The fission product poisoning and burnup calculation for IHNI－1 reactor based on coupled codeof MCNP-ORIGEN

Strategic Study of CAE ›› 2012, Vol. 14 ›› Issue (8) : 69 -71.

Zhang Xinyi,Zhao Zhumin,Jiang Xinbiao,Guo Hewei,Chen Lixin,Zhou Yongmao

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Abstract

To calculate the fission product poisoning and burnup of the reactor accurately, the paper sets up the coupled calculation methods based on MCNP code and ORIGEN2 code and program data translation, cross section revision and date interface codes. Making use of elaborate reactor model to calculate the fission product poisoning and burnup for in-hospital neutron irradiator mark 1 reactor.

Keywords

IHNI-1 / MCNP / ORIGEN2 / burnup

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Zhang Xinyi,Zhao Zhumin,Jiang Xinbiao,Guo Hewei,Chen Lixin,Zhou Yongmao. The fission product poisoning and burnup calculation for IHNI－1 reactor based on coupled codeof MCNP-ORIGEN. Strategic Study of CAE, 2012, 14(8): 69-71 DOI: