Alert

The NRC is shutdown due to the lapse in appropriations. Exempted activities to maintain critical health and safety activities and progress on critical activities, including activities outlined in Executive Order 14300, as described in the OMB Approved NRC Lapse Plan will continue.

Assessment of RELAP5/MOD 2 Against Critical Flow Data From Marviken Tests JIT 11 and CFT 21 (NUREG/IA-0007)

On this page:

Publication Information
Abstract

Download complete document

NUREG/IA-0007 (PDF 1.84 MB)

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.

Page Last Reviewed/Updated Tuesday, March 09, 2021