Neutronics and Thermal-Hydraulics Safety Related Investigations of an Innovative Boron-Free Core Integrated Within a Generic Small Modular Reactor
- Location
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Deutsche Nationalbibliothek Frankfurt am Main
- Extent
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Online-Ressource
- Language
-
Englisch
- Notes
-
Karlsruhe, Karlsruher Institut für Technologie (KIT), Dissertation, 2019
- Classification
-
Ingenieurwissenschaften und Maschinenbau
- Keyword
-
Boron
Thermal hydraulics
Investigations
- Event
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Veröffentlichung
- (where)
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Karlsruhe
- (who)
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KIT-Bibliothek
- (when)
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2019
- Creator
- Contributor
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Stieglitz, R.
- DOI
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10.5445/IR/1000099483
- URN
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urn:nbn:de:101:1-2019111312012932544529
- Rights
-
Der Zugriff auf das Objekt ist unbeschränkt möglich.
- Last update
-
15.08.2025, 7:22 AM CEST
Data provider
This object is provided by:
Deutsche Nationalbibliothek. If you have any questions about the object, please contact the data provider.
Deutsche Nationalbibliothek. If you have any questions about the object, please contact the data provider.
Associated
- Alzaben, Yousef Ibrahim
- Stieglitz, R.
- KIT-Bibliothek
Time of origin
- 2019
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High Fidelity Monte Carlo Based Reactor Physics Calculations
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Advanced Reactor Physics Methods for Transient Analysis of Boiling Water Reactors
Advanced High-Fidelity Reactor Simulators Based on Neutron Transport and Subchannel Methodologies
Neutron Transport in Hexagonal Reactor Cores Modeled by Trigonal-Geometry Diffusion and Simplified P3 Nodal Methods
Experimental Study on Deuterium Extraction from Liquid Pb-Li with the Vacuum Sieve Tray Technique for the European DEMO Fusion Reactor
Computational approaches for nuclear design analyses of the stellarator power reactor HELIAS
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Advanced Methodology to Simulate Boiling Water Reactor Transient Using Coupled Thermal-Hydraulic/Neutron-Kinetic Codes
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Improvements in Multi-physics and Multi-scale Methodologies for Safety-related Investigations of Pressurized Water Reactors within the NURESIM Platform
Development of a Coupled Neutronics/Thermal-Hydraulics/Fuel Thermo-Mechanics Multiphysics Tool for Best-Estimate PWR Core Simulations
High Fidelity Monte Carlo Based Reactor Physics Calculations
Development of CFD Thermal Hydraulics and Neutron Kinetics Coupling Methodologies for the Prediction of Local Safety Parameters for Light Water Reactors
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Advanced High-Fidelity Reactor Simulators Based on Neutron Transport and Subchannel Methodologies
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