.. _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 <http://hdl.handle.net/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
  <http://hdl.handle.net/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
  <http://hdl.handle.net/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).
