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

doi:10.1016/j.pnucene.2007.11.018

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

Nuclear Energy Systems

Research output: Contribution to journal › Article › peer-review

34 Citations (Scopus)

Abstract

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.

Original language	English
Pages (from-to)	363-369
Number of pages	7
Journal	Progress in Nuclear Energy
Volume	50
Issue number	2-6
DOIs	https://doi.org/10.1016/j.pnucene.2007.11.018
Publication status	Published - Mar 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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10.1016/j.pnucene.2007.11.018

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

abstract = "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.",

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AU - Wang, S.

AU - Flad, M.

AU - Maschek, W.

AU - Agostini, P.

AU - Pellini, D.

AU - Bandini, G.

AU - Suzuki, T.

AU - Morita, K.

N1 - Funding Information: The authors appreciate the efforts and support of all the scientists and institutions involved in EUROTRANS and the presented work, as well as the financial support of the European Commission through the contract FI6W-CT-2004-516520.

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AB - 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.

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

Abstract

All Science Journal Classification (ASJC) codes

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