压水堆堆芯稳态单通道热工计算

The Stable Single Channel Thermal Calculation for Pressurized Water Reactor Core

本文通过对六控制体压水堆堆芯单通道热工计算及模拟,发现:1) 燃料棒包壳温度在第四控制体出现峰值;2) 燃料芯块外壁及中心温度最大值出现在第四控制体;3) 最小烧毁比在第四控制体。这些结果显示在压水堆运行安全监控中,对温度的监测重点应放在第四控制体。本文计算及模拟结果可为反应堆热工设计及堆芯温度校核提供一个参考。

The heat transfer in the pressurized water reactor (PWR) core, which is divided into six control volumes, is investigated by stable single channel calculation and simulation. It is concluded that: 1) Temperature peak of fuel cladding arises in the fourth control volume;2) The maximum temperatures of the outer and center fuel pellets appear in the fourth control volume;3) The minimum departure from nucleate boiling ratio (DNBR) also appears in the fourth control volume. These results suggest that the key of temperature monitoring should be in the fourth control volume in the PWR operation. This phenomenon may provide a reference for the thermal design of reactor and the check of core temperature.