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Application of RELAP5/MOD3.1 Code to the LOFT Test L3-6 (NUREG/IA-0024)

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Abstract

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NUREG/IA-0024 (PDF 2.88 MB)

Publication Information

Date Published: February 1998

Prepared by:
S.S. Pylev and V.L. Roginskaja

Nuclear Safety Institute
Russian Research Centre
"Kurchatov Institute"
Kurchatov Square, 1
123182, Moscow
Russia

Prepared as part of:
The Agreement on Research Participation and Technical Exchange
under the Code Assessment and Maintenance Program

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

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Abstract

A calculation of LOFT Experiment L3-6, a small break equivalent to a 4-in. diameter rupture in the cold leg of a four-loop commercial pressurized water reactor, has been performed to help validate RELAP5/MOD3.1 for this application.

The version of the code to be used is SCDAP/RELAP5/MOD3.1.8d0.

Three calculations were carried out in order to study the sensitivity to change break nozzle superheated discharge coefficient.

Conducted comparative analysis of the LOFT L3-6 experiment shows on the whole a reasonable agreement between calculated and measured data. Some discrepancies in the system pressure do not distort a picture of the transient.

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