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Code Issues Projects Releases Packages Wiki Activity Actions 5
OpenMC/docs/source/publications.rst
Paul Romano 906548db20
Release notes for 0.15.1 (#3340) 
Co-authored-by: Patrick Shriwise <pshriwise@gmail.com>
2025-03-07 14:49:36 -06:00

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.. _publications:
============
Publications
============
---------
Overviews
---------
- Paul K. Romano, Nicholas E. Horelik, Bryan R. Herman, Adam G. Nelson, Benoit
Forget, and Kord Smith, "`OpenMC: A State-of-the-Art Monte Carlo Code for
Research and Development <https://doi.org/10.1016/j.anucene.2014.07.048>`_,"
*Ann. Nucl. Energy*, **82**, 90--97 (2015).
- Paul K. Romano, Bryan R. Herman, Nicholas E. Horelik, Benoit Forget, Kord
Smith, and Andrew R. Siegel, "Progress and Status of the OpenMC Monte Carlo
Code," *Proc. Int. Conf. Mathematics and Computational Methods Applied to
Nuclear Science and Engineering*, Sun Valley, Idaho, May 5--9 (2013).
- Paul K. Romano and Benoit Forget, "`The OpenMC Monte Carlo Particle Transport
Code <https://doi.org/10.1016/j.anucene.2012.06.040>`_,"
*Ann. Nucl. Energy*, **51**, 274--281 (2013).
------------
Benchmarking
------------
- Travis J. Labossiere-Hickman and Benoit Forget, "Selected VERA Core Physics
Benchmarks in OpenMC," *Trans. Am. Nucl. Soc.*, **117**, 1520-1523 (2017).
- Khurrum S. Chaudri and Sikander M. Mirza, "`Burnup dependent Monte Carlo
neutron physics calculations of IAEA MTR benchmark
<https://doi.org/10.1016/j.pnucene.2014.12.018>`_," *Prog. Nucl. Energy*,
**81**, 43-52 (2015).
- Daniel J. Kelly, Brian N. Aviles, Paul K. Romano, Bryan R. Herman,
Nicholas E. Horelik, and Benoit Forget, "Analysis of select BEAVRS PWR
benchmark cycle 1 results using MC21 and OpenMC," *Proc. PHYSOR*, Kyoto,
Japan, Sep. 28--Oct. 3 (2014).
- Bryan R. Herman, Benoit Forget, Kord Smith, Paul K. Romano, Thomas M. Sutton,
Daniel J. Kelly, III, and Brian N. Aviles, "Analysis of tally correlations in
large light water reactors," *Proc. PHYSOR*, Kyoto, Japan, Sep. 28--Oct. 3
(2014).
- Nicholas Horelik, Bryan Herman, Benoit Forget, and Kord Smith, "Benchmark for
Evaluation and Validation of Reactor Simulations,"
*Proc. Int. Conf. Mathematics and Computational Methods Applied to Nuclear
Science and Engineering*, Sun Valley, Idaho, May 5--9 (2013).
- Jonathan A. Walsh, Benoit Forget, and Kord S. Smith, "Validation of OpenMC
Reactor Physics Simulations with the B&W 1810 Series Benchmarks,"
*Trans. Am. Nucl. Soc.*, **109**, 1301--1304 (2013).
--------------------------
Coupling and Multi-physics
--------------------------
- Miriam A. Kreher, Benoit Forget, and Kord Smith, "Single-Batch Monte Carlo
Multiphysics Coupling," *Proc. M&C*, 1789-1797, Portland, Oregon, Aug. 25-29
(2019).
- Ze-Long Zhao, Yongwei Yang, and Shuang Hong, "`Application of FLUKA and OpenMC
in coupled physics calculation of target and subcritical reactor for ADS
<https://doi.org/10.1007/s41365-018-0539-1>`_," *Nucl. Sci. Tech.*, **30**: 10
(2019).
- April Novak, Paul Romano, Brycen Wendt, Ron Rahaman, Elia Merzari, Leslie
Kerby, Cody Permann, Richard Martineau, and Rachel N. Slaybaugh, "Preliminary
Coupling of OpenMC and Nek5000 within the MOOSE Framework," *Proc. PHYSOR*,
Cancun, Mexico, Apr. 22-26 (2018).
- Sterling Harper, Kord Smith, and Benoit Forget, "Faster Monte Carlo
multiphysics using temperature derivatives," *Proc. PHYSOR*, Cancun, Mexico,
Apr. 22-26 (2018).
- Jun Chen, Liangzhi Cao, Chuanqi Zhao, and Zhouyu Liu, "`Development of
Subchannel Code SUBSC for high-fidelity multi-physics coupling application
<https://doi.org/10.1016/j.egypro.2017.08.121>`_", *Energy Procedia*, **127**,
264-274 (2017).
- Tianliang Hu, Liangzhu Cao, Hongchun Wu, Xianan Du, and Mingtao He, "`Coupled
neutronics and thermal-hydraulics simulation of molten salt reactors based on
OpenMC/TANSY <https://doi.org/10.1016/j.anucene.2017.05.002>`_,"
*Ann. Nucl. Energy*, **109**, 260-276 (2017).
- Matthew Ellis, Derek Gaston, Benoit Forget, and Kord Smith, "`Preliminary
Coupling of the Monte Carlo Code OpenMC and the Multiphysics Object-Oriented
Simulation Environment for Analyzing Doppler Feedback in Monte Carlo
Simulations <https://doi.org/10.13182/NSE16-26>`_," *Nucl. Sci. Eng.*,
**185**, 184-193 (2017).
- Matthew Ellis, Benoit Forget, Kord Smith, and Derek Gaston, "Continuous
Temperature Representation in Coupled OpenMC/MOOSE Simulations," *Proc. PHYSOR
2016*, Sun Valley, Idaho, May 1-5, 2016.
- Antonios G. Mylonakis, Melpomeni Varvayanni, and Nicolas Catsaros,
"`Investigating a Matrix-free, Newton-based, Neutron-Monte
Carlo/Thermal-Hydraulic Coupling Scheme
<https://www.researchgate.net/publication/282001032>`_",
*Proc. Int. Conf. Nuclear Energy for New Europe*, Portoroz, Slovenia, Sep
.14-17 (2015).
- Matt Ellis, Benoit Forget, Kord Smith, and Derek Gaston, "Preliminary coupling
of the Monte Carlo code OpenMC and the Multiphysics Object-Oriented Simulation
Environment (MOOSE) for analyzing Doppler feedback in Monte Carlo
simulations," *Proc. Joint Int. Conf. M&C+SNA+MC*, Nashville, Tennessee,
Apr. 19--23 (2015).
- Bryan R. Herman, Benoit Forget, and Kord Smith, "`Progress toward Monte
Carlo-thermal hydraulic coupling using low-order nonlinear diffusion
acceleration methods <https://doi.org/10.1016/j.anucene.2014.10.029>`_,"
*Ann. Nucl. Energy*, **84**, 63-72 (2015).
- Bryan R. Herman, Benoit Forget, and Kord Smith, "Utilizing CMFD in OpenMC to
Estimate Dominance Ratio and Adjoint," *Trans. Am. Nucl. Soc.*, **109**,
1389-1392 (2013).
--------------------------
Geometry and Visualization
--------------------------
- Patrick C. Shriwise, Xiaokang Zhang, and Andrew Davis, "DAG-OpenMC: CAD-Based
Geometry in OpenMC", *Trans. Am. Nucl. Soc.*, **122**, 395-398 (2020).
- Sterling Harper, Paul Romano, Benoit Forget, and Kord Smith, "Efficient
dynamic threadsafe neighbor lists for Monte Carlo ray tracing," *Proc. M&C*,
918-926, Portland, Oregon, Aug. 25-29 (2019).
- Jin-Yang Li, Long Gu, Hu-Shan Xu, Nadezha Korepanova, Rui Yu, Yan-Lei Zhu, and
Chang-Ping Qin, "`CAD modeling study on FLUKA and OpenMC for accelerator
driven system simulation <https://doi.org/10.1016/j.anucene.2017.12.050>`_",
*Ann. Nucl. Energy*, **114**, 329-341 (2018).
- Logan Abel, William Boyd, Benoit Forget, and Kord Smith, "Interactive
Visualization of Multi-Group Cross Sections on High-Fidelity Spatial Meshes,"
*Trans. Am. Nucl. Soc.*, **114**, 391-394 (2016).
- Derek M. Lax, "`Memory efficient indexing algorithm for physical properties in
OpenMC <https://dspace.mit.edu/handle/1721.1/97862>`_," S. M. Thesis,
Massachusetts Institute of Technology (2015).
- Derek Lax, William Boyd, Nicholas Horelik, Benoit Forget, and Kord Smith, "A
memory efficient algorithm for classifying unique regions in constructive
solid geometries," *Proc. PHYSOR*, Kyoto, Japan, Sep. 28--Oct. 3 (2014).
-------------
Miscellaneous
-------------
- Shikhar Kumar, Benoit Forget, and Kord Smith, "`Stationarity Diagnostic using
Functional Expansion Tallies
<https://doi.org/10.1016/j.anucene.2020.107388>`_", *Ann. Nucl. Energy*,
**143**, 107388 (2020).
- T. Eade, B. Colling, J. Naish, L. W. Packer, and A. Valentine, "`Shutdown dose
rate benchmarking using modern particle transport codes
<https://doi.org/10.1088/1741-4326/ab8181>`_, *Nucl. Fusion*, **60**, 056024
(2020).
