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Dissertations / Theses on the topic 'Marine nuclear reactor plants'

Author: Grafiati

Published: 4 June 2021

Last updated: 11 February 2022

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1

Alam, Syed Bahauddin. "The design of reactor cores for civil nuclear marine propulsion." Thesis, University of Cambridge, 2018. https://www.repository.cam.ac.uk/handle/1810/275650.

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Perhaps surprisingly, the largest experience in operating nuclear power plants has been in nuclear naval propulsion, particularly submarines. This accumulated experience may become the basis of a proposed new generation of compact nuclear power plant designs. In an effort to de-carbonise commercial freight shipping, there is growing interest in the possibility of using nuclear propulsion systems. Reactor cores for such an application would need to be fundamentally different from land-based power generation systems, which require regular refueling, and from reactors used in military submarines,

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2

McKillop, Jordan M. "Reducing the activation of the IRIS reactor building using the SCALE/MAVRIC methodology." Thesis, Georgia Institute of Technology, 2009. http://hdl.handle.net/1853/37209.

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The main objective of this research is: (1) to develop a model and perform numerical simulations to evaluate the radiation field and the resulting dose to personnel and activation of materials and structures throughout the IRIS nuclear power plant, and (2) to confirm that the doses are below the regulatory limit, and assess the possibility to reduce the activation of the concrete walls around the reactor vessel to below the free release limit. IRIS is a new integral pressurized water reactor (PWR) developed by an international team led by Westinghouse with an electrical generation capacity of

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3

Foster, Jack Warren. "Development and implementation of a response-function concept for spent nuclear fuel cask analysis." Thesis, Georgia Institute of Technology, 1993. http://hdl.handle.net/1853/17275.

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4

Jourdan, Grégoire. "Using risk-based regulations for licensing nuclear power plants : case study of gas-cooled fast reactor." Thesis, Massachusetts Institute of Technology, 2005. http://hdl.handle.net/1721.1/32278.

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Thesis (S.M.)--Massachusetts Institute of Technology, Engineering Systems Division, Technology and Policy Program, 2005.<br>Includes bibliographical references (p. 78-82).<br>The strategy adopted for national energy supply is one of the most important policy choice for the US. Although it has been dismissed in the past decades, nuclear power today has key assets when facing concerns on energy dependence and global warming. However, reactor licensing regulations need to be changed to get all the advantages of the most promising technologies. After reviewing the well-known drawbacks of the curre

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5

Khamis, Ibrahim Ahmad. "Simulation of nuclear power plant pressurizers with application to an inherently safe reactor." Diss., The University of Arizona, 1988. http://hdl.handle.net/10150/184378.

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Pressurizer modeling for predicting the dynamic pressure of the PIUS system is presented. The transient behavior of this model for the PIUS system was investigated. The validity of this model for the PIUS system is limited to transients that are neither too large nor too long in duration. For example, the model is not capable of describing events following a complete loss of liquid for the pressurizer. However, the model can be used for qualitative prediction of the PIUS system behavior for a wide variety of severe transients. A review of pressurizer modeling indicates that the neglecting of t

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6

Reperant, Jefferey John Robert. "Studies of turbulent liquid sheets for protecting IFE reactor chamber first walls." Thesis, Georgia Institute of Technology, 2002. http://hdl.handle.net/1853/18921.

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7

Maples, Allen B. "Design of a robust acoustic positioning system for an underwater nuclear reactor vessel inspection robot." Thesis, This resource online, 1993. http://scholar.lib.vt.edu/theses/available/etd-06232009-063217/.

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8

Pounders, Justin Michael. "A coarse-mesh transport method for time-dependent reactor problems." Diss., Georgia Institute of Technology, 2010. http://hdl.handle.net/1853/39586.

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A new solution technique is derived for the time-dependent transport equation. This approach extends the steady-state coarse-mesh transport method that is based on global-local decompositions of large (i.e. full-core) neutron transport problems. The new method is based on polynomial expansions of the space, angle and time variables in a response-based formulation of the transport equation. The local problem (coarse mesh) solutions, which are entirely decoupled from each other, are characterized by space-, angle- and time-dependent response functions. These response functions are, in turn, used

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9

Sumner, Tyler Scott. "A safety and dynamics analysis of the subcritical advanced burner reactor: SABR." Thesis, Atlanta, Ga. : Georgia Institute of Technology, 2008. http://hdl.handle.net/1853/24636.

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10

BRAGA, CLAUDIA C. "Analise de sensibilidade para modelagem semi-mecanistica de acidentes severos." reponame:Repositório Institucional do IPEN, 1994. http://repositorio.ipen.br:8080/xmlui/handle/123456789/10399.

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Adams, William Mark 1961. "APPLICATION OF THE VARIANCE-TO-MEAN RATIO METHOD FOR DETERMINING NEUTRON MULTIPLICATION PARAMETERS OF CRITICAL AND SUBCRITICAL REACTORS (REACTOR NOISE, FEYNMAN-ALPHA)." Thesis, The University of Arizona, 1985. http://hdl.handle.net/10150/275438.

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12

Huggett, Jenny A. "The effect of chlorine, heat and physical stress on entrained plankton at Koeberg Nuclear Power Station." Master's thesis, University of Cape Town, 1988. http://hdl.handle.net/11427/17079.

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Bibliography: pages 112-138.<br>The large volume of seawater used for cooling at Koeberg Nuclear Power Station contains many planktonic organisms which are exposed to heat, chlorine and physical stress during their passage through the system. Phytoplankton biomass, measured as chlorophyll a, was reduced by an average of 55.32% due to entrainment, and productivity was decreased by 38.30% on average, mainly due to chlorination. Zooplankton mortality averaged 22.34% for all species and 30.52% for copepods, the dominant group. The copepod Paracartia africana was used in laboratory experiments desi

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13

Gros, Emilien B. "Liquid-Salt-Cooled Reactor start-up with natural circulation under Loss-of-Offsite-Power (LOOP) conditions." Thesis, Georgia Institute of Technology, 2012. http://hdl.handle.net/1853/43745.

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The Liquid-Salt-Cooled Very High-Temperature Reactor (LS-VHTR) was modeled using the neutronics analysis code SCALE6.0 and the thermal-hydraulics and kinetics modeling code RELAP5-3D with objective to devise, analyze, and evaluate the feasibility and stability of a start-up procedure for this reactor using natural circulation of the coolant and under the Loss Of Offsite Power (LOOP) conditions. This Generation IV reactor design has been studied by research facilities worldwide for almost a decade. While neutronics and thermal-hydraulics analyses have been previously performed to show the pe

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14

Hidalga, García-Bermejo Patricio. "Development and validation of a multi-scale and multi-physics methodology for the safety analysis of fast transients in Light Water Reactors." Doctoral thesis, Universitat Politècnica de València, 2021. http://hdl.handle.net/10251/160135.

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[ES] La tecnología nuclear para el uso civil genera más preocupación por la seguridad que muchas otras tecnologías que se usan a diario. La Autoridad Nuclear define las bases de cómo debe realizarse la operación segura de una Central Nuclear. De acuerdo a las directrices establecidas por la Autoridad Nuclear, una Central Nuclear debe analizar una envolvente de escenarios hipotéticos y comprobar de manera determinista que los criterios de aceptación para dicho evento se cumplen. El Análisis Determinista de Seguridad utiliza herramientas de simulación que aplican la física conocida sobre el comp

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15

Tshamala, Mubenga Carl. "Simulation and control implications of a high-temperature modular reactor (HTMR) cogeneration plant." Thesis, Stellenbosch : Stellenbosch University, 2014. http://hdl.handle.net/10019.1/86264.

