Xenon poisoning calculation code for miniature neutron source reactor (MNSR)

KE Guo-Tu，

LI Zhun-Jie，

XU Han-Ming

Nuclear Science and Techniques

Vol.12, No.2

pp.135-142

Published in print 01 May 2001

CLC：TL411+.7, TL36

20400

In line with the actual requirements and based upon the specific characteristics of MNSR, a revised point-reactor model was adopted to model MNSR's xenon poisoning. The corresponding calculation code, MNSRXPCC (Xenon Poisoning Calculation Code for MNSR), was developed and tested by the Shanghai MNSR data.

Miniature neutron source reactor (MNSR)Xenon poisoning

References

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Fowler T B, Vondy D R et al. Nuclear Reactor Core Analysis Code:CITATION, ORNL-TM-2496, Rev.2, July 1971.

Guo Chengzhan et al.

Safety analysis report for miniature neutron source reactor (MNSR), CIAE report

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