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Thematische Bibliographien / Nuclear boiling / Dissertationen

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Dissertationen zum Thema „Nuclear boiling“

Autor: Grafiati

Veröffentlicht am 14. Dezember 2024

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1

Doney, George Daniel. "Acoustic boiling detection." Thesis, Massachusetts Institute of Technology, 1994. http://hdl.handle.net/1721.1/28110.

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2

Aziz, S. "Forced convection film boiling on spheres." Thesis, University of Oxford, 1986. http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.371536.

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3

Samaroo, Randy. "The effects of geometric, flow, and boiling parameters on bubble growth and behavior in subcooled flow boiling." Thesis, The City College of New York, 2016. http://pqdtopen.proquest.com/#viewpdf?dispub=10159915.

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<p> Air bubble injection and subcooled flow boiling experiments have been performed to investigate the liquid flow field and bubble nucleation, growth, and departure, in part to contribute to the DOE Nuclear HUB project, Consortium for Advanced Simulation of Light Water Reactors (CASL). The main objective was to obtain quantitative data and compartmentalize the many different interconnected aspects of the boiling process — from the channel geometry, to liquid and gas interactions, to underlying heat transfer mechanisms. </p><p> The air bubble injection experiments were performed in ann

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4

Zeng, Yi. "Effect of peripheral wall conduction in pool boiling." Thesis, University of Ottawa (Canada), 1985. http://hdl.handle.net/10393/22397.

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5

Gao, Qi. "A boiling water reactor simulator for stability analysis." Thesis, Massachusetts Institute of Technology, 1996. http://hdl.handle.net/1721.1/39053.

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6

Lange, Carsten. "Advanced nonlinear stability analysis of boiling water nuclear reactors." Doctoral thesis, Saechsische Landesbibliothek- Staats- und Universitaetsbibliothek Dresden, 2009. http://nbn-resolving.de/urn:nbn:de:bsz:14-qucosa-24954.

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This thesis is concerned with nonlinear analyses of BWR stability behaviour, contributing to a deeper understanding in this field. Despite negative feedback-coefficients of a BWR, there are operational points (OP) at which oscillatory instabilities occur. So far, a comprehensive and an in-depth understanding of the nonlinear BWR stability behaviour are missing, even though the impact of the significant physical parameters is well known. In particular, this concerns parameter regions in which linear stability indicators, like the asymptotic decay ratio, lose their meaning. Nonlinear stability a

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7

Chen, Xiangbin. "Direct numerical simulation of nuclear boiling on nanopatterned surface." Electronic Thesis or Diss., Sorbonne université, 2024. https://accesdistant.sorbonne-universite.fr/login?url=https://theses-intra.sorbonne-universite.fr/2024SORUS289.pdf.

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Les dynamiques de l'ébullition nucléée sont intimement influencées par les interactions entre les domaines fluide et solide, en particulier dans des conditions de petits angles de contact et de phénomènes d'interface complexes. Cette thèse présente le développement et l'application de méthodes numériques avancées pour simuler ces interactions avec une précision accrue. Au cœur de ce travail se trouve la mise en œuvre d'une méthode de convection Volume de Fluide (VOF) conservatrice de masse, intégrée de manière fluide avec une approche de domaine solide intégré. Cette technique est spécifiqueme

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Breen, R. J. "PWR safety studies : nucleate boiling heat transfer." Thesis, University of Oxford, 1988. http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.236258.

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9

Kim, Sung Joong Ph D. Massachusetts Institute of Technology. "Pool boiling heat transfer characteristics of nanofluids." Thesis, Massachusetts Institute of Technology, 2007. http://hdl.handle.net/1721.1/41306.

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Thesis (S.M.)--Massachusetts Institute of Technology, Dept. of Nuclear Science and Engineering, 2007.<br>Includes bibliographical references (leaves 79-83).<br>Nanofluids are engineered colloidal suspensions of nanoparticles in water, and exhibit a very significant enhancement (up to 200%) of the boiling Critical Heat Flux (CHF) at modest nanoparticle concentrations (50.1% by volume). Since CHF is the upper limit of nucleate boiling, such enhancement offers the potential for major performance improvement in many practical applications that use nucleate boiling as their prevalent heat transfer

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10

Mason, VerrDon Holbrook. "Chemical characterization of simulated boiling water reactor coolant." Thesis, Massachusetts Institute of Technology, 1990. http://hdl.handle.net/10945/28026.

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11

Burns, Chad (Chad D. ). III. "Optimization algorithms in boiling water reactor lattice design." Thesis, Massachusetts Institute of Technology, 2013. http://hdl.handle.net/1721.1/82443.

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Thesis (S.B.)--Massachusetts Institute of Technology, Dept. of Nuclear Science and Engineering, 2013.<br>"June 2013." Cataloged from PDF version of thesis.<br>Includes bibliographical references (pages 32-33).<br>Given the highly complex nature of neutronics and reactor physics, efficient methods of optimizing are necessary to effectively design the core reloading pattern and operate a nuclear reactor. The current popular methods for optimization are Simulated Annealing and the Genetic Algorithm; this paper explores the potential for a new method called Greedy Exhaustive Dual Binary Swaps (GED

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12

Uhle, Jennifer Lee. "Boiling heat transfer characteristics of steam generator U-tube fouling." Thesis, Massachusetts Institute of Technology, 1997. http://hdl.handle.net/1721.1/17499.

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Thesis (Ph.D.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1997.<br>Includes bibliographical references (leaves 109-111).<br>The boiling heat transfer characteristics of steam generator u-tube fouling deposits were identified by developing a boiling heat transfer model and determining its accuracy through the comparison of calculated and experimental results. Magnetite deposits were fabricated in the laboratory and were characterized using a variety of techniques. Heat transfer measurements were then taken, so that the effect of deposit parameters, including pore size

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Truong, Bao H. (Bao Hoai). "Effects of surface parameters on boiling heat transfer phenomena." Thesis, Massachusetts Institute of Technology, 2011. http://hdl.handle.net/1721.1/76925.

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Thesis (Ph. D.)--Massachusetts Institute of Technology, Dept. of Nuclear Science and Engineering, 2011.<br>Cataloged from PDF version of thesis.<br>Includes bibliographical references (p. 148-156).<br>Nanofluids, engineered colloidal dispersions of nanoparticles in fluid, have been shown to enhance pool and flow boiling CHF. The CHF enhancement was due to nanoparticle deposited on the heater surface, which was verified in pool boiling. However, no such work has been done for flow boiling. Using a cylindrical tube pre-coated with Alumina nanoparticles coated via boiling induced deposition, CHF

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Kossolapov, Artyom. "Transient flow boiling CHF under exponentially escalating heat inputs." Thesis, Massachusetts Institute of Technology, 2018. http://hdl.handle.net/1721.1/119047.

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Thesis: S.M., Massachusetts Institute of Technology, Department of Nuclear Science and Engineering, 2018.<br>This electronic version was submitted by the student author. The certified thesis is available in the Institute Archives and Special Collections.<br>Cataloged from student-submitted PDF version of thesis.<br>Includes bibliographical references (pages 41-42).<br>Reactivity initiated accidents (RIAs) are a potential concern for nuclear reactor safety. In RIA scenarios, following the insertion of positive reactivity, e.g. by an unanticipated extraction of the control rods, the reactor pow

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Grover, David J. (David Joseph). "Modeling water chemistry and electrochemical corrosion potential in boiling water reactors." Thesis, Massachusetts Institute of Technology, 1997. http://hdl.handle.net/1721.1/39772.

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O'Hanley, Harrison Fagan. "Separate effects of surface roughness, wettability and porosity on boiling heat transfer and critical heat flux and optimization of boiling surfaces." Thesis, Massachusetts Institute of Technology, 2012. http://hdl.handle.net/1721.1/78208.

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Thesis (S.M.)--Massachusetts Institute of Technology, Dept. of Nuclear Science and Engineering; and, (S.B.)--Massachusetts Institute of Technology, Dept. of Mechanical Engineering, 2012.<br>Cataloged from PDF version of thesis.<br>Includes bibliographical references (p. 157-161).<br>The separate effects of surface wettability, porosity, and roughness on critical heat flux (CHF) and heat transfer coefficient (HTC) were examined using carefully-engineered surfaces. All test surfaces were prepared on nanosmooth indium tin oxide - sapphire heaters and tested in a pool boiling facility in MIT's Rea

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Fridström, Richard. "Response of the Gamma TIP Detectorsin a Nuclear Boiling Water Reactor." Thesis, Uppsala University, Applied Nuclear Physics, 2010. http://urn.kb.se/resolve?urn=urn:nbn:se:uu:diva-126969.

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<p>In order to monitor a nuclear boiling water reactor fixed and movable detectors are used, such as the neutron sensitive LPRM (Local Power Range Monitors) detectors and the gamma sensitive TIP (Traversing Incore Probe) detectors. These provide a mean to verify the predictions obtained from core simulators, which are used for planning and following up the reactor operation. The core simulators calculate e.g. the neutron flux and power distribution in the reactor core. The simulators can also simulate the response in the LPRM and TIP detectors. By comparing with measurements the accuracy of th

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Ko, Yu-Chih Ph D. Massachusetts Institute of Technology. "Conceptual design of an annular-fueled superheat boiling water reactor." Thesis, Massachusetts Institute of Technology, 2010. http://hdl.handle.net/1721.1/76976.

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Thesis (Ph. D.)--Massachusetts Institute of Technology, Dept. of Nuclear Science and Engineering, February 2011.<br>"September 2010." Cataloged from PDF version of thesis.<br>Includes bibliographical references (p. 219-225).<br>The conceptual design of an annular-fueled superheat boiling water reactor (ASBWR) is outlined. The proposed design, ASBWR, combines the boiler and superheater regions into one fuel assembly. This ensures good neutron moderation throughout the reactor core. A single fuel design is used in the core. Each annular fuel element, or fuel tube, is cooled externally by boiling

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Truong, Bao H. (Bao Hoai). "Determination of pool boiling Critical Heat Flux enhancement in nanofluids." Thesis, Massachusetts Institute of Technology, 2007. http://hdl.handle.net/1721.1/41689.

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Thesis (S.B.)--Massachusetts Institute of Technology, Dept. of Nuclear Science and Engineering, June 2007.<br>"May 2007."<br>Includes bibliographical references (leaves 51-53).<br>Nanofluids are engineered colloids composed of nano-size particles dispersed in common fluids such as water or refrigerants. Using an electrically controlled wire heater, pool boiling Critical Heat Flux (CHF) of Alumina and Silica water-based nanofluids of concentration less than or equal to 0.1 percent by volume were measured. Silica nanofluids showed CHF enhancement up to 68% and there seems to be a monotonic relat

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Mowrey, James A. "Control system modeling for a boiling water reactor." Thesis, Georgia Institute of Technology, 1995. http://hdl.handle.net/1853/17083.

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Maurer, John H. (John Howard). "Surveillance strategy for a four year operating cycle in commercial boiling water reactors." Thesis, Massachusetts Institute of Technology, 1996. http://hdl.handle.net/1721.1/39051.

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Correll, Sam. "Flow film boiling on levitated molten drops and vapour explosion triggering." Thesis, University of Oxford, 1989. http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.352915.

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23

Richenderfer, Andrew Jonathan. "Experimental study of heat flux partitioning in pressurized subcooled flow boiling." Thesis, Massachusetts Institute of Technology, 2018. http://hdl.handle.net/1721.1/119033.

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Thesis: Ph. D., Massachusetts Institute of Technology, Department of Nuclear Science and Engineering, 2018.<br>This electronic version was submitted by the student author. The certified thesis is available in the Institute Archives and Special Collections.<br>Cataloged from student-submitted PDF version of thesis.<br>Includes bibliographical references (pages 133-137).<br>Understanding of subcooled flow boiling and the critical heat flux (CHF) is of the utmost importance for both safety and profitability of pressurized water nuclear reactors since they are major factors in the determination o

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Lenci, Giancarlo. "Prediction of departure from nucleate boiling in PWR fast power transients." Thesis, Massachusetts Institute of Technology, 2013. http://hdl.handle.net/1721.1/80659.

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Thesis (S.M.)--Massachusetts Institute of Technology, Dept. of Nuclear Science and Engineering, 2013.<br>Cataloged from PDF version of thesis.<br>Includes bibliographical references (p. 89-91).<br>An assessment is conducted of the differences in predicted results between use of steady state versus transient Departure from Nucleate Boiling (DNB) models, for fast power transients under forced convective heat exchange conditions. Theoretical DNB models based on liquid film thickness variation are adapted and modified from existing studies into a generalized formulation to allow implementation int

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Hu, Rui Ph D. Massachusetts Institute of Technology. "Stability analysis of the boiling water reactor : methods and advanced designs." Thesis, Massachusetts Institute of Technology, 2010. http://hdl.handle.net/1721.1/62693.

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Thesis (Ph. D.)--Massachusetts Institute of Technology, Dept. of Nuclear Science and Engineering, 2010.<br>Cataloged from PDF version of thesis.<br>Includes bibliographical references (p. 278-285).<br>Density Wave Oscillations (DWOs) are known to be possible when a coolant undergoes considerable density reduction while passing through a heated channel. In the development of boiling water reactors (BWRs), there has been considerable concern about the effects of such oscillations when coupled with neutronic feedback. The current trend of increasing reactor power density and relying more extensiv

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Caraghiaur, Diana. "On drops and turbulence in nuclear fuel assemblies of Boiling Water Reactors." Doctoral thesis, KTH, Reaktorteknologi, 2012. http://urn.kb.se/resolve?urn=urn:nbn:se:kth:diva-107115.

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The study aims to develop the understanding of the mechanistic-type approach to quantify drop deposition in nuclear fuel assemblies of Boiling Water Reactors. This includes the effect of spacers. Spacers have a complex geometry to serve their purposes, but optimization of them alone can improve the thermal limit parameters in nuclear fuel assemblies. Thus, a mechanistic model might prove useful to increase the safety of the reactor as well as economic competitiveness of the nuclear power plant. In this thesis, measurement techniques, such as mobile pressure rod and Laser Doppler Velocimetry ar

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BOADU, HERBERT ODAME. "CONTINUOUS-TIME OPTIMAL CONTROL OF A SIMULATED BOILING WATER NUCLEAR (BWR) POWER PLANT." Diss., The University of Arizona, 1985. http://hdl.handle.net/10150/188087.

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A suboptimal controller has been developed for a Boiling Water Reactor Nuclear Power Plant, using the DARE P Continuous Simulation Language, which was developed in the Electrical Engineering Department at the University of Arizona. A set of 48 nonlinear first-order differential equations and a large number of algebraic equations has been linearized about the equilibrium state. Using partitioning, the linearized equations were transformed into a block triangular form. The concept of optimal control and a square performance index reflecting the desired plant behavior have been applied on the slo

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Coyle, Carolyn Patricia. "Synthesis of CRUD and its effects on pool and subcooled flow boiling." Thesis, Massachusetts Institute of Technology, 2016. http://hdl.handle.net/1721.1/103652.

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Thesis: S.M., Massachusetts Institute of Technology, Department of Nuclear Science and Engineering, 2016.<br>This electronic version was submitted by the student author. The certified thesis is available in the Institute Archives and Special Collections.<br>Cataloged from student-submitted PDF version of thesis.<br>Includes bibliographical references (pages 127-132).<br>This work is dedicated to studying the effects of synthetic CRUD (Chalk River Unidentified Deposits) on pool and subcooled flow boiling parameters. Previous pool boiling studies have demonstrated the potential of porous, hydro

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Latif, Medhat Gamil. "Modelling the simplified boiling water reactor natural circulation loop and its stability." Diss., The University of Arizona, 1993. http://hdl.handle.net/10150/186405.

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An integrated model that estimates loop flow rate, heat removal, and stability parameters for the General Electric Simplified Boiling Water Reactor SBWR was developed. The three parameters above used to be calculated individually each by a separate code. The initial approach in loop thermal hydraulic modelling was the steady state solution of the SBWR loop mass, energy, and momentum equations. The power-to-flow map obtained proved to be quite comparable with the Natural Circulation in Boiling Water Reactor (NATBWR) code developed by EPRI, in addition to that of General Electric. At low power l

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Brodeur, David Lester 1963. "A study of US nuclear power boiling water reactor, class IV, operating performance, 1992-1997." Thesis, Massachusetts Institute of Technology, 1998. http://hdl.handle.net/1721.1/49796.

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Thesis (Nucl.E. and S.M.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1998.<br>Includes bibliographical references.<br>The steady improvement of US Nuclear Utility generation capability observed over the past two decades has recently halted and somewhat degraded. For the industry to resume its upward trend in performance a detailed examination must be performed of current performance and new methods developed to continue the improvement. A detailed study of Boiling Water Reactor, Class IV (BWR/4) performance over the past five years was conducted to gain insight to th

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Johnsson, John. "Detailed B-10 depletion in control rods operatingin a Nuclear Boiling Water Reactor." Thesis, Uppsala universitet, Institutionen för materialkemi, 2011. http://urn.kb.se/resolve?urn=urn:nbn:se:uu:diva-155416.

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In a nuclear power plant, control rods play a central role to control the reactivity ofthe core. In an inspection campaign of three control rods (CR 99) operated in theKKL reactor in Leibstadt, Switzerland, during 6 respectively 7 consecutive cycles,defects were detected in the top part of the control rods due to swelling caused bydepletion of the neutron-absorbing 10B isotope (Boron-10). In order to correlatethese defects to control rod depletion, the 10B depletion has in this study beencalculated in detail for the absorber pins in the top node of the control rods.Today the core simulator PLO

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Ahmad, Masroor. "Critical heat flux and associated phenomena in forced convective boiling in nuclear systems." Thesis, Imperial College London, 2012. http://hdl.handle.net/10044/1/9181.

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In evaporation of a liquid flowing in a tube or nuclear fuel element, there exists a transition (known as "dryout", "burnout", "boiling crisis" or "critical heat flux", CHF) from a high heat transfer coefficient regime to one of greatly reduced heat transfer coefficient. The conditions leading to dryout or CHF and the behaviour of wall temperatures in the ("post dryout or post CHF") region beyond it are of immense importance in nuclear reactor safety. In a nuclear reactor, the clad temperature excursion in the post-dryout region may be unacceptably high and the prediction of the location of dr

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Li, Jinghui Carleton University Dissertation Engineering Mechanical. "The Onset of significant void in boiling flows over a wide range of operation conditions." Ottawa, 1992.

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Phillips, Bren Andrew. "Nano-engineering the boiling surface for optimal heat transfer rate and critical heat flux." Thesis, Massachusetts Institute of Technology, 2011. http://hdl.handle.net/1721.1/76536.

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Thesis (S.M.)--Massachusetts Institute of Technology, Dept. of Nuclear Science and Engineering, 2011.<br>Cataloged from PDF version of thesis.<br>Includes bibliographical references (p. 130-133).<br>The effects on pool boiling characteristics such as critical heat flux and the heat transfer coefficient of different surface characteristics such as surface wettability, roughness, morphology, and porosity are not well understood. Layer-by-layer nanoparticle coatings were used to modify the surface of a sapphire heater to control the surface roughness, the layer thickness, and the surface chemistr

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Feng, Bo Ph D. Massachusetts Institute of Technology. "Feasibility of breeding in hard spectrum boiling water reactors with oxide and nitride fuels." Thesis, Massachusetts Institute of Technology, 2011. http://hdl.handle.net/1721.1/76497.

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Thesis (Ph. D.)--Massachusetts Institute of Technology, Dept. of Nuclear Science and Engineering, 2011.<br>Cataloged from PDF version of thesis.<br>Includes bibliographical references (p. 262-269).<br>This study assesses the neutronic, thermal-hydraulic, and fuel performance aspects of using nitride fuel in place of oxides in Pu-based high conversion light water reactor designs. Using the higher density nitride fuel hardens the neutron energy spectrum and results in higher breeding ratios. The state-of-the-art high conversion light water reactor, the Resource-renewable Boiling Water Reactor (R

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Han, Gee Yang. "A mathematical dynamic modeling and thermal hydraulic analysis of boiling water reactors using moving boundaries." Diss., The University of Arizona, 1993. http://hdl.handle.net/10150/186191.

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A new development and practical application of a mathematical dynamic modeling for simulating normal and accidental transient analysis for the boiling water reactor system is presented in this dissertation. The mathematical dynamic modeling represents a new technology based on a moving boundary concept. The mathematical model developed for fluid flows is based on a set of the four equation mixture model, one-dimensional, single channel with a drift flux model in the two-phase flow regime. The four conservation equations used in the mathematical model formulation include the vapor phase mass eq

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Guion, Alexandre Nicolas. "Modeling and simulation of liquid microlayer formation and evaporation in nucleate boiling using computational fluid dynamics." Thesis, Massachusetts Institute of Technology, 2017. http://hdl.handle.net/1721.1/112380.

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Thesis: Ph. D., Massachusetts Institute of Technology, Department of Nuclear Science and Engineering, 2017.<br>This electronic version was submitted by the student author. The certified thesis is available in the Institute Archives and Special Collections.<br>Cataloged from student-submitted PDF version of thesis.<br>Includes bibliographical references (pages 243-252).<br>The transport of latent heat makes boiling one of the most efficient modes of heat transfer, allowing a wide range of systems to improve their thermal performance, from microelectronic devices to nuclear power plants. In par

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Tetreault-Friend, Melanie. "Systematic investigation of the effects of hydrophilic porosity on boiling heat transfer and critical heat flux." Thesis, Massachusetts Institute of Technology, 2014. http://hdl.handle.net/1721.1/95571.

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Thesis: S.M., Massachusetts Institute of Technology, Department of Nuclear Science and Engineering, 2014.<br>Cataloged from PDF version of thesis.<br>Includes bibliographical references (pages 97-99).<br>Predicting the conditions of critical heat flux (CHF) is of considerable importance for safety and economic reasons in heat transfer units, such as in nuclear power plants. It is greatly advantageous to increase this thermal limit and much effort has been devoted to studying the effects of surface characteristics on it. In particular, recent work carried out by O'Hanley demonstrated the separa

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Su, Guanyu Ph D. Massachusetts Institute of Technology. "Experimental study of transient pool boiling heat transfer under exponential power excursion on plate-type heater." Thesis, Massachusetts Institute of Technology, 2015. http://hdl.handle.net/1721.1/97863.

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Thesis: S.M., Massachusetts Institute of Technology, Department of Nuclear Science and Engineering, 2015.<br>Cataloged from PDF version of thesis.<br>Includes bibliographical references (page 82).<br>Conduction and single-phase convective heat transfer are well understood phenomena: analytical models [1] and empirical correlations [2] allow capturing the thermal behavior of plate-type fuels or heaters in contact with a single-phase coolant. On the other hand, transient boiling heat transfer is a scarcely studied and much less understood phenomenon. Although, earlier studies have shown that imp

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Kim, Sung Joong Ph D. Massachusetts Institute of Technology. "Subcooled flow boiling heat transfer and critical heat flux in water-based nanofluids at low pressure." Thesis, Massachusetts Institute of Technology, 2009. http://hdl.handle.net/1721.1/53274.

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Thesis (Ph. D.)--Massachusetts Institute of Technology, Dept. of Nuclear Science and Engineering, 2009.<br>Cataloged from PDF version of thesis.<br>Includes bibliographical references (p. 285-290).<br>A nanofluid is a colloidal suspension of nano-scale particles in water, or other base fluids. Previous pool boiling studies have shown that nanofluids can improve the critical heat flux (CHF) by as much as 200%. In this study, subcooled flow boiling heat transfer and CHF experiments were performed with low concentrations of alumina, zinc oxide, and diamond nanoparticles in water (< 0.1 % by volum

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Lucas, Timothy R. "The effect of thermal aging and boiling water reactor environment on Type 316L stainless steel welds." Thesis, Massachusetts Institute of Technology, 2011. http://hdl.handle.net/1721.1/76921.

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Thesis (Ph. D.)--Massachusetts Institute of Technology, Dept. of Nuclear Science and Engineering, 2011.<br>Cataloged from PDF version of thesis.<br>Includes bibliographical references (p. 185-191).<br>The thermal aging and consequent embrittlement of materials are ongoing issues in cast stainless steels and duplex stainless steels. Spinodal decomposition is largely responsible for the well known "475°C" embrittlement that results in drastic reductions in ductility and toughness in these materials, and this process is operative also in welds of either cast or wrought stainless steels where 6-fe

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), Lerch Andrew (Andrew J. "Measurement of near-surface void fraction and macrolayer thickness in boiling water and silica-based nanofluid." Thesis, Massachusetts Institute of Technology, 2008. http://hdl.handle.net/1721.1/44839.

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Thesis (S.B.)--Massachusetts Institute of Technology, Dept. of Nuclear Science and Engineering, 2008.<br>Includes bibliographical references (leaves 48-49).<br>Nanofluids are engineered fluids that contain a suspension of nanoparticles in a pure substance. Nanoparticles can be any variety of metals, metal oxides, or ceramics. They have been shown to increase heat transfer properties such as thermal conductivity, convective heat transfer, and critical heat flux(CHF). An optical probe used to detect phase was used to measure the void fraction during boiling, from which the macrolayer thickness c

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Brodeur, David Lester. "A study of US Nuclear Power Boiling Water Reactor, Class IV, operating performance, 1992-1997." Thesis, Monterey, California. Naval Postgraduate School, 1998. http://hdl.handle.net/10945/9035.

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Virgen, Matthew Miguel. "Comparison of water boiling models against recent experimental data, with special emphasis on the bubble ebullition cycle." Thesis, Massachusetts Institute of Technology, 2011. http://hdl.handle.net/1721.1/76939.

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Thesis (S.B.)--Massachusetts Institute of Technology, Dept. of Nuclear Science and Engineering, 2011.<br>Cataloged from PDF version of thesis.<br>Includes bibliographical references (p. 37).<br>Using recently collected data which was measured with state-of-the-art techniques, models for nucleation site density, bubble departure diameter, and nucleation frequency were compared against the acquired data. The particular focus of this work is on the ebullition cycle and associated bubble nucleation frequency, looking at the models proposed by M.Z. Podowski. In my analysis, I took the average value

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Phillips, Bren Andrew. "Experimental investigation of subcooled flow boiling using synchronized high speed video, infrared thermography, and particle image velocimetry." Thesis, Massachusetts Institute of Technology, 2014. http://hdl.handle.net/1721.1/92060.

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Thesis: Ph. D., Massachusetts Institute of Technology, Department of Nuclear Science and Engineering, 2014.<br>This electronic version was submitted by the student author. The certified thesis is available in the Institute Archives and Special Collections.<br>Cataloged from student-submitted PDF version of thesis.<br>Includes bibliographical references (pages [133]-138).<br>Subcooled flow boiling of water was experimentally investigated using high-speed video (HSV), infrared (IR) thermography, and particle image velocimetry (PIV) to generate a unique database of synchronized data. HSV allowed

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Stehle, Gregory Raymond. "Confinement of Nucleation Sites in Nucleate Pool Boiling Using Atomic Layer Deposition and Constrictive Heaters." Thesis, University of Pittsburgh, 2017. http://pqdtopen.proquest.com/#viewpdf?dispub=10645783.

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<p> Boiling heat transfer is a powerful cooling mechanism used in a variety of industries to efficiently dissipate heat by taking advantage of latent heat. Nucleation site interactions have been demonstrated to affect behaviors in the bulk fluid, in the solid substrate and coalescence. Despite extensive studies of multi-site interactions, the conclusions of these studies are not in agreement. Namely, hydrodynamic effects are explained by some studies to promote nucleation while other studies find that, even with thermally isolated heat supplies, the presence of nearby sites diminishes nucleati

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Su, Guanyu Ph D. Massachusetts Institute of Technology. "Thermohydraulics and suppression of nucleate boiling in upward two-phase annular flow : probing multiscale physics by innovative diagnostics." Thesis, Massachusetts Institute of Technology, 2018. http://hdl.handle.net/1721.1/119035.

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Thesis: Ph. D., Massachusetts Institute of Technology, Department of Nuclear Science and Engineering, 2018.<br>This electronic version was submitted by the student author. The certified thesis is available in the Institute Archives and Special Collections.<br>Cataloged from student-submitted PDF version of thesis.<br>Includes bibliographical references (pages 176-181).<br>In the fuel assemblies of a boiling water reactor (BWR) the steam quality increases along the assembly's length as heat is transferred from the fuel rods to the water coolant. Nucleate boiling is the dominant heat transfer m

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Arment, Tyrell W. (Tyrell Wayne) 1988. "Departure from nucleate boiling and pressure drop prediction for tubes containing multiple short-length twisted-tape swirl promoters." Thesis, Massachusetts Institute of Technology, 2012. http://hdl.handle.net/1721.1/76962.

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Thesis (S.M.)--Massachusetts Institute of Technology, Dept. of Nuclear Science and Engineering, 2012.<br>Cataloged from PDF version of thesis.<br>Includes bibliographical references (p. 150-157).<br>Previous studies conducted at MIT showed that the power performance of an inverted pressurized water reactor (IPWR) conceptual design, i.e. the coolant and moderator are inverted such that the fuel is the continuous medium and the moderator flows through coolant channels, has potential to outperform a traditional pressurized water reactor (PWR). Similar to the traditional PWR, the IPWR design invol

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Gupta, Atul. "Development of Boiling Water Reactor Nuclear Power Plant Simulator for Human Reliability Analysis Education and Research." The Ohio State University, 2013. http://rave.ohiolink.edu/etdc/view?acc_num=osu1355347881.

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Sapin, Paul. "Etude expérimentale de l'ébullition en masse dans un milieu poreux modèle." Phd thesis, Toulouse, INPT, 2014. http://oatao.univ-toulouse.fr/12148/1/sapin_partie_1_sur_2.pdf.

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Ce travail propose une étude expérimentale de l'ébullition en masse dans une structure poreuse modèle. L'objectif est d'approfondir la compréhension des transferts de chaleur dans un écoulement diphasique avec changement de phase liquide-vapeur en milieu poreux, en liaison avec la problématique de la gestion des accidents graves dans les réacteurs nucléaires. A la suite d'un dysfonctionnement sur le circuit de refroidissement d'un réacteur nucléaire, l'augmentation de la température au sein du cœur provoque l'effondrement des tubes contenant le combustible. Il en résulte la formation d'un l

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