Published November 1975 | Version v1
Report Restricted

Transient three-dimensional thermal-hydraulic analysis of nuclear reactor fuel rod arrays: general equations and numerical scheme

Creators

Description

A mathematical model and a numerical solution scheme for thermal-hydraulic analysis of fuel rod arrays are given. The model alleviates the two major deficiencies associated with existing rod array analysis models, that of a correct transverse momentum equation and the capability of handling reversing and circulatory flows. Possible applications of the model include steady state and transient subchannel calculations as well as analysis of flows in heat exchangers, other engineering equipment, and porous media

Availability note (English)

MF available from INIS under the Report Number; Available from NTIS.

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Additional details

Publishing Information

Imprint Pagination
47 p.
Report number
ANCR--1207

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
7244569
Subject category
S61: RADIATION PROTECTION AND DOSIMETRY;
Descriptors DEI
BWR TYPE REACTORS; FUEL ASSEMBLIES; HEAT TRANSFER; HYDRAULICS; MATHEMATICAL MODELS; PWR TYPE REACTORS; THREE-DIMENSIONAL CALCULATIONS; TWO-PHASE FLOW
Descriptors DEC
ENERGY TRANSFER; FLUID FLOW; REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
Available from NTIS.