Study of the hovering period and bubble size in fully developed pool nucleate boiling of saturated liquid with a time-dependent heat source
Description
In this paper, the bubble behavior in saturated pool boiling with a time-dependent heat source is analyzed. The study is restricted to the period from fully developed nucleate boiling until critical heat flux occurs. The hovering period and the departure volume of the bubble are selected as the characteristic parameters for bubble behavior. These parameters are quantified by solving the equation of motion for an idealized bubble. This equation is solved for cases in which the surface heat flux changes linearly and exponentially as a function of time. After nondimensionalization, the results are compared directly with the results of the steady-state problem. The comparison shows that the transient heat input has practically no effect on the hovering period. However, the transient heat flux causes a decreased volume at bubble departure. The volume decrease is dependent on the severity of the transient. These results are in qualitative agreement with the experimental observation quoted in the literature
Availability note (English)
Available from NTIS, PC A02/MF A01 as DE87005110.
Files
Additional details
Publishing Information
- Imprint Pagination
- 15 p.
- Report number
- LA-UR--87-116
Conference
- Title
- 24. national heat transfer conference and exhibition.
- Dates
- 9-12 Aug 1987.
- Place
- Pittsburgh, PA (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 19018871
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S42: ENGINEERING;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BUBBLES; BWR TYPE REACTORS; EQUATIONS OF MOTION; HEAT FLUX; MATHEMATICAL MODELS; NUCLEATE BOILING; POOL BOILING; PWR TYPE REACTORS; TRANSIENT OVERPOWER ACCIDENTS
- Descriptors DEC
- ACCIDENTS; BOILING; DIFFERENTIAL EQUATIONS; ENRICHED URANIUM REACTORS; EQUATIONS; PARTIAL DIFFERENTIAL EQUATIONS; PHASE TRANSFORMATIONS; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-870816--5.