TY - GEN
T1 - Decay heat removal from a GFR core by natural convection
AU - Williams, Wesley C.
AU - Hejzlar, Pavel
AU - Driscoll, Michael J.
PY - 2004
Y1 - 2004
N2 - One of the primary challenges for Gas-cooled Fast Reactors (GFR) is decay heat removal after a loss of coolant accident (LOCA). Due to the fact that thermal gas cooled reactors currently under design rely on passive mechanisms to dissipate decay heat, there is a strong motivation to accomplish GFR core cooling through natural phenomena. This work investigates the potential of post-LOCA decay heat removal from a GFR core to a heat sink using an external convection loop. A model was developed in the form of the LOCA-COLA (Loss of Coolant Accident - Convection Loop Analysis) computer code as a means for ID steady state convective heat transfer loop analysis. The results show that decay heat removal by means of gas cooled natural circulation is feasible under elevated post-LOCA containment pressure conditions.
AB - One of the primary challenges for Gas-cooled Fast Reactors (GFR) is decay heat removal after a loss of coolant accident (LOCA). Due to the fact that thermal gas cooled reactors currently under design rely on passive mechanisms to dissipate decay heat, there is a strong motivation to accomplish GFR core cooling through natural phenomena. This work investigates the potential of post-LOCA decay heat removal from a GFR core to a heat sink using an external convection loop. A model was developed in the form of the LOCA-COLA (Loss of Coolant Accident - Convection Loop Analysis) computer code as a means for ID steady state convective heat transfer loop analysis. The results show that decay heat removal by means of gas cooled natural circulation is feasible under elevated post-LOCA containment pressure conditions.
UR - http://www.scopus.com/inward/record.url?scp=10644296539&partnerID=8YFLogxK
M3 - Conference contribution
AN - SCOPUS:10644296539
SN - 0894486802
SN - 9780894486807
T3 - Proceedings of the 2004 International Congress on Advances in Nuclear Power Plants, ICAPP'04
SP - 624
EP - 636
BT - Proceedings of the 2004 International Congress on Advances in Nuclear Power Plants, ICAPP'04
T2 - Proceedings of the 2004 International Congress on Advances in Nuclear Power Plants, ICAPP'04
Y2 - 13 June 2004 through 17 June 2004
ER -