Nuclear Science and Techniques ›› 2001, Vol. 12 ›› Issue (2):
KE Guo-Tu1, LI Zhun-Jie2, XU Han-Ming1
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.
Miniature neutron source reactor (MNSR),
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