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Title: Uncertainty quantification and sensitivity analysis with CASL Core Simulator VERA-CS

Journal Article · · Annals of Nuclear Energy (Oxford)
 [1];  [2]
  1. North Carolina State Univ., Raleigh, NC (United States). Dept. of Nuclear Engineering
  2. Idaho National Lab. (INL), Idaho Falls, ID (United States)

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 surface temperature were chosen as the selected figures of merit. Pearson, Spearman, and partial correlation coefficients were considered for all of the figures of merit in sensitivity analysis and coolant inlet temperature was consistently the most influential parameter. We used parameters as inputs to the critical heat flux calculation with the W-3 correlation were shown to be the most influential on the MDNBR, maximum fuel center-line temperature, and maximum outer clad surface temperature.

Research Organization:
Idaho National Laboratory (INL), Idaho Falls, ID (United States)
Sponsoring Organization:
USDOE Office of Nuclear Energy (NE)
Grant/Contract Number:
AC07-05ID14517
OSTI ID:
1357750
Alternate ID(s):
OSTI ID: 1326416
Report Number(s):
INL/JOU-16-38314; PII: S0306454916302894
Journal Information:
Annals of Nuclear Energy (Oxford), Vol. 95, Issue C; ISSN 0306-4549
Publisher:
ElsevierCopyright Statement
Country of Publication:
United States
Language:
English
Citation Metrics:
Cited by: 13 works
Citation information provided by
Web of Science

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AREVA's realistic large break LOCA analysis methodology journal July 2005
Prediction of departure from nucleate boiling for an axially non-uniform heat flux distribution journal January 1967

Cited By (1)

Combining simulations and data with deep learning and uncertainty quantification for advanced energy modeling journal August 2019