Published 1989 | Version v1
Book Metadata-only

The effect of thermal gravity on turbulent heat transfer in vertical channels

Creators

  • 1. AN Litovskoj SSR, Kaunas (USSR). Inst. Fiziko-Tekhnicheskikh Problem Ehnergetiki

Description

Some experimental results of combined forced and free convection are presented for an upward flow in a heated vertical right pipe. Different heat loads were studied, and a general correlation equation was found able to predict the locations of the first temperature maximum in the pipe wall, and the heat transfer rate at this point for air and water. Some experimental data on combined convection for upward and downward flows of air in a vertical, concentric annulus are also presented. The minimum heat transfer due to thermal gravity was less pronounced in the annulus, than in the pipe. (orig.)

Additional details

Publishing Information

Publisher
Braun.
Imprint Place
Karlsruhe (Germany, F.R.)
ISBN
3-7650-1116-9
Imprint Title
Fourth international topical meeting on nuclear reactor thermal-hydraulics (NURETH-4). Proceedings. Vol. 2
Imprint Pagination
696 p.
Journal Page Range
p. 753-758.

Conference

Title
4. international topical meeting on nuclear reactor thermal-hydraulics (NURETH-4).
Dates
10-13 Oct 1989.
Place
Karlsruhe (Germany, F.R.).

INIS

Country of Publication
Germany
Country of Input or Organization
Germany
INIS RN
22037746
Subject category
S42: ENGINEERING; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
AIR; BWR TYPE REACTORS; FORCED CONVECTION; HEAT TRANSFER; HYDRAULICS; NATURAL CONVECTION; PIPES; PWR TYPE REACTORS; REACTOR SAFETY EXPERIMENTS; SIMULATION; TURBULENCE; TWO-PHASE FLOW
Descriptors DEC
CONVECTION; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; FLUID FLOW; FLUIDS; GASES; POWER REACTORS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS