热工水力学
中子输运
增压室空间
流量(数学)
机械
传热
计算机科学
核反应堆
代表(政治)
流体力学
应用数学
状态方程
质量守恒
编码(集合论)
压水堆
稳态(化学)
水力学
核工程
热力学
数学
物理
化学
工程类
核物理学
中子
集合(抽象数据类型)
程序设计语言
法学
物理化学
政治
政治学
作者
Joseph M. Kelly,Charles W. Stewart,Judith M. Cuta
摘要
The VIPRE-02 code is a thermal-hydraulic analysis code designed to model steady-state conditions and operational transients in light water reactor cores and vessels. It uses a two-fluid representation of two-phase flow that solves conservation equations for mass, momentum, and energy for each phase. The code uses a subchannel formulation of the conservation equations but also contains an optional three-dimensional (r-θ coordinates) representation of the lower plenum for vessel modeling. The six-equation formulation is solved implicitly, by a modified Gauss-Seidel iteration procedure, and has no time step size limitation for stability. Models for phase interaction based on flow regime mapping are provided that use empirical models and correlations for heat and mass transfer at the interface and vapor generation. In addition, the code contains as an option a dynamic flow regime model, which uses an interfacial area transport equation to determine the phase interaction terms.
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