REVIEW OF SMALL SPECIMEN TEST TECHNIQUES FOR IRRADIATION TESTING

被引:92
作者
LUCAS, GE [1 ]
机构
[1] UNIV CALIF SANTA BARBARA, DEPT MAT, SANTA BARBARA, CA 93106 USA
来源
METALLURGICAL TRANSACTIONS A-PHYSICAL METALLURGY AND MATERIALS SCIENCE | 1990年 / 21卷 / 05期
关键词
D O I
10.1007/BF02656531
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
Small specimen test technology has evolved out of the necessity to develop and monitor materials proposed for or used in nuclear power generation systems. Development of materials for improved cladding and in-core structures for fission reactors and assessment of core materials and pressure vessel steels already under irradiation necessitated the use of specimens which fit into existing irradiation space or which could be extracted from irradiated structures, such as cladding or ducts. Interest in simulating neutron irradiation by light and heavy ion irradiation led to the development of thin foil and wire geometry specimens. Further, interest in developing materials for fusion reactors has added additional constraints on specimen sizes associated with available irradiation volumes in existing and proposed high-energy neutron irradiation facilities. Consequently, a wide array of specimen geometries and test techniques has now been developed. It is the purpose of this paper to review these techniques and examine their status, problems, and potential for future applications. © 1990 The Metallurgical of Society of AIME.
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页码:1105 / 1119
页数:15
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