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Title: MPACT VERA Input User s Manual, Version 2.2.0

Abstract

The MPACT (Michigan PArallel Charactistics based Transport) code is designed to perform high-fidelity light water reactor (LWR) analysis using whole-core pin-resolved neutron transport calculations on modern parallel-computing hardware. The code consists of several libraries which provide the functionality necessary to solve steady-state eigenvalue problems. Several transport capabilities are available within MPACT including both 2-D and 3-D Method of Characteristics (MOC). A three-dimensional whole core solution based on the 2D-1D solution method provides the capability for full core depletion calculations.

Authors:
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  1. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
  2. Univ. of Michigan, Ann Arbor, MI (United States)
Publication Date:
Research Org.:
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Consortium for Advanced Simulation of LWRs (CASL)
Sponsoring Org.:
USDOE
OSTI Identifier:
1342675
Report Number(s):
ORNL/TM-2016/429
CASL-U-2016-1109-000; TRN: US1701890
DOE Contract Number:  
AC05-00OR22725
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
97 MATHEMATICS AND COMPUTING; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; WATER MODERATED REACTORS; MANUALS; NEUTRON TRANSPORT; EIGENVALUES; WATER COOLED REACTORS

Citation Formats

Collins, Benjamin S., Downar, Thomas, Fitzgerald, Andrew, Gehin, Jess C., Godfrey, Andrew T., Graham, Aaron, Jabaay, Daniel, Kelley, Blake W., Kim, Kang, Kochunas, Brendan, Kulesza, Joel A., Larsen, Edward W., Liu, Yuxuan, Liu, Zhouyu, Martin, William R., Nelson, Adam G., Palmtag, Scott, Rose, Michael, Saller, Thomas, Stimpson, Shane G., Trahan, Travis, Wang, J. W., Wieselquist, William A., Young, Mitchell, and Zhu, Ang. MPACT VERA Input User s Manual, Version 2.2.0. United States: N. p., 2016. Web. doi:10.2172/1342675.
Collins, Benjamin S., Downar, Thomas, Fitzgerald, Andrew, Gehin, Jess C., Godfrey, Andrew T., Graham, Aaron, Jabaay, Daniel, Kelley, Blake W., Kim, Kang, Kochunas, Brendan, Kulesza, Joel A., Larsen, Edward W., Liu, Yuxuan, Liu, Zhouyu, Martin, William R., Nelson, Adam G., Palmtag, Scott, Rose, Michael, Saller, Thomas, Stimpson, Shane G., Trahan, Travis, Wang, J. W., Wieselquist, William A., Young, Mitchell, & Zhu, Ang. MPACT VERA Input User s Manual, Version 2.2.0. United States. doi:10.2172/1342675.
Collins, Benjamin S., Downar, Thomas, Fitzgerald, Andrew, Gehin, Jess C., Godfrey, Andrew T., Graham, Aaron, Jabaay, Daniel, Kelley, Blake W., Kim, Kang, Kochunas, Brendan, Kulesza, Joel A., Larsen, Edward W., Liu, Yuxuan, Liu, Zhouyu, Martin, William R., Nelson, Adam G., Palmtag, Scott, Rose, Michael, Saller, Thomas, Stimpson, Shane G., Trahan, Travis, Wang, J. W., Wieselquist, William A., Young, Mitchell, and Zhu, Ang. Thu . "MPACT VERA Input User s Manual, Version 2.2.0". United States. doi:10.2172/1342675. https://www.osti.gov/servlets/purl/1342675.
@article{osti_1342675,
title = {MPACT VERA Input User s Manual, Version 2.2.0},
author = {Collins, Benjamin S. and Downar, Thomas and Fitzgerald, Andrew and Gehin, Jess C. and Godfrey, Andrew T. and Graham, Aaron and Jabaay, Daniel and Kelley, Blake W. and Kim, Kang and Kochunas, Brendan and Kulesza, Joel A. and Larsen, Edward W. and Liu, Yuxuan and Liu, Zhouyu and Martin, William R. and Nelson, Adam G. and Palmtag, Scott and Rose, Michael and Saller, Thomas and Stimpson, Shane G. and Trahan, Travis and Wang, J. W. and Wieselquist, William A. and Young, Mitchell and Zhu, Ang},
abstractNote = {The MPACT (Michigan PArallel Charactistics based Transport) code is designed to perform high-fidelity light water reactor (LWR) analysis using whole-core pin-resolved neutron transport calculations on modern parallel-computing hardware. The code consists of several libraries which provide the functionality necessary to solve steady-state eigenvalue problems. Several transport capabilities are available within MPACT including both 2-D and 3-D Method of Characteristics (MOC). A three-dimensional whole core solution based on the 2D-1D solution method provides the capability for full core depletion calculations.},
doi = {10.2172/1342675},
journal = {},
number = ,
volume = ,
place = {United States},
year = {2016},
month = {6}
}

Technical Report:

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