Search for dissertations about: "Core voiding"

Found 3 swedish dissertations containing the words Core voiding.

  1. 1. Validation and Application of CFD to Safety-Related Phenomena in Lead-Cooled Fast Reactors

    Author : Marti Jeltsov; Pavel Kudinov; Walter Villanueva; Dmitry Grishchenko; Afaque Shams; KTH; []
    Keywords : ENGINEERING AND TECHNOLOGY; TEKNIK OCH TEKNOLOGIER; TEKNIK OCH TEKNOLOGIER; ENGINEERING AND TECHNOLOGY; Verification; Validation; Calibration; Sensitivity Analysis; Uncertainty Analysis; CFD; STH; Code Coupling; Liquid Lead Coolant; LFR; SGTL R; Bubble transport; Core voiding; Seismic Sloshing; Melting Solidification; Physics; Fysik;

    Abstract : Carbon-free nuclear power production can help to relieve the increasing energy demand in the world. New generation reactors with improved safety, sustainability, reliability, economy and security are being developed. Lead-cooled fast reactor (LFR) is one of them. READ MORE

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

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

    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

  3. 3. Advanced fuels for thermal spectrum reactors

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

    Abstract : 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). READ MORE