Hydride Effects on Discharged Fuel Clad Related to Accident Conditions during Dry Storage and Handling /

por Kesterson, Ron L., Korinko, Paul S., Lam, Poh-Sang, Sindelar, Robert L.
Publicado em 2018

In Situ Investigations of the Hydrogen Uptake of Zirconium Alloys during Steam Oxidation /

por Grosse, Mirco, Kaestner, Anders, Schillinger, Burkhard, Steinbrueck, Martin
Publicado em 2018

Is Spent Nuclear Fuel Immune from Delayed Hydride Cracking during Dry Storage? An IAEA Coordinated Research Project /

por Ali, Liaqat, Alvarez-Holston, Anna-Maria, Chakravartty, Jayanta Kumar, Coleman, Christopher E., He, Zhang, Inozemtsev, Victor, Makarevicius, Vidas, Markelov, Vladimir A., Ramanathan, Lalgudi, Roth, Maria
Publicado em 2018

Effect of Irradiation on Terminal Solid Solubility of Hydrogen in Zr-2.5Nb /

por Buyers, Andrew W., Coleman, Christopher E., Hilton, Vicky, McRae, Glenn A., Nordin, Heidi M.
Publicado em 2018

Effect of Alloying Elements, Cold Work, and Hydrogen on the Irradiation-Induced Growth Behavior of Zirconium Alloy Variants /

por Adamson, Ronald, Chen, Jen-Hung, Fukuda, Takuji, Gilbon, Didier, Hallstadius, Lars, Ishimoto, Shinji, Kobylyansky, Gennady, Mahmood, Sheikh, Obukhov, Alexander, Yagnik, Suresh
Publicado em 2018

Transmission Electron Microscopy Examinations of Metal-Oxide Interface of Zirconium-Based Alloys Irradiated in Halden Reactor-IFA-638 /

por Abolhassani, Sousan, Bennett, Peter, Espeland, Marit, Garde, A. M., Hallstadius, Lars, Jenssen, Håkon, Karlsen, Torill Marie, Oberländer, Barbara, Proff, Christian, Veleva, Lyubomira
Publicado em 2018

Out-of-Reactor Test of Corrosion and Hydrogen Pickup in Fuel Cladding Materials in Contact with Nickel Metal /

por Anghel, Clara, Becker, Richard, Chen, Jiaxin, Hussey, Dennis, Iyer, Jayashri, Stevens, Jacqueline, Wells, Daniel M.
Publicado em 2018

In-Pile Testing of CrN, TiAlN, and AlCrN Coatings on Zircaloy Cladding in the Halden Reactor /

por Andersson, Vendi, Balak, Juraj, Nieuwenhove, Rudi van, Oberländer, Barbara
Publicado em 2018

Temperature and Neutron Flux Dependence of In-Reactor Creep for Cold-Worked Zr-2.5Nb /

por Bickel, Grant A., Buyers, Andrew W., DeAbreu, Robert F., Donohue, Stephen A., Dunn, Kris, Griffiths, Malcolm, Walters, Lori
Publicado em 2018

Behavior of Fuel with Zirconium Alloy Cladding in Reactivity-Initiated Accident and Loss-of-Coolant Accident /

por Fuketa, Toyoshi, Nagase, Fumihisa
Publicado em 2018

Neutron Irradiation Effects on the Corrosion of Zircaloy-4 in a Pressurized Water Reactor Environment /

por Bajaj, Ram, Gruber, Jason A., Kammenzind, Bruce F., Smee, James D.
Publicado em 2018

Microstructure Evolution in Ion-Irradiated Oxidized Zircaloy-4 Studied with Synchrotron Radiation Microdiffraction and Transmission Electron Microscopy /

por Bossis, Philippe, Cai, Zhonghou, Colas, Kimberly, Jublot, Michael, Tupin, Marc, Verlet, Romain, Wolski, Krzysztof
Publicado em 2018

Equivalent Radiation Damage in Zirconium Irradiated in Various Reactors /

por Douglas, Stephen R., Griffiths, Malcolm, Walters, Lori
Publicado em 2018

Mechanistic Understanding of Zirconium Alloy Fuel Cladding Performance /

por Motta, Arthur T.
Publicado em 2018

Predicting the Flow Stress of Zircaloy-4 under In-Reactor Accident Conditions /

por Ambard, Antoine, Nguyen, Chi-Toan, Preuss, Michael, Romero, Javier E., da Fonseca, João Quinta
Publicado em 2018

Influence of Hydride Precipitation on the Corrosion Kinetics of Zircaloy-4 : Effect of the Nanostructure and Grain Boundary Properties of the Zirconium Oxide Layer on Oxygen Diffus...

por Berdin, Clotilde, Bisor, Caroline, Blat-Yrieix, Martine, Jublot, Michael, Pascal, Serge, Tupin, Marc, Zumpicchiat, Guillaume
Publicado em 2018

Investigating the Effect of Zirconium Oxide Microstructure on Corrosion Performance : A Comparison between Neutron, Proton, and Nonirradiated Oxides /

por Baxter, Felicity, Cole-Baker, Aidan, Darby, Edward C., Frankel, Philipp, Garner, Alistair, Gass, Mhairi, Harte, Allan, Preuss, Michael, Romero, Javier E., Slater, Thomas, Tejland, Pia, Topping, Matthew
Publicado em 2018

Preliminary Irradiation Effect on Corrosion Resistance of Zirconium Alloys /

por Eremin, Sergey, Gusev, Anatoly, Konkov, Viktor, Markelov, Vladimir, Novikov, Vladimir, Obukhov, Alexander, Peregud, Michael, Pokrovskiĭ, Aleksandr, Shevyakov, Alexandr
Publicado em 2018

Understanding Corrosion and Hydrogen Pickup of Zirconium Fuel Cladding Alloys : The Role of Oxide Microstructure, Porosity, Suboxides, and Second-Phase Particles /

por Aarholt, Thomas, Bagot, Paul, Frankel, Philipp, Garner, Alistair, Grovenor, Chris, Hu, Jing, Lozano-Perez, Sergio, Moody, Michael, Partezana, Jonna M., Preuss, Michael, Setiadinata, Brian, Vilalta-Clemente, Arantxa, Wilkinson, Angus
Publicado em 2018

The Effect of Iron on Dislocation Evolution in Model and Commercial Zirconium Alloys /

por Andrén, H-O (Hans-Olof), Darby, Edward C., Dumbill, Simon, Frankel, Philipp, Hallstadius, Lars, Harte, Allan, Jadernas, Daniel, Preuss, Michael, Race, Christopher, Romero, Javier E., Sundell, Gustav, Tejland, Pia, Thuvander, Mattias, Topping, Matthew
Publicado em 2018