Reentrainment of droplet from grid spacer in mist flow portion of LOCA reflood of PWR
Description
An investigation is made on the influence of a quenched grid spacer on the greatly enhanced heat transfer from heated fuel rods during the mist flow phase of emergency reflood of loss of coolant accident (LOCA) of a pressurized water reactor (PWR). The situation for the case of a dry grid spacer before its quenching has not been covered in this study. The experimental technique used is a relatively simple optical scheme which combines the reference-mode laser-Doppler anemometry making use of the scattering of a light beam from a droplet. The results reveal that the large droplets in the mist flow, which are intercepted by the grid spacer, are responsible for the creation of a large number of smaller droplets. These small droplets, due to their large surface area to mass ratios, can serve as superb evaporative cooling agents to heat transfer downstream of the grid spacer
Additional details
Publishing Information
- Imprint Title
- Joint NRC/ANS meeting on basic thermal hydraulic mechanisms in LWR analysis
- Journal Page Range
- p. 477-492.
- Report number
- NUREG/CP--0043
Conference
- Title
- NRC/ANS meeting on basic thermal hydraulic mechanisms in LWR analysis.
- Dates
- 14-15 Sep 1982.
- Place
- Bethesda, MD (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 15009321
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ANEMOMETERS; DROPLETS; ECCS; ENTRAINMENT; EVAPORATIVE COOLING; FUEL ASSEMBLIES; HEAT TRANSFER; HYDRAULICS; LOSS OF COOLANT; PWR TYPE REACTORS; SPACERS
- Descriptors DEC
- ACCIDENTS; COOLING; ENERGY TRANSFER; MEASURING INSTRUMENTS; PARTICLES; REACTOR ACCIDENTS; REACTOR PROTECTION SYSTEMS; REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS