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Dissertations / Theses on the topic 'Reactor'

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Published: 4 June 2021
Last updated: 6 July 2024

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1

DeWitte, Jacob D. (Jacob Dominic). "Reactor protection system design alternatives for sodium fast reactors." Thesis, Massachusetts Institute of Technology, 2011. http://hdl.handle.net/1721.1/76523.

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Thesis (S.M.)--Massachusetts Institute of Technology, Dept. of Nuclear Science and Engineering, 2011.
"January 2011." Cataloged from PDF version of thesis.
Includes bibliographical references (p. 110-112).
Historically, unprotected transients have been viewed as design basis events that can significantly challenge sodium-cooled fast reactors. The perceived potential consequences of a severe unprotected transient in a sodium-cooled fast reactor include an energetic core disruptive accident, vessel failure, and a large early release. These consequences can be avoided if unprotected transients are properly defended against, potentially improving the economics of sodium fast reactors. One way to defend against such accidents is to include a highly reliable reactor protection system. The perceived undesirability of the consequences arising from an unprotected transient has led some sodium fast reactor designers to consider incorporating several design modifications to the reactor protection system, including: self-actuated shutdown systems, articulated control rods, and seismic anticipatory scram systems. This study investigates the performance of these systems in sodium fast reactors. To analyze the impact of these proposed design alternatives, a model to analyze plant performance that incorporates uncertainty analysis is developed using RELAP5-3D and the ABR-1000 as the reference design. The performance of the proposed alternatives is analyzed during unprotected loss of flow and unprotected transient overpower scenarios, each exacerbated by a loss of heat sink. The recently developed Technology Neutral Framework is used to contextually rate performance of the proposed alternatives. Ultimately, this thesis offers a methodology for a designer to analyze reactor protection system design efficacy. The principle results of this thesis suggest that when using the Technology Neutral Framework as a licensing framework for a sodium-cooled fast reactor, the two independent scram systems of the ABR- 1000's reactor protection system perform well enough to screen unprotected transients from the design basis. While a regulator may still require consideration of accidents involving the failure of the reactor protection system, these events will not drive the design of the system. However, self-actuated shutdown systems may be called for to diversify the reactor protection system. Of these, the Curie point latch marginally reduces the conditional cladding damage probability for metal cores because of their rapid inherent feedback effects, but is more effective for the more sluggish oxide cores given reasonably long pump coastdown times. Flow levitated absorbers are highly effective at mitigating unprotected loss of flow events for both fuel types, but are limited in response during unprotected transient overpower events. When considered from a risk-informed perspective, a clear rationale and objective is needed to justify the inclusion of an additional feature such as self-actuated shutdown systems. The use of articulated safety rods as one of the diverse means of reactivity insertion and the implementation of an anticipatory seismic scram system may be the most cost-effective alternatives to provide defense in depth in light of the sodium fast reactor's susceptibility to seismic events.
by Jacob D. DeWitte.
S.M.
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2

Pope, Michael A. (Michael Alexander). "Reactor physics design of supercritical CO₂-cooled fast reactors." Thesis, Massachusetts Institute of Technology, 2004. http://hdl.handle.net/1721.1/33633.

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Thesis (S.M.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 2004.
Includes bibliographical references (p. 109-113).
Gas-Cooled Fast Reactors (GFRs) are among the GEN-IV designs proposed for future deployment. Driven by anticipated plant cost reduction, the use of supercritical CO₂ (S-CO₂) as a Brayton cycle working fluid in a direct cycle is evaluated. By using S- CO₂ at turbine inlet conditions of 20 MPa and 550⁰C - 700⁰C, efficiencies between 45% and 50% can be achieved with extremely compact components. Neutronic evaluation of candidate core materials was performed for potential use in block-type matrix fueled GFRs with particular concentration on lowering coolant void reactivity to less than $1. SiC cercer fuel was found to have relatively low coolant void worth (+22 cents upon complete depressurization of S-CO₂ coolant) and tolerable reactivity- limited burnup at matrix volume fractions of 60% or less in a 600 MWth core having H/D of 0.85 and titanium reflectors. Pin-type cores were also evaluated and demonstrated higher kff versus burnup, and higher coolant void reactivity than the SiC cercer cores (+$2.00 in ODS MA956-clad case having H/D of 1).
(cont.) It was shown, however, that S-CO₂ coolant void reactivity could be lowered significantly - to less than $1 - in pin cores by increasing neutron leakage (e.g. lowering the core H/D ratio to 0.625 in a pin core with ODS MA956 cladding), an effect not observed in cores using helium coolant at 8 MPa and 500⁰C. An innovative "block"-geometry tube-in-duct fuel consisting of canisters of vibrationally compacted (VIPAC) oxide fuel was introduced and some preliminary calculations were performed. A reference tube-in-duct core was shown to exhibit favorable neutron economy with a conversion ratio (CR) at beginning of life (BOL) of 1.37, but had a coolant void reactivity of +$ 1.4. The high CR should allow designers to lower coolant void worth by increasing leakage while preserving the ability of the core to reach high burnup. Titanium, vanadium and scandium were found to be excellent reflector materials from the standpoint of ... and coolant void reactivity due to their unique elastic scattering cross-section profiles: for example, the SiC cercer core having void reactivity of +$0.22 with titanium was shown to have +$0.57 with Zr₃Si₂.
(cont.) Overall, present work confirmed that the S-CO₂-cooled GFR concept has promising characteristics and a sufficiently broad opion space such that a safe and competitive design could be developed in future work with considerably less than $1 void reactivity and a controllable [delta]k due to burnup.
by Michael A. Pope.
S.M.
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3

MARTINS, MARIA da P. S. "Estudo de fatores humanos, e observacao dos seus aspectos basicos, focados em operadores do reator de pesquisa IEA-R1, objetivando a prevencao de acidentes ocasionados por falhas humanas." reponame:Repositório Institucional do IPEN, 2008. http://repositorio.ipen.br:8080/xmlui/handle/123456789/11737.

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Dissertação (Mestrado)
IPEN/D
Instituto de Pesquisas Energeticas e Nucleares - IPEN-CNEN/SP
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4

Ahola, J. (Juha). "Reaction kinetics and reactor modelling in the design of catalytic reactors for automotive exhaust gas abatement." Doctoral thesis, University of Oulu, 2009. http://urn.fi/urn:isbn:9789514290305.

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Abstract The tightening environmental legislation and technological development in automotive engineering form a challenge in reactor design of catalytic reactors for automotive exhaust gas abatement. The catalytic reactor is the heart of the exhaust aftertreatment processes, but it can be seen also just as one subsidiary part of vehicles. The aim of this work is to reveal applicable kinetic models to predict behaviour of the particular catalysts and to establish guidelines for modelling procedures and experimentation facilitating catalytic reactor design, especially in the field of automotive exhaust gas abatement. The studies in this thesis include catalyst kinetics with synthetic exhaust gas composition in stoichiometric and net oxidative conditions, DRIFT measurements, and the warm-up of three-way catalysts in real conditions. Knowledge on surface concentrations facilitates kinetic model construction and discrimination. For example, identification of even semi-quantitative surface concentrations may lead to a successful falsification of incorrect kinetic model candidates. Especially, that is clearly seen in cases where models predict the same kind of gas phase behaviour but different kinds of surface concentration profiles. The transient kinetic experiments could give a hint on predominant reaction mechanism, support quantifying of the adsorption capacity and reveal the impact of surface phenomena on reactor dynamics. The level of model complexity should be adapted depending on the purpose of the model. For example, it is mostly convenient for reactor design purposes to perceive only one type of active sites even in a case of mechanical mixture of different catalytic materials; whereas the optimisation of catalyst content demands the management of every prominent site type separately. Or, when a catalytic material has been selected, the stationary kinetic model is, in most cases, adequate for the catalytic converter design and structural optimization for warm-up conditions.
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5

Oliveira, Graca C. de. "Reaction rate studies in a fusion reactor blanket." Thesis, University of Cambridge, 1986. http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.384479.

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6

Nguyen, Hung Viet Flagan Richard C. Flagan Richard C. "Powder production in aerosol reactors : particle structure and reactor optimization /." Diss., Pasadena, Calif. : California Institute of Technology, 1990. http://resolver.caltech.edu/CaltechETD:etd-03122007-105616.

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7

Mandal, A. K. "Reaction and reactor modelling for synthesis of insensitive HEMs." Thesis(Ph.D.), CSIR-National Chemical Laboratory, Pune, 2010. http://dspace.ncl.res.in:8080/xmlui/handle/20.500.12252/3724.

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8

Anadani, Mohamed. "Decision support systems for nuclear reactor control." Thesis, University of Sheffield, 2000. http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.341828.

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9

CARVALHO, RICARDO P. de. "Desenvolvimento de um simulador de treinamento para operadores do reator de pesquisa IEA-R1." reponame:Repositório Institucional do IPEN, 2006. http://repositorio.ipen.br:8080/xmlui/handle/123456789/11445.

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Dissertação (Mestrado)
IPEN/D
Instituto de Pesquisas Energeticas e Nucleares - IPEN-CNEN/SP
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10

DINIZ, RICARDO. "Obtencao das constantes de decaimento e abundancias relativas de neutrons atrasados atraves da analise de ruido em reatores de potencia zero." reponame:Repositório Institucional do IPEN, 2005. http://repositorio.ipen.br:8080/xmlui/handle/123456789/11247.

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Tese (Doutoramento)
IPEN/T
Intituto de Pesquisas Energeticas e Nucleares, IPEN/CNEN-SP
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11

MAI, LUIZ A. "Analise tecnico-economico do ciclo de combustivel 'Tandem'. Um estudo do caso Brasil-Argentina." reponame:Repositório Institucional do IPEN, 1997. http://repositorio.ipen.br:8080/xmlui/handle/123456789/10684.

