Uncertainty Quantification Study of CTF for the OECD/NEA LWR Uncertainty Analysis in Modeling Benchmark

Porter, Nathan W.; Avramova, Maria N.; Mousseau, Vincent Andrew

doi:10.1080/00295639.2018.1435135

Title: 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 thermal-hydraulic subchannel code for nuclear engineering applications, Coolant Boiling in Rod Arrays-Three Field (COBRA-TF). CTF is used, which is a version of COBRA-TF developed in cooperation between the Consortium for Advanced Simulation of Light Water Reactors and North Carolina State University. Four steady-state cases from Phase II Exercise 3 of the Organisation for Economic Co-operation 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:

^[1];

^[1]; Mousseau, Vincent Andrew ^[2]

North Carolina State Univ., Raleigh, NC (United States)
Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

Publication Date:: Mon Mar 05 00:00:00 EST 2018

Research Org.:: Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

Sponsoring Org.:: USDOE National Nuclear Security Administration (NNSA)

OSTI Identifier:: 1496638

Report Number(s):: SAND-2019-0961J
Journal ID: ISSN 0029-5639; 671938

Grant/Contract Number:: AC04-94AL85000

Resource Type:: Accepted Manuscript

Journal Name:: Nuclear Science and Engineering

Additional Journal Information:: Journal Volume: 190; Journal Issue: 3; Journal ID: ISSN 0029-5639

Publisher:: American Nuclear Society - Taylor & Francis

Country of Publication:: United States

Language:: English

Subject:: 42 ENGINEERING; Organization for Economic Co-operation 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.

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                    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.  https://doi.org/10.1080/00295639.2018.1435135

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                    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.  https://doi.org/10.1080/00295639.2018.1435135.  https://www.osti.gov/servlets/purl/1496638.

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@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 thermal-hydraulic subchannel code for nuclear engineering applications, Coolant Boiling in Rod Arrays-Three Field (COBRA-TF). CTF is used, which is a version of COBRA-TF developed in cooperation between the Consortium for Advanced Simulation of Light Water Reactors and North Carolina State University. Four steady-state cases from Phase II Exercise 3 of the Organisation for Economic Co-operation 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         = {Mon Mar 05 00:00:00 EST 2018},

  month        = {Mon Mar 05 00:00:00 EST 2018}

}

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https://doi.org/10.1080/00295639.2018.1435135

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Cited by: 4 works

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Figure 1: Axial cross-section for each selected UAM Benchmark cases

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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
DOI: 10.1080/00295450.2019.1580533

Figures / Tables found in this record:

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Uncertainty Analysis of CTF for the Uncertainty Analysis in Modeling Benchmark

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This work describes the results of a quantitative sensitivity and uncertainty analysis of the thermal hydraulic subchannel code, Coolant Boiling in Rod Arrays - Three Field (COBRA-TF). Four steady state cases from Phase II, Exercise 3 of the Organisation for Economic Co-operation and Development/Nuclear Energy Agency Uncertainty Analysis in Modeling (OECD/NEA UAM) Benchmark are analyzed using the statistical analysis tool, Design Analysis Kit for Optimization and Tera-scale Applications (Dakota). This study supports the larger goal of the UAM Benchmark, which is to assess the uncertainty inherent in nuclear codes in a straightforward framework. The benchmark first focuses on assessing themore »« less
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Similar Records

Title: Uncertainty Quantification Study of CTF for the OECD/NEA LWR Uncertainty Analysis in Modeling Benchmark

Abstract

Citation Formats

Figures / Tables:

Determination of Sample Sizes for Setting Tolerance Limits journal, March 1941

Monte-Carlo based uncertainty analysis: Sampling efficiency and sampling convergence journal, January 2013

Bootstrap Methods: Another Look at the Jackknife journal, January 1979

Factorial Sampling Plans for Preliminary Computational Experiments journal, May 1991

Large Sample Confidence Regions Based on Subsamples under Minimal Assumptions journal, December 1994

Factorial Sampling Plans for Preliminary Computational Experiments journal, May 1991

Linear Statistical Inference and its Applications. journal, December 1966

Linear Statistical Inference and its Applications. journal, September 1975

Linear statistical inference and its applications journal, September 1966

Uncertainty Quantification and Propagation of Multiphysics Simulation of the Pressurized Water Reactor Core journal, March 2019

Determination of Sample Sizes for Setting Tolerance Limits
journal, March 1941

Monte-Carlo based uncertainty analysis: Sampling efficiency and sampling convergence
journal, January 2013

Bootstrap Methods: Another Look at the Jackknife
journal, January 1979

Factorial Sampling Plans for Preliminary Computational Experiments
journal, May 1991

Large Sample Confidence Regions Based on Subsamples under Minimal Assumptions
journal, December 1994

Factorial Sampling Plans for Preliminary Computational Experiments
journal, May 1991

Linear Statistical Inference and its Applications.
journal, December 1966

Linear Statistical Inference and its Applications.
journal, September 1975

Linear statistical inference and its applications
journal, September 1966

Uncertainty Quantification and Propagation of Multiphysics Simulation of the Pressurized Water Reactor Core
journal, March 2019