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