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Thesis (MScEng)--Stellenbosch University, 2014.<br>ENGLISH ABSTRACT: Traditionally nuclear reactor power plants have been optimised for electrical power generation only. In the light of the ever-rising cost of dwindling fossil fuel resources as well the global polluting effects and consequences of their usage, the use of nuclear energy for process heating is becoming increasingly attractive. In this study the use of a so-called cogeneration plant in which a nuclear reactor energy source is optimised for the simultaneous production of superheated steam for electrical power generation and proces

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16

Burnfield, Daniel L. "An advanced system for quantifying the effects of radiological releases following a major nuclear accident." Master's thesis, This resource online, 1994. http://scholar.lib.vt.edu/theses/available/etd-03302010-020420/.

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17

SILVESTRE, LARISSA J. B. "PCRELAP5 - Programa de cálculo para os dados de entrada do código RELAP5." reponame:Repositório Institucional do IPEN, 2016. http://repositorio.ipen.br:8080/xmlui/handle/123456789/26393.

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Submitted by Claudinei Pracidelli (cpracide@ipen.br) on 2016-06-22T14:12:07Z No. of bitstreams: 0<br>Made available in DSpace on 2016-06-22T14:12:07Z (GMT). No. of bitstreams: 0<br>Dissertação (Mestrado em Tecnologia Nuclear)<br>IPEN/D<br>Instituto de Pesquisas Energeticas e Nucleares - IPEN-CNEN/SP

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18

Bollen, Rob. "Verification and validation of computer simulations with the purpose of licensing a pebble bed modular reactor." Thesis, Stellenbosch : Stellenbosch University, 2002. http://hdl.handle.net/10019.1/53216.

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Thesis (MBA)--Stellenbosch University, 2002.<br>ENGLISH ABSTRACT: The Pebble Bed Modular Reactor is a new and inherently safe concept for a nuclear power generation plant. In order to obtain the necessary licenses to build and operate this reactor, numerous design and safety analyses need to be performed. The results of these analyses must be supported with substantial proof to provide the nuclear authorities with a sufficient level of confidence in these results to be able to supply the required licences. Beside the obvious need for a sufficient level of confidence in the safety analyses, the

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19

CARNEIRO, ALVARO L. G. "Desenvolvimento de sistema de monitoracao e diagnostico aplicado a valvulas moto-operadas utilizadas em centrais nucleares." reponame:Repositório Institucional do IPEN, 2003. http://repositorio.ipen.br:8080/xmlui/handle/123456789/11109.

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MESQUITA, ROBERTO N. de. "Classificação de defeitos em tubos de gerador de vapor de plantas nucleares utilizando mapas auto-organizáveis." reponame:Repositório Institucional do IPEN, 2002. http://repositorio.ipen.br:8080/xmlui/handle/123456789/11640.

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Made available in DSpace on 2014-10-09T12:54:13Z (GMT). No. of bitstreams: 0<br>Made available in DSpace on 2014-10-09T14:09:27Z (GMT). No. of bitstreams: 1 12432.pdf: 12974191 bytes, checksum: ddfc093df6afa20374e446cb5c994b88 (MD5)<br>Tese (Doutoramento)<br>IPEN/T<br>Escola Politecnica, Universidade de São Paulo - POLI/USP

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21

PERRENOUD, HELENA G. "Modulo de extracao de eventos em assinaturas de potencia de valvulas moto-operadas, usando um sistema especialista para o sistema de diagnostico de MOV's utilizado em reatores nucleares." reponame:Repositório Institucional do IPEN, 2001. http://repositorio.ipen.br:8080/xmlui/handle/123456789/10967.

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SANTOS, GEAN R. dos. "Algoritmo de colônia de formigas e redes neurais artificiais aplicados na monitoração e detecção de falhas em centrais nucleares." reponame:Repositório Institucional do IPEN, 2016. http://repositorio.ipen.br:8080/xmlui/handle/123456789/26798.

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Submitted by Claudinei Pracidelli (cpracide@ipen.br) on 2016-11-11T09:45:23Z No. of bitstreams: 0<br>Made available in DSpace on 2016-11-11T09:45:23Z (GMT). No. of bitstreams: 0<br>Um desafio recorrente em processos produtivos é o desenvolvimento de sistemas de monitoração e diagnóstico. Esses sistemas ajudam na detecção de mudanças inesperadas e interrupções, prevenindo perdas e mitigando riscos. Redes Neurais Artificiais (RNA) têm sido largamente utilizadas na criação de sistemas de monitoração. Normalmente as RNA utilizadas para resolver este tipo de problema são criadas levando-se em cont

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23

CRUZ, JULIO R. B. "Procedimento analitico para previsao do comportamento estrutural de componentes truncados." reponame:Repositório Institucional do IPEN, 1998. http://repositorio.ipen.br:8080/xmlui/handle/123456789/10665.

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24

Wåxberg, Tim, and Henrik Olsson. "Sjöingenjör : Möjligheternas Yrke." Thesis, University of Kalmar, Kalmar Maritime Academy, 2008. http://urn.kb.se/resolve?urn=urn:nbn:se:hik:diva-243.

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<p>Kärnkraften ser vi som ett miljövänligt och bra alternativ för framtiden. Därför kändes det intressant att undersöka om vi som blivande sjöingenjörer har en framtid där efter våran karriär till sjöss. Syftet med detta arbete är att få ökad insikt om vilka teoretiska kunskaper, praktiska och personliga egenskaper som gör sjöingenjören attraktiv i ledande befattningar vid kärnkraftsverk. Datainsamlingen skedde med hjälp av en enkätundersökning och en intervju. Undersökningen skickades ut till Sveriges samtliga kärnkraftverk och intervjun gjordes med en anställd på ett utav dem. Detta citat if

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25

Netopilová, Petra. "Systémy přeměn energie pro jaderné elektrárny se sodíkem chlazeným reaktorem (SFR)." Master's thesis, Vysoké učení technické v Brně. Fakulta strojního inženýrství, 2011. http://www.nusl.cz/ntk/nusl-229737.

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The aim of the dissertation is proposing and solving energy convection systems for nuc-lear power plants with a sodium fast reactor of the 4th generation. The first part of the dissertation deals with collection and evaluation of information available about nuclear power plants with sodium fast reactor which use nuclear or non-nuclear reheating to increase thermal efficiency. On the basis of the acquired information, thermal schemes are developed and thermal effi-ciency is determined for the systems working in both Rankine thermal cycle and Brayton thermal cycle. In the further part of the dis

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Svoboda, Pavel. "Návrh těsnění HDR HCČ 317 v JE Paks." Master's thesis, Vysoké učení technické v Brně. Fakulta strojního inženýrství, 2009. http://www.nusl.cz/ntk/nusl-228604.

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This diploma work is engaged in replacement of gasket main dividing plane of reactor coolant pumps in nuclear power plant Paks. Of the newly suggested gasket is kammprofile gasket with expanded graphite layer. This work contain suggestion and calculation of new sealing a knot and calculation existing sealing the knot. Results are confrontacion and sequentially is discussed influence on main dividing plane HCČ 317 by use the new and the existing gasket. In this work is contained description brief of legislation. This legislation must keep by design components dedicated for nuclear equipment. Ne

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27

Barci-Funel, Geneviève. "Etudes radiochimiques de nuclides de fission et transuraniens a longues vies dans des ecosystemes marins et terrestres." Nice, 1987. http://www.theses.fr/1987NICE4156.

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Estimation de la pollution radioactive par les radionuclides artificiels a vie longue disperses dans l'environnement suite a des tests nucleaires dans l'atmosphere et suite aux rejets d'installations nucleaires ou aux accidents comme celui de tchernobyl.

