Fabrication and preliminary evaluation of metal matrix microencapsulated fuels
- 1. Fuel Cycle and Isotopes Division, Oak Ridge National Laboratory, Oak Ridge, TN 37831 (United States)
- 2. Materials Science and Technology Division, Oak Ridge National Laboratory, Oak Ridge, TN 37831 (United States)
Description
The metal matrix microencapsulated (M3) fuel concept for light water reactors (LWRs), consisting of coated fuel particles dispersed in a zirconium metal matrix, is introduced. Fabrication of M3 fuels by hot pressing, hot isostatic pressing, or extrusion methodologies has been demonstrated over the temperature range 800–1050 °C. Various types of coated fuel particles with outermost layers of pyrocarbon, SiC, ZrC, and TiