TY - JOUR
T1 - Improved core design of the high temperature supercritical-pressure light water reactor
AU - Yamaji, A.
AU - Kamei, K.
AU - Oka, Y.
AU - Koshizuka, S.
PY - 2005/5
Y1 - 2005/5
N2 - A new coolant flow scheme has been devised to raise the average coolant core outlet temperature of the High Temperature Supercritical-Pressure Light Water Reactor (SCLWR-H). A new equilibrium core is designed with this flow scheme to show the feasibility of an SCLWR-H core with an average coolant core outlet temperature of 530 °C. In previous studies, the average coolant core outlet temperature was limited by the relatively low temperature outlet coolant from the core periphery. In order to achieve an average coolant core outlet temperature of 500 °C, each fuel assembly had to be horizontally divided into four sub-assemblies by coolant flow separation plates, and coolant flow rate had to be adjusted for each sub-assembly by an inlet orifice. However, the difficulty of raising the outlet coolant temperature from the core periphery remained. In this study, a new coolant flow scheme is devised, in which the fuel assemblies loaded on the core periphery are cooled by a descending flow. The new flow scheme has eliminated the need for raising the outlet coolant temperature from the core periphery and removed the coolant flow separation plates from the fuel assemblies.
AB - A new coolant flow scheme has been devised to raise the average coolant core outlet temperature of the High Temperature Supercritical-Pressure Light Water Reactor (SCLWR-H). A new equilibrium core is designed with this flow scheme to show the feasibility of an SCLWR-H core with an average coolant core outlet temperature of 530 °C. In previous studies, the average coolant core outlet temperature was limited by the relatively low temperature outlet coolant from the core periphery. In order to achieve an average coolant core outlet temperature of 500 °C, each fuel assembly had to be horizontally divided into four sub-assemblies by coolant flow separation plates, and coolant flow rate had to be adjusted for each sub-assembly by an inlet orifice. However, the difficulty of raising the outlet coolant temperature from the core periphery remained. In this study, a new coolant flow scheme is devised, in which the fuel assemblies loaded on the core periphery are cooled by a descending flow. The new flow scheme has eliminated the need for raising the outlet coolant temperature from the core periphery and removed the coolant flow separation plates from the fuel assemblies.
UR - http://www.scopus.com/inward/record.url?scp=16244380834&partnerID=8YFLogxK
UR - http://www.scopus.com/inward/citedby.url?scp=16244380834&partnerID=8YFLogxK
U2 - 10.1016/j.anucene.2004.12.006
DO - 10.1016/j.anucene.2004.12.006
M3 - Article
AN - SCOPUS:16244380834
SN - 0306-4549
VL - 32
SP - 651
EP - 670
JO - Annals of Nuclear Energy
JF - Annals of Nuclear Energy
IS - 7
ER -