Identification of Integral Benchmarks for Nuclear Data Testing Using DICE (Database for the International Handbook of Evaluated Criticality Safety Benchmark Experiments)

By Briggs J. Blair, N. A, Rugama Yolanda, Soppera Nicolas, Bossant Manuel. 2011

233 citations recorded by the source corpus.

Subfields: Aerospace Engineering, Materials Chemistry, Safety, Risk, Reliability and Quality

View Paper: https://www.semanticscholar.org/paper/d4b3656acad4f19d691a1ec128a51af8b8fd0f68

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1. Ho Jin Park
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Citations in the corpus

• The OpenMC Monte Carlo particle transport code (2012, background): “To demonstrate the salient features of the user input format, let us look at an example of a set of input files from a real model, in this case the U233-MET-FAST-002 benchmark problem from the International Handbook of Evaluated Criti-cality Safety Benchmark Experiments (NEA Nuclear Science Committee”
• MCCARD : MONTE CARLO CODE FOR ADVANCED REACTOR DESIGN AND ANALYSIS (2012, background): “…are tested against well-publicized neutronics benchmark problems such as International Criticality Safety Benchmark Experimental Problem (ICSBEP) [32], the Venus PWR engineering experiments [33-35], and the burnup benchmark problem suite for the reactor physics studies of next-generation fuels…”