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 (APOLLO2, TRIPOLI4 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.
Results of Neutronic Benchmark Analysis for a High Temperature Reactor of the GT-MHR Type
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Boyarinov, VF, Bryzgalov, VI, Davidenko, VD, Fomichenko, PA, Glushkov, ES, Gomin, EA, Gurevich, MI, Kodochigov, NG, Marova, EV, Mitenkova, EF, Novikov, NV, Osipov, SL, Sukharev, YP, Tsibulsky, VF, & Yudkevich, MS. "Results of Neutronic Benchmark Analysis for a High Temperature Reactor of the GT-MHR Type." Proceedings of the Fourth International Topical Meeting on High Temperature Reactor Technology. Fourth International Topical Meeting on High Temperature Reactor Technology, Volume 2. Washington, DC, USA. September 28–October 1, 2008. pp. 329-335. ASME. https://doi.org/10.1115/HTR2008-58107
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