紧急停堆
锅炉给水
编码(集合论)
计算机科学
瞬态(计算机编程)
体积热力学
冷却液
压水堆
失水事故
控制棒
核工程
源代码
工程类
机械工程
涡轮机
热力学
程序设计语言
物理
集合(抽象数据类型)
作者
S.M. Sloan,Richard R. Schultz,G.E. Wilson
摘要
The RELAP5 code has been developed for best-estimate transient simulation of light water reactor coolant systems during a severe accident. The code models the coupled behavior of the reactor coolant system and the core during the severe accident transient, as well as large and small break loss-of-coolant accidents and operational transients, such as anticipated transients without scram, loss of offsite power, loss of feedwater, and loss of flow. A generic modeling approach is used that permits as much of a particular system to be modeled as necessary. Control system and secondary system components are included to permit modeling of plant controls, turbines, condensers, and secondary feedwater conditioning systems. RELAP5/MOD3 code documentation is divided into five volumes: Volume 1 describes modeling theory and associated numerical schemes, Volume 2 contains detailed instructions for code application and input data preparation, Volume 3 provides the results of developmental assessment cases that demonstrate and verify the models used in the code, and Volume 4 presents a detailed discussion of RELAP5 models and correlations. Volumes 1--4 are in varying stages of development. This document, Volume 5, contains guidelines that have evolved over the past several years through use of the RELAP5 code.
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