[2I03-08] Analysis Technique Development 2

[2I08] Schematic evaluation of burnup behavior based on core-scale spectral evaluation in graphite moderated systems

*Katsuki Fukuhara¹, Nozomu Fujimoto¹, Yuji Fukaya², Hai Quan Ho², Satoru Nagasumi², Toshiaki Ishii², Shinpei Hamamoto², Etsuo Ishitsuka² (1. Kyushu Univ., 2. JAEA)

Keywords:high-temperature gas-cooled reactor, HTTR, MVP-BURN, ORIGEN, reflector

As one of the evaluations of the effect of HTGR fuel on the nuclide production and decay behavior, the ORIGEN library was prepared and analyzed using neutron spectra of a simplified graphite-moderated system considering a real core-size reflector region. The results of the ORIGEN library and the burnup calculation of MVP were comparable. From this result, it is necessary to evaluate the neutron spectrum of the fuel region of the graphite-moderated system for the whole core including the reflector region, not for pin cells or block cells.