Published 1987 | Version v1
Book Metadata-only

PWR steam generators: A set of experimental programs for three dimensional code validation

Creators

Description

The Steam Generators of PWRs must remain perfectly leaktight throughout years of operation. They are designed with two-phase flow three-dimensional computer codes (i.e. CAFCA). This article deals with experiments carried out in tube bundles to improve some empirical laws used in these codes. In particular the authors measured pressure drops and local void fraction (by optical probes) in crossflow across various tube layouts. The results obtained by measurements in two-phase flow conditions are quite different from the stranded correlations found in the literature

Additional details

Publishing Information

Publisher
American Society of Mechanical Engineers.
Imprint Place
New York, NY (USA)
Imprint Pagination
6 p.

Conference

Title
ASME winter meeting.
Dates
13-18 Dec 1987.
Place
Boston, MA (USA).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
19084598
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Numerical Data
Descriptors DEI
COMPUTER CODES; EXPERIMENTAL DATA; FUEL ELEMENT CLUSTERS; LEAK DETECTORS; PRESSURE DROP; PWR TYPE REACTORS; REACTOR COMPONENTS; REACTOR SAFETY EXPERIMENTS; SPECIFICATIONS; STEAM GENERATORS; THREE-DIMENSIONAL CALCULATIONS; TWO-PHASE FLOW
Descriptors DEC
BOILERS; DATA; ENRICHED URANIUM REACTORS; FLUID FLOW; FUEL ASSEMBLIES; INFORMATION; NUMERICAL DATA; POWER REACTORS; REACTORS; THERMAL REACTORS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
Technical Paper 87-WA/NE-4.
Secondary number(s)
CONF-871234--.