Multiscale development of a fission gas thermal conductivity model: Coupling atomic, meso and continuum level simulations-Reference-Cited by-同舟云学术

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Multiscale development of a fission gas thermal conductivity model: Coupling atomic, meso and continuum level simulations

Published:2013-09 Issue:1-3 Volume:440 Page:193-200
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Tonks Michael R.,Millett Paul C.,Nerikar Pankaj,Du Shiyu,Andersson David,Stanek Christopher R.,Gaston Derek,Andrs David,Williamson Richard

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics

Reference38 articles.

1. A pragmatic approach to modelling thermal conductivity of irradiated UO2 fuel: Review and recommendations

2. Diffusion theory of fission gas migration in irradiated nuclear fuel UO2

3. Physics-based modelling of fission gas swelling and release in UO2 applied to integral fuel rod analysis

4. Thermal transport properties of uranium dioxide by molecular dynamics simulations

5. Thermal conductivity of UO2 fuel: Predicting fuel performance from simulation

Cited by 35 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. Study of xenon evolution in UO2 using multi-grain cluster dynamics modeling;Nuclear Engineering and Design;2023-12

2. Finite temperature properties of uranium mononitride;Journal of Nuclear Materials;2023-04

3. Accelerating cluster dynamics simulation of fission gas behavior in nuclear fuel on deep computing unit–based heterogeneous architecture supercomputer;The International Journal of High Performance Computing Applications;2023-03-14

4. An experimentally validated mesoscale model for the effective thermal conductivity of U-Zr fuels;Journal of Nuclear Materials;2023-02

5. Influence of point defect accumulation on in-pile thermal conductivity degradation: Fuel rod defect distribution and deviation between in-pile and post irradiation thermal conductivity;Journal of Nuclear Materials;2023-01

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