An Assessment of PWR Steam Generator Condensation at the Oregon State University APEX Facility (NUREG/CR-6963)

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Publication Information

Manuscript Completed: September 2008
Date Published: June 2012

Prepared by:
B. G. Woods, J. T. Groome, B. A. Collins

Oregon State University
Department of Nuclear Engineering
and Radiation Health Physics
128 Radiation Center
Corvallis, OR 97331-5902

G. S. Rhee/W. J. Krotiuk, NRC Project Managers

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

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Abstract

This report describes the testing to assess steam generator U-tube steam condensation conducted at the Oregon State University Advanced Plant Experiment Test Facility from 2005 through 2007. Eight separate steam generator condensation tests were sponsored by the Nuclear Regulatory Commission and completed at the APEX test facility. These tests were designed to evaluate steam condensation rates in a scaled Pressurized Water Reactor steam generator at various primary and secondary side pressures and inlet steam mass flow rates. Two of the tests included the presence of non-condensable gases. The experimental data will provide a basis to assess TRACE steam generator modeling techniques and to assist in development of improved models for condensation and steam generator thermal-hydraulics.