Mechanical Properties of Cubic (U,Zr)O2

Author:

Kitagaki Toru1,Hoshino Takanori1,Yano Kimihiko1,Okamura Nobuo1,Ohara Hiroshi2,Fukasawa Tetsuo3,Koizumi Kenji1

Affiliation:

1. Japan Atomic Energy Agency, Nuclear Fuel Cycle Engineering Laboratories, 4-33 Muramatsu, Tokai-mura 319-1194, Ibaraki, Japan e-mail:

2. Nippon Nuclear Fuel Development Co., LTD., 2163 Narita-cho, Oarai-Machi 311-1313, Ibaraki, Japan e-mail:

3. Hitachi-GE Nuclear Energy, LTD., 3-1-1 Saiwai-cho, Hitachi-Shi 317-0073, Ibaraki, Japan e-mail:

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 Three Mile Island unit 2 (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 reactors. 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 the case of (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.

Funder

"Ministry of Economy, Trade and Industry"

Publisher

ASME International

Subject

Nuclear Energy and Engineering,Radiation

Reference18 articles.

1. TMI-2 Defueling Tools Engineering Report;Bechtel North American Power Corporation,1986

2. Yano, K., Kitagaki, T., Ikeuchi, H., Wakui, R., Higuchi, H., Kaji, N., Koizumi, K., and Washiya, T., 2013, “Direction on Characterization of Fuel Debris for Defueling Process in Fukushima Daiichi Nuclear Power Station,” GLOBAL2013, American Nuclear Society, Salt Lake City, UT, Sept. 29−Oct. 3, pp. 1554–1559.https://inis.iaea.org/search/search.aspx?orig_q=RN:45085452

3. TMI-2 Core Materials and Fission Product Inventory;Nucl. Eng. Des.,1990

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