TY - JOUR
T1 - Parallelization and application of SACOS-LMR for whole-core pin-by-pin thermal-hydraulic analysis in LMFRs
AU - Wang, Jinshun
AU - Chen, Ronghua
AU - Xiao, Sicong
AU - Zhu, Xinyang
AU - Gui, Minyang
AU - Tian, Wenxi
AU - Qiu, Suizheng
N1 - Publisher Copyright:
© 2024
PY - 2025/5
Y1 - 2025/5
N2 - The liquid metal cooled fast reactor is considered a representative design for the fourth generation of advanced reactors, owing to its inherent safety features, high power density, extended refueling intervals, and compactness. Thermal-hydraulic analysis of the reactor core remains critical for both safety and economic evaluations. In this work, we implemented parallel computing capabilities in SACOS-LMR using MPI, achieving a speedup ratio of 76 and maintaining parallel efficiency above 60% for a 100-processors parallel calculation. This work successfully resolved challenges related to inter-wrapper flow (IWF) in whole-core parallel computations and validated the IWF model using experimental data from the KALLA-IWF tests. Furthermore, we conducted whole-core pin-by-pin sub-channel calculations for the ALFRED reactor, analyzing the effects of the two-step and pin-level methods, as well as IWF flow rates, on the thermal–hydraulic characteristics of the reactor core.
AB - The liquid metal cooled fast reactor is considered a representative design for the fourth generation of advanced reactors, owing to its inherent safety features, high power density, extended refueling intervals, and compactness. Thermal-hydraulic analysis of the reactor core remains critical for both safety and economic evaluations. In this work, we implemented parallel computing capabilities in SACOS-LMR using MPI, achieving a speedup ratio of 76 and maintaining parallel efficiency above 60% for a 100-processors parallel calculation. This work successfully resolved challenges related to inter-wrapper flow (IWF) in whole-core parallel computations and validated the IWF model using experimental data from the KALLA-IWF tests. Furthermore, we conducted whole-core pin-by-pin sub-channel calculations for the ALFRED reactor, analyzing the effects of the two-step and pin-level methods, as well as IWF flow rates, on the thermal–hydraulic characteristics of the reactor core.
KW - Inter-wrapper flow
KW - MPI parallelization
KW - Pin-by-Pin
KW - Sub-channel code
KW - Thermal-hydraulic analysis
KW - Whole-core calculation
UR - https://www.scopus.com/pages/publications/85214655903
U2 - 10.1016/j.anucene.2024.111177
DO - 10.1016/j.anucene.2024.111177
M3 - 文章
AN - SCOPUS:85214655903
SN - 0306-4549
VL - 214
JO - Annals of Nuclear Energy
JF - Annals of Nuclear Energy
M1 - 111177
ER -