Thermal-hydraulics and safety concepts of supercritical water cooled reactors

被引：12
作者：
Schulenberg, Thomas [1 ]
Visser, Dirk C. [2 ]
机构：
[1] Karlsruhe Inst Technol, Inst Nucl & Energy Technol IKET, D-76021 Karlsruhe, Germany
[2] NRG Safety & Power, NL-1755 ZG Petten, Netherlands
来源：
NUCLEAR ENGINEERING AND DESIGN | 2013年 / 264卷
关键词：
D O I：
10.1016/j.nucengdes.2012.08.040
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：
The paper summarizes the status of safety system development for supercritical water cooled reactors and thermal-hydraulic codes required to analyze them. While active safety systems are well-understood today and expected to perform as required, the development of passive safety systems will still require further optimization. Depressurization transients have successfully been simulated with some codes by a pseudo-two-phase flow simulation of supercritical water. Open issues of thermal-hydraulic codes include modeling of deteriorated heat transfer in one-dimensional system codes and predictions of heat transfer during depressurization transients from supercritical to sub-critical conditions. (C) 2013 Elsevier B.V. All rights reserved.
引用
收藏
页码：231 / 237
页数：7
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