TY - GEN
T1 - Thermal-hydraulic analyses of the LS-VHTR
AU - Davis, Cliff B.
AU - Hawkes, Grant L.
PY - 2006
Y1 - 2006
N2 - Thermal-hydraulic analyses were performed to evaluate the safety characteristics of the Liquid-Salt-Cooled Very High-Temperature Reactor (LS-VHTR). A one-dimensional model of the LS-VHTR was developed using the RELAP5-3D computer program. The thermal calculations from the one-dimensional model of a fuel block were benchmarked against a multi-dimensional finite element model. The RELAP5-3D model was used to simulate a transient initiated by loss of forced convection in which the Reactor Vessel Auxiliary Cooling System (RVACS) passively removed decay heat. Parametric calculations were performed to investigate the effects of various parameters, including bypass flow fraction, coolant channel diameter, and the coolant outlet temperature. Additional parametric calculations investigated the effects of an enhanced RVACS design, failure to scram, and radial/axial conduction in the core.
AB - Thermal-hydraulic analyses were performed to evaluate the safety characteristics of the Liquid-Salt-Cooled Very High-Temperature Reactor (LS-VHTR). A one-dimensional model of the LS-VHTR was developed using the RELAP5-3D computer program. The thermal calculations from the one-dimensional model of a fuel block were benchmarked against a multi-dimensional finite element model. The RELAP5-3D model was used to simulate a transient initiated by loss of forced convection in which the Reactor Vessel Auxiliary Cooling System (RVACS) passively removed decay heat. Parametric calculations were performed to investigate the effects of various parameters, including bypass flow fraction, coolant channel diameter, and the coolant outlet temperature. Additional parametric calculations investigated the effects of an enhanced RVACS design, failure to scram, and radial/axial conduction in the core.
UR - https://www.scopus.com/pages/publications/33845763912
M3 - Conference contribution
AN - SCOPUS:33845763912
SN - 0894486985
SN - 9780894486982
T3 - Proceedings of the 2006 International Congress on Advances in Nuclear Power Plants, ICAPP'06
SP - 672
EP - 681
BT - Proceedings of the 2006 International Congress on Advances in Nuclear Power Plants, ICAPP'06
T2 - American Nuclear Society Embedded Topical Meeting - 2006 International Congress on Advances in Nuclear Power Plants, ICAPP'06
Y2 - 4 June 2006 through 8 June 2006
ER -