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Journal Articles

Research program for ageing of nuclear power plant based characteristics of Fukui area

Sakakibara, Yasuhide; Isomura, Kazutoshi; Yamashita, Takuya; Watashi, Katsumi; Doi, Motoo; Okusa, Kyoichi; Tagawa, Akihiro; Hirahara, Kenji

Nihon Hozen Gakkai Dai-3-Kai Gakujutsu Koenkai Yoshishu, p.283 - 286, 2006/06

This study was performed to enrich the contents of measures for an ageing of the nuclear power plants at Fukui area, where infrastructures of research works, for example, institutes, universities etc. are intensively existed., according to the Road-Map established by the Atomic Energy Society of Japan at 2005.

JAEA Reports

Development of Advanced Methodology for Defect Assessment in FBR Power Plants (Phase II)

Meshii, Toshiyuki*; Watashi, Katsumi; Doi, Motoo; Hashimoto, Takashi

JNC TY4400 2004-001, 90 Pages, 2004/03

JNC-TY4400-2004-001.pdf:10.67MB

Based on the results of the Phase I of the titled research, we started Phase II scheduled to reach conclusion (develop basic methods necessary for FBR post-construction code) in three years. The following results were obtained. (1) Development of assessment procedure for multiple defects due to creep damage: We first confirmed that multiple surface cracks in axial and circumferential direction inside a cylinder can be evaluated independently by investigating multiple flaws found in a cylinder due to cyclic thermal shock. Then we developed a method to evaluate the stress intensity factors (SIFs) of the multiple circumferential cracks in a finite legth cylinder under axisymmetric loads. (2) Improving creep-fatigue crack grown (C-FCG) assessment pfodedure: We reviewed the French code A16 for flaw assessment and compared it with the JNC proposal. Since the fundamenfal philosophy for both was to evaluate the C-FCG by estimating elastic-plastic fracture mechanics parameter from the SIF, we developed a "3D crack finite element analysis system that can specify the target error in SIF." (3) Crack propagation assessment under thermal stresses (fatigue crack grown (FCG) resistace for small load): To improve accuracy of FCG assesment for components in FBR power plants (designed to minimize thermal stresses) under thermal cycles, we obtained near threshold FCG data for S55C, SUS304, HT60, SS400, 2.25Cr-1Mo, SUS316, SUS321, T91, Inconel718 by Kmax = constant test method. The results showed that FCG curves in the JSME post construction code (which is an extrapolation of the curves in ASME PVP code sec. XI) are valid in general. However, precise review of S55C, HT60's data suggested that the JSME FCG, evaluation curve may not have enough safety margin. In addition, we proposed a method to predict the decrease in the threshold SIF range DeltaKth due to high Kmax and showed its validity.

JAEA Reports

Development of advanced methodology for defect assessment in FBR power plants (Phase II); 2002 Annual Report

Meshii, Toshiyuki*; Watashi, Katsumi; Doi, Motoo; Hashimoto, Takashi

JNC TY4400 2003-002, 63 Pages, 2003/03

JNC-TY4400-2003-002.pdf:3.95MB

no abstracts in English

Oral presentation

Study on Risk-Based Maintenance approach to FBR plant

Doi, Motoo; Tsukimori, Kazuyuki; Watashi, Katsumi

no journal, , 

no abstracts in English

Oral presentation

Vibration and deformation monitoring for high temperature structures by heat-resistant FBG

Shimada, Yukihiro; Masuzumi, Takashi; Nishimura, Akihiko; Doi, Motoo*; Tsukimori, Kazuyuki

no journal, , 

We performed irreversible lattice processing into the quartz board using the technique of non-heat processing which used femtosecond laser. The heat-resistant evaluation was performed for the purpose of development of heat-resistant FBG for always supervising heat transfer system vibration and modification of a high temperature structure. As a result, the intensity ratio of diffraction light did not change but after rising temperature up to 950 $$^{circ}$$C showed that the system of heat-resistant FBG was effective as a local vibration of high temperature piping, and the distorted detection technique.

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