Published 2006
| Version v1
Book
Towards a new modeling of the non-uniform flux effect on the boiling crisis
Creators
- 1. CEA Grenoble, Lab. de Thermohydraulique Gaz et Diphasique, 38 (France)
- 2. CEA Grenoble, Service d'Etudes Thermohydrauliques et Technologiques, 38 (France)
Description
In this work, a new approach is proposed which aims at quantifying the influence of an axial non-uniformity of the power profile on the boiling crisis (history effect). This model is inspired from the works initiated by Weisman and Pei (1983) and is based on a mechanical criterion for the occurrence of the critical flux. Several original closure laws established from the tests performed at the DEBORA facility have been developed (local measurements of the topology of a high pressure boiling two-phase flow using Freon R-12 refrigerant). The first tests are encouraging and promising. (J.S.)
Additional details
Additional titles
- Original title (French)
- Vers une nouvelle modelisation de l'effet de flux non uniforme sur la crise d'ebullition
Publishing Information
- Publisher
- Editions Societe Francaise de Thermique
- Imprint Place
- Paris (France)
- ISBN
- 2-905267-49-6
- Imprint Title
- Heat transfer challenges in the nuclear industry
- Imprint Pagination
- (t.1-3) 1263 p.
- Journal Page Range
- p. 101-106
Conference
- Title
- SFT 2006. French congress of thermal engineering. Heat transfer challenges in the nuclear industry
- Original Conference Title
- SFT 2006. Congres francais de thermique. Defis thermiques dans l'industrie nucleaire
- Dates
- 16-19 May 2006
- Place
- Ile de Re (France)
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 38088668
- Subject category
- S42: ENGINEERING; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BUBBLES; CRITICAL HEAT FLUX; DEPARTURE NUCLEATE BOILING; FLOW MODELS; FREONS; PWR TYPE REACTORS; THERMAL HYDRAULICS; THICKNESS; TWO-PHASE FLOW; VOID FRACTION
- Descriptors DEC
- BOILING; DIMENSIONS; ENRICHED URANIUM REACTORS; FLUID FLOW; FLUID MECHANICS; HALOGENATED ALIPHATIC HYDROCARBONS; HEAT FLUX; HYDRAULICS; MATHEMATICAL MODELS; MECHANICS; NUCLEATE BOILING; ORGANIC COMPOUNDS; ORGANIC HALOGEN COMPOUNDS; PHASE TRANSFORMATIONS; POWER REACTORS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 12 refs. Imprint:Defis thermiques dans l'industrie nucleaire