Analysis on the calculation of power and thermal neutron flux distribution for RGTT200K reactor

RGTT200K reactor, as an high temperature gas-cooled reactor, is designed for cogeneration with a thermal power of 200 MWt h using TRISO pebble fuel. The RGTT200K fuel is kernel UO₂ (uranium dioxide) with 10 % enrichment. The power and thermal neutron flux distribution calculation are using Monte Carlo MCNP5v1.2 code, by utilizing of continuous energy cross-sections taken from ENDF/B-VII files. The purpose of this research is to determine the distribution of neutron flux and the power generated by RGTT200K core. Those important parameters are used in the next calculation of the thermal flow analysis. The RGTT200K core is modeled with dimensional geometry. The active RGTT200K core is divided into 25 zones, with 5 zones to the radial direction and 5 zones in the axial direction and the volume of each zone is made equal. The calculation results and analysis of the thermal neutron flux distributions in the active core of RGTT200K reactor are ranging from 7.7 x 10¹³ neutron/cm².sec occur on core position of R5Z1 (zone 79), to maximum value 2.4 x 10¹⁴ neutron/cm².sec on the core position of R1Z4 (zone 80). The power distributions generated by the active core of RGTT200K reactor are ranging from 4.249341 MWth at the position of R4Z5 (zone 88, Top part of core) up to a maximum value is 12.5810 MWth reached at the position of R1Z3 (zone 75) on the axial height of 3/5 active core. (author)