core thermal design 堆芯热工设计
core thermal power 堆芯热功率
Unified thermal core 统一散热架构
reactor thermal core 反应堆堆心
thermal core 热中子活性区
core physical-thermal calculation 堆芯物理热工计算
GNPS begins to implement the 18-month fuel cycles from the initial annual reload at cycle 9, thus the initial core thermal hydraulic design is not valid any more.
大亚湾核电站从第九循环开始由年换料向18个月换料转换，使得原堆芯热工水力设计不再适用。
They are the natural circulation flow analysis code (MC-FLOW), the core thermal hydraulic analysis code (MC-THAS) and the pulsed reactor transient analysis code (MC-TRAN).
它包括脉冲堆自然循环分析程序（MC-FLOW）、堆芯热工水力分析程序（MC-THAS）和脉冲堆瞬态分析程序（MC-TRAN）。
The PWR core thermal-hydraulic design, including the design objective, criteria and main design parameters, specifically that for the Qin-Shan Nuclear Power Plant is described.
本文介绍了压水堆堆芯的热工-水力设计，其中包括了设计任务、准则和主要设计参数，并对秦山核电厂的热工和水力设计作了较详细的描述。
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