Modelling Fission Gas Bubble Distribution in UO<sub>2</sub>-Reference-Cited by-同舟云学术

Modelling Fission Gas Bubble Distribution in UO₂

Published:2012-04 Issue: Volume:323-325 Page:209-214
ISSN:1662-9507
Container-title:Defect and Diffusion Forum
language:
Short-container-title:DDF

Author:

Skorek Richard¹,Maillard Serge¹,Michel Amélie¹,Carlot Gaëlle²,Gilabert Eric³,Jourdan Thomas⁴

Affiliation:

1. Commissariat à l’Energie Atomique (CEA), DEN, DEC

2. CEA

3. Chimie Nucléaire Analytique and Bio-Environnementale (CNAB)

4. Commissariat à l’Energie Atomique (CEA),

Abstract

The Cluster Dynamics method is assessed for the investigation of fission gas behaviour in a krypton-implanted and annealed UO2sample. The simulation results are then compared to Thermal Desorption Spectroscopy (TDS) data. A release mechanism is proposed: the initial burst is related to krypton migration via an interstitial mechanism, while the second stage of the release process can be accounted for by the diffusion of krypton in a substitutional position. This latter mechanism is compatible with a diffusion coefficient of 4.10-21m²/s.

Publisher

Trans Tech Publications, Ltd.

Subject

Condensed Matter Physics,General Materials Science,Radiation

Link

https://www.scientific.net/DDF.323-325.209.pdf

Reference10 articles.

1. C. Struzik, M. Moyne and J.P. Piron, in: Proc. 1997 Int. Topical Meeting on Light Water Reactor Fuel Performance, Portland, Oregon USA (1997), p.126.

2. G. Kaganas and J. Rest: A physical description of ﬁssion product behavior in fuels for advanced power reactors (2007).

3. L. Noirot, in: Nuclear Engineering and Design, Corrected Proof (2011), in press.

4. M.H. Wood: Journal of Nuclear Materials 82 (1979), pp.257-263.

5. J.M. Griesmeyer and N.M. Ghoniem: Journal of Nuclear Materials 80 (1979), pp.88-101.

Cited by 15 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. In-Situ TEM Study of Microstructural Evolution in Proton Irradiated Single Crystal UO <sub>2</sub> under High-temperature Annealing;SSRN Electronic Journal;2024

2. Evolution of dislocation loops and voids in post-irradiation annealed ThO2: A combined in-situ TEM and cluster dynamics investigation;Journal of Nuclear Materials;2023-12

3. A combined theoretical-experimental investigation of thermal transport in low-dose irradiated thorium dioxide;Acta Materialia;2022-12

4. Atomistically-informed modeling of point defect clustering and evolution in irradiated ThO2;Chemical Physics;2022-10

5. Modeling mesoscale fission gas behavior in UO2 by directly coupling the phase field method to spatially resolved cluster dynamics;Materials Theory;2022-01-27