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蒸汽发生器传热管束过冷沸腾区两相流动数值模拟

王成龙 丛腾龙 田文喜 秋穗正 苏光辉

原子能科学技术Issue(8):1392-1397,6.
原子能科学技术Issue(8):1392-1397,6.DOI:10.7538/yzk.2014.48.08.1392

蒸汽发生器传热管束过冷沸腾区两相流动数值模拟

Numerical Simulation of Two-phase Flow in Subcooled Boiling Region of Steam Generator

王成龙 1丛腾龙 1田文喜 1秋穗正 1苏光辉1

作者信息

  • 1. 西安交通大学 能源与动力工程学院,陕西 西安 710049
  • 折叠

摘要

Abstract

Based on two fluid Euler model combining with RPI wall boiling model ,the coupled heat transfer among the primary side ,the tube wall and the secondary side in the subcooled boiling region of the heat transfer tube bundle of steam generator (SG) was simulated by using ANSYS CFX 12.0 code .The flow boiling phenomenon occurred in the heat transfer tube bundle of SG under trefoil orifice plate and different inlet subcooling conditions was researched . The velocity and temperature distributions of both the primary and the secondary sides ,the void fraction distribution of the secondary side ,the local flow characteristics around trefoil orifice plate ,and the effect of different inlet subcoolings on thermal-hydraulic characteristics of SG were acquired .Numerical simulated results show that the existence of trefoil orifice plate and inlet subcooling have a significant influence on thermal-hydraulic characteristics in the subcooled boiling region of the tube bundle of SG .

关键词

蒸汽发生器/两相流动/梅花孔支撑板/入口过冷度

Key words

steam generator/two-phase flow/trefoil orifice plate/inlet subcooling

分类

能源科技

引用本文复制引用

王成龙,丛腾龙,田文喜,秋穗正,苏光辉..蒸汽发生器传热管束过冷沸腾区两相流动数值模拟[J].原子能科学技术,2014,(8):1392-1397,6.

基金项目

国家杰出青年科学基金资助项目 ()

原子能科学技术

OA北大核心CSCDCSTPCD

1000-6931

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