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Tese (Doutoramento)
IPEN/T
Instituto de Pesquisas Energeticas e Nucleares - IPEN/CNEN-SP
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12

Sommer, Christopher. "Fuel cycle design and analysis of SABR subrcritical advanced burner reactor /." Thesis, Atlanta, Ga. : Georgia Institute of Technology, 2008. http://hdl.handle.net/1853/24720.

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13

Kingdon, David Ross. "Safety characteristics of a suspended-pellet fission reactor system." Thesis, National Library of Canada = Bibliothèque nationale du Canada, 1998. http://www.collectionscanada.ca/obj/s4/f2/dsk1/tape11/PQDD_0001/NQ42856.pdf.

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14

RICCI, FILHO WALTER. "Analise do elemento de irradiacao de berilio no reactor IEA-R1m." reponame:Repositório Institucional do IPEN, 1998. http://repositorio.ipen.br:8080/xmlui/handle/123456789/10707.

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Dissertacao (Mestrado)
IPEN/D
Instituto de Pesquisas Energeticas e Nucleares - IPEN/CNEN-SP
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15

Knight, Daniel William. "Reactor behavior and its relation to chemical reaction network structure." The Ohio State University, 2015. http://rave.ohiolink.edu/etdc/view?acc_num=osu1438274630.

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16

MASOTTI, PAULO H. F. "Desenvolvimento de um cartao digital para simulacao da variacao do periodo em reatores." reponame:Repositório Institucional do IPEN, 1999. http://repositorio.ipen.br:8080/xmlui/handle/123456789/10747.

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Dissertacao [Mestrado]
IPEN/D
Instituto de Pesquisas Energeticas e Nucleares - IPEN/CNEN-SP
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17

Adikesavalu, Ravichandran. "Preliminary modeling of in-duct desulfurization using condensation aerosols." Ohio : Ohio University, 1997. http://www.ohiolink.edu/etd/view.cgi?ohiou1177616476.

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18

Gottfridsson, Filip. "Simulation of Reactor Transient and Design Criteria of Sodium-cooled Fast Reactors." Thesis, Uppsala universitet, Tillämpad kärnfysik, 2010. http://urn.kb.se/resolve?urn=urn:nbn:se:uu:diva-148572.

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The need for energy is growing in the world and the market of nuclear power is now once more expanding. Some issues of the current light-water reactors can be solved by the next generation of nuclear power, Generation IV, where sodium-cooled reactors are one of the candidates. Phénix was a French prototype sodium-cooled reactor, which is seen as a success. Although it did encounter an earlier unexperienced phenomenon, A.U.R.N., in which a negative reactivity transient followed by an oscillating behavior forced an automatic emergency shutdown of the reactor. This phenomenon lead to a lot of downtime of the reactor and is still unsolved. However, the most probable cause of the transients is radial movements of the core, referred to as core-flowering. This study has investigated the available documentation of the A.U.R.N. events. A simplified model of core-flowering was also created in order to simulate how radial expansion affects the reactivity of a sodium-cooled core. Serpent, which is a Monte-Carlo based simulation code, was chosen as calculation tool. Furthermore, a model of the Phénix core was successfully created and partly validated. The model of the core has a k_eff = 1.00298 and a neutron flux of (8.43+-0.02)!10^15 neutrons/cm^2 at normal state. The result obtained from the simulations shows that an expansion of the core radius decreases the reactivity. A linear approximation of the result gave the relation: change in k_eff/core extension = - 60 pcm/mm. This value corresponds remarkably well to the around - 60 pcm/mm that was obtained from the dedicated core-flowering experiments in Phénix made by the CEA. Core-flowering can recreate similar signals to those registered during the A.U.R.N. events, though the absence of trace of core movements in Phénix speaks against this. However, if core-flowering is the sought answer, it can be avoided by design. The equipment that registered the A.U.R.N. events have proved to be insensitive to noise. Though, the high amplitude of the transients and their rapidness have made some researcher believe that the events are a combination of interference in the equipment of Phénix and a mechanical phenomenon. Regardless, the origin of A.U.R.N. seems to be bound to some specific parameter of Phénix due to the fact that the transients only have occurred in this reactor. A safety analysis made by an expert committee, appointed by CEA, showed that the A.U.R.N. events are not a threat to the safety of Phénix. However, the origin of these negative transients has to be found before any construction of a commercial size sodium-cooled fast reactor can begin. Thus, further research is needed.
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19

FERNANDO, ALBERTO de J. "Desenvolvimento e implementação de um novo sistema pneumático de transferência para irradiação de materiais no reator IEA-R1." reponame:Repositório Institucional do IPEN, 2011. http://repositorio.ipen.br:8080/xmlui/handle/123456789/9968.

