Critical quality prediction for saturated flow boiling of CO2 in horizontal small diameter tubes

The dryout for flow boiling carbon dioxide (CO₂) in horizontal small diameter tubes is investigated through experiment and theoretical modeling. Tests are conducted in conditions where the saturation temperature is 0, 5, and 10 °C, heat flux is 7.2-48.1 kW/m² and mass flux is 500-3000 kg/m² s. The dryout phenomena of CO₂ are similar with those of water in many respects, while the effects of mass flux on dryout show differences among them. The dryout of CO₂ is predicted by a theoretical dryout model, which is developed and verified with steam-water data. Two entrainment mechanisms of interface deformation and bubble bursting are considered in the model and dryout is determined when the liquid film thickness is less than the critical liquid film thickness, the criteria film thickness of dryout. The present model well predicts the experimental critical qualities except when mass flux is relatively high, at which the deposition of liquid droplet on the liquid film and the occurrence of dryout patches become very significant.     

基于逐步回归无量纲棒束CHF关系式开发与DNBR限值确定

针对目前国内外先进压水堆棒束临界热流密度（CHF）经验关系式普遍存在数学形式复杂、自变量系数众多且缺乏物理意义的共性问题,以美国电力研究院（EPRI）棒束CHF数据库中遴选的485个5×5压水堆棒束CHF数据点为基础,基于逐步回归分析开发了一套新型无量纲棒束CHF关系式。考虑了导向管冷壁效应与轴向非均匀加热效应后,实测CHF与预测CHF之比M/P的平均值为0.998,均方根偏差为0.0546,标准差为0.0546,基于分组法确定了关系式的95/95 偏离泡核沸腾比（DNBR）限值为1.16。     

Surface Coating Studies of Alkyd-Castor Oil-Epoxy Resin Condensate-Ketone Resin Blends

Castor oil (CO) was reacted with commercial epoxy resin (ER) (diglycidylether of bisphenol-A, DGEBA) at various mole ratios. The resultant products were designated as COERs and characterized by physical, chemical and IR spectral studies. A commercial alkyd resin was blended with various proportions of COERs and ketone resin (i.e., cyclohexanone-formaldehyde resin) (CHF). All the blends were applied on mild steel panels and characterized for drying time, adhesion, flexibility, hardness, impact resistance and chemical resistance properties.     

Determination of Electron Swarm Parameters in Pure CHF3 and CF4 by a Time-Resolved Method

The density-normalized effective ionization coefficient (α-η)/N (α and η are the ionization and attachment coefficients respectively), the electron drift velocity V e and density-normalized longitudinal diffusion coefficient ND L in trifluoromethane (CHF3 ) and carbon tetrafluoride (CF4 ) were measured using a pulsed Townsend technique over a wide E/N range. From the plots of (α-η)/N, we have derived the limiting field strength, (E/N) lim , which is valid for the analysis of insulation characteristics and applications to power equipment. Comparisons of the electron swarms parameters between CHF3 and CF4 have been performed, and the global warming potential (GWP) is also taken into account.     

Single nozzle spray cooling heat transfer mechanisms

An investigation into single nozzle spray cooling heat transfer mechanisms with varying amounts of dissolved gas was performed using two powerful techniques. Time and space resolved heat transfer distributions produced by a single nozzle were measured using an array of individually controlled microheaters, while visualization and measurements of the liquid-solid contact area and the three-phase contact line length were made using a total internal reflectance technique. The presence of dissolved gas increased the effective subcooling of the liquid, and shifted the spray cooling curves to higher wall temperatures, but CHF was also increased. The phase-change heat transfer contribution was found to correlate directly with the contact line length for the experimental conditions tested.     

Model‐Based Analysis of the ZrO2 Etching Mechanism in Inductively Coupled BCl3/Ar and BCl3/CHF3/Ar Plasmas

The etching mechanism of ZrO₂ thin films and etch selectivity over some materials in both BCl₃/Ar and BCl3/CHF3/Ar plasmas are investigated using a combination of experimental and modeling methods. To obtain the data on plasma composition and fluxes of active species, global (0‐dimensional) plasma models are developed with Langmuir probe diagnostics data. In BCl3/Ar plasma, changes in gas mixing ratio result in nonlinear changes of both densities and fluxes for Cl, BCl2, and BCl2⁺. In this work, it is shown that the nonmonotonic behavior of the ZrO2 etch rate as a function of the BCl3/Ar mixing ratio could be related to the ion‐assisted etch mechanism and the ion‐flux‐limited etch regime. The addition of up to 33% CHF₃ to the BCl₃‐rich BCl3/Ar plasma does not influence the ZrO2 etch rate, but it non‐monotonically changes the etch rates of both Si and SiO2. The last effect can probably be associated with the corresponding behavior of the F atom density.     

Experimental investigation on critical heat flux in horizontal channel for low pressure low flow (LPLF) condition

Studies reported in the past on critical heat flux (CHF) are mostly limited to vertical flow, large channel diameter, high pressure and high mass flux. Only few investigations are reported in the literature for horizontal flow CHF especially under low pressure and low flow conditions. Hence, predictive methods of CHF for horizontal flow are scarce. There is a need for understanding CHF in horizontal flow under low pressure and low flow conditions because they are commonly encountered in nuclear reactor fuel channels of pressurized heavy water reactor (PHWR) under loss of coolant accidental (LOCA) conditions. The present work investigates CHF of horizontal flow for low flow rates (mass flux of 100–400 kg/m² s) at nearly atmospheric pressure conditions. Parameters covered in this study are diameter (5.5 mm, 7.5 mm and 9.5 mm), length (0.45 m and 0.8 m) and a inlet temperature of 32 °C. The first occurrence of ‘red hot’ spot on the test section is considered as the onset of critical heat flux condition in the present work. Experimental results obtained are compared with Groeneveld et al. (2007) look up table data for vertical flow after applying correction factor given by Wong et al. (1990). The deviation of experimental CHF data from those predicted using Groeneveld et al. (2007) look up table and Wong et al. (1990) correction factor is more than 50%.     

Investigations on heat transfer enhancement in pool boiling with water-CuO nano-fluids

The main focus of the present work is to investigate Critical Heat Flux (CHF) enhancement using CuO nanofluid relative to CHF of pure water. To estimate the effect of nanoparticles on the CHF, pool boiling CHF values were measured for various volume concentrations of CuO nanofluid and compared with pure water. CHF enhancement of 130% was recorded at 0.2 % by volume of CuO nano-fluids. Surface roughness of the heater surface exposed to three measured heating cycles indicated surface modifications at different volume concentrations of nanofluid. SEM image of the heater surface revealed porous layer build up, which is thought to be the reason for CHF enhancement.     

倾角变化的窄缝通道内CHF理论模型

对倾角变化的矩形窄缝通道的临界热流密度(CHF)进行分析,基于逆向对流限制(CCFL)机理建立相应的理论分析模型,并将该理论模型的预测结果与已有的实验结果进行对比。结果表明:当矩形窄缝通道尺寸为1 mm和2 mm,且倾角在范围在15°~90°时,预测结果与实验值符合得比较好;在倾角小于15°时,理论模型对CHF的预测明显小于实验值;修正的Katto-Kosho关系式可以比较准确地预测倾角小于15°时的CHF值;当通道尺寸为5 mm和10 mm时,预测值比实验值大,这表明基于CCFL机理的CHF预测理论模型仅适用于通道尺寸小于等于2 mm的窄缝通道。     

Steady state thermal-hydraulic analysis of hydride-fueled grid-supported BWRs

A steady state thermal-hydraulic analysis was performed to estimate the power density attainable with hydride-fueled boiling water reactor (BWR) cores with respect to that of an existing oxide BWR core chosen as reference. The power-limiting constraints taken into account were the minimum critical power ratio (MCPR), core pressure drop, fuel average and centerline temperature, cladding outer temperature, flow-induced vibrations and power/flow ratio.The study consisted of two independent analyses: a whole core analysis and a single bundle analysis. The whole core analysis was performed, with a fixed core volume, for both hydride and oxide fuel over hundreds of combinations of rod diameter-rod pitch, referred to as “geometries”, in the ranges 0.6 ≤ D ≤ 1.6 cm and 1.1 ≤ P/D ≤ 1.6. For each geometry, the maximum achievable steady state core power was calculated. Preliminary neutronics results derived from a companion neutronic study were then overlaid on the whole-core thermal-hydraulic results to estimate the reduction in maximum achievable power caused by the application of neutronic constraints. The single bundle analysis was performed to compare in greater detail the thermal-hydraulic performance of a limited number of hydride and oxide fuel bundles having D and P values similar to those of the reference oxide bundle, and for which the compliance with neutronic constraints was demonstrated in a companion neutronic study.The study concluded that, if the core pressure drop is not allowed to increase above the reference core value, the power density increase attainable with hydride fuel is estimated to be in the range 0-15%. If the pressure drop is allowed to increase up to a value 50% higher than the reference core value, the power density increase is estimated to be in the range 25-45%. These power density increases, which are defined with respect to the reference oxide core, decrease about 10% if the comparison is made with respect to oxide designs resembling the most recent commercial high-performance oxide cores.The power gain capability of hydride fuel is primarily due to the possibility of: (1) replacing volumes occupied by water rods and water gaps in oxide fuel cores with fuel rods, thus increasing the heat transfer area per core volume, and (2) flattening the bundle pin-by-pin power distribution.The actual achievement of the above-mentioned power density increase is however conditioned to the compliance of hydride-fueled cores to safety requirements related to core behavior during transients, hydrodynamic stability and steam dryer performance, which are fields of study not addressed in this work. A potential 25-45% power density increase justifies however interest for further investigation on this alternative fuel.