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. © 2007 Elsevier Ltd. All rights reserved.
All Science Journal Classification (ASJC) codes
- Energy Engineering and Power Technology
- Nuclear Energy and Engineering
Wang, S., Flad, M., Maschek, W., Agostini, P., Pellini, D., Bandini, G., ... Morita, K. (2008). Evaluation of a steam generator tube rupture accident in an accelerator driven system with lead cooling. Progress in Nuclear Energy, 50(2-6), 363 - 369. https://doi.org/10.1016/j.pnucene.2007.11.018