Review on neutronic/thermal-hydraulic coupling simulation methods for nuclear reactor analysis
J Wang, Q Wang, M Ding - Annals of Nuclear Energy, 2020 - Elsevier
In an operating nuclear reactor system, various physical phenomena of different properties
are intimately linked. These multiphysics phenomena include neutronics (N), thermal …
are intimately linked. These multiphysics phenomena include neutronics (N), thermal …
The multiscale thermal‐hydraulic simulation for nuclear reactors: A classification of the coupling approaches and a review of the coupled codes
K Zhang - International Journal of Energy Research, 2020 - Wiley Online Library
Simulation is becoming increasingly important in the safety analysis of nuclear reactors
nowadays. The physical phenomena in a nuclear power plant happen on three classified …
nowadays. The physical phenomena in a nuclear power plant happen on three classified …
Validation of the subchannel code SUBCHANFLOW using the NUPEC PWR tests (PSBT)
U Imke, VH Sanchez - Science and Technology of Nuclear …, 2012 - Wiley Online Library
SUBCHANFLOW is a computer code to analyze thermal‐hydraulic phenomena in the core
of pressurized water reactors, boiling water reactors, and innovative reactors operated with …
of pressurized water reactors, boiling water reactors, and innovative reactors operated with …
High-fidelity coupled Monte Carlo neutron transport and thermal-hydraulic simulations using Serpent 2/SUBCHANFLOW
M Daeubler, A Ivanov, BL Sjenitzer, V Sanchez… - Annals of Nuclear …, 2015 - Elsevier
Efforts to develop high-fidelity, in silico or ab initio, high performance multi-physics tools are
undertaken by many groups due to the availability of relatively cheap, large-scale parallel …
undertaken by many groups due to the availability of relatively cheap, large-scale parallel …
Development and verification of the coupled thermal–hydraulic code–TRACE/SCF based on the ICoCo interface and the SALOME platform
K Zhang, AC Munoz, VH Sanchez-Espinoza - Annals of Nuclear Energy, 2021 - Elsevier
The system thermal–hydraulic code TRAC/RELAP Advanced Computational Engine
(TRACE) and the sub-channel code SubChanFlow (SCF) have been coupled together …
(TRACE) and the sub-channel code SubChanFlow (SCF) have been coupled together …
Subchannel analysis–Current practice and development for the future
BW Yang, H Ninokata, J Long, A Liu, B Han - Nuclear Engineering and …, 2021 - Elsevier
Major progress in subchannel analysis development and application are reviewed in this
paper with focus mainly on the computational schemes, model improvements (including …
paper with focus mainly on the computational schemes, model improvements (including …
Coupled neutronics/thermal-hydraulics analysis of a full PWR core using RMC and CTF
J Guo, S Liu, X Shang, S Huang, K Wang - Annals of Nuclear Energy, 2017 - Elsevier
A hybrid coupled strategy was proposed for a coupled neutronics and thermal-hydraulics
analysis of a full PWR core, using the continuous-energy Reactor Monte Carlo code (RMC) …
analysis of a full PWR core, using the continuous-energy Reactor Monte Carlo code (RMC) …
High fidelity simulation of conventional and innovative LWR with the coupled Monte-Carlo thermal-hydraulic system MCNP-SUBCHANFLOW
In order to increase the accuracy and the degree of spatial and energy resolution of core
design studies, coupled 3D neutronic (multi-group deterministic and continuous energy …
design studies, coupled 3D neutronic (multi-group deterministic and continuous energy …
Development of a coupling scheme between MCNP5 and SUBCHANFLOW for the pin-and fuel assembly-wise simulation of LWR and innovative reactors
A Ivanov, V Sanchez, U Imke - 2011 - inis.iaea.org
In order to increase the accuracy and the degree of spatial resolution of core design studies,
coupled 3D neutronic (deterministic and Monte Carlo) and 3D thermal hydraulics (CFD and …
coupled 3D neutronic (deterministic and Monte Carlo) and 3D thermal hydraulics (CFD and …
Validation of the Serpent 2-DYNSUB code sequence using the special power excursion reactor test III (SPERT III)
M Knebel, L Mercatali, V Sanchez, R Stieglitz… - Annals of Nuclear …, 2016 - Elsevier
Abstract The Special Power Excursion Reactor Test III (SPERT III) is studied using the
Serpent 2-DYNSUB code sequence in order to validate it for modeling reactivity insertion …
Serpent 2-DYNSUB code sequence in order to validate it for modeling reactivity insertion …