Published 2008 | Version v1
Book

Assessment of compensating error in the WCOBRA/TRAC-TF2 thermal-hydraulic code

  • 1. LOCA Integrated Services, Westinghouse Electric Company, Pittsburgh PA 15235 (United States)

Description

US NRC Regulatory Guide 1.157 outlines the acceptable models and methods by which the performance of an Emergency Core Cooling System (ECCS) can be calculated in a best-estimate loss-of-coolant accident (BE LOCA) analysis. Empiricism in complex, two-phase thermal modeling requires accurate uncertainty assessment on many fronts, including compensating errors, or those model errors which, when applied in combination, could result in good but misleading prediction of the peak cladding temperature (PCT) during the transient. For example, a model that over-predicts vapor temperature and heat transfer coefficient might predict heat flux, and therefore PCT, in accordance with experimental data. The potential existence of this type of error must be investigated to assure confidence in the code's assessment of full plant safety analysis. An extensive evaluation of potential compensating error in the predicted results of integral and single-effects tests was performed in the qualification of the WCOBRA/TRAC BE methodology. Experimental results such as FLECHT forced reflood, ORNL high pressure film boiling, and single tube film boiling tests provided the basis for evaluation. This paper focuses on the studies associated with the reflood heat transfer. The intent is to provide the details of the compensating error analysis in modeling post-critical heat flux (post-CHF) heat transfer phenomena by looking at a subset of the FLECHT tests with very high and very low forced reflood rates. (authors)

Part of:
Proceedings of the 2008 International Congress on Advances in Nuclear Power Plants - ICAPP '08

Additional details

Publishing Information

Publisher
American Nuclear Society - ANS
Imprint Place
La Grange Park (United States)
ISBN
0-89448-061-8
Imprint Title
Proceedings of the 2008 International Congress on Advances in Nuclear Power Plants - ICAPP '08
Imprint Pagination
2696 p.
Journal Page Range
p. 1457-1465

Conference

Title
2008 International Congress on Advances in Nuclear Power Plants
Acronym
ICAPP '08
Dates
8-12 Jun 2008
Place
Anaheim, CA (United States)

Optional Information

Notes
10 refs.