Analysis of ECC bypass data
Description
Data from small scale tests investigating the delivery of emergency core cooling water into the lower plenum of a pressurized water reactor during a loss-of-coolant accident have been analyzed. A statistical analysis of data trends has been performed and the data represented in correlational form. The effects of test pressure are well understood and all pressure effects observed are accounted for by steam properties. Uncertainty exists concerning how to extrapolate these small scale test results to full scale. However, small scale tests indicate that a constant momentum flux scaling of the hydraulics may be more appropriate than the traditional J* scaling. Evidence also exists which suggests that condensation effects may be increasing in importance as scale size increases
Availability note (English)
MF available from INIS under the Report Number; NTI.
Files
Additional details
Additional titles
- Augmented title (English)
- PWR
Publishing Information
- Imprint Pagination
- 124 p.
- Report number
- NUREG--0573
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 11513687
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- ECCS; HYDRAULICS; LIQUID FLOW; LOSS OF COOLANT; PERFORMANCE; PRESSURE GRADIENTS; PWR TYPE REACTORS; REACTOR SAFETY; SIMULATION
- Descriptors DEC
- ACCIDENTS; FLUID FLOW; REACTOR ACCIDENTS; REACTOR PROTECTION SYSTEMS; REACTORS; SAFETY; WATER COOLED REACTORS; WATER MODERATED REACTORS