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Title: Verification of Reduced Order Modeling Based Uncertainty/Sensitivity Estimator (ROMUSE)

Abstract

This article presents a number of verification case studies for a recently developed sensitivity/uncertainty code package. The code package, ROMUSE (Reduced Order Modeling based Uncertainty/Sensitivity Estimator) is an effort to provide an analysis tool to be used in conjunction with reactor core simulators, in particular the Virtual Environment for Reactor Applications (VERA) core simulator. ROMUSE has been written in C++ and is currently capable of performing various types of parameter perturbations and associated sensitivity analysis, uncertainty quantification, surrogate model construction and subspace analysis. The current version 2.0 has the capability to interface with the Design Analysis Kit for Optimization and Terascale Applications (DAKOTA) code, which gives ROMUSE access to the various algorithms implemented within DAKOTA, most importantly model calibration. The verification study is performed via two basic problems and two reactor physics models. The first problem is used to verify the ROMUSE single physics gradient-based range finding algorithm capability using an abstract quadratic model. The second problem is the Brusselator problem, which is a coupled problem representative of multi-physics problems. This problem is used to test the capability of constructing surrogates via ROMUSE-DAKOTA. Finally, light water reactor pin cell and sodium-cooled fast reactor fuel assembly problems are simulated via SCALEmore » 6.1 to test ROMUSE capability for uncertainty quantification and sensitivity analysis purposes.« less

Authors:
 [1]; ORCiD logo [2]; ORCiD logo [3]; ORCiD logo [1]
  1. Univ. of Sharjah, Sharjah (United Arab Emirates). Dept. of Mechanical and Nuclear Engineering
  2. Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
  3. North Carolina State Univ., Raleigh, NC (United States). Dept. of Nuclear Engineering
Publication Date:
Research Org.:
Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
Sponsoring Org.:
USDOE Office of Nuclear Energy (NE)
OSTI Identifier:
1494470
Report Number(s):
LA-UR-18-30655
Journal ID: ISSN 1738-5733
Grant/Contract Number:  
89233218CNA000001
Resource Type:
Journal Article: Accepted Manuscript
Journal Name:
Nuclear Engineering and Technology
Additional Journal Information:
Journal Name: Nuclear Engineering and Technology; Journal ID: ISSN 1738-5733
Publisher:
Korean Nuclear Society
Country of Publication:
United States
Language:
English
Subject:
97 MATHEMATICS AND COMPUTING; sensitivity/uncertainty estimation; CASL; VERA; DAKOTA; SCALE; ROMUSE 2.0

Citation Formats

Khuwaileh, Bassam, Williams, Brian, Turinsky, Paul, and Hartanto, Donny. Verification of Reduced Order Modeling Based Uncertainty/Sensitivity Estimator (ROMUSE). United States: N. p., 2019. Web. doi:10.1016/j.net.2019.01.020.
Khuwaileh, Bassam, Williams, Brian, Turinsky, Paul, & Hartanto, Donny. Verification of Reduced Order Modeling Based Uncertainty/Sensitivity Estimator (ROMUSE). United States. doi:10.1016/j.net.2019.01.020.
Khuwaileh, Bassam, Williams, Brian, Turinsky, Paul, and Hartanto, Donny. Thu . "Verification of Reduced Order Modeling Based Uncertainty/Sensitivity Estimator (ROMUSE)". United States. doi:10.1016/j.net.2019.01.020. https://www.osti.gov/servlets/purl/1494470.
@article{osti_1494470,
title = {Verification of Reduced Order Modeling Based Uncertainty/Sensitivity Estimator (ROMUSE)},
author = {Khuwaileh, Bassam and Williams, Brian and Turinsky, Paul and Hartanto, Donny},
abstractNote = {This article presents a number of verification case studies for a recently developed sensitivity/uncertainty code package. The code package, ROMUSE (Reduced Order Modeling based Uncertainty/Sensitivity Estimator) is an effort to provide an analysis tool to be used in conjunction with reactor core simulators, in particular the Virtual Environment for Reactor Applications (VERA) core simulator. ROMUSE has been written in C++ and is currently capable of performing various types of parameter perturbations and associated sensitivity analysis, uncertainty quantification, surrogate model construction and subspace analysis. The current version 2.0 has the capability to interface with the Design Analysis Kit for Optimization and Terascale Applications (DAKOTA) code, which gives ROMUSE access to the various algorithms implemented within DAKOTA, most importantly model calibration. The verification study is performed via two basic problems and two reactor physics models. The first problem is used to verify the ROMUSE single physics gradient-based range finding algorithm capability using an abstract quadratic model. The second problem is the Brusselator problem, which is a coupled problem representative of multi-physics problems. This problem is used to test the capability of constructing surrogates via ROMUSE-DAKOTA. Finally, light water reactor pin cell and sodium-cooled fast reactor fuel assembly problems are simulated via SCALE 6.1 to test ROMUSE capability for uncertainty quantification and sensitivity analysis purposes.},
doi = {10.1016/j.net.2019.01.020},
journal = {Nuclear Engineering and Technology},
issn = {1738-5733},
number = ,
volume = ,
place = {United States},
year = {2019},
month = {1}
}

Journal Article:
Free Publicly Available Full Text
Publisher's Version of Record

Figures / Tables:

Table 1 Table 1: Results for quadratic problem

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