Highly-detailed neutronic and thermal-hydraulic coupled calculations for OPAL reactor using diverse codes and approaches

The industry-standard approach for designing and operating research reactors cores relies on well-established methodologies that consider uncoupled neutronic calculations and a subchannel analysis of the Thermal-Hydraulic (TH) associated problem. Advancements in computing power and codes allow detailed Multiphysics approaches to be implemented, thereby reducing conservatism. In this study, a comparative analysis of results from diverse detailed neutronic-TH coupled core approaches is developed. To address a realistic application case, the comparison is made for a reported critical configuration from the Open Pool Australian Lightwater research reactor (OPAL) at Hot Full Power (HFP) and low burnup. Both cell-core and stochastic methodologies for neutronics are evaluated, whereas two different subchannel codes are considered for TH. In conclusion, the convergence of the coupled schemes, and the consistency of the main parameters are discussed, showing the compatibility of the alternative methods and their ability to offer critical insights not captured by standard practices.. Authors: Ferraro, Diego [INVAP S.E. Nuclear Engineering Department, Buenos Aires (Argentina)]; Ferrari, Ignacio [INVAP S.E. Nuclear Engineering Department, Buenos Aires (Argentina)]; Doval, Alicia [INVAP S.E. Nuclear Engineering Department, Bariloche (Argentina)]; Villarino, Eduardo [INVAP S.E. Nuclear Engineering Department, Bariloche (Argentina)] (ORCID:0000000272125182); Ozar, Basar [Argonne National Laboratory (ANL), Argonne, IL (United States)]. DOE Contract: AC02-06CH11357. Subjects: 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; CITVAP code; Condor code; OPAL research reactor; PLTEMP/ANL code; Serpent code; TERMIC code; highly-detailed coupled neutronic-TH