Dissertations / Theses on the topic 'Neutronics and thermal-hydraulics coupling'
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Guyot, Maxime. "Neutronics and thermal-hydraulics coupling : some contributions toward an improved methodology to simulate the initiating phase of a severe accident in a sodium fast reactor." Thesis, Aix-Marseille, 2014. http://www.theses.fr/2014AIXM4345.
Full textFaucher, Margaux. "Coupling between Monte Carlo neutron transport and thermal-hydraulics for the simulation of transients due to reactivity insertions." Thesis, Université Paris-Saclay (ComUE), 2019. http://www.theses.fr/2019SACLS387/document.
Full textCHIESA, DAVIDE. "Development and experimental validation of a Monte Carlo simulation model for the Triga Mark II reactor." Doctoral thesis, Università degli Studi di Milano-Bicocca, 2014. http://hdl.handle.net/10281/50064.
Full textWaata, Christine Lylin. "Coupled neutronics, thermal-hydraulics analysis of a high-performance light-water reactor fuel assembly." Karlsruhe : FZKA, 2006. http://bibliothek.fzk.de/zb/berichte/FZKA7233.pdf.
Full textWaata, Christine Lylin. "Coupled neutronics, thermal hydraulics analysis of a high-performance light water reactor fuel assembly." Karlsruhe FZKA, 2005. http://bibliothek.fzk.de/zb/berichte/FZKA7233.pdf.
Full textWaata, Christine Lylin [Verfasser], and Eckart [Akademischer Betreuer] Laurien. "Coupled neutronics thermal hydraulics analysis of a high-performance light-water reactor fuel assembly / Christine Lylin Waata. Betreuer: Eckart Laurien." Stuttgart : Universitätsbibliothek der Universität Stuttgart, 2006. http://d-nb.info/1081642378/34.
Full textWaata, Christine Lylin [Verfasser]. "Coupled neutronics, thermal hydraulics analysis of a high-performance light water reactor fuel assembly / Kernforschungszentrum Karlsruhe GmbH, Karlsruhe. Christine Lylin Waata." Karlsruhe : FZKA, 2006. http://d-nb.info/982286341/34.
Full textBasualdo, Perelló Joaquín Rubén [Verfasser], and R. [Akademischer Betreuer] Stieglitz. "Development of a Coupled Neutronics/Thermal-Hydraulics/Fuel Thermo-Mechanics Multiphysics Tool for Best-Estimate PWR Core Simulations / Joaquín Rubén Basualdo Perelló ; Betreuer: R. Stieglitz." Karlsruhe : KIT-Bibliothek, 2020. http://d-nb.info/1220359068/34.
Full textSilva, Rodney Aparecido Busquim e. "Implications of advanced computational methods for reactivity initiated accidents in nuclear reactors." Universidade de São Paulo, 2015. http://www.teses.usp.br/teses/disponiveis/3/3139/tde-20072016-142605/.
Full textAlzaben, Yousef Ibrahim [Verfasser], and R. [Akademischer Betreuer] Stieglitz. "Neutronics and Thermal-Hydraulics Safety Related Investigations of an Innovative Boron-Free Core Integrated Within a Generic Small Modular Reactor / Yousef Ibrahim Alzaben ; Betreuer: R. Stieglitz." Karlsruhe : KIT-Bibliothek, 2019. http://d-nb.info/1199459127/34.
Full textPeltonen, Joanna. "Development of effective algorithm for coupled thermal-hydraulics : neutron-kinetics analysis of reactivity transient." Licentiate thesis, Stockholm : Skolan för teknikvetenskap, Kungliga Tekniska högskolan, 2009. http://urn.kb.se/resolve?urn=urn:nbn:se:kth:diva-11033.
Full textPeréz, Mañes Jorge [Verfasser], and R. [Akademischer Betreuer] Stieglitz. "Development of CFD Thermal Hydraulics and Neutron Kinetics Coupling Methodologies for the Prediction of Local Safety Parameters for Light Water Reactors / Jorge Peréz Mañes. Betreuer: R. Stieglitz." Karlsruhe : KIT-Bibliothek, 2013. http://d-nb.info/1045663654/34.
Full textLázaro, Chueca Aurelio. "Development, assessment and application of computational tools for design safety analysis of liquid metal cooled fast breeder reactors." Doctoral thesis, Universitat Politècnica de València, 2014. http://hdl.handle.net/10251/39353.
Full textFabbris, Olivier. "Optimisation multi-physique et multi-critère des coeurs de RNR-Na : application au concept CFV." Thesis, Grenoble, 2014. http://www.theses.fr/2014GRENI055/document.
Full textAlam, 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.
Full textGrundmann, Ulrich, Ulrich Rohde, Siegfried Mittag, and Sören Kliem. "DYN3D version 3.2 - code for calculation of transients in light water reactors (LWR) with hexagonal or quadratic fuel elements - description of models and methods -." Forschungszentrum Dresden, 2010. http://nbn-resolving.de/urn:nbn:de:bsz:d120-qucosa-28604.
Full textGrundmann, Ulrich, Ulrich Rohde, Siegfried Mittag, and Sören Kliem. "DYN3D version 3.2 - code for calculation of transients in light water reactors (LWR) with hexagonal or quadratic fuel elements - description of models and methods -." Forschungszentrum Rossendorf, 2005. https://hzdr.qucosa.de/id/qucosa%3A21687.
Full textHu, Po. "Coupled neutronics/thermal-hydraulics analyses of supercritical water reactor." 2008. http://www.library.wisc.edu/databases/connect/dissertations.html.
Full textBreitkreutz, Harald [Verfasser]. "Coupled neutronics and thermal hydraulics of high density cores for FRM II / Harald Breitkreutz." 2011. http://d-nb.info/1011059835/34.
Full textChuang, Chun Hao, and 莊鈞皓. "3D Coupled Neutronics/Thermal-Hydraulics Analyses for a Simple Natural Convection Molten Salt Reactor." Thesis, 2016. http://ndltd.ncl.edu.tw/handle/72127922160307730838.
Full textTai, Cheng-Kai, and 戴承楷. "Neutronic and Thermal-hydraulic Coupling Study on High Temperature Gas-cooled Reactor." Thesis, 2017. http://ndltd.ncl.edu.tw/handle/4vasjv.
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