Study on Incorporation of a New Design Fatigue Curve Into the JSME Environmental Fatigue Evaluation Method

2019 ◽  
Author(s):  
Seiji Asada ◽  
Shengde Zhang ◽  
Masahiro Takanashi ◽  
Yuichirou Nomura
Keyword(s):  
Nuclear Power ◽  
Evaluation Method ◽  
Fatigue Curve ◽  
Fatigue Analysis ◽  
Analysis Method ◽  
Energy Research ◽  
Research Committee ◽  
Engineering Society ◽  
Fatigue Evaluation ◽  
Generation Facility

Abstract A new fatigue analysis method was developed in the Subcommittee on Design Fatigue Curve in the Atomic Energy Research Committee in the Japan Welding Engineering Society JWES). If the new design fatigue curves are incorporated into the Environmental Fatigue Evaluation Method of the Japan Society of Mechanical Engineers (JSME), the environmental fatigue analysis can be optimized. The Subgroup on Fatigue Evaluation of the Subcommittee on Nuclear Power in the Main Committee on Power Generation Facility Codes in the JSME is reviewing the new design fatigue curves to incorporate into the JSME Environmental Fatigue Evaluation Method. This paper discuss the new design fatigue curves which is under review.

Plan and Status of Development of Design Fatigue Curves: Phase 1

2013 ◽  
Author(s):  
Seiji Asada ◽  
Akihiko Hirano ◽  
Masao Itatani ◽  
Munehiro Yasuda ◽  
Takehiko Sera ◽  
...  
Keyword(s):  
Stainless Steels ◽  
Phase 1 ◽  
Austenitic Stainless Steels ◽  
Fatigue Curve ◽  
Carbon Steels ◽  
Low Alloy Steels ◽  
Energy Research ◽  
Research Committee ◽  
Engineering Society ◽  
Alloy Steels

In order to develop and propose new design fatigue curves for austenitic stainless steels, carbon steels and low alloy steels that are rational and have clear design basis, Design Fatigue Curve (DFC) subcommittee has been established in the Atomic Energy Research Committee in the Japan Welding Engineering Society and the study on design fatigue curves are going on. This paper introduces the plan and status of the activities of the DFC subcommittee.

Optimization of Environmental Fatigue Evaluation: Step 1

2007 ◽  
Author(s):  
Takao Nakamura ◽  
Masanobu Iwasaki ◽  
Seiji Asada
Keyword(s):  
Evaluation Method ◽  
Fatigue Curve ◽  
Design Stage ◽  
Total System ◽  
Analysis Method ◽  
Safety Factors ◽  
Alternative Evaluation ◽  
Plant Construction ◽  
Fatigue Evaluation ◽  
Design And Construction

In order to introduce environmental effects into fatigue evaluation of design and construction codes, the environmental fatigue evaluation method should not only be established, but the conservativeness of the codes, such as safety factors of design fatigue curve and simplified elastic-plastic analysis method (Ke factor), etc. should also be reviewed. Then plant designers should optimize total system of fatigue evaluation according to the objective of the codes by properly selecting design transient conditions and stress analysis methods used in fatigue evaluations as necessary. In addition, investigation of measures for reducing fatigue should be performed to mitigate possible fatigue initiators and alternative evaluation methods in case that the evaluation result should exceed the criteria specified in the design and construction codes. This paper discusses the present status in the review of these items for the Japanese PWR plants and future prospects to tackle on the application of environmental fatigue evaluation in design stage of plant construction.

Study on Mean Stress Effects for Design Fatigue Curves

2016 ◽  
Author(s):  
Seiji Asada ◽  
Takeshi Ogawa ◽  
Makoto Higuchi ◽  
Hiroshi Kanasaki ◽  
Yasukazu Takada
Keyword(s):  
Evaluation Method ◽  
Austenitic Stainless Steels ◽  
Fatigue Curve ◽  
Carbon Steels ◽  
Low Alloy Steels ◽  
Mean Stress ◽  
Research Committee ◽  
Stress Effects ◽  
Alloy Steels ◽  
Design Factors

In order to develop new design fatigue curves for austenitic stainless steels, carbon steels and low alloy steels and a new design fatigue evaluation method that are rational and have a clear design basis, the Design Fatigue Curve (DFC) subcommittee was established in the Atomic Energy Research Committee in the Japan Welding Engineering Society. Mean stress effects for design fatigue curves are to be considered in the development of design fatigue curves. The Modified Goodman approach for mean stress effects is used in the design fatigue curves of the ASME B&PV Code. Tentative design fatigue curves were developed and studies on the effect of mean stress and design factors are on-going. Development of design fatigue curves, effect of mean stress and design factors is needed to establish a new fatigue design evaluation method. The DFC subcommittee has studied correction approaches for mean stress effects and the approaches of modified Goodman, Gerber, Peterson and Smith-Watson-Topper were compared using test data in literature. An appropriate approach for mean stress effects are discussed in this paper.

Guidelines on Environmental Fatigue Evaluation for LWR Component

2003 ◽  
Author(s):  
Takao Nakamura ◽  
Itaru Saito ◽  
Yasuhide Asada
Keyword(s):  
Environmental Effects ◽  
Nuclear Power ◽  
Reduction Factor ◽  
Engineering Society ◽  
Fatigue Initiation ◽  
Plant Life ◽  
Actual Operating ◽  
Fatigue Evaluation ◽  
Fatigue Life Reduction ◽  
Operating Plant

Japanese utilities and vendors have taken environmental effects on fatigue (EF) into consideration in the plant life management (PLM) activity of operating plants for several years. In Sep. 2000 MITI notified the utilities to adopt “The Guidelines for Evaluating Fatigue Initiation Life Reduction in LWR Environment (MITI guidelines)” for PLM evaluation of operating plants [1]. In April 2001, the study started to establish detailed procedures for EF evaluation and the committee was organized for developing detailed guidelines at Thermal and Nuclear Power Engineering Society (TENPES). The evaluation guidelines were completed and published as TENPES guidelines [2]. These guidelines proposed several practical options to apply fatigue life reduction factor for environmental effects (Fen) on actual operating plant fatigue evaluation.

Inspection Guideline of BWR Core Internals in Japan

2002 ◽  
Author(s):  
Akio Yamamoto ◽  
Naoto Iizuka ◽  
Takeshi Yoshinaga ◽  
Haruo Fujimori ◽  
Yuuichi Motora
Keyword(s):  
Basic Concept ◽  
Nuclear Power ◽  
Evaluation Method ◽  
Structural Integrity ◽  
Nuclear Power Engineering ◽  
Power Engineering ◽  
Jet Pump ◽  
Engineering Society ◽  
Core Shroud

There are crack experiences of core internal components worldwide. So Thermal and Nuclear Power Engineering Society in Japan organized the committee to prepare the appropriate inspection and evaluation guidelines for core internal components at February, 2000. This committee consists of scholars and representatives from utilities and vendors in Japan. At this committee, guidelines for rational inspection and the evaluation method for structural integrity of each core internal components have been developed. For BWR, inspection guidelines for main core internal components like shroud support, core shroud, top guide, core plate, jet pump etc. were prepared at March 2002. Basic concept of guidelines and inspection guideline of shroud support as example will be explained here.

Study on a New Design Fatigue Evaluation Method

2015 ◽  
Author(s):  
Seiji Asada ◽  
Takashi Hirano ◽  
Takehiko Sera
Keyword(s):  
Evaluation Method ◽  
Austenitic Stainless Steels ◽  
Carbon Steels ◽  
Design Evaluation ◽  
Low Alloy Steels ◽  
Mean Stress ◽  
Research Committee ◽  
Fatigue Design ◽  
Fatigue Evaluation ◽  
Design Factors

In order to develop new design fatigue curves for austenitic stainless steels, carbon steels and low alloy steels and a new design fatigue evaluation method that is rational and has a clear design basis, the Design Fatigue Curve (DFC) subcommittee was established in the Atomic Energy Research Committee in the Japan Welding Engineering Society. Tentative design fatigue curves were developed and studies on the effects of mean stress and design factors are ongoing. Design fatigue curves, including the effects of mean stress and design factors, are needed to establish a new fatigue design evaluation method. This paper describes the study on the new fatigue design evaluation method.

Development of Fatigue Assessment Method Based on Flaw Tolerance Concept

2013 ◽  
Author(s):  
Seiji Asada ◽  
Takeda Shuhei ◽  
Taiji Hirasawa ◽  
Toshiyuki Saito ◽  
Itaru Saito ◽  
...  
Keyword(s):  
Power Generation ◽  
Nuclear Power ◽  
Evaluation Method ◽  
Assessment Method ◽  
Fatigue Assessment ◽  
Nondestructive Examination ◽  
Flaw Tolerance ◽  
Fatigue Evaluation ◽  
Tolerance Method ◽  
Operating Plant

The Japan Society of Mechanical Engineers (JSME) Committee on Power Generation Facility Codes recognizes the importance of fatigue evaluation methods based on the latest knowledge and is developing a fatigue evaluation method by flaw tolerance. The ASME B&PV Code Section XI has Non-mandatory Appendix L, “Operating Plant Fatigue Assessment” (hereinafter “App. L”), which provides a flaw tolerance method for fatigue evaluation when a cumulative usage factor (CUF) of a component is greater than 1.0. In order to develop a flaw tolerance method for the JSME Codes for nuclear power generation facilities, postulated initial flaws, capability of nondestructive examination, compatibility to rules and flaw tolerance codes are discussed.

Applicability of Seismic Fatigue Evaluation by JSME Code Case, NC-CC-008

2019 ◽  
Author(s):  
Akihito Otani ◽  
Izumi Nakamura ◽  
Tomoyoshi Watakabe ◽  
Masaki Morishita ◽  
Tadahiro Shibutani ◽  
...  
Keyword(s):  
Evaluation Method ◽  
Shaking Table Test ◽  
Shaking Table ◽  
Evaluation Methodology ◽  
Response Analysis ◽  
Analysis Method ◽  
Seismic Evaluation ◽  
Fatigue Evaluation ◽  
Conservative Result ◽  
Current Rule

Abstract A Code Case, JSME S NC1, NC-CC-008, in the framework of JSME Nuclear Codes and Standards has been published. New seismic evaluation methodology for piping by utilizing advanced elastic-plastic response analysis method and strain-based fatigue criteria has been incorporated into the code case. It can achieve more rational seismic design than the current rule. This paper demonstrates validity and applicability of fatigue evaluation method proposed in the code case. Experimental results of a shaking table test for a piping model is used for comparing the evaluation by the current rule with one by the code case. As a result, it is confirmed that the code case can provide a rational and conservative result in the fatigue evaluation of piping. Moreover, cycle counting in the fatigue evaluation was examined for further progress of the code case.

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