Abstract
The Pressure Vessel Research Committee (PVRC) Subcommittee on Elevated Temperature Design has been actively engaged in an International Benchmark on Simplified Methods for Elevated Temperature Design. At the Third International Seminar on Inelastic Analysis and Life Prediction in High Temperature Environment held in conjunction with the 6th International Conference on Structural Mechanics in Reactor Technology (SMiRT), August 1981, a progress report on the International Benchmark Project was first reported. This paper is an update of the results of that project. A brief description of the PVRC activities on Elevated Temperature Design is first given. The International Benchmark Problems I, II, and III will then be described. The comparisons between analyses and the recently released experimental results of the French Commissariat l’ Energie Atomique test on fluctuating sodium level in a pool reactor model is now included in this paper. Potential benchmark problems for future consideration by the Subcommittee are also mentioned.
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