Experimental studies of PWR safety injection branch flow
Creators
- 1. Societe Franco-Americaine de Constructions Atomiques (FRAMATOME), 92 - Courbevoie (France)
- 2. Ecole des Mines de Saint Etienne, Grenoble, France
Description
The safety injection water, injected through the auxilliary piping in the primary circuit of pressurized water reactors, may be at a temperature significantly different from that of the primary fluid. Some fatigue analyses have shown that it is necessary to install thermal sleeves for protecting nozzles against cyclical thermal stresses. Moreover, the primary flow can induce vibrations at a level which can have a detrimental effect on the thermal sleeve. This paper shows the results of an experimental study performed by Framatome, which presents both the thermal efficiency and the vibration behaviour of thermal sleeves. Two reduced scale models (1/5) of a 12 inch size nozzle have been tested. One nozzle is perpendicular to the main circuit, the other inclined at 450. (Auth.)
Additional details
Publishing Information
- Publisher
- North-Holland.
- Imprint Place
- Amsterdam, Netherlands
- ISBN
- 0 444 85062 7
- Imprint Title
- Structural mechanics in reactor technology
- Journal Page Range
- v. B p. B5/3 1-15.
Conference
- Title
- 4. international conference on structural mechanics in reactor technology.
- Dates
- 15 - 19 Aug 1977.
- Place
- San Francisco, USA.
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- Netherlands
- INIS RN
- 10433721
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AUXILIARY WATER SYSTEMS; FLUID FLOW; PRIMARY COOLANT CIRCUITS; PWR TYPE REACTORS; REACTOR SAFETY; THERMAL SHOCK; THERMAL STRESSES
- Descriptors DEC
- COOLING SYSTEMS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; SAFETY; STRESSES; WATER COOLED REACTORS; WATER MODERATED REACTORS