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Penn State University
1.
Huang, Shan.
INVESTIGATION OF ENHANCEMENT OF DOWNWARD FACING BOILING HEAT TRANSFER USING MICRO-POROUS COATINGS.
Degree: 2018, Penn State University
URL: https://submit-etda.libraries.psu.edu/catalog/15297sxh515 
► Nucleate boiling is a well-recognized means for passively removing high heat loads (up to ~106 W/m2) generated by a molten reactor core under severe accident…
(more)
▼ Nucleate boiling is a well-recognized means for passively removing high heat loads (up to ~106 W/m2) generated by a molten reactor core under severe accident conditions while maintaining relatively low reactor vessel temperature (<800 °C). With the upgrade and development of advanced power reactors, however, enhancing the nucleate boiling rate and its upper limit, Critical Heat Flux (CHF), becomes the key to the success of external passive cooling of reactor vessel undergoing core disrupture accidents. In the present study, I mainly focus on the use of a suitable surface coating to enhance downward-facing boiling rate and CHF limit so as to substantially increase the possibility of reactor vessel surviving high thermal load attack.
Among the various available surface coating techniques, metallic micro-porous layer surface coating has been identified as an appropriate coating material for use in External Reactor Vessel Cooling (ERVC) based on the overall consideration of enhanced performance, durability, the ease of manufacturing and application. Since no previous research work had explored the feasibility of applying such a metallic micro-porous layer surface coating on a large, downward facing and curved surface such as the bottom head of a reactor vessel, a series of characterization tests and experiments were performed in the present study to determine a suitable coating material composition and application method. Using the optimized metallic micro-porous surface coatings, quenching and steady-
state boiling experiments were conducted in the Sub-scale Boundary Layer Boiling (SBLB) test facility at
Penn State to investigate the nucleate boiling and CHF enhancement effects of the surface coatings by comparing the measurements with those for a plain vessel without coatings. An overall enhancement in nucleate boiling rates and CHF limits up to 100% were observed. Based on the results of visualizations in the quenching experiments, the coated vessel was found to quench much faster than the bare vessel under identical experimental conditions, indicating a higher downward-facing boiling heat transfer (i.e., cooling rate) for the coated vessel. It was also observed that the local rate of boiling and the local CHF limit tended to vary appreciably along the outer surface of the test vessel. Quantitative measurements showed that for all angular locations on the vessel outer surface, the local CHF values for the coated vessel were consistently higher than the corresponding CHF values for the bare vessel. Moreover, combination of data from quenching experiments and steady-
state experiments produced new sets of boiling curves, which covered both the nucleate and transient boiling regimes with much greater accuracy. Beside the experimental work, a theoretical CHF model has also been developed by considering the vapor dynamics and the boiling-induced two-phase motions in three separate regions adjacent to the heating surface. The CHF model is capable of predicting the performance of micro-porous coatings with given particle…
Advisors/Committee Members: Bill%20B%20Cheung%2C%20Thesis%20Advisor%2FCo-
Advisor%22%29&pagesize-30">
Fan-
Bill B Cheung,
Thesis Advisor/
Co-
Advisor.
Subjects/Keywords: CHF coating vessel
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APA (6th Edition):
Huang, S. (2018). INVESTIGATION OF ENHANCEMENT OF DOWNWARD FACING BOILING HEAT TRANSFER USING MICRO-POROUS COATINGS. (Thesis). Penn State University. Retrieved from https://submit-etda.libraries.psu.edu/catalog/15297sxh515
Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation
Chicago Manual of Style (16th Edition):
Huang, Shan. “INVESTIGATION OF ENHANCEMENT OF DOWNWARD FACING BOILING HEAT TRANSFER USING MICRO-POROUS COATINGS.” 2018. Thesis, Penn State University. Accessed March 03, 2021.
https://submit-etda.libraries.psu.edu/catalog/15297sxh515.
Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation
MLA Handbook (7th Edition):
Huang, Shan. “INVESTIGATION OF ENHANCEMENT OF DOWNWARD FACING BOILING HEAT TRANSFER USING MICRO-POROUS COATINGS.” 2018. Web. 03 Mar 2021.
Vancouver:
Huang S. INVESTIGATION OF ENHANCEMENT OF DOWNWARD FACING BOILING HEAT TRANSFER USING MICRO-POROUS COATINGS. [Internet] [Thesis]. Penn State University; 2018. [cited 2021 Mar 03].
Available from: https://submit-etda.libraries.psu.edu/catalog/15297sxh515.
Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation
Council of Science Editors:
Huang S. INVESTIGATION OF ENHANCEMENT OF DOWNWARD FACING BOILING HEAT TRANSFER USING MICRO-POROUS COATINGS. [Thesis]. Penn State University; 2018. Available from: https://submit-etda.libraries.psu.edu/catalog/15297sxh515
Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation
Penn State University
2.
Li, Zhiyu.
Inverted Annular Film Boiling Model Analysis.
Degree: 2013, Penn State University
URL: https://submit-etda.libraries.psu.edu/catalog/19185
► ABSTRACT Theoretical and experimental investigations conducted in the field of Inverted Annular Film Boiling (IAFB) have led to considerable developments. The heightened interest in IAFB…
(more)
▼ ABSTRACT
Theoretical and experimental investigations conducted in the field of Inverted Annular Film Boiling (IAFB) have led to considerable developments. The heightened interest in IAFB is also attributed to the increased importance of the same in a variety of practical applications across various industries. The occurrence of critical heat flux prompts an abrupt increase in the wall temperature which is further responsible for a physical burnout of the heated surface. IAFB conditions are usually not present during normal operations in nuclear reactors, but can be encountered in case of an accident following a loss of coolant. Experiments for measuring IAFB are not easy in conventional heat flux controlled systems and as a result different models and experiments need to be conducted. As a part of this
thesis, different methods have been discussed for the purpose of conducting experiments.
The data has been collected from 10 experiments involving reflood heat transfer performed in The Pennsylvania
State University/U.S. Nuclear Regulatory Commission Rod Bundle Heat Transfer (RBHT) Test Facility. Measurements were taken for heater rod temperatures, bundle power, upper plenum pressure, inlet flow rate and inlet subcooling, superheated vapor temperatures in the bundle, liquid carryover, spacer grid temperatures and axial bundle pressure drop. The results obtained from the reflood data were used as a basis for developing and accessing the model.
Many theoretical and experimental models have been developed for IAFB, as many heat transfer coefficient correlations have been proposed to predict the experimental data. In this work, all the important theoretical models applicable to IAFB are reviewed and the major correlations for IAFB are evaluated by comparing them with experimental data in order to identify the most optimized correlation.
Advisors/Committee Members: Advisor%22%29&pagesize-30">
Fan Bill B Cheung,
Thesis Advisor/
Co-
Advisor.
Subjects/Keywords: heat transfer; two-phase heat transfer; inverted annular film boiling; heat transfer; two-phase heat transfer; inverted annular film boiling; heat transfer; two-phase heat transfer; inverted annular film boiling
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APA (6th Edition):
Li, Z. (2013). Inverted Annular Film Boiling Model Analysis. (Thesis). Penn State University. Retrieved from https://submit-etda.libraries.psu.edu/catalog/19185
Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation
Chicago Manual of Style (16th Edition):
Li, Zhiyu. “Inverted Annular Film Boiling Model Analysis.” 2013. Thesis, Penn State University. Accessed March 03, 2021.
https://submit-etda.libraries.psu.edu/catalog/19185.
Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation
MLA Handbook (7th Edition):
Li, Zhiyu. “Inverted Annular Film Boiling Model Analysis.” 2013. Web. 03 Mar 2021.
Vancouver:
Li Z. Inverted Annular Film Boiling Model Analysis. [Internet] [Thesis]. Penn State University; 2013. [cited 2021 Mar 03].
Available from: https://submit-etda.libraries.psu.edu/catalog/19185.
Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation
Council of Science Editors:
Li Z. Inverted Annular Film Boiling Model Analysis. [Thesis]. Penn State University; 2013. Available from: https://submit-etda.libraries.psu.edu/catalog/19185
Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation
Penn State University
3.
Almudhhi, Turki Khalid.
EXPERIMENTAL STUDY OF HEAT TRANSFER DURING QUENCHING OF A HEATED ROD.
Degree: 2017, Penn State University
URL: https://submit-etda.libraries.psu.edu/catalog/14854tka5098
► Quenching experiments of a cylindrical rod were conducted in a distilled water pool in order to study the behavior of the critical heat flux (CHF)…
(more)
▼ Quenching experiments of a cylindrical rod were conducted in a distilled water pool in order to study the behavior of the critical heat flux (CHF) and the minimum heat flux (MHF). The effects of liquid subcooling, initial rod temperature, and surface condition on CHF and MHF were investigated during the quench process. The test specimen is a hollow stainless steel rod. The tip of the specimen is welded to prevent any water leakage inside the rod. The specimen has two thermocouples, one at the inner diameter and the other embedded in the wall. Both thermocouples are located at the same axial elevation. During the experiment, all thermocouple readings were taken by a data acquisition system. In addition, a video was recorded by a high-speed video camera for visualization of the boiling phenomenon. The surface heat flux was calculated using a 1-D inverse heat conduction code at each location.
It has been found that the MHF and CHF were significantly influenced by the degree of subcooling. However, the MHF and CHF values were almost independent of initial rod temperature and surface condition. The calculated surface heat flux based on each thermocouple location was found to be consistent during the film boiling regime. The inconsistency in the evaluated surface heat fluxes at both locations begins after the MHF point and reaches a maximum near the CHF. After the CHF point, the inconsistency decays dramatically. The inconsistency in CHF values could be related to the axial conduction effect due to the large temperature gradient above and below the quench front.
Advisors/Committee Members: Bill%20B%20Cheung%2C%20Thesis%20Advisor%2FCo-
Advisor%22%29&pagesize-30">
Fan-
Bill B Cheung,
Thesis Advisor/
Co-
Advisor.
Subjects/Keywords: Pool boiling; Heat transfer; Quenching; critical heat flux
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APA (6th Edition):
Almudhhi, T. K. (2017). EXPERIMENTAL STUDY OF HEAT TRANSFER DURING QUENCHING OF A HEATED ROD. (Thesis). Penn State University. Retrieved from https://submit-etda.libraries.psu.edu/catalog/14854tka5098
Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation
Chicago Manual of Style (16th Edition):
Almudhhi, Turki Khalid. “EXPERIMENTAL STUDY OF HEAT TRANSFER DURING QUENCHING OF A HEATED ROD.” 2017. Thesis, Penn State University. Accessed March 03, 2021.
https://submit-etda.libraries.psu.edu/catalog/14854tka5098.
Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation
MLA Handbook (7th Edition):
Almudhhi, Turki Khalid. “EXPERIMENTAL STUDY OF HEAT TRANSFER DURING QUENCHING OF A HEATED ROD.” 2017. Web. 03 Mar 2021.
Vancouver:
Almudhhi TK. EXPERIMENTAL STUDY OF HEAT TRANSFER DURING QUENCHING OF A HEATED ROD. [Internet] [Thesis]. Penn State University; 2017. [cited 2021 Mar 03].
Available from: https://submit-etda.libraries.psu.edu/catalog/14854tka5098.
Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation
Council of Science Editors:
Almudhhi TK. EXPERIMENTAL STUDY OF HEAT TRANSFER DURING QUENCHING OF A HEATED ROD. [Thesis]. Penn State University; 2017. Available from: https://submit-etda.libraries.psu.edu/catalog/14854tka5098
Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation
Penn State University
4.
Riley, Michael Patrick.
Development of a Correlation for Nucleate Boiling Heat Flux on a Hemispherical Downward Facing Surface.
Degree: 2012, Penn State University
URL: https://submit-etda.libraries.psu.edu/catalog/14213
► A new physics-based heat transfer correlation has been developed that can be used to predict the local variation of the nucleate boiling heat flux on…
(more)
▼ A new physics-based heat transfer correlation has been developed that can be used to predict the local variation of the nucleate boiling heat flux on a downward facing heating surface. It is widely known that the heat transfer mechanism of nucleate boiling involves the growth and departure of vapor bubbles on a heated surface. When the vapor bubbles have grown to their mature size, they depart from the heating surface, agitating the surrounding fluid. This bubble agitation results in strong turbulent mixing of the fluid. For the case of an upward facing surface, the nucleate boiling heat flux has been determined using the single-phase turbulent heat transfer correlation. The correlation relates the Nusselt number to the Reynolds number and Prandtl number. Through the use of proper velocity and length scales, Rohsenow (1952) developed a correlation to predict the nucleate boiling heat flux on an upward facing surface. The resulting correlation relates the nucleate boiling heat flux to the wall superheat and fluid properties and a correlation coefficient.
For the case of downward facing boiling on a hemispherical surface, however, the Rohsenow correlation cannot be applied. Due to the surface orientation, buoyancy effects have a significant impact on the behavior of the flow and heat transfer. The heating surface causes the fluid in close proximity to increase in temperature, lowering the density of the fluid. When the liquid begins to vaporize, the density of the resulting vapor is several orders of magnitude less than the surrounding liquid, resulting in strong buoyancy forces that entrain the liquid upward. The downward facing surface hinders this upward motion of vapor bubbles, causing them to have to take an alternative upward route. If the surface is inclined, the bubbles will flow along the heating surface which develops into a two-phase boundary layer flow. When the surface is completely horizontally downward facing, the bubbles cannot flow along the surface, forming a vapor blanket from which bubbles shear off.
The Rohsenow correlation relates the nucleate boiling heat flux to only wall superheat and fluid properties. Local variation does not appear in the correlation because the nucleate boiling heat flux conditions are equivalent at all locations of an upward facing surface. On a downward facing hemispherical surface, however, local variation plays a significant role in the nucleate boiling heat flux. At the bottom of the hemispherical surface, the buoyancy force presses the vapor bubbles against the surface. As the local coordinate along the surface is increased, the buoyancy forces have an increasing impact on the flow characteristics and, thus, the heat flux.
The present study has successfully captured the local buoyancy effects and local variation of the nucleate boiling heat flux on a downward facing surface. The correlation predicts the nucleate boiling heat flux based on the wall superheat, fluid properties, and, most importantly, local variation along the heating surface. Similar…
Advisors/Committee Members: Advisor%22%29&pagesize-30">
Fan Bill B Cheung,
Thesis Advisor/
Co-
Advisor.
Subjects/Keywords: Nucleate Boiling; Critical Heat Flux; Pool Boiling; Heat Transfer; Buoyancy Driven Flow; Buoyancy Driven Heat Transfer
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Manager
APA (6th Edition):
Riley, M. P. (2012). Development of a Correlation for Nucleate Boiling Heat Flux on a Hemispherical Downward Facing Surface. (Thesis). Penn State University. Retrieved from https://submit-etda.libraries.psu.edu/catalog/14213
Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation
Chicago Manual of Style (16th Edition):
Riley, Michael Patrick. “Development of a Correlation for Nucleate Boiling Heat Flux on a Hemispherical Downward Facing Surface.” 2012. Thesis, Penn State University. Accessed March 03, 2021.
https://submit-etda.libraries.psu.edu/catalog/14213.
Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation
MLA Handbook (7th Edition):
Riley, Michael Patrick. “Development of a Correlation for Nucleate Boiling Heat Flux on a Hemispherical Downward Facing Surface.” 2012. Web. 03 Mar 2021.
Vancouver:
Riley MP. Development of a Correlation for Nucleate Boiling Heat Flux on a Hemispherical Downward Facing Surface. [Internet] [Thesis]. Penn State University; 2012. [cited 2021 Mar 03].
Available from: https://submit-etda.libraries.psu.edu/catalog/14213.
Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation
Council of Science Editors:
Riley MP. Development of a Correlation for Nucleate Boiling Heat Flux on a Hemispherical Downward Facing Surface. [Thesis]. Penn State University; 2012. Available from: https://submit-etda.libraries.psu.edu/catalog/14213
Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation
Penn State University
5.
Gorman, Nicolas Stephen.
Experimental Study of Downward Facing Boiling under IVR-ERVC Conditions.
Degree: 2014, Penn State University
URL: https://submit-etda.libraries.psu.edu/catalog/21833
► New correlations are developed to more completely capture the physics of downward facing boiling, especially under nuclear accident conditions requiring In Vessel Retention External Reactor…
(more)
▼ New correlations are developed to more completely capture the physics of downward
facing boiling, especially under nuclear accident conditions requiring In Vessel
Retention External Reactor Pressure Vessel Cooling (IVR-ERVC) strategies. Extending
the length scale correlations used by Rohsenow to derive the heat
ux from a
at
plate (Reference [16]), a correlation based on bubble size at detachment is obtained for
downward facing boiling. To validate this correlation, downward facing boiling data was
obtained in the Subscale Boundary Layer Boiling(SBLB) facility, which was refurbished
and out�tted with a new data acquisition system.
In addition to correlating the heat
ux to the wall superheat, video was taken of
downward facing boiling so that the volumetric
ow rate and the
ow area may be better
understood and observed. In particular, IVR-ERVC strategies require that adequate
steam venting be provided. Because the speed of sound is so slow in saturated water, it
is possible that for some designs of reactor pressure vessels (RPVs) and their insulation
structures, the entrained
ow of steam will become choked. If the
ow becomes choked,
then it will prevent the liquid water from reaching the surface of the RPV, and ERVC
will fail. The size and frequency of bubble formation is recorded, and a lower bound on
the minimum allowable
ow area for an insulation structure is established. The validity
of the bubble size correlation is established by using it to back-predict the heat
ux.
Measurements are made of the wall superheat at various locations on the RPV
surface, as well. From these measurements and the extension of the Rohsenow correlation,
it was possible to predict the heat
ux as a function of location on the RPV and
surface temperature. By performing downward facing boiling experiments with di�ering
levels of subcooling, it was possible to predict the e�ect of subcooling on surface
temperature, with known heat
ux and position. The validity of these correlations is
established by using them to accurately predict the superheat at di�erent locations for
downward facing boiling using both saturated and subcooled liquid.
Advisors/Committee Members: Advisor%22%29&pagesize-30">
Fan Bill B Cheung,
Thesis Advisor/
Co-
Advisor,
Advisor%22%29&pagesize-30">Gita Talmage, Thesis Advisor/Co-Advisor.
Subjects/Keywords: IVR; ERVC; Boiling; Two-phase; heat transfer; nucleate boiling
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APA (6th Edition):
Gorman, N. S. (2014). Experimental Study of Downward Facing Boiling under IVR-ERVC Conditions. (Thesis). Penn State University. Retrieved from https://submit-etda.libraries.psu.edu/catalog/21833
Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation
Chicago Manual of Style (16th Edition):
Gorman, Nicolas Stephen. “Experimental Study of Downward Facing Boiling under IVR-ERVC Conditions.” 2014. Thesis, Penn State University. Accessed March 03, 2021.
https://submit-etda.libraries.psu.edu/catalog/21833.
Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation
MLA Handbook (7th Edition):
Gorman, Nicolas Stephen. “Experimental Study of Downward Facing Boiling under IVR-ERVC Conditions.” 2014. Web. 03 Mar 2021.
Vancouver:
Gorman NS. Experimental Study of Downward Facing Boiling under IVR-ERVC Conditions. [Internet] [Thesis]. Penn State University; 2014. [cited 2021 Mar 03].
Available from: https://submit-etda.libraries.psu.edu/catalog/21833.
Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation
Council of Science Editors:
Gorman NS. Experimental Study of Downward Facing Boiling under IVR-ERVC Conditions. [Thesis]. Penn State University; 2014. Available from: https://submit-etda.libraries.psu.edu/catalog/21833
Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation
Penn State University
6.
Fudurich, Valerie Diane.
Effect of Liquid Subcooling, Initial Surface Temperature, and Surface Properties on the Minimum Film Boiling Temperature.
Degree: 2016, Penn State University
URL: https://submit-etda.libraries.psu.edu/catalog/29148
► An experimental test facility has been designed and constructed with the purpose of performing high-temperature pool boiling experiments for vertical cylinder geometry. The heat transfer…
(more)
▼ An experimental test facility has been designed and constructed with the purpose of performing high-temperature pool boiling experiments for vertical cylinder geometry. The heat transfer regime of interest is high temperature film boiling and the transition point at the minimum film boiling temperature, Tmin. The large superheat temperature and heat flux are able to sustain a vapor blanket that prevents the bulk liquid from direct physical contact with the heated surface. Experiments focused on varying the initial rod temperature, liquid subcooling, and surface conditions through oxidation to study their influence on Tmin and the boiling curve. These initial conditions were varied for two series of quenching experiments. The first varied the rod and bath temperatures and the second held these temperatures constant for sequential tests to build an oxide layer. A stainless steel cylindrical rod fitted with embedded thermocouples was heated to a temperature well in the film boiling regime and quickly inserted in an otherwise quiescent pool of distilled water. The superheated surface is quenched when the liquid comes into contact after the collapse of the vapor film. The embedded thermocouples were connected to a data acquisition system to record temperature-time traces. Additionally, video was recorded during the quenching process for visualization of the vapor film. Quenching curves were used to calculate the heat flux and construct the boiling curve. The minimum film boiling temperature was calculated by finding the minimum heat flux associated with Tmin. Data reduction was performed by using an inverse heat conduction code (DATARH) to calculate surface temperature and heat flux. It was found that, similar to the majority of previous research, the liquid subcooling strongly influences the minimum film boiling temperature. In addition, the vapor film thickness and the behavior of the liquid-vapor boundary layer is closely linked to the liquid subcooling. The initial surface temperature had little effect on Tmin compared to the large effect of liquid subcooling. The duration of the entire quench process however, was extended when the initial surface temperature was increased. A second series of tests to investigate the effects of oxidation were also undertaken. When several tests were completed in succession without restoring the rod surface to bare conditions, Tmin changed subtly after the first oxidized test. The effect did not become more pronounced with subsequent tests. However when the rods were given multiple hours to oxidize, Tmin did not stay constant. This suggests that although stainless steel is resistant to changes to the oxide layer during short term heat cycles, extended heat influences the oxide layer.
The current findings were used to observe the effectiveness of a correlation produced by Peterson and Bajorek. As the surface conditions of the oxidized rod were unable to be quantified, the basic form of the correlation was used. Most experimental data was predicted within ±10% by the correlation.
Advisors/Committee Members: Advisor%22%29&pagesize-30">
Fan Bill B Cheung,
Thesis Advisor/
Co-
Advisor,
Advisor%22%29&pagesize-30">Justin Kyle Watson, Thesis Advisor/Co-Advisor,
Advisor%22%29&pagesize-30">Arthur Thompson Motta, Thesis Advisor/Co-Advisor.
Subjects/Keywords: Minimum Film Boiling Temperature; Film Boiling; Quench; Pool Boiling Experiments
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Manager
APA (6th Edition):
Fudurich, V. D. (2016). Effect of Liquid Subcooling, Initial Surface Temperature, and Surface Properties on the Minimum Film Boiling Temperature. (Thesis). Penn State University. Retrieved from https://submit-etda.libraries.psu.edu/catalog/29148
Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation
Chicago Manual of Style (16th Edition):
Fudurich, Valerie Diane. “Effect of Liquid Subcooling, Initial Surface Temperature, and Surface Properties on the Minimum Film Boiling Temperature.” 2016. Thesis, Penn State University. Accessed March 03, 2021.
https://submit-etda.libraries.psu.edu/catalog/29148.
Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation
MLA Handbook (7th Edition):
Fudurich, Valerie Diane. “Effect of Liquid Subcooling, Initial Surface Temperature, and Surface Properties on the Minimum Film Boiling Temperature.” 2016. Web. 03 Mar 2021.
Vancouver:
Fudurich VD. Effect of Liquid Subcooling, Initial Surface Temperature, and Surface Properties on the Minimum Film Boiling Temperature. [Internet] [Thesis]. Penn State University; 2016. [cited 2021 Mar 03].
Available from: https://submit-etda.libraries.psu.edu/catalog/29148.
Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation
Council of Science Editors:
Fudurich VD. Effect of Liquid Subcooling, Initial Surface Temperature, and Surface Properties on the Minimum Film Boiling Temperature. [Thesis]. Penn State University; 2016. Available from: https://submit-etda.libraries.psu.edu/catalog/29148
Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation
Penn State University
7.
Goverapet Srinivasan, Sriram.
DEVELOPMENT OF A WET GRID MODEL FOR
TWO – PHASE DISPERSED FLOW FILM BOILING PHENOMENA
.
Degree: 2010, Penn State University
URL: https://submit-etda.libraries.psu.edu/catalog/11495
► The present study focuses on the development of a Wet Grid Model to describe the wet grid phenomenon observed during the reflood stage of a…
(more)
▼ The present study focuses on the development of a Wet Grid Model to describe the wet grid phenomenon observed during the reflood stage of a postulated Loss of Coolant Accident (LOCA) in a nuclear reactor. At high flooding rates, it has been observed that the spacer grids at elevations above the quench front undergo rewetting much earlier than the fuel rod. A consequence of this is the establishment of a liquid film on the surface of the spacer grid. Liquid droplet sizes found downstream of a wet grid are larger than those found upstream of the grid indicating a distinctly different mechanism of droplet generation as compared to a dry grid scenario for which the droplets decrease in size as they pass through the grid. In this study, a possible mechanism is postulated and a mathematical model is derived for the same.
The wet grid phenomenon is postulated to be consisting of four individual processes. Firstly, the deposition of droplets from the dispersed two phase mixture onto the spacer grid surface, then the establishment of a liquid film of equilibrium thickness on the surface of the spacer strap, thirdly, the entrainment of liquid ligaments from the liquid film due to the shear action of the steam flow and finally the breakup of these ligaments into a number of fine droplets downstream of the grid. A mathematical model is formulated for each of these processes which can be used to predict the droplet diameter downstream of a wet grid, given the flow and system conditions upstream of the grid. In addition, a numerical based correlation is proposed to obtain the downstream to upstream ratio of the sauter mean diameter of droplets in a wet grid situation.
The flow of superheated steam through the span of a wet spacer grid results in a significant de – superheating and acceleration of the steam due to the evaporation of the liquid film on the surface of the wet spacer grid. The simultaneous effect of steam de – superheating and acceleration greatly enhances the heat transfer rate from the surface of the nuclear fuel rod, downstream of a wet grid. A mechanistic model is proposed to determine the Grid Enhanced Heat Transfer (GEHT) downstream of a wet grid. The numerical solution to the model equations shows that over a void fraction range of 0.99 to 0.999, the equilibrium film thickness varies between 0.12 and 0.1 mm while the average liquid film velocity varies between 0.7 and 0.1 m/s. The downstream to upstream ratio of the sauter mean diameter of the droplets was found to vary between 2.75 and 0.8. A reduction of around 100 deg. C in the steam temperature was obtained as it flows through the span of the wet spacer spacer grid. A wet grid was found to be more effective in augmenting heat transfer than a dry grid under the same flow conditions. This augmentation was found to be as much as three times higher for void fractions very close to unity. Results obtained from the models, however, are still parametric in nature since no experimental data under wet grid like conditions is available in the literature…
Advisors/Committee Members: Advisor%22%29&pagesize-30">
Fan Bill B Cheung,
Thesis Advisor/
Co-
Advisor,
Advisor%22%29&pagesize-30">Fan Bill B Cheung, Thesis Advisor/Co-Advisor.
Subjects/Keywords: LOCA; Wet Grid Phenomena; Dispersed flow; Grid Enhanced Heat Transfer
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APA (6th Edition):
Goverapet Srinivasan, S. (2010). DEVELOPMENT OF A WET GRID MODEL FOR
TWO – PHASE DISPERSED FLOW FILM BOILING PHENOMENA
. (Thesis). Penn State University. Retrieved from https://submit-etda.libraries.psu.edu/catalog/11495
Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation
Chicago Manual of Style (16th Edition):
Goverapet Srinivasan, Sriram. “DEVELOPMENT OF A WET GRID MODEL FOR
TWO – PHASE DISPERSED FLOW FILM BOILING PHENOMENA
.” 2010. Thesis, Penn State University. Accessed March 03, 2021.
https://submit-etda.libraries.psu.edu/catalog/11495.
Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation
MLA Handbook (7th Edition):
Goverapet Srinivasan, Sriram. “DEVELOPMENT OF A WET GRID MODEL FOR
TWO – PHASE DISPERSED FLOW FILM BOILING PHENOMENA
.” 2010. Web. 03 Mar 2021.
Vancouver:
Goverapet Srinivasan S. DEVELOPMENT OF A WET GRID MODEL FOR
TWO – PHASE DISPERSED FLOW FILM BOILING PHENOMENA
. [Internet] [Thesis]. Penn State University; 2010. [cited 2021 Mar 03].
Available from: https://submit-etda.libraries.psu.edu/catalog/11495.
Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation
Council of Science Editors:
Goverapet Srinivasan S. DEVELOPMENT OF A WET GRID MODEL FOR
TWO – PHASE DISPERSED FLOW FILM BOILING PHENOMENA
. [Thesis]. Penn State University; 2010. Available from: https://submit-etda.libraries.psu.edu/catalog/11495
Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation
Penn State University
8.
Kern, Ludwig August.
FLUENT CFD MODELING IN DESIGN OF SPENT NUCLEAR FUEL DRY STORAGE CASK.
Degree: 2009, Penn State University
URL: https://submit-etda.libraries.psu.edu/catalog/9685
► A FLUENT Computational Fluid Dynamics (CFD) model of a spent nuclear fuel dry storage cask was created to predict several critical design temperatures in order…
(more)
▼ A FLUENT Computational Fluid Dynamics (CFD) model of a spent nuclear fuel dry storage cask was created to predict several critical design temperatures in order to aid in the design of a dry storage cask. Thermal tests were conducted to determine the ability of the FLUENT CFD code to accurately predict solid structure and fluid temperatures in simple and complex flow geometries. The thermal tests included natural convective flow in a single heated annular tube and realistic heating of a full-scale prototype dry storage cask using heating configurations which bounded the heat source distributions of all possible fuel loading patterns. The FLUENT CFD model of the prototype dry storage cask was successful in demonstrating reasonable accuracy (20% agreement) in predicting the majority of temperatures measured during the thermal tests. The model showed even better accuracy in predicting the hottest rod temperature, the hottest temperature within the cask, which is a critical design temperature, and conservatively bounded all rod temperatures if allowance is given for the measurement uncertainties in the experimental data. However, there was no validation during this set of thermal experiments of the FLUENT CFD model’s ability to accurately model heat transfer between adjacent rods in individual fuel assemblies, which will be necessary before the model is ready for use as part of the thermal design basis for spent nuclear fuel dry storage cask design. A general discussion of computational methods, modeling methodology, FLUENT and other CFD codes, spent nuclear fuel storage, the design of nuclear fuel dry storage casks, and the heat transfer mechanisms modeled for the dry storage cask is also included in addition to the information specific to the dry storage cask FLUENT CFD model and the model validation experiments conducted with the full-scale prototype cask.
Advisors/Committee Members: Advisor%22%29&pagesize-30">
Fan Bill B Cheung,
Thesis Advisor/
Co-
Advisor,
Advisor%22%29&pagesize-30">Fan Bill B Cheung, Thesis Advisor/Co-Advisor,
Advisor%22%29&pagesize-30">John Michael Cimbala, Thesis Advisor/Co-Advisor.
Subjects/Keywords: Fluent; fluent modeling; cfd; cfd modeling; fluent model; cfd model; computational fluid dynamics; nuclear; nuclear engineering; dry storage; dry storage cask; spent fuel; spent nuclear fuel; nuclear fuel; rbmk; chernobyl; holtec; thermal; heat transfer; natural convection; convection; natural convective flow; annular; prototype; full-scale; validation; cfd code; navier-stokes; navier-stokes equation
Record Details
Similar Records
Cite
Share »
Record Details
Similar Records
Cite
« Share
❌
APA ·
Chicago ·
MLA ·
Vancouver ·
CSE |
Export
to Zotero / EndNote / Reference
Manager
APA (6th Edition):
Kern, L. A. (2009). FLUENT CFD MODELING IN DESIGN OF SPENT NUCLEAR FUEL DRY STORAGE CASK. (Thesis). Penn State University. Retrieved from https://submit-etda.libraries.psu.edu/catalog/9685
Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation
Chicago Manual of Style (16th Edition):
Kern, Ludwig August. “FLUENT CFD MODELING IN DESIGN OF SPENT NUCLEAR FUEL DRY STORAGE CASK.” 2009. Thesis, Penn State University. Accessed March 03, 2021.
https://submit-etda.libraries.psu.edu/catalog/9685.
Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation
MLA Handbook (7th Edition):
Kern, Ludwig August. “FLUENT CFD MODELING IN DESIGN OF SPENT NUCLEAR FUEL DRY STORAGE CASK.” 2009. Web. 03 Mar 2021.
Vancouver:
Kern LA. FLUENT CFD MODELING IN DESIGN OF SPENT NUCLEAR FUEL DRY STORAGE CASK. [Internet] [Thesis]. Penn State University; 2009. [cited 2021 Mar 03].
Available from: https://submit-etda.libraries.psu.edu/catalog/9685.
Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation
Council of Science Editors:
Kern LA. FLUENT CFD MODELING IN DESIGN OF SPENT NUCLEAR FUEL DRY STORAGE CASK. [Thesis]. Penn State University; 2009. Available from: https://submit-etda.libraries.psu.edu/catalog/9685
Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation
. 
Open Access Theses and Dissertations