Inference of crud model parameters from plant data

Benjamin Collins, William Gurecky, Lindsay Gilkey, Alicia Elliott, David Kropaczek

Research output: Contribution to conferencePaperpeer-review

Abstract

Over the past several years, the Virtual Environment for Reactor Analysis, VERA, has provided a novel capability for the Consortium for Advanced Simulation of Light Water Reactors (CASL) to model crud-induced power shift (CIPS) in reactors operated by the Tennessee Valley Authority (TVA). While this developed capability in VERA is unique, multiple key parameters in the crud physics have remained unknown. The methodology employed here provides the capability to infer these key model parameters from measured plant data. Once the model parameters have been determined, a forward VERA computation is performed and results are compared to measured flux map data to determine the efficacy of the calibrated crud model.

Original languageEnglish
Pages326-333
Number of pages8
StatePublished - 2020
Event14th International Nuclear Fuel Cycle Conference, GLOBAL 2019 and Light Water Reactor Fuel Performance Conference, TOP FUEL 2019 - Seattle, United States
Duration: Sep 22 2019Sep 27 2019

Conference

Conference14th International Nuclear Fuel Cycle Conference, GLOBAL 2019 and Light Water Reactor Fuel Performance Conference, TOP FUEL 2019
Country/TerritoryUnited States
CitySeattle
Period09/22/1909/27/19

Funding

This research was supported by the Consortium for Advanced Simulation of Light Water Reactors (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 Contract No. DE-AC05-00OR22725. This research was supported by the Consortium for Advanced Simulation of Light Water Reactors (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 Contract No. DE-AC05-00OR22725. This research made use of the resources of the High Performance Computing Center at Idaho National Laboratory, which is supported by the Office of Nuclear Energy of the US Department of Energy under Contract No. DE-AC07-05ID14517. Notice: This manuscript has been authored by UT-Battelle, LLC, under Contract No. DE-AC05-00OR22725 with the US Department of Energy (DOE). The US government retains and the publisher, by accepting the article for publication, acknowledges that the US government retains a nonexclusive, paid-up, irrevocable, worldwide license to publish or reproduce the published form of this manuscript, or allow others to do so, for US government purposes. DOE will provide public access to these results of federally sponsored research in accordance with the DOE Public Access Plan (http://energy. gov/downloads/doe-public-access-plan).

FundersFunder number
Consortium for Advanced Simulation of Light Water Reactors
Energy Innovation Hub
Modeling and Simulation of Nuclear Reactors
US Department of EnergyDE-AC07-05ID14517
U.S. Department of EnergyDE-AC05-00OR22725
Office of Nuclear Energy

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