skip to main content
OSTI.GOV title logo U.S. Department of Energy
Office of Scientific and Technical Information

Title: Uncertainty and Sensitivity Analyses of a Pebble Bed HTGR Loss of Cooling Event

Journal Article · · Science and Technology of Nuclear Installations
DOI:https://doi.org/10.1155/2013/426356· OSTI ID:1198171
 [1]
  1. Nuclear Science and Engineering Division, Idaho National Laboratory (INL), 2525 N. Fremont Avenue, Idaho Falls, ID 83415, USA

The Very High Temperature Reactor Methods Development group at the Idaho National Laboratory identified the need for a defensible and systematic uncertainty and sensitivity approach in 2009. This paper summarizes the results of an uncertainty and sensitivity quantification investigation performed with the SUSA code, utilizing the International Atomic Energy Agency CRP 5 Pebble Bed Modular Reactor benchmark and the INL code suite PEBBED-THERMIX. Eight model input parameters were selected for inclusion in this study, and after the input parameters variations and probability density functions were specified, a total of 800 steady state and depressurized loss of forced cooling (DLOFC) transient PEBBED-THERMIX calculations were performed. The six data sets were statistically analyzed to determine the 5% and 95% DLOFC peak fuel temperature tolerance intervals with 95% confidence levels. It was found that the uncertainties in the decay heat and graphite thermal conductivities were the most significant contributors to the propagated DLOFC peak fuel temperature uncertainty. No significant differences were observed between the results of Simple Random Sampling (SRS) or Latin Hypercube Sampling (LHS) data sets, and use of uniform or normal input parameter distributions also did not lead to any significant differences between these data sets.

Sponsoring Organization:
USDOE
Grant/Contract Number:
AC07-05ID1451
OSTI ID:
1198171
Journal Information:
Science and Technology of Nuclear Installations, Journal Name: Science and Technology of Nuclear Installations Vol. 2013; ISSN 1687-6075
Publisher:
Hindawi Publishing CorporationCopyright Statement
Country of Publication:
Egypt
Language:
English
Citation Metrics:
Cited by: 8 works
Citation information provided by
Web of Science

References (7)

Uncertainty and sensitivity analyses of the Kozloduy pump trip test using coupled thermal–hydraulic 3D kinetics code journal June 2006
Uncertainty and sensitivity analysis of the LOFT L2-5 test: Results of the BEMUSE programme journal December 2008
Determination of Sample Sizes for Setting Tolerance Limits journal March 1941
A comparison of uncertainty and sensitivity analysis results obtained with random and Latin hypercube sampling journal September 2005
Automated Design and Optimization of Pebble-Bed Reactor Cores journal July 2010
Survey of sampling-based methods for uncertainty and sensitivity analysis journal October 2006
On the Kolmogorov-Smirnov Test for Normality with Mean and Variance Unknown journal June 1967