Show simple item record

contributor authorKitagaki, Toru
contributor authorHoshino, Takanori
contributor authorYano, Kimihiko
contributor authorOkamura, Nobuo
contributor authorOhara, Hiroshi
contributor authorFukasawa, Tetsuo
contributor authorKoizumi, Kenji
date accessioned2019-02-28T11:05:29Z
date available2019-02-28T11:05:29Z
date copyright5/16/2018 12:00:00 AM
date issued2018
identifier issn2332-8983
identifier otherners_004_03_031011.pdf
identifier urihttp://yetl.yabesh.ir/yetl1/handle/yetl/4252577
description abstractEvaluation 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.
publisherThe American Society of Mechanical Engineers (ASME)
titleMechanical Properties of Cubic (U,Zr)O2
typeJournal Paper
journal volume4
journal issue3
journal titleJournal of Nuclear Engineering and Radiation Science
identifier doi10.1115/1.4039847
journal fristpage31011
journal lastpage031011-7
treeJournal of Nuclear Engineering and Radiation Science:;2018:;volume( 004 ):;issue: 003
contenttypeFulltext


Files in this item

Thumbnail

This item appears in the following Collection(s)

Show simple item record