Evaluation of a steam generator tube rupture accident in an accelerator driven system with lead cooling

被引：37
|
作者：
Wang, S. [1 ]
Flad, M. [2 ]
Maschek, W. [1 ]
Agostini, P. [3 ]
Pellini, D. [3 ]
Bandini, G. [3 ]
Suzuki, T. [4 ]
Morita, K. [5 ]
机构：
[1] Forschungszentrum Karlsruhe, IKET, D-76021 Karlsruhe, Germany
[2] ProSci, D-76275 Ettlingen, Germany
[3] Ente Nuove Tecnol Energia & Ambiente ENEA, I-40129 Bologna, Italy
[4] JAEA, Reactor Safety Engn Grp, Oarai, Ibaraki, Japan
[5] Kyushu Univ, Grad Sch Engn, Inst Environm Syst, Fukuoka 81, Japan
来源：
PROGRESS IN NUCLEAR ENERGY | 2008年 / 50卷 / 2-6期
关键词：
steam generator tube rupture accident; accelerator driven transmuter; coolant-coolant interaction; EFIT;
D O I：
10.1016/j.pnucene.2007.11.018
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：
A postulated steam generator tube rupture (SGTR) accident in a lead cooled accelerator driven transmitter (ADT) is investigated. The design of the ADT without intermediate loops bears the risk of water/steam blasting into the primary coolant. As a consequence a nuclear power excursion could be triggered by steam ingress into the ADT core which has a significant positive void worth. A thermal coolant-coolant interaction (CCI) might initiate a local core voiding too and additionally could lead to sloshing of the lead pool with mechanical impact of the heavy liquid on structures. The steam formation will also lead to a pressurization of the cover gas. The problems related to an SGTR are identified and investigated with the SIMMER-III accident code. (C) 2007 Elsevier Ltd. All rights reserved.
引用
收藏
页码：363 / 369
页数：7
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