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28

LIN, ZHI-HONG, and 林志鴻. "The dynamic analysis of power systems with pressurized water reactor nuclear plants." Thesis, 1991. http://ndltd.ncl.edu.tw/handle/78616965538465438582.

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29

Gedeon, Stephen R. "Nuclear design analysis of low-power (1-30 KWe) space nuclear reactor systems." Thesis, 1993. http://hdl.handle.net/1957/37043.

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Preliminary nuclear design studies have been completed on ten configurations of nuclear reactors for low power (1-30 kWe) space applications utilizing thermionic energy conversion. Additional design studies have been conducted on the TRICE multimegawatt in-core thermionic reactor configuration. In each of the cases, a reactor configuration has been determined which has the potential for operating 7 years with sufficient reactivity margin. Additional safety evaluations have been conducted on these configurations including the determination of sufficient shutdown reactivity, and consideration of

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30

Lee, Hsing Hui. "System modeling and reactor design study of an advanced incore thermionic space reactor." Thesis, 1992. http://hdl.handle.net/1957/35935.

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Incore thermionic space reactor design concepts which operate at a nominal power output range of 20 to 50 kWe are described. Details of the neutronic, thermionic, thermal hydraulics and shielding performance are presented. Due to the strong absorption of thermal neutrons by natural tungsten, and the large amount of that material within the reactor core, two designs are considered. An overall system design code has been developed at Oregon State University to model advanced incore thermionic energy conversion based nuclear reactor systems for space applications. The code modules include neutron

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31

Wei, Hong-Lin, and 魏宏霖. "Effect of Clad Thickness on Reliability of Reactor Pressure Vessels in Nuclear Power Plants." Thesis, 2011. http://ndltd.ncl.edu.tw/handle/80415965040954219618.

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碩士<br>國立臺灣大學<br>機械工程學研究所<br>99<br>Nowadays, we are facing problems of global energy shortage as well as the need of environmental protection. The advantage of low cost and small amount of CO2 discharge makes nuclear power an important choice for energy. However, the safety of structures, systems and mechanical components employed in a nuclear power plant has to be assured before a plant can be constructed. One of the most important pressure boundary components in the steam supply system of a nuclear power plant is the reactor pressure vessel (RPV). It is welded together by several steel plates

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32

Matthews, Christopher. "Analysis of the antineutrino rate during CANDU reactor startup." Thesis, 2012. http://hdl.handle.net/1957/27973.

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Detection systems used to monitor reactor operations are of significant interest as tools for verification of operator declarations. Current reactor site safeguards are limited to visual inspections and intrusive monitoring systems. The recent development of antineutrino detectors may soon allow real-time monitoring from an unobtrusive location. Antineutrinos are produced through beta decay of fission products in the core. The lack of charge and small mass of the antineutrino ensures an extremely low interaction probability with all matter, effectively making the particle impossible to shield.

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33

Moleme, Pulane Adelaide. "Establishment of technical basis for the nuclear emergency planning and preparedness programme for the Pebble Bed Modular Reactor(PBMR) nuclear power station / Pulane Adelaide Moleme." Thesis, 2003. http://hdl.handle.net/10394/11307.

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In this work, description and explanation for the conditions of emergency preparedness is given. The aim was to establish the technical basis for emergency response plans in the event of a nuclear incident that might occur at the PBMR nuclear power station. The Koeberg Nuclear Power Station Technical Basis for Emergency Planning was basically used as a guideline and PC COSYMA, a programme that runs on PC, was used to help ,model the release as described or specified by the regulations set in [5] for South Africa. PC COSYMA runs were done to calculate doses to specific organs and to the whole b

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Lewis, Bryan R. "Development of systems analysis program for space reactor studies." Thesis, 1993. http://hdl.handle.net/1957/35762.

