{"title":"Induction heating of composite billet of T91 and Zircaloy-4 for manufacturing of double clad tube: Simulation and experimental validation","authors":"Navinkumar Dubey , Aarti Chaudhary , Arijit Laik , Sugilal Gopalakrishnan , Komal Kapoor","doi":"10.1016/j.pnucene.2025.105761","DOIUrl":null,"url":null,"abstract":"<div><div>Metallic fuel is the preferred choice for future Fast Breeder Reactors due to higher breeding ratio. A mechanical bonded double clad tube with a T91 steel outer shell and Zr inner liner is a potential choice for metallic fuel. However, the metallurgical bonded clad tube will have superior properties against the mechanical bonded tube. The metallurgically bonded co-axial tube of T91 and Zr/Zircaloy-4 (Zr-4) can be manufactured by the co-extrusion route. The significant difference in deformation behavior of the two alloys demands a temperature gradient over the thickness of the composite billet for co-extrusion. The fine control of temperature gradient across the cross section of the billet can be achieved only by induction heating. The present study focuses on simulating the induction preheating process of a double-clad billet of outer T91 and inner Zr-4. A 2-D axisymmetric model was considered and simulation studies with several key parameters such as coil frequency, current, pitch, and diameter were carried out with an aim to reduce temperature variation at the interface of T91 and Zr-4 in the billet. Simulations using optimised coil frequency and current reduced the temperature variation at the interface to as low as 22 °C. Subsequent simulations with variable coil pitch and diameter reduced the temperature variation to less than ±3 °C at the interface ignoring axial ends. The mean temperature across the T91 was 967.4 °C and across Zr-4 was 850.3 °C. Experiments were conducted for the co-axial tube of T91 and Zr-4 to validate the simulation model.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"185 ","pages":"Article 105761"},"PeriodicalIF":3.3000,"publicationDate":"2025-03-28","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Progress in Nuclear Energy","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S0149197025001593","RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q1","JCRName":"NUCLEAR SCIENCE & TECHNOLOGY","Score":null,"Total":0}
引用次数: 0
Abstract
Metallic fuel is the preferred choice for future Fast Breeder Reactors due to higher breeding ratio. A mechanical bonded double clad tube with a T91 steel outer shell and Zr inner liner is a potential choice for metallic fuel. However, the metallurgical bonded clad tube will have superior properties against the mechanical bonded tube. The metallurgically bonded co-axial tube of T91 and Zr/Zircaloy-4 (Zr-4) can be manufactured by the co-extrusion route. The significant difference in deformation behavior of the two alloys demands a temperature gradient over the thickness of the composite billet for co-extrusion. The fine control of temperature gradient across the cross section of the billet can be achieved only by induction heating. The present study focuses on simulating the induction preheating process of a double-clad billet of outer T91 and inner Zr-4. A 2-D axisymmetric model was considered and simulation studies with several key parameters such as coil frequency, current, pitch, and diameter were carried out with an aim to reduce temperature variation at the interface of T91 and Zr-4 in the billet. Simulations using optimised coil frequency and current reduced the temperature variation at the interface to as low as 22 °C. Subsequent simulations with variable coil pitch and diameter reduced the temperature variation to less than ±3 °C at the interface ignoring axial ends. The mean temperature across the T91 was 967.4 °C and across Zr-4 was 850.3 °C. Experiments were conducted for the co-axial tube of T91 and Zr-4 to validate the simulation model.
期刊介绍:
Progress in Nuclear Energy is an international review journal covering all aspects of nuclear science and engineering. In keeping with the maturity of nuclear power, articles on safety, siting and environmental problems are encouraged, as are those associated with economics and fuel management. However, basic physics and engineering will remain an important aspect of the editorial policy. Articles published are either of a review nature or present new material in more depth. They are aimed at researchers and technically-oriented managers working in the nuclear energy field.
Please note the following:
1) PNE seeks high quality research papers which are medium to long in length. Short research papers should be submitted to the journal Annals in Nuclear Energy.
2) PNE reserves the right to reject papers which are based solely on routine application of computer codes used to produce reactor designs or explain existing reactor phenomena. Such papers, although worthy, are best left as laboratory reports whereas Progress in Nuclear Energy seeks papers of originality, which are archival in nature, in the fields of mathematical and experimental nuclear technology, including fission, fusion (blanket physics, radiation damage), safety, materials aspects, economics, etc.
3) Review papers, which may occasionally be invited, are particularly sought by the journal in these fields.