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Dissertacao (Mestrado)
IPEN/D
Instituto de Pesquisas Energeticas e Nucleares - IPEN-CNEN/SP
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20

CONCEICAO, JUNIOR OSMAR. "Aplicacao da tecnica de analise de modos de falha e efeitos ao sistema de resfriamento de emergencia de uma instalacao nuclear experimental." reponame:Repositório Institucional do IPEN, 2009. http://repositorio.ipen.br:8080/xmlui/handle/123456789/9367.

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Dissertacao (Mestrado)
IPEN/D
Instituto de Pesquisas Energeticas e Nucleares - IPEN-CNEN/SP
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21

ANDRZEJEWSKI, CLAUDIO S. "Avaliação de alternativas de combustível tipo placa para reatores de pequeno porte." reponame:Repositório Institucional do IPEN, 2005. http://repositorio.ipen.br:8080/xmlui/handle/123456789/11364.

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Dissertacao (Mestrado)
IPEN/D
Instituto de Pesquisas Energeticas e Nucleares - IPEN/CNEN-SP
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22

Filippou, Dimitrios. "Reaction kinetics and reactor modelling of zinc-ferrite hot-acid leaching." Thesis, McGill University, 1994. http://digitool.Library.McGill.CA:80/R/?func=dbin-jump-full&object_id=41588.

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The main objectives of this Thesis were the determination of the reaction kinetics of the dissolution of zinc-ferrite particles ((Zn$ sb{1-x}$, Fe$ sbsp{x}{2+}$)$ rm Fe sbsp{2}{3+}O sb4$, x $ le$ 0.4) in hot aqueous solutions of sulphuric acid, and the development of a mathematical model for the prediction of the performance of a series of continuous stirred-tank reactors where zinc ferrite is leached.
Well-characterised, porous zinc-ferrite particles of industrial origin were subjected to controlled leaching experiments at temperatures close to 373 K in sulphuric acid solutions of concentration higher than 0.25mol L$ sp{-1}$. The dissolution process was found to be described most adequately by the grain model with surface reaction being the rate-controlling step. After analysing the experimental results through this model, a unique rate equation for zinc-ferrite dissolution as a function of temperature and solution composition, was obtained.
Based on this rate equation, a mathematical framework was built for the analysis of the start-up and the steady-state of reactor cascades where zinc ferrite is continuously leached. This framework consisted of population-balance and mass-balance equations, which were solved analytically or numerically. Computer simulation results, which were obtained by this reactor model, showed very good agreement with actual industrial data.
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23

Lim, Hankwon. "Studies of the Ethanol Steam Reforming Reaction in a Membrane Reactor." Diss., Virginia Tech, 2007. http://hdl.handle.net/10919/29675.

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The subject of this dissertation is advanced inorganic membranes and their application in membrane reactors (MRs). The reaction studied is the ethanol steam reforming (ESR) reaction using Co-Na/ZnO catalysts, chosen because of their high activity and stability. The Co-Na/ZnO catalysts were prepared by a co-precipitation method and it was found that promotion with a moderate amount of Na (1.0 wt%) produced a catalyst with stable ethanol conversion and product selectivity. Higher cobalt loading, higher W:E ratio, higher reaction temperature, and lower space velocity enhanced the conversion of ethanol to H2 and CO2 while reducing the formation of undesirable acetaldehyde. Acetaldehyde was a primary product of the ESR reaction. Studies of the effect of hydrogen permeance on the ESR reaction at 623 K were performed in MRs equipped with silica-based and palladium-based membranes of different hydrogen permeances, and the highest ethanol conversion enhancement of 44 % and hydrogen molar flow enhancement of 69 % compared to a packed-bed reactor (PBR) were obtained in a MR fitted with a membrane with the highest hydrogen permeance. An operability level coefficient (OLC), defined as the ratio of the hydrogen permeation and hydrogen formation rates, was suggested as a useful tool for estimating performances of MRs for different reforming reactions such as methane dry reforming (MDR), methane steam reforming (MSR), methanol steam reforming (MeSR), and ethanol steam reforming (ESR) reactions. Studies of the effect of pressure (1-10 atm) on the ESR reaction at 623 K were carried out in a PBR and a MR fitted with a Pd-Cu membrane prepared by an electroless plating of palladium and copper at 333 K. Comparison studies showed that increasing pressure in both reactors resulted in decreasing ethanol conversions and increasing hydrogen molar flows. Compared to the PBR, higher ethanol conversions and hydrogen molar flows were obtained in the MR for all pressures studied. Increasing pressure was favorable for enhancing ethanol conversion and hydrogen molar flow in the MR compared to the PBR, and the highest ethanol conversion enhancement of 48 % with the highest hydrogen molar flow enhancement of 55 % was obtained at 10 atm in the MR.
Ph. D.
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24

Tien, Ta-Ching. "Catalytic ignition model in a monolithic reactor with in-depth reaction." Case Western Reserve University School of Graduate Studies / OhioLINK, 1991. http://rave.ohiolink.edu/etdc/view?acc_num=case1059412740.

