Conceptual study of a Complementary Scram System For Liquid Metal Cooled Nuclear Reactors

Simon Vanmaercke; Gert Van den Eynde; Engelbert Tijskens; Yann Bartosiewicz

Conceptual study of a Complementary Scram System For Liquid Metal Cooled Nuclear Reactors

Simon Vanmaercke, Gert Van den Eynde, Engelbert Tijskens, Yann Bartosiewicz

Research output › peer-review

Abstract

GEN-IV reactors promise higher safety and reliability as one of the major improvements over previous generations of reactors. To achieve that, all GEN-IV reactor concepts require two completely independent shutdown systems that rely on different operating principles. For liquid metal cooled reactors the first system is an absorber-rod based solution. The second system that by requirement should rely on another principle, is however quite a challenge to design. In this presentation an overview of the existing literature on scram systems is given, each with their advantages and limitations . A promising new concept is also presented. The ongoing work conducted at SCK-CEN and UCL/TERM aims at assessing the reliability of this new concept both experimentally and numerically. Some preliminary experimental and DEM simulation results will be presented.

Original language	English
Title of host publication	13th International Topical Meeting on Nuclear Reactor Thermal Hydraulics Proceedings
Place of Publication	Japan
State	Published - 27 Sep 2009
Event	2013 - NURETH: 13th International Topical Meeting on Nuclear Reactor Thermal Hydraulics - Kanazawa Duration: 27 Sep 2009 → 2 Oct 2009

Conference

Conference	2013 - NURETH
Country/Territory	Japan
City	Kanazawa
Period	2009-09-27 → 2009-10-02

Cite this

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title = "Conceptual study of a Complementary Scram System For Liquid Metal Cooled Nuclear Reactors",

abstract = "GEN-IV reactors promise higher safety and reliability as one of the major improvements over previous generations of reactors. To achieve that, all GEN-IV reactor concepts require two completely independent shutdown systems that rely on different operating principles. For liquid metal cooled reactors the first system is an absorber-rod based solution. The second system that by requirement should rely on another principle, is however quite a challenge to design. In this presentation an overview of the existing literature on scram systems is given, each with their advantages and limitations . A promising new concept is also presented. The ongoing work conducted at SCK-CEN and UCL/TERM aims at assessing the reliability of this new concept both experimentally and numerically. Some preliminary experimental and DEM simulation results will be presented.",

keywords = "Scram System Liquid Metal Reactor Safety System Self Actuating",

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AU - Vanmaercke, Simon

AU - Van den Eynde, Gert

AU - Tijskens, Engelbert

AU - Bartosiewicz, Yann

N1 - Score = 3

PY - 2009/9/27

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N2 - GEN-IV reactors promise higher safety and reliability as one of the major improvements over previous generations of reactors. To achieve that, all GEN-IV reactor concepts require two completely independent shutdown systems that rely on different operating principles. For liquid metal cooled reactors the first system is an absorber-rod based solution. The second system that by requirement should rely on another principle, is however quite a challenge to design. In this presentation an overview of the existing literature on scram systems is given, each with their advantages and limitations . A promising new concept is also presented. The ongoing work conducted at SCK-CEN and UCL/TERM aims at assessing the reliability of this new concept both experimentally and numerically. Some preliminary experimental and DEM simulation results will be presented.

AB - GEN-IV reactors promise higher safety and reliability as one of the major improvements over previous generations of reactors. To achieve that, all GEN-IV reactor concepts require two completely independent shutdown systems that rely on different operating principles. For liquid metal cooled reactors the first system is an absorber-rod based solution. The second system that by requirement should rely on another principle, is however quite a challenge to design. In this presentation an overview of the existing literature on scram systems is given, each with their advantages and limitations . A promising new concept is also presented. The ongoing work conducted at SCK-CEN and UCL/TERM aims at assessing the reliability of this new concept both experimentally and numerically. Some preliminary experimental and DEM simulation results will be presented.

KW - Scram System Liquid Metal Reactor Safety System Self Actuating

UR - http://ecm.sckcen.be/OTCS/llisapi.dll/open/ezp_100025

UR - http://knowledgecentre.sckcen.be/so2/bibref/6060

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BT - 13th International Topical Meeting on Nuclear Reactor Thermal Hydraulics Proceedings

CY - Japan

T2 - 2013 - NURETH

Y2 - 27 September 2009 through 2 October 2009

ER -