@inproceedings{96ca596432c24265ad5cab6c2dd820a9,
title = "Validation and application of the 3D neutron transport MPACT code within CASL VERA-CS",
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).",
keywords = "CASL, MOC, Neutronics, VERA-CS",
author = "Brendan Kochunas and Thomas Downar and Dan Jabaay and Benjamin Collins and Shane Stimpson and Andrew Godfrey and Kim, \{Kang Seog\} and Jess Gehin and Scott Palmtag and Fausto Franceschini",
note = "Publisher Copyright: {\textcopyright} Copyright (2015) by American Nuclcar Society All rights reserved.; 16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2015 ; Conference date: 30-08-2015 Through 04-09-2015",
year = "2015",
language = "English",
series = "International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015",
publisher = "American Nuclear Society",
pages = "2931--2944",
booktitle = "International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015",
}