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In-situ TEM study on the evolution of dislocation loops and bubbles in CeO_(2)during Kr^(+)single-beam and Kr^(+)-H_(2)^(+)dual-beam synergetic irradiation

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Journal of Materials Science & Technology 2022年第28期123卷 49-59页

作者： Ziqi Cao Guang Ran Zhen Wang Yipeng Li Xiaoyong Wu Lu Wu Xiuyin Huang Huajun Mo College of Energy Xiamen UniversityXiamen 361102China The First Sub-Institute Nuclear Power Institute of ChinaChengdu 610041China Fujian Provincial nuclear Energy Engineering Technology Research Center Xiamen 361102China

CeO_(2)is widely used as the nonradioactive surrogate fuel of UO_(2)when studying the irradiation performance of UO_(2).The evolution and characteristics of dislocation loops and bubbles in CeO_(2)foils were studied by in-situ transmission electron microscopy(TEM)observation during 400 ke V Kr^(+)&30 ke V H_(2)^(+)dual-beam synergetic irradiation and 400 ke V Kr^(+)single-beam irradiation at 1073 K.The rotation of the habit plane of dislocation loops induced by above ion irradiation was found in the CeO_(2)for the first time,such as from[211]to[311]and then to[100].The rafted loops were first observed under Kr^(+)&H_(2)^(+)dual-beam synergetic irradiation,which not only had similar[111]direction,but also belonged to perfect dislocation loops(PDLs).The rafted loops were formed not only by the growth of loops that absorbed irradiation defects,but also by the combination of loops.But,this phenomenon of loop rafting was not obvious during Kr single-beam irradiation.It was first found that Kr^(+)irradiation induced the change of Burgers vectors of PDLs.The absorption of large PDLs to small PDLs was also observed.The average size and areal number density of dislocation loops and gas bubbles as a function of irradiation dose were constructed,which showed that the addition of H_(2)^(+)obviously affected the characteristics of dislocation loops and gas bubbles and the swelling of CeO_(2).

关键词： nuclear fuel Cerium dioxide In-situ TEM Irradiation Dislocation Bubbles

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Applying multi-scale simulations to materials research of nuclear fuels:A review

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Materials Reports(Energy) 2021年第3期1卷 64-80页

作者： Chunyang Wen Di Yun Xinfu He Yong Xin Wenjie Li Zhipeng Sun School of nuclear Science and Technology Xi'an Jiaotong UniversityXi'an710049China State Key Laboratory of Multiphase Flow Xi'an Jiaotong UniversityXi'an710049China China Institute of Atomic Energy Beijing102413China Key Laboratory of nuclear Reactor System Design Technology Nuclear Power Institute of ChinaChengdu610213China

Computational simulation is an important technical means in research of nuclear fuel materials.Since nuclear fuel issues are inherently multi-scopic,it is imperative to study them with multi-scale simulation scheme.At present,the development of multi-scale simulation for nuclear fuel materials calls for a more systematic approach,in which lies the main purpose of this article.The most important thing in multi-scale simulation is to accurately formulate the goals to be achieved and the types of methods to be used.In this regard,we first summarize the basic principles and applicability of the simulation methods which are commonly used in nuclear fuel research and are based on different scales ranging from micro to macro,i.e.First-Principles(FP),Molecular Dynamics(MD),Kinetic Monte Carlo(KMC),Phase Field(PF),Rate Theory(RT),and Finite Element Method(FEM).And then we discuss the major material issues in this field,also ranging from micro-scale to macro-scale and covering both pellets and claddings,with emphasis on what simulation method would be most suitable for solving each of the issues.Finally,we give our prospective analysis and understanding about the feasible ways of multi-scale integration and relevant handicaps and challenges.

关键词： Computational simulation nuclear fuel Multi-scale modeling Irradiation behavior

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Atomization of UMo Particles under Nitrogen Atmosphere

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World Journal of nuclear Science and Technology 2016年第1期6卷 43-52页

作者： Luis Olivares Jaime Lisboa Jorge Marin Mario Barrera Alberto Navarrete nuclear Materials Department Chilean Commission for Nuclear Energy (CCHEN) Santiago Chile Physic Department Universidad de Santiago de Chile (USACH) Santiago Chile

Generally, the atomization of UMo particles is done under vacuum or argon atmosphere, and the surface modification of these UMo particles is, usually, carried on through a further process. The techniques for surface modification of atomized UMo particles, aimed to control the fuel/Matrix interaction, involve, in some cases, complex methodologies and often with minor effect due to the limited solubility of third elements in solid UMo alloy. The atomization and surface conditioning, applied in separate stages, may affect the efficiency of powder production process. Then, the main goal of this study is to explore the surface modification of UMo particles in liquid state or during the solidification that follows the centrifugal atomization process. Through the change of atomization atmosphere, could be possible to promote liquid/gas reactions, with a higher solubility of the modifier element in micro drops of UMo alloy, before they become solid particles. This paper presents comparative results of centrifugal atomization of UMo particles, carried out under inert argon and reactive nitrogen atmospheres. Dissolved nitrogen contents, measured by SEM-EDS analyses, reached up to 7.57 wt% at the center of under nitrogen atomized particles, very higher than 0.84 wt% of nitrogen measured at the center of UMo particle atomized under argon. The presence of uranium nitride was partially verified by conventional XRD analysis. Nevertheless, Out-of-Pile interaction test result, reveals decreasing of aluminium contents into UMo particles atomized under nitrogen atmosphere;Just 3.77 wt% of Al was the maximum content detected in the center of these particles, very lower than 29.11 wt% of Al measured inside UMo particles atomized under argon. Finally, it is possible to conclude that the atomization under reactive atmosphere may modify the surface composition and the behavior of UMo fuel particles dispersed in aluminium, for dispersion type nuclear fuel application.

关键词： Atomization UMo Particles Dispersion nuclear fuel

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The AFA 3G fuel Assembly,a Tried and Tested Design for High Burnups

The AFA 3G Fuel Assembly,a Tried and Tested Design for High ...

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第13届太平洋地区核能大会

作者： A.Hrault J.P.Balon F.Florentin nuclear fuel Design and Sales Division Framatome ANP 10 rue Juliette Recamier-69456 Lyon Cedes 06-France

The AFA 3G fuel assembly design is based on feedback from the AFA 2G fuelassembly, and benefits from the results of the world’s largest R and D program, in-pileand out-of-pile testing carried out by Framatome ANP in conjunction with EDF and theCEA. The AFA 3G shows improvement in the following areas: - a reinforced structure using Monobloc guide-thimbles, which improvesresistance to assembly bow, phenomenon affecting RCCA insertion, fuel handling, andcore physics, - excellent thermal-hydraulic behaviour based on the proven mixing vane array ofAFA 2G spacer grids, and which can be further enhanced with the combination of threeadditional Mid Span Mixing Grids, - extremely effective debris protection using the Trapper bottom nozzle. Furthermore, for high burnups application, the AFA 3G is fitted with M5cladding which presents very high corrosion resistance properties and excellentbehaviour with regard to growth and creep under irradiation. In the latest version, theuse of the M5 material for the structure as well gives to the AFA 3G fuel assembly thecapability to operate at very high burnups in the range of 65 000 MWd/t and higher.

关键词： nuclear fuel High burnup

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