FRACTURE AND TENSILE BEHAVIOR OF NEUTRON-IRRADIATED A533-B PRESSURE VESSEL STEEL

被引:19
作者
HUNTER, CW
WILLIAMS, JA
机构
关键词
D O I
10.1016/0029-5493(71)90045-8
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
收藏
页码:131 / &
相关论文
共 50 条
[31]   Examination of neutron-irradiated pressure-vessel steel using positron annihilation lifetime spectrosopy [J].
Cumblidge, SE ;
Motta, AT ;
Catchen, GL .
MICROSTRUCTURAL PROCESSES IN IRRADIATED MATERIALS, 1999, 540 :471-476
[32]   Effect of Neutron Flux on Magnetic Hysteresis in Neutron-Irradiated Pressure Vessel Steels [J].
Kobayashi, Satoru ;
Yamamoto, Takuya ;
Klingensmith, Doug ;
Odette, G. Robert ;
Kikuchi, Hiroaki ;
Kamada, Yasuhiro .
IEEE TRANSACTIONS ON MAGNETICS, 2014, 50 (04)
[33]   INITIAL ASSESSMENTS OF NOTCH DUCTILITY BEHAVIOR OF A533 PRESSURE VESSEL STEEL WITH NEUTRON IRRADIATION [J].
HAWTHORN.JR .
MATERIALS RESEARCH AND STANDARDS, 1968, 8 (05) :61-&
[34]   TENSILE PROPERTIES OF NEUTRON-IRRADIATED GRAPHITES [J].
PRICE, RJ .
CARBON, 1977, 15 (06) :436-436
[35]   Prediction of the brittle fracture toughness of neutron-irradiated reactor pressure vessel steels. Part 2 [J].
Margolin B.Z. ;
Shvetsova V.A. ;
Gulenko A.G. .
Strength of Materials, 2001, Springer Science and Business Media, LLC (33) :201-206
[36]   DYNAMIC FRACTURE-TOUGHNESS OF IRRADIATED A533 GRADE-B CLASS-1 PRESSURE-VESSEL STEEL [J].
MURTY, KL ;
SHOGAN, RP ;
BAMFORD, WH .
NUCLEAR TECHNOLOGY, 1984, 64 (03) :268-274
[37]   COMPUTATIONAL MODELING OF MICROSTRUCTURAL FRACTURE PROCESSES IN A533B PRESSURE VESSEL STEEL. [J].
Anon .
Electric Power Research Institute (Report) EPRI NP, 1980, (1398)
[38]   NEUTRON IRRADIATION EMBRITTLEMENT CHARACTERISTICS OF A533-B ELECTROSLAG WELDMENTS [J].
HAWTHORN.JR .
TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1970, 13 (02) :613-&
[39]   MECHANICAL-PROPERTIES OF NEUTRON-IRRADIATED REACTOR PRESSURE-VESSEL STEEL DEPENDENT ON RADIATION MECHANISMS [J].
PACHUR, D .
TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1983, 44 :229-231
[40]   The changes of the structural, magnetic, and mechanical properties in a reactor pressure vessel steel neutron-irradiated at 70°C [J].
Park, DG ;
Hong, JH ;
Jang, KS ;
Jung, MM ;
Kim, GM .
JOURNAL OF THE KOREAN PHYSICAL SOCIETY, 1999, 34 (05) :434-438