- Jiankai Yu, Qiudong Wang, Ding She, and Benoit Forget, "Modelling of the
HTR-PM Pebble-bed Reactor using OpenMC", *Trans. Am. Nucl. Soc.*, **122**,
643-646 (2020).
- Sharif Abu Darda, Abdelfattah Y. Soliman, Mohammed S. Aljohani, and Ned Xoubi,
"`Technical feasibility study of BAEC TRIGA reactor (BTRR) as a neutron source
for BNCT using OpenMC Monte Carlo code
<https://doi.org/10.1016/j.pnucene.2020.103418>`_", *Prog. Nucl. Energy*,
**126**, 103418 (2020).
- Stefano Segantin, Raffaella Testoni, and Massimo Zucchetti, "`ARC reactor --
Neutron irradiation analysis <https://doi.org/10.1016/j.fusengdes.2020.111792>`_",
*Fus. Eng. Design*, **159**, 111792 (2020).
- Muhammad Ilham, Helen Raflis, and Zaki Suud, "`Full Core Optimization of Small
Modular Gas-Cooled Fast Reactors Using OpenMC Program Code
<https://doi.org/10.1088/1742-6596/1493/1/012007>`_", *J. Phys.: Conf. Series*,
**1493**, 012007 (2020).
- Ned Xoubi, Sharif Abu Darda, Abdelfattah Y. Soliman, and Tareq Abulfaraj,
"`An investigative study of enrichment reduction impact on the neutron flux in
the in-core flux-trap facility of MTR research reactors
<https://doi.org/10.1016/j.net.2019.08.008>`_", *Nucl. Eng. Technol.*, **52**,
469-476 (2020).
- J. Rolando Granada, J. Ignacio Marquez Damian, and Christian Helman, "`Studies
on Reflector Materials for Cold Neutrons
<https://doi.org/10.1051/epjconf/202023104002>`_, *Eur. Phys. J. Web Conf.*,
**231**, 04002 (2020).
- Govatsa Acharya, "`Investigating the Application of Self-Actuated Passive
Shutdown System in a Small Lead-Cooled Reactor
<https://doi.org/10.13140/RG.2.2.26088.01281>`_," M.S. Thesis, KTH Royal
Institute of Technology (2019).
- Ilham Variansyah, Benjamin R. Betzler, and William R. Martin,
"α-weighted transition rate matrix method", *Proc. M&C*, 1368-1377, Portland,
Oregon, Aug. 25-29 (2019).
- Shikhar Kumar, Benoit Forget, and Kord Smith, "Analysis of fission source
convergence for a 3-D SMR core using functional expansion tallies," *Proc.
M&C*, 937-947, Portland, Oregon, Aug. 25-29 (2019).
- Faisal Qayyum, Muhammad R. Ali, Awais Zahur, and R. Khan, "`Improvements in
methodology to determine feedback reactivity coefficients
<https://doi.org/10.1007/s41365-019-0588-0>`_," *Nucl. Sci. Tech.*, **30**: 63
(2019).
- M. Sajjad, Muhammad Rizwan Ali, M. Naveed Ashraf, Rustam Khan, Tasneem Fatima,
"`KANUPP Reactor Core Model and its Validation
<https://doi.org/10.1109/PGSRET.2018.8685948>`_," International Conference on
Power Generation Systems and Renewable Energy Technologies, Islamabad,
Pakistan, Sep. 10-12 (2018).
- Muhammad Waqas Tariq, Muhammad Sohail, and Sikander Majid Mirza, "`Calculation
of Neutronic Parameters using OpenMC for Potential Dispersed Fuels of MNSR
<https://doi.org/10.1109/PGSRET.2018.8685927>`_," International Conference on
Power Generation Systems and Renewable Energy Technologies, Islamabad,
Pakistan, Sep. 10-12 (2018).
- Amanda L. Lund and Paul K. Romano, "`Implementation and Validation of Photon
Transport in OpenMC <https://doi.org/10.2172/1490825>`_", Argonne National
Laboratory, Technical Report ANL/MCS-TM-381 (2018).
- Bruno Merk, Dzianis Litskevich, R. Gregg, and A. R. Mount, "`Demand driven
salt clean-up in a molten salt fast reactor -- Defining a priority list
<https://doi.org/10.1371/journal.pone.0192020>`_", *PLOS One*, **13**,
e0192020 (2018).
- Adam G. Nelson, Samuel Shaner, William Boyd, and Paul K. Romano,
"Incorporation of a Multigroup Transport Capability in the OpenMC Monte Carlo
Particle Transport Code," *Trans. Am. Nucl. Soc.*, **117**, 679-681 (2017).
- Youqi Zheng, Yunlong Xiao, and Hongchun Wu, "`Application of the virtual
density theory in fast reactor analysis based on the neutron transport
calculation <https://doi.org/10.1016/j.nucengdes.2017.05.020>`_,"
*Nucl. Eng. Des.*, **320**, 200-206 (2017).
