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

页码：363 / 369

页数：7

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