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An overall systems design code was developed to model an advanced in-core thermionic energy conversion based nuclear reactor system for space applications at power levels of 10 to 50 kWe. The purpose of this work was to provide the overall shell for the systems code and to also provide the detailed neutronic analysis section of the code. The design code that was developed is to be used to evaluate a reactor system based upon a single cell thermionic fuel element which uses advanced technology to enhance the performance of single cell thermionic fuel elements. A literature survey provided infor

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35

Welter, Kent B. "Experimental investigation of liquid entrainment in a reactor hot-leg with a vertical branch." Thesis, 2001. http://hdl.handle.net/1957/30753.

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A literature review of current phase separation publications was conducted. Data sets were collected and compiled into a Two-Phase Flow Separation Database. Examination of this database indicating a need for further investigation into the liquid entertainment phenomena for smaller hot-leg to branch diameters and intermittent flow regimes. A detailed analysis to the prototypic phase separation process is presented and the associated phenomena are identified. Appropriate scaling criteria were employed for the design of a scaled test facility. Geometry and the flow conditions of the test facility

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Sajish, S. D. "Reliability And Response Uncertainty Analyses Of Piping And Shutdown Systems Of Nuclear Power Plants Under Seismic Loading." Thesis, 2011. http://etd.iisc.ernet.in/handle/2005/1989.

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Earthquake safety engineering of nuclear power plant structures poses several challenges to the analyst and designer. These problems are characterized by highly transient and dynamic nature of earthquake induced excitations, random nature of details of support motions (in terms of duration, frequency content, amplitude modulation, multiple components, and spatial variability), nonlinear nature of structural behavior, geometrical complexity of the primary and a large number of secondary systems (such as, for example, piping, rotors, and machine panels), soil-structure interactions, demands on h

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37

"A study of the performance of a sparse grid cross section representation methodology as applied to MOX fuel." Thesis, 2015. http://hdl.handle.net/10210/15086.

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M.Phil. (Energy Studies)<br>Nodal diffusion methods are often used to calculate the distribution of neutrons in a nuclear reactor core. They require few-group homogenized neutron cross sections for every heterogeneous sub-region of the core. The homogenized cross sections are pre-calculated at various reactor states and represented in a way that facilitates the reconstruction of cross sections at other possible states. In this study a number of such representations were built for the homogenized cross sections of a MOX (mixed oxide) fuel assembly via hierarchical Lagrange interpolation on Clen

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Sedumoeng, Lillian M. "Deterministic analysis for the sensitivity of Licensing Basis Events (LBE) radiological consequences to various exposure pathways for the Pebble Bed Modular Reactor (PMBR) / Lillian M. Sedumoeng." Thesis, 2004. http://hdl.handle.net/10394/11316.

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Nuclear safety is the main concern for the licensing of nuclear power plants, not only in the Republic of South Africa but also worldwide. The design of the nuclear power plant plays an important role in the licensing process, which includes probabilistic and deterministic analysis of a set of design or Licensing basis events. This study was about the deterministic analysis for the sensitivity of licensing basis events radiological consequences to different radiological pathways. The study was done for the Pebble Bed Modular Reactor (PBMR), which is a nuclear power plant, still in its early ph

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Hallee, Brian Todd. "Feed-and-bleed transient analysis of OSU APEX facility using the modern Code Scaling, Applicability, and Uncertainty method." Thesis, 2013. http://hdl.handle.net/1957/37872.

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The nuclear industry has long relied upon bounding parametric analyses in predicting the safety margins of reactor designs undergoing design-basis accidents. These methods have been known to return highly-conservative results, limiting the operating conditions of the reactor. The Best-Estimate Plus Uncertainty (BEPU) method using a modernized version of the Code-Scaling, Applicability, and Uncertainty (CSAU) methodology has been applied to more accurately predict the safety margins of the Oregon State University Advanced Plant Experiment (APEX) facility experiencing a Loss-of-Feedwater Acciden

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