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

S. Wang, M. Flad, W. Maschek, P. Agostini, D. Pellini, G. Bandini, T. Suzuki, K. Morita

研究成果: Contribution to journalArticle査読

25 被引用数 (Scopus)

抄録

A postulated steam generator tube rupture (SGTR) accident in a lead cooled accelerator driven transmuter (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.

本文言語英語
ページ(範囲)363-369
ページ数7
ジャーナルProgress in Nuclear Energy
50
2-6
DOI
出版ステータス出版済み - 3 2008

All Science Journal Classification (ASJC) codes

  • Nuclear Energy and Engineering
  • Safety, Risk, Reliability and Quality
  • Energy Engineering and Power Technology
  • Waste Management and Disposal

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