- Amanda L. Lund, Paul K. Romano, and Andrew R. Siegel, "Accelerating Source
Convergence in Monte Carlo Criticality Calculations Using a Particle Ramp-Up
Technique," *Proc. Int. Conf. Mathematics & Computational Methods Applied to
Nuclear Science and Engineering*, Jeju, Korea, Apr. 16-20, 2017.
- Antonios G. Mylonakis, M. Varvayanni, D.G.E. Grigoriadis, and N. Catsaros,
"Developing and investigating a pure Monte-Carlo module for transient neutron
transport analysis," *Ann. Nucl. Energy*, **104**, 103-112 (2017).
- Timothy P. Burke, Brian C. Kiedrowski, William R. Martin, and
Forrest B. Brown, "GPU Acceleration of Kernel Density Estimators in Monte
Carlo Neutron Transport Simulations," *Trans. Am. Nucl. Soc.*, **115**,
531-534 (2016).
- Timothy P. Burke, Brian C. Kiedrowski, and William R. Martin, "Cylindrical
Kernel Density Estimators for Monte Carlo Neutron Transport Reactor Physics
Problems," *Trans. Am. Nucl. Soc.*, **115**, 563-566 (2016).
- Yunzhao Li, Qingming He, Liangzhi Cao, Hongchun Wu, and Tiejun Zu, "`Resonance
Elastic Scattering and Interference Effects Treatments in Subgroup Method
<https://doi.org/10.1016/j.net.2015.12.015>`_," *Nucl. Eng. Tech.*, **48**,
339-350 (2016).
- William Boyd, Sterling Harper, and Paul K. Romano, "Equipping OpenMC for the
big data era," *Proc. PHYSOR*, Sun Valley, Idaho, May 1-5, 2016.
- Michal Kostal, Vojtech Rypar, Jan Milcak, Vlastimil Juricek, Evzen Losa,
Benoit Forget, and Sterling Harper, "`Study of graphite reactivity worth on
well-defined cores assembled on LR-0 reactor
<https://doi.org/10.1016/j.anucene.2015.10.010>`_," *Ann. Nucl. Energy*,
**87**, 601-611 (2016).
- Qicang Shen, William Boyd, Benoit Forget, and Kord Smith, "Tally precision
triggers for the OpenMC Monte Carlo code," *Trans. Am. Nucl. Soc.*, **112**,
637-640 (2015).
- Kyungkwan Noh and Deokjung Lee, "Whole Core Analysis using OpenMC Monte Carlo
Code," *Trans. Kor. Nucl. Soc. Autumn Meeting*, Gyeongju, Korea,
Oct. 24-25, 2013.
- Timothy P. Burke, Brian C. Kiedrowski, and William R. Martin, "Flux and
Reaction Rate Kernel Density Estimators in OpenMC," *Trans. Am. Nucl. Soc.*,
**109**, 683-686 (2013).
-----------------------------------
Multigroup Cross Section Generation
-----------------------------------
- Ilham Variansyah, Benjamin R. Betzler, and William R. Martin, "`Multigroup
Constant Calculation with Static α-Eigenvalue Monte Carlo for
Time-Dependent Neutron Transport Simulation
<https://doi.org/10.1080/00295639.2020.1743578>`_", *Nucl. Sci. Eng.*, 2020.
- Chenghui Wan, Tianliang Hu, and Liangzhi Cao, "`Multi-physics numerical
analysis of the fuel-addition transients in the liquid-fuel molten salt reactor
<https://doi.org/10.1016/j.anucene.2020.107514>`_", *Ann. Nucl. Energy*,
**144**, 107514 (2020).
- William Boyd, Adam Nelson, Paul K. Romano, Samuel Shaner, Benoit Forget, and
Kord Smith, "`Multigroup Cross-Section Generation with the OpenMC Monte Carlo
Particle Transport Code <https://doi.org/10.1080/00295450.2019.1571828>`_,"
*Nucl. Technol.*, **205**, 928-944 (2019).
- William Boyd, Benoit Forget, and Kord Smith, "`A single-step framework to
generate spatially self-shielded multi-group cross sections from Monte Carlo
transport simulations <https://doi.org/10.1016/j.anucene.2018.11.017>`_,"
*Ann. Nucl. Energy*, **125**, 261-271 (2019).
- Kun Zhuang, Xiaobin Tang, and Liangzhi Cao, "`Development and verification of
a model for generation of MSFR few-group homogenized cross-sections based on a
Monte Carlo code OpenMC <https://doi.org/10.1016/j.anucene.2018.09.037>`_,"
*Ann. Nucl. Energy*, **124**, 187-197 (2019).
- Changho Lee and Yeon Sang Jung, "Verification of the Cross Section Library
Generated Using OpenMC and MC\ :sup:`2`-3 for PROTEUS," *Proc. PHYSOR*, Cancun,
Mexico, Apr. 22-26 (2018).
