首页> 中文期刊> 《原子能科学技术》 >瞬态工况下压水堆稳压器波动管热分层现象数值模拟

瞬态工况下压水堆稳压器波动管热分层现象数值模拟

         

摘要

T he thermal stratification under transient condition in pressurizer surge line of Qinshan Phase Ⅱ extension nuclear power project (2 × 650 MW PWR generator 4) was investigated by computational fluid dynamics program ANSYS/CFX .The whole and cross‐sectional thermal stratification transient analysis models for the pressurizer surge line were established ,and the heat stratified flow and heat transfer of the surge line were studied .The way of temperature growth is different between high‐and low‐temperature fluid layers in the same cross section . T he fluid temperature distribution has great difference in different cross sections , but the temperature difference first increases and then decreases in every cross section .The research results can provide a basis for subsequent analysis of thermal stress and lifespan .%利用计算流体动力学软件ANSYS/CFX ,对秦山核电二期扩建工程2×650 MW压水堆核电站四号机组核岛厂房的稳压器波动管进行了三维全尺寸非稳态计算。建立了波动管整体和不同截面的热分层瞬态,对管内热分层流动与换热进行了研究。研究结果表明:同一截面内高温层流体和低温层流体的升温方式不同;不同截面位置的管内流动温度分布特性差别较大,但均呈现分层流体温差先增大后减小的趋势。计算结果可为后续波动管热应力分析及寿命评价提供一定基础。

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