Uncertainty Quantification Study of CTF for the OECD/NEA LWR Uncertainty Analysis in Modeling Benchmark
Abstract
This work describes the results of a quantitative uncertainty analysis of the thermalhydraulic subchannel code for nuclear engineering applications, Coolant Boiling in Rod ArraysThree Field (COBRATF). CTF is used, which is a version of COBRATF developed in cooperation between the Consortium for Advanced Simulation of Light Water Reactors and North Carolina State University. Four steadystate cases from Phase II Exercise 3 of the Organisation for Economic Cooperation and Development/Nuclear Energy Agency Light Water Reactor Uncertainty Analysis in Modeling (UAM) Benchmark are analyzed using the statistical analysis tool, Design Analysis Kit for Optimization and Terascale Applications (Dakota). The input parameters include boundary condition, geometry, and modeling uncertainties, which are selected using a sensitivity study and then defined based on expert judgment. Here, a forward uncertainty quantification method with Latin hypercube sampling (LHS) is used, where the sample size is based on available computational resources.
 Authors:

 North Carolina State Univ., Raleigh, NC (United States)
 Sandia National Lab. (SNLNM), Albuquerque, NM (United States)
 Publication Date:
 Research Org.:
 Sandia National Lab. (SNLNM), Albuquerque, NM (United States)
 Sponsoring Org.:
 USDOE National Nuclear Security Administration (NNSA)
 OSTI Identifier:
 1496638
 Report Number(s):
 SAND20190961J
Journal ID: ISSN 00295639; 671938
 Grant/Contract Number:
 AC0494AL85000
 Resource Type:
 Accepted Manuscript
 Journal Name:
 Nuclear Science and Engineering
 Additional Journal Information:
 Journal Volume: 190; Journal Issue: 3; Journal ID: ISSN 00295639
 Publisher:
 American Nuclear Society  Taylor & Francis
 Country of Publication:
 United States
 Language:
 English
 Subject:
 42 ENGINEERING; Organization for Economic Cooperation and Development/Nuclear Energy Agency Light Water Reactor Uncertainty Analysis in Modeling Benchmark; thermal hydraulics; CTF
Citation Formats
Porter, Nathan W., Avramova, Maria N., and Mousseau, Vincent Andrew. Uncertainty Quantification Study of CTF for the OECD/NEA LWR Uncertainty Analysis in Modeling Benchmark. United States: N. p., 2018.
Web. doi:10.1080/00295639.2018.1435135.
Porter, Nathan W., Avramova, Maria N., & Mousseau, Vincent Andrew. Uncertainty Quantification Study of CTF for the OECD/NEA LWR Uncertainty Analysis in Modeling Benchmark. United States. doi:10.1080/00295639.2018.1435135.
Porter, Nathan W., Avramova, Maria N., and Mousseau, Vincent Andrew. Mon .
"Uncertainty Quantification Study of CTF for the OECD/NEA LWR Uncertainty Analysis in Modeling Benchmark". United States. doi:10.1080/00295639.2018.1435135. https://www.osti.gov/servlets/purl/1496638.
@article{osti_1496638,
title = {Uncertainty Quantification Study of CTF for the OECD/NEA LWR Uncertainty Analysis in Modeling Benchmark},
author = {Porter, Nathan W. and Avramova, Maria N. and Mousseau, Vincent Andrew},
abstractNote = {This work describes the results of a quantitative uncertainty analysis of the thermalhydraulic subchannel code for nuclear engineering applications, Coolant Boiling in Rod ArraysThree Field (COBRATF). CTF is used, which is a version of COBRATF developed in cooperation between the Consortium for Advanced Simulation of Light Water Reactors and North Carolina State University. Four steadystate cases from Phase II Exercise 3 of the Organisation for Economic Cooperation and Development/Nuclear Energy Agency Light Water Reactor Uncertainty Analysis in Modeling (UAM) Benchmark are analyzed using the statistical analysis tool, Design Analysis Kit for Optimization and Terascale Applications (Dakota). The input parameters include boundary condition, geometry, and modeling uncertainties, which are selected using a sensitivity study and then defined based on expert judgment. Here, a forward uncertainty quantification method with Latin hypercube sampling (LHS) is used, where the sample size is based on available computational resources.},
doi = {10.1080/00295639.2018.1435135},
journal = {Nuclear Science and Engineering},
number = 3,
volume = 190,
place = {United States},
year = {2018},
month = {3}
}
Web of Science
Figures / Tables:
Works referenced in this record:
Determination of Sample Sizes for Setting Tolerance Limits
journal, March 1941
 Wilks, S. S.
 The Annals of Mathematical Statistics, Vol. 12, Issue 1
MonteCarlo based uncertainty analysis: Sampling efficiency and sampling convergence
journal, January 2013
 Janssen, Hans
 Reliability Engineering & System Safety, Vol. 109
Bootstrap Methods: Another Look at the Jackknife
journal, January 1979
 Efron, B.
 The Annals of Statistics, Vol. 7, Issue 1
Factorial Sampling Plans for Preliminary Computational Experiments
journal, May 1991
 Morris, Max D.
 Technometrics, Vol. 33, Issue 2
Large Sample Confidence Regions Based on Subsamples under Minimal Assumptions
journal, December 1994
 Politis, Dimitris N.; Romano, Joseph P.
 The Annals of Statistics, Vol. 22, Issue 4
Factorial Sampling Plans for Preliminary Computational Experiments
journal, May 1991
 Morris, Max D.
 Technometrics, Vol. 33, Issue 2
Works referencing / citing this record:
Uncertainty Quantification and Propagation of Multiphysics Simulation of the Pressurized Water Reactor Core
journal, March 2019
 Zeng, Kaiyue; Hou, Jason; Ivanov, Kostadin
 Nuclear Technology, Vol. 205, Issue 12
Figures / Tables found in this record: