MINIATURE TENSILE TEST SPECIMENS FOR FUSION-REACTOR IRRADIATION STUDIES

被引：38

作者：

KLUEH, RL

机构：

[1] Oak Ridge Natl Lab, Metals &, Ceramics Div, Oak Ridge, TN, USA, Oak Ridge Natl Lab, Metals & Ceramics Div, Oak Ridge, TN, USA

来源：

NUCLEAR ENGINEERING AND DESIGN-FUSION | 1985年 / 2卷 / 04期

关键词：

Because of space limitations for test specimens in most nuclear reactors used for irradiating materials for * Research sponsored by the Office of Fusion Energy; US Department of Energy; under Contract No. DE-AC05-840R21400 with Martin Marietta Energy Systems; Inc;

D O I：

10.1016/0167-899X(85)90028-X

中图分类号：

TL [原子能技术]; O571 [原子核物理学];

学科分类号：

0827 ; 082701 ;

摘要：

引用

页码：407 / 416

页数：10

共 12 条

[1]

BAJAJ R, 1981, ASTM STP, V725, P326

[2]

BAUER RE, 1985, UNPUB ASTM STP, V870

[3] EFFECTS OF LARGE CONCENTRATIONS OF HELIUM ON MECHANICAL-PROPERTIES OF NEUTRON-IRRADIATED STAINLESS-STEEL [J].

BLOOM, EE ;

WIFFEN, FW .

JOURNAL OF NUCLEAR MATERIALS, 1975, 58 (02) :171-184

[4]

CHOI SC, 1978, INTRO APPLIED STATIS, P133

[5]

DIETER GE, 1976, MECHANICAL METALLURY, P346

[6]

LUCAS G, 1985, UNPUB ASTM STP, V888

[7]

PANAYOTOU NF, 1981, J NUCL MATER, V103, P1523

[8]

PICKERING FB, 1978, PHYSICAL METALLURGY, P230

[9]

RICKERBY DG, 1985, UNPUB ASTM STP, V888

[10]

Sikka V. K., 1975, Transactions of the ASME. Series J, Journal of Pressure Vessel Technology, V97, P243, DOI 10.1115/1.3454303

← 1 2 →