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research-article

Mechanical properties of cubic (U,Zr)O2

[+] Author and Article Information
Toru Kitagaki

Japan Atomic Energy Agency, Nuclear Fuel Cycle Engineering Laboratories 4-33 Muramatsu, Tokai-mura, ibaraki, 319-1194 Japan
kitagaki.toru@jaea.go.jp

Takanori Hoshino

Japan Atomic Energy Agency, Nuclear Fuel Cycle Engineering Laboratories 4-33 Muramatsu, Tokai-mura, ibaraki, 319-1194 Japan
hoshino.takanori@jaea.go.jp

Kimihiko Yano

Japan Atomic Energy Agency, Nuclear Fuel Cycle Engineering Laboratories 4-33 Muramatsu, Tokai-mura, ibaraki, 319-1194 Japan
yano.kimihiko@jaea.go.jp

Nobuo Okamura

Japan Atomic Energy Agency, Nuclear Fuel Cycle Engineering Laboratories 4-33 Muramatsu, Tokai-mura, ibaraki, 319-1194 Japan
okamura.nobuo@jaea.go.jp

Hiroshi Ohara

Nippon Nuclear Fuel Development Co., LTD. 2163 Narita-cho, Oarai-Machi, Ibaraki, 311-1313 Japan
ohara@nfd.co.jp

Tetsuo Fukasawa

Hitachi-GE Nuclear Energy, LTD. 3-1-1 Saiwai-cho, Hitachi-Shi, Ibaraki, 317-0073 Japan
tetsuo.fukasawa.gx@hitachi.com

Kenji Koizumi

Japan Atomic Energy Agency, Nuclear Fuel Cycle Engineering Laboratories 4-33 Muramatsu, Tokai-mura, ibaraki, 319-1194 Japan
koizumi.kenji@jaea.go.jp

1Corresponding author.

ASME doi:10.1115/1.4039847 History: Received July 14, 2017; Revised February 13, 2018

Abstract

Evaluation of fuel debris properties in the Fukushima Daiichi Nuclear Power Plant (1F) is required to develop fuel debris removal tools. In the removal of debris resulting from the TMI-2 accident, a core-boring system played an important role. Considering the working principle of core boring, hardness, elastic modulus, and fracture toughness were found to be important fuel debris properties that profoundly influenced the performance of the boring machine. It is speculated that uranium and zirconium oxide solid solution (U,Zr)O2 is one of the major materials in the fuel debris from 1F. In addition, the Zr content of the fuel debris from 1F is expected to be higher than that of the debris from TMI-2 because the 1F reactors were boiling-water reactor (BWR). In this research, the mechanical properties of cubic (U,Zr)O2 samples containing 10%¬-65% ZrO2 are evaluated. The hardness, elastic modulus, and fracture toughness are measured by the Vickers test, ultrasonic pulse echo method, and indentation fracture method, respectively. In case of the (U,Zr)O2 samples containing less than 50% ZrO2, Vickers hardness and fracture toughness increased, and the elastic modulus decreased slightly with increasing ZrO2 content. Moreover, all of those values of the (U,Zr)O2 samples containing 65% ZrO2 increased slightly compared to (U,Zr)O2 samples containing 55% ZrO2. ZrO2 content affects fracture toughness significantly in the case of samples containing less than 10% ZrO2. Higher Zr content (exceeding 50%) has little effect on the mechanical properties.

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