Multiscale thermal-hydraulic modeling of the pebble bed fluoride-salt-cooled high-temperature reactor

Novak, A. J.; Schunert, S.; Carlsen, R. W.; Balestra, P.; Slaybaugh, R. N.; Martineau, R. C.

doi:10.1016/j.anucene.2020.107968

Title: Multiscale thermal-hydraulic modeling of the pebble bed fluoride-salt-cooled high-temperature reactor

Authors:: Novak, A. J.; Schunert, S.; Carlsen, R. W.; Balestra, P.; Slaybaugh, R. N.; Martineau, R. C.

Publication Date:: Sat May 01 00:00:00 EDT 2021

Sponsoring Org.:: USDOE

OSTI Identifier:: 1782261

Grant/Contract Number:: AC07-05ID14517

Resource Type:: Publisher's Accepted Manuscript

Journal Name:: Annals of Nuclear Energy

Additional Journal Information:: Journal Name: Annals of Nuclear Energy Journal Volume: 154 Journal Issue: C; Journal ID: ISSN 0306-4549

Publisher:: Elsevier

Country of Publication:: United Kingdom

Language:: English

Citation Formats


                    Novak, A. J., Schunert, S., Carlsen, R. W., Balestra, P., Slaybaugh, R. N., and Martineau, R. C. Multiscale thermal-hydraulic modeling of the pebble bed fluoride-salt-cooled high-temperature reactor.  United Kingdom: N. p., 2021. 
Web.  doi:10.1016/j.anucene.2020.107968.

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                    Novak, A. J., Schunert, S., Carlsen, R. W., Balestra, P., Slaybaugh, R. N., & Martineau, R. C. Multiscale thermal-hydraulic modeling of the pebble bed fluoride-salt-cooled high-temperature reactor.  United Kingdom.  https://doi.org/10.1016/j.anucene.2020.107968

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                    Novak, A. J., Schunert, S., Carlsen, R. W., Balestra, P., Slaybaugh, R. N., and Martineau, R. C. Sat .  
"Multiscale thermal-hydraulic modeling of the pebble bed fluoride-salt-cooled high-temperature reactor".  United Kingdom.  https://doi.org/10.1016/j.anucene.2020.107968.

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@article{osti_1782261,

  title        = {Multiscale thermal-hydraulic modeling of the pebble bed fluoride-salt-cooled high-temperature reactor},

  author       = {Novak, A. J. and Schunert, S. and Carlsen, R. W. and Balestra, P. and Slaybaugh, R. N. and Martineau, R. C.},

  abstractNote = {},

  doi          = {10.1016/j.anucene.2020.107968},

  journal      = {Annals of Nuclear Energy},

  number       = C,

  volume       = 154,

  place        = {United Kingdom},

  year         = {Sat May 01 00:00:00 EDT 2021},

  month        = {Sat May 01 00:00:00 EDT 2021}

}

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Title: Multiscale thermal-hydraulic modeling of the pebble bed fluoride-salt-cooled high-temperature reactor

Citation Formats

Simple stabilizing matrices for the computation of compressible flows in primitive variables journal, October 2001

MOOSE: Enabling massively parallel multiphysics simulation journal, January 2020

Dimensional change, irradiation creep and thermal/mechanical property changes in nuclear graphite journal, April 2016

Estimation of maximum coated particle fuel compact packing fraction journal, March 2007

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Validation of Pronghorn friction-dominated porous media thermal-hydraulics model with the SANA experiments journal, August 2019

Experimental study of bypass flow in near wall gaps of a pebble bed reactor using hot wire anemometry technique journal, March 2014

An improved porous media approach to thermal–hydraulics analysis of high-temperature gas-cooled reactors journal, February 2015

Effect of fluid dispersion coefficients on particle-to-fluid heat transfer coefficients in packed beds journal, January 1979

Development of a fast 3D thermal-hydraulic tool for design and safety studies for HTRS journal, November 2008

On the general equations for flow in porous media and their reduction to Darcy's Law journal, April 1976

Estimating correlations for the effective thermal conductivity of granular materials journal, December 2002

Construction and operating experience with the 300-MW THTR nuclear power plant journal, July 1990

Neutronic evaluation of a PWR with fully ceramic microencapsulated fuel. Part II: Nodal core calculations and preliminary study of thermal hydraulic feedback journal, December 2013

libMesh : a C++ library for parallel adaptive mesh refinement/coarsening simulations journal, November 2006

CFD investigation of bypass flow in HTR-PM journal, April 2018

Individual pebble temperature peaking factor due to local pebble arrangement in a pebble bed reactor core journal, January 2011

The potential impact of Fully Ceramic Microencapsulated (FCM) fuel on thermal hydraulic performance of SMART reactor journal, December 2018

GMRES: A Generalized Minimal Residual Algorithm for Solving Nonsymmetric Linear Systems journal, July 1986

Wall effects in laminar flow of fluids through packed beds journal, September 1981

Preliminary phenomena identification and ranking tables on the subject of the High Temperature Gas-cooled Reactor-Pebble Bed Module thermal fluids and accident analysis journal, June 2018

Studies on effective thermal conductivities in packed beds journal, September 1957

Analysis of the interfacial heat transfer process in a pebble fuel journal, May 2013

Measured and modeled superficial flow profiles in packed beds with liquid flow journal, February 1998

Liquid Salt Test Loop modeling using TRACE journal, August 2017

On the characteristics of the flow and heat transfer in the core bypass region of a PWR journal, April 2018

CFD study of fluid flow and wall heat transfer in a fixed bed of spheres journal, January 2004

Two-temperature homogenized model for steady-state and transient thermal analyses of a pebble with distributed fuel particles journal, May 2009

Fluoride salt coolant properties for nuclear reactor applications: A review journal, November 2017

Graphite as a neutron moderator and reflector material journal, February 1971

Bypass flow in small absorber sphere channels of the high-temperature gas-cooled reactor pebble-bed module journal, December 2017

Thermal conductivity of packed beds: A review journal, July 1987

OpenMC: A state-of-the-art Monte Carlo code for research and development journal, August 2015

Finite element stabilization parameters computed from element matrices and vectors journal, October 2000

Simple stabilizing matrices for the computation of compressible flows in primitive variables
journal, October 2001

MOOSE: Enabling massively parallel multiphysics simulation
journal, January 2020

Dimensional change, irradiation creep and thermal/mechanical property changes in nuclear graphite
journal, April 2016

Estimation of maximum coated particle fuel compact packing fraction
journal, March 2007

Experimental measurement and numerical modeling of the effective thermal conductivity of TRISO fuel compacts
journal, March 2015

Systematic mesh development for 3D CFD simulation of fixed beds: Contact points study
journal, January 2013

A CFD method to evaluate the integrated influence of leakage and bypass flows on the PBMR Reactor Unit
journal, November 2010

Validation of Pronghorn friction-dominated porous media thermal-hydraulics model with the SANA experiments
journal, August 2019

Experimental study of bypass flow in near wall gaps of a pebble bed reactor using hot wire anemometry technique
journal, March 2014

An improved porous media approach to thermal–hydraulics analysis of high-temperature gas-cooled reactors
journal, February 2015

Effect of fluid dispersion coefficients on particle-to-fluid heat transfer coefficients in packed beds
journal, January 1979

Development of a fast 3D thermal-hydraulic tool for design and safety studies for HTRS
journal, November 2008

On the general equations for flow in porous media and their reduction to Darcy's Law
journal, April 1976

Estimating correlations for the effective thermal conductivity of granular materials
journal, December 2002

Construction and operating experience with the 300-MW THTR nuclear power plant
journal, July 1990

Neutronic evaluation of a PWR with fully ceramic microencapsulated fuel. Part II: Nodal core calculations and preliminary study of thermal hydraulic feedback
journal, December 2013

libMesh : a C++ library for parallel adaptive mesh refinement/coarsening simulations
journal, November 2006

CFD investigation of bypass flow in HTR-PM
journal, April 2018

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journal, January 2011

The potential impact of Fully Ceramic Microencapsulated (FCM) fuel on thermal hydraulic performance of SMART reactor
journal, December 2018

GMRES: A Generalized Minimal Residual Algorithm for Solving Nonsymmetric Linear Systems
journal, July 1986

Wall effects in laminar flow of fluids through packed beds
journal, September 1981

Preliminary phenomena identification and ranking tables on the subject of the High Temperature Gas-cooled Reactor-Pebble Bed Module thermal fluids and accident analysis
journal, June 2018

Studies on effective thermal conductivities in packed beds
journal, September 1957

Analysis of the interfacial heat transfer process in a pebble fuel
journal, May 2013

Measured and modeled superficial flow profiles in packed beds with liquid flow
journal, February 1998

Liquid Salt Test Loop modeling using TRACE
journal, August 2017

On the characteristics of the flow and heat transfer in the core bypass region of a PWR
journal, April 2018

CFD study of fluid flow and wall heat transfer in a fixed bed of spheres
journal, January 2004

Two-temperature homogenized model for steady-state and transient thermal analyses of a pebble with distributed fuel particles
journal, May 2009

Fluoride salt coolant properties for nuclear reactor applications: A review
journal, November 2017

Graphite as a neutron moderator and reflector material
journal, February 1971

Bypass flow in small absorber sphere channels of the high-temperature gas-cooled reactor pebble-bed module
journal, December 2017

Thermal conductivity of packed beds: A review
journal, July 1987

OpenMC: A state-of-the-art Monte Carlo code for research and development
journal, August 2015

Finite element stabilization parameters computed from element matrices and vectors
journal, October 2000