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Purpose: The aim of the research was to identify possibility of extending the life time of zirconium claddings. Materials used in nuclear reactors work in extremely hard conditions: irradiation, corrosion, stress. Zirconium alloys, due to their good water corrosion and radiation resistance at normal working conditions of nuclear reactors are used as cladding material for fuel elements. In the case of loss-of-coolant accident (LOCA), the extremely fast oxidation of zirconium at steam or air/steam mixture at temperatures above 800°C results in intense hydrogen generation and possible hydrogen-oxide mixture explosion. The development of the solution to minimize the risk of the accidents mentioned above is urgently needed. The concept of Accident Tolerant Materials (ATM) has been developed recently. Design/methodology/approach: Zirconium surface were treated with 30 high intensity pulsed plasma beams (HIPPB) Cr+Ar, Y+Ar or Al+Ar, with energy density of 4.0 J/cm2. Oxidation tests: autoclave (water, 360°C, 19.50 MPa) for 7 and 40 days and oven (700°C and 800°C/1000 s/air) followed by cooling in water were performed. Samples were characterised with: SEMs, EDS and GXRD. Findings: Zirconium samples with modified surface layer showed the higher resistance for oxidation in simulated conditions of normal work of PWR reactor and in elevated temperatures. Originality/value: Carried out work was connected with new concept of development accident tolerant materials - ATM.
Wydawca
Rocznik
Tom
Strony
53--57
Opis fizyczny
Bibliogr. 12 poz.
Twórcy
autor
- Institute of Nuclear Chemistry and Technology, ul. Dorodna 16, 03-195 Warszawa, Poland
autor
- Institute of Nuclear Chemistry and Technology, ul. Dorodna 16, 03-195 Warszawa, Poland
autor
- National Centre for Nuclear Research, ul. A. Sołtana 7, 05-400 Otwock-Świerk, Poland
autor
- Institute of Nuclear Chemistry and Technology, ul. Dorodna 16, 03-195 Warszawa, Poland
Bibliografia
- [1] S.J. Zinkle, K.A. Terrani, J.C. Gehin, L.J. Ott, L.L. Snead, Accident tolerant fuels for LWRs: A perspective, Journal of Nuclear Materials 448/1-3 (2014) 374-379.
- [2] R. Mariani, P. Medveedev, D.L. Porter, S.L. Hayes, J.I. Cole, X.-M. Bai, Novel Accident-Tolerant Fuel Meat and Cladding, Top Fuels September (2013) 15-19.
- [3] P. Bossis, D. Pêcheur, K. Hanifi, J. Thomazet, M. Blat, Comparison of the high burn-up corrosion on M5 and low tin Zircaloy-4, Journal of ASTM International 3/1 (2006) 494-525.
- [4] Y.H. Lee, T. McKrell, M.S. Kazimi, Safety of light water reactor fuel with silicon carbide cladding, Advanced Nuclear Power Program, MIT-ANP-TR- 150, 2014.
- [5] T. Sawabe, T. Sonoda, M. Furuya, S. Kitajima, M. Kinoshita, M. Tokiwai, Microstructure of oxide layers formed on zirconium alloy by air oxidation, uniform corrosion and fresh-green surface modification, Journal of Nuclear Materials 419/1 (2011) 310-319.
- [6] I.P. Chernov, S.V. Ivanova, M.Kh. Krening, N. Koval’, V.V. Larionov, A.M. Lider, N.S. Pushilina, E.N. Stepanova, O.M. Stepanova, Yu.P. Cherdantsev, Properties and structural state of the surface layer in a zirconium alloy modified by a pulsed electron beam and saturated by hydrogen, Zhurnal Tekhnicheskoi Fiziki 82/3 (2012) 81-87.
- [7] X. Bai, J. Xu, F. He, Y. Fan, The air oxidation of yttrium ion implanted zircaloy-4 at 500°C, Nuclear Instruments and Methods in Physics Research B 160/1 (2000) 49-53.
- [8] N. Chaia, S. Mathieu, F. Rouillard, M. Vilasi, The ability of silicide coating to delay the catastrophic oxidation of vanadium under severe conditions, Journal of Nuclear Materials 457 (2015) 124-129.
- [9] M.W. Barsoum, MAX Phases - Properties of machinable ternary carbides and nitrides, Wiley-VCH Verlag GmBH, Weinheim, Germany, 2013.
- [10] K.A. Terrani, S.J. Zinkle, L.L. Snead, Advanced oxidation-resistant iron-based alloys for LWR fuel cladding, Journal of Nuclear Materials 448 (2014) 420-435.
- [11] Z. Werner, J. Piekoszewski, W. Szymczyk, Generation of high-intensity pulsed ion and plasma beams for material processing, Vacuum 63 (2001) 701-708.
- [12] T.R. Allen, R.J.M. Konings, A.T. Motta, Corrosion of Zirconium Alloys, Comprehensive Nuclear Materials 5 (2012) 49-68.
Uwagi
Opracowanie ze środków MNiSW w ramach umowy 812/P-DUN/2016 na działalność upowszechniającą naukę (zadania 2017)
Typ dokumentu
Bibliografia
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