Oxide-Metal Ratio Dependence of Central Void Formation of Mixed Oxide Fuel Irradiated in Fast Reactors-Reference-Cited by-同舟云学术

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Oxide-Metal Ratio Dependence of Central Void Formation of Mixed Oxide Fuel Irradiated in Fast Reactors

Published:2017-06-16 Issue:1 Volume:199 Page:83-95
ISSN:0029-5450
Container-title:Nuclear Technology
language:en
Short-container-title:Nuclear Technology

Author:

Ikusawa Yoshihisa¹^ORCID,Maeda Koji²,Kato Masato²,Uno Masayoshi³

Affiliation:

1. Japan Atomic Energy Agency, 4-33 Muramatsu, Tokai-mura, Naka-gun, Ibaraki 319-1194, Japan

2. Japan Atomic Energy Agency, 4002 Narita-Cho, Oarai-machi, Higashiibaraki-gun, Ibaraki 311-1393, Japan

3. University of Fukui, 1-2-4 Kanawachou, Turuga-city 914-0055, Japan

Publisher

Informa UK Limited

Subject

Condensed Matter Physics,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Link

https://www.tandfonline.com/doi/pdf/10.1080/00295450.2017.1314748

Reference16 articles.

1. Microstructure and elemental distribution of americium-containing uranium plutonium mixed oxide fuel under a short-term irradiation test in a fast reactor

2. Short-term irradiation behavior of minor actinide doped uranium plutonium mixed oxide fuels irradiated in an experimental fast reactor

3. Short-term irradiation behavior of low-density americium-doped uranium–plutonium mixed oxide fuels irradiated in a fast reactor

4. Y. IKUSAWA et al. “Development and Verification of the Thermal Behavior Analysis Code for MA Containing MOX Fuels,” Proc. ICONE22, Prague, Czech Republic, July 7–11, 2014.

5. Development of the thermal behavior analysis code DIRAD and the fuel design procedure for LMFBR

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1. A science‐based mixed oxide property model for developing advanced oxide nuclear fuels;Journal of the American Ceramic Society;2023-12-17

2. Key technologies for future sodium-cooled fast reactors;Sodium-cooled Fast Reactors;2022

3. Development of fuel performance analysis code, BISON for MOX, named Okami: Analyses of pore migration behavior to affect the MA-bearing MOX fuel restructuring;Journal of Nuclear Materials;2021-09

4. Fuel Design and Fabrication: Pellet-Type Fuel;Encyclopedia of Nuclear Energy;2021

5. Oxygen potential measurement of (U,Pu,Am)O2±x and (U,Pu,Am,Np)O2±x;Journal of Nuclear Materials;2020-12

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