SCALE ContinuousEnergy Eigenvalue Sensitivity Coefficient Calculations
Sensitivity coefficients describe the fractional change in a system response that is induced by changes to system parameters and nuclear data. The Tools for Sensitivity and UNcertainty Analysis Methodology Implementation (TSUNAMI) code within the SCALE code system makes use of eigenvalue sensitivity coefficients for an extensive number of criticality safety applications, including quantifying the datainduced uncertainty in the eigenvalue of critical systems, assessing the neutronic similarity between different critical systems, and guiding nuclear data adjustment studies. The need to model geometrically complex systems with improved fidelity and the desire to extend TSUNAMI analysis to advanced applications has motivated the development of a methodology for calculating sensitivity coefficients in continuousenergy (CE) Monte Carlo applications. The ContributonLinked eigenvalue sensitivity/Uncertainty estimation via Tracklength importance CHaracterization (CLUTCH) and Iterated Fission Probability (IFP) eigenvalue sensitivity methods were recently implemented in the CEKENO framework of the SCALE code system to enable TSUNAMI3D to perform eigenvalue sensitivity calculations using continuousenergy Monte Carlo methods. This work provides a detailed description of the theory behind the CLUTCH method and describes in detail its implementation. This work explores the improvements in eigenvalue sensitivity coefficient accuracy that can be gained through the use of continuousenergy sensitivity methods and also compares severalmore »
 Authors:

^{[1]};
^{[1]};
^{[2]}
 Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
 Univ. of Michigan, Ann Arbor, MI (United States)
 Publication Date:
 Grant/Contract Number:
 AC0500OR22725
 Type:
 Accepted Manuscript
 Journal Name:
 Nuclear Science and Engineering
 Additional Journal Information:
 Journal Volume: 182; Journal Issue: 3; Journal ID: ISSN 00295639
 Publisher:
 American Nuclear Society
 Research Org:
 Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
 Sponsoring Org:
 USDOE National Nuclear Security Administration (NNSA)
 Country of Publication:
 United States
 Language:
 English
 Subject:
 46 INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND TECHNOLOGY; TSUNAMI; eigenvalue sensitivity coefficients; Monte Carlo
 OSTI Identifier:
 1246770
Perfetti, Christopher M., Rearden, Bradley T., and Martin, William R.. SCALE ContinuousEnergy Eigenvalue Sensitivity Coefficient Calculations. United States: N. p.,
Web. doi:10.13182/NSE1512.
Perfetti, Christopher M., Rearden, Bradley T., & Martin, William R.. SCALE ContinuousEnergy Eigenvalue Sensitivity Coefficient Calculations. United States. doi:10.13182/NSE1512.
Perfetti, Christopher M., Rearden, Bradley T., and Martin, William R.. 2016.
"SCALE ContinuousEnergy Eigenvalue Sensitivity Coefficient Calculations". United States.
doi:10.13182/NSE1512. https://www.osti.gov/servlets/purl/1246770.
@article{osti_1246770,
title = {SCALE ContinuousEnergy Eigenvalue Sensitivity Coefficient Calculations},
author = {Perfetti, Christopher M. and Rearden, Bradley T. and Martin, William R.},
abstractNote = {Sensitivity coefficients describe the fractional change in a system response that is induced by changes to system parameters and nuclear data. The Tools for Sensitivity and UNcertainty Analysis Methodology Implementation (TSUNAMI) code within the SCALE code system makes use of eigenvalue sensitivity coefficients for an extensive number of criticality safety applications, including quantifying the datainduced uncertainty in the eigenvalue of critical systems, assessing the neutronic similarity between different critical systems, and guiding nuclear data adjustment studies. The need to model geometrically complex systems with improved fidelity and the desire to extend TSUNAMI analysis to advanced applications has motivated the development of a methodology for calculating sensitivity coefficients in continuousenergy (CE) Monte Carlo applications. The ContributonLinked eigenvalue sensitivity/Uncertainty estimation via Tracklength importance CHaracterization (CLUTCH) and Iterated Fission Probability (IFP) eigenvalue sensitivity methods were recently implemented in the CEKENO framework of the SCALE code system to enable TSUNAMI3D to perform eigenvalue sensitivity calculations using continuousenergy Monte Carlo methods. This work provides a detailed description of the theory behind the CLUTCH method and describes in detail its implementation. This work explores the improvements in eigenvalue sensitivity coefficient accuracy that can be gained through the use of continuousenergy sensitivity methods and also compares several sensitivity methods in terms of computational efficiency and memory requirements.},
doi = {10.13182/NSE1512},
journal = {Nuclear Science and Engineering},
number = 3,
volume = 182,
place = {United States},
year = {2016},
month = {2}
}