IRRADIATION EMBRITTLEMENT OF NEUTRON-IRRADIATED LOW ACTIVATION FERRITIC STEELS

被引：50

作者：

KAYANO, H ^{[1
]}

KIMURA, A ^{[1
]}

NARUI, M ^{[1
]}

SASAKI, Y ^{[1
]}

SUZUKI, Y ^{[1
]}

OHTA, S ^{[1
]}

机构：

[1] KOBE STEEL LTD,MAT RES LAB,KOBE 651,JAPAN

来源：

JOURNAL OF NUCLEAR MATERIALS | 1988年 / 155卷 / pt B期

关键词：

Iron and Alloys--Activation - Neutrons - Steel--Embrittlement;

D O I：

10.1016/0022-3115(88)90452-7

中图分类号：

T [工业技术];

学科分类号：

08 ;

摘要：

Effects of neutron irradiation and additions of small amounts of alloying elements on the ductile-brittle transition temperature (DBTT) of three different groups of ferritic steels were investigated by means of the Charpy impact test in order to gain an insight into the development of low-activation ferritic steels suitable for the nuclear fusion reactor. The groups of ferritic steels used in this study were (1) basic 0-5% Cr ferritic steels, (2) low-activation ferritic steels which are Fe-Cr-W steels with additions of small amounts of V, Mn, Ta, Ti, Zr, etc. and (3) Fe-Cr-Mo, Nb or V ferritic steels for comparison. In Fe-0-15% Cr and Fe-Cr-W-Mo steels, Fe-3-9% Cr steels showed minimum brittleness and provided good resistance against irradiation embrittlement.

引用

页码：978 / 981

页数：4

共 5 条

[1]

GELLES DS, DOEER004513 ADIP REP, P128

[2] IRRADIATION EMBRITTLEMENT OF NEUTRON-IRRADIATED FERRITIC STEEL [J].