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Update list of publications, fix documentation for CMFD
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Paul Romano
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3 changed files with 59 additions and 32 deletions
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@ -62,6 +62,11 @@ Coupling and Multi-physics
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<https://doi.org/10.1007/s41365-018-0539-1>`_," *Nucl. Sci. Tech.*, **30**
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(2019).
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- April Novak, Paul Romano, Brycen Wendt, Ron Rahaman, Elia Merzari, Leslie
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Kerby, Cody Permann, Richard Martineau, and Rachel N. Slaybaugh, "Preliminary
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Coupling of OpenMC and Nek5000 within the MOOSE Framework," *Proc. PHYSOR*,
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Cancun, Mexico, Apr. 22-26 (2018).
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- Jun Chen, Liangzhi Cao, Chuanqi Zhao, and Zhouyu Liu, "`Development of
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Subchannel Code SUBSC for high-fidelity multi-physics coupling application
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<https://doi.org/10.1016/j.egypro.2017.08.121>`_", *Energy Procedia*, **127**,
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@ -129,6 +134,10 @@ Geometry and Visualization
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Miscellaneous
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-------------
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- Amanda L. Lund and Paul K. Romano, "`Implementation and Validation of Photon
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Transport in OpenMC <https://doi.org/10.2172/1490825>`_", Argonne National
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Laboratory, Technical Report ANL/MCS-TM-381 (2018).
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- Bruno Merk, Dzianis Litskevich, R. Gregg, and A. R. Mount, "`Demand driven
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salt clean-up in a molten salt fast reactor -- Defining a priority list
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<https://doi.org/10.1371/journal.pone.0192020>`_", *PLOS One*, **13**,
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@ -191,6 +200,10 @@ Miscellaneous
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Multi-group Cross Section Generation
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------------------------------------
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- Changho Lee and Yeon Sang Jung, "Verification of the Cross Section Library
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Generated Using OpenMC and MC\ :sup:`2`-3 for PROTEUS," *Proc. PHYSOR*, Cancun,
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Mexico, Apr. 22-26 (2018).
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- Zhaoyuan Liu, Kord Smith, Benoit Forget, and Javier Ortensi, "`Cumulative
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migration method for computing rigorous diffusion coefficients and transport
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cross sections from Monte Carlo
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@ -454,3 +467,21 @@ Depletion
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- Kai Huang, Hongchun Wu, Yunzhao Li, and Liangzhi Cao, "Generalized depletion
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chain simplification based of significance analysis," *Proc. PHYSOR*, Sun
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Valley, Idaho, May 1-5, 2016.
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--------------------
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Sensitivity Analysis
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--------------------
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- Xingjie Peng, Jingang Liang, Benoit Forget, and Kord Smith, "`Calculation of
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adjoint-weighted reactor kinetics parameters in OpenMC
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<https://doi.org/10.1016/j.anucene.2019.01.007>`_", *Ann. Nucl. Energy*,
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**128**, 231-235 (2019).
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- Zeyun Wu, Jingang Liang, Xingjie Peng, and Hany S. Abdel-Khalik, "`GPT-Free
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Sensitivity Analysis for Monte Carlo Models
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<https://doi.org/10.1080/00295450.2018.1556062>`_", *Nucl. Technol.* (2019).
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- Xingjie Peng, Jingang Liang, Abdulla Alhajri, Benoit Forget, and Kord Smith,
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"`Development of continuous-energy sensitivity analysis capability in OpenMC
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<https://doi.org/10.1016/j.anucene.2017.06.061>`_", *Ann. Nucl. Energy*,
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**110**, 362-383 (2017).
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@ -202,27 +202,20 @@ Coarse Mesh Finite Difference Acceleration
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------------------------------------------
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CMFD is implemented in OpenMC and allows users to accelerate fission source
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convergence during inactive neutron batches. To run CMFD, the CMFDRun class
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should be used, and :mod:`from openmc import cmfd` should be included at the
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top of the Python input file. Additionally, this class has a dependence on the
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C API.
