DEVELOPMENT OF POTENTIAL LOW ACTIVATION FERRITIC AND AUSTENITIC STEELS

被引：169

作者：

TAMURA, M ^{[1
]}

HAYAKAWA, H ^{[1
]}

TANIMURA, M ^{[1
]}

HISHINUMA, A ^{[1
]}

KONDO, T ^{[1
]}

机构：

[1] JAPAN ATOM ENERGY RES INST, TOKAI, IBARAKI 31911, JAPAN

来源：

JOURNAL OF NUCLEAR MATERIALS | 1986年 / 141卷 / pt B期

关键词：

RADIOACTIVE WASTES - Disposal - STAINLESS STEEL - Mechanical Properties - STEEL CORROSION - TOKAMAK DEVICES - Materials;

D O I：

10.1016/0022-3115(86)90144-3

中图分类号：

T [工业技术];

学科分类号：

08 ;

摘要：

New experimental steels were designed and tested as reduced activation alternatives to austenitic and ferritic prime candidate alloys for applications to the first wall structural components of tokamak reactors. Four alloys were melted for testing with the following compositional specifications: 0. 1 C-8 Cr-2 W-0. 2 V-Fe, 0. 1 C-8 Cr-2 W-0. 2 V-0. 04 Ta-Fe, 0. 25 C-25 Mn-14 Cr-0. 2 Ti-Fe and 0. 02 C-18 Ni-18 Cr-0. 3 Ti-Fe. Tests were made to determine tensile, creep-rupture, impact before and after thermal aging, wet and dry corrosion, and weldability properties. Among the materials tested the ferritic alloy with 0. 04 Ta showed attractive features.

引用

页码：1067 / 1073

页数：7

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