Published 2013 | Version v1
Book

Overview of development and design of MPACT: Michigan parallel characteristics transport code

  • 1. Department of Nuclear Engineering and Radiological Sciences, University of Michigan, 2200 Bonisteel, Ann Arbor, MI 48109 (United States)

Description

MPACT (Michigan Parallel Characteristics Transport Code) is a new reactor analysis tool. It is being developed by students and research staff at the University of Michigan to be used for an advanced pin-resolved transport capability within VERA (Virtual Environment for Reactor Analysis). VERA is the end-user reactor simulation tool being produced by the Consortium for the Advanced Simulation of Light Water Reactors (CASL). The MPACT development project is itself unique for the way it is changing how students do research to achieve the instructional and research goals of an academic institution, while providing immediate value to industry. The MPACT code makes use of modern lean/agile software processes and extensive testing to maintain a level of productivity and quality required by CASL. MPACT's design relies heavily on object-oriented programming concepts and design patterns and is programmed in Fortran 2003. These designs are explained and illustrated as to how they can be readily extended to incorporate new capabilities and research ideas in support of academic research objectives. The transport methods currently implemented in MPACT include the 2-D and 3-D method of characteristics (MOC) and 2-D and 3-D method of collision direction probabilities (CDP). For the cross section resonance treatment, presently the subgroup method and the new embedded self-shielding method (ESSM) are implemented within MPACT. (authors)

Additional details

Publishing Information

Publisher
American Nuclear Society - ANS
Imprint Place
La Grange Park (United States)
ISBN
978-0-89448-700-2
Imprint Title
Proceedings of the 2013 International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering - M and C 2013
Imprint Pagination
3016 p.
Journal Page Range
p. 42-53

Conference

Title
2013 International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering
Acronym
M and C 2013
Dates
5-9 May 2013
Place
Sun Valley, ID (United States)

INIS

Country of Publication
United States
Country of Input or Organization
France
INIS RN
45033649
Subject category
S97: MATHEMATICAL METHODS AND COMPUTING; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference
Quality check status
Yes
Descriptors DEI
DESIGN; FORTRAN; I CODES; NEUTRON TRANSPORT; REACTOR PHYSICS; SIMULATION; WATER COOLED REACTORS; WATER MODERATED REACTORS;
Descriptors DEC
COMPUTER CODES; NEUTRAL-PARTICLE TRANSPORT; PHYSICS; PROGRAMMING LANGUAGES; RADIATION TRANSPORT; REACTORS;

Optional Information

Lead record
cgjt4-fyf07
Notes
21 refs.