Published June 1974 | Version v1
Journal article Metadata-only

Cross-flow approximations used in the thermal-hydraulic multichannel analysis

Creators

  • 1. Argonne National Lab., IL

Description

no abstract available

Additional details

Publishing Information

Journal Title
Trans. Amer. Nucl. Soc.
Journal Volume
18
Series
Trans. Amer. Nucl. Soc.
Journal Page Range
134-135

Conference

Title
Annual meeting of the American Nuclear Society.
Dates
23 Jun 1974.
Place
Philadelphia, PA.

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
5153114
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference, No Abstract
Descriptors DEI
DIFFERENTIAL EQUATIONS; FLUID FLOW; FUEL ASSEMBLIES; FUEL CHANNELS; HEAT TRANSFER; HYDRAULICS
Descriptors DEC
ENERGY TRANSFER; EQUATIONS; REACTOR CHANNELS; REACTOR COMPONENTS

Optional Information

Notes
Published in summary form only.