- Zhaoyuan Liu, Kord Smith, Benoit Forget, and Javier Ortensi, "`Cumulative
migration method for computing rigorous diffusion coefficients and transport
cross sections from Monte Carlo
<https://doi.org/10.1016/j.anucene.2017.10.039>`_," *Ann. Nucl. Energy*,
**112**, 507-516 (2018).
- Gang Yang, Tongkyu Park, and Won Sik Yang, "Effects of Fuel Salt Velocity
Field on Neutronics Performances in Molten Salt Reactors with Open Flow
Channels," *Trans. Am. Nucl. Soc.*, **117**, 1339-1342 (2017).
- William Boyd, Nathan Gibson, Benoit Forget, and Kord Smith, "`An analysis of
condensation errors in multi-group cross section generation for fine-mesh
neutron transport calculations
<https://doi.org/10.1016/j.anucene.2017.09.052>`_," *Ann. Nucl. Energy*,
**112**, 267-276 (2018).
- Hong Shuang, Yang Yongwei, Zhang Lu, and Gao Yucui, "`Fabrication and
validation of multigroup cross section library based on the OpenMC code
<https://doi.org/10.11889/j.0253-3219.2017.hjs.40.040502>`_,"
*Nucl. Techniques* **40** (4), 040504 (2017). (in Mandarin)
- Nicholas E. Stauff, Changho Lee, Paul K. Romano, and Taek K. Kim,
"Verification of Mixed Stochastic/Deterministic Approach for Fast and Thermal
Reactor Analysis," *Proc. ICAPP*, Fukui and Kyoto, Japan, Apr. 24-28, 2017.
- Zhauyuan Liu, Kord Smith, and Benoit Forget, "Progress of Cumulative Migration
Method for Computing Diffusion Coefficients with OpenMC,"
*Proc. Int. Conf. Mathematics & Computational Methods Applied to Nuclear
Science and Engineering*, Jeju, Korea, Apr. 16-20, 2017.
- Geoffrey Gunow, Samuel Shaner, William Boyd, Benoit Forget, and Kord Smith,
"Accuracy and Performance of 3D MOC for Full-Core PWR Problems,"
*Proc. Int. Conf. Mathematics & Computational Methods Applied to Nuclear
Science and Engineering*, Jeju, Korea, Apr. 16-20, 2017.
- Tianliang Hu, Liangzhi Cao, Hongchun Wu, and Kun Zhuang, "A coupled neutronics
and thermal-hydraulic modeling approach to the steady-state and dynamic
behavior of MSRs," *Proc. Int. Conf. Mathematics & Computational Methods
Applied to Nuclear Science and Engineering*, Jeju, Korea, Apr. 16-20, 2017.
- William R. D. Boyd, "Reactor Agnostic Multi-Group Cross Section Generation for
Fine-Mesh Deterministic Neutron Transport Simulations," Ph.D. Thesis,
Massachusetts Institute of Technology (2017).
- Zhaoyuan Liu, Kord Smith, and Benoit Forget, "A Cumulative Migration Method
for Computing Rigorous Transport Cross Sections and Diffusion Coefficients for
LWR Lattices with Monte Carlo," *Proc. PHYSOR*, Sun Valley, Idaho, May
1-5, 2016.
- Adam G. Nelson and William R. Martin, "Improved Monte Carlo tallying of
multi-group scattering moments using the NDPP code," *Trans. Am. Nucl. Soc.*,
**113**, 645-648 (2015)
- Adam G. Nelson and William R. Martin, "Improved Monte Carlo tallying of
multi-group scattering moment matrices," *Trans. Am. Nucl. Soc.*, **110**,
217-220 (2014).
- Adam G. Nelson and William R. Martin, "Improved Convergence of Monte Carlo
Generated Multi-Group Scattering Moments," *Proc. Int. Conf. Mathematics and
Computational Methods Applied to Nuclear Science and Engineering*, Sun Valley,
Idaho, May 5--9 (2013).
------------------
Doppler Broadening
------------------
- Jonathan A. Walsh, Benoit Forget, Kord S. Smith, and Forrest B. Brown,
"`On-the-fly Doppler broadening of unresolved resonance region cross sections
<https://doi.org/10.1016/j.pnucene.2017.05.032>`_," *Prog. Nucl. Energy*,
**101**, 444-460 (2017).
- Colin Josey, Pablo Ducru, Benoit Forget, and Kord Smith, "`Windowed multipole
for cross section Doppler broadening
<https://doi.org/10.1016/j.jcp.2015.08.013>`_," *J. Comput. Phys.*, **307**,
715-727 (2016).
- Jonathan A. Walsh, Benoit Forget, Kord S. Smith, and Forrest B. Brown,
"On-the-fly Doppler Broadening of Unresolved Resonance Region Cross Sections
via Probability Band Interpolation," *Proc. PHYSOR*, Sun Valley, Idaho, May
1-5, 2016.
