Double diffusive dissolution model of UO<sub>2</sub> pellet in molten Zr cladding-Reference-Cited by-同舟云学术

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Double diffusive dissolution model of UO₂ pellet in molten Zr cladding

Published:2022-09-01 Issue:4 Volume:60 Page:450-459
ISSN:0022-3131
Container-title:Journal of Nuclear Science and Technology
language:en
Short-container-title:Journal of Nuclear Science and Technology

Author:

Itoh Ayumi¹,Yamashita Susumu²,Tasaki Yudai³^ORCID,Kakiuchi Kazuo³,Kobayashi Yoshinao¹

Affiliation:

1. Laboratory for Zero-Carbon Energy, Tokyo Institute of Technology, Meguro-ku, Japan

2. Nuclear Science and Engineering Center, Japan Atomic Energy Agency, Naka-gun, Japan

3. Nuclear Safety Research Center, Japan Atomic Energy Agency, Naga-gun, Japan

Publisher

Informa UK Limited

Subject

Nuclear Energy and Engineering,Nuclear and High Energy Physics

Link

https://www.tandfonline.com/doi/pdf/10.1080/00223131.2022.2114956

Reference19 articles.

1. Phenomenology of BWR fuel assembly degradation

2. Hayward PJ, Hofmann P, Stuckert J, et al. UO2 dissolution by molten zircaloy. New experimental results and modelling. FZKA 6379; 1999.

3. Dissolution of UO2 in molten Zircaloy-4 Part 1: Solubility from 2000 to 2200°C

4. Dissolution of UO2 in molten Zircaloy-4 Part 3: Solubility from 2000 to 2500°C

5. The kinetics of the uranium dioxide—Zircaloy reactions at high temperatures

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