ARRC: A random ray neutron transport code for nuclear reactor simulation

Tramm, John R.; Smith, Kord S.; Forget, Benoit; Siegel, Andrew R.

doi:10.1016/j.anucene.2017.10.015

Title: ARRC: A random ray neutron transport code for nuclear reactor simulation

Authors:

Tramm, John R.; Smith, Kord S.;

; Siegel, Andrew R.

Publication Date:: 2018-02-01

Sponsoring Org.:: USDOE Office of Science (SC), Advanced Scientific Computing Research (ASCR)

OSTI Identifier:: 1549043

Grant/Contract Number:: AC02-06CH11357

Resource Type:: Publisher's Accepted Manuscript

Journal Name:: Annals of Nuclear Energy (Oxford)

Additional Journal Information:: Journal Name: Annals of Nuclear Energy (Oxford) Journal Volume: 112 Journal Issue: C; Journal ID: ISSN 0306-4549

Publisher:: Elsevier

Country of Publication:: United Kingdom

Language:: English

Citation Formats


                    Tramm, John R., Smith, Kord S., Forget, Benoit, and Siegel, Andrew R. ARRC: A random ray neutron transport code for nuclear reactor simulation.  United Kingdom: N. p., 2018. 
Web.  doi:10.1016/j.anucene.2017.10.015.

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                    Tramm, John R., Smith, Kord S., Forget, Benoit, & Siegel, Andrew R. ARRC: A random ray neutron transport code for nuclear reactor simulation.  United Kingdom.  https://doi.org/10.1016/j.anucene.2017.10.015

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                    Tramm, John R., Smith, Kord S., Forget, Benoit, and Siegel, Andrew R. Thu .  
"ARRC: A random ray neutron transport code for nuclear reactor simulation".  United Kingdom.  https://doi.org/10.1016/j.anucene.2017.10.015.

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@article{osti_1549043,

  title        = {ARRC: A random ray neutron transport code for nuclear reactor simulation},

  author       = {Tramm, John R. and Smith, Kord S. and Forget, Benoit and Siegel, Andrew R.},

  abstractNote = {},

  doi          = {10.1016/j.anucene.2017.10.015},

  journal      = {Annals of Nuclear Energy (Oxford)},

  number       = C,

  volume       = 112,

  place        = {United Kingdom},

  year         = {2018},

  month        = {2}

}

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Title: ARRC: A random ray neutron transport code for nuclear reactor simulation

Citation Formats

Comparison of four parallel algorithms for domain decomposed implicit Monte Carlo journal, March 2006

With Extreme Computing, the Rules Have Changed journal, May 2017

The Random Ray Method for neutral particle transport journal, August 2017

RMC - A Monte Carlo Code for Reactor Core Analysis conference, June 2014

Scaling to a million cores and beyond: Using light-weight simulation to understand the challenges ahead on the road to exascale journal, January 2014

The low power architecture approach towards exascale computing journal, November 2013

Improvement of transport-corrected scattering stability and performance using a Jacobi inscatter algorithm for 2D-MOC journal, July 2017

The OpenMOC method of characteristics neutral particle transport code journal, June 2014

Particle clustering in Monte Carlo criticality simulations journal, January 2014

Method of characteristics – A review with applications to science and nuclear engineering computation journal, November 2015

Development and verification of an MOC code employing assembly modular ray tracing and efficient acceleration techniques journal, August 2009

The OpenMC Monte Carlo particle transport code journal, January 2013

Trends in supercomputing: The European path to exascale journal, September 2011

Tracking strategies in 3D axial geometries for a MOC solver conference, June 2014

Monte Carlo power iteration: Entropy and spatial correlations journal, August 2016

Analysis of communication costs for domain decomposed Monte Carlo methods in nuclear reactor analysis journal, April 2012

GENESIS: A Three-Dimensional Heterogeneous Transport Solver Based on the Legendre Polynomial Expansion of Angular Flux Method journal, March 2017

A Nonlinear Space-Angle Multigrid Acceleration for the Method of Characteristics in Unstructured Meshes journal, February 2007

Programming for Exascale Computers journal, November 2013

Monte Carlo domain decomposition for robust nuclear reactor analysis journal, December 2014

