PWR FLECHT cosine low flooding rate test series evaluation report

Technical Report · Tue Mar 01 04:00:00 EST 1977

OSTI ID:7209789

Lilly, G P; Yeh, H C; Hochreiter, L E; Yamaguchi, N

The overall objective of the FLECHT test program has been to obtain heat transfer data useful for calculating the reflooding behavior of a PWR core following a postulated loss of coolant accident. The behavior of the emergency core coolant (ECC) with respect to the mass stored and mass flow leaving the core during reflood is also needed for this purpose. The capability for meeting this latter need, has been made possible with the improved hardware and instrumentation of the cosine tests. Information on the FLECHT Low Flooding Rate Cosine test is presented concerning test description, data evaluation, bundle flow conditions and heat transfer mechanisms, model for mass flow above froth level, and heat transfer correlation.

• Research Organization: Westinghouse Electric Corp., Pittsburgh, PA (USA). Nuclear Energy Systems Div.
• OSTI ID: 7209789
• Report Number(s): WCAP-8838
• Country of Publication: United States
• Language: English

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ACCIDENTS
ECCS
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
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FLUID MECHANICS
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HYDRAULICS
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LOSS OF COOLANT
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REACTOR ACCIDENTS
REACTOR PROTECTION SYSTEMS
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WATER COOLED REACTORS
WATER MODERATED REACTORS