程序中还引入停堆保护计算模块以模拟反应堆事故停堆后的运行工况。
The function of reactor shutdown system can be simulated by the code to calculate the operating parameters after accidental shutdown.
证明该二配套程序可用于反应堆设计计算。
Therefore. This matching codes is applicable for reactor designs.
简要介绍了加拿大原子能公司（AECL）目前用于CANDU 反应堆物理设计和分析的计算机程序和方法。
This paper presents an overview of the physics codes and methods that are in current use at AECL for physics design and analysis of CANDU reactors.
本文介绍了CPWR640反应堆的核设计准则、堆芯特性与主要参数，并给出了堆芯核设计的主要计算机程序、计算结果及分析。
The paper presents the nuclear design criterion, reactor core characteristics and main parameters, and shows some computer codes, calculation results and analyses.
本文介绍了CPWR640反应堆的核设计准则、堆芯特性与主要参数，并给出了堆芯核设计的主要计算机程序、计算结果及分析。
The paper presents the nuclear design criterion, reactor core characteristics and main parameters, and shows some computer codes, calculation results and analyses.
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