Transient Thermal-hydraulic Analysis of a Scaled Down Test Loop for the VVER-1000 Reactor using RELAP5 Code

被引：0
|
作者：
Khonsha, Babak [1 ]
Jahanfarnia, Gholamreza [1 ]
Sepanloo, Kamran [2 ]
Nematollahi, Mohammadreza [3 ]
机构：
[1] Islamic Azad Univ, Dept Nucl Engn, Sci & Res Branch, Tehran, Iran
[2] Atom Energy Org Iran, Res Inst, Nucl Sci & Technol, Tehran, Iran
[3] Shiraz Univ, Sch Mech Engn, Shiraz, Iran
来源：
ATW-INTERNATIONAL JOURNAL FOR NUCLEAR POWER | 2020年 / 65卷 / 11-12期
关键词：
REDUCED-PRESSURE; TEST FACILITY; SINGLE-PHASE; SCALING LAWS; HEIGHT; SYSTEM;
D O I：
暂无
中图分类号：
TL [原子能技术]; O571 [原子核物理学];
学科分类号：
0827 ; 082701 ;
摘要：
引用
收藏
页码：595 / 602
页数：8
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