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作 者:MAO Yu-long, ZHAO Ai-hu, CHEN Yu-zhou
出 处:《Annual Report of China Institute of Atomic Energy》2007年第1期170-170,共1页中国原子能科学研究院年报(英文版)
摘 要:The In-hospital neutron irradiator is a modified miniature neutron source reactor (MNSR) with coolant of de-ion water in natural circulation. A numerical simulation of the flow and heat transfer inThe In-hospital neutron irradiator is a modified miniature neutron source reactor (MNSR) with coolant of de-ion water in natural circulation. A numerical simulation of the flow and heat transfer in this nuclear facility is made using computational fluid dynamic code. The calculation is verified by an integral simulation test with scaling ratio of 1 : 1 and uniform heating, suggesting the predictive capability of the code for the thermal hydraulic behavior in this natural circulation.
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