Microstructure, irradiation hardening and embrittlement of 13Cr2MoNbVB ferritic-martensitic steel after neutron irradiation at low temperatures
- 1. State Sci. Center of Russian Federation, Obninsk (Russian Federation). Inst. of Phys. and Power Eng.
Description
Tensile mechanical tests and TEM-study of type 13Cr2MoNbVB ferritic-martensitic steel (Russian-made steel EP-450), neutron-irradiated at temperatures in the range 280-350 C up to doses of 85 dpa, have been carried out. At doses of 0.5-25 dpa, the increment of the yield stress in irradiated steel can be fitted by the equation Δσ, MPa=300 x (dose)0.2. As the dose increases, the yield stress increment reaches a maximum at 30-40 dpa and then begins to decrease. Damage dose and irradiation temperature dependencies of the ductility, upper shelf energy and ductile-to-brittle transition temperature have also been examined. A TEM-analysis revealed dislocation loops, void and α'-precipitation in the microstructure of the irradiated steel. At damage doses higher than 40 dpa, a decrease of loop number density and increase of loop size seem to be the main reasons for irradiation softening and ductility improvement in the temperature interval 330-360 C. (orig.)
Additional details
Publishing Information
- Journal Title
- Journal of Nuclear Materials
- Journal Volume
- 233-237
- Journal Issue
- pt.A
- Journal Page Range
- p. 236-239.
- ISSN
- 0022-3115
- CODEN
- JNUMAM
Conference
- Title
- 7. international conference on fusion reactor materials (ICFRM-7).
- Dates
- 25-29 Sep 1995.
- Place
- Obninsk (Russian Federation).
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- Netherlands
- INIS RN
- 28022775
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY; S36: MATERIALS SCIENCE; S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ANNEALING; CHARPY TEST; CHROMIUM-MOLYBDENUM STEELS; DISLOCATIONS; DUCTILE-BRITTLE TRANSITIONS; DUCTILITY; EMBRITTLEMENT; FAST NEUTRONS; FERRITIC STEELS; MARTENSITIC STEELS; MICROSTRUCTURE; PRECIPITATION; RADIATION HARDENING; SWELLING; TEMPERATURE RANGE 0400-1000 K; THERMONUCLEAR REACTOR MATERIALS; VOIDS; YIELD STRENGTH
- Descriptors DEC
- ALLOYS; BARYONS; CARBON ADDITIONS; CHROMIUM ALLOYS; CHROMIUM STEELS; CRYSTAL DEFECTS; CRYSTAL STRUCTURE; DEFORMATION; DESTRUCTIVE TESTING; ELEMENTARY PARTICLES; FERMIONS; HADRONS; HARDENING; HEAT TREATMENTS; HIGH ALLOY STEELS; IMPACT TESTS; IRON ALLOYS; IRON BASE ALLOYS; LINE DEFECTS; MATERIALS; MATERIALS TESTING; MECHANICAL PROPERTIES; MECHANICAL TESTS; MOLYBDENUM ALLOYS; NEUTRONS; NUCLEONS; PHYSICAL RADIATION EFFECTS; RADIATION EFFECTS; SEPARATION PROCESSES; STAINLESS STEELS; STEELS; TEMPERATURE RANGE; TENSILE PROPERTIES; TESTING; TRANSITION ELEMENT ALLOYS