Chromium Coating as a Surface Protection of Zirconium Alloys-Reference-Cited by-同舟云学术

Chromium Coating as a Surface Protection of Zirconium Alloys

Published:2017-12-20 Issue:5 Volume:61 Page:169-172
ISSN:1804-1213
Container-title:Koroze a ochrana materialu
language:en
Short-container-title:

Author:

Krausová A.¹,Tůma L.¹,Novák M.¹,Cvrček L.²,Krejčí J.³,Macák J.¹

Affiliation:

1. Ústav energetiky, Vysoká škola chemicko-technologická v Praze, 166 28 Praha 6 - Dejvice-Praha 6, Czech Republic

2. Ústav materiálového inženýrství, Fakulta strojní, České vysoké učení technické v Praze, 121 35 Praha 2 - Nové Město , Czech Republic

3. UJP Praha a.s., 156 00 Praha-Zbraslav , Czech Republic

Abstract

Abstract Increasing of nuclear safety, higher demands for longer nuclear fuel campaign and higher levels of burnout are based on improving the properties of zirconium alloys. Protective coatings appears to be a promising way to reduce their chemical reactivity and increase resistance to hydriding. In this work, a thin chromium coating applied to a standard Zr1Nb zirconium alloy was studied using in-situ impedance spectroscopy. Exposure was carried out at a temperature of 280 ° C and a pressure of 8 MPa in a simulated WWER primary coolant environment. The results show that the chromium-coated Zr1Nb alloy is under these conditions oxidized significantly slower than the non-coated alloy.

Publisher

Walter de Gruyter GmbH

Subject

General Materials Science

Reference14 articles.

1. 1. Große, M.; Lehmann, E.; Steinbrück, M.; Kühne, G.; Stuckert, J. Influence of oxide layer morphology on hydrogen concentration in tin and niobium containing zirconium alloys after high temperature steam oxidation. Journal of Nuclear Materials 2009, 385, 339-345.

2. 2. Labib, A.; Harris, M.J. Learning how to learn from failures: The Fukushima nuclear disaster. Engineering Failure Analysis 2015, 47, 117-128.

3. 3. Tsuruda, T.; Nuclear power plant explosions at Fukushima-Daiichi. Procedia Engineering 2015, 62, 71-77.

4. 4. Yamamoto, Y.; Field, K. G.; Snead, L. L. IAEA TECDOC SERIES 2016, 55.

5. 5. Ashcheulova, P.; Škoda, R.; Škarohlíd, J.; Taylora, A.; Fekete, L.; Fendrych, F.; Vega, R.; Shao, L.; Kalvoda, L.; Vratislav, S.; Cháb, V.; Horáková, K.; Kůsová, K.; Klimša, L.; Kopeček, J.; Sajdl, P.; Macák, J.; Johnson, S.; Kratochvílová, I. Thin polycrystalline diamond films protecting zirconium alloyssurfaces: From technology to layer analysis and applicationin nuclear facilities. Applied Surface Science 2015, 359, 621-628.

Cited by 3 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. Irradiation resistance of chromium coatings for ATFC in the temperature range 300–550°C;Journal of Nuclear Materials;2021-06

2. Study on neutronics of VVER-1200 with accident tolerant fuel cladding;Annals of Nuclear Energy;2019-02

3. Irradiation resistance of vacuum arc chromium coatings for zirconium alloy fuel claddings;Journal of Nuclear Materials;2018-11