POSTCHF——临界热流密度后传热区广义二维计算模型  

POSTCHF——A TWO-DIMENSION GENERIZED ANALYTICAL MODEL DURING POST-CHF REGION

作　　者：杨燕华[1] 徐济鋆[1] 

机构地区：[1]上海交通大学

出　　处：《核科学与工程》1993年第3期193-203,5,共11页Nuclear Science and Engineering

基　　金：国家教委科学基金

摘　　要：核动力反应堆失水事故或超功率暂态工况下,常会发生临界热流密度后的传热模式,其主要流型为弥散流和反环状流,这引起核安全研究界的广泛关注。经验方法不能很好地模拟各种工况范围及流型内部各种参数的分布及变化,随着实验技术和计算方法的发展,正在开发较为精确的二维计算模型。作者在多年的实验和理论研究基础上,发展了弥散流和反环状流的广义二维数学模型POSTCHF,并开发了计算程序。本文详细介绍该模型的基本守恒方程、本构关系式、网格划分、数值方法和计算结果。A generized two-dimensional analytical model and a computer code POSTCHF for both dispersed flow and inverted annular flow during post-CHF region have been developed. The model was based on the basic two-phase conservation equations and related constitutional correlations. The basic idea and mathematical model are presented in this paper. It was concluded from the calculation that the initial droplet size in dispered flow has strong influence on wall temperature, but the initial film thickness in inverted annular flow has been found less infenencing. The Tatterson annular droplet model and the turblenct coefficient C_v= 0. 55-0.62 were used with which the results were agreed well with the experimental data.

关 键 词：传热 二相流动 反应堆安全 

分 类 号：TL364.1[核科学技术—核技术及应用]