Loss of feed flow, steam generator tube rupture and steam line break thermohydraulic experiments

Technical Report · Wed Oct 01 00:00:00 EDT 1986

DOI:https://doi.org/10.2172/5088258· OSTI ID:5088258

Mendler, O J; Takeuchi, K; Young, M Y

The Westinghouse Model Boiler No. 2 (MB-2) steam generator test model at the Engineering Test Facility in Tampa, Florida, was reinstrumented and modified for performing a series of tests simulating steam generator accident transients. The transients simulated were: loss of feed flow, steam generator tube rupture, and steam line break events. This document presents a description of (1) the model boiler and the associated test facility, (2) the tests performed, and (3) the analyses of the test results.

• Research Organization: Westinghouse Electric Corp., Pittsburgh, PA (USA). Nuclear Technology Div.
• OSTI ID: 5088258
• Report Number(s): NUREG/CR-4751; EPRI-NP-4786; WCAP-11206; ON: TI87900114
• Country of Publication: United States
• Language: English

Related Subjects

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21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
PWR TYPE REACTORS
LOSS OF FLOW
STEAM GENERATORS
TUBES
FAILURES
HEAT TRANSFER
HYDRAULICS
REACTOR SAFETY EXPERIMENTS
TEST FACILITIES
TRANSIENTS
ACCIDENTS
BOILERS
ENERGY TRANSFER
FLUID MECHANICS
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REACTOR ACCIDENTS
REACTORS
VAPOR GENERATORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
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Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled