Computer code analysis of irradiation performance of axially heterogeneous mixed oxide fuel elements attaining high burnup in a fast reactor-Reference-Cited by-同舟云学术

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Computer code analysis of irradiation performance of axially heterogeneous mixed oxide fuel elements attaining high burnup in a fast reactor

Published:2020-04 Issue: Volume:359 Page:110448
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Uwaba Tomoyuki,Yokoyama Keisuke,Nemoto Junichi,Ishitani Ikuo,Ito Masahiro,Pelletier Michel

Publisher

Elsevier BV

Subject

Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference17 articles.

1. Mechanistic models for cesium thermo-migration and cesium-fuel chemomechanical interactions in mixed-oxide fuel pins;Adamson;Trans. Am. Nucl. Soc.,1981

2. Axial distribution of cesium in heterogeneous FBR fuel pins;Furuya;J. Nucl. Mater.,1993

3. Ikusawa, Y., Uwaba, T., Nemoto, J., Tanno, T., Oka, H., Kaito, K., 2017. Axial migration and accumulation behavior of cesium in fast reactor fuel pins

4. (3) Evaluation of cesium accumulation effect on life time of fuel cladding tube. In: Proceedings of the Fall Meeting on Atomic Energy Society of Japan, September 13-15, 2017, Sapporo, Japan, p. 3J16.

5. Thermal conductivity of cesium molybdate Cs2MoO4;Ishii;J. Nucl. Mater.,1996

Cited by 1 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. Computer code analysis of irradiation performance of an annular mixed oxide fuel element;Journal of Nuclear Science and Technology;2023-03-23

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