Published 1989 | Version v1
Book Metadata-only

Single phase flow mixing studies of nuclear fuel bundles for PHWRs

Creators

  • 1. Reactor System and Analysis Division, BARC, Bombay (India)
  • 2. Nuclear Power Corporation, South Site, BARC, Bombay, (India)
  • 3. Indian Inst. of Science, Bangalore (India)

Description

Turbulent cross-flow mixing characteristics for PHWR fuel bundles was studied by conducting an experiment using salt injection technique. Plots of normalised concentration vs. axial distance for various turbulent cross-flow mixing factors (β) were compared with the corresponding values obtained from the experiment. In this paper, the theoretical aspects of mixing, details of experiment conducted, correlation for cross-flow mixing factor and future work planned are presented. (author). 7 refs., 4 figs

Additional details

Publishing Information

Publisher
Indian Society for Heat and Mass Transfer.
Imprint Place
Madras (India)
Imprint Title
Proceedings of the 10"t"h national heat and mass transfer conference [held at Srinagar during August 23-25, 1989]
Imprint Pagination
534 p.
Journal Page Range
p. 165-170.

Conference

Title
10. National heat and mass transfer conference.
Dates
23-25 Aug 1989.
Place
Srinagar (India).

INIS

Country of Publication
India
Country of Input or Organization
India
INIS RN
24007466
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Numerical Data
Descriptors DEI
C CODES; COOLANT LOOPS; CROSSFLOW SYSTEMS; EXPERIMENTAL DATA; FUEL CHANNELS; FUEL ELEMENT CLUSTERS; MIXING; PHWR TYPE REACTORS; REACTOR COOLING SYSTEMS; SODIUM CHLORIDES; TURBULENT FLOW
Descriptors DEC
ALKALI METAL COMPOUNDS; CHLORIDES; CHLORINE COMPOUNDS; COMPUTER CODES; COOLING SYSTEMS; DATA; FLUID FLOW; FUEL ASSEMBLIES; HALIDES; HALOGEN COMPOUNDS; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; INFORMATION; NUMERICAL DATA; REACTOR CHANNELS; REACTOR COMPONENTS; REACTORS; SODIUM COMPOUNDS