4.7 Review

Review of sintering and densification in nuclear fuels: Physical mechanisms, experimental results, and computational models

期刊

JOURNAL OF NUCLEAR MATERIALS
卷 507, 期 -, 页码 381-395

出版社

ELSEVIER SCIENCE BV
DOI: 10.1016/j.jnucmat.2018.03.046

关键词

-

资金

  1. Nuclear Energy Advanced Modeling and Simulation (NEAMS) program
  2. Idaho National Laboratory Fuel Modeling and Simulation department

向作者/读者索取更多资源

This work is a review of two density changes common in UO2 nuclear fuel: sintering and irradiation-enhanced densification. These density changes must be understood in order to predict fuel behavior, increase fuel lifetime, and design safer and more economical reactor fuels. The physical causes of each dimensional change are summarized. Then a summary is given of published experimental data as well as conclusions that can be drawn from that data. Finally, the most commonly used models for predicting these behaviors are summarized and compared based on the type of model, assumptions in the model, and the physics accounted for in each model. Models are categorized as empirical, semi-empirical, continuous, or microstructural. Commonly used models are presented, summarized, and compared based on the model category, assumptions, and physics that are included in the models. Finally, recommendations are given for future model development. (C) 2018 Elsevier B.V. All rights reserved.

作者

我是这篇论文的作者
点击您的名字以认领此论文并将其添加到您的个人资料中。

评论

主要评分

4.7
评分不足

次要评分

新颖性
-
重要性
-
科学严谨性
-
评价这篇论文

推荐

暂无数据
暂无数据