Essays about: "zircaloy"

Found 5 essays containing the word zircaloy.

1. 1. 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

3. 2. 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

4. 3. Extraction Replicas of Common Engineering Alloys for Analysis of Small Precipitates

   University essay from KTH/Materialvetenskap

   Author : Monika Rolinska; [2020]
   Keywords : Extraction replica; transmission electron microscopy; materials characterization; precipitation; Extraktionsrepliker; transmissionselektronmikroskopi; materialkaraktarisering; utskiljningar;

   Abstract : Characterization of small precipitates is important for development of new alloys. One inherent  difficulty  in  characterisation  of  small  precipitates  with  electron microscopy techniques  while  the  particles  are  embedded  in  the  matrix,  is  that the surrounding bulk material will contribute to the analysed signal- limiting, for example, the quantification of the composition of particles. READ MORE

5. 4. Degradation mechanisms of UN and UN–10U3Si2 pellets of varying microstructure by comparative steam oxidation experiments

   University essay from KTH/Reaktorfysik

   Author : Selim Uygur; [2016]
   Keywords : Uranium Mononitride; Uranium Silicide; Composite; Steam degradation; corrosion mechanism;

   Abstract : During an extended LOCA in a LWR, the current UO2 fuel reaches very high temperatures and eventually melts, while the current Zircaloy fuel cladding oxidizes releasing hydrogen. These two consequences can lead to an unacceptable amount of radioactive release by presenting accident routes for containment failure. READ MORE

6. 5. Experimental evalution of oxide growth in binary zirconium alloys along with pure zirconium and Zircaloy-2 by steam corrosion testing

   University essay from KTH/Fysik

   Author : Bhadrinarayanan Lalgudi Srinivas; [2012]
   Keywords : ;

   Abstract : .... READ MORE