Defects and Diffusion Phenomena in Materials for Nuclear Technologies

Volume 375

doi: 10.4028/

Paper Title Page

Authors: Rodolfo A. Pérez

Abstract: Diffusion at infinite dilution of U in metals, with particular emphasis in those used in nuclear facilities, is revisited. Early works...

Authors: Ryan Newell, Abhishek Mehta, Young Joo Park, Yong Ho Sohn, Jan Fong Jue, Dennis D. Keiser Jr.

Abstract: Monolithic fuel system with U – 10 wt.% Mo (U10Mo) fuel alloy has been developed for the Materials Management and Minimization reactor...

Authors: Boris A. Tarasov, Stepan N. Nikitin, Dmitry P. Shornikov, Maria S. Tarasova, Igor I. Konovalov

Abstract: Paper presents the results of the growth rate of the interaction layer of uranium-molybdenum dispersed fuel in aluminum matrix and influence...

Authors: Ajay Annamareddy, Jacob Eapen

Abstract: UO2 transforms into a superionic conductor at temperatures in excess of 2000 K with oxygen ions becoming mobile and exhibiting...

Authors: Masato Kato, Hiroki Nakamura, Masashi Watanabe, Taku Matsumoto, Masahiko Machida

Abstract: The basic properties of PuO2βˆ’x were reviewed, and the equilibrium defects in...

Authors: Vladimir I. Tarasov, Pavel V. Polovnikov

Abstract: Atomistic simulations of radiation impact due to collision cascades in oxide and nitride nuclear fuels are performed in this work using...

Authors: Masashi Watanabe, Takeo Sunaoshi, Masato Kato

Abstract: The oxygen chemical diffusion coefficient in (U, Pu)O2-x was determined by thermo-gravimetry as functions of the Pu content,...

Authors: Igor I. Konovalov, Boris A. Tarasov, Eduard M. Glagovskiy

Abstract: Article discusses experimental data on creep of (U,Pu)N and other uranium compounds, and possible mechanism of mass-transfer. Proposed...

Authors: Sergey Starikov, Alexey Kuksin, Daria Smirnova, Alexey Dolgodvorov, Vladimir Ozrin

Abstract: Multiscale computational approach is used to evaluate microscopic parameters for description of nitride nuclear fuel. The results of...


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