The mechanical properties and microstructure of the OPTIMAX series of low activation ferritic-martensitic steels

被引:25
作者
Baluc, N [1 ]
Schäublin, R [1 ]
Bailat, C [1 ]
Paschoud, F [1 ]
Victoria, M [1 ]
机构
[1] Swiss Fed Inst Technol, Ctr Rech Phys Plasmas, Fus Technol Mat Div, CH-5232 Villigen, Switzerland
基金
欧盟地平线“2020”;
关键词
We gratefully acknowledge EURATOM and the Swiss National Science Foundation for providing financial support; and the Paul Scherrer Institute for the overall use of the facilities;
D O I
10.1016/S0022-3115(00)00282-8
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
Polycrystalline specimens of the ferritic-martensitic OPTIMAX A steel have been irradiated on the one hand with neutrons at 523 K to a dose of 2.5 dpa and with 590 MeV protons at ambient temperature and 523 K to doses of about 0.3 and 1 dpa on the other. Charpy tests reveal a shift of the ductile-to-brittle transition temperature from about 190 to 268 K in the neutron-irradiated steel. Proton irradiations at ambient temperature lead to hardening and reduction of tensile ductility of the material. Both phenomena are strongly and positively dependent on dose. After irradiation at 523 K, they appear negligible (at least for the dose of 0.75 dpa). Transmission electron microscopy observations reveal that neutron irradiation leads to the formation of only a few Visible black dots, together with a few faceted cavities, while proton irradiations also produce few visible defect clusters with sizes of about 1-2 nm, with no clear difference in size and density with dose and temperature. As a particular result, from proton irradiations performed at ambient temperature, the embedded carbides become amorphous, while at 523 K they remain crystalline. (C) 2000 Elsevier Science B.V. All rights reserved.
引用
收藏
页码:731 / 735
页数:5
相关论文
共 7 条
[1]   A comparison of the microstructure and tensile behaviour of irradiated fcc and bcc metals [J].
Baluc, N ;
Bailat, C ;
Dai, Y ;
Luppo, MI ;
Schaublin, R ;
Victoria, M .
MICROSTRUCTURAL PROCESSES IN IRRADIATED MATERIALS, 1999, 540 :539-548
[2]  
BALUC N, IN PRESS
[3]   Microstructure in Martensitic Steel DIN 1.4926 after 800 MeV proton irradiation [J].
Dai, Y ;
Bauer, GS ;
Carsughi, F ;
Ullmaier, H ;
Maloy, SA ;
Sommer, WF .
JOURNAL OF NUCLEAR MATERIALS, 1999, 265 (1-2) :203-207
[4]   Microstructure assessment of the low activation ferritic/martensitic steel F82H [J].
Schaublin, R ;
Spatig, P ;
Victoria, M .
JOURNAL OF NUCLEAR MATERIALS, 1998, 258 :1178-1182
[5]   Evolution of the mechanical properties of the F82H ferritic/martensitic steel after 590 MeV proton irradiation [J].
Spatig, P ;
Schaublin, R ;
Gyger, S ;
Victoria, M .
JOURNAL OF NUCLEAR MATERIALS, 1998, 258 :1345-1349
[6]  
VANOSCH EV, 1998, P IEA WORKSH WORK GR
[7]  
VICTORIA M, 1995, P 17 ASTM S EFF RAD, P721