TY - JOUR
T1 - Design of a complementary scram system for liquid metal cooled nuclear reactors
AU - Vanmaercke, Simon
AU - Van den Eynde, Gert
AU - Tijskens, Engelbert
AU - Bartosiewicz, Yann
A2 - Aït Abderrahim, Hamid
N1 - SCORE=10
PY - 2012/2
Y1 - 2012/2
N2 - Generation IV (GEN IV) reactors promise higher safety levels compared to current generation II or III reactors, one of the most important safety aspects of any reactor is the ability to shutdown the reactor in any condition. The shutdown mechanism in current designs of liquid metal cooled Gen IV reactors is based on absorber rods. Although these rod based systems are duplicated to provide redundancy, they all have a common mode of failure as a consequence of their identical operating mechanism; possible causes being a largely deformed core or blockage of the rod guidance channel. To achieve the goal of higher safety, a complementary scram system is desirable. In this paper an overview of existing solutions of such a complementary system is given and a new concept based on absorber particles and the existing solutions is proposed. This original system, which is not rod based, is under investigation and its feasibility is verified both by experiments and simulations.
AB - Generation IV (GEN IV) reactors promise higher safety levels compared to current generation II or III reactors, one of the most important safety aspects of any reactor is the ability to shutdown the reactor in any condition. The shutdown mechanism in current designs of liquid metal cooled Gen IV reactors is based on absorber rods. Although these rod based systems are duplicated to provide redundancy, they all have a common mode of failure as a consequence of their identical operating mechanism; possible causes being a largely deformed core or blockage of the rod guidance channel. To achieve the goal of higher safety, a complementary scram system is desirable. In this paper an overview of existing solutions of such a complementary system is given and a new concept based on absorber particles and the existing solutions is proposed. This original system, which is not rod based, is under investigation and its feasibility is verified both by experiments and simulations.
KW - Secondary SCRAM system
KW - DEM
KW - GEN IV
UR - http://ecm.sckcen.be/OTCS/llisapi.dll/open/ezp_120867
UR - http://knowledgecentre.sckcen.be/so2/bibref/9025
U2 - 10.1016/j.nucengdes.2011.12.007
DO - 10.1016/j.nucengdes.2011.12.007
M3 - Article
SN - 0029-5493
VL - 243
SP - 87
EP - 94
JO - Nuclear Engineering and Design
JF - Nuclear Engineering and Design
ER -