Published May 2014 | Version v1
Book

Effect of pre-oxidized film on high-temperature oxidation behavior for N18 zirconium alloy in steam

  • 1. Science and Technology on Reactor Fuel and Material Laboratory, NPIC, Chengdu (China)

Description

Understanding the charicteristics of N18 zirconium alloy developed by china during the postulated LOCA conditions can supply the reference data for the fuel cladding design and safety analysis and evaluation when N18 zirconium alloy used in nuclear reactor. The effect of pre-oxidized film with different thickness on the oxidation behavior for N18 zirconium alloy in steam at the temperature of 700 ℃, 900 ℃, 1100 ℃ is studied. The results show that pre-oxidized film would retard the oxidation rate of N18 zirconium alloy in steam below the temperature of 900 ℃, but the effect is reducing with the temperature increase. The effect pre-oxidized film on oxidation resistence for N18 zirconium alloy can be neglected. (authors)

Part of:
Progress report on nuclear science and technology in China (Vol.3). Proceedings of academic annual meeting of China Nuclear Society in 2013, No.4--nuclear material sub-volume

Additional details

Publishing Information

Publisher
China Nuclear Physics Society
Imprint Place
Beijing (China)
ISBN
978-7-5022-6126-9
Imprint Title
Progress report on nuclear science and technology in China (Vol.3). Proceedings of academic annual meeting of China Nuclear Society in 2013, No.4--nuclear material sub-volume
Imprint Pagination
375 p.
Journal Page Range
p. 359-364

Conference

Title
2013 academic annual meeting of China Nuclear Society
Dates
10-14 Sep 2013
Place
Harbin (China)

Optional Information

Notes
6 figs., 1 tab., 9 refs.