Effect of blisters and rims on radial hydride precipitation in fuel elements under dry storage conditions

被引:0
作者
Ines Luppo, Maria [1 ]
Roberto Amoruso, Francisco [2 ]
Haddad, Roberto [1 ]
Domizzi, Gladys [1 ,3 ]
机构
[1] Argentina Atom Energy Commiss, Mat Dept, Av Gral Paz 1499,B1650KNA, San Martin, Buenos Aires, Argentina
[2] Argentina Atom Energy Commiss, Nucl Fuel Dept, Av Gral Paz 1499,B1650KNA, San Martin, Buenos Aires, Argentina
[3] Natl Univ San Martin, Argentina Atom Energy Commiss, Inst Sabato, Av Gral Paz 1499,B1650KNA, San Martin, Buenos Aires, Argentina
来源
MATERIA-RIO DE JANEIRO | 2018年 / 23卷 / 02期
关键词
zirconium hydrides; dry storage; Zry-4; blister; hydride reorientation; EMBRITTLEMENT;
D O I
10.1590/S1517-707620180002.0434
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
Hydrogen enters in Zry clads during fuel element life in service; when hydrogen exceeds the terminal solid solubility, circumferential hydrides are precipitated. In the presence of thermal gradients, produced for instance by oxide spallation, localized concentration of hydrides - known as blisters - can be formed. Due to the fact that zirconium hydrides have a lower density that zirconium alloys, stresses are produced around blisters. These stresses may overcome the necessary threshold to precipitate radial hydrides. Moreover, cracks inside blisters may act as initiators of delayed hydride cracking (DHC). In the dry storage facilities developed for Atucha 1, Zry - 4 clads of spent fuel elements (SFE) must withstand environmental conditions which include maximum temperature of 200 degrees C and internal SFE pressure of similar to 75 bar (value at end of cycle). During dry storage, if blisters are present, stresses around them are superposed to circumferential stresses generated by the internal pressure due to fission gasses helping precipitation and/or growth of radial hydrides and DHC process. In order to assess this possibility, in the present work sections of Zry-4 cladding were hydrided. Blisters have been grown by thermal gradient under different conditions of temperature and shapes of thermal contact in order to obtain different blister dimensions and fraction of radial hydrides. After blister formation, some specimens were subjected to Hydride Reorientation Test (HRT) by applying an internal pressure of 75 bar at 200 degrees C. Finally, tubes were sectioned and metallographically analyzed looking for radial hydrides. In some samples radial hydrides were observed, which effectively grew by the internal pressure of Zry-cladding during HRT.
引用
收藏
页数:10
相关论文
共 13 条
[1]  
AOMI M., 1998, STP ASTM, V1505, P651
[2]   HYDRIDE EMBRITTLEMENT IN ZIRCALOY-4 PLATE .1. INFLUENCE OF MICROSTRUCTURE ON THE HYDRIDE EMBRITTLEMENT IN ZIRCALOY-4 AT 20-DEGREES-C AND 350-DEGREES-C [J].
BAI, JB ;
PRIOUL, C ;
FRANCOIS, D .
METALLURGICAL AND MATERIALS TRANSACTIONS A-PHYSICAL METALLURGY AND MATERIALS SCIENCE, 1994, 25 (06) :1185-1197
[3]   Rupture of spent fuel Zircaloy cladding in dry storage due to delayed hydride cracking [J].
Chao, C. K. ;
Yang, K. C. ;
Tseng, C. C. .
NUCLEAR ENGINEERING AND DESIGN, 2008, 238 (01) :124-129
[4]   Hydride distribution around a blister in Zr-2.5Nb pressure tubes [J].
Domizzi, G ;
Vigna, G ;
Bermúdez, S ;
Ovejero-García, J .
JOURNAL OF NUCLEAR MATERIALS, 1999, 275 (03) :255-267
[5]  
ELLS C. E, 1978, INFLUENCE HYDROGEN B, P32
[6]  
GLENDENING A., 2004, STP ASTM, V1467, P833
[7]  
HERMANN A., 2009, STP ASTM, V1505, P141
[8]   EFFECT OF DISPERSION AND SPHEROIDIZATION TREATMENT OF DELTA-ZIRCONIUM HYDRIDES ON THE MECHANICAL-PROPERTIES OF ZIRCALOY [J].
LIN, SC ;
HAMASAKI, M ;
CHUANG, YD .
NUCLEAR SCIENCE AND ENGINEERING, 1979, 71 (03) :251-266
[9]  
Marshall R.P., 1963, T ASM, V56M, P693
[10]  
McMinn A., 1998, STP ASTM, P173