Fission gas release measurement of reactor fuel rods is one of the main issues of post-irradiation examination, which plays a key role to the evaluation of fuel performance.

反应堆燃料元件的裂变气体释放率测量是辐照后检验的一项重要内容，它对于评价燃料元件的性能起着重要作用。

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Based on an exact mathematic model, a measurement method regarding core thermal power of nuclear power pressurized water reactor and its error analysis were presented in this paper.

通过建立精确的数学模型，提出了一种测量核电站压水反应堆堆芯热功率的方法，并对该方法进行了误差分析。

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The computer system of neutron distribution measurement and data processing in pool type reactor including its principle, method, design and work situation is described.

介绍了某池式研究堆中子通量分布测量及数据的计算机处理原理、方法、开发及工作情况。

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