Essays about: "advanced nuclear fuel"

Found 4 essays containing the words advanced nuclear fuel.

  1. 1. Experimental studies of radiation damage in uranium nitride

    University essay from KTH/Fysik

    Author : Maria Giamouridou; [2023]
    Keywords : uranium nitride nuclear fuel; advanced nuclear fuel; uranium nitride fabrication; uranium nitride characterisation; Spark Plasma Sintering; proton irradiation; irradiation damage; TANDEM accelerator; irradiation induced cracking; irradiation induced hardening; irradiation induced swelling; hydrogen implantation; dislocation loops; kärnbränsle av urannitrid; avancerat kärnbränsle; tillverkning av urannitrid; karakterisering av urannitrid; Spark Plasma Sintering; protonbestrålning; strålningsskador; TANDEM-accelerator; strålningsinducerad sprickbildning; strålningsinducerad härdning; strålningsinducerad svällning; väteimplantation; dislokationsloopar;

    Abstract : The effect of proton (H+) irradiation on uranium mononitride (UN) and UN compositefuel with 10 at.% ZrN (UN10at%ZrN) was examined. Protons of 2 MeV with fluences of1E17, 1E18, 1E19 and 1E20 ions/cm2 were accelerated towards the fabricated samples in orderto investigate the evolution of the micro-structure. READ MORE

  3. 2. Feasibility of HALEU-loaded Breed-and-Burn Molten Salt Fast Reactor without Online Actinide Treatment

    University essay from KTH/Fysik

    Author : Lei Shi; [2023]
    Keywords : Molten salt; Chloride fuel; Fast reactor; Breed-and-Burn; Smält salt; kloridbränsle; snabbreaktor; avel och bränning;

    Abstract : Molten Salt Fast Reactors (MSFRs) have prominent advantages such as fuel breeding, nuclear waste transmutation, and inherent safety. They are the only liquid-fueled nuclear reactors currently receiving significant attention as fourth-generation advanced nuclear systems. READ MORE

  4. 3. Analysis of Advanced Fuel Behaviour during Loss of Coolant Accident in Swedish Boiling Water Reactor

    University essay from KTH/Kärnkraftssäkerhet

    Author : Paul Breijder; [2011]
    Keywords : Accident analysis; BWR; LOCA; sensitivity study; thermal hydraulic system code; TRACE;

    Abstract : In accident analysis regarding nuclear power plants, it is very common to use thermal hydraulic system codes, such as TRACE, developed by U.S. NRC. In the case of licensing a power plant, this is one of the necessities. READ MORE

  5. 4. Monte  Carlo simulation for the prediction of gamma-induced damage in metals  

    University essay from KTH/Reaktorfysik

    Author : Luca Messina; [2010]
    Keywords : ;

    Abstract : Nuclear waste management represents the main problem related to nuclear power generation. The Swedish project for an ultimate nuclear waste repos- itory  is in a very advanced state and cast iron-copper canisters have been designed with the aim of isolating the spent fuel from the environment for at least 105 years. READ MORE