Search for dissertations about: "reactor safety analysis"
Showing result 1 - 5 of 35 swedish dissertations containing the words reactor safety analysis.
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1. Assessment and improvements of thermal-hydraulic correlations and methods for the analysis of the Jules Horowitz Reactor
Abstract : Nuclear research reactors are used to test materials for current and future nuclear technologies, and to produce radioisotopes for medical purposes. Most of the existing Material Testing Reactors in Europe have operated for more than 50 years and new ones are needed. READ MORE
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2. 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
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3. Uncertainty and Sensitivity Analysis Applied to the Validation of BWR Bundle Thermal-Hydraulic Calculations
Abstract : In recent years, more realistic safety analyses of nuclear reactors have been based on best estimate (BE) computercodes. The need to validate and refine BE codes that are used in the predictions of relevant reactor safetyparameters, led to the organization of international benchmarks based on high quality experimental data. READ MORE
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4. Development of an Improved Thermal-Hydraulic Modeling of the Jules Horowitz Reactor
Abstract : The newest European high performance material testing reactor, the Jules Horowitz Reactor, is under construction at CEA Cadarache research center in France. The reactor will support existing and future nuclear reactor technologies, with the first criticality expected at the end of this decade. READ MORE
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5. Thermo-mechanical Assessment of Reactor Pressure Vessels of Light Water Reactors During Severe Accidents
Abstract : The reactor pressure vessel (RPV) is one of the crucial safety barriers designed to isolate the reactor core, safeguarding against potential radioactive releases into the environment during a severe accident. The assessment of RPV behaviour and its failure is necessary to predict the characteristics of melt release into the reactor pit and succeeding ex-vessel accident progression. READ MORE