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

核エネルギーシステム学

研究成果: ジャーナルへの寄稿 › 学術誌 › 査読

36 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
巻	50
号	2-6
DOI	https://doi.org/10.1016/j.pnucene.2007.11.018
出版ステータス	出版済み - 3月 2008

!!!All Science Journal Classification (ASJC) codes

原子力エネルギーおよび原子力工学
安全性、リスク、信頼性、品質管理
エネルギー工学および電力技術
廃棄物管理と処理

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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.",

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

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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

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!!!All Science Journal Classification (ASJC) codes

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