Published August 1980
| Version v1
Report
Boiling heat transfer mechanisms in reactor thermal-hydraulics
Description
This review discusses basic boiling heat transfer mechanisms of interest to boiling water reactor and pressurized water reactor thermal-hydraulics. Included are the present understanding and recent advances in incipient boiling, nucleate boiling, burnout, post dryout, and quenching. Brief mention is made of other heat transfer processes of interest to reactor operation under normal and fault conditions
Additional details
Additional titles
- Augmented title (English)
- PWR; BWR
Publishing Information
- Imprint Title
- Proceedings of the ANS/ASME/NCR international topical meeting on nuclear reactor thermal-hydraulics: fundamental aspects of two-phase flow and boiling heat transfer
- Journal Page Range
- p. 1019-1042.
- Report number
- NUREG/CP--0014(Vol.2)
Conference
- Title
- ANS/ASME topical meeting on reactor thermal-hydraulics.
- Dates
- 9 - 12 Oct 1980.
- Place
- Saratoga, NY, USA.
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 12641495
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BURNOUT; BWR TYPE REACTORS; CRITICAL HEAT FLUX; HEAT TRANSFER; HYDRAULICS; LOSS OF COOLANT; NUCLEATE BOILING; PWR TYPE REACTORS; REACTOR SAFETY; TWO-PHASE FLOW
- Descriptors DEC
- ACCIDENTS; BOILING; ENERGY TRANSFER; FLUID FLOW; HEAT FLUX; PHASE TRANSFORMATIONS; REACTOR ACCIDENTS; REACTORS; SAFETY; WATER COOLED REACTORS; WATER MODERATED REACTORS