Published 1980
| Version v1
Report
Condensation heat transfer coefficients in LWR-containments during LOCA
Description
Best estimate calculations in nuclear safety analysis require replacement of conservative assumptions by measured data or verified correlations. In the field of containment response analysis this holds for condensation heat transfer coefficients at containment structures. In a large scale pressure suppression test facility heat transfer coefficients are determined at structures of the drywell in order to get data representative for break compartments of LWR-containments. Experimental results show heat transfer coefficients of the order 104 W.m-2.K-1 even at presence of noncondensable gas
Additional details
Publishing Information
- Imprint Title
- Proceedings of the ANS/ASME/NRC international topical meeting on nuclear reactor thermal-hydraulics: PWR and BWR reactor-plant performance analysis and containment technology
- Journal Page Range
- p. 400-415.
- Report number
- NUREG/CP--0014(Vol.1)
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
- 12641480
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BWR TYPE REACTORS; CONTAINMENT SYSTEMS; HEAT TRANSFER; HYDRAULICS; LOSS OF COOLANT; PRESSURE SUPPRESSION; PWR TYPE REACTORS; REACTOR SAFETY
- Descriptors DEC
- ACCIDENTS; CONTAINMENT; ENERGY TRANSFER; REACTOR ACCIDENTS; REACTORS; SAFETY; WATER COOLED REACTORS; WATER MODERATED REACTORS