Thermal and Mechanical Properties of Fe<sub>2</sub>Zr-Reference-Cited by-同舟云学术

Thermal and Mechanical Properties of Fe₂Zr

Published:2019-03-01 Issue:1 Volume:18 Page:37-42
ISSN:1347-2879
Container-title:Transactions of the Atomic Energy Society of Japan
language:en
Short-container-title:Transactions of the Atomic Energy Society of Japan

Author:

OKADA Daisuke¹,ISHII Hiroto¹,OHISHI Yuji¹,MUTA Hiroaki¹,KUROSAKI Ken¹²³

Affiliation:

1. Graduate School of Engineering, Osaka University

2. Research Institute of Nuclear Engineering, University of Fukui

3. JST, PRESTO

Publisher

Atomic Energy Society of Japan

Subject

Safety, Risk, Reliability and Quality,Nuclear Energy and Engineering

Link

https://www.jstage.jst.go.jp/article/taesj/18/1/18_J18.011/_pdf

Reference24 articles.

1. 1) Tokyo Electric Power Company, Inc., Fukushima Nuclear Accident Analysis Report, Tokyo Electric Power Company, 2012, Oct. 1(English), (Internet), http://www.tepco.co.jp/en/press/corp-com/release/betu12_e/images/120620e0104.pdf, (cited 2018 April 5).

2. 2) D. Klein, M. Corradini, Fukushima Daiichi: ANS Committee Report, American Nuclear Society, 2012, Sep. 18 (English), (Internet), http://fukushima.ans.org/report/Fukushima_report.pdf, (cited 2018 April 5).

3. 3) F. Tanabe, “Analysis of core melt accident in Fukushima Daiichi-Unit 1 Nuclear Reactor,” J. Nucl. Sci. Technol., 48[8], 1135–1139 (2011).

4. 4) M. Takano, T. Nishi, N. Shirasu, “Characterization of solidified melt among materials of UO₂ fuel and B₄C control blade,” J. Nucl. Sci. Technol., 51[7–8], 859–875 (2014).

5. 5) S. Hirooka, M. Kato, K. Morimoto, A. Komeno, T. Uchida, M. Akashi, “Effect of oxygen-to-metal ratio on properties of corium prepared from UO₂ and zircaloy–2,” J. Nucl. Mater., 437, 130–134 (2013).

Cited by 4 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. Aging of fuel-containing materials (fuel debris) in the Chornobyl (Chernobyl) Nuclear Power Plant and its implication for the decommissioning of the Fukushima Daiichi Nuclear Power Station;Journal of Nuclear Materials;2023-04

2. Phase behavior of oxidized Ce and Gd-doped (U,Zr)O₂;Journal of Nuclear Science and Technology;2022-08-23

3. Mechanical properties and thermal conductivity of (U,Zr)SiO4;Journal of Nuclear Materials;2021-12

4. Mechanical and thermal properties of Zr-B and Fe-B alloys;Journal of Nuclear Science and Technology;2020-03-06