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25

Serbetcioglu, Serpil. "Mass transfer and catalytic reaction in a three-phase monolith reactor." Thesis, University of Bath, 1993. https://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.332665.

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26

Palfelt, Alexander, Wilhelm Thunberg, and Anders Winka. "Determining the Sensitivity of Reactor Parameters in a Sodium Cooled Fast Reactor." Thesis, Uppsala universitet, Tillämpad kärnfysik, 2020. http://urn.kb.se/resolve?urn=urn:nbn:se:uu:diva-413073.

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The sensitivity of two operational output parameters, criticality and isotopic composition during burnup, to specific design and operational reactor parameters in a Sodium Cooled Fast Reactor, is investigated. The computational simulation tool Serpent is used. The parameters varied include Uranium enrichment, Plutonium content, rod thickness, fuel temperature, and sodium density. In burnup, the development of the fraction of fissile isotopes, isotopes used for measurements, the isotopic composition of Plutonium, and isotopes that complicate fuel reprocessing is displayed. A surrogate model, optimized for use in determining how criticality develops between data points, is used. The results are displayed as plots created in Matlab. The results are discussed, with a focus on how large an effect varying different parameters have on different outputs related to the reactor's operation. It is concluded that the Plutonium content has the largest effect on the isotopic composition and that, based on the performed simulations, MOX fuel is potentially safer than Zirconium alloy fuel in a practical setting.
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27

MACEDO, VAGNER dos S. "Desenvolvimento de uma base de dados computacional para aplicação em Análise Probabilística de Segurança de reatores nucleares de pesquisa." reponame:Repositório Institucional do IPEN, 2016. http://repositorio.ipen.br:8080/xmlui/handle/123456789/27500.

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O objetivo deste trabalho é apresentar a base de dados que foi desenvolvida para armazenar dados técnicos e processar dados sobre operação, falha e manutenção de equipamentos dos reatores nucleares de pesquisa localizados no Instituto de Pesquisas Energéticas e Nucleares (IPEN), em São Paulo - SP. Os dados extraídos desta base poderão ser aplicados na Análise Probabilística de Segurança dos reatores de pesquisa ou em avaliações quantitativas menos complexas relacionadas à segurança, confiabilidade, disponibilidade e manutenibilidade destas instalações. Esta base de dados foi desenvolvida de modo a permitir que as informações nela contidas estejam disponíveis aos usuários da rede corporativa, que é a intranet do IPEN. Os profissionais interessados deverão ser devidamente cadastrados pelo administrador do sistema, para que possam efetuar a consulta e/ou o manuseio dos dados. O modelo lógico e físico da base de dados foi representado por um diagrama de entidades e relacionamento e está de acordo com os módulos de segurança instalados na intranet do IPEN. O sistema de gerenciamento da base de dados foi desenvolvido com o MySQL, o qual utiliza a linguagem SQL como interface. A linguagem de programação PHP foi usada para permitir o manuseio da base de dados pelo usuário. Ao final deste trabalho, foi gerado um sistema de gerenciamento de base de dados capaz de fornecer as informações de modo otimizado e com bom desempenho.
Dissertação (Mestrado em Tecnologia Nuclear)
IPEN/D
Instituto de Pesquisas Energéticas e Nucleares - IPEN-CNEN/SP
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28

MELLO, JOSÉ ROBERTO de. "Regulamentação do sistema elétrico do reator IEA-R1." reponame:Repositório Institucional do IPEN, 2016. http://repositorio.ipen.br:8080/xmlui/handle/123456789/26928.

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O reator IEA-R1 do Instituto de Pesquisas Energéticas e Nucleares (IPENCNEN/ SP) é um reator de pesquisa tipo piscina aberta, projetado e construído pela empresa norte-americana \"Babcock & Wilcox\", tendo, como refrigerante e moderador, água leve deionizada e berílio e grafite como refletores. Até cerca de 1988, os sistemas de segurança do reator recebiam alimentação de uma única fonte de energia. Nos anos de 1989 e 1990, uma reforma de modernização do sistema elétrico para aumentar a potência do reator e, também, para atender às normas técnicas da Comissão Nacional de Energia Nuclear (CNEN) e da Associação Brasileira de Normas Técnicas (ABNT) foi realizada. Este trabalho tem o objetivo de mostrar a relação entre o sistema de energia elétrica e a segurança do reator IEA-R1. Além disso, ele demonstra que, caso ocorra alguma interrupção de energia elétrica durante a operação do reator, esta ocorrência não irá começar um evento de acidente.
Dissertação (Mestrado em Tecnologia Nuclear)
IPEN/D
Instituto de Pesquisas Energéticas e Nucleares - IPEN-CNEN/SP
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29

Bopp, Andrew T. "The calculation of fuel bowing reactivity coefficients in a subcritical advanced burner reactor." Thesis, Georgia Institute of Technology, 2013. http://hdl.handle.net/1853/50295.

