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Dissertations / Theses on the topic 'Neutronics and thermal-hydraulics coupling'

Author: Grafiati

Published: 9 March 2023

Last updated: 31 July 2025

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1

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.

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Le sujet de la thèse s'inscrit dans le cadre de la rénovation des outils et des méthodes de calculs appliqués aux accidents graves des Réacteurs à Neutrons Rapides refroidis au Sodium (RNR-Na). En particulier, on s'intéresse aux biais et conservatismes liés à la méthodologie de calculs de la phase primaire d'un accident grave. Pour évaluer les conséquences d'un accident de fusion du coeur d'un RNR-Na, une approche déterministe est généralement réalisée en considérant des hypothèses dites "best-estimate". Cette approche repose sur l'utilisation de codes informatiques pour simuler numériquement

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2

Faucher, 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.

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Dans le contexte de la physique des réacteurs, l’analyse du comportement non stationnaire de la population neutronique avec contre-réactions dans le combustible et dans le modérateur se rend indispensable afin de caractériser les transitoires opérationnels et accidentels dans les systèmes nucléaires et d’en améliorer par conséquent la sûreté. Pour ces configurations non stationnaires, le développement de méthodes Monte-Carlo qui prennent en compte la dépendance en temps du système neutronique, mais aussi le couplage avec les autres physiques, comme la thermohydraulique et la thermomécanique, a

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3

CHIESA, 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.

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In recent years, many computer codes, based on Monte Carlo methods or deterministic calculations, have been developed to separately analyze different aspects regarding nuclear reactors. Nuclear reactors are very complex systems, which require an integrated analysis of all the variables which are intrinsically correlated: neutron fluxes, reaction rates, neutron moderation and absorption, thermal and power distributions, heat generation and transfer, criticality coefficients, fuel burnup, etc. For this reason, one of the main challenges in the analysis of nuclear reactors is the coupling o

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4

Waata, 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.

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5

Waata, 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.

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6

Waata, 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.

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7

Waata, 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.

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8

Basualdo, 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.

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9

Silva, 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/.

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Advanced computational tools are applied to simulate a nuclear power plant (NPP) control rod assembly ejection (CRE) accident. The impact of these reactivity-initiated accidents (RIAs) on core reactivity behavior, 3D power distribution and stochastic reactivity estimation are evaluated. The three tools used are: the thermal-hydraulic (TH) RELAP5 (R5) code, the neutronic (NK) PARCS (P3D) code, and the coupled version P3D/R5, with specially developed linkage using the environment code MATLAB. This study considers three different-size cores: NPP1 (2772 MWt); NPP2 (530 MWt); and NPP3 (1061 MWt). T

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10

Alzaben, 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.

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11

Peltonen, 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.

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12

ALIKANIOTIS, KATIA. "Combined tumour treatment by coupling conventional radiotherapy to an additional dose contribution from thermal neutrons." Doctoral thesis, Università degli Studi di Trieste, 2019. http://hdl.handle.net/11368/2936426.

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Aim: To employ the thermal neutron background in conventional X-rays radiotherapy treatments in order to add a localized neutron dose boost to the patient, enhancing the treatment effectiveness. Background: Conventional linear accelerators for radiotherapy produce fast secondary neutrons with a mean energy of about 1 MeV due to (γ, n) reaction. This neutron field, isotropically distributed, is considered as an extra unaccounted dose during the treatment. Moreover, considering the moderating effect of human body, a thermal neutron field is localized in the tumour area: this neutron background

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13

Peréz, 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.

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14

Lázaro, 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.

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El Generation IV International Forum (GIF) [1] es un programa internacional dedicado a apoyar, coordinar y dirigir las iniciativas de investigación y desarrollo encaminados a implementar las soluciones tecnológicas que caracterizarán a la siguiente generación de reactores nucleares. Estos reactores se caracterizaran por una gestión más eficiente del combustible nuclear, un incremento en las exigencias de seguridad y una alta competitividad económica. Con tales objetivos, GIF propuso una serie de diseños potencialmente capaces de alcanzarlos. Estos diseños son tecnológicamente muy distintos a

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15

Fabbris, 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.

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La conception du coeur d’un réacteur nucléaire est fortement multidisciplinaire (neutronique, thermo-hydraulique, thermomécanique du combustible, physique du cycle, etc.). Le problème est aussi de type multi-objectif (plusieurs performances) à grand nombre de dimensions (plusieurs dizaines de paramètres de conception).Les codes de calculs déterministes utilisés traditionnellement pour la caractérisation des coeurs demandant d’importantes ressources informatiques, l’approche de conception classique rend difficile l’exploration et l’optimisation de nouveaux concepts innovants. Afin de pallier ce

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16

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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17

Grundmann, 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.

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DYN3D is an best estimate advanced code for the three-dimensional simulation of steady-states and transients in light water reactor cores with quadratic and hexagonal fuel assemblies. Burnup and poison-dynamic calculations can be performed. For the investigation of wide range transients, DYN3D is coupled with system codes as ATHLET and RELAP5. The neutron kinetic model is based on the solution of the three-dimensional two-group neutron diffusion equation by nodal expansion methods. The thermal-hydraulics comprises a one- or two-phase coolant flow model on the basis of four differential balanc

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18

Grundmann, 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.

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DYN3D is an best estimate advanced code for the three-dimensional simulation of steady-states and transients in light water reactor cores with quadratic and hexagonal fuel assemblies. Burnup and poison-dynamic calculations can be performed. For the investigation of wide range transients, DYN3D is coupled with system codes as ATHLET and RELAP5. The neutron kinetic model is based on the solution of the three-dimensional two-group neutron diffusion equation by nodal expansion methods. The thermal-hydraulics comprises a one- or two-phase coolant flow model on the basis of four differential balanc

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19

Hu, Po. "Coupled neutronics/thermal-hydraulics analyses of supercritical water reactor." 2008. http://www.library.wisc.edu/databases/connect/dissertations.html.

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20

Breitkreutz, Harald [Verfasser]. "Coupled neutronics and thermal hydraulics of high density cores for FRM II / Harald Breitkreutz." 2011. http://d-nb.info/1011059835/34.

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21

Chuang, 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.

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碩士<br>國立清華大學<br>核子工程與科學研究所<br>104<br>Molten salt reactor (MSR) is one of the generation IV reactor which fuel is liquid phase state of molten salt fluorides. MSRs are distinguished by the circulation of fluid fuel in and out of reactor cores, which provides unique advantages for innovative applications, such as fuel addition, fission products removal. However, these features complicate neutronics analyses because of online reprocessing and fuel mixing. The goal of this research is to establish the Neutronics and Thermal-Hydraulics coupled calculation procedures, and to take fuel depletion, cir

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22

Tai, 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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