Published February 1987
| Version v1
Report
Dryout front modeling for rod bundles
Creators
- 1. Massachusetts Institute of Technology, Cambridge
Description
The dryout zone is that region between the calculated pool liquid level and the point where a rod or tube submerged in the pool dries out. A method of calculating the extent of the dryout zone is presented. Recommended values for the drift flux model constants are given for rod bundles. These are needed to make these calculations. For void fractions less than 0.45 at the free surface, the dryout front and the water are level virtually the same. For void fractions above, 0.45, the extent of the dryout front is proportioned to the superficial velocity of the vapor, rising to a value of .3m for a superficial velocity of 2m/s
Additional details
Publishing Information
- Imprint Title
- Proceedings of the US Nuclear Regulatory Commission fourteenth water reactor safety information meeting: Volume 4, ECCS [Emergency Core Cooling Systems] rule revision, integral systems testing, separate effects/experiments and analyses, 2D/3D research
- Journal Page Range
- p. 265-276.
- Report number
- NUREG/CP--0082-Vol.4
Conference
- Title
- 14. water reactor safety information meeting.
- Dates
- 27-31 Oct 1986.
- Place
- Gaithersburg, MD (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 19002127
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S42: ENGINEERING;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BWR TYPE REACTORS; DRYOUT; FLOW MODELS; FUEL ELEMENT CLUSTERS; HEAT TRANSFER; HYDRAULICS; LOSS OF COOLANT; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR SAFETY; TRANSIENTS; WATER
- Descriptors DEC
- ACCIDENTS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; FUEL ASSEMBLIES; HYDROGEN COMPOUNDS; MATHEMATICAL MODELS; OXYGEN COMPOUNDS; POLAR SOLVENTS; POWER REACTORS; REACTORS; SAFETY; SOLVENTS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS