TY - JOUR
T1 - Preliminary design study of a board type radial fuel shuffling sodium cooled breed and burn reactor core
AU - Zheng, Meiyin
AU - Tian, Wenxi
AU - Chu, Xiao
AU - Zhang, Dalin
AU - Qiu, Suizheng
AU - Su, Guanghui
N1 - Publisher Copyright:
© 2014 Elsevier B.V.
PY - 2014/10/15
Y1 - 2014/10/15
N2 - In this paper, a preliminary board type radial fuel shuffling sodium cooled breed and burn reactor core is designed. In the current design, a number of breeding subassemblies are arranged in the center core to ensure enough breeding. A self-developed MCNP-ORIGEN coupled system with the ENDF/B-VI data library is applied to perform neutronics and burn-up calculations. For a 2.0 m radius and 2.5 m height core, the results demonstrate the feasibility of the board type radial fuel shuffling strategy. Breeding mainly occurs in the breeding subassemblies during the first 6 fuel cycles as they are moved to the burning/breeding region. The core will become asymptotically stable after about 24 years. The discharged burn-up of most subassemblies is about 15.0-30.0%. The influences of the core size on the major core parameters, such as initial keff, steady keff, maximum power density, peak burn-up and burn-up ratio between breeding and ignition subassemblies are calculated and investigated. The results indicate that the initial keff increases with fuel height and core radius and finally reaches stability; the steady keff increases with fuel height and core radius, then reaches peak value and finally decreases; the maximum power density, the peak burn-up and the burn-up ratio between breeding and ignition subassemblies decrease with the increase of fuel height and core radius; if core radius is less than 1.875 m, they increase sharply with the decrease of core radius.
AB - In this paper, a preliminary board type radial fuel shuffling sodium cooled breed and burn reactor core is designed. In the current design, a number of breeding subassemblies are arranged in the center core to ensure enough breeding. A self-developed MCNP-ORIGEN coupled system with the ENDF/B-VI data library is applied to perform neutronics and burn-up calculations. For a 2.0 m radius and 2.5 m height core, the results demonstrate the feasibility of the board type radial fuel shuffling strategy. Breeding mainly occurs in the breeding subassemblies during the first 6 fuel cycles as they are moved to the burning/breeding region. The core will become asymptotically stable after about 24 years. The discharged burn-up of most subassemblies is about 15.0-30.0%. The influences of the core size on the major core parameters, such as initial keff, steady keff, maximum power density, peak burn-up and burn-up ratio between breeding and ignition subassemblies are calculated and investigated. The results indicate that the initial keff increases with fuel height and core radius and finally reaches stability; the steady keff increases with fuel height and core radius, then reaches peak value and finally decreases; the maximum power density, the peak burn-up and the burn-up ratio between breeding and ignition subassemblies decrease with the increase of fuel height and core radius; if core radius is less than 1.875 m, they increase sharply with the decrease of core radius.
UR - https://www.scopus.com/pages/publications/84907510705
U2 - 10.1016/j.nucengdes.2014.08.017
DO - 10.1016/j.nucengdes.2014.08.017
M3 - 文章
AN - SCOPUS:84907510705
SN - 0029-5493
VL - 278
SP - 679
EP - 685
JO - Nuclear Engineering and Design
JF - Nuclear Engineering and Design
ER -