Abstract
MPACT is a new high-fidelity neutron transport code designed to provide an advanced pin-resolved transport capability for the VERA (Virtual Environment for Reactor Applications) which is the end-user reactor simulation tool being developed for the Consortium for the Advanced Simulation of Light Water Reactors (CASL). The transport methods currently implemented in MPACT are based on the 2-D/l-D method of characteristics (MOC) capabilities to provide a pin-resolved solution of the neutron flux and power throughout the reactor. The cross section resonance treatment utilizes the subgroup method and thermal-hydraulic feedback capability within MPACT includes a simplified T/H feedback model, as well as coupling to the subchannel code CTF and ongoing work to couple MPACT to Computational Fluid Dynamics (CFD). Other features include full core depletion and parallel execution enabling efficient scaling up to 0(105) processors. This capability has been validated for several benchmark problems and several cycles of operating Pressurized Water Reactors (PWR).
Original language | English |
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Title of host publication | International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015 |
Publisher | American Nuclear Society |
Pages | 2931-2944 |
Number of pages | 14 |
ISBN (Electronic) | 9781510811843 |
State | Published - 2015 |
Event | 16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2015 - Chicago, United States Duration: Aug 30 2015 → Sep 4 2015 |
Publication series
Name | International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015 |
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Volume | 4 |
Conference
Conference | 16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2015 |
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Country/Territory | United States |
City | Chicago |
Period | 08/30/15 → 09/4/15 |
Funding
ACKNOWLEDGEMENTS This research was supported by the Consortium for Advanced Simulation of Light Water Reactors (wvw.casl.gov'). an Energy Innovation Hub (http://www.energy.gov/hubs') for Modeling and Simulation of Nuclear Reactors under U.S. Department of Energy, and used resources of the Oak Ridge Leadership Computing Facility at the Oak Ridge National Laboratory.
Keywords
- CASL
- MOC
- Neutronics
- VERA-CS