秦山核电二期工程堆芯测量系统采用计算机技术实现了对相关数据的自动采集、数据处理和信息显示。
With computer technology, the in-core instrumentation system of Qinshan phase II nuclear power plant can automatically perform parameter acquisition, data process and information display.
此测量方法已通过实验验证，并得到了用于计算堆芯冷却剂出口温度的经验公式。
This measuring method has been tested by experiments, an empirical formula is for evaluating the core coolant temperature has been obtained.
堆芯出口热气混合实验用于测量和分析该混流结构的混合性能及其阻力特性。
A hot gas mixing experiment of outlet of HTR-PM reactor core was proposed to measure and analyze the actual mixing performance and resistance property of this mixing structure.
计算了西安脉冲堆堆芯热工参数，并进行了堆芯温度场测量实验。
The experiment to measure the temperature field distribution in XAPR core has been carried out.
介绍了大亚湾核电站堆芯换料设计准则、计算机程序、设计内容以及设计预计值与测量值的比较。
The design criteria, codes, basic principles and contents of the reload design for Daya Bay Nuclear Power Station are briefly introduced.
介绍了大亚湾核电站堆芯换料设计准则、计算机程序、设计内容以及设计预计值与测量值的比较。
The design criteria, codes, basic principles and contents of the reload design for Daya Bay Nuclear Power Station are briefly introduced.
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