Impact of Radial Reflector Fidelity on Neutronics and Vessel Fluence Simulations

S. Stimpson, T. Pandya, K. Royston, B. Collins, A. Godfrey

Research output: Contribution to journalArticlepeer-review

2 Scopus citations

Abstract

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 transport solver in VERA, provides sub-pin level flux and power distributions as part of full-scale cycle depletion and analysis. In such calculations, an important aspect is the radial reflector treatment. To improve the fidelity of the radial reflector treatment, MPACT was extended to approximate the modeling of the reactor’s structural components such as the core shroud, barrel, neutron pads, and vessel. This work explores several modeling configurations with varying levels of fidelity and computational burden and assesses the importance of modeling fidelity on the eigenvalue and pin power distribution. Two two-dimensional (2-D) problems were analyzed to assess the impact on eigenvalue and pin power distributions with low-fidelity, coarse square cell reflector representations: (1) a Watts Bar Nuclear Plant Unit 1 (WBN1) quarter-core slice with depletion and (2) an AP1000 quarter-core slice. The analyses showed that the effect on eigenvalue is fairly small, but the effect on pin power is more pronounced, especially locally in the assemblies closest to the periphery, where the maximum pin power difference is nearly 3.5% in the AP1000 case. Two additional 2-D problems were used to assess the comparison between the low-fidelity coarse square cell treatment and a high-fidelity geometric representation that uses subpin material specification: (1) the same WBN1 quarter-core slice and (2) a representative model of the NuScale small modular reactor (SMR), which features a solid reflector design with moderator holes. These results demonstrate that even a coarse, low-fidelity representation adequately captures the necessary simulation characteristics. Last, these capabilities were applied to the 2-D WBN1 quarter-core depletion to assess the impact on vessel fluence using VeraShift. From adjoint calculations, pins along the periphery were observed to be of highest importance for fluence calculation, so the impact of the reflector representation in MPACT could theoretically substantially affect the predicted result. However, it was observed that the change in pin powers along the periphery minimally impacts the maximum vessel fluence with a difference within the statistical uncertainty but provides terrific insight on the sensitivity of the peripheral pins.

Original languageEnglish
Pages (from-to)582-595
Number of pages14
JournalNuclear Technology
Volume207
Issue number4
DOIs
StatePublished - 2021

Funding

This work was supported by CASL ( www.casl.gov ), an energy innovation hub ( http://www.energy.gov/hubs ) for modeling and simulation of nuclear reactors under U.S. Department of Energy (DOE) contract number DE-AC05-00OR22725. This research also used resources of the Compute and Data Environment for Science at ORNL, which is supported by the DOE Office of Science.

FundersFunder number
Energy Innovation Hub
U.S. Department of EnergyDE-AC05-00OR22725
Office of Science
Center for Applied Strategic Learning

    Keywords

    • MPACT
    • Shift
    • VERA
    • reflector
    • vessel fluence

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