Reactor Physics Analysis of the VHTGR Core
نویسندگان
چکیده
As part of an I-NERI project to develop safety analysis codes and experimental validation for a VeryHigh Temperature Gas-Cooled Reactor (VHTGR), we have developed MCNP5 [1] models to represent material heterogeneities inherent in the microsphere fuel particles and fuel compacts for a GT-MHR design [2]. We have also performed preliminary coupled nuclear-thermalhydraulic (NTH) analysis to obtain self-consistent global power and temperature distributions using a homogenized global model for MCNP5 and three-ring core model for the RELAP5-3D/ATHENA code [3]. We present a comparison of heterogeneous and homogeneous representations of the microsphere and fuel compact cells, establishing the impact of heterogeneities on the overall VHTGR neutronics analysis. We also discuss the importance of fuel temperature feedback on the global power distribution.
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