Application of RELAP5/MOD3.1 Code to the LOFT Test L3-6 (NUREG/IA-0024)
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Date Published: February 1998
S.S. Pylev and V.L. Roginskaja
Nuclear Safety Institute
Russian Research Centre
Kurchatov Square, 1
Prepared as part of:
The Agreement on Research Participation and Technical Exchange
under the Code Assessment and Maintenance Program
Office of Nuclear Regulatory Research
U.S. Nuclear Regulatory Commission
Washington, DC 20555
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.