Search Menu
DOE PAGES title logo U.S. Department of Energy
Office of Scientific and Technical Information
Search Scholarly Publications

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

Journal Article · · Nuclear Science and Engineering
ORCiD logo [1]; ORCiD logo [1];  [2]
  1. North Carolina State Univ., Raleigh, NC (United States)
  2. Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)
+ Show Author Affiliations

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.

Research Organization:
Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)
Sponsoring Organization:
USDOE National Nuclear Security Administration (NNSA)
Grant/Contract Number:
AC04-94AL85000
OSTI ID:
1496638
Report Number(s):
SAND-2019-0961J; 671938
Journal Information:
Nuclear Science and Engineering, Vol. 190, Issue 3; ISSN 0029-5639
Publisher:
American Nuclear Society - Taylor & FrancisCopyright Statement
Country of Publication:
United States
Language:
English

References (10)

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
Bootstrap Methods: Another Look at the Jackknife book January 1992
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

Cited By (1)

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

Figures / Tables (19)

Figure 1(p. 4)figure Figure 1
Table I(p. 4)table Table I
Table II(p. 7)table Table II
Table III(p. 11)table Table III
Table IV(p. 12)table Table IV
Figure 2(p. 13)figure Figure 2
Table V(p. 13)table Table V
Table VI(p. 14)table Table VI
Figure 3(p. 15)figure Figure 3
Table VII(p. 15)table Table VII
Table VIII(p. 16)table Table VIII
Figure 4(p. 17)figure Figure 4
Figure 5(p. 18)figure Figure 5
Figure 6(p. 18)figure Figure 6
Table IX(p. 18)table Table IX
Table X(p. 19)table Table X
Figure 7(p. 20)figure Figure 7
Table XI(p. 20)table Table XI
Figure 8(p. 21)figure Figure 8

Similar Records

Related Subjects

42 ENGINEERING
Organization for Economic Co-operation and Development/Nuclear Energy Agency Light Water Reactor Uncertainty Analysis in Modeling Benchmark
thermal hydraulics
CTF