Published January 1980
| Version v1
Journal article
Homogeneous critical flow model for analysis of loss-of-coolant accident for BWR
Description
The determination of the blowdown flow rate is reviewed for the analysis of hypothetical nuclear reactor accidents. Blowdown tests simulating pipe ruptures in a boiling water reactor were conducted with various discharge nozzles. Transient vessel pressure, stagnation quality and blowdown flow rate were measured. The data obtained were compared with Moody's model and with the homogeneous model. Moody's model over-estimated the measured flow rate, while the homogeneous model gave a better estimate. 16 refs
Additional details
Publishing Information
- Journal Title
- Energy Dev. Jpn.
- Journal Volume
- 2
- Journal Issue
- 3
- Series
- Energy Dev. Jpn.
- Journal Page Range
- 265-278
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 13653641
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY;
- Descriptors DEI
- BLOWDOWN; BWR TYPE REACTORS; CRITICAL FLOW; LOSS OF COOLANT; MATHEMATICAL MODELS; PRESSURE GRADIENTS; SIMULATION
- Descriptors DEC
- ACCIDENTS; FLUID FLOW; REACTOR ACCIDENTS; REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS