Sökning: "light water reactor"

Visar resultat 1 - 5 av 42 avhandlingar innehållade orden light water reactor.

  1. 1. Thorium fuels for light water reactors - steps towards commercialization

    Författare :Klara L Insulander Björk; Chalmers tekniska högskola; []
    Nyckelord :TEKNIK OCH TEKNOLOGIER; ENGINEERING AND TECHNOLOGY; Halden research reactor; light water reactors; fuel performance; plutonium; Thorium; neutronic simulations;

    Sammanfattning : Thorium-containing nuclear fuel is proposed as a means of gaining a number of benefits in the operation of light water reactors, some related to the nuclear properties of thorium and some related to the material properties of thorium dioxide. This thesis aims to investigate some of these benefits and to widen the knowledge base on thorium fuel behaviour, in order to pave the way for its commercial use. LÄS MER

  2. 2. The Effective Convectivity Model for Simulation and Analysis of Melt Pool Heat Transfer in a Light Water Reactor Pressure Vessel Lower Head

    Författare :Chi Thanh Tran; Tomas Lefvert; Harri Tuomisto; KTH; []
    Nyckelord :TEKNIK OCH TEKNOLOGIER; ENGINEERING AND TECHNOLOGY; light water reactor; hypothetical severe accident; accident progression; accident scenario; core melt pool; heat transfer; turbulent natural convection; heat transfer coefficient; phase change; mushy zone; crust; lower plenum; analytical model; effective convectivity model; CFD simulation; Thermal energy engineering; Termisk energiteknik;

    Sammanfattning : Severe accidents in a Light Water Reactor (LWR) have been a subject of intense research for the last three decades. The research in this area aims to reach understanding of the inherent physical phenomena and reduce the uncertainties in their quantification, with the ultimate goal of developing models that can be applied to safety analysis of nuclear reactors, and to evaluation of the proposed accident management schemes for mitigating the consequences of severe accidents. LÄS MER

  3. 3. Development, validation and application of an effective convectivity model for simulation of melt pool heat transfer in a light water reactor lower head

    Författare :Chi Thanh Tran; Truc-Nam Dinh; Florian Fichot; KTH; []
    Nyckelord :NATURVETENSKAP; NATURAL SCIENCES; light water reactor; hypothetical severe accident; accident progression; accident scenario; core melt pool; heat transfer; turbulent natural convection; heat transfer coefficient; phase change; mushy zone; crust; lower plenum; analytical model; effective convectivity model; CFD simulation.; Other physics; Övrig fysik;

    Sammanfattning : Severe accidents in a Light Water Reactor (LWR) have been a subject of the research for the last three decades. The research in this area aims to further understanding of the inherent physical phenomena and reduce the uncertainties surrounding their quantification, with the ultimate goal of developing models that can be applied to safety analysis of nuclear reactors. LÄS MER

  4. 4. Visionen om outtömlig energi : Bridreaktorn i svensk kärnkraftshistoria 1945–80

    Författare :Maja Fjæstad; Thomas Kaiserfeld; Thomas Jonter; Henrik Björck; KTH; []
    Nyckelord :HUMANIORA; HUMANITIES; HUMANIORA; HUMANITIES; HUMANIORA; HUMANITIES; nuclear power; nuclear energy; nuclear power history; nuclear weapons; breeder reactor; fast reactor; AB Atomenergi; history; history of science; history of technology; environmental history; Sweden; 20th century; vision; technological vision; interpretative flexibility; kärnkraft; kärnkraftshistoria; kärnvapen; bridreaktorer; snabba reaktorer; AB Atomenergi; historia; vetenskapshistoria; teknikhistoria; miljöhistoria; Sverige; svensk historia; 1900-tal; vision; tekniska visioner; utopi; tolkningsflexibilitet; History of technology; Teknikhistoria; History of science and ideas; Idé- o lärdomshistoria; History of science; Vetenskapshistoria;

    Sammanfattning : The fast breeder is a type of nuclear reactor that aroused much attention in the 1950s and 60s. Its ability to produce more nuclear fuel than it consumes offered promises of cheap and reliable energy, and thereby connected it to utopian ideas about an eternal supply of energy. LÄS MER

  5. 5. 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