PROTEUSSN User Manual
Abstract
PROTEUSSN is a threedimensional, highly scalable, highfidelity neutron transport code developed at Argonne National Laboratory. The code is applicable to all spectrum reactor transport calculations, particularly those in which a high degree of fidelity is needed either to represent spatial detail or to resolve solution gradients. PROTEUSSN solves the second order formulation of the transport equation using the continuous Galerkin finite element method in space, the discrete ordinates approximation in angle, and the multigroup approximation in energy. PROTEUSSN’s parallel methodology permits the efficient decomposition of the problem by both space and angle, permitting large problems to run efficiently on hundreds of thousands of cores. PROTEUSSN can also be used in serial or on smaller compute clusters (10’s to 100’s of cores) for smaller homogenized problems, although it is generally more computationally expensive than traditional homogenized methodology codes. PROTEUSSN has been used to model partially homogenized systems, where regions of interest are represented explicitly and other regions are homogenized to reduce the problem size and required computational resources. PROTEUSSN solves forward and adjoint eigenvalue problems and permits both neutron upscattering and downscattering. An adiabatic kinetics option has recently been included for performing simple timedependent calculations in addition to standard steady statemore »
 Authors:

 Argonne National Lab. (ANL), Argonne, IL (United States)
 Publication Date:
 Research Org.:
 Argonne National Lab. (ANL), Argonne, IL (United States)
 Sponsoring Org.:
 USDOE Office of Nuclear Energy (NE)
 OSTI Identifier:
 1240157
 Report Number(s):
 ANL/NE14/6 (Rev 3.0)
125699
 DOE Contract Number:
 AC0206CH11357
 Resource Type:
 Technical Report
 Country of Publication:
 United States
 Language:
 English
 Subject:
 97 MATHEMATICS AND COMPUTING
Citation Formats
Shemon, Emily R., Smith, Micheal A., and Lee, Changho. PROTEUSSN User Manual. United States: N. p., 2016.
Web. doi:10.2172/1240157.
Shemon, Emily R., Smith, Micheal A., & Lee, Changho. PROTEUSSN User Manual. United States. doi:10.2172/1240157.
Shemon, Emily R., Smith, Micheal A., and Lee, Changho. Tue .
"PROTEUSSN User Manual". United States. doi:10.2172/1240157. https://www.osti.gov/servlets/purl/1240157.
@article{osti_1240157,
title = {PROTEUSSN User Manual},
author = {Shemon, Emily R. and Smith, Micheal A. and Lee, Changho},
abstractNote = {PROTEUSSN is a threedimensional, highly scalable, highfidelity neutron transport code developed at Argonne National Laboratory. The code is applicable to all spectrum reactor transport calculations, particularly those in which a high degree of fidelity is needed either to represent spatial detail or to resolve solution gradients. PROTEUSSN solves the second order formulation of the transport equation using the continuous Galerkin finite element method in space, the discrete ordinates approximation in angle, and the multigroup approximation in energy. PROTEUSSN’s parallel methodology permits the efficient decomposition of the problem by both space and angle, permitting large problems to run efficiently on hundreds of thousands of cores. PROTEUSSN can also be used in serial or on smaller compute clusters (10’s to 100’s of cores) for smaller homogenized problems, although it is generally more computationally expensive than traditional homogenized methodology codes. PROTEUSSN has been used to model partially homogenized systems, where regions of interest are represented explicitly and other regions are homogenized to reduce the problem size and required computational resources. PROTEUSSN solves forward and adjoint eigenvalue problems and permits both neutron upscattering and downscattering. An adiabatic kinetics option has recently been included for performing simple timedependent calculations in addition to standard steady state calculations. PROTEUSSN handles void and reflective boundary conditions. Multigroup cross sections can be generated externally using the MC23 fast reactor multigroup cross section generation code or internally using the cross section application programming interface (API) which can treat the subgroup or resonance table libraries. PROTEUSSN is written in Fortran 90 and also includes C preprocessor definitions. The code links against the PETSc, METIS, HDF5, and MPICH libraries. It optionally links against the MOAB library and is a part of the SHARP multiphysics suite for coupled multiphysics analysis of nuclear reactors. This user manual describes how to set up a neutron transport simulation with the PROTEUSSN code. A companion methodology manual describes the theory and algorithms within PROTEUSSN.},
doi = {10.2172/1240157},
journal = {},
number = ,
volume = ,
place = {United States},
year = {2016},
month = {2}
}