2012, Volume 14, Issue 8
Strategic Study of CAE >> 2012, Volume 14, Issue 8
The fission product poisoning and burnup calculation for IHNI－1 reactor based on coupled codeof MCNP-ORIGEN
1. Northwest Institute of Nuclear Technology, Xi'an 710024, China;
2. China Zhongyuan Engineering Corporation, China National Nuclear Corporation, Beijing 100191, China
Next Previous
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.
Figures
图1
京公网安备 11010502051620号
