was caused by a change in the temperature dependence of rupture life due to the change in microstructure and fracture mode with temperature.抄録全体を表示PDF形式でダウンロード (4372K) -
汎用パーソナルCADシステムAuto-CADとの結合門 謙一郎, 佐藤 拓哉, 吉村 忍, 矢川 元基1994 年 32 巻 3 号 p. 139-144
発行日: 1994/05/25
公開日: 2010/08/05
ジャーナル フリーThis paper describes the automatic mesh generation system for 2D axisymmetric and 3D shell structures based on the fuzzy knowledge processing. In this system, an analysis model, i.e. a geometric model, is first defined using a conventional method for 2D structures and a commercial CAD system, Auto-CAD, for 3D shell structures. Nodes are then generated based on the fuzzy knowledge processing technique, well controlling the node density distribution over the whole analysis domain. Triangular elements are generated using the Delaunay triangulation technique. The triangular elements are converted to quadrilateral elements. The fundamental performances of the system are demonstrated through its application to typical components of a pressure vessel.抄録全体を表示PDF形式でダウンロード (672K) -
伊藤 義康, 斉藤 正弘, 豊田 政男1994 年 32 巻 3 号 p. 145-153
発行日: 1994/05/25
公開日: 2010/08/05
ジャーナル フリーA computer-aided interactive system has been developed, which enables to conveniently analyze the thermal stress for multi-layered composites including coating components and functionally gradient materials etc. This system consists of an interactive pre-processor, data bases of material constants, a steady state analysis of heat conduction and thermal stress and a post-processor of calculated results. The thermal stresses are calculated by the analytical method based on strain suppression and beam theory. The analysis can be easily conducted by the selection of menus and the data input acceding to a few commands.
The thermal stress distributions of thermal barrier coating and sixth-layered graded composite are analyzed using the developed system. The calculated results are in good agreement with the calculated results by finite element analysis. Consequently, it is confirmed that the developed system is useful to apply for designing the multi-layered composites.抄録全体を表示PDF形式でダウンロード (3156K) -
栗原 良一, 橘 幸男, 西原 哲夫, 丸山 創, 塩沢 周策, 大下 真一1994 年 32 巻 3 号 p. 154-165
発行日: 1994/05/25
公開日: 2010/08/05
ジャーナル フリーThe High Temperature Engineering Test Reactor (HTTR), whose outlet gas temperature and thermal output are 950°C and 30 MWt, respectively, started the construction in FY 1990 on the site of the Oarai Establishment of the Japan Atomic Energy Research Institute (JAERI). The HTTR aims at establishing and upgrading the technology basis necessary for the high temperature gas-cooled reactors (HTGR), serving at the same time as a potential tool for new and innovative basic researches related to various high temperature engineering areas. The construction of the reactor building on the site and the manufacture of the components at the factories are now proceeding. The first criticality will be attained in FY 1998.
The HTTR contains helium gas with the pressure of 3.9MPa and the temperature from 400°C to 950°C. Pressure boundaries of the HTTR are composed of a reactor pressure vessel (RPV), an intermediate heat exchanger (IHX), a primary pressurized water cooler (primary PWC) and so on. The RPV is the most important component of those pressure boundaries, since it contains core components such as fuel blocks, graphite reflectors, reactivity control system and core support structures which are very important for the safety of the HTTR.
The RPV, 13.2m in height and 5.5m in diameter, consists of a vertical cylinder, an upper and a lower hemispheres. As a material for the RPV, 21/4Cr-1Mo steel is employed, because this steel has better creep strength at high temperatures than Mn-Mo steel which is used widely in the pressure vessels of light water reactors. This paper briefly introduces the structural design of the RPV in the HTTR.抄録全体を表示PDF形式でダウンロード (1379K) -
筧 勝行1994 年 32 巻 3 号 p. 167-174
発行日: 1994/05/25
公開日: 2010/08/05
ジャーナル フリーThis paper discusses the load conditions to be applied in designing oil storage tank with outer flooting roof. This type of tank has been suffered severe damages by strong earthquake and/or big typhoon.
It is considered to some extent the damages come from the actual dynamic force which is not taken into account in the rules, standards and other specific documents for this type of tank today.
After analyzing the damages caused by large scale natural forces, author got some insights of load-characteristics. This paper proposes the application of dynamic force in design, adding to the on-going modified static forces defined as specific loads.抄録全体を表示PDF形式でダウンロード (861K)
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