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[en] The paper presents a description of benchmark cases, achieved results, analysis of possible reasons of differences of calculation results obtained by various neutronic codes. The comparative analysis is presented showing the benchmark-results obtained with reference and design codes by Russian specialists (WIMS-D, JAR-HTGR, UNK, MCU, MCNP5-MONTEBURNS1.0-ORIGEN2.0), by French specialists (AP0LL02, TRIP0LI4 codes), and by Korean specialists (HELIOS, MASTER, MCNP5 codes). The analysis of possible reasons for deviations was carried out, which was aimed at the decrease of uncertainties in calculated characteristics. This additional investigation was conducted with the use of 2D models of a fuel assembly cell and a reactor plane section. (authors)
Source
2008; 7 p; American Society of Mechanical Engineers - ASME; New York, NY (United States); HTR2008: 4. International Topical Meeting on High Temperature Reactor Technology; Washington, DC (United States); 28 Sep - 1 Oct 2008; ISBN 978-0-7918-3834-1; 
; Country of input: France; 6 refs.
; Country of input: France; 6 refs.