TY - GEN
T1 - Preliminary core design of the long life s-co2 Cooled fast reactor with 300wmth
AU - Liu, Baolin
AU - Wu, Hongchun
AU - Zheng, Youqi
AU - Cao, Liangzhi
AU - Yuan, Xianbao
N1 - Publisher Copyright:
Copyright © 2014 by ASME.
PY - 2014
Y1 - 2014
N2 - Gas cooled fast reactors are one of the Generation 4 nuclear power plants with hard neutron spectrum and high conversion ratio. In the study a long life Supercritical CO2 (S-CO2) cooled fast reactor core design with 300 MWth is presented. Physical calculation was carried out based on Dragon and CITATION, and thermal hydraulic analysis was performed based on the single channel code. The MOX fuel was utilized in the core design, and the tube-in-duct (TID) assembly was chosen for its excellent characteristics. According to the physical and thermal hydraulic coupling calculation, the reactor in the study can be operated with 300MWth for 20Ys without shuffling or refueling. Through the core life power peaking was kept relatively low, and the fuel temperature was kept below the 1800 degree centigrade.
AB - Gas cooled fast reactors are one of the Generation 4 nuclear power plants with hard neutron spectrum and high conversion ratio. In the study a long life Supercritical CO2 (S-CO2) cooled fast reactor core design with 300 MWth is presented. Physical calculation was carried out based on Dragon and CITATION, and thermal hydraulic analysis was performed based on the single channel code. The MOX fuel was utilized in the core design, and the tube-in-duct (TID) assembly was chosen for its excellent characteristics. According to the physical and thermal hydraulic coupling calculation, the reactor in the study can be operated with 300MWth for 20Ys without shuffling or refueling. Through the core life power peaking was kept relatively low, and the fuel temperature was kept below the 1800 degree centigrade.
UR - https://www.scopus.com/pages/publications/84911474581
U2 - 10.1115/ICONE22-30390
DO - 10.1115/ICONE22-30390
M3 - 会议稿件
AN - SCOPUS:84911474581
T3 - International Conference on Nuclear Engineering, Proceedings, ICONE
BT - Next Generation Reactors and Advanced Reactors; Nuclear Safety and Security
PB - American Society of Mechanical Engineers (ASME)
T2 - 2014 22nd International Conference on Nuclear Engineering, ICONE 2014
Y2 - 7 July 2014 through 11 July 2014
ER -