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

by Kesterson, Ron L., Korinko, Paul S., Lam, Poh-Sang, Sindelar, Robert L.
Published 2018

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

by Grosse, Mirco, Kaestner, Anders, Schillinger, Burkhard, Steinbrueck, Martin
Published 2018

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

by 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
Published 2018

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

by Buyers, Andrew W., Coleman, Christopher E., Hilton, Vicky, McRae, Glenn A., Nordin, Heidi M.
Published 2018

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

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

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

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

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

by Anghel, Clara, Becker, Richard, Chen, Jiaxin, Hussey, Dennis, Iyer, Jayashri, Stevens, Jacqueline, Wells, Daniel M.
Published 2018

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

by Andersson, Vendi, Balak, Juraj, Nieuwenhove, Rudi van, Oberländer, Barbara
Published 2018

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

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

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

by Fuketa, Toyoshi, Nagase, Fumihisa
Published 2018

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

by Bajaj, Ram, Gruber, Jason A., Kammenzind, Bruce F., Smee, James D.
Published 2018

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

by Bossis, Philippe, Cai, Zhonghou, Colas, Kimberly, Jublot, Michael, Tupin, Marc, Verlet, Romain, Wolski, Krzysztof
Published 2018

Equivalent Radiation Damage in Zirconium Irradiated in Various Reactors /

by Douglas, Stephen R., Griffiths, Malcolm, Walters, Lori
Published 2018

Mechanistic Understanding of Zirconium Alloy Fuel Cladding Performance /

by Motta, Arthur T.
Published 2018

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

by Ambard, Antoine, Nguyen, Chi-Toan, Preuss, Michael, Romero, Javier E., da Fonseca, João Quinta
Published 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...

by Berdin, Clotilde, Bisor, Caroline, Blat-Yrieix, Martine, Jublot, Michael, Pascal, Serge, Tupin, Marc, Zumpicchiat, Guillaume
Published 2018

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

by 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
Published 2018

Preliminary Irradiation Effect on Corrosion Resistance of Zirconium Alloys /

by Eremin, Sergey, Gusev, Anatoly, Konkov, Viktor, Markelov, Vladimir, Novikov, Vladimir, Obukhov, Alexander, Peregud, Michael, Pokrovskiĭ, Aleksandr, Shevyakov, Alexandr
Published 2018

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

by 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
Published 2018

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

by 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
Published 2018