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The United States' fleet of Light Water Reactors (LWRs) produces a large amount of spent fuel each year; all of which is presently intended to be stored in a fuel repository for disposal. As these LWRs continue to operate and more are built to match the increasing demand for electricity, the required capacity for these repositories grows. Georgia Tech's Subcritical Advanced Burner Reactor (SABR) has been designed to reduce the capacity requirements for these repositories and thereby help close the back end of the nuclear fuel cycle by burning the long-lived transuranics in spent nuclear fuel. SABR's design is based heavily off of the Integral Fast Reactor (IFR). It is important to understand whether the SABR design retains the passive safety characteristics of the IFR. A full safety analysis of SABR's transient response to various possible accident scenarios needs to be performed to determine this. However, before this safety analysis can be performed, it is imperative to model all components of the reactivity feedback mechanism in SABR. The purpose of this work is to develop a calculational model for the fuel bowing reactivity coefficients that can be used in SABR's future safety analysis. This thesis discusses background on fuel bowing and other reactivity coefficients, the history of the IFR, the design of SABR, describes the method that was developed for calculating fuel bowing reactivity coefficients and its validation, and presents an example of a fuel bowing reactivity calculation for SABR.
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30

Wojcik, Adam Gabriel. "A versatile MOCVD reactor." Thesis, Imperial College London, 1989. http://hdl.handle.net/10044/1/47718.

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31

Bondarenko, О. О. "International thermonuclear experimental reactor." Thesis, Сумський державний університет, 2012. http://essuir.sumdu.edu.ua/handle/123456789/28681.

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ITER (originally an acronym of International Thermonuclear Experimental Reactor) is an international nuclear fusion research and engineering project, which is currently building the world's largest and most advanced experimental tokamak nuclear fusion reactor at Cadarache in the south of France. When you are citing the document, use the following link http://essuir.sumdu.edu.ua/handle/123456789/28681
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32

Stewart, Christopher L. "Investigation of fuel cycle for a sub-critical fusion-fission hybrid breeder reactor." Thesis, Georgia Institute of Technology, 2013. http://hdl.handle.net/1853/50407.

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The SABR fusion-fission hybrid concept for a fast burner reactor, which combines the IFR-PRISM fast reactor technology and the ITER tokamak physics and fusion technology, is adapted for a fusion-fission hybrid reactor, designated SABrR. SABrR is a sodium-cooled 3000 MWth reactor fueled with U-Pu-10Zr. For the chosen fuel and core geometry, two configurations of neutron reflector and tritium breeding structures are investigated: one which emphasizes a high tritium production rate and the other which emphasizes a high fissile production rate. Neutronics calculations are performed using the ERANOS 2.0 code package, which was developed in order to model the Phenix and SuperPhenix reactors. Both configurations are capable of producing fissile breeding ratios of about 1.3 while producing enough tritium to remain tritium-self-sufficient throughout the burnup cycle; in addition, the major factors which limit metal fuel residence time, fuel burnup and radiation damage to the cladding material, are modest.
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33

Nachaiyasit, Suyanee. "The effect of process parameters on reactor performance in an anaerobic baffled reactor." Thesis, Imperial College London, 1995. http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.481427.

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34

Ledgerwood, Jonathan Patrick. "Reaction phenomena of iron oxide leaching in an evaporative acid bake reactor." Master's thesis, University of Cape Town, 2012. http://hdl.handle.net/11427/10850.

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Includes abstract.
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Namakwa Sands is a heavy mineral mining and beneficiation business within Tronox, and produces two major products, zircon (zr02.Si02 99.9%) and rutile (Ti02 99.9%) at a combined annual rate of 140kt. The heavy mineral concentrates are exported to international markets to make specialist coatings for the paints and ceramics industries. The ceramic industry is very strict on the purity of the minerals used. Namakwa Sands prides itself in being able to produce zircon and rutile at these requirements; however, strict requirements, especially in terms of Fe impurities (Fe203 content in zircon concentrate must be < 600ppm), limit the productivity and come at a cost to recovery. The concentration and separation of heavy minerals is a complex process, which utilizes conductivity differences between minerals. Zircon coated with iron oxides (Fe203, FeOOH) reports as more conductive during electrostatic separation, which can result in a zircon particle to behave like a rutile particle and in this way cause both products (rutile and zircon) to become off specification.
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35

Sivena, Anastassia. "Hydrocracking reaction pathways of 1-methylnaphthalene in a continous fixed-bed reactor." Thesis, Imperial College London, 2014. http://hdl.handle.net/10044/1/29868.

