Coupled computer code study on irradiation performance of a fast reactor mixed oxide fuel element with an emphasis on the fission product cesium behavior-Reference-Cited by-同舟云学术

Coupled computer code study on irradiation performance of a fast reactor mixed oxide fuel element with an emphasis on the fission product cesium behavior

Published:2018-05 Issue: Volume:331 Page:186-193
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Uwaba Tomoyuki,Nemoto Junichi,Ishitani Ikuo,Ito Masahiro

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

Reference19 articles.

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2. Oxygen pressures over fast breeder reactor fuel (I) a model for UO2±x;Blackburn;J. Nucl. Mater.,1973

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

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

5. Cesium interaction with irradiated oxide fuel pins;Johnson;Trans. Am. Nucl. Soc.,1973

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