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Title: Source Range Detector Response Modeling using VERA

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.

Authors:
ORCiD logo [1]; ORCiD logo [1]; ORCiD logo [1]; ORCiD logo [1]; ORCiD logo [1]; ORCiD logo [1]; ORCiD logo [1]; ORCiD logo [1]; ORCiD logo [1]; ORCiD logo [1]; ORCiD logo [1]; ORCiD logo [1];  [1];  [1]
  1. ORNL
Publication Date:
Research Org.:
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Sponsoring Org.:
USDOE
OSTI Identifier:
1570126
DOE Contract Number:  
AC05-00OR22725
Resource Type:
Conference
Resource Relation:
Conference: Global/Top Fuel 2019 - Seattle, Washington, United States of America - 9/22/2019 8:00:00 AM-9/27/2019 8:00:00 AM
Country of Publication:
United States
Language:
English

Citation Formats

Gentry, Cole A., Godfrey, Andrew T., Davidson, Eva E., Ilas, Germina, Collins, Benjamin S., Hart, Shane W., Kim, Kang Seog, Pandya, Tara M., Royston, Katherine E., Davidson, Gregory G., Johnson, Seth R., Evans, Thomas M., Wolfram, Gary T., and Palmtag, Scott. Source Range Detector Response Modeling using VERA. United States: N. p., 2019. Web.
Gentry, Cole A., Godfrey, Andrew T., Davidson, Eva E., Ilas, Germina, Collins, Benjamin S., Hart, Shane W., Kim, Kang Seog, Pandya, Tara M., Royston, Katherine E., Davidson, Gregory G., Johnson, Seth R., Evans, Thomas M., Wolfram, Gary T., & Palmtag, Scott. Source Range Detector Response Modeling using VERA. United States.
Gentry, Cole A., Godfrey, Andrew T., Davidson, Eva E., Ilas, Germina, Collins, Benjamin S., Hart, Shane W., Kim, Kang Seog, Pandya, Tara M., Royston, Katherine E., Davidson, Gregory G., Johnson, Seth R., Evans, Thomas M., Wolfram, Gary T., and Palmtag, Scott. Sun . "Source Range Detector Response Modeling using VERA". United States. https://www.osti.gov/servlets/purl/1570126.
@article{osti_1570126,
title = {Source Range Detector Response Modeling using VERA},
author = {Gentry, Cole A. and Godfrey, Andrew T. and Davidson, Eva E. and Ilas, Germina and Collins, Benjamin S. and Hart, Shane W. and Kim, Kang Seog and Pandya, Tara M. and Royston, Katherine E. and Davidson, Gregory G. and Johnson, Seth R. and Evans, Thomas M. and Wolfram, Gary T. and Palmtag, Scott},
abstractNote = {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.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {2019},
month = {9}
}

Conference:
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