IRRADIATION GROWTH IN ANNEALED ZIRCALOY-2

被引：37

作者：

MURGATROYD, RA

ROGERSON, A

机构：

[1] UKAEA, Risley Nuclear Power Development Laboratories, Risley, Warrington

来源：

JOURNAL OF NUCLEAR MATERIALS | 1979年 / 79卷 / 02期

关键词：

D O I：

10.1016/0022-3115(79)90095-3

中图分类号：

T [工业技术];

学科分类号：

08 ;

摘要：

Irradiation growth in annealed zircaloy-2 has been studied at 353 K and 553 K. Growth is initially rapid during irradiation at 353 K but saturates above a dose of 2 ×1024 n/m2. The saturation growth strain is found to be strongly dependent upon crystallographic texture. At 553 K, growth in longitudinal specimens attenuates with dose but does not saturate up to a dose of 12.3 ×1024n/m2; in transverse specimens growth is observed to saturate at a dose of less than 1.3 ×1024n/m2. The effect of changing irradiation temperature has been studied. The observed growth behaviour is interpreted in terms of a growth model in which growth is produced by the formation of sub-microscopic interstitial clusters on prism planes, possibly combined with a small volume increase. © 1979.

引用

页码：302 / 311

页数：10

共 18 条

[1]

ADAMSON RB, 1978, P ASTM INT C ZIRCONI, P326

[2]

[Anonymous], COMMUNICATION

[3]

Buckley S. N., 1962, PROPERTIES REACTOR M, P413

[4] CONTRIBUTION OF DISLOCATION LOOPS TO RADIATION GROWTH AND CREEP OF ZIRCALOY-2 [J].