Microstructural understanding on the fouling behavior of crud on PWR fuel cladding surface

IF 2.8 2区工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY

Journal of Nuclear Materials Pub Date : 2023-08-15 DOI:10.1016/j.jnucmat.2023.154500

Jianqiao Yang , Jiahuan Wang , Junkai Liu , Shuzhong Wang , Di Yun , Dayan Ma , Yanhui Li , Donghai Xu

引用次数: 0

Abstract

In the present paper, an accelerate crud creation experiment was conducted by a laboratory simulation facility. A TEM sample was prepared at the interface between the crud layer and pressurized water reactor (PWR) fuel cladding tube to investigate the fouling behavior of crud on the surface of cladding tubes at a microstructural level. The results show that the crud layer consisted mainly of NiFe₂O₄, as Fe³⁺ and Ni²⁺ serving as the primary sources. Heterogeneous growth of Fe₃O₄ was observed by HRTEM, which formed dislocations NiFe₂O₄ grains. Based on the microstructural characterization results, the growth mechanism of crud particles on cladding tube surface during subcooled nucleate boiling was discussed with a focus on mass and heat transfer.

查看原文本刊更多论文

压水堆燃料包壳表面污垢行为的微观结构研究

本文在实验室模拟装置上进行了加速造渣实验。在压水堆(PWR)燃料包壳管与原油层界面处制备了TEM样品，从微观结构层面研究了原油在包壳管表面的结垢行为。结果表明:渣层主要由NiFe2O4组成，主要来源为Fe3+和Ni2+;HRTEM观察到Fe3O4的非均相生长，形成位错NiFe2O4晶粒。基于微观组织表征结果，讨论了过冷核沸腾过程中包层管表面粗颗粒的生长机理，重点讨论了质量和传热问题。

本文章由计算机程序翻译，如有差异，请以英文原文为准。

求助全文

约1分钟内获得全文求助全文

来源期刊

Journal of Nuclear Materials 工程技术-材料科学：综合

CiteScore

5.70

自引率

25.80%

发文量

601

审稿时长

63 days

期刊介绍： The Journal of Nuclear Materials publishes high quality papers in materials research for nuclear applications, primarily fission reactors, fusion reactors, and similar environments including radiation areas of charged particle accelerators. Both original research and critical review papers covering experimental, theoretical, and computational aspects of either fundamental or applied nature are welcome. The breadth of the field is such that a wide range of processes and properties in the field of materials science and engineering is of interest to the readership, spanning atom-scale processes, microstructures, thermodynamics, mechanical properties, physical properties, and corrosion, for example. Topics covered by JNM Fission reactor materials, including fuels, cladding, core structures, pressure vessels, coolant interactions with materials, moderator and control components, fission product behavior. Materials aspects of the entire fuel cycle. Materials aspects of the actinides and their compounds. Performance of nuclear waste materials; materials aspects of the immobilization of wastes. Fusion reactor materials, including first walls, blankets, insulators and magnets. Neutron and charged particle radiation effects in materials, including defects, transmutations, microstructures, phase changes and macroscopic properties. Interaction of plasmas, ion beams, electron beams and electromagnetic radiation with materials relevant to nuclear systems.