Application of regression, variance, and density based global sensitivity methods to integrated VERA-CS and BISON simulations [Application of regression, variance, and density based global sensitivity methods to integrated VERA-CS and BISON simulations]

Blakely, Cole; Zhang, Hongbin; Folsom, Charlie; Ban, Heng; Szilard, Ronaldo

doi:10.1016/j.nucengdes.2018.03.023

Title: Application of regression, variance, and density based global sensitivity methods to integrated VERA-CS and BISON simulations [Application of regression, variance, and density based global sensitivity methods to integrated VERA-CS and BISON simulations]

Full Record
Other Related Research

Abstract

Uncertainty quantification (UQ) and sensitivity analyses (SA) are performed for coupled simulations between VERA-CS, a coupled pin resolved neutron transport and subchannel thermal hydraulics code, and the fuel performance code BISON. The interface between VERA-CS and BISON is performed in a multiphysics environment known as the LOCA Toolkit for U.S. light water reactors (LOTUS) currently under development at Idaho National Laboratory (INL). A focus is placed on using a variety of SA measures, including two regression based (Pearson and Spearman), one variance based (Sobol indices), and three moment independent measures (Delta moment independent measures with L₁, L₂, and L_∞ norms). The problem under inspection is a single assembly depletion case for three fuel cycles. The figures of merit are the minimum departure from nucleate boiling ratio (MDNBR), maximum fuel centerline temperature (MFCT), and gap conductance at peak power (GCPP). SA results show MDNBR to be linear with consistent rankings throughout the fuel cycles. MFCT is linear, but with a change in rankings at the switch from open gap to closed gap models. GCPP is nonlinear at intermediate states that coincide with the onset of contact between fuel and cladding. Furthermore, these nonlinear states allow for the showcasing of higher ordermore » SA measures over first order methods.« less

Authors:

Blakely, Cole ^[1];

^[2]; Folsom, Charlie ^[2]; Ban, Heng ^[3]; Szilard, Ronaldo ^[2]

Utah State Univ., Logan, UT (United States)
Idaho National Lab. (INL), Idaho Falls, ID (United States)
Univ. of Pittsburgh, Pittsburgh, PA (United States)

Publication Date:: Wed Mar 28 00:00:00 EDT 2018

Research Org.:: Idaho National Lab. (INL), Idaho Falls, ID (United States)

Sponsoring Org.:: USDOE Office of Nuclear Energy (NE)

OSTI Identifier:: 1557666

Alternate Identifier(s):: OSTI ID: 1548532

Report Number(s):: INL/JOU-17-43167-Rev000
Journal ID: ISSN 0029-5493

Grant/Contract Number:: AC07-05ID14517

Resource Type:: Accepted Manuscript

Journal Name:: Nuclear Engineering and Design

Additional Journal Information:: Journal Volume: 332; Journal Issue: C; Journal ID: ISSN 0029-5493

Publisher:: Elsevier

Country of Publication:: United States

Language:: English

Subject:: 22 GENERAL STUDIES OF NUCLEAR REACTORS; LOTUS VERA-CS BISON

Citation Formats


                    Blakely, Cole, Zhang, Hongbin, Folsom, Charlie, Ban, Heng, and Szilard, Ronaldo. Application of regression, variance, and density based global sensitivity methods to integrated VERA-CS and BISON simulations [Application of regression, variance, and density based global sensitivity methods to integrated VERA-CS and BISON simulations].  United States: N. p., 2018. 
Web.  doi:10.1016/j.nucengdes.2018.03.023.

Copy to clipboard


                    Blakely, Cole, Zhang, Hongbin, Folsom, Charlie, Ban, Heng, & Szilard, Ronaldo. Application of regression, variance, and density based global sensitivity methods to integrated VERA-CS and BISON simulations [Application of regression, variance, and density based global sensitivity methods to integrated VERA-CS and BISON simulations].  United States.  https://doi.org/10.1016/j.nucengdes.2018.03.023

Copy to clipboard


                    Blakely, Cole, Zhang, Hongbin, Folsom, Charlie, Ban, Heng, and Szilard, Ronaldo. Wed .  
"Application of regression, variance, and density based global sensitivity methods to integrated VERA-CS and BISON simulations [Application of regression, variance, and density based global sensitivity methods to integrated VERA-CS and BISON simulations]".  United States.  https://doi.org/10.1016/j.nucengdes.2018.03.023.  https://www.osti.gov/servlets/purl/1557666.

Copy to clipboard


                    
@article{osti_1557666,

  title        = {Application of regression, variance, and density based global sensitivity methods to integrated VERA-CS and BISON simulations [Application of regression, variance, and density based global sensitivity methods to integrated VERA-CS and BISON simulations]},

  author       = {Blakely, Cole and Zhang, Hongbin and Folsom, Charlie and Ban, Heng and Szilard, Ronaldo},

  abstractNote = {Uncertainty quantification (UQ) and sensitivity analyses (SA) are performed for coupled simulations between VERA-CS, a coupled pin resolved neutron transport and subchannel thermal hydraulics code, and the fuel performance code BISON. The interface between VERA-CS and BISON is performed in a multiphysics environment known as the LOCA Toolkit for U.S. light water reactors (LOTUS) currently under development at Idaho National Laboratory (INL). A focus is placed on using a variety of SA measures, including two regression based (Pearson and Spearman), one variance based (Sobol indices), and three moment independent measures (Delta moment independent measures with L1, L2, and L∞ norms). The problem under inspection is a single assembly depletion case for three fuel cycles. The figures of merit are the minimum departure from nucleate boiling ratio (MDNBR), maximum fuel centerline temperature (MFCT), and gap conductance at peak power (GCPP). SA results show MDNBR to be linear with consistent rankings throughout the fuel cycles. MFCT is linear, but with a change in rankings at the switch from open gap to closed gap models. GCPP is nonlinear at intermediate states that coincide with the onset of contact between fuel and cladding. Furthermore, these nonlinear states allow for the showcasing of higher order SA measures over first order methods.},

  doi          = {10.1016/j.nucengdes.2018.03.023},

  journal      = {Nuclear Engineering and Design},

  number       = C,

  volume       = 332,

  place        = {United States},

  year         = {Wed Mar 28 00:00:00 EDT 2018},

  month        = {Wed Mar 28 00:00:00 EDT 2018}

}

Copy to clipboard

Journal Article:

Free Publicly Available Full Text

Accepted Manuscript (Publisher)

Accepted Manuscript (DOE)

Publisher's Version of Record

https://doi.org/10.1016/j.nucengdes.2018.03.023

Other availability

Search WorldCat to find libraries that may hold this journal

Citation Metrics:

Cited by: 3 works

Citation information provided by
Web of Science

Save / Share:

Export Metadata

Save to My Library

Similar Records in DOE PAGES and OSTI.GOV collections:

Sensitivity analysis of VERA-CS and FRAPCON coupling in a multiphysics environment

Journal Article Blakely, Cole ; Zhang, Hongbin ; Ban, Heng - Annals of Nuclear Energy (Oxford)

A demonstration and description of the LOCA Toolkit for US light water reactors (LOTUS) is presented. Through LOTUS, the core simulator VERA-CS developed by CASL is coupled with the fuel performance code FRAPCON. The coupling is performed with consistent uncertainty propagation with all model inconsistencies being well-documented. Monte Carlo sampling is performed on a single 17 × 17 fuel assembly with a three cycle depletion case. Both uncertainty quantification (UQ) and sensitivity analysis (SA) are used at multiple states within the simulation to elucidate the behavior of minimum departure from nucleate boiling ratio (MDNBR), maximum fuel centerline temperature (MFCT), andmore »« less
Cited by 6
https://doi.org/10.1016/j.anucene.2017.09.029

Full Text Available
AN INVESTIGATION OF CONSISTENT UNCERTAINTY PROPAGATION AND SENSITIVITY ANALYSIS IN A MULTIPHYSICS ENVIRONMENT

Conference Blakely, Cole ; Zhang, Hongbin ; Ban, Heng

The framework for a LOCA toolkit for the U.S. light water reactors (LOTUS) is outlined. LOTUS allows for the coupling of the core design code VERA-CS with the fuel performance code FRAPCON such that uncertainties can be propagated consistently. An analysis of inherent model discrepancies, confirms that all differences are either negligible or the focus on immediate future work. Monte Carlo sampling is performed on 15 inputs for a depletion case of one fuel assembly. Both uncertainty quantification (UQ) and sensitivity analysis (SA) are performed on the figures of merit (FOM) of minimum departure from nucleate boiling ratio (MDNBR), maximummore »« less
Full Text Available
Uncertainty Quantification and Sensitivity Analysis for Coupled VERA-CS and FRAPCON

Journal Article Blakely, Cole ; Ban, Heng ; Zhang, Hongbin - Transactions of the American Nuclear Society

The current nuclear power plant fleet in the U.S. is facing numerous challenges economically ranging from low natural gas price to the rapidly growing renewable energy sources such as wind and solar power. In order for the nuclear industry to keep the viability of its operating fleet, new innovations have to be introduced to lower the costs to operate the fleet. One area that could contribute to the cost reduction is to lower the fuel cycle cost and improve the plant safety through initiatives such as higher burnup fuel and accident tolerant fuel. At the same time, the nuclear industrymore »« less
Uncertainty quantification and sensitivity analysis with CASL Core Simulator VERA-CS

Journal Article Brown, C. S. ; Zhang, Hongbin - Annals of Nuclear Energy (Oxford)

Uncertainty quantification and sensitivity analysis are important for nuclear reactor safety design and analysis. A 2x2 fuel assembly core design was developed and simulated by the Virtual Environment for Reactor Applications, Core Simulator (VERA-CS) coupled neutronics and thermal-hydraulics code under development by the Consortium for Advanced Simulation of Light Water Reactors (CASL). An approach to uncertainty quantification and sensitivity analysis with VERA-CS was developed and a new toolkit was created to perform uncertainty quantification and sensitivity analysis with fourteen uncertain input parameters. Furthermore, the minimum departure from nucleate boiling ratio (MDNBR), maximum fuel center-line temperature, and maximum outer clad surfacemore »« less
Cited by 13
https://doi.org/10.1016/j.anucene.2016.05.016

Full Text Available
Executing BISON-CASL Fuel Performance Cases Using VERA-CS Output

Technical Report Pawlowski, Roger P. ; Stimpson, Shane ; Clarno, Kevin ; ...

As the Consortium for Advanced Simulation of Light Water Reactors (CASL) moves forward with more complex multiphysics simulations, there is increased focus on incorporating fuel performance analysis methods. The coupled neutronics/thermal-hydraulics capabilities within the Virtual Environment for Reactor Applications Core Simulator (VERA-CS) have become relatively stable and major advances have been made in analysis efforts, including the simulations of twelve cycles of Watts Bar Nuclear Unit 1 (WBN1) operation. However, VERA-CS approaches for treating fuel pin heat transfer have well-known limitations that could be eliminated through better integration with the BISON-CASL fuel performance code. Several approaches are being taken tomore »« less
https://doi.org/10.2172/1895202

Full Text Available

Similar Records