Published February 1987 | Version v1
Journal article

Discussions on loop seal behavior during cold leg small break LOCAs of a PWR

Creators

  • 1. Westinghouse Electric Corp., Pittsburgh, PA (USA). Nuclear Technology Div.

Description

This paper analyzes loop seal clearing behavior during small break LOCA transients to point out a possible uncertainty in the process. Further it also discusses core mixture level behavior during the small break transients. Energy balances in the broken and intact loop identify a difference in the mixture level drop velocities between the broken and intact loop. A hypothesis in the velocity fluctuation intensity as a function of a break size is proposed. This leads to a conclusion that, for certain break sizes, it is not certain which loop seal will pass steam to the break first during the transient. This fact has a very important implication in interpreting test data or numerical simulations with a lumped intact loop. The amount of water delivered to the core/vessel region after the loop seal clearing may differ significantly depending on whether the water is from the single broken loop or the lumped intact loop. (orig.)

Additional details

Publishing Information

Journal Title
Nucl. Eng. Des.
Journal Volume
99
Series
Nucl. Eng. Des.
Journal Page Range
453-458
ISSN
0029-5493
CODEN
NEDEA

Conference

Title
3. international topical meeting on reactor thermal hydraulics.
Dates
15-18 Oct 1985.
Place
Newport, RI (USA).

INIS

Country of Publication
Netherlands
Country of Input or Organization
Netherlands
INIS RN
18057613
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BOUNDARY CONDITIONS; FLOW RATE; LOSS OF COOLANT; MASS TRANSFER; MIXING; NUMERICAL SOLUTION; OSCILLATIONS; PWR TYPE REACTORS; RUPTURES; SIMULATION; TRANSIENTS
Descriptors DEC
ACCIDENTS; ENRICHED URANIUM REACTORS; FAILURES; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS