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Source Range Detector Response Modeling using VERA

Publication Type
Conference Paper
Book Title
American Nuclear Society Proceedings of Top Fuel 2019
Publication Date
Page Numbers
233 to 239
Conference Name
Global and Top Fuel 2019
Conference Location
Seattle, Washington, United States of America
Conference Sponsor
ANS
Conference Date
-

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.