Thermally activated deformation of irradiated reactor pressure vessel steel

被引：5

作者：

Böhmert, J ^{[1
]}

Müller, G ^{[1
]}

机构：

[1] Forschungszentrum Rossendorf EV, Inst Sicherheitsforsch, Abt Mat & Komponenten, D-01314 Dresden, Germany

来源：

JOURNAL OF NUCLEAR MATERIALS | 2002年 / 301卷 / 2-3期

关键词：

Activation analysis - Deformation - Friction - Irradiation - Pressure vessels - Radiation hardening - Steel - Strain rate - Tensile testing - Thermal effects;

D O I：

10.1016/S0022-3115(02)00709-2

中图分类号：

T [工业技术];

学科分类号：

08 ;

摘要：

Temperature and strain rate change tensile tests were performed on two VVER 1000-type reactor pressure vessel welds with different contents of nickel in unirradiated and irradiated conditions in order to determine the activation parameters of the contribution of the thermally activated deformation. There are no differences of the activation parameters in the unirradiated and the irradiated conditions as well as for the two different materials. This shows that irradiation hardening preferentially results from a friction hardening mechanism by long-range obstacles. (C) 2002 Published by Elsevier Science B.V.

引用

页码：227 / 232

页数：6

共 6 条

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[4]

CONRAD H, 1961, J IRON STEEL I, P364

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