• 대한기계학회논문집A
• /
• 제27권5호
• /
• pp.724-733
• /
• 2003

Fatigue design rules for welds in the ASME Boiler and Pressure Vessels Code are based on the use of Fatigue Strength Reduction Factors(FSRF) against a code specified fatigue design curve generated from smooth base metal specimens without the presence of welds. Similarly, stress intensification factors that are used in the ASME B3l.1 Piping Code are based on component S-N curves with a reference fatigue strength based on straight pipe girth welds. But the determination of either the FSRF or stress intensification factor requires extensive fatigue testing to take into account the stress concentration effects associated with various types of component geometry, weld configuration and loading conditions. As the fatigue behavior of welded joints is being better understood, it has been generally accepted that the difference in fatigue lives from one type of weld to another is dominated by the difference in stress concentration. However, general finite element procedures are currently not available for effective determination of such stress concentration effects. In this paper, a mesh-insensitive structural stress method is used to re-evaluate the S-N test data, and then more effective method is proposed for pressure vessel and piping fatigue design.

• 한국안전학회지
• /
• 제21권6호
• /
• pp.20-25
• /
• 2006

In the design of class 1 components to apply ASME code section III NB, a fatigue is considered as one of the important failure mechanisms. Fatigue analysis procedure and standard fatigue design curve(S-N curve) is suggested in ASME code, which had to be performed to meet the integrity of components at the design step. As the plant life extension for operating power plants and the long-lived plant design, however, are being progressed, the fact which the existing ASME fatigue design curve can not consider fatigue effects sufficiently comes to the fore. To find the technical solution for these problems, a number of researches and discussion are continued up to now. In this study, the detailed fatigue analyses using the 3 dimensional modeling for the fatigue-weakened components were performed to develop the optimized fatigue analysis procedure and their results are compared with other reference solutions.

• Nuclear Engineering and Technology
• /
• 제56권9호
• /
• pp.3764-3774
• /
• 2024

In accordance with Regulatory Guide 1.207, Rev.1, fatigue assessments must be conducted considering the influence of primary coolant environment in nuclear reactors. Environmental fatigue, resulting from corrosion in the primary coolant, is evaluated in air fatigue life assessments through the application of an environmental fatigue correction factor. This environmental fatigue correction factor depends on sulfur content, operating temperature, dissolved oxygen, and strain rate. It remains constant for sulfur content, operating temperature, and dissolved oxygen, while strain rate introduces potential errors based on the analysis method. The current fatigue evaluation procedure for air, following ASME B&PV Code Sec.III, NB-3200, employs elastic analysis with a simplified elastic-plastic correction factor(Ke). However, Ke factor is considered excessively conservative, prompting less conservative alternatives proposed by JSME, RCC-M, ASME Code Case N-779. This study applied both ASME Ke and JSME Ke for fatigue evaluations considering environmental effects. Additionally, fatigue assessments accounting for elastic-plastic effects were conducted using Neuber and Glinka methods, compared with actual experiments. The analysis systematically examined changes in fatigue life and the environmental fatigue correction factor due to plastic effects in environmental fatigue evaluations.

• 한국원자력학회:학술대회논문집
• /
• 한국원자력학회 1998년도 춘계학술발표회논문집(2)
• /
• pp.795-801
• /
• 1998

Metallic fatigue of Pressurized Water Reactor(PWR) materials is a generic safety issue for commercial nuclear power plants. It is very important to obtain the fatigue usage factor for component integrity and life extension. In this paper, fatigue usage was obtained at the inside surface of Kori unit 2, 3 and 4 RCP casing weld, based on the design transient. And it was intended to establish the procedure and the detailed method of fatigue evaluation in accordance with ASME Section III Code. According to this code rule, two methods to determine the stress cycle and the number of cycles could be applied. One method is the superposition of cycles of various design transients and the other is based on the assumption that a stress cycle correspond to only one design transient. Both method showed almost same fatigue usage in the RCP casing weld.

• 한국철도학회:학술대회논문집
• /
• 한국철도학회 2002년도 추계학술대회 논문집(II)
• /
• pp.884-891
• /
• 2002

This report is the result performed the structural analysis and the static and fatigue load test of bogie frame for the purpose of designing and verifying the bogie frame which satisfy the load condition required in the UIC code. This investigation is proposed the efficient draft of the design to satisfy the load condition required in the UIC code. And It is performed the structural analysis to evaluate the static strength and the fatigue life of the patient material and the welded part. Also, This is proposed the efficient draft of the test to satisfy the method of the static and fatigue test required in the UC code. And it is carried out the static and the fatigue load test to verify it. We can designed the bogie frame in compliance with UIC 515-4 and 615-4 code.

