Published 1977 | Version v1
Book

Experimental studies of PWR safety injection branch flow

  • 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