Steam oxidation of Zr-1.5Nb-0.4Sn-0.2Fe-0.1Cr and Zircaloy-4 at 900-1200°C

被引:29
作者
Baek, Jong Hyuk [1 ]
Jeong, Yong Hwan [1 ]
机构
[1] Korea Atom Energy Res Inst, Adv Core Mat Lab, Taejon 305600, South Korea
关键词
D O I
10.1016/j.jnucmat.2006.10.015
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
The steam oxidation characteristics for the Zr-1.5Nb-0.4Sn-0.2Fe-0.1Cr (HANA-4) and Zircaloy-4 claddings were elucidated at LOCA temperatures of 900-1200 degrees C by using a modified thermo-gravimetric analyzer. After the oxidation tests, the oxidation behaviors, oxidation rates, surface appearances, and microstructures of the as-received, as-oxidized, and burn-up simulated claddings were evaluated in this study. The high-temperature oxidation resistance of the as-received HANA-4 cladding was superior to that of the Zircaloy-4. The superior oxidation resistance of the HANA-4 cladding could be attributed to the higher Nb and the lower Sn within its cladding. The pre-oxidized layer formed at the low temperatures below 500 degrees C could retard the oxidation rate at the high temperatures above 900 degrees C. And the soundness of the pre-oxidized layer formed at a lower temperature could influence the oxidation kinetics and the rate constants during a steam oxidation at LOCA temperatures from 900 to 1200 degrees C. (c) 2006 Elsevier B.V. All rights reserved.
引用
收藏
页码:30 / 40
页数:11
相关论文
共 30 条
[1]  
AOMI M, 2000, P ANS TOP M CIT PARK
[2]   Oxidation kinetics of Zircaloy-4 and Zr-1Nb-1Sn-0.1Fe at temperatures of 700-1200°C [J].
Baek, JH ;
Park, KB ;
Jeong, YH .
JOURNAL OF NUCLEAR MATERIALS, 2004, 335 (03) :443-456
[3]  
Baker L., 1962, ANL 6548
[4]  
BOHMERT J, 1993, NUCL ENG DES, V147, P53
[5]  
Brachet J.-C., 2001, TCM FUEL BEH TRANS L
[6]  
Cathcart JV., 1977, ORNLNUREG17
[7]  
CHUNG HM, 1984, ASTM, P793
[8]  
DOBSON WG, 1977, ASTM STP, V633, P150
[9]  
Erbacher F., 1987, Zircon. Nucl. Ind., V939, P451
[10]  
Etoh Y., 1996, ASTM STP, V1295, P825