High temperature nanoindentation of (U,Ce)O compounds

Frazer, D.*; Saleh, T. A.*; Matsumoto, Taku; Hirooka, Shun; Kato, Masato; McClellan, K.*; White, J. T.*

Nuclear Engineering and Design, 423, p.113136_1 - 113136_7, 2024/07

https://doi.org/10.1016/j.nucengdes.2024.113136

Nanoindentation based techniques can be employed on minute volumes of material to measure mechanical properties, including Young's modulus, hardness, and creep stress exponents. In this study, (U,Ce)O solid solutions samples are used to develop elevated temperature nanoindentation and nanoindentation creep testing methods for use on mixed oxide fuels. Nanoindentation testing was performed on 3 separate (Ux-1,Cex)O compounds ranging from x equals 0.1 to 0.3 at up to 800 C: their Young's modulus, hardness, and creep stress exponents were evaluated. The Young's modulus decreases in the expected linear manner while the hardness decreases in the expected exponential manner. The nanoindentation creep experiments at 800 C give stress exponent values, n=4.7-6.9, that suggests dislocation motion as the deformation mechanism.

Mechanical property of superplastic-deformed ceramics by micro-indentation method

Shibata, Taiju; Ishihara, Masahiro; Takahashi, Tsuneo*; Motohashi, Yoshinobu*; Hayashi, Kimio

JAERI-Research 2001-024, 24 Pages, 2001/03

JAERI-Research-2001-024.pdf:6.25MB

no abstracts in English

Nanoindentation behavior of a two-dimensional carbon-carbon composite for nuclear applications

Kanari, Moriyasu*; *; ; Eto, Motokuni

Carbon, 35(10-11), p.1429 - 1437, 1997/00

https://doi.org/10.1016/S0008-6223(97)00042-0

no abstracts in English

Mechanical property evaluation on irradiated materials with gradient damage distribution

Sakai, Tomoki*; Wakui, Takashi; Saito, Shigeru; Futakawa, Masatoshi; Mori, Kotaro*

no journal, , 

One of dominant factors to determine the lifetime of components used under the high-radiation environment is the radiation damage of materials and then understanding of the radiation damage is very important. Although ion irradiation has been conducted as the method simulating the radiation damage, the damaged area is limited to the surface layer of the specimen and has the gradient damage distribution. Micro-indentation tests with a Berkovich indenter were conducted in irradiated and unirradiated area on ion irradiated specimens and the micro-hardness was estimated from load and depth curve. The micro-hardness increased by the irradiation. The micro-hardness increased further under the irradiation condition that hydrogen ion and helium ion were added. On the other hand, the micro-hardness decreased with increasing irradiated temperature.