[2D01-05] Analysis Code Development

[2D01] Study of ORIGEN library preparation method for high temperature gas cooled reactors

Katuki Fukuhara¹, *Nozomu Fujimoto¹, Irwan Liapto Simanullang¹, Yuuji Fukaya², Hai Quan Ho², Satoru Nagazumi², Toshiaki Ishii², Shimpei Hamamoto², Etuo Isihituka² (1. Kyushu University, 2. JAEA)

Keywords:HTGR, Fuel, Burnup, Monte Carlo

In order to establish the evaluation method of nuclide burnup behavior in HTGR fuels, an ORIGEN libraries preparation method for the HTTR has been studied. It has been clarified that it is necessary to prepare libraries based on neutron spectrum from the whole core calculation. In this study, libraries based on the evaluation were prepared. The validation of the libraries was evaluated by comparing an ORIGEN burnup results with the Monte Carlo burnup results.