Published November 2009 | Version v1
Journal article

Thermal-hydraulics system codes uncertainty assessment: A review of the methodologies

  • 1. Goodman Global Inc., Houston, TX (United States)

Description

By revising the ECCS licensing rules in 1989, the USNRC has allowed the use of 'best estimate' thermal-hydraulics computer codes (such as RELAP5, TRAC, and TRACE), with the requirement that uncertainty analysis accompany the results. Several methodologies have been developed for the quantification of the uncertainties of such codes. These methodologies are either input-driven or output-driven. They disagree in definition for the uncertainty range, qualification and quantification steps, types of uncertainty sources considered, methods of assignment of uncertainty distribution or range to various parameters, approach to propagation of uncertainty, and the way the dynamic characteristics of TH codes are handled. The IMTHUA methodology, developed by the author, is a hybrid approach where an input-driven 'white box' method is augmented with output correction based on experimental results relevant to code output. This paper offers a comparative assessment of uncertainty analysis methodologies for thermal-hydraulics transient calculations. The methods will be compared based on their approaches for treatment of input, propagation, and code models and correlations, as well as output. Comprehensiveness, approach to data treatment, and interpretation of results are among the criteria for comparison. Several examples are provided to clarify the differences.

Availability note (English)

Available from http://dx.doi.org/10.1016/j.anucene.2009.08.018

Additional details

Identifiers

DOI
10.1016/j.anucene.2009.08.018;
PII
S0306-4549(09)00279-5;

Publishing Information

Journal Title
Annals of Nuclear Energy (Oxford)
Journal Volume
36
Journal Issue
11-12
Journal Page Range
p. 1774-1786
ISSN
0306-4549
CODEN
ANENDJ

INIS

Country of Publication
United Kingdom
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
41074029
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Descriptors DEI
CALCULATION METHODS; COMPARATIVE EVALUATIONS; COMPUTER CODES; CORRECTIONS; ECCS; REACTOR LICENSING; THERMAL HYDRAULICS
Descriptors DEC
ENGINEERED SAFETY SYSTEMS; EVALUATION; FLUID MECHANICS; HYDRAULICS; LICENSING; MECHANICS; REACTOR PROTECTION SYSTEMS

Optional Information

Copyright
Copyright (c) 2009 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.