Zobrazeno 1 - 10
of 38
pro vyhledávání: '"Shane Stimpson"'
Publikováno v:
Nuclear Engineering and Technology, Vol 49, Iss 6, Pp 1240-1249 (2017)
An essential component of the neutron transport solver is the resonance self-shielding calculation used to determine equivalence cross sections. The neutron transport code, MPACT, is currently using the subgroup self-shielding method, in which the me
Externí odkaz:
https://doaj.org/article/662c4939a39f41288fa3559d7c3ff10f
Publikováno v:
Nuclear Science and Engineering. 195:890-905
For full-core modeling in the Virtual Environment for Reactor Analysis (VERA), the three-dimensional multigroup eigenvalue neutron transport problem is solved by MPACT. To improve the efficiency of...
Publikováno v:
Nuclear Science and Engineering. 195:778-793
Recent efforts in MPACT have focused on improving the performance of the 2D/1D subplane implementation to help target computational performance goals. This paper builds on previous efforts that tar...
Publikováno v:
Nuclear Technology. 207:582-595
The Consortium for Advanced Simulation of Light Water Reactors is developing the Virtual Environment for Reactor Applications (VERA), and the MPACT code, which is the primary deterministic neutron ...
Publikováno v:
Annals of Nuclear Energy. 132:686-701
Spatial decomposition methods based on graph partitioning are developed and implemented in the high fidelity neutron transport code MPACT. These graph-based spatial decomposition methods are more general than previous decomposition methods and typica
Autor:
Cole Gentry, Kang Seog Kim, R.W. Mills, Benjamin Collins, Shane Stimpson, Brian J Ade, Andrew J. Conant, Nicholas P. Luciano
Publikováno v:
EPJ Web of Conferences, Vol 247, p 06041 (2021)
The MPACT code, jointly developed by Oak Ridge National Laboratory and University of Michigan, is designed to perform high-fidelity light water reactor (LWR) analysis using wholecore pin-resolved neutron transport calculations on modern parallel-comp
Publikováno v:
EPJ Web of Conferences, Vol 247, p 06051 (2021)
Recent efforts in the development of the deterministic transport code MPACT have been devoted to preparing the 2D/1D subplane method to be a production-level capability, as well as leveraging a multilevel coarse mesh finite difference (CMFD) approach
Publikováno v:
EPJ Web of Conferences, Vol 247, p 02037 (2021)
Ongoing efforts are being made to improve the performance of MPACT as the deterministic neutron transport solver in the Virtual Environment for Reactor Analysis (VERA). As other parts of the code have been improved, the coarse mesh finite difference