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Coupled Monte Carlo Transport and Conjugate Heat Transfer for Wire-Wrapped Bundles Within the MOOSE Framework

Journal Article · · Nuclear Science and Engineering
 [1];  [1];  [1];  [2];  [3];  [4]
  1. Argonne National Laboratory (ANL), Argonne, IL (United States)
  2. Georgia Institute of Technology, Atlanta, GA (United States)
  3. Pennsylvania State University, State College, PA (United States)
  4. Idaho National Laboratory (INL), Idaho Falls, ID (United States)

Cardinal is an open-source application that couples OpenMC Monte Carlo transport and NekRS computational fluid dynamics (CFD) to the Multiphysics Object-Oriented Simulation Environment (MOOSE), closing neutronics and thermal-fluid gaps in conducting high-resolution multiscale and multiphysics analyses of nuclear systems. We first provide a brief introduction to Cardinal's software design, data mapping, and coupling strategy to highlight our approach to overcoming common challenges in high-fidelity multiphysics simulations. Here we then present two Cardinal simulations for hexagonal pin bundles. The first is a validation of Cardinal's conjugate heat transfer coupling of NekRS's Reynolds-Averaged Navier Stokes model with MOOSE's heat conduction physics for a bare seven-pin Freon-12 bundle flow experiment. Predictions for pin surface temperatures under three different heating modes agree reasonably well with experimental data and similar CFD modeling from the literature. The second simulation is a multiphysics coupling of OpenMC, NekRS, and BISON for a reduced-scale, seven-pin wire-wrapped version of an Advanced Burner Reactor bundle. Wire wraps are approximated using a momentum source model, and coupled predictions are provided for velocity, temperature, and power distribution.

Research Organization:
Argonne National Laboratory (ANL), Argonne, IL (United States); Idaho National Laboratory (INL), Idaho Falls, ID (United States)
Sponsoring Organization:
USDOE Office of Science (SC); USDOE Laboratory Directed Research and Development (LDRD) Program
Grant/Contract Number:
AC02-06CH11357; AC05-00OR22725
OSTI ID:
2203852
Journal Information:
Nuclear Science and Engineering, Journal Name: Nuclear Science and Engineering Journal Issue: 10 Vol. 197; ISSN 0029-5639
Publisher:
Taylor & FrancisCopyright Statement
Country of Publication:
United States
Language:
English

References (33)

Thermal conductivity and thermal expansion of stainless steels D9 and HT9 journal September 1988
The thermal conductivity of nickel journal May 1965
Experimental investigations of the hydraulic field in wire-wrapped LMFBR core assemblies journal December 1980
Characterization of heat transfer and temperature distributions in an electrically heated model of an LMFBR blanket assembly journal December 1980
Critical heat flux and turbulent mixing in hexagonal tight rod bundles journal December 1998
An experimental study and assessment of existing friction factor correlations for wire-wrapped fuel assemblies journal November 2001
OpenMC: A state-of-the-art Monte Carlo code for research and development journal August 2015
Experimental study of the flow characteristics in an SFR type 61-pin rod bundle using iso-kinetic sampling method journal August 2017
A Newton-based Jacobian-free approach for neutronic-Monte Carlo/thermal-hydraulic static coupled analysis journal December 2017
Flow visualization on SFR wire-wrapped 19-pin bundle geometry using MIR-PIV-PLIF and comparisons with RANS-based CFD analysis journal November 2020
Neutronic and thermal-mechanical coupling analyses in a solid-state reactor using Monte Carlo and finite element methods journal February 2021
Coupled Monte Carlo and thermal-fluid modeling of high temperature gas reactors using Cardinal journal November 2022
PTV/PIV measurements of turbulent flows in interior subchannels of a 61-pin wire-wrapped hexagonal fuel bundle journal June 2018
Local thermal–hydraulic behaviour in tight 7-rod bundles journal October 2009
A CFD simulation process for fast reactor fuel assemblies journal September 2010
Description and preliminary results of PHENIX core flowering test journal October 2011
A momentum source model for wire-wrapped rod bundles—Concept, validation, and application journal September 2013
High fidelity simulation of conventional and innovative LWR with the coupled Monte-Carlo thermal-hydraulic system MCNP-SUBCHANFLOW journal September 2013
Heat Transfer in Turbulent Tube Flow of Liquid Metals journal January 2016
MOOSE: Enabling massively parallel multiphysics simulation journal January 2020
MOOSE Stochastic Tools: A module for performing parallel, memory-efficient in situ stochastic simulations journal May 2023
Thermal Conductivities of MgO, Al 2 O 3 , and ZrO 2 Powders to 850°C. I. Experimental journal January 1966
CFD Verification and Validation of Wire-Wrapped Pin Assemblies journal March 2020
Cardinal: A Lower-Length-Scale Multiphysics Simulator for Pebble-Bed Reactors journal January 2021
Pronghorn: A Multidimensional Coarse-Mesh Application for Advanced Reactor Thermal Hydraulics journal February 2021
Measurement of Pressure Drop in a Full-Scale Fuel Assembly of a Liquid Metal Reactor journal May 2003
Natural Convection in a Partially Heat Generating Rod Bundle Inside an Enclosure journal July 2010
Development of an MCNP6-ANSYS FLUENT Multiphysics Coupling Capability
  • Gurecky, William; Schneider, Erich
  • Volume 4: Computational Fluid Dynamics (CFD) and Coupled Codes; Decontamination and Decommissioning, Radiation Protection, Shielding, and Waste Management; Workforce Development, Nuclear Education and Public Acceptance; Mitigation Strategies for Beyond Design Basis Events; Risk Management https://doi.org/10.1115/ICONE24-60937
conference June 2016
Stochastic Approximation for Monte Carlo Calculation of Steady-State Conditions in Thermal Reactors journal March 2006
Laminar, Transition, and Turbulent Parallel Flow Pressure Drop Across Wire-Wrap-Spaced Rod Bundles journal February 1979
Pressure Drop Correlations for Fuel Element Spacers journal January 1973
Temperature Distribution in the Duct Wall and at the Exit of a 19-Rod Simulated LMFBR Fuel Assembly (FFM Bundle 2A) journal November 1974
Bow in Experimental Breeder Reactor II Reflector Subassemblies journal February 1981