Published September 1978 | Version v1
Report Restricted

COMMIX-1: a three-dimensional transient single-phase component computer program for thermal-hydraulic analysis

Creators

Description

A mathematical model, COMMIX-1 Computer Program, for three-dimensional, transient, single-phase, thermal-hydraulic analysis of reactor components is presented. A set of governing equations for the conservation of mass, momentum, and energy is solved as a boundary-value problem in space and as an initial-value problem in time. The model can treat both continuum (e.g., reactor plenum) and quasi-continuum (e.g., rod bundles or fuel assembly) sodium systems. Volume porosity, surface permeability, and distributed resistance are used in the quasi-continuum approach, which alleviates two inherent deficiencies associated with conventional subchannel analysis; one is the approximation used in the formulation of transverse momentum equations, the other is its inability of handling reverse flow or recirculatory flow

Availability note (English)

MF available from INIS under the Report Number; Available from NTIS., PC A06/MF A01.

Files

Restricted

The record is publicly accessible, but files are restricted to users with access.

Additional details

Additional titles

Augmented title (English)
LMFBR

Publishing Information

Imprint Pagination
122 p.
Report number
NUREG/CR--0785

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
10480703
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Descriptors DEI
C CODES; HEAT TRANSFER; HYDRAULICS; LIQUID FLOW; LMFBR TYPE REACTORS; MIXING; REACTOR COMPONENTS; REACTOR CORES; SPATIAL DISTRIBUTION
Descriptors DEC
BREEDER REACTORS; COMPUTER CODES; DISTRIBUTION; ENERGY TRANSFER; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; FLUID FLOW; LIQUID METAL COOLED REACTORS; REACTORS

Optional Information

Secondary number(s)
ANL--77-96.