• 한국강구조학회 논문집
• /
• 제21권3호
• /
• pp.331-342
• /
• 2009

Miner의 피로손상법칙을 적용하여 피로파괴에 대한 한계상태함수를 표현하고, 실제 국내 통행차량의 통계적 특성을 반영하여 LRFD 설계기준(안)의 피로설계트럭모형과 현 도로교설계기준의 DB-24 하중에 대한 피로파괴 신뢰도해석을 수행하였다. 피로한계상태함수는 Miner의 피로손상법칙을 확률변수의 함수로 나타내고 이들 확률변수에 대하여 국내 통행트럭 등의 실측 통계자료를 분석하여 구한 통계치와 문헌에 보고된 결과를 조사하여 구한 통계치를 적용하여 지간별 및 피로상세별 신뢰도지수를 Rackwitz-Fiessler법으로 구하고, 신뢰도해석 결과를 분석하여 LRFD 설계기준(안)의 피로설계트럭모형을 제안하였다. 아울러, 제안된 피로설계트럭모형을 적용하여 단경간 및 3경간 연속 플레이트 및 박스 거더교의 총 16개 실교량에 대한 피로설계를 수행하고, 설계결과를 현 도로교설계기준의 DB-24 하중에 의한 피로설계 결과와 비교하여 LRFD 피로설계트럭 모형의 적용성을 검토하였다.

• 한국해양공학회지
• /
• 제10권2호
• /
• pp.13-19
• /
• 1996

For fatigue analsis of offshore structures, existing methods have been reviewed and a computer code has been developed on PC. As methods to estimate the probabillity distribution of the fatigue stress, three methods(the deterministic method, the stochastic method, and the simplified method) are used in this code, to choose the appropriate method according to the situations. This code estimates damage ratios, fatigue lives, and probabilities of fatigue failure considering scatterness of SN-data, based on linear damage rule and SN-curves. Also, allowable stress for the design extreme wave can calculated by the simplified method.

• 대한기계학회논문집A
• /
• 제33권10호
• /
• pp.1151-1157
• /
• 2009

Nuclear power plants applying for the continued operation over design life are required to address the effects of reactor water environment in fatigue design requirement of the ASME Code. Reactor water environmental effects are generally evaluated by calculating fatigue correction factors on fatigue usage. This paper describes the application for pressurizer surge line of environmental fatigue correction factors and the strain rate impact in the application. From this paper, the environmental fatigue correction factors resulted from the assumption of a step change in temperature are especially compared with those calculated from the data measured during plant startup. As a conclusion of this paper, the design transient conditions applied to the fatigue design may be conservative in case of the environmental fatigue evaluation.

• 한국강구조학회 논문집
• /
• 제9권2호통권31호
• /
• pp.237-248
• /
• 1997

크레인 주행거더에서 빈번히 발생되는3 종류의 균열을 재현하기 위해서 거더 길이 640 mm, 높이 600 mm, 폭 300 mm의 시험체 2기를 제작하여 피로실험을 수행하였다. 시험체의 균열은 재하점 부근과 가세트 단부 및 하부플랜지와 웨브의 모살용접부에서 발생하였다. 재하점 근방의 균열은 수직보강재가 위치한 상부플랜지와 웨브 사이의 모살용접부에서 발생해서 웨브의 대각선 방향으로 진전하였다. 또한 하부플랜지 종비드에서 발생된 균열은 주행거더방향에 수직으로 성장하였다. 크레인 주행거더의 각 부위의 피로등급은 JSSC 피로설계지침의 피로등급과 비교해 보면, 재하점 근방의 모살용접부는 E 등급, 가세트 단부는 G 또는 H 등급, 하부플랜지 종비드 부위는 D 등급 정도로 나타났다. 가세트 단부와 종비드 부위는 피로설계지침과 잘 일치하고 있음을 알 수 있다.

• 한국압력기기공학회 논문집
• /
• 제15권2호
• /
• pp.19-30
• /
• 2019

In this study, to evaluate conservatism of various fatigue life evaluation procedures, fatigue tests were conducted using compact tension (CT) specimens with a round notch, made of A516 Gr.70 carbon steel and A240 TP304 stainless steel, under load-controlled cyclic condition. Experimental fatigue failure cycles were measured and compared with predicted fatigue lives using two different life evaluation methods; (1) Design-By-Analysis (DBA) procedure given in ASME B&PV Code, Sec. III, Div. 1, Subsec. NB-3200 and (2) structural stress-based approach provided in ASME B&PV Code, Sec. VIII, Div. 2, Part 5. To predict fatigue failure cycles, three-dimensional elastic finite element analysis was conducted. Fatigue lives were predicted by both design fatigue curve given in ASME B&PV Code, Sec. III, Div. 1, Appendices and best-fit fatigue curve suggested in NUREG/CR-6815 for the DBA procedure. Finally, fatigue lives evaluated by various methods were compared with test results, and then conservatism between each evaluation procedure was discussed.