Nuclear Science and Techniques

《核技术》(英文版) ISSN 1001-8042 CN 31-1559/TL     2019 Impact factor 1.556

Nuclear Science and Techniques ›› 2001, Vol. 12 ›› Issue (2): 135

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

KE Guo-Tu1, LI Zhun-Jie2, XU Han-Ming1   

  1. 1 China Institute of Atomic Energy, Beijing, 102413;
    2 Raoyan No. 2 Middle School of Hebei Province, Raoyan, 053827
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KE Guo-Tu, LI Zhun-Jie, XU Han-Ming. Xenon poisoning calculation code for miniature neutron source reactor (MNSR).Nuclear Science and Techniques, 2001, 12(2): 135

Abstract: 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 Poison ing Calculation Code for MNSR), was developed and tested by the Shanghai MNSR. data.

Key words: Miniature neutron source reactor (MNSR), Xenon poisoning