Comparative analysis of swelling and porosity evolution in UO2 fuel via two approaches

被引:0
|
作者
Roostaii, Bahareh [1 ]
机构
[1] Nucl Sci & Technol Res Inst, POB 11365-3486, Tehran, Iran
关键词
high burnup structure; matrix swelling; porosity; Xe depletion; BURN-UP; PWR-FUELS; RECRYSTALLIZATION; IRRADIATION; COMPLETION; MODEL;
D O I
10.1515/kern-2022-0121
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
A correlation for the volume porosity of irradiated UO2 fuel as a sum of the individual contributions of the pore and swelling porosity in terms of the local density and fractional matrix swelling is developed. By using the existing low temperature low burnup model of swelling, evolution of the matrix swelling and porosity terms are calculated for UO2 fuel in the low burnup but in the high burnup two various models are applied, the one with considering grain recrystallization and another without it but with the method of Xe depletion measurement. The purpose of the paper is comparison of fuel swelling behavior between two models at high burnups. The bulk swelling and porosity evolution in both methods are also validated by experimental data. Finally, one conclusion from this comparison is obtained, as the method which considering grain recrystallization has more rational behavior in the fuel swelling and porosity.
引用
收藏
页码:354 / 360
页数:7
相关论文
共 50 条
  • [1] Porosity evolution study in irradiated UO2 fuel based on fuel matrix swelling
    Roostaii, B.
    Kazeminejad, H.
    Khakshournia, S.
    KERNTECHNIK, 2018, 83 (02) : 86 - 90
  • [2] Models for fuel porosity evolution in UO2 under various regimes of reactor operation
    Tarasov, V. I.
    Veshchunov, M. S.
    NUCLEAR ENGINEERING AND DESIGN, 2014, 272 : 65 - 83
  • [3] MODELING THE IRRADIATION SWELLING OF UO2 AT THE FUEL PELLET RIM
    Gao, Lijun
    Chen, Bingde
    Xiao, Zhong
    Jiang, Shengyao
    Yu, Jiyang
    PROCEEDINGS OF THE 21ST INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING - 2013, VOL 1, 2014,
  • [4] Comparative investigations of aftersintering of UO2 fuel pellets
    V. V. Basov
    Russian Journal of Non-Ferrous Metals, 2010, 51 : 173 - 176
  • [5] Comparative investigations of aftersintering of UO2 fuel pellets
    Basov, V. V.
    RUSSIAN JOURNAL OF NON-FERROUS METALS, 2010, 51 (02) : 173 - 176
  • [6] Impact of high porosity on thermal transport in UO2 nuclear fuel
    Yun, Di
    Stan, Marius
    JOURNAL OF MATERIALS RESEARCH, 2013, 28 (17) : 2308 - 2315
  • [7] Modelling of as-fabricated porosity in UO2 fuel by MFPR code
    Tarasov, Vladimir I.
    Veshchunov, Mikhail S.
    EPJ NUCLEAR SCIENCES & TECHNOLOGIES, 2016, 2
  • [9] Impact of high porosity on thermal transport in UO2 nuclear fuel
    Di Yun
    Marius Stan
    Journal of Materials Research, 2013, 28 : 2308 - 2315
  • [10] Microstructural analysis and modelling of intergranular swelling of an irradiated UO2 fuel treated at high temperature
    CEA/Saclay, Gif sur Yvette, France
    J Nucl Mater, 2-3 (92-104):