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.
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。
3
The computer system of neutron distribution measurement and data processing in pool type reactor including its principle, method, design and work situation is described.