Search for dissertations about: "core melt pool"
Showing result 1 - 5 of 12 swedish dissertations containing the words core melt pool.
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1. The Effective Convectivity Model for Simulation and Analysis of Melt Pool Heat Transfer in a Light Water Reactor Pressure Vessel Lower Head
Abstract : Severe accidents in a Light Water Reactor (LWR) have been a subject of intense research for the last three decades. The research in this area aims to reach understanding of the inherent physical phenomena and reduce the uncertainties in their quantification, with the ultimate goal of developing models that can be applied to safety analysis of nuclear reactors, and to evaluation of the proposed accident management schemes for mitigating the consequences of severe accidents. READ MORE
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2. Development, validation and application of an effective convectivity model for simulation of melt pool heat transfer in a light water reactor lower head
Abstract : Severe accidents in a Light Water Reactor (LWR) have been a subject of the research for the last three decades. The research in this area aims to further understanding of the inherent physical phenomena and reduce the uncertainties surrounding their quantification, with the ultimate goal of developing models that can be applied to safety analysis of nuclear reactors. READ MORE
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3. Melt-water interactions in a reactor containment : from integrated assesment to phenomenological studies
Abstract : This thesis examines melt-water interactions for theex-vessel phase of a severe reactor accident. The studies startfrom the development of an assessment methodology that tiestogether the vessel melt release scenarios and the mainprocesses affecting the melt-water interaction effects in thereactor containment. READ MORE
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4. An Experimental Study on Melt Fragmentation, Oxidation and Steam Explosion during Fuel Coolant Interactions
Abstract : Nordic type boiling water reactors (BWRs) adopt reactor cavity flooding as a severe accident mitigation strategy (SAMS) to achieve core melt fragmentation and long-term cooling of decay heat generating core debris. The qualification of this SAMS needs to address two main severe accident issues: debris bed coolability and steam explosion. READ MORE
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5. Analysis methodology for RBMK-1500 core safety and investigations on corium coolabiblty during a LWR sever accidnet
Abstract : This thesis presents the work involving two broad aspectswithin the field of nuclear reactor analysis and safety. Theseare: - development of a fully independent reactor dynamics andsafety analysis methodology of the RBMK-1500 core transientaccidents and - experiments on the enhancement of coolabilityof a particulate bed or a melt pool due to heat removal throughthe control rod guide tubes. READ MORE