Essays about: "nuclear cladding"

Showing result 1 - 5 of 14 essays containing the words nuclear cladding.

1. 1. Improved Modelling For Oxidation Of Zircalloy Fuel Cladding Tubes In PWRs

   University essay from KTH/Fysik

   Author : Rafaël Bellachia; [2023]
   Keywords : Nuclear Engineering; Corrosion; Zircalloy; PWR; Nuclear Fuel; Kärnteknik; Korrosion; Zircalloy; PWR; Kärnbränsle;

   Abstract : The fuel cladding is an essential component in the defence-in-depth strategy for nuclear safety. Its integrity and durability are therefore critical for maintaining acceptable safety conditions. However, the integrity of the cladding can be compromised during normal operation due to corrosion and hydriding. READ MORE

3. 2. High spatial resolution study of local corrosion effects on BWR-fuel cladding : Using a combined method of GEANT4 and lwrChem

   University essay from Uppsala universitet/Tillämpad kärnfysik

   Author : Martin Nilsson Lind; [2023]
   Keywords : fission; zircaloy; corrosion; radiolysis; radiation; BWR; Monte Carlo; GEANT4; lwrChem;

   Abstract : The core of a BWR constitutes a highly complex radiational and chemical environment. Nuclear fission is utilized to generate power and as a consequence, large quantities of ionizing radiation are produced. Gamma and beta-particles along with neutrons have the sufficient ranges to escape the fuel rods and deposit energy in the reactor coolant. READ MORE

4. 3. Qualification of a Physical Model of Cladding Creep During Dry Storage of Spent Nuclear Fuel

   University essay from KTH/Fysik

   Author : Robin Andersson; [2022]
   Keywords : Dry Storage; Thermal Creep; Zircaloy-4; Pellet-Cladding Interaction; Torrt Förvar; Termisk Krypning; Zircaloy-4; Kuts-Kapsling Interaktion;

   Abstract : In dry interim storage of spent nuclear fuel, thermal creep is one of the major threats to the fuel cladding integrity due to the constant decay heat generation from the fission products and minor actinides in the fuel, and the increase in fuel rod internal pressure which is present after burnup. Plenty of research has been done on either empty cladding tubes irradiated in a research reactor, or on spent fuel that is defueled prior to the examination. READ MORE

5. 4. Power Increase Limits to Prevent Pellet-Cladding Interaction : Calculation of Strain- and Fission Gas Release Margins

   University essay from Uppsala universitet/Institutionen för fysik och astronomi

   Author : Viktor Nerlander; [2022]
   Keywords : pci; fuel damage; FRAPCON; FRAPTRAN; FPO;

   Abstract : With a growing share of intermittent electrical energy sources in the national grid of Sweden, areview of the safety of using nuclear power for flexible operation is necessary. Today nuclearpower is used as base load power and when examining challenges of flexible power operation,the risk for Pellet-Cladding Interaction (PCI), stands out. READ MORE

6. 5. Uncertainty & Sensitivity Analysis of Nuclear Fuel Using Transuranus & Dakota

   University essay from KTH/Fysik

   Author : Udyanth Vaidya; [2021]
   Keywords : Nuclear; Nuclear Energy; SUNRISE; Transuranus; Dakota; LFR; Lead cooled fast reactor; Simulations; modelling; fuel performance code;

   Abstract : With the initiative taken by the SUNRISE project (Sustainable Nuclear Energy Research in Sweden) to construct a Lead-cooled research reactor, this thesis intends to extend the knowledge within nuclear fuel development. By using integral iterative modelling and simulating techniques that mimic real-world phenomena, novel fuel materials like uranium nitride are assessed for future validation. READ MORE