Source range detector response modeling using VERA

Research output: Contribution to conferencePaperpeer-review

1 Scopus citations

Abstract

The CASL reactor simulation package VERA has been adapted to provide high-fidelity simulation capabilities for modeling source range detector response during subcritical reactor configurations. New features include the activation and shuffling of secondary source assemblies, transfer of burned fuel neutron emission data from the ORIGEN depletion solver to the MPACT deterministic neutron transport solver, allowance of user-defined sources in MPACT based on material composition, ability to solve the subcritical source-driven system with neutron multiplication using the MPACT diffusion solver, and transfer of the calculated fission source from MPACT to the continuous energy Monte Carlo solver Shift for final detector response evaluation. These new capabilities were benchmarked against Watts Bar Unit 1 plant operating data and found to be in very good agreement.

Original languageEnglish
Pages233-239
Number of pages7
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 CASL (www.casl.gov), an Energy Innovation Hub for Modeling and Simulation of Nuclear Reactors (http://www.energy.gov/hubs) under US Department of Energy (DOE) Contract No. DE-AC05-00OR22725 This research made use of the resources of the High Performance Computing Center at Idaho National Laboratory (INL), which is supported by the DOE's Office of Nuclear Energy of the US under Contract No. DEAC07-05ID14517. This research also used resources of CADES at the Oak Ridge National Laboratory, which is supported by the Office of Science of the US Department of Energy under Contract No. DE-AC05-00OR22725. This research was supported by CASL (www.casl.gov), an Energy Innovation Hub for Modeling and Simulation of Nuclear Reactors (http://www.energy.gov/hubs) under US Department of Energy (DOE) Contract No. DE-AC05-00OR22725 This research made use of the resources of the High Performance Computing Center at Idaho National Laboratory (INL), which is supported by the DOE’s Office of Nuclear Energy of the US under Contract No. DE-AC07-05ID14517. This research also used resources of CADES at the Oak Ridge National Laboratory, which is supported by the Office of Science of the US Department of Energy under Contract No. DE-AC05-00OR22725.

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