Analysis of an OECD/NEA high-temperature reactor benchmark
- Serco Assurance, Winfrith Technology Centre, Dorchester, DT2 8DH (United Kingdom)
- CEA-Cadarache, 13108 Saint Paul Lez Durance (France)
- Nexia Solutions (United Kingdom)
- Nuclear Science and Technology Div., ORNL, Oak Ridge, TN 37831-6170 (United States)
- Nuclear Engineering Dept., Hacettepe Univ. (Turkey)
- OECD NEA Data Bank, 92130 Issy-les-Moulineaux (France)
This paper describes analyses of the OECD/NEA HTR benchmark organized by the 'Working Party on the Scientific Issues of Reactor Systems (WPRS)', formerly the 'Working Party on the Physics of Plutonium Fuels and Innovative Fuel Cycles'. The benchmark was specifically designed to provide inter-comparisons for plutonium and thorium fuels when used in HTR systems. Calculations considering uranium fuel have also been included in the benchmark, in order to identify any increased uncertainties when using plutonium or thorium fuels. The benchmark consists of five phases, which include cell and whole-core calculations. Analysis of the benchmark has been performed by a number of international participants, who have used a range of deterministic and Monte Carlo code schemes. For each of the benchmark phases, neutronics parameters have been evaluated. Comparisons are made between the results of the benchmark participants, as well as comparisons between the predictions of the deterministic calculations and those from detailed Monte Carlo calculations. (authors)
- Research Organization:
- American Nuclear Society, 555 North Kensington Avenue, La Grange Park, IL 60526 (United States)
- OSTI ID:
- 22039554
- Resource Relation:
- Conference: PHYSOR-2006: American Nuclear Society's Topical Meeting on Reactor Physics - Advances in Nuclear Analysis and Simulation, Vancouver, BC (Canada), 10-14 Sep 2006; Other Information: Country of input: France; 8 refs.
- Country of Publication:
- United States
- Language:
- English
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