The terminal solid solubility of hydrogen in irradiated Zircaloy-2 and microscopic modeling of hydride behavior

被引:43
|
作者
Une, K. [1 ]
Ishimoto, S. [1 ]
Etoh, Y. [1 ]
Ito, K. [2 ]
Ogata, K. [3 ]
Baba, T. [3 ]
Kamimura, K. [3 ]
Kobayashi, Y. [4 ]
机构
[1] Nippon Nucl Fuel Dev Co Ltd, Oarai, Ibaraki 3111313, Japan
[2] Global Nucl Fuel Japan Co Ltd, Yokosuka, Kanagawa 2390836, Japan
[3] Japan Nucl Energy Safety Org, Minato Ku, Tokyo 1050001, Japan
[4] MOX Corp, Mito, Ibaraki 3100853, Japan
关键词
ALPHA-PHASE; STRESS; ZIRCONIUM; HEAT;
D O I
10.1016/j.jnucmat.2009.01.017
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
Differential scanning calorimetry (DSC) has been applied to elucidate the terminal solid solubility (TSS) of hydrogen in Zircaloy-2 cladding tubes and spacer bands irradiated in commercial BWRs. While recovery of irradiation defects during the first heating stage of as-irradiated specimens made the DSC peak of hydride dissolution dull or broader, no significant difference was detected in the TSS between unirradiated and irradiated Zircaloy-2, irrespective of fast neutron fluence. The effect of post-irradiation annealing on TSS was also examined. The results suggest almost no interaction between irradiation defects and dissolved hydrogen or hydrides at temperatures around 300 degrees C. Using the present TSS data and reported hydrogen- and hydride-related properties, a microscopic analysis code HYMAC for analyzing hydride behavior in cladding tube with textured grains was constructed. Stress-induced preferential precipitation and dissolution of hydrides were reproduced by adopting a TSS sub-model in which the solubilities decrease in proportion to stress normal to the habit plane in grains and to grain faces. Analyzed results by the code were consistent with typical experimental results of hydride behavior. (c) 2009 Elsevier B.V. All rights reserved.
引用
收藏
页码:127 / 136
页数:10
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