Published September 1995 | Version v1
Report Metadata-only

The sudden coalescene model of the boiling crisis

Creators

  • 1. Centro Atomico Bariloche and Instituto Balseiro, Bariloche (Argentina)

Description

A local two-phase flow integral model of nucleate boiling and crisis is presented. The model is based on average balances on a control volume, yielding to a set of three nonlinear differential equations for the local void fraction, bubble number density and velocity. Boiling crisis as critical heat flux is interpreted as a dynamic transition caused by the coalescence of bubbles near the heater. The theoretical dynamic model is compared with experimental results obtained for linear power ramps in a horizontal plate heater in R-113, showing an excellent qualitative agreement

Additional details

Publishing Information

Imprint Title
Proceedings of the 7th International Meeting on Nuclear Reactor Thermal-Hydraulics NURETH-7. Sessions 17-24
Imprint Pagination
825 p.
Journal Page Range
p. 2452-2469.
Report number
NUREG/CP--0142-Vol.4

Conference

Title
7. international meeting on nuclear reactor thermal hydraulics.
Dates
10-15 Sep 1995.
Place
Saratoga, NY (United States).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
27019806
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BUBBLES; BWR TYPE REACTORS; COALESCENCE; HEAT TRANSFER; HOT SPOTS; HYDRAULICS; MATHEMATICAL MODELS; NUCLEATE BOILING; PWR TYPE REACTORS; REACTOR COOLING SYSTEMS; TWO-PHASE FLOW; VOID FRACTION
Descriptors DEC
BOILING; COOLING SYSTEMS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; FLUID FLOW; PHASE TRANSFORMATIONS; POWER REACTORS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Secondary number(s)
CONF-950904--Vol.4.