Application of two-phase flow modeling. Final report. [BWR; PWR]

Technical Report · Sat Jan 01 00:00:00 EST 1977

DOI:https://doi.org/10.2172/7315511· OSTI ID:7315511

Stuhmiller, J. H.

The report summarizes research conducted under EPRI Project RP599-1 to advance the understanding and ability to predict multi-phase flows. Various computational and theoretical methods are evaluated for their pertinence to problems of reactor safety. An analytical technique based on rigorous consideration of subprocesses is described that offers a general framework for obtaining engineering models. The boiling of superheated water is analyzed in some detail to illustrate the application of the procedure in a specific case. Comparisons with experimental measurement are given.

• Research Organization: JAYCOR, Del Mar, CA (USA)
• OSTI ID: 7315511
• Report Number(s): EPRI-NP-349; TRN: 77-007245
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
42 ENGINEERING
BWR TYPE REACTORS
LOSS OF COOLANT
TWO-PHASE FLOW
PWR TYPE REACTORS
MATHEMATICAL MODELS
FLUID FLOW
ACCIDENTS
REACTOR ACCIDENTS
REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
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420400 - Engineering- Heat Transfer & Fluid Flow