Search for dissertations about: "Sodium fast reactor"

Showing result 1 - 5 of 10 swedish dissertations containing the words Sodium fast reactor.

  1. 1. Modelling the system Cr-Fe-Ni-Te via the CALPHAD method, DFT and experiments : for fast nuclear reactor applications

    Author : Carl-Magnus Arvhult; Malin Selleby; Jean-Marc Joubert; KTH; []
    Keywords : ENGINEERING AND TECHNOLOGY; TEKNIK OCH TEKNOLOGIER; TEKNIK OCH TEKNOLOGIER; ENGINEERING AND TECHNOLOGY; Phase diagrams; Calphad; thermodynamics; microscopy; XRD; thermal analysis; phase transitions; nuclear materials; Materials Science and Engineering; Teknisk materialvetenskap;

    Abstract : In the pursuit of safer, more environmentally friendly and sustainable forms of energy production for our ever growing demands, a type of nuclear reactor cooled by liquid metal instead of water is under development. Specific to this type of reactor are special forms of corrosion of the material that encapsulates the fuel pins in the reactor core, called Fuel-Clad Chemical Interaction (FCCI) or Fission Product-induced Liquid Metal Embrittlement (FPLME). READ MORE

  2. 2. Transmutation of Americium in Fast Neutron Facilities

    Author : Youpeng Zhang; Janne Wallenius; Sandra Dulla; KTH; []
    Keywords : NATURAL SCIENCES; NATURVETENSKAP; NATURVETENSKAP; NATURAL SCIENCES; americium; transmutation; fast reactor; Nuclear physics; Kärnfysik; TECHNOLOGY; TEKNIKVETENSKAP;

    Abstract : In this thesis, the feasibility to use a medium sized sodium cooled fast reactor fully loaded with MOX fuel for efficient transmutation of americium is investigated by simulating the safety performance of a BN600-type fast reactor loaded with different fractions of americium in the fuel, using the safety parameters obtained with the SERPENT Monte Carlo code. The focus is on americium mainly due to its long-term contribution to the radiotoxicity of spent nuclear fuel and its deterioration on core's safety parameters. READ MORE

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

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

    Abstract : 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. READ MORE

  4. 4. Control Rod Homogenization in Heterogeneous Sodium-Cooled Fast Reactors

    Author : Mikael Andersson; Chalmers University of Technology; []
    Keywords : Homogenization; Monte Carlo; Fast Reactors; Reactivity Equivalence; Control rod;

    Abstract : The sodium-cooled fast reactor is one of the candidates for a sustainable nuclearreactor system. In particular, the French ASTRID project employs an axiallyheterogeneous design, proposed in the so-called CFV (low sodium effect) core, toenhance the inherent safety features of the reactor. READ MORE

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

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

    Abstract : 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. READ MORE