The influence of fast neutron irradiation and irradiation temperature on the tensile properties of wrought LCAC and TZM molybdenum
Creators
- 1. Bettis Atomic Power Laboratory, Bechtel-Bettis, Inc., P.O. Box 79, West Mifflin, PA 15122-0079 (United States)
- 2. Oak Ridge National Laboratory, P.O. Box 2008, Oak Ridge, TN 37831-6138 (United States)
Description
The effects of irradiation temperature on embrittlement are evaluated by the irradiation of wrought low carbon arc cast (LCAC) and TZM molybdenum in the High Flux Isotope Reactor at 294-1100 deg. C to neutron doses between 0.6 and 13.1 dpa Mo. Irradiation at 300 deg. C is shown to result in elevation of the ductile to brittle transition temperature (DBTT) from a pre-irradiated value of -100 to -50 deg. C to a post-irradiated value of 800 deg. C for both alloys with an increase in fracture stress. Irradiation at 560 deg. C also resulted in an increase in fracture stress, but the post-irradiated DBTT for LCAC (300 deg. C) was much lower than TZM (700 deg. C). Irradiation of both LCAC and TZM between 935 deg. C and 1100 deg. C resulted in little radiation hardening and a -50 deg. C DBTT for both alloys. The finer grain size and absence of coarse carbide particles may explain the slightly improved embrittlement resistance of LCAC compared to TZM for 600 deg. C irradiations
Additional details
Identifiers
- DOI
- 10.1016/j.jnucmat.2005.06.016;
- PII
- S0022-3115(05)00291-6;
Publishing Information
- Journal Title
- Journal of Nuclear Materials
- Journal Volume
- 346
- Journal Issue
- 2-3
- Journal Page Range
- p. 145-164
- ISSN
- 0022-3115
- CODEN
- JNUMAM
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 37013764
- Subject category
- S36: MATERIALS SCIENCE;
- Descriptors DEI
- ALLOY-MO99; ATOMIC DISPLACEMENTS; CARBIDES; CARBON; DUCTILE-BRITTLE TRANSITIONS; EMBRITTLEMENT; FAST NEUTRONS; FRACTURES; GRAIN SIZE; HFIR REACTOR; IRRADIATION; LETHAL DOSES; MOLYBDENUM; RADIATION HARDENING; STRESSES; TEMPERATURE RANGE 0400-1000 K; TEMPERATURE RANGE 1000-4000 K; TENSILE PROPERTIES
- Descriptors DEC
- ALLOYS; BARYONS; CARBON COMPOUNDS; CORROSION RESISTANT ALLOYS; DOSES; ELEMENTARY PARTICLES; ELEMENTS; ENRICHED URANIUM REACTORS; FAILURES; FERMIONS; HADRONS; HARDENING; HEAT RESISTANT MATERIALS; HEAT RESISTING ALLOYS; IRRADIATION REACTORS; ISOTOPE PRODUCTION REACTORS; MATERIALS; MECHANICAL PROPERTIES; METALS; MICROSTRUCTURE; MOLYBDENUM ALLOYS; MOLYBDENUM BASE ALLOYS; NEUTRONS; NONMETALS; NUCLEONS; PHYSICAL RADIATION EFFECTS; RADIATION EFFECTS; REACTORS; REFRACTORY METALS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SIZE; TANK TYPE REACTORS; TEMPERATURE RANGE; TEST FACILITIES; TEST REACTORS; THERMAL REACTORS; TITANIUM ADDITIONS; TITANIUM ALLOYS; TRANSITION ELEMENT ALLOYS; TRANSITION ELEMENTS; WATER COOLED REACTORS; WATER MODERATED REACTORS; ZIRCONIUM ADDITIONS; ZIRCONIUM ALLOYS
Optional Information
- Copyright
- Copyright (c) 2005 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.