Published May 1984 | Version v1
Report Restricted

Two-field and drift-flux models with applications to nuclear reactor safety

Creators

Description

The ideas of the two-field (6 equation model) and drift-flux (4 equation model) description of two-phase flows are presented. Several example calculations relating to reactor safety are discussed and comparisons of the numerical results and experimental data are shown to be in good agreement

Availability note (English)

MF available from INIS under the Report Number; Available from NTIS, PC A02/MF A01; 1 as DE84012456.

Files

Restricted

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

Additional details

Publishing Information

Imprint Pagination
16 p.
Report number
LA-UR--84-1650

Conference

Title
IAEA technical committee/workshop on the uses of computer codes for nuclear reactor safety analysis.
Dates
29 May - 1 Jun 1984.
Place
Varna (Bulgaria).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
16006992
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
CRITICAL FLOW; FLOW RATE; FLUID-STRUCTURE INTERACTIONS; LMFBR TYPE REACTORS; LOSS OF COOLANT; MATHEMATICAL MODELS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR SAFETY; TWO-PHASE FLOW
Descriptors DEC
ACCIDENTS; BREEDER REACTORS; ENRICHED URANIUM REACTORS; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; FLUID FLOW; LIQUID METAL COOLED REACTORS; POWER REACTORS; REACTORS; SAFETY; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Secondary number(s)
CONF-8405164--3.