Published November 2014 | Version v1
Journal article

Accuracy quantification metrics for CFD simulation of in-vessel flows

Description

Highlights: • CFD code validation involves accuracy quantification. • Accuracy evaluation requires metrics for comparison of multi-variable data. • Proposal of possible metrics, based on a set of quantitative parameters. • Providing examples applied to distribution of coolant properties at core inlet. • Applying the proposed set of parameters to a number of code validation cases. - Abstract: Within more general frameworks dealing with uncertainty evaluation and code assessment, well assessed methodologies exist for the accuracy evaluation of system thermal hydraulic analysis results. As long as multi-dimensional transient data is involved, such as space and time distributions obtained from CFD calculations and experiments, the task of quantifying the accuracy and defining acceptance criteria becomes harder, and there seems to be a lack of systematic approaches available to that purpose. An example of such multi-dimensional data is represented by the time and space distribution of coolant properties (e.g. temperature, boron concentration) at the reactor core inlet, which is relevant to reactor safety as local perturbations potentially induce power excursions. An attempt is made here to tackle the accuracy quantification issue for that class of data, in a somewhat empirical way, i.e. by proposing a set of parameters that can be used, after proper qualitative analysis of measured data and code simulation results, to characterize the target variable time and space distributions, and to quantify the deviation of the simulation from the experimental data. The advantage of using such kind of metrics based on many parameters relies in the ability to cover different relevant features of the target variables and thus provide a more complete assessment and allow statements about the overall agreement

Availability note (English)

Available from http://dx.doi.org/10.1016/j.nucengdes.2014.03.003

Additional details

Identifiers

DOI
10.1016/j.nucengdes.2014.03.003;
PII
S0029-5493(14)00112-5;

Publishing Information

Journal Title
Nuclear Engineering and Design
Journal Volume
279
Journal Page Range
p. 200-209
ISSN
0029-5493
CODEN
NEDEAU

INIS

Country of Publication
Netherlands
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
46100765
Subject category
S42: ENGINEERING; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Descriptors DEI
ACCURACY; COOLANTS; DISTRIBUTION; METRICS; REACTOR CORES; REACTOR SAFETY; SIMULATION; THERMAL HYDRAULICS; VALIDATION
Descriptors DEC
FLUID MECHANICS; HYDRAULICS; MECHANICS; REACTOR COMPONENTS; SAFETY; TESTING

Optional Information

Copyright
Copyright (c) 2014 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.