Assessment of RELAP5/MOD 2 Against Critical Flow Data From Marviken Tests JIT 11 and CFT 21 (NUREG/IA-0007)
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Publication Information
Date Published: September 1986
Prepared by:
0. Rosdahl, D. Caraher
Swedish Nuclear Power Inspectorate
P.O. Box 27106
S102 #52 Stockholm, Sweden
Prepared as part of:
The Agreement on Research Participation and Technical Exchange
under the International Thermal-Hydraulic Code Assessment
and Application Program (ICAP)
Published by:
Office of Nuclear Regulatory Research
U.S. Nuclear Regulatory Commission
Washington, DC 20555
Availability Notice
Abstract
RELAP5/ MOD2 simulations of the critical flow of saturated steam are reported together with simulations of the critical flow of subcooled liquid and a low quality two-phase mixture. The experiments which were simulated used nozzle diameters of 0.3 m and 0.5 m. RELAP5 overpredicted the experimental flow rates by 10 to 25 percent unless discharge coefficients were applied.
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