Issue |
EPJ Web Conf.
Volume 247, 2021
PHYSOR2020 – International Conference on Physics of Reactors: Transition to a Scalable Nuclear Future
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|
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Article Number | 10014 | |
Number of page(s) | 9 | |
Section | Verification & Validation | |
DOI | https://doi.org/10.1051/epjconf/202124710014 | |
Published online | 22 February 2021 |
https://doi.org/10.1051/epjconf/202124710014
VERA-CS VALIDATION OF CRITICAL EXPERIMENTS
North Carolina State University Department of Nuclear Engineering, North Carolina State University, Raleigh, NC, USA 27695-7909
vnnovell@ncsu.edu
sppalmta@ncsu.edu
Published online: 22 February 2021
VERA is a suite of multiphysics codes which uses MPACT to model neutron transport in light water reactors (LWRs) [1]. In this paper, we validate MPACT by modeling critical experiments conducted at the IPEN/MB-01 and B&W facilities. We modeled critical loading experiments with a variety of different fuel pins and materials placed in the core. The experiments were modeled in two dimensions using MPACT and an axial buckling term. Default mesh parameters exist in MPACT for modeling larger reactor cores, and a mesh convergence study was performed to find appropriate mesh parameters for modeling the smaller critical reactors. The keff results show a consistent bias and small standard deviation for the IPEN/MB-01 reactor and a small bias and small standard deviation for the B&W facility. Overall, the results show that MPACT performs well for modeling small critical reactors.
Key words: IPEN / B&W / VERA / CASL / MPACT / Validation
© The Authors, published by EDP Sciences, 2021
This is an Open Access article distributed under the terms of the Creative Commons Attribution License 4.0, which permits unrestricted use, distribution, and reproduction in any medium, provided the original work is properly cited.
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