The effect of plasma vacuum arc coating CrN, CrAl and Al2O3 on the process of saturation with deuterium alloy Zr + 1 % Nb

  • В. А. Бартак Научный физико-технологический центр МОН и НАН Украины
  • Г. Д. Толстолуцкая Национальный научный центр «Харьковский физико-технический институт»
Keywords: plasma coatings, zirconium alloy, gas phase, hydrogen permeability, nuclear reactions

Abstract

In this work the hydrogen permeability of plasma not drop coatings CrN, CrAl and Al2O3, deposited  on alloy Zr + 1 % Nb. To measure the space-deuterium concentration distributions in the source of zirconium alloy and alloy coated after saturation of the gas phase at a temperature of 300–600 °C was used method of nuclear reactions. Saturation carried out under conditions of pressure deuterium  PD = (2–9)·10–3 Pa, the saturation time was 120 minutes; also used the method of ion implantation. It was found that the coating CrN, CrAl and Al2O3 serve protective barrier, protecting the interaction of zirconium isotope of hydrogen. Deuterium does not penetrate into the bulk samples coated, adsorption their surface areas.

 

Downloads

Download data is not yet available.

Author Biographies

В. А. Бартак, Научный физико-технологический центр МОН и НАН Украины
с.н.с.
Г. Д. Толстолуцкая, Национальный научный центр «Харьковский физико-технический институт»
с.н.с.

References

Калин Б. А., Шмаков А. А. Поведение водорода в реакторных сплавах циркония // Физика и химия обработки материалов. — 2005. — No. 1. — С. 78–84.

Zinkle S. J., Terrani K. A., Gehin J. C., Ott L. J., Snead L. L. Accident tolerant fuels for LWRs: A perspective // Journal of Nuclear Materials. — 2014. — Vol. 448. — P. 374–379.

Yan Y., Burtseva T. A., Billone M. C. Hightemperature steam-oxidation behavior of Zr1Nb cladding alloy E110 // Journal of Nuclear Materials. — 2009. — Vol. 393. — P. 433–448.

Гельд П. В., Рябов Р. А., Мохрачова Л. П. Водород и физические свойства металлов и сплавов. — М.: Наука, 1985. — 232 с.

Levchuk D., Koch F., Maier H., Bolt H. Deuterium permeation through Eurofer and a-alumina coated Eurofer // Journal of Nuclear Materials. — 2004. — Vol. 328. — P. 103–106.

Чернов И. П.,Черданцев Ю. П., Лидер А. М. и др. // Поверхность. Рентген., синхротр. и нейтрон. исслед. — 2009. — No. 4. — 1 c.

IAEA-TECDOC-1410. Delayed hydride cracking in pressure tube nuclear reactors. International Atomic Energy Agency. —Vienna, 2004.

IAEA-TECDOC-1649. Delayed hydride cracking of zirconium alloy fuel cladding. International Atomic Energy Agenc. — Vienna, 2010.

Chao C. K., Yang K. C., Tseng C. C. Rupture of spent fuel zircaloy cladding in dry storage due to delayed hydride cracking // Nuclear Engineering and Design. — 2008. — Vol. 238, No.1. — P. 124–129.

Fukai Y. The metal-hydrogen system. Basic bulk properties.Series: Springer Series in Materials Science. — 2005. — Vol. 21. 2 rev. and updated ed., XII. — 497 p.

Davis J. R. ASM Handbook. Alloy phase diagrams. — 1992. — Vol. 3.— P. 1–1471. GmbH & Co. KGaA.Weinheim, 2008.

Гольдшмидт Х. Д. Сплавы внедрения. Выпуск II. — М.: «Мир», 1971.

Dupin N., Ansara I., Servant C., Toffolon C., Lemaignan C., Brachet J. C. A thermodynamic database for zirconium alloys // Journal of Nuclear Materials. — 1999. — Vol. 275, No. 3. — P. 287–295.
Published
2017-04-27
How to Cite
Бартак, В. А., & Толстолуцкая, Г. Д. (2017). The effect of plasma vacuum arc coating CrN, CrAl and Al2O3 on the process of saturation with deuterium alloy Zr + 1 % Nb. Journal of Surface Physics and Engineering, 1(4), 398-403. Retrieved from https://periodicals.karazin.ua/pse/article/view/8503