Journal of KSNVE (소음진동)

The Korean Society for Noise and Vibration Engineering (한국소음진동공학회)
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Structural Integrity of a Fuel Assembly for the Secondary Side Pipe Breaks

2차측 배관파단에 대한 핵연료 집합체의 구조 건전성

  • Jhung, M. J. ;
  • ;
  • ;
  • 정명조 (한국원자력연구소 고성능핵연료개발분야) ;
  • 이정배 (한국원자력안전기술원 기계설비그룹)
  • Published : 1996.12.01
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Abstract

The effect of pipe breaks in the secondary side is investigated as a part of the fuel assembly qualification program. Using the detailed dynamic analysis of a reactor core, peak responses for the motions induced from pipe breaks are obtained for a detailed core model. The secondary side pipe breaks such as main steam line and economizer feedwater line braksare considered because leak-before-break methodology has provided a technical basis for the elimination of double ended guillotine breaks of all high energy piping systems with a diameter of 10 inches or over in the primary side from the design basis. The dynamic responses such as fuel assembly shear force, bending moment, axial force and displacement, and spacer grid impact loads are carefully investigated. Also, the stress analysis is performed and the effect of the secondary side pipe breaks on the fuel assembly structural integrity under the faulted condition is addressed.

본연구에서는 핵연료집합체의 검증계획의 일환으로 2차측 배관파단의 영향을 조사하였다. 원자로노심의 상세모델을 이용한 동적해석으로 배관파단에 의한 응답을 구하였다. 파단적 누설개념의 적용으로 10인치 이상의 고에너지 배관에 대하여 양단 파단이 설계에서 배제됨에 따라 본 연구에서는 주증기관과 급수관의 파단을 가정 하였다. 핵연료 집합체의 전단력, 굽힘모우멘트, 변위 및 지지격자체의 충격하중에 대하여 자세히 고찰하였고 이들 동적해석 결과를 이용하여 핵연료집합체의 구조적 건전성을 평가하였으며 사고조건에서 2차측 배관파단이 핵연료집합체의 구조적 건전성 에 미치는 영향을 검토하였다.

Keywords

References

  1. Structural Engineering and Mechanics v.2 Seismic Behavior of Fuel Assembly for Pressurized Water Reactor Jhung, M. J.;Hwang, W. G.
  2. AMSE Boiler and Pressure Vessel Code, Sec. Ⅲ, Rules for Construction of Nuclear Power Plant Components AMSE
  3. ASME Boiler and Pressure Vessel Code, Sec. XI, Rules for Inservics Inspection of Nuclear Power Plant Components ASME
  4. Evaluation of Potential for Pipe Breaks, NUREG-1061 v.3 USNRC
  5. Licensing of productions and Utilization Facilities : Appendix A, General Design Criteria for Nuclear Power plants, 10 CFR Part 50 USNRC
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