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

The Korean Society of Mechanical Engineers (대한기계학회)
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Fracture Mechanics Analysis of Reactor Pressure Vessel Under Pressurized Thermal Shock-The Effect of Elastic-Plastic Behavior and Stainless Steel Cladding-

원자로 용기의 가압열충격에 대한 파괴역학 해석 - 탄소성 거동과 클래드부의 영향 -

  • Published : 2002.01.01
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Abstract

Performed here is an assessment study for deterministic fracture mechanics analysis of a pressurized thermal shock(PTS). The PTS event means an event or transient in pressurized water reactors(PWRs) causing severe overcooling(thermal shock) concurrent with or followed by significant pressure in the reactor vessel. The problems consisting of two transients and 10 cracks are solved and maximum stress intensity factors and maximum allowable nil-ductility reference temperatures are calculated. Their results are compared each other to address the general characteristics between transients, crack types and analysis methods. The effects of elastic-plastic material behavior and clad coating on the inner surface are explored.

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References

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