Sökning: "fast reactor"

Visar resultat 11 - 15 av 92 avhandlingar innehållade orden fast reactor.

  1. 11. Advanced fuels for thermal spectrum reactors

    Författare :Jitka Zakova; Janne Wallenius; Jan-Leen Kloosterman; KTH; []
    Nyckelord :NATURVETENSKAP; NATURAL SCIENCES; BWR; transmutation; thorium; Pu; MA; Am; Cm; AHTR; thermal; reactor; neutron;

    Sammanfattning : The advanced fuels investigated in this thesis comprise fuels non− conventional in their design/form (TRISO), their composition (high content of plutonium and minor actinides) or their use in a reactor type, in which they have not been used before (e.g. nitride fuel in BWR). LÄS MER

  3. 12. 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

  4. 13. Transmutation of Am in sodium fast reactors and accelerator driven systems

    Författare :Youpeng Zhang; Janne Wallenius; Gérald Rimpault; KTH; []
    Nyckelord :NATURVETENSKAP; NATURAL SCIENCES; Sodium cooled fast reactor; accelerator driven system; americium; transmutation; transient analysis;

    Sammanfattning : In this thesis, the feasibility to use sodium cooled fast reactors loaded with MOX, metallic and nitride fuels for efficient transmutation of americium is investigated by performing transient analysis for cases with different americium contents in fuels, using safety parameters obtained with the SERPENT Monte Carlo code. It was then demonstrated that there is no solid limit for the Am introduction into oxide, metallic and nitride fuels that were loaded into sodium fast reactors. LÄS MER

  5. 14. Development of a Neutron Flux Monitoring System for Sodium-cooled Fast Reactors

    Författare :Vasudha Verma; Carl Hellesen; Uppsala universitet; []
    Nyckelord :NATURVETENSKAP; NATURAL SCIENCES; Protection systems; safety; accidents; sodium-cooled fast reactor; instrumentation; fission chamber; self powered neutron detector;

    Sammanfattning : Safety and reliability are one of the key objectives for future Generation IV nuclear energy systems. The neutron flux monitoring system forms an integral part of the safety design of a nuclear reactor and must be able to detect any irregularities during all states of reactor operation. LÄS MER

  7. 15. A feasibility study of coolant void detection in a lead-cooled fast reactor using fission chambers

    Författare :Peter Wolniewicz; Nils Sandberg; Uppsala universitet; []
    Nyckelord :NATURVETENSKAP; NATURAL SCIENCES; neutron monitoring spectrum fast reactor fission chamber coolant void; Applied Nuclear Physics; Tillämpad kärnfysik;

    Sammanfattning : One of the future reactor technologies defined by the Generation-IV International Forum (GIF) is the Lead-Cooled Fast Reactor (LFR). An advantage with this reactor technology is that steam production is accomplished by means of heat exchangers located within the primary reactor vessel, which decreases costs and increases operational safety. LÄS MER