Published February 1993
| Version v1
Journal article
Experimental study of thermal-hydraulic processes and distribution in the model of the AST-500 protection vessel
Description
The results of experimental study of the thermal-hydraulic processes and gas distribution in the AST-500 protection vessel model designed for localization of steam outflow are presented. The recommendations for calculating the intensity of vertical heat transfer over one-phase flow (water, air) and conditions for gas exhausting (without mixing) by steam against gravitation forces are proposed. 5 refs., 7 figs
Additional details
Additional titles
- Original title (Russian)
- Экспериментальное исследование теплогидравлических процессов и газораспределения в модели страховочного корпуса AST-500
Publishing Information
- Journal Title
- Atomnaya Ehnergiya
- Journal Volume
- 74
- Journal Issue
- 2
- Journal Page Range
- p. 108-113.
- ISSN
- 0004-7163
- CODEN
- AENGAB
INIS
- Country of Publication
- Russian Federation
- Country of Input or Organization
- Russian Federation
- INIS RN
- 25044782
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- AIR; CONTAINMENT SHELLS; DISTRICT HEATING; HEAT TRANSFER; HYDRAULICS; LOSS OF COOLANT; MEDIUM PRESSURE; NUCLEAR POWER PLANTS; PRESSURE GRADIENTS; SIMULATION; SPATIAL DISTRIBUTION; STEAM; TEMPERATURE DISTRIBUTION; TEMPERATURE RANGE 0273-0400 K; TEMPERATURE RANGE 0400-1000 K; WWER TYPE REACTORS
- Descriptors DEC
- ACCIDENTS; CONTAINMENT; DISTRIBUTION; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; FLUIDS; GASES; HEATING; NUCLEAR FACILITIES; POWER PLANTS; POWER REACTORS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTORS; TEMPERATURE RANGE; THERMAL POWER PLANTS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS