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Dissertations / Theses on the topic 'Pressurized steam'

Author: Grafiati

Published: 4 June 2021

Last updated: 7 February 2022

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1

Choi, Jung In. "Nonlinear digital computer control for the steam generator system in a pressurized water reactor plant." Thesis, Massachusetts Institute of Technology, 1987. http://hdl.handle.net/1721.1/42103.

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2

Elliott, Alicia M. "Multiphysics modeling of activity transport and evolution of CRUD and steam generator oxides in pressurized water reactors." Thesis, Massachusetts Institute of Technology, 2018.

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This electronic version was submitted by the student author. The certified thesis is available in the Institute Archives and Special Collections.<br>Thesis: S.M., Massachusetts Institute of Technology, Department of Nuclear Science and Engineering, 2018<br>Cataloged from student-submitted PDF version of thesis.<br>Includes bibliographical references (pages 121-123).<br>Fouling deposits of corrosion products on fuel cladding, known as crud, in the core of light water reactors can cause a variety of operational issues. Buildup of radioactive crud and corrosion products on ex-core structures, suc

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3

Rebak, Raúl Basilio. "Environmentally induced cracking in alloy 600 and SA 302 steel in pressurized water reactor steam generator conditions /." The Ohio State University, 1993. http://rave.ohiolink.edu/etdc/view?acc_num=osu1487846885777343.

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4

Namduri, Haritha Nasrazadani Seifollah. "Formation and quantification of corrosion deposits in the power industry." [Denton, Tex.] : University of North Texas, 2007. http://digital.library.unt.edu/permalink/meta-dc-3635.

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5

Nakka, Ravi Kumar Nasrazadani Seifollah. "Flow accelerated corrosion experience at Comanche Peak Steam Electric Station." [Denton, Tex.] : University of North Texas, 2008. http://digital.library.unt.edu/permalink/meta-dc-6072.

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6

Andersson, Victor. "Flödesanalys av roterande ventil i ångmotor." Thesis, Karlstads universitet, Fakulteten för hälsa, natur- och teknikvetenskap (from 2013), 2018. http://urn.kb.se/resolve?urn=urn:nbn:se:kau:diva-68099.

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This report is a bachelor thesis at Karlstad University in collaboration with Invencon AB and Ranotor AB. The goal was to analyze a rotating valve leading water vapor through an inlet and five outlets. The quantifiable results that were addressed in this project are the mass flow through the outlets and the forces affecting the valve and its shaft (primarily radial forces). The tools used for this project are PTC Creo and ANSA for modelling and mesh as well as ANSYS-CFX and Matlab for computational help. The results show that the specified rotational speed of 4600 rpm doesn’t work for this mod

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7

Cilliers, Charl. "Thermal-fluid simulation of nuclear steam generator performance using Flownex and RELAP5/mod3.4 / Charl Cilliers." Thesis, North-West University, 2012. http://hdl.handle.net/10394/9777.

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The steam generator plays a primary role in the safety and performance of a pressurized water reactor nuclear power plant. The cost to utilities is in the order of millions of Rands a year as a direct result of damage to steam generators. The damage results in lower efficiency or even plant shutdown. It is necessary for the utility and for academia to have models of nuclear components by which research and analysis may be performed. It must be possible to analyse steam generator performance for both day-to-day operational analysis as well as in the case of extreme accident scenarios. The homog

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8

Sakabe, Akira. "Steam Generator Liquid Mass as a Control Input for the Movement of the Feed Control Valve in a Pressurized Water Reactor." NCSU, 2001. http://www.lib.ncsu.edu/theses/available/etd-20011121-172405.

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<p> The steam generator in a nuclear power plant plays an important role in cooling the reactor and producing steam for the turbine-generators. As a result, control of the water inventory in the steam generator is crucial. The water mass in the steam generator cannot be measured directly, so the water mass is generally inferred from the downcomer differential pressure as a measure of the downcomer water level. The water level in the downcomer is a good indication of the water mass inventory at or near steady-state conditions. Conventional PI controllers are used to maintain the water level in

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9

Nakka, Ravi Kumar. "Flow Accelerated Corrosion Experience at Comanche Peak Steam Electric Station." Thesis, University of North Texas, 2008. https://digital.library.unt.edu/ark:/67531/metadc6072/.

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Flow accelerated corrosion (FAC) is a major concern in the power industry as it causes thinning of the pipes by the dissolution of the passive oxide layer formed on the pipe surface. Present research deals with comparing the protection offered by the magnetite (Fe3O4) versus maghemite (γ-Fe2O3) phases thickness loss measurements. Fourier transform infrared spectroscopy (FTIR) is used in distinguishing these two elusive phases of iron oxides. Representative pipes are collected from high pressure steam extraction line of the secondary cycle of unit 2 of Comanche Peak Steam Electric Station (CPSE

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10

Brink, Michael Joseph. "Hardware-in-the-loop simulation of pressurized water reactor steam-generator water-level control, designed for use within physically distributed testing environments." The Ohio State University, 2013. http://rave.ohiolink.edu/etdc/view?acc_num=osu1357273230.

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11

Namduri, Haritha. "Characterization of Iron Oxide Deposits Formed at Comanche Peak Steam Electric Station." Thesis, University of North Texas, 2003. https://digital.library.unt.edu/ark:/67531/metadc5521/.

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The presence of deposits leading to corrosion of the steam generator (SG) systems is a major contributor to operation and maintenance cost of pressurized water reactor (PWR) plants. Formation and transport of corrosion products formed due to the presence of impurities, metallic oxides and cations in the secondary side of the SG units result in formation of deposits. This research deals with the characterization of deposit samples collected from the two SG units (unit 1 and unit 2) at Comanche Peak Steam Electric Station (CPSES). X-ray diffraction (XRD), Fourier transform infrared spectrophotom

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12

Namduri, Haritha. "Formation and Quantification of Corrosion Deposits in the Power Industry." Thesis, University of North Texas, 2007. https://digital.library.unt.edu/ark:/67531/metadc3635/.

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The presence of deposits on the secondary side of pressurized water reactor (PWR) steam generator systems is one of the main contributors to the high maintenance costs of these generators. Formation and transport of corrosion products formed due to the presence of impurities, metals and metallic oxides in the secondary side of the steam generator units result in formation of deposits. This research deals with understanding the deposit formation and characterization of deposits by studying the samples collected from different units in secondary side system at Comanche Peak Steam Electric Statio

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13

Rohde, U., U. Grundmann, and S. Kliem. "Methodenentwicklung zur Analyse von Störfallszenarien mit Frischdampfleck und Borverdünnung mit Hilfe des Codesystems ATHLET-DYN3D - Abschlussbericht Teil 2." Forschungszentrum Dresden, 2010. http://nbn-resolving.de/urn:nbn:de:bsz:d120-qucosa-28576.

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Es wurde ein Modell zur realistischen Beschreibung der Kühlmittelvermischung innerhalb des Reaktordruckbehälters von Druckwasserreaktoren in den gekoppelten Programmkomplex DYN3D/ATHLET implementiert. Diese Modell basiert auf dem Prinzip der linearen Superposition Dirac-Impuls-ähnlicher Störungen und kann für die Modellierung der Vermischung von Kühlmittel unterschiedlicher Temperatur und/oder unterschiedlicher Borsäurekonzentration eingesetzt werden. Der um das Vermischungsmodell erweiterte Programmkomplex DYN3D/ATHLET wurde für Analyse von Borverdünnungsstörfällen und Frischdampflecks angewa

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14

Rohde, U., U. Grundmann, and S. Kliem. "Methodenentwicklung zur Analyse von Störfallszenarien mit Frischdampfleck und Borverdünnung mit Hilfe des Codesystems ATHLET-DYN3D - Abschlussbericht Teil 2." Forschungszentrum Rossendorf, 2005. https://hzdr.qucosa.de/id/qucosa%3A21684.

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Es wurde ein Modell zur realistischen Beschreibung der Kühlmittelvermischung innerhalb des Reaktordruckbehälters von Druckwasserreaktoren in den gekoppelten Programmkomplex DYN3D/ATHLET implementiert. Diese Modell basiert auf dem Prinzip der linearen Superposition Dirac-Impuls-ähnlicher Störungen und kann für die Modellierung der Vermischung von Kühlmittel unterschiedlicher Temperatur und/oder unterschiedlicher Borsäurekonzentration eingesetzt werden. Der um das Vermischungsmodell erweiterte Programmkomplex DYN3D/ATHLET wurde für Analyse von Borverdünnungsstörfällen und Frischdampflecks angewa

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15

Ranc, Isabelle. "Modélisation de la fragmentation fine lors de la phase de déclenchement d'une explosion de vapeur." Université Joseph Fourier (Grenoble ; 1971-2015), 1997. http://www.theses.fr/1997GRE10106.

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Ce travail est motive par les etudes de surete relatives aux accidents graves des reacteurs a eau pressurisee, qui envisagent la fusion du coeur. Dans ce cadre, on etudie une des phases de l'explosion de vapeur ou interaction corium-eau, c'est-a-dire la vaporisation violente du refrigerant lors d'un choc thermique entre un liquide tres chaud et un liquide froid. L'objet de l'etude est la phase de declenchement de l'interaction, pendant laquelle une goutte de combustible, de l'ordre du centimetre, initialement entouree d'un film de vapeur, se fragmente en debris de l'ordre de la centaine de mic

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16

Nyawo, Talent. "Design of a rotary valve for pressurised steam." Thesis, KTH, Maskinkonstruktion (Inst.), 2016. http://urn.kb.se/resolve?urn=urn:nbn:se:kth:diva-192859.

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Denna rapport är gjord på ett examensarbete som var utfört på uppdrag av det svenska företaget Ranotor AB. Syftet var att utveckla en konceptuell lösning för en rotationsventil som skall fungera i en miljö med hög temperatur och högt tryck. Ventilen skall arbeta under höga rotationshastigheter, vilket kräver korta öppettider.Tekniska hjälpmedel såsom SolidWorks, ANSYS och MATLAB användes för att modellera och analysera de konceptuella lösningarna. Slutlösningen valdes från ett flertal olika koncept, varpå detta vidareutvecklades och optimerades. Betydande material och gastätningslösningar iden

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17

Tulloch, Sam. "The use of dispersants in pressurised water reactor steam generators." Thesis, University of Birmingham, 2011. http://etheses.bham.ac.uk//id/eprint/706/.

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Environmental degradation promoted by the presence of sludge piles in the steam generators of Pressurised Water Reactors (PWR) can pose a threat to their safe and continuous operation. The use of dispersants can reduce the rate at which sludge accumulates. Polyacrylic acid (PAA) is currently the only dispersant used in PWRs. Settling rate tests identified several dispersants with the potential to outperform PAA, notably Hydroxyethylidene-1,1-diphosphonic Acid (HEDP). To estimate the dispersant concentration required during plant operation, optimum concentrations were identified for both PAA an

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18

Barham, Scott. "High quality steam measurement in power station pipework : accuracy assessment of electrical capacitance measurements in pressurised wet steam." Thesis, University of Nottingham, 2016. https://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.754211.

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19

Ṭāha, ʿUṯmān. "Commande automatique robustesse du générateur de vapeur REP." Vandoeuvre-les-Nancy, INPL, 1993. http://www.theses.fr/1993INPL1280.

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Le générateur de vapeur est un élément essentiel pour le fonctionnement des centrales nucléaires à réacteur à eau pressurisée. La régulation du niveau d'eau de ces générateurs pose beaucoup de problèmes à basse charge: 30% des arrêts d'urgences constatées sont imputables à la régulation du niveau d'eau. Il faut souligner que le générateur de vapeur est un système à déphasage non minimal, fortement non linéaire et difficile à identifier étant donné qu'on ne peut l'isoler du reste de la centrale. Les mesures du débit vapeur sortant du générateur deviennent de mauvaise qualité à faible charge, ce

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20

Hamdani, Fethi. "Improvement of the corrosion and oxidation resistance of Ni-based alloys by optimizing the chromium content." Thesis, Lyon, INSA, 2015. http://www.theses.fr/2015ISAL0012/document.

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Cette étude fondamentale est dédiée à la compréhension de l’influence de la composition chimique, notamment la teneur en chrome, des alliages base de nickel sur leur mécanismes de corrosion et d’oxydation. La corrosion sous contrainte intergranular (CSCIG) est un mode de dégradation qui affecte de nombreux alliages au sein des réacteurs à eau pressurisé. En particulier, les alliages base nickel tubes des générateur de vapeur (GV). La sensibilité à la CSC est désormais dépend de la teneur en chrome, ce qui a conduit au remplacement de l’alliage 600 (Ni-16Cr-9Fe) par l’alliage 690 (Ni-30Cr-9Fe).

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21

Kliem, S., U. Grundmann, and U. Rohde. "Qualifizierung des Kernmodells DYN3D im Komplex mit dem Störfallcode ATHLET als fortgeschrittenes Werkzeug für die Störfallanalyse von WWER-Reaktoren - Teil 2." Forschungszentrum Dresden, 2010. http://nbn-resolving.de/urn:nbn:de:bsz:d120-qucosa-29356.

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Benchmark calculations for the validation of the coupled neutron kinetics/thermohydraulic code complex DYN3D-ATHLET are described. Two benchmark problems concerning hypothetical accident scenarios with leaks in the steam system for a VVER-440 type reactor and the TMI-1 PWR have been solved. The first benchmark task has been defined by FZR in the frame of the international association "Atomic Energy Research" (AER), the second exercise has been organised under the auspices of the OECD. While in the first benchmark the break of the main steam collector in the sub-critical hot zero power state o

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22

Kliem, S., U. Grundmann, and U. Rohde. "Qualifizierung des Kernmodells DYN3D im Komplex mit dem Störfallcode ATHLET als fortgeschrittenes Werkzeug für die Störfallanalyse von WWER-Reaktoren - Teil 2." Forschungszentrum Rossendorf, 2002. https://hzdr.qucosa.de/id/qucosa%3A21762.

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Benchmark calculations for the validation of the coupled neutron kinetics/thermohydraulic code complex DYN3D-ATHLET are described. Two benchmark problems concerning hypothetical accident scenarios with leaks in the steam system for a VVER-440 type reactor and the TMI-1 PWR have been solved. The first benchmark task has been defined by FZR in the frame of the international association "Atomic Energy Research" (AER), the second exercise has been organised under the auspices of the OECD. While in the first benchmark the break of the main steam collector in the sub-critical hot zero power state o

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23

Mubarok, Mahdi. "Valorization of beech wood through development of innovative and environmentally friendly chemical modification treatments." Electronic Thesis or Diss., Université de Lorraine, 2019. http://www.theses.fr/2019LORR0141.

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Dans cette étude, l’amélioration des propriétés physiques et de sa durabilité aux agents de dégradation biologique du hêtre européen (Fagus sylvatica) a été réalisée au moyen de différents traitements. Les premiers types de traitements sont basés sur l'imprégnation de dérivés vinyliques de glycérol ou de polyglycérol en tant qu'additif suivi d’une étape de modification thermique réalisée dans un réacteur ouvert (OHT) ou fermé (HPS). Le deuxième type de traitement repose sur la poly-estérification in situ du sorbitol et de l'acide citrique à différentes concentrations et températures de durciss

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24

Macário, Marco Cláudio Torres. "Evaluation of Simplified Nuclear Power Plant Simulator in Case of a Main Steam Line Break." Master's thesis, 2016. http://hdl.handle.net/10316/81591.

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Dissertação de Mestrado Integrado em Engenharia Electrotécnica e de Computadores apresentada à Faculdade de Ciências e Tecnologia<br>Nesta dissertação é apresentada a simulação simplificada de uma rutura na conduta principal de vapor de uma central nuclear de dois circuitos de permutação de calor e reator de água pressurizada. O modelo de central usado neste trabalho, é um modelo genérico de uma central de água pressurizada com dois circuitos de permutação de calor, com geradores de vapor de tipo tubo em U invertido e com sistema de contenção do reator, seco. Com uma potencia térmica de aproxi

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