Oxidation properties of Zr-Nb alloys at 973-1273 K in air

被引:32
作者
Arima, Tatsumi [1 ]
Miyata, Kensaku [1 ]
Idemitsu, Kazuya [1 ]
Inagaki, Yaohiro [1 ]
机构
[1] Kyushu Univ, Fac Engn, Dept Appl Quantum Phys & Nucl Engn, Fukuoka 8190395, Japan
关键词
Zr-Nb alloy; High temperature oxidation; Reactor accident; 6ZrO(2)-Nb(2)O(5); HIGH-TEMPERATURE OXIDATION; CORROSION BEHAVIOR; ZIRCONIUM ALLOYS; XNB ALLOYS; KINETICS; ZIRCALOY-4; OXYGEN; PHASE; OXIDE; ATMOSPHERE;
D O I
10.1016/j.pnucene.2008.08.001
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
In order to investigate the oxidation behavior of LWR cladding materials under the condition of reactor accidents, e.g. LOCA, Zr-Nb alloys with 1-10 wt%Nb and Zircaloy-4 (0 wt%Nb) were oxidized at 973-1273 K in dry air. The weight gain due to oxidation increased with Nb content at 973 and 1073 K was the smallest for 2.5 wt%Nb at 1173 and 1273 K. The oxidation kinetics obeyed the parabolic rate law without a few cases, e.g. 6-10 wt%Nb and 1273 K. The parabolic rate constant at high temperatures had the somewhat low activation energy compared to that at low temperatures. These results implied that such oxidation behaviors of Zr-Nb alloys related to the lattice structures of oxide films as well as underlying metal during oxidation. Especially at high temperatures, 6ZrO(2)-Nb(2)O(5) compound might promote the oxidation of Zr-Nb alloys with high content of Nb. (C) 2008 Elsevier Ltd. All rights reserved.
引用
收藏
页码:307 / 312
页数:6
相关论文
共 26 条
[1]  
[Anonymous], 1978, Report KFK 2587
[2]  
[Anonymous], NUCL ENG DES
[3]   Oxidation properties of Zr-Nb alloys at 500-600°C under low oxygen potentials [J].
Arima, T ;
Miyata, K ;
Inagaki, Y ;
Idemitsu, K .
CORROSION SCIENCE, 2005, 47 (02) :435-446
[4]   The oxidation kinetics and the structure of the oxide film on Zircaloy before and after the kinetic transition [J].
Arima, T ;
Masuzumi, T ;
Furuya, H ;
Idemitsu, K ;
Inagaki, Y .
JOURNAL OF NUCLEAR MATERIALS, 2001, 294 (1-2) :148-153
[5]   Oxidation kinetics of Zircaloy-2 between 450°C and 600°C in oxidizing atmosphere [J].
Arima, T ;
Moriyama, K ;
Gaja, N ;
Furuya, H ;
Idemitsu, K ;
Inagaki, Y .
JOURNAL OF NUCLEAR MATERIALS, 1998, 257 (01) :67-77
[6]   Steam oxidation of Zr-1.5Nb-0.4Sn-0.2Fe-0.1Cr and Zircaloy-4 at 900-1200°C [J].
Baek, Jong Hyuk ;
Jeong, Yong Hwan .
JOURNAL OF NUCLEAR MATERIALS, 2007, 361 (01) :30-40
[7]  
BAKER L, 1962, AL6548
[8]   OXIDATION REACTION-KINETICS OF ZIRCALOY-4 IN AN UNLIMITED STEAM ENVIRONMENT [J].
BALLINGER, RG ;
DOBSON, WG ;
BIEDERMAN, RR .
JOURNAL OF NUCLEAR MATERIALS, 1976, 62 (2-3) :213-220
[9]  
Cathcart J., 1977, ORNLNUREG17
[10]  
Etoh Y., 1996, ZIRCONIUM NUCL IND 1, P825