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Round Robin Analysis of Pressure-Temperature Limit Curve for Reactor Vessel  

정명조 (한국원자력안전기술원)
이진호 (한국원자력안전기술원)
박윤원 (한국원자력안전기술원)
최영환 (한국원자력안전기술원)
김영진 (성균관대학교)
Publication Information
Journal of the Computational Structural Engineering Institute of Korea / v.16, no.2, 2003 , pp. 153-163 More about this Journal
Abstract
Performed here is a comparative assessment study for the generation of the pressure-temperature limit curve of the reactor vessel. A round robin problem is proposed using the data available in Korea and all organizations interested in the generation of the pressure-temperature limit curve are invited. The problems consisting of 12 cases for cool-down are solved and their results are compared to generate a reference solution for the reference problem, which will be useful in the evaluation of the generation of the pressure-temperature limit curve in the future.
Keywords
pressure-temperature limit curve; fracture toughness; stress intensity factor; heat-up; cool-down; reactor vessel; ASME code;
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  • Reference
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