- Jonathan A. Walsh, Benoit Forget, Kord S. Smith, Brian C. Kiedrowski, and
Forrest B. Brown, "`Direct, on-the-fly calculation of unresolved resonance
region cross sections in Monte Carlo simulations
<https://dspace.mit.edu/handle/1721.1/108644>`_," *Proc. Joint Int. Conf.
M&C+SNA+MC*,
Nashville, Tennessee, Apr. 19--23 (2015).
- Colin Josey, Benoit Forget, and Kord Smith, "`Windowed multipole sensitivity
to target accuracy of the optimization procedure
<https://doi.org/10.1080/00223131.2015.1035353>`_,"
*J. Nucl. Sci. Technol.*, **52**, 987-992 (2015).
- Paul K. Romano and Timothy H. Trumbull, "`Comparison of algorithms for Doppler
broadening pointwise tabulated cross sections
<https://doi.org/10.1016/j.anucene.2014.08.046>`_," *Ann. Nucl. Energy*,
**75**, 358--364 (2015).
- Tuomas Viitanen, Jaakko Leppanen, and Benoit Forget, "Target motion sampling
temperature treatment technique with track-length esimators in OpenMC --
Preliminary results," *Proc. PHYSOR*, Kyoto, Japan, Sep. 28--Oct. 3 (2014).
- Benoit Forget, Sheng Xu, and Kord Smith, "`Direct Doppler broadening in Monte
Carlo simulations using the multipole representation
<https://doi.org/10.1016/j.anucene.2013.09.043>`_," *Ann. Nucl. Energy*,
**64**, 78--85 (2014).
------------
Nuclear Data
------------
- Jonathan A. Walsh, "Comparison of Unresolved Resonance Region Cross Section
Formalisms in Transport Simulations," *Trans. Am. Nucl. Soc.*, **117**,
749-752 (2017).
- Jonathan A. Walsh, Benoit Forget, Kord S. Smith, and Forrest B. Brown,
"`Uncertainty in Fast Reactor-Relevant Critical Benchmark Simulations Due to
Unresolved Resonance Structure
<https://www.kns.org/files/int_paper/paper/MC2017_2017_3/P197S03-09WalshJ.pdf>`_,"
*Proc. Int. Conf. Mathematics & Computational Methods Applied to Nuclear
Science and Engineering*, Jeju, Korea, Apr. 16-20, 2017.
- Vivian Y. Tran, Jonathan A. Walsh, and Benoit Forget, "Treatments for Neutron
Resonance Elastic Scattering Using the Multipole Formalism in Monte Carlo
Codes," *Trans. Am. Nucl. Soc.*, **115**, 1133-1137 (2016).
- Paul K. Romano and Sterling M. Harper, "Nuclear data processing capabilities
in OpenMC", *Proc. Nuclear Data*, Sep. 11-16, 2016.
- Jonathan A. Walsh, Benoit Froget, Kord S. Smith, and Forrest B. Brown,
"`Neutron Cross Section Processing Methods for Improved Integral Benchmarking
of Unresolved Resonance Region Evaluations
<https://doi.org/10.1051/epjconf/201611106001>`_," *Eur. Phys. J. Web Conf.*
**111**, 06001 (2016).
- Jonathan A. Walsh, Paul K. Romano, Benoit Forget, and Kord S. Smith,
"`Optimizations of the energy grid search algorithm in continuous-energy Monte
Carlo particle transport codes
<https://doi.org/10.1016/j.cpc.2015.05.025>`_", *Comput. Phys. Commun.*,
**196**, 134-142 (2015).
- Amanda L. Lund, Andrew R. Siegel, Benoit Forget, Colin Josey, and
Paul K. Romano, "Using fractional cascading to accelerate cross section
lookups in Monte Carlo particle transport calculations," *Proc. Joint
Int. Conf. M&C+SNA+MC*, Nashville, Tennessee, Apr. 19--23 (2015).
- Ronald O. Rahaman, Andrew R. Siegel, and Paul K. Romano, "Monte Carlo
performance analysis for varying cross section parameter regimes,"
*Proc. Joint Int. Conf. M&C+SNA+MC*, Nashville, Tennessee, Apr. 19--23 (2015).
- Jonathan A. Walsh, Benoit Forget, and Kord S. Smith, "`Accelerated sampling of
the free gas resonance elastic scattering kernel
<https://doi.org/10.1016/j.anucene.2014.01.017>`_," *Ann. Nucl. Energy*,
**69**, 116--124 (2014).
-----------
Parallelism
-----------
- Paul K. Romano and Andrew R. Siegel, "`Limits on the efficiency of event-based
algorithms for Monte Carlo neutron transport
<https://www.kns.org/files/int_paper/paper/MC2017_2017_2/P099S02-02RomanoP.pdf>`_,"
*Proc. Int. Conf. Mathematics & Computational Methods Applied to Nuclear
Science and Engineering*, Jeju, Korea, Apr. 16-20, 2017.
