Sökning: "reactor safety analysis"

Visar resultat 1 - 5 av 35 avhandlingar innehållade orden reactor safety analysis.

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

   Författare :Alberto Ghione; Chalmers tekniska högskola; []
   Nyckelord :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;

   Sammanfattning : 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. LÄS MER

3. 2. Analysis methodology for RBMK-1500 core safety and investigations on corium coolabiblty during a LWR sever accidnet

   Författare :Audrius Jasiulevicius; KTH; []
   Nyckelord :RBMK. Light water reactor. Core analysis; transient analysis; reactor dynamics;

   Sammanfattning : 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. LÄS MER

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

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

   Sammanfattning : 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. LÄS MER

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

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

   Sammanfattning : 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. LÄS MER

7. 5. Thermo-mechanical Assessment of Reactor Pressure Vessels of Light Water Reactors During Severe Accidents

   Författare :Hongdi Wang; Walter Villanueva; Sevostian Bechta; Weimin Ma; Artem Kulachenko; Michael Fitzpatrick; KTH; []
   Nyckelord :Severe accident scenario; reactor pressure vessel; in-vessel melt retention; failure analysis; finite element analysis; validations; Scenario för svåra haverier; reaktortank; in-vessel retention; feleffektsanalys; Finite Element Analyser; validering; Physics; Fysik;

   Sammanfattning : 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. LÄS MER