VERA-CS VALIDATION OF CRITICAL EXPERIMENTS

Author:

Novellino Vincent,Palmtag Scott

Abstract

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.

Publisher

EDP Sciences

Reference11 articles.

1. Kochunas B. et al. “VERA Core Simulator Methodology for Pressurized Water Reactor Cycle Depletion.” Nucl Sci Eng, volume 185 (2017).

2. Palmtag S., Godfrey A., Baird M., and Walker E.. “VERA Common Input.” Revision 3. CASL Technical Report: CASL-U-2014-0014-003, Consortium for Advanced Simulation of Light Water Reactors (2019).

3. Godfrey A.. “VERA-CS Validation Plan.” Revision 0. CASL Technical Report: CASL-U-0185-000, Consortium for Advanced Simulation of Light Water Reactors (2014).

4. Hykes J., Ferrer R., and Rhodes J.. “CASMO5 Analysis of Select IPEN/MB-01 Experiments.” In PHYSOR 2018: Reactor Physics Paving the Way Towards More Efficient Systems. American Nuclear Society, Cancun, Mexico (2018).

5. Wemple C. A.. “Benchmarking the HELIOS-2 ENDF/B-VII Library: B&W-1484 and DIMPLE S-06 Criticals.” In Advances in Nuclear Fuel Management IV (ANFM 2009). American Nuclear Society, Hilton Head, SC, USA (2009).

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