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convergence during inactive neutron batches. To use CMFD, the
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:class:`openmc.cmfd.CMFDRun` class executes OpenMC through the C API, solving
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the CMFD system between fission generations and modifying the source weights.
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Note that the :mod:`openmc.cmfd` module is not imported by default with the
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:mod:`openmc` namespace and needs to be imported explicitly.
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.. autosummary::
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:toctree: generated
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:nosignatures:
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:template: myclass.rst
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openmc.CMFDMesh
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openmc.CMFDRun
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At the minimum, a CMFD mesh needs to be specified in order to run CMFD. Once
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these properties are set, an OpenMC simulation can be run with CMFD turned on
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with the function:
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.. autosummary::
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:toctree: generated
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:nosignatures:
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:template: myfunction.rst
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openmc.CMFDRun.run
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openmc.cmfd.CMFDMesh
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openmc.cmfd.CMFDRun
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At the minimum, a CMFD mesh needs to be specified in order to run CMFD. Once the
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mesh and other optional properties are set, a simulation can be run with CMFD
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turned on using :meth:`openmc.cmfd.CMFDRun.run`.
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@ -53,7 +53,7 @@ _CURRENTS = {
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class CMFDMesh(object):
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""""A structured Cartesian mesh used for CMFD acceleration.
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"""A structured Cartesian mesh used for CMFD acceleration.
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Attributes
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----------
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@ -199,14 +199,16 @@ class CMFDRun(object):
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display : dict
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Dictionary indicating which CMFD results to output. Note that CMFD
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k-effective will always be outputted. Acceptable keys are:
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* "balance" - Whether to output RMS [%] of the resdiual from the
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neutron balance equation on CMFD tallies (bool)
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* "dominance" - Whether to output the estimated dominance ratio from
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the CMFD iterations (bool)
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* "entropy" - Whether to output the *entropy* of the CMFD predicted
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fission source (bool)
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* "source" - Whether to ouput the RMS [%] between the OpenMC fission
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source and CMFD fission source (bool)
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* "balance" - Whether to output RMS [%] of the resdiual from the
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neutron balance equation on CMFD tallies (bool)
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* "dominance" - Whether to output the estimated dominance ratio from
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the CMFD iterations (bool)
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* "entropy" - Whether to output the *entropy* of the CMFD predicted
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fission source (bool)
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* "source" - Whether to ouput the RMS [%] between the OpenMC fission
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source and CMFD fission source (bool)
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downscatter : bool
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Indicate whether an effective downscatter cross section should be used
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when using 2-group CMFD.
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@ -215,7 +217,7 @@ class CMFDRun(object):
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of fission source neutrons on the next OpenMC batch. Defaults to False.
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cmfd_ktol : float
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Tolerance on the eigenvalue when performing CMFD power iteration
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mesh : openmc.CMFDMesh
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mesh : openmc.cmfd.CMFDMesh
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Structured mesh to be used for acceleration
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norm : float
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Normalization factor applied to the CMFD fission source distribution
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@ -244,16 +246,17 @@ class CMFDRun(object):
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``run_adjoint`` must be true for an adjoint calculation to be
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perfomed. Options are:
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* "physical" - Create adjoint matrices from physical parameters of
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CMFD problem
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* "math" - Create adjoint matrices mathematically as the transpose of
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loss and production CMFD matrices
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* "physical" - Create adjoint matrices from physical parameters of
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CMFD problem
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* "math" - Create adjoint matrices mathematically as the transpose of
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loss and production CMFD matrices
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indices : numpy.ndarray
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Stores spatial and group dimensions as [nx, ny, nz, ng]
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cmfd_src : numpy.ndarray
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CMFD source distribution calculated from solving CMFD equations
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entropy : list of floats
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"Shannon entropy" from cmfd fission source, stored for each generation
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"Shannon entropy" from CMFD fission source, stored for each generation
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that CMFD is invoked
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balance : list of floats
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RMS of neutron balance equations, stored for each generation that CMFD
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