- Paul K. Romano, John R. Tramm, and Andrew R. Siegel, "Efficacy of hardware
threading for Monte Carlo particle transport calculations on multi- and
many-core systems," *PHYSOR 2016*, Sun Valley, Idaho, May 1-5, 2016.
- David Ozog, Allen D. Malony, and Andrew R. Siegel, "A performance analysis of
SIMD algorithms for Monte Carlo simulations of nuclear reactor cores,"
*Proc. IEEE Int. Parallel and Distributed Processing Symposium*, Hyderabad,
India, May 25--29 (2015).
- David Ozog, Allen D. Malony, and Andrew Siegel, "Full-core PWR transport
simulations on Xeon Phi clusters," *Proc. Joint Int. Conf. M&C+SNA+MC*,
Nashville, Tennessee, Apr. 19--23 (2015).
- Paul K. Romano, Andrew R. Siegel, and Ronald O. Rahaman, "Influence of the
memory subsystem on Monte Carlo code performance," *Proc. Joint
Int. Conf. M&C+SNA+MC*, Nashville, Tennessee, Apr. 19--23 (2015).
- Hajime Fujita, Nan Dun, Aiman Fang, Zachary A. Rubinstein, Ziming Zheng, Kamil
Iskra, Jeff Hammond, Anshu Dubey, Pavan Balaji, and Andrew A. Chien, "Using
Global View Resilience (GVR) to add Resilience to Exascale Applications,"
*Proc. Supercomputing*, New Orleans, Louisiana, Nov. 16--21, 2014.
- Nicholas Horelik, Benoit Forget, Kord Smith, and Andrew Siegel, "Domain
decomposition and terabyte tallies with the OpenMC Monte Carlo neutron
transport code," *Proc. PHYSOR*, Kyoto Japan, Sep. 28--Oct. 3 (2014).
- John R. Tramm, Andrew R. Siegel, Tanzima Islam, and Martin Schulz, "XSBench --
the development and verification of a performance abstraction for Monte Carlo
reactor analysis," *Proc. PHYSOR*, Kyoto, Japan, Sep 28--Oct. 3, 2014.
- Nicholas Horelik, Andrew Siegel, Benoit Forget, and Kord Smith, "`Monte Carlo
domain decomposition for robust nuclear reactor analysis
<https://doi.org/10.1016/j.parco.2014.10.001>`_," *Parallel Comput.*,
**40**, 646--660 (2014).
- Andrew Siegel, Kord Smith, Kyle Felker, Paul Romano, Benoit Forget, and Peter
Beckman, "`Improved cache performance in Monte Carlo transport calculations
using energy banding <https://doi.org/10.1016/j.cpc.2013.10.008>`_,"
*Comput. Phys. Commun.*, **185** (4), 1195--1199 (2014).
- Paul K. Romano, Benoit Forget, Kord Smith, and Andrew Siegel, "`On the use of
tally servers in Monte Carlo simulations of light-water reactors
<https://doi.org/10.1051/snamc/201404301>`_," *Proc. Joint International
Conference on Supercomputing in Nuclear Applications and Monte Carlo*, Paris,
France, Oct. 27--31 (2013).
- Kyle G. Felker, Andrew R. Siegel, Kord S. Smith, Paul K. Romano, and Benoit
Forget, "`The energy band memory server algorithm for parallel Monte Carlo
calculations <https://doi.org/10.1051/snamc/201404207>`_," *Proc. Joint
International Conference on Supercomputing in Nuclear Applications and Monte
Carlo*, Paris, France, Oct. 27--31 (2013).
- John R. Tramm and Andrew R. Siegel, "`Memory Bottlenecks and Memory Contention
in Multi-Core Monte Carlo Transport Codes
<https://doi.org/10.1051/snamc/201404208>`_," *Proc. Joint International
Conference on Supercomputing in Nuclear Applications and Monte Carlo*, Paris,
France, Oct. 27--31 (2013).
- Andrew R. Siegel, Kord Smith, Paul K. Romano, Benoit Forget, and Kyle Felker,
"`Multi-core performance studies of a Monte Carlo neutron transport code
<https://doi.org/10.1177/1094342013492179>`_," *Int. J. High
Perform. Comput. Appl.*, **28** (1), 87--96 (2014).
- Paul K. Romano, Andrew R. Siegel, Benoit Forget, and Kord Smith, "`Data
decomposition of Monte Carlo particle transport simulations via tally servers
<https://doi.org/10.1016/j.jcp.2013.06.011>`_," *J. Comput. Phys.*, **252**,
20--36 (2013).