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Trends in the crude oil supply have shown a decline in reserves of conventional oil, which has been offset by increasing volumes of heavy oil. Therefore, hydrocracking has become an increasingly attractive process for upgrading heavy oil fractions. This process, however, presents major challenges that have to be overcome. The present work had two principal aims. The first was to develop a new continuous fixed-bed hydrocracking reactor (CFBR) to conduct long time-on-stream experiments, ranging from 180-360 minutes. Several challenges were faced during the design and construction caused by operating conditions constraints. Factors such as safety and effective control of the system were also taken into consideration. The second was to study hydrocracking experiments at different operating conditions performed in the CFBR. These were carried out with a model compound, 1-methylnaphthalene (C11-1MN) and a commercial catalyst, NiMo/Al2O3. Three residence times (1, 10, 20 minutes) and four temperatures (400, 420, 430 and 450 °C) were used, while keeping pressure constant at 10 MPa. Four main groups of products prevailed: partially hydrogenated bicyclic products, hydrogenated bicyclic products, ring-opening products and cracked products. Each group was further divided in alkyl and alkenyl benzenes, alkyl cyclohexane and decalin. The reaction pathway consisted of a mixture of parallel and consecutive reactions. The activation energy for the decomposition of C11-1MN was obtained with the Arrhenius equation. The overall selectivity of partially hydrogenated products and ring-opening products were mirrored and the overall selectivity for cracked products decreased with increasing temperature. The selectivity of hydrogenated products was very low. The effect of the sulphiding agent, diheptyl disulphide (DHDS) present in the feed, was elucidated on the activation of the catalyst. A decrease in sulphur concentration in products was coupled with a noticeable increase in C11-1MN conversion. Finally, the role of DHDS decomposition products in catalyst activation was investigated.
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36

Saw, Shuey Zi. "Design, Optimization, and Control of Membrane Reactor for Water-Gas Shift Reaction." Thesis, Curtin University, 2017. http://hdl.handle.net/20.500.11937/59694.

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In this study, the overall goal is to design, optimize and control a novel WGSR-MR system via process engineering approach. The main contributions of the study include: a new intensified process design of WGSR-MR system with good economic and dynamic controllability performances, a new simultaneous optimization methodology to address trade-off between the steady-state economic and dynamic controllability performances, and a new complete design procedure for triple-loop parallel cascade PID control strategy.
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37

SILVEIRA, RENATO C. da. "Avaliacao da estabilidade estrutural de contencoes metalicas de centrais nucleares." reponame:Repositório Institucional do IPEN, 2000. http://repositorio.ipen.br:8080/xmlui/handle/123456789/10795.

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Dissertacao (Mestrado)
IPEN/D
Instituto de Pesquisas Energeticas e Nucleares - IPEN/CNEN-SP
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38

ARONNE, IVAN D. "Desenvolvimento de um sistema de identificacao e classificacao de transientes para um reator nuclear a agua pressurizada integral." reponame:Repositório Institucional do IPEN, 2009. http://repositorio.ipen.br:8080/xmlui/handle/123456789/9380.

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Tese (Doutoramento)
IPEN/T
Instituto de Pesquisas Energeticas e Nucleares - IPEN-CNEN/SP
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39

Aworinde, Samson Mayowa. "The control of selectivity in partial oxidation of hydrocarbons." Thesis, University of Cambridge, 2018. https://www.repository.cam.ac.uk/handle/1810/276367.

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40

Novick, Vincent John. "Aerosol measurement techniques developed for nuclear reactor accident simulations /." Thesis, Connect to this title online; UW restricted, 1989. http://hdl.handle.net/1773/10112.

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41

Shih, Chuan-Cheng. "The internal circulation of the adjacent fluidized bed reactor." Ohio : Ohio University, 1989. http://www.ohiolink.edu/etd/view.cgi?ohiou1182516493.

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42

Anderson, Jonathan Kristofer. "Experimental studies of high-speed liquid films on downward-facing surfaces for IFE applications." Thesis, Georgia Institute of Technology, 2002. http://hdl.handle.net/1853/19685.

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43

PORFIRIO, ROGILSON N. da S. "Modelagem e simulacao do termo-fonte radioativo de produtos de fissao em reatores nucleares do tipo PWR." reponame:Repositório Institucional do IPEN, 1996. http://repositorio.ipen.br:8080/xmlui/handle/123456789/10450.

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Dissertacao (Mestrado)
IPEN/D
Instituto de Pesquisas Energeticas e Nucleares - IPEN/CNEN-SP
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44

Nuwayhid, Rida Y. "Assessment of thermal and fast reactor designs based upon the advance gas-cooled reactor." Thesis, Imperial College London, 1989. http://hdl.handle.net/10044/1/47595.

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45

Hetherington, Andrew. "Characterisation of reactor graphite to inform strategies for the disposal of reactor decommissioning waste." Thesis, University of Birmingham, 2013. http://etheses.bham.ac.uk//id/eprint/4409/.

