TY - JOUR
T1 - Three-dimensional core design of high temperature supercritical-pressure light water reactor with neutronic and thermal-hydraulic coupling
AU - Yamaji, Akifumi
AU - Oka, Yoshiaki
AU - Koshizuka, Seiichi
PY - 2005/1
Y1 - 2005/1
N2 - The equilibrium core of the High Temperature Supercritical-Pressure Light Water Reactor (SCLWR-H) is designed by three-dimensional neutronic and thermal-hydraulic coupled core calculations. The average coolant core outlet temperature of 500°C is accurately evaluated for the first time in the development of the SCLWR-H. The average coolant core outlet temperature is one of the key parameters, which must be accurately determined in order to establish the concept of this unique reactor design. However, it can only be determined by three-dimensional core design method, taking into account the control rod patterns, fuel loading patterns, coupling of the neutronic and thermal-hydraulic calculations, and burnup distribution of each fuel assembly. The R—Z two-dimensional core design method used in previous studies could not model or evaluate such parameters with sufficient accuracy. In this study, a three-dimensional equilibrium core design method for the SCLWR-H is established. This method can accurately evaluate the average coolant core outlet temperature and has permitted a comprehensive equilibrium core to be developed, which satisfies all design criteria. The design criteria are maximum fuel rod cladding surface temperature of 650°C, maximum linear heat generation rate of 39 kW/m, and a positive water density reactivity coefficient.
AB - The equilibrium core of the High Temperature Supercritical-Pressure Light Water Reactor (SCLWR-H) is designed by three-dimensional neutronic and thermal-hydraulic coupled core calculations. The average coolant core outlet temperature of 500°C is accurately evaluated for the first time in the development of the SCLWR-H. The average coolant core outlet temperature is one of the key parameters, which must be accurately determined in order to establish the concept of this unique reactor design. However, it can only be determined by three-dimensional core design method, taking into account the control rod patterns, fuel loading patterns, coupling of the neutronic and thermal-hydraulic calculations, and burnup distribution of each fuel assembly. The R—Z two-dimensional core design method used in previous studies could not model or evaluate such parameters with sufficient accuracy. In this study, a three-dimensional equilibrium core design method for the SCLWR-H is established. This method can accurately evaluate the average coolant core outlet temperature and has permitted a comprehensive equilibrium core to be developed, which satisfies all design criteria. The design criteria are maximum fuel rod cladding surface temperature of 650°C, maximum linear heat generation rate of 39 kW/m, and a positive water density reactivity coefficient.
KW - Average coolant core outlet temperature
KW - Equilibrium core
KW - Generation IV reactor
KW - Light water cooling
KW - Neutronic and thermal-hydraulic coupling
KW - Once-through direct cycle
KW - Supercritical-pressure
KW - Thermal reactor
KW - Three-dimensional core calculations
UR - http://www.scopus.com/inward/record.url?scp=14844363454&partnerID=8YFLogxK
UR - http://www.scopus.com/inward/citedby.url?scp=14844363454&partnerID=8YFLogxK
U2 - 10.1080/18811248.2005.9726359
DO - 10.1080/18811248.2005.9726359
M3 - Article
AN - SCOPUS:14844363454
SN - 0022-3131
VL - 42
SP - 8
EP - 19
JO - Journal of Nuclear Science and Technology
JF - Journal of Nuclear Science and Technology
IS - 1
ER -