MPACT VERA Input User s Manual, Version 2.2.0

Technical Report · Thu Jun 09 00:00:00 EDT 2016

DOI:https://doi.org/10.2172/1342675· OSTI ID:1342675

Collins, Benjamin S. ^[1]; Downar, Thomas ^[2]; Fitzgerald, Andrew ^[2]; Gehin, Jess C. ^[1]; Godfrey, Andrew T. ^[1]; Graham, Aaron ^[2]; Jabaay, Daniel ^[2]; Kelley, Blake W. ^[2]; Kim, Kang ^[1]; Kochunas, Brendan ^[2]; Kulesza, Joel A. ^[2]; Larsen, Edward W. ^[2]; Liu, Yuxuan ^[2]; Liu, Zhouyu ^[2]; Martin, William R. ^[2]; Nelson, Adam G. ^[2]; Palmtag, Scott ^[1]; Rose, Michael ^[2]; Saller, Thomas ^[2]; Stimpson, Shane G. ^[1] ; Trahan, Travis ^[2]; Wang, J. W. ^[2]; Wieselquist, William A. ^[1]; Young, Mitchell ^[2]; Zhu, Ang ^[2]

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1. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
2. Univ. of Michigan, Ann Arbor, MI (United States)

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.

• Research Organization: Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Consortium for Advanced Simulation of LWRs (CASL)
• Sponsoring Organization: USDOE
• DOE Contract Number: AC05-00OR22725
• OSTI ID: 1342675
• Report Number(s): ORNL/TM-2016/429; CASL-U-2016-1109-000; TRN: US1701890
• Country of Publication: United States
• Language: English

Related Subjects

97 MATHEMATICS AND COMPUTING
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
WATER MODERATED REACTORS
MANUALS
NEUTRON TRANSPORT
EIGENVALUES
WATER COOLED REACTORS