Assessment of MIT and UCB wall condensation tests and of the pre-release RELAP5/MOD3.2 code condensation models

Technical Report · Sat Dec 31 23:00:00 EST 1994

DOI:https://doi.org/10.2172/34423· OSTI ID:34423

Shumway, R W

In recent years, a new class of reactor designs has been proposed that utilize passive safety systems. General Electric has developed a Simplified Boiling Water Reactor (SBWR) design that relies on such passive systems. The SBWR has two passive cooling systems that involve energy transfer by condensation. These are the isolation condenser system (ICS) and the passive containment cooling systems (PCCS). It is important that such heat transfer phenomena be correctly understood and quantified. The General Electric Company has sponsored tests at the Massachusetts Institute of Technology (MIT) and at the University of California at Berkeley (UCB) to obtain data simulating PCCS conditions. Data was obtained with pure steam, steam-air mixtures and steam-helium mixtures. INEL has been contracted by the NRC to evaluate these tests and assess existing condensation heat transfer correlations against the test data. This report assesses the relevance of the tests to SBWR conditions and shows RELAP5/MOD3.2 predictions of the tests.

• Research Organization: Lockheed Idaho Technologies Co., Idaho Falls, ID (United States)
• Sponsoring Organization: Nuclear Regulatory Commission, Washington, DC (United States)
• DOE Contract Number: AC07-94ID13223
• OSTI ID: 34423
• Report Number(s): INEL--95/0050; ON: TI95008661
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
BWR TYPE REACTORS
COMPARATIVE EVALUATIONS
COMPUTERIZED SIMULATION
CONTAINMENT BUILDINGS
ENGINEERED SAFETY SYSTEMS
EVALUATION
HEAT EXCHANGERS
HEAT TRANSFER
ISOLATION CONDENSERS
PERFORMANCE TESTING
R CODES
REACTOR ACCIDENTS
REACTOR SAFETY EXPERIMENTS
TEST FACILITIES
VAPOR CONDENSATION