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Global and local texture development during initial plastic deformation of cold-pilgered Zircaloy-4 tubing
(Elsevier, 2022-01)
This work presents a thorough characterization of the texture development during the initial step of a cold pilgering process of a Zircaloy-4 TREX tube, on which the axial cross section is reduced by 80% over a 40cm length ...
A new irradiation growth model for Zr-based components of nuclear reactors for the DIONISIO code
(Elsevier Science SA, 2021-03)
When zirconium-based materials are subjected to irradiation, dimensional changes occur due to irradiation creep and growth. Predicting the behavior of these phenomena is necessary to determine the maximum time of operation ...
Effect of temperature on the stress corrosion cracking of zircaloy-4 in iodine alcoholic solutions
(Pergamon-Elsevier Science Ltd, 2007-07)
Zircaloy-4 is susceptible to stress corrosion cracking (SCC) in solutions of iodine dissolved in different alcohols (methanol, ethanol, 1-propanol, 1-butanol, 1-pentanol and 1-octanol). The crack propagation rate is known ...
Analysis of the behavior under irradiation of high burnup nuclear fuels with the computer programs FRAPCON and FRAPTRAN
(Associa????o Brasileira de Energia Nuclear, 2018)
Estudos comparativos entre os programas FRAPCON-1 e FRAPCON-3
(Sao Paulo: ABEN, 2005, 2014)
Neutronic screening of potential candidate for accident tolerant fuelLight Water Reactor Fuel Enrichment beyond the Five Per Cent Limit: Perspectives and Challenges
(International Atomic Energy Agency, 2020)