A new spatially resolved model for defects and fission gas bubbles interaction at the mesoscale-Reference-Cited by-同舟云学术

A new spatially resolved model for defects and fission gas bubbles interaction at the mesoscale

Published:2019-11 Issue: Volume:458 Page:151-158
ISSN:0168-583X
Container-title:Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms
language:en
Short-container-title:Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms

Author:

Verma L.,Noirot L.,Maugis P.

Publisher

Elsevier BV

Subject

Instrumentation,Nuclear and High Energy Physics

Reference17 articles.

1. MARGARET: a comprehensive code for the description of fission gas behavior;Noirot;Nucl. Eng. Des.,2011

2. Focused ion beam-scanning electron microscope examination of high burn-up UO2 in the center of a pellet;Noirot;Nucl. Eng. Technol.,2018

3. Gas release and swelling in oxide fuel; modeling of the kinetics of gas porosity development;Mikhlin;J. Nucl. Mater.,1982

4. Modelling of fission-gas release from fuel undergoing isothermal heating;Brearley;J. Nucl. Mater.,1983

5. Etude des méchanismes microstructuraux liés au relâchement des gaz de fission du dioxyde d’uranium irradié;Valin;Institut National Polytechnique de Grenoble,1999

Cited by 6 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. Towards modelling defective fuel rods in TRANSURANUS: Benchmark and assessment of gaseous and volatile radioactive fission product release;Annals of Nuclear Energy;2024-03

2. The SCIANTIX code for fission gas behaviour: Status, upgrades, separate-effect validation, and future developments;Journal of Nuclear Materials;2023-12

3. Oriented intra-granular bubble transport due to coupling of pinned bubble growth and dislocation climb;Journal of Nuclear Materials;2023-04

4. 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

5. SCIANTIX: A new open source multi-scale code for fission gas behaviour modelling designed for nuclear fuel performance codes;Journal of Nuclear Materials;2020-04