Simulation of PKL Loss of RHRS Experiment E3.1 with RELAP5 and TRACE Codes – Application to a PWR NPP Model (NUREG/IA-0256)

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Publication Information

Manuscript Completed: June 2011
Date Published: September 2011

Prepared by:
César Queral¹, Alberto Concejal¹, Antonio Expósito¹, and Issac González¹,

¹ Universidad Politécnica de Madrid
Alenza 4. 28003 Madrid
SPAIN

A. Calvo, NRC Project Manager

Office of Nuclear Regulatory Research
U.S. Nuclear Regulatory Commission
Washington, DC 20555-0001

Prepared as part of:
The Agreement on Research Participation and Technical Exchange Under the Thermal-Hydraulic Code Applications and Maintenance Program (CAMP)

Published by:
Office of Nuclear Regulatory Research
U.S. Nuclear Regulatory Commission
Washington, DC 20555-0001

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Abstract

An analysis of PKL midloop test E3,1 has been performed with TRACE and RELAP5/MOD3 codes. This test, included within the OECD/PKL project, tries to analyze the phenomenology and different accident management actions after a loss of RHRS at midloop conditions with primary side closed. The comparison between the results obtained with both codes shows that, in general, the main phenomena are well reproduced. However, there are still a few phenomena that are not well predicted, like pressurizer level. The good results obtained simulating another similar test (PKL test F2.2 run2) enables to confirm that the modelling methodology is adequate for this kind of transients. This modelling methodology has been also applied to a TRACE model of a Spanish PWR, Westinghouse design, simulating a similar transient to test E3.1, obtaining similar results than in PKL models.