DART Model for Irradiation-Induced Swelling of Uranium Silicide Dispersion Fuel Elements-Reference-Cited by-同舟云学术

DART Model for Irradiation-Induced Swelling of Uranium Silicide Dispersion Fuel Elements

Published:1999-04 Issue:1 Volume:126 Page:88-101
ISSN:0029-5450
Container-title:Nuclear Technology
language:en
Short-container-title:Nuclear Technology

Author:

Rest Jeffrey¹,Hofman Gerard L.¹

Affiliation:

1. Argonne National Laboratory 9700 South Cass Avenue, Argonne, Illinois 60439

Publisher

Informa UK Limited

Subject

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

Link

https://www.tandfonline.com/doi/pdf/10.13182/NT99-A2960

Reference11 articles.

1. Crystal structure stability and fission gas swelling in intermetallic uranium compounds

2. J. REST, “The DART Dispersion Analysis Research Tool: A Mechanistic Model for Predicting Fission-Product-Induced Swelling of Aluminum Dispersion Fuels,” ANL-95/36, Argonne National Laboratory (Aug. 1995).

3. J. W. BLAKE, “A Mathematical Model of the Irradiation Behavior of Uranium Silicide Fuel Plates,” MS Thesis, Northwestern University, Department of Mechanical Engineering (June 1984).

Cited by 19 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. Phase-field simulation of the effect of grain boundary on fission gas migration in UO₂ fuel;Journal of Physics: Conference Series;2024-04-01

2. Phase-field simulation study on fission gas release behavior of large grain UO2 fuel;Acta Physica Sinica;2024

3. Performance evaluation of thermal conductivity models for fission gases with application to UO2-zirconium dispersion fuel;Annals of Nuclear Energy;2023-06

4. The swelling pressure induced by irradiation in ceramic dispersion fuel meat;Progress in Nuclear Energy;2022-09

5. Modeling of Mesoscale Creep Behaviors and Macroscale Creep Responses of Composite Fuels Under Irradiation Conditions;Acta Mechanica Solida Sinica;2022-07-21