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Journal Articles

Plasticity correction on stress intensity factor evaluation for underclad cracks in reactor pressure vessels

Lu, K.; Katsuyama, Jinya; Li, Y.

Journal of Pressure Vessel Technology, 142(5), p.051501_1 - 051501_10, 2020/10

 Times Cited Count:2 Percentile:15.81(Engineering, Mechanical)

Journal Articles

Development of stress intensity factors for subsurface flaws in plates subjected to polynomial stress distributions

Lu, K.; Mano, Akihiro; Katsuyama, Jinya; Li, Y.; Iwamatsu, Fuminori*

Journal of Pressure Vessel Technology, 140(3), p.031201_1 - 031201_11, 2018/06

 Times Cited Count:9 Percentile:45.47(Engineering, Mechanical)

Journal Articles

Plasticity correction on the stress intensity factor evaluation for underclad cracks under pressurized thermal shock events

Lu, K.; Katsuyama, Jinya; Li, Y.

Proceedings of 2016 ASME Pressure Vessels and Piping Conference (PVP 2016) (Internet), 8 Pages, 2016/07

Journal Articles

Development of stress intensity factors for surface cracks with large aspect ratio in plates

Li, Y.; Hasegawa, Kunio; Katsumata, Genshichiro; Osakabe, Kazuya*; Okada, Hiroshi*

Journal of Pressure Vessel Technology, 137(5), p.051207_1 - 051207_8, 2015/10

 Times Cited Count:8 Percentile:37.14(Engineering, Mechanical)

A number of surface cracks with large aspect ratio have been detected in components of nuclear power plants in recent years. The depths of these cracks are even larger than the half of crack lengths. However, the solutions of the stress intensity factor were not provided for semi-elliptical surface cracks with large aspect ratio in the current fitness-for-service codes. In this study, in order to conduct integrity assessment for cracked components, the solutions of the stress intensity factor were calculated using finite element analysis for semi-elliptical surface cracks with large aspect ratio in plates. Solutions were provided at both the deepest and the surface points of the surface cracks. Some of solutions were compared with the available existing results. As the result, it was concluded that the solutions proposed in this paper are applicable in engineering applications.

Journal Articles

Fracture mechanics analysis including the butt joint geometry for the superconducting conductor conduit of the national centralized tokamak

Takahashi, Hiroyuki*; Kudo, Yusuke; Tsuchiya, Katsuhiko; Kizu, Kaname; Ando, Toshinari*; Matsukawa, Makoto; Tamai, Hiroshi; Miura, Yukitoshi

Fusion Engineering and Design, 81(8-14), p.1005 - 1011, 2006/02

 Times Cited Count:2 Percentile:17.18(Nuclear Science & Technology)

This paper presents dependence of the stress intensity factor, around the defect in the butt joint welding of a superconducting conductor conduit, on a geometrical factor estimated by fracture mechanics analysis. The stress intensity factor can be estimated by the Newman-Raju equation about CICC section, but the effect of the difference between the geometry assumed in the equation and CICC has not been clarified yet. Therefore, the three-dimensional finite element method (3D-FEM) is performed to estimate the geometrical factor. As a result, the Newman-Raju equation is considered to be available for the assessment of the fracture toughness of the conduit of rectangular shape because the maximum stress intensity factor by 3-D FEM is only 3% larger than that by the Newman-Raju equation in the maximum postulated defect.

Journal Articles

Elasto-plastic analysis of re-distribution of residual stress due to crack extension and fracture mechanics parameters

Shibata, Katsuyuki*; Onizawa, Kunio; Suzuki, Masahide; Li, Y.*

Nihon Kikai Gakkai M&M 2005 Zairyo Rikigaku Kanfarensu Koen Rombunshu, p.299 - 300, 2005/11

no abstracts in English

Journal Articles

Development of Stress intensity factor coefficients database for a surface crack of an RPV considering the stress discontinuity between cladding and base metal

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.

Journal Articles

Improvements to a probabilistic fracture mechanics code for evaluating the integrity of a RPV under transient loading

Li, Y.*; Kato, Daisuke*; Shibata, Katsuyuki; Onizawa, Kunio

International Journal of Pressure Vessels and Piping, 78(4), p.271 - 282, 2001/04

 Times Cited Count:5 Percentile:41.41(Engineering, Multidisciplinary)

no abstracts in English

Journal Articles

Fracture toughness of a fine-grained nuclear graphite by means of various methods

Eto, Motokuni; Ishiyama, Shintaro; Nishiyama, Yutaka; Oku, Tatsuo*; T.D.Burchell*

Int. Symp. on Carbon New Processing and New Applications; Extended Abstracts,Vol. 1, p.170 - 173, 1990/11

no abstracts in English

Journal Articles

Effect of stress ratio on crack extension rate of fine-grained isotropic nuclear graphite

; ;

Journal of Nuclear Science and Technology, 24(9), p.719 - 723, 1987/09

 Times Cited Count:6 Percentile:55.66(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Stress Intensity Factor Analyses of Surface Cracks in Three-Dimensional Structures

*; ; *; *

JAERI-M 83-189, 44 Pages, 1983/11

JAERI-M-83-189.pdf:1.05MB

no abstracts in English

JAEA Reports

Cyclic Crack Growth Typical Weld HAZ Microstructures of SA 533gr.B Steel in Simulated BWR Environment

; ; Shindo, Masami; ; ; ; ; ; *; *; et al.

JAERI-M 82-062, 23 Pages, 1982/06

JAERI-M-82-062.pdf:1.31MB

no abstracts in English

Journal Articles

Fatigue behavior of pipes containing multiple flaws in inner surface

; ; ; ;

Nucl.Eng.Des., 74(2), p.199 - 213, 1982/00

 Times Cited Count:1 Percentile:22.52(Nuclear Science & Technology)

no abstracts in English

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