Transactions of the Korean Society of Mechanical Engineers A (대한기계학회논문집A)

The Korean Society of Mechanical Engineers (대한기계학회)
권호 표지
DOI QR코드

DOI QR Code

Development of Mesh Generation Program for the Primary System of Nuclear Power Plant

원자력 주요기기 해석을 위한 자동요소망 생성프로그램 개발

  • Published : 2000.02.01
Download PDF
⟨ Previous Next ⟩

Abstract

Fracture mechanics analysis (FMA) is an essential work for integrity evaluation of nuclear power plant. The flaws inspected by In-Service Inspection(ISI) should be confirmed by FMA for the decision of the operation status of stop or continuance. The basic data for FMA are the stress of the interested area. The purpose of this research is to develop a system which can obtain stress data efficiently based on various database. Mesh generation program generates mesh using MSC/PATRAN and provides input file for finite element analysis according to the databases (shape, dimension, transient and material). The stress data from the finite element analysis are stored to be stress database so that it can be applied to FMA. As an example, the system developed by this study is applied to pressurizer nozzle and confirmed to be a useful tool for efficient FMA.

Keywords

References

  1. ASME, 1992, ASME Boiler and Pressure Vessel Code, Section XI
  2. Westinghouse, 1997, Stress Distributions for The KORI 1,2 Pressurizers
  3. 최성남, 1998, '원자력발전소 가압기 노즐의 피로균열 안정성 분석,' 대한기계학회지, 제22권, 제6호, pp. 1125-1133
  4. MSC, 1994, Introduction to the P3/PATRAN Command Language Course Notes
  5. Netsarang, 1997, Xmanager User's Manual
  6. ASME, 1992, 'Rules for Construction of Nuclear Power Plant Components, ASME Boiler and Pressure Vessel Code, Section III, Division 1, Subsection NB, Class 1 Components,
  7. 장창희, 1998, '원자로 압력용기 원주방향 용접부의 가압열충격 심사기준온도의 적정성 평가,' 한국원자력학회 춘계학술대회 논문집, pp. 369-376
  8. ASME, 1992, ASME Boiler and Pressure Vessel Code, Division I, Section III, Appendices
  9. ASME,1995, ASME Bliler and Pressure Vessel Code Section II, 'Materials, Part D-Properties.'
  10. 성균관대학교 과학기술연구소, '고리2호기 가압기 용접결함의 파괴역학 해석.'
  11. 문호림, 전현규, 최재붕, 김영진, 표창률, 최성남, 장기상, 1998, '원자력 설비 건전성 평가를 위한 통합데이터베이스 프로그램 개발,' 대한기계학회 추계학술대회 논문집 B, pp. 936-941