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RELAP4/MOD7 - A Best Estimate Computer Program to Calculate Thermal and Hydraulic Phenomena in a Nuclear Reactor or Related System, Supplement 1.

机译：RELap4 / mOD7 - 计算核反应堆或相关系统中热和水力现象的最佳估算计算机程序，补编1。

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This supplement consists of new sections to the original Document EGG-2089. They are numbered for appropriate insertion into the original text.

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作者
Behling, S. R.; Hsu, M. T.; Dobbe, C. A.; Fischer, S. R.;
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年度 1981
页码 1-28
总页数 28
原文格式 PDF
正文语种 eng
中图分类工业技术;
关键词
Nuclear reactor safety; Thermal analysis; Hydraulics; RELAP4/MOD7 computer program; Loss of coolant; PWR reactors;

机译：核反应堆安全;热分析;液压系统; RELap4 / mOD7计算机程序;冷却剂损失;压水堆反应堆;

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专利

1. FONESYS: The FOrum & NEtwork of SYStem Thermal-Hydraulic Codes in Nuclear Reactor Thermal-Hydraulics [J] . S.H. Ahn, N. Aksan, H. Austregesilo, Nuclear Engineering and Design . 2015,第jana期

机译：FONESYS：核反应堆热工系统中系统热工代码的主要内容
2. An overview on thermal-hydraulic phenomena for water cooled nuclear reactors; part Ⅱ: ALWRs and SCWRs [J] . Aksan N. Nuclear Engineering and Design . 2019,第Deca期

机译：水冷核反应堆热工现象概述；
3. An overview on thermal-hydraulic phenomena for water cooled nuclear reactors; part Ⅰ: SETs, and ITFs of PWRs, BWRs, VVERs [J] . Aksan N. Nuclear Engineering and Design . 2019,第Deca期

机译：水冷核反应堆热工现象概述；
4. Coupled Calculations Using the Numerical Nuclear Reactor for IntegratedSimulation of Neutronic and Thermal-Hydraulic Phenomena [C] . D. P. Weber, T. Sofu, W. S. Yang, PHYSOR 2004 - the physics of fuel cycles and advanced nuclear systems: global developments . 2004

机译：使用数值核反应堆进行中子和热工-液压现象综合模拟的耦合计算
5. Scaling approach and thermal-hydraulic analysis in the reactor cavity cooling system of a high temperature gas -cooled reactor and thermal-jet mixing in a sodium fast reactor. [D] . Omotowa, Olumuyiwa A. 2014

机译：高温气冷反应堆的反应堆腔冷却系统中的结垢方法和热工水力分析，以及钠快速反应堆中的热喷射混合。
6. A condensed review of nuclear reactor thermal-hydraulic computer codes for two-phase flow analysis [O] . Kazimi Mujid S., Massoud Mahmoud 1980

机译：核反应堆热工水力计算机规范的两阶段流动分析综述
7. RELAP4/MOD7--A Best Estimate Computer Program to Calculate Thermal and Hydraulic Phenomena in a Nuclear Reactor or Related System [R] . Behling, S. R., Jayne, G. A., Tolli, J. E., 1981

机译：RELap4 / mOD7 - 计算核反应堆或相关系统中热和水力现象的最佳估算计算机程序

RELAP4/MOD7 - A Best Estimate Computer Program to Calculate Thermal and Hydraulic Phenomena in a Nuclear Reactor or Related System, Supplement 1.

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