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Title: SCALE Continuous-Energy Eigenvalue Sensitivity Coefficient Calculations

Journal Article · · Nuclear Science and Engineering
DOI:https://doi.org/10.13182/NSE15-12· OSTI ID:1246770
 [1];  [1];  [2]
  1. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
  2. Univ. of Michigan, Ann Arbor, MI (United States)
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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 data-induced 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 continuous-energy (CE) Monte Carlo applications. The Contributon-Linked eigenvalue sensitivity/Uncertainty estimation via Tracklength importance CHaracterization (CLUTCH) and Iterated Fission Probability (IFP) eigenvalue sensitivity methods were recently implemented in the CE-KENO framework of the SCALE code system to enable TSUNAMI-3D to perform eigenvalue sensitivity calculations using continuous-energy 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 continuous-energy sensitivity methods and also compares several sensitivity methods in terms of computational efficiency and memory requirements.

Research Organization:
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Sponsoring Organization:
USDOE National Nuclear Security Administration (NNSA)
Grant/Contract Number:
AC05-00OR22725
OSTI ID:
1246770
Journal Information:
Nuclear Science and Engineering, Vol. 182, Issue 3; ISSN 0029-5639
Publisher:
American Nuclear SocietyCopyright Statement
Country of Publication:
United States
Language:
English
Citation Metrics:
Cited by: 37 works
Citation information provided by
Web of Science

References (1)

The Relations Between Various Contributon Variables Used in Spatial Channel Theory journal June 1977

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Adjoint-Based Sensitivity and Uncertainty Analysis for Density and Composition: A User’s Guide journal March 2017
Nuclear data-induced uncertainty quantification of prompt neutron decay constant based on perturbation theory for ADS experiments at KUCA journal August 2019
Calculating the k -Eigenvalue Sensitivity to Typical Geometric Perturbations with the Adjoint-Weighted Method in the Continuous-Energy Reactor Monte Carlo Code RMC journal June 2019
Experimental analysis and uncertainty quantification using random sampling technique for ADS experiments at KUCA journal November 2017
Further development of methodology to model TRISO fuel and BISO absorber particles and related uncertainty quantification using SCALE 6 journal May 2019
Estimating Code Biases for Criticality Safety Applications with Few Relevant Benchmarks journal May 2019
GPT-Free Sensitivity Analysis for Monte Carlo Models journal January 2019
Nuclear data-induced uncertainty quantification of prompt neutron decay constant based on perturbation theory for ADS experiments at KUCA text January 2019
Nuclear data-induced uncertainty quantification of prompt neutron decay constant based on perturbation theory for ADS experiments at KUCA text January 2019

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46 INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND TECHNOLOGY
TSUNAMI
eigenvalue sensitivity coefficients
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