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Graphite has been used extensively in UK reactors since the 1950s. The UK nuclear decommissioning programme will result in some 90,000 tonnes of waste graphite being removed from Magnox, AGR, research reactors and plutonium production reactors. It is necessary to understand the radiological characteristics of reactor graphite as a prerequisite for decisions about its interim management as well as final disposition. There is in particular a need to improve confidence in the disposal inventory of the long-lived radionuclides carbon-14 and chlorine-36. Models have been developed to predict the distribution of principal radionuclides for Chapelcross reactor 1 and Wylfa reactor 1, and the calculated inventory compared with published experimental measurements on active samples. The models show good agreement with experimental values for carbon-14 and cobalt-60. However, for the highly mobile and volatile radionuclides chlorine-36 and tritium agreement is poor. The models provide a crude upper limit on the inventory, but certain radionuclides may be released during irradiation. For Wylfa it is predicted that all graphite waste arisings will be ILW. For Chapelcross of the order of 16% of the graphite core may be classified as LLW after the C&M period, but levels of carbon-14 rule out disposal to the LLWR facility.
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46

Yarsky, Peter. "Core design and reactor physics of a breed and burn gas-cooled fast reactor." Thesis, Massachusetts Institute of Technology, 2005. http://hdl.handle.net/1721.1/34650.

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Thesis (Ph. D.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 2005.
Includes bibliographical references (p. 245-248).
In order to fulfill the goals set forth by the Generation IV International Forum, the current NERI funded research has focused on the design of a Gas-cooled Fast Reactor (GFR) operating in a Breed and Burnm (B&B) fuel cycle mode. B&B refers to a once-through fuel cycle where low enriched uranium (less than 5 w/o 235U in U) subcritical assemblies are loaded into the core in equilibrium, yet in-situ plutonium breeding carries the fuel through a discharge burnup on the order of 150 MWD/kgHM. The B&B fuel cycle meets the GenIV goals of sustainability, economics, and proliferation resistance by increasing fuel burnup without the need for spent fuel reprocessing, recycle, or reuse of any kind. The neutronic requirements for B&B are strict and require an ultra-hard neutron spectrum. Therefore, the GFR is ideally suited for this fuel cycle. In the present work the B&B GFR concept evolved into two practical reactor designs, both of which build on extensive previous gas-cooled reactor design experience. The first version is the "demonstration" concept using highly neutronically reactive U15N fuel in a hexagonal pin fuel array that is nearly 50 v/o fuel. The core is helium cooled, with an outlet temperature of 570 °C.
The helium primary circuit is coupled to a steam Rankine power conversion system essentially identical to that for the British Advanced Gas-cooled Reactors. One advantage of the low coolant temperature compared to other GenIV GFR concepts is that it allows for the use of oxide dispersion strengthened stainless steels (ODS) in core. The fuel is manufactured using advanced vibration compaction techniques, clad in ODS, and vented in order to achieve the high burnup goal. The second version, the "advanced" concept builds on the experience of the demonstration concept to develop a B&B GFR without the need for expensive U'5N fuel. In order to substitute the nitride fuel with carbide, significantly higher heavy metal loadings are required (60 v/o fuel for UC versus 50 v/o fuel for U'5N) which are not practically achievable with a conventional pin fuel array. Therefore, an innovative tube-in-duct assembly design was proposed to achieve B&B operation with the less neutronically reactive carbide fuel. The advanced core offers significantly reduced natural uranium requirements and lower equilibrium fuel cycle costs (5 mills/kWhre) compared with conventional light water reactors (7 mills/kWhre), as the burnup is tripled for the same reload enrichment.
(cont.) The B&B GFR designs, though requiring active decay heat removal, are semi-self-regulating from a reactivity feedback standpoint and are designed to withstand all plausible accident scenarios, including loss of flow, loss of heat sink, and transient overpower all without scram. Reactor pressure vessel blowdown (LOCA) was investigated and while the B&B GFR has a low positive coolant void reactivity (less than 1$), the added reactivity during blowdown is compensated through other strong negative reactivity feedback mechanisms, thereby allowing for the safe operation of the B&B GFR.
by Peter Yarsky.
Ph.D.
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47

Nie, Markus. "Temporary melt retention in the reactor pit of the European pressurized water reactor (EPR)." [S.l. : s.n.], 2005. http://www.bsz-bw.de/cgi-bin/xvms.cgi?SWB11759373.

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48

Wei, Hong-Chan. "Reactor cavity cooling system heat removal analysis for a high temperature gas cooled reactor." [Gainesville, Fla.] : University of Florida, 2009. http://purl.fcla.edu/fcla/etd/UFE0024427.

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49

Mansfield, Jonathan Mark. "Reaction behaviour from temperature dynamics." Thesis, University of Nottingham, 1997. http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.339552.

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50

MARTINS, MAURO O. "Desenvolvimento de sistema computacional para planejamento e controle da manutenção do reator IEA-R1." reponame:Repositório Institucional do IPEN, 2015. http://repositorio.ipen.br:8080/xmlui/handle/123456789/23822.

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Dissertação (Mestrado em Tecnologia Nuclear)
IPEN/D
Instituto de Pesquisas Energeticas e Nucleares - IPEN-CNEN/SP
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