Sökning: "Reactor Safety"

Visar resultat 11 - 15 av 78 avhandlingar innehållade orden Reactor Safety.

1. 11. 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

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

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

   Sammanfattning : 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. LÄS MER

4. 13. Coil Design and Related Studies for the Fusion-Fission Reactor Concept SFLM Hybrid

   Författare :Anders Hagnestål; Olov Ågren; Vladimir Moiseenko; Ladislav Bardos; Jan Scheffel; Uppsala universitet; []
   Nyckelord :NATURVETENSKAP; NATURAL SCIENCES; Fusion; Fission; Hybrid reactor; Actinides; Mirror Machine; Quadrupolar mirror; Coils; Fysik; Physics;

   Sammanfattning : A fusion-fission (hybrid) reactor is a combination of a fusion device and a subcritical fission reactor, where the fusion device acts as a neutron source and the power is mainly produced in the fission core. Hybrid reactors may be suitable for transmutation of transuranic isotopes in the spent nuclear fuel, due to the safety margin on criticality imposed by the subcritical fission core. LÄS MER

5. 14. Development of Effective Algorithm for Coupled Thermal-Hydraulics – Neutron-Kinetics Analysis of Reactivity Transient

   Författare :Joanna Peltonen; Tomas Lefvert; Paolo Vinai; KTH; []
   Nyckelord :Light Water Reactor; BWR; RELAP5; PARCS; Coupling TH NK; Mapping; Spatial Refinement; Turbine Trip; Feedwater Transient; Control Rod Drop; Reactor Stability;

   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. To produce results within a reasonable computing time, the coupled codes use different spatial description of the reactor core. LÄS MER

7. 15. Modeling and Simulation of a Multi Phase Semi-batch Reactor

   Författare :Anna Nyström; Göteborgs universitet; []
   Nyckelord :TEKNIK OCH TEKNOLOGIER; ENGINEERING AND TECHNOLOGY; NATURVETENSKAP; NATURAL SCIENCES; NATURVETENSKAP; NATURAL SCIENCES; semi-batch reactor; modeling; simulation; optimization; simulation;

   Sammanfattning : The operation of an industrial semi-batch reactor is modeled and the flow of one reactant is investigated. In the reactor a strongly exothermic polymerization reaction takes place followed by a slightly exothermic reaction, and the objective is to minimize the duration of the operation of the process. LÄS MER