- Andrew R. Siegel, Kord Smith, Paul K. Romano, Benoit Forget, and Kyle Felker,
"`The effect of load imbalances on the performance of Monte Carlo codes in LWR
analysis <https://doi.org/10.1016/j.jcp.2012.06.012>`_," *J. Comput. Phys.*,
**235**, 901--911 (2013).
- Paul K. Romano and Benoit Forget, "Reducing Parallel Communication in Monte
Carlo Simulations via Batch Statistics," *Trans. Am. Nucl. Soc.*, **107**,
519--522 (2012).
- Paul K. Romano and Benoit Forget, "`Parallel Fission Bank Algorithms in Monte
Carlo Criticality Calculations <https://doi.org/10.13182/NSE10-98>`_,"
*Nucl. Sci. Eng.*, **170**, 125--135 (2012).
---------
Depletion
---------
- Binhang Zhang, XianBao Yuan, Yonghong Zhang, Haibo Tang, and Liangzhi Cao,
"`Development of a versatile depletion code AMAC
<https://doi.org/10.1016/j.anucene.2020.107446>`_", *Ann. Nucl. Energy*,
**143**, 107446 (2020).
- Zelong Zhao, Yongwei Yang, and Qingyu Gao, "`Development and verification of
code IMPC-Depletion for nuclide depletion calculation
<https://doi.org/10.1016/j.nucengdes.2020.110616>`_", *Nucl. Eng. Des.*,
**363**, 110616 (2020).
- Kun Zhuang, Ting Li, Qian Zhang, Qinghua He, and Tengfei Zhang, "`Extended
development of a Monte Carlo code OpenMC for fuel cycle simulation of molten
salt reactor <https://doi.org/10.1016/j.pnucene.2019.103115>`_", *Prog. Nucl.
Energy*, **118**, 103115 (2020).
- Jose L. Salcedo-Perez, Benoit Forget, Kord Smith, and Paul Romano, "Hybrid
tallies to improve performance in depletion Monte Carlo simulations," *Proc.
M&C*, 927-936, Portland, Oregon, Aug. 25-29 (2019).
- Zhao-Qing Liu, Ze-Long Zhao, Yong-Wei Yang, Yu-Cui Gao, Hai-Yan Meng, and
Qing-Yu Gao, "`Development and validation of depletion code system IMPC-Burnup
for ADS <https://doi.org/10.1007/s41365-019-0560-z>`_," *Nucl. Sci. Tech.*,
**30**: 44 (2019).
- Colin Josey, Benoit Forget, and Kord Smith, "`High order methods for the
integration of the Bateman equations and other problems of the form of y' =
F(y,t)y <https://doi.org/10.1016/j.jcp.2017.08.025>`_," *J. Comput. Phys.*,
**350**, 296-313 (2017).
- Matthew S. Ellis, Colin Josey, Benoit Forget, and Kord Smith, "`Spatially
Continuous Depletion Algorithm for Monte Carlo Simulations
<https://dspace.mit.edu/handle/1721.1/107880>`_," *Trans. Am. Nucl. Soc.*,
**115**,
1221-1224 (2016).
- Anas Gul, K. S. Chaudri, R. Khan, and M. Azeen, "`Development and verification
of LOOP: A Linkage of ORIGEN2.2 and OpenMC
<https://doi.org/10.1016/j.anucene.2016.09.016>`_," *Ann. Nucl. Energy*,
**99**, 321--327 (2017).
- Kai Huang, Hongchun Wu, Yunzhao Li, and Liangzhi Cao, "Generalized depletion
chain simplification based of significance analysis," *Proc. PHYSOR*, Sun
Valley, Idaho, May 1-5, 2016.
--------------------
Sensitivity Analysis
--------------------
- Abdulla Alhajri and Benoit Forget, "Eigenvalue Sensitivity in Monte Carlo
Simulations to Nuclear Data Parameters using the Multipole Formalism," *Proc.
M&C*, 1895-1906, Portland, Oregon, Aug. 25-29 (2019).
- Xingjie Peng, Jingang Liang, Benoit Forget, and Kord Smith, "`Calculation of
adjoint-weighted reactor kinetics parameters in OpenMC
<https://doi.org/10.1016/j.anucene.2019.01.007>`_", *Ann. Nucl. Energy*,
**128**, 231-235 (2019).
- Zeyun Wu, Jingang Liang, Xingjie Peng, and Hany S. Abdel-Khalik, "`GPT-Free
Sensitivity Analysis for Monte Carlo Models
<https://doi.org/10.1080/00295450.2018.1556062>`_", *Nucl. Technol.* (2019).
- Xingjie Peng, Jingang Liang, Abdulla Alhajri, Benoit Forget, and Kord Smith,
"`Development of continuous-energy sensitivity analysis capability in OpenMC
<https://doi.org/10.1016/j.anucene.2017.06.061>`_", *Ann. Nucl. Energy*,
**110**, 362-383 (2017).
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