TY - GEN
T1 - The thermal-hydraulic analyses of transients in PBWFR
AU - Tian, Yonghong
AU - Su, Guanghui
AU - Wang, Jun
AU - Tian, Wenxi
AU - Qiu, Suizheng
PY - 2012
Y1 - 2012
N2 - Pb-Bi-cooled direct contact boiling water fast reactor (PBWFR) can produce steam from direct contact of feedwater and lead bismuth eutectic (LBE) in the chimney of 3m height, which could eliminate the steam generators. Meanwhile it circulates LBE by means of buoyancy of steam bubbles and the primary pump is not necessary. The concept makes the reactor simple and compact. The thermal-hydraulic behavior and safety performance were studied by a computer program in the paper. The reactor power was simulated by the point reactor kinetics equations. The drift flux model was adopted to calculate the fluid density and pressure drops in the chimney. The rate of heat exchange of the feed water and LBE in the chimney was supposed to be constant. The results showed that PBWFR had very good inherent safety. The designs could ensure the integrity of the claddings. Meanwhile the impacts of axial conduction were also researched. It showed that even in the PBWFR, in which the temperature difference between inlet and outlet of core was 150°C, the impacts could also be ignored.
AB - Pb-Bi-cooled direct contact boiling water fast reactor (PBWFR) can produce steam from direct contact of feedwater and lead bismuth eutectic (LBE) in the chimney of 3m height, which could eliminate the steam generators. Meanwhile it circulates LBE by means of buoyancy of steam bubbles and the primary pump is not necessary. The concept makes the reactor simple and compact. The thermal-hydraulic behavior and safety performance were studied by a computer program in the paper. The reactor power was simulated by the point reactor kinetics equations. The drift flux model was adopted to calculate the fluid density and pressure drops in the chimney. The rate of heat exchange of the feed water and LBE in the chimney was supposed to be constant. The results showed that PBWFR had very good inherent safety. The designs could ensure the integrity of the claddings. Meanwhile the impacts of axial conduction were also researched. It showed that even in the PBWFR, in which the temperature difference between inlet and outlet of core was 150°C, the impacts could also be ignored.
UR - https://www.scopus.com/pages/publications/84890079541
U2 - 10.1115/ICONE20-POWER2012-54373
DO - 10.1115/ICONE20-POWER2012-54373
M3 - 会议稿件
AN - SCOPUS:84890079541
SN - 9780791844977
T3 - International Conference on Nuclear Engineering, Proceedings, ICONE
SP - 273
EP - 282
BT - 2012 20th International Conference on Nuclear Engineering and the ASME 2012 Power Conference, ICONE 2012-POWER 2012
T2 - 2012 20th International Conference on Nuclear Engineering and the ASME 2012 Power Conference, ICONE 2012-POWER 2012
Y2 - 30 July 2012 through 3 August 2012
ER -