Prospects in Deterministic Three-Dimensional Whole-Core Transport Calculations journal, March 2012

Simulation at Extreme-Scale: Co-Design Thinking and Practices journal, February 2014

Optimizing Memory Constrained Environments in Monte Carlo Nuclear Reactor Simulations journal, June 2012

Memory bottlenecks and memory contention in multi-core Monte Carlo transport codes journal, August 2015

Analysis of correlations and their impact on convergence rates in Monte Carlo eigenvalue simulations journal, June 2016

The Serpent Monte Carlo code: Status, development and applications in 2013 journal, August 2015

TRIPOLI: A general Monte Carlo code, present state and future prospects journal, January 1990

A task-based parallelism and vectorized approach to 3D Method of Characteristics (MOC) reactor simulation for high performance computing architectures journal, May 2016

The effect of load imbalances on the performance of Monte Carlo algorithms in LWR analysis journal, February 2013

Neutronics Modeling and Simulation of Sharp for fast Reactor Analysis journal, October 2010

Tracking algorithms for multi-hexagonal assemblies (2D and 3D) journal, July 2014

Knights Landing: Second-Generation Intel Xeon Phi Product journal, March 2016

Data decomposition of Monte Carlo particle transport simulations via tally servers journal, November 2013

Computation of 3D neutron fluxes in one pin hexagonal cell journal, June 2013

Comparison of four parallel algorithms for domain decomposed implicit Monte Carlo
journal, March 2006

With Extreme Computing, the Rules Have Changed
journal, May 2017

The Random Ray Method for neutral particle transport
journal, August 2017

RMC - A Monte Carlo Code for Reactor Core Analysis
conference, June 2014

Scaling to a million cores and beyond: Using light-weight simulation to understand the challenges ahead on the road to exascale
journal, January 2014

The low power architecture approach towards exascale computing
journal, November 2013

Improvement of transport-corrected scattering stability and performance using a Jacobi inscatter algorithm for 2D-MOC
journal, July 2017

The OpenMOC method of characteristics neutral particle transport code
journal, June 2014

Particle clustering in Monte Carlo criticality simulations
journal, January 2014

Method of characteristics – A review with applications to science and nuclear engineering computation
journal, November 2015

Development and verification of an MOC code employing assembly modular ray tracing and efficient acceleration techniques
journal, August 2009

The OpenMC Monte Carlo particle transport code
journal, January 2013

Trends in supercomputing: The European path to exascale
journal, September 2011

Tracking strategies in 3D axial geometries for a MOC solver
conference, June 2014

Monte Carlo power iteration: Entropy and spatial correlations
journal, August 2016

Analysis of communication costs for domain decomposed Monte Carlo methods in nuclear reactor analysis
journal, April 2012

GENESIS: A Three-Dimensional Heterogeneous Transport Solver Based on the Legendre Polynomial Expansion of Angular Flux Method
journal, March 2017

A Nonlinear Space-Angle Multigrid Acceleration for the Method of Characteristics in Unstructured Meshes
journal, February 2007

Programming for Exascale Computers
journal, November 2013

Monte Carlo domain decomposition for robust nuclear reactor analysis
journal, December 2014

Prospects in Deterministic Three-Dimensional Whole-Core Transport Calculations
journal, March 2012

Simulation at Extreme-Scale: Co-Design Thinking and Practices
journal, February 2014

Optimizing Memory Constrained Environments in Monte Carlo Nuclear Reactor Simulations
journal, June 2012

Memory bottlenecks and memory contention in multi-core Monte Carlo transport codes
journal, August 2015

Analysis of correlations and their impact on convergence rates in Monte Carlo eigenvalue simulations
journal, June 2016

The Serpent Monte Carlo code: Status, development and applications in 2013
journal, August 2015

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A task-based parallelism and vectorized approach to 3D Method of Characteristics (MOC) reactor simulation for high performance computing architectures
journal, May 2016

The effect of load imbalances on the performance of Monte Carlo algorithms in LWR analysis
journal, February 2013

Neutronics Modeling and Simulation of Sharp for fast Reactor Analysis
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Tracking algorithms for multi-hexagonal assemblies (2D and 3D)
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