{"title":"Study of oxide and α-Zr(O) growth kinetics in the temperature range 1000–1500 °C during steam oxidation of Indian PHWR cladding","authors":"Tapan K. Sawarn , Suparna Banerjee , Saee Jagtap , Alexander Rajath , Raman Saini , Sayandeep Kundu , Sripooja Mishra , P.P. Nanekar","doi":"10.1016/j.pnucene.2025.105632","DOIUrl":null,"url":null,"abstract":"<div><div>Isothermal steam oxidation of Indian pressurized heavy water reactors (IPHWRs) cladding (Zircaloy-4) has been studied in the temperature range of 1000–1500 °C. Growth kinetics of inherently brittle phases, oxide and oxygen stabilized α-Zr, developed during the high temperature steam oxidation were established. A ductile phase known as prior β-Zr, lying either underneath the α-Zr(O), in case of a single sided oxidation, or in between two layers of α-Zr(O) at the inner and the outer surface of the clad, governs the extent of embrittlement of the clad. Thickness of prior β-Zr is decided by the rate of growth of oxide and oxygen stabilized α-Zr. The kinetic rate constant K<sub>p</sub> (cm<sup>2</sup>/sec) obeyed a parabolic rate equation. The Arrhenius expression of parabolic rate constants for oxide scale and α-Zr(O) layer growth compares well with those established by other investigators. An in-house oxidation model, OXYCON was evaluated against the experimental data of oxide and α-Zr(O) layer thickness. The model under-predicted the oxide layer thickness and over-predicted the α-Zr(O) layer thickness in its existing form. However the prediction of oxide, α-Zr (O) and total oxide+α-Zr(O) improved to a significant extent by using kinetic equations derived in the present study done on the indigenously fabricated Zircaloy-4 cladding. Hence, successively the prediction of the prior β-Zr layer thickness could also be done with further accuracy.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"180 ","pages":"Article 105632"},"PeriodicalIF":3.3000,"publicationDate":"2025-02-01","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/S0149197025000307","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
Isothermal steam oxidation of Indian pressurized heavy water reactors (IPHWRs) cladding (Zircaloy-4) has been studied in the temperature range of 1000–1500 °C. Growth kinetics of inherently brittle phases, oxide and oxygen stabilized α-Zr, developed during the high temperature steam oxidation were established. A ductile phase known as prior β-Zr, lying either underneath the α-Zr(O), in case of a single sided oxidation, or in between two layers of α-Zr(O) at the inner and the outer surface of the clad, governs the extent of embrittlement of the clad. Thickness of prior β-Zr is decided by the rate of growth of oxide and oxygen stabilized α-Zr. The kinetic rate constant Kp (cm2/sec) obeyed a parabolic rate equation. The Arrhenius expression of parabolic rate constants for oxide scale and α-Zr(O) layer growth compares well with those established by other investigators. An in-house oxidation model, OXYCON was evaluated against the experimental data of oxide and α-Zr(O) layer thickness. The model under-predicted the oxide layer thickness and over-predicted the α-Zr(O) layer thickness in its existing form. However the prediction of oxide, α-Zr (O) and total oxide+α-Zr(O) improved to a significant extent by using kinetic equations derived in the present study done on the indigenously fabricated Zircaloy-4 cladding. Hence, successively the prediction of the prior β-Zr layer thickness could also be done with further accuracy.
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.