Search for dissertations about: "THERMAL HYDRAULIC SAFETY NUCLEAR"

Showing result 1 - 5 of 13 swedish dissertations containing the words THERMAL HYDRAULIC SAFETY NUCLEAR.

2. 1. Accelerator-driven systems : safety and kinetics

   Author : Marcus Eriksson; Janne Wallenius; Hamid Aït Abderrrahim; KTH; []
   Keywords : NATURVETENSKAP; NATURAL SCIENCES; Nuclear physics; Kärnfysik; Nuclear physics; Kärnfysik;

   Abstract : 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. READ MORE

4. 2. Assessment and improvements of thermal-hydraulic correlations and methods for the analysis of the Jules Horowitz Reactor

   Author : Alberto Ghione; Chalmers tekniska högskola; []
   Keywords : TEKNIK OCH TEKNOLOGIER; ENGINEERING AND TECHNOLOGY; NATURVETENSKAP; NATURAL SCIENCES; Flow instability; Uncertainty; Narrow channels; Jules Horowitz Reactor; Safety analysis; Critical heat flux; Thermal-hydraulic correlations; Heat transfer; Best-Estimate; Material Testing 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

5. 3. Improvement of the nuclear safety code CATHARE based on thermal-hydraulic experiments for the Jules Horowitz Reactor

   Author : Alberto Ghione; Chalmers tekniska högskola; []
   Keywords : TEKNIK OCH TEKNOLOGIER; ENGINEERING AND TECHNOLOGY; nuclear research reactor; fully developed boiling; single-phase heat transfer; CATHARE; laminar-turbulent transition; narrow rectangular channels; JHR; single-phase friction; SULTAN-JHR;

   Abstract : The Jules Horowitz Reactor (JHR) is a material testing research reactor under construction at CEA-Cadarache (France). One of the computer codes employed in the safety analysis of this reactor is the thermal-hydraulic system code CATHARE. READ MORE

6. 4. Uncertainty and Sensitivity Analysis Applied to the Validation of BWR Bundle Thermal-Hydraulic Calculations

   Author : Augusto Hernandéz Solís; Chalmers tekniska högskola; []
   Keywords : TEKNIK OCH TEKNOLOGIER; ENGINEERING AND TECHNOLOGY; Latin Hypercube sampling; uncertainty and sensitivity analysis; Thermal‐hydraulic codes; simple random sampling; reactor safety analysis; BFBT benchmark;

   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

7. 5. Development of an Improved Thermal-Hydraulic Modeling of the Jules Horowitz Reactor

   Author : Reijo Pegonen; Henryk Anglart; Yann Bartosiewicz; KTH; []
   Keywords : TEKNIK OCH TEKNOLOGIER; ENGINEERING AND TECHNOLOGY; Jules Horowitz Reactor; CATHARE2; STAR-CCM ; FLICA4; Material Testing Reactor; Computational Fluid Dynamics; System code; Reactor modeling;

   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