A study was designed to examine the pharmacokinetics of theophylline in a well defined group of congestive heart failure (CHF) patients, without liver disease, and to evaluate the validity of the dosage guidelines recommended by the FDA. A total of five CHF patients and seven non-CHF patients were entered and...
Occurring in the most challenging nuclear power plant accidents, transient critical heat flux (CHF) is the primary phenomenon that drives peak cladding temperature and ultimately fuel failure. It is unclear whether the use of steady-state CHF correlations can accurately predict the gross thermal-hydraulic perturbations of a blowdown in a large...
Enhanced pool boiling critical heat fluxes (CHF) at reduced wall superheat on nanostructured
substrates are reported. Nanostructured surfaces were realized using a low temperature process,
microreactor-assisted-nanomaterial-deposition. Using this technique we deposited ZnO nanostructures
on Al and Cu substrates. We observed pool boiling CHF of 82.5 W/cm2 with water as
fluid...
In the most challenging nuclear power plant accidents, transient critical heat flux (CHF) is a primary phenomenon that drives peak cladding temperature and ultimately fuel failure. It is not yet determined whether the use of steady-state CHF methods can accurately predict transient CHF under the conditions of a blowdown due...
The reactivity-initiated accident (RIA) accident has stirred wide interest for the need of designing advanced and high tolerance fuels for next generation nuclear power plants. For pressurized water reactors (PWRs), the accidentally induced reactivity pulse adds transient energy input to the fuel. As a result, boiling may happen locally. Boiling...
A mechanistic based critical heat flux (CHF) correlation has been developed derived from a mass, momentum, and energy balance at a nucleation site for water. The trigger mechanism for the CHF condition is postulated to be related to the maximum boiling frequency on a heated surface. It is observed that...
Critical Heat Flux (CHF) is an important safety parameter for the design of nuclear reactors. The most commonly used predictive tool for determination of CHF is a look-up table developed using tube data with an average hydraulic test diameter of 8 mm. There exist in the world today nuclear reactors...
The collective understanding of the critical heat flux phenomenon is crucial to the safety and operational power limits of every nuclear and petrochemical power plant in the world. To define the maximum heat transfer capability in the postulated reactivity-initiated accident in a nuclear reactor, the mechanisms that trigger the departure...
This objective of this study is to investigate the capability of nanostructured surfaces on dissipating heat flux by performing pool boiling and convective flow boiling. The generation of ultra-high heat flux from high performance electric devices has motivated a number of investigations related to advanced heat transfer especially in two-phase...
The understanding of critical heat flux is crucial for the safety of nuclear reactors. To this end, many studies have been carried out to understand various aspects of the boiling crisis phenomenon. Power transient critical heat flux trigger mechanisms is a small category that is relatively under-studied and not well...