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Onizawa, Kunio; Shibata, Katsuyuki*; Suzuki, Masahide
Proceedings of 2005 ASME/JSME Pressure Vessels and Piping Division Conference (PVP 2005), 12 Pages, 2005/07
Under a transient loading like pressurized thermal shock (PTS), the stress discontinuity near the interface between cladding and base metal of a reactor pressure vessel (RPV) is caused by the difference in their thermal expansion factors. So the stress intensity factor (SIF) of a surface crack which the deepest point exceeds the interface should be calculated by taking account of the stress discontinuity. Many SIF calculations are performed in Monte Carlo simulation of the probabilistic fracture mechanics (PFM) analysis. To avoid the time consuming process from the SIF calculation in the PFM analysis, the non-dimensional SIF coefficients corresponding to the stress distributions in the cladding and base metal were developed. The non-dimensional SIF coefficients database were obtained from 3D FEM analyses. The SIF value at the surface was determined by linear extrapolation of SIF value near the surface. Using the SIF coefficients database, the SIF values at both surface and deepest points of a surface crack can be evaluated precisely and in a reasonable time.
Takahashi, Kenji; Inoue, Kazuhiko; Ito, Kei; Fujita, Takafumi*
Proceedings of 2005 ASME/JSME Pressure Vessels and Piping Division Conference (PVP 2005), 8 Pages, 2005/07
We carried out reflection seismic and multi-offset VSP surveys at JNC Shobasama-site to develop the investigation technique in the granite area, and evaluated the applicability of these geophysical methods.As the result of this study, we consider that a) It is possible to infer the existence of the lower angle fracture zone in the granite by reflection seismic survey and b) Multi-offset VSP supplements the result of reflection seismic survey and it is possible to infer the distribution of the fracture zone in deeper area in the granite.
kasahara, Naoto; Ando, Masanori; Ito, Kei; Tanaka, Yoshihiko; Shibamoto, Hiroshi; Inoue, Kazuhiko
ASME PVP-Vol.472, p.25-32, p.25 - 32, 2004/07
For the realization of safe and economical fast reactor (FR) plants, the Japan Nuclear Cycle Development Institute (JNC) and Japan Atomic Power Company (JAPC) are cooperating on a research project titled "Feasibility Study on Commercialized FR Cycle Systems. To certify the design concepts and validate their structural integrity,the research and development of the "Fast Reactor Structural Design Standard (FDS)" is recognized as begin an essential theme.
Tanaka, Yoshihiko; Shibamoto, Hiroshi; Inoue, Kazuhiko; kasahara, Naoto; Ando, Masanori; Ito, Kei
ASME PVP-Vol.472, p.53-60, p.53 - 60, 2004/07
The guideline on inelastic analysis for design, one of the key items of Fast Reactor Design Standard(FDS), is being developed.The basic policies of this guideline are as follows:(a) to emphasis conservative analysis output rather than nominal value representing actual behavior, (b) to clarify the applicable area for assurance of conservative results. With such concepts, it would be possible that the guideline provides useful explanations on the manner of analysis and estimation in the form of concrete examples of design as well as general rules (somehow vague). As the first step of the guideline development, the following five issues to be solved were extracted:1) applicable area, 2) selection of constitutive equation, 3) modeling method of the load history, 4) ratchet strain and creep fatigue damage evaluation methods by inelastic analysis and 5) example design problems to check users' analysis quality and to complement the general rules. In parallel, inelastic analyses with the promising constitutive equations were applied by way of trial to obtain rough presumption on their effects on structural design of the components. As a result,all inelastic analyses provided smaller cumulative strains and equivalent strain ranges than the existing design method based on elastic analysis,suggesting advantage of introducing them into actual design.
kasahara, Naoto; Hasebe, Shinichi; Kobayashi, Sumio; Ando, Masanori; Kawasaki, Nobuchika; Morita, Hiroshi*
ASME PVP-Vol.472, P. 2986, 2004/00
Focusing on the cover layer materials (as the Radon Barrier Materials), which could have the effect to restrain the radon from scattering into the air and the effect of the radiation shielding, we produced the radon barrier materials with crude bentonite on an experimental basis, using the rotary type comprehensive unit for grinding and mixing, through which we carried out the evaluation of the characteristics thereof.
Harding; ; ; ;
ASME/JSME PVP Conference, 0 Pages, 1999/00
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; Ouchi, Yuichiro; ; ; Harding
ASME/JSME PVP Conference, 0 Pages, 1999/00
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; Ouchi, Yuichiro; ; ; Harding*
ASME/JSME PVP Conference, 0 Pages, 1999/00
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