Microstructural evolution on neutron-irradiated molybdenum alloys
Creators
- 1. Hokkaido Univ., Materials Science and Engineering Div., Graduate School of Engineering, Sapporo (Japan)
- 2. ORNL, Oak Ridge National Laboratory, Oak Ridge, Tennessee, TN (United States)
- 3. Bettis Atomic Power Laboratory, West Mifflin, PA (United States)
Description
Full text of publication follows: Molybdenum is a refractory metal that has high strength and creep resistance at high temperatures, as well as possessing high thermal conductivity, and measurable tensile ductility, which are desired properties for many advanced applications. One concern associated with the irradiation of molybdenum, regardless of its good behavior in the unirradiated condition, is the loss of ductility resulting from irradiation hardening that could increase susceptibility to brittle fracture. However, microstructural evolution in molybdenum alloys at various irradiation temperatures is not well-known. In order to better understand the influence of composition, irradiation temperature and fluence on microstructural evolution, three kinds of molybdenum alloys, low carbon arc cast (LCAC), TZM, and ODS molybdenum, were prepared and neutron-irradiated up to 2.2x1026 n/m2 in the temperature range between 300 and 1000 deg. C. Irradiation of molybdenum alloys at 300 deg. C results in the higher number density of smaller loops and voids other than that at 600 deg. C, leading to formation of a stable distribution of obstacles that limits dislocation motion at much lower dose than required for the coarser void structure produced by the 600 deg. C irradiations. This may explain large increases in tensile strength at 300 deg. C, which are comparable for all alloys and irradiation temperature, and also saturation of the increase in tensile strength at lower dose for the 300 deg. C irradiation other than that for the 600 deg. C irradiations. In addition, irradiation-induced precipitates were also observed in matrix of LCAC and ODS molybdenum irradiated at higher irradiation temperature (600 and 1000 deg. C). Energy-dispersive spectrometry (EDS) and diffraction analysis indicated that the precipitates had hypothetical structure composed of molybdenum and ruthenium. (authors)
Availability note (English)
Available in abstract form only, full text entered in this recordAdditional details
Publishing Information
- Imprint Pagination
- 1 p.
- Report number
- INIS-FR--09-0554
Conference
- Title
- 13. International Conference on Fusion Reactor Materials
- Acronym
- ICFRM-13
- Dates
- 10-14 Dec 2007
- Place
- Nice (France)
INIS
- Country of Publication
- France
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 40067832
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY; S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- ALLOY-MO99; CREEP; DENSITY; DIFFRACTION; DISLOCATIONS; DUCTILITY; EVOLUTION; FRACTURES; IRRADIATION; MICROSTRUCTURE; MOLYBDENUM; NEUTRONS; PRECIPITATION; RADIATION HARDENING; RUTHENIUM; TEMPERATURE RANGE 0400-1000 K; THERMAL CONDUCTIVITY; VOIDS
- Descriptors DEC
- ALLOYS; BARYONS; COHERENT SCATTERING; CORROSION RESISTANT ALLOYS; CRYSTAL DEFECTS; CRYSTAL STRUCTURE; ELEMENTARY PARTICLES; ELEMENTS; FAILURES; FERMIONS; HADRONS; HARDENING; HEAT RESISTANT MATERIALS; HEAT RESISTING ALLOYS; LINE DEFECTS; MATERIALS; MECHANICAL PROPERTIES; METALS; MOLYBDENUM ALLOYS; MOLYBDENUM BASE ALLOYS; NUCLEONS; PHYSICAL PROPERTIES; PHYSICAL RADIATION EFFECTS; PLATINUM METALS; RADIATION EFFECTS; REFRACTORY METALS; SCATTERING; SEPARATION PROCESSES; TEMPERATURE RANGE; TENSILE PROPERTIES; THERMODYNAMIC PROPERTIES; TITANIUM ADDITIONS; TITANIUM ALLOYS; TRANSITION ELEMENT ALLOYS; TRANSITION ELEMENTS; ZIRCONIUM ADDITIONS; ZIRCONIUM ALLOYS