Published 1980
| Version v1
Report
Experimental determination of the two-phase flow distribution at the tube sheet of a model PWR steam generator
Description
This paper presents the results of a series of air/water flow tests run on two model steam generator inlet plenums. The tests measured the two-phase flow distribution at the entrance region of each of the 32 tubes in the model steam generator tube bundle. The test superficial velocity boundary conditions are representative of steam generator inlet plenum conditions during the reflood phase of a large loss of coolant accident transient. The first test series was run on a 1/10 scale model of a vertical U-tube steam generator inlet plenum. The second model plenum was a long cylindrical plenum identical to the inlet plenum of the FLECHT-SEASET model steam generator
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. 504-534.
- 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
- 12641482
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- HEAT TRANSFER; HYDRAULICS; LOSS OF COOLANT; MOCKUP; PWR TYPE REACTORS; REACTOR SAFETY; STEAM GENERATORS; TWO-PHASE FLOW
- Descriptors DEC
- ACCIDENTS; BOILERS; ENERGY TRANSFER; FLUID FLOW; REACTOR ACCIDENTS; REACTORS; SAFETY; STRUCTURAL MODELS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS