{"title":"裂纹铬包覆锆合金后气胀及爆裂蒸汽氧化的研究","authors":"Hyunwoo Yook, Sunghoon Joung, Youho Lee","doi":"10.1016/j.jnucmat.2025.156095","DOIUrl":null,"url":null,"abstract":"<div><div>This study presents a mechanistic model for coating cracking and subsequent oxidation of burst Cr-coated Zircaloy cladding under Design Basis Accident (DBA) conditions. A series of sequential simulated Loss Of Coolant Accident (LOCA) experiments were conducted using the <em>i</em>-LOCA facility and the high-temperature oxidation facility at Seoul National University. 1.5 m long Cr-coated claddings(15μm) with inserted ZrO<sub>2</sub> pellets were internally pressurized and inductively heated in an inert environment using the <em>i</em>-LOCA facility to induce ballooning and burst under various internal pressures and two pellet configurations—cylindrical and single powder pellet—designed to simulate unfragmented (<55 GWd/MTU) and fully pulverized (∼94 GWd/MTU) fuel conditions, respectively. The resulting post-burst cladding geometries with various burst hoop strains were analyzed via 3D scanning. The burst region (±1.5 inches from the burst center) of the post-burst specimens was subsequently subjected to two-sided oxidation using the high-temperature oxidation facility.</div><div>Mechanistic models for coating cracking and Equivalent Cladding Reacted (ECR) calculation were developed based on the conventional definition of ECR and a phenomenological understanding derived from microstructural characterization of post-burst specimens, thereby providing a general framework applicable irrespective of the specific coating. Under DBA conditions, the additional oxidation attributable to coating cracking was quantified to be no more than 25 % relative to inner-sided oxidation. Accident coping time analyses indicated that, even when accounting for burst-induced deformation and coating cracking, the application of Cr coating maintains compliance with existing regulatory safety margins.</div></div>","PeriodicalId":373,"journal":{"name":"Journal of Nuclear Materials","volume":"616 ","pages":"Article 156095"},"PeriodicalIF":3.2000,"publicationDate":"2025-08-06","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":"{\"title\":\"Post-ballooning and burst steam oxidation of accident tolerant zirconium alloy cladding with cracked chromium coating\",\"authors\":\"Hyunwoo Yook, Sunghoon Joung, Youho Lee\",\"doi\":\"10.1016/j.jnucmat.2025.156095\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"<div><div>This study presents a mechanistic model for coating cracking and subsequent oxidation of burst Cr-coated Zircaloy cladding under Design Basis Accident (DBA) conditions. A series of sequential simulated Loss Of Coolant Accident (LOCA) experiments were conducted using the <em>i</em>-LOCA facility and the high-temperature oxidation facility at Seoul National University. 1.5 m long Cr-coated claddings(15μm) with inserted ZrO<sub>2</sub> pellets were internally pressurized and inductively heated in an inert environment using the <em>i</em>-LOCA facility to induce ballooning and burst under various internal pressures and two pellet configurations—cylindrical and single powder pellet—designed to simulate unfragmented (<55 GWd/MTU) and fully pulverized (∼94 GWd/MTU) fuel conditions, respectively. The resulting post-burst cladding geometries with various burst hoop strains were analyzed via 3D scanning. The burst region (±1.5 inches from the burst center) of the post-burst specimens was subsequently subjected to two-sided oxidation using the high-temperature oxidation facility.</div><div>Mechanistic models for coating cracking and Equivalent Cladding Reacted (ECR) calculation were developed based on the conventional definition of ECR and a phenomenological understanding derived from microstructural characterization of post-burst specimens, thereby providing a general framework applicable irrespective of the specific coating. Under DBA conditions, the additional oxidation attributable to coating cracking was quantified to be no more than 25 % relative to inner-sided oxidation. Accident coping time analyses indicated that, even when accounting for burst-induced deformation and coating cracking, the application of Cr coating maintains compliance with existing regulatory safety margins.</div></div>\",\"PeriodicalId\":373,\"journal\":{\"name\":\"Journal of Nuclear Materials\",\"volume\":\"616 \",\"pages\":\"Article 156095\"},\"PeriodicalIF\":3.2000,\"publicationDate\":\"2025-08-06\",\"publicationTypes\":\"Journal Article\",\"fieldsOfStudy\":null,\"isOpenAccess\":false,\"openAccessPdf\":\"\",\"citationCount\":\"0\",\"resultStr\":null,\"platform\":\"Semanticscholar\",\"paperid\":null,\"PeriodicalName\":\"Journal of Nuclear Materials\",\"FirstCategoryId\":\"5\",\"ListUrlMain\":\"https://www.sciencedirect.com/science/article/pii/S0022311525004891\",\"RegionNum\":2,\"RegionCategory\":\"工程技术\",\"ArticlePicture\":[],\"TitleCN\":null,\"AbstractTextCN\":null,\"PMCID\":null,\"EPubDate\":\"\",\"PubModel\":\"\",\"JCR\":\"Q3\",\"JCRName\":\"MATERIALS SCIENCE, MULTIDISCIPLINARY\",\"Score\":null,\"Total\":0}","platform":"Semanticscholar","paperid":null,"PeriodicalName":"Journal of Nuclear Materials","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S0022311525004891","RegionNum":2,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q3","JCRName":"MATERIALS SCIENCE, MULTIDISCIPLINARY","Score":null,"Total":0}
Post-ballooning and burst steam oxidation of accident tolerant zirconium alloy cladding with cracked chromium coating
This study presents a mechanistic model for coating cracking and subsequent oxidation of burst Cr-coated Zircaloy cladding under Design Basis Accident (DBA) conditions. A series of sequential simulated Loss Of Coolant Accident (LOCA) experiments were conducted using the i-LOCA facility and the high-temperature oxidation facility at Seoul National University. 1.5 m long Cr-coated claddings(15μm) with inserted ZrO2 pellets were internally pressurized and inductively heated in an inert environment using the i-LOCA facility to induce ballooning and burst under various internal pressures and two pellet configurations—cylindrical and single powder pellet—designed to simulate unfragmented (<55 GWd/MTU) and fully pulverized (∼94 GWd/MTU) fuel conditions, respectively. The resulting post-burst cladding geometries with various burst hoop strains were analyzed via 3D scanning. The burst region (±1.5 inches from the burst center) of the post-burst specimens was subsequently subjected to two-sided oxidation using the high-temperature oxidation facility.
Mechanistic models for coating cracking and Equivalent Cladding Reacted (ECR) calculation were developed based on the conventional definition of ECR and a phenomenological understanding derived from microstructural characterization of post-burst specimens, thereby providing a general framework applicable irrespective of the specific coating. Under DBA conditions, the additional oxidation attributable to coating cracking was quantified to be no more than 25 % relative to inner-sided oxidation. Accident coping time analyses indicated that, even when accounting for burst-induced deformation and coating cracking, the application of Cr coating maintains compliance with existing regulatory safety margins.
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.