Irradiation behavior of ferritic-martensitic 9-12%Cr steels

被引：12

作者：

Horsten, MG ^{[1
]}

van Osch, EV ^{[1
]}

Gelles, DS ^{[1
]}

Hamilton, ML ^{[1
]}

机构：

[1] NRG, NL-1755 LE Petten, Netherlands

来源：

EFFECTS OF RADIATION ON MATERIALS: 19TH INTERNATIONAL SYMPOSIUM | 2000年 / 1366卷

关键词：

neutron irradiation; ferritic-martensitic 9-12%Cr steels; tensile properties; fracture toughness; Charpy impact behavior; embrittlement; hardening; ductility;

D O I：

10.1520/STP12416S

中图分类号：

T [工业技术];

学科分类号：

08 ;

摘要：

A dedicated series of irradiation experiments has been executed in the high flux reactor (HFR) in Petten (Netherlands) to evaluate the irradiation behavior of ferritic-martensitic 9-12%Cr steels at temperatures in the range of 70 degrees C to 370 degrees C and damage dose levels up to 3 dpa. Materials investigated in the program comprise Mod.9%Cr (9Cr-1Mo-0.2V-0.08Nb), HT9 (12Cr-1Mo-0.5W-0.5Ni-0.3V), MANET type steel (10Cr-0.5Mo-0.6Ni-0.2V-0.15Nb), NF616 (9Cr-2W-0.5Mo-0.2V-0.07Nb) and HCM12A (12Cr-2W-1Cu-0.4Mo-0.3Ni-0.2V-0.05Nb). The 9-12%Cr steels show severe hardening and ductility reduction at room temperature (RT) after neutron irradiation. Strength, ductility and toughness of material irradiated at 70"C gradually recover with increase in test temperature. Similar ductility trends of material irradiated at 300 degrees C are observed as for unirradiated material, but recovery with increase in temperature is not observed below temperatures of 400 degrees C. The 9%Cr steels show less hardening and reduction in ductility than the 10-12%Cr steels. The reduction of area and 0.2% yield stress correlate well with the upper-shelf energy and ductile-to-brittle transition temperature, respectively, both for the unirradiated and irradiated condition. in general, the 9%Cr steels show more resistance to irradiation at 300 degrees C than the 10-12%Cr steels with respect to fracture toughness.

引用

页码：579 / 593

页数：5