由于临界热流密度(CHF)与反应堆安全密切相关，所以人们从实验和理论上都已经对该现象进行了广泛的研究。
Considering the relationship between the phenomena of critical heat flux (CHF) and the safety of nuclear reactor, the research of CHF on experiment and theory has been carried in detail.
计算结果表明，该装置的堆芯布置满足临界和控制要求，能够满足乏燃料临界实验的需求。
The result indicates that the reactor core arrangement satisfies the critical and control request, and can meet the purpose of spent fuel critical experiments.
MW高温气冷实验堆（HTR- 10 ）于2 0 0 0年底在中国建成并实现临界，是一项重大的科研成果。
The 10 MW high temperature gas cooled reactor (HTR 10) reached critical in the end of 2000 in China.
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