Sökning: "nuclear reactor safety"
Visar resultat 1 - 5 av 58 avhandlingar innehållade orden nuclear reactor safety.
1. Effective Spatial Mapping for Coupled Code Analysis of Thermal–Hydraulics/Neutron–Kinetics of Boiling Water Reactors
Sammanfattning : Analyses of nuclear reactor safety have increasingly required coupling of full three dimensional neutron kinetics (NK) core models with system transient thermal–hydraulics (TH) codes. In order to produce results within a reasonable computing time, the coupled codes use two different spatial description of the reactor core. LÄS MER
2. Streams, Steams, and Steels : A Transnational History of Risk Regulation in Nuclear Power Plants (1850–1985)
Sammanfattning : Water is essential to produce nuclear energy and prevent nuclear disasters. As light water reactors are increasingly seen as a solution to achieving a sustainable energy transition and battling the climate crisis, it is more important than ever to investigate the risks of using water for nuclear power production. LÄS MER
3. Structural integrity of prestressed nuclear reactor containments
Sammanfattning : A nuclear power plant is provided with an extensive defense intended to prevent radioactive discharge in case of a reactor accident. This defense is built up of several independent safety barriers, where the reactor containment constitutes the last barrier to the environment. LÄS MER
4. Accelerator-driven systems : safety and kinetics
Sammanfattning : The accelerator-driven system (ADS) is recognized as a promising system for the purpose of nuclear waste transmutation and minimization of spent fuel radiotoxicity. The primary cause for this derives from its accelerator-driven, sub-critical operating state, which introduces beneficial safety-related features allowing for application of cores employing fuel systems containing pure transuranics or minor actinides, thereby offering increased incineration rate of waste products and minimal deployment of advanced (and expensive) partitioning and transmutation technologies. LÄS MER
5. Inherent Safety Features and Passive Prevention Approaches for Pb/Bi-cooled Accelerator-Driven Systems
Sammanfattning : This thesis is devoted to the investigation of passivesafety and inherent features of subcritical nucleartransmutation systems - accelerator-driven systems. The generalobjective of this research has been to improve the safetyperformance and avoid elevated coolant temperatures inworst-case scenarios like unprotected loss-of-ow accidents,loss-of-heat-sink accidents, and a combination of both theseaccident initiators. LÄS MER