Argonne National Laboratory
RERTR
Reduced Enrichment for Research and Test Reactors
Nuclear Engineering Division at Argonne
U.S. Department of Energy

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Abstracts and Available Papers Presented at the
2002 International RERTR Meeting

UNCERTAINTIES ASSESMENT FOR SAFETY MARGINS EVALUATION IN MTR REACTORS CORE THERMAL-HYDRAULIC DESIGN

M. Giménez, M. Schlamp, A. Vertullo

Nuclear Safety Group - Bariloche Atomic Center - CNEA

ABSTRACT

This report contains a bibliographic review and a critical analysis of different methodologies used for uncertainty evaluation in research reactors core safety related parameters. Different parameters where uncertainties are considered are also presented and discussed, as well as their intrinsic nature regarding the way their uncertainty combination must be done. Finally a combined statistical method with direct propagation of uncertainties and a set of basic parameters as wall and ONB temperatures, CHF, PRD and their respective ratios where uncertainties should be considered is proposed.


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Contact:
Ms. Alicia C. Vertullo

CNEA-CAB, Researcher
Av. Bustillo 9500, 8400
San Carlos de Bariloche
Pcia. Río Negro, Argentina
Phone: (54 2944) 445218
Fax: (54 2944) 445199
E-mail: vertullo@cab.cnea.gov.ar

2016 RERTR Meeting

The 2016 International RERTR Meeting (RERTR-2016) will take place in Belgium. Stay tuned for further details.

2015 RERTR Meeting

The 2015 International RERTR Meeting (RERTR-2015) took place in Seoul, Korea on Oct. 11-14, 2015.
For more information visit RERTR-2015.

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Last modified on July 29, 2008 11:33 +0200