TY - GEN
T1 - Numerical research on fuel rod progression during core degradation process using MELCOR
AU - Feng, Tangtao
AU - Wang, Jun
AU - Qiu, Suizheng
AU - Tian, Wenxi
AU - Wang, Mingjun
AU - Song, Ping
AU - Su, G. H.
N1 - Publisher Copyright:
Copyright © 2018 ASME
PY - 2018
Y1 - 2018
N2 - Core degradation experiment will be conducted in Fuel Rod Melt Progression apparatus (FROMA) to investigate the distribution of mass and energy in designed fuel rod during a core degradation process. Numerical research on the core degradation experiment is mainly to evaluate the designed parameters of FROMA. The pre-numerical study was conducted using the widely accepted severe accident analysis software MELCOR. The fuel rods used in the experiment consisted of real reactor fuel elements, and the designed fuel rods were electrically heated with internal center tungsten-rhenium rod to a very high temperature. Numerical analysis model is described, and the input parameters are in accord with experimental conditions. In the transient period of core degradation, the production hydrogen and the distribution of mass and temperature are obtained. All the predicted MELCOR results will be compared with the experimental measurements.
AB - Core degradation experiment will be conducted in Fuel Rod Melt Progression apparatus (FROMA) to investigate the distribution of mass and energy in designed fuel rod during a core degradation process. Numerical research on the core degradation experiment is mainly to evaluate the designed parameters of FROMA. The pre-numerical study was conducted using the widely accepted severe accident analysis software MELCOR. The fuel rods used in the experiment consisted of real reactor fuel elements, and the designed fuel rods were electrically heated with internal center tungsten-rhenium rod to a very high temperature. Numerical analysis model is described, and the input parameters are in accord with experimental conditions. In the transient period of core degradation, the production hydrogen and the distribution of mass and temperature are obtained. All the predicted MELCOR results will be compared with the experimental measurements.
UR - https://www.scopus.com/pages/publications/85056186834
U2 - 10.1115/ICONE26-81738
DO - 10.1115/ICONE26-81738
M3 - 会议稿件
AN - SCOPUS:85056186834
T3 - International Conference on Nuclear Engineering, Proceedings, ICONE
BT - Student Paper Competition
PB - American Society of Mechanical Engineers (ASME)
T2 - 2018 26th International Conference on Nuclear Engineering, ICONE 2018
Y2 - 22 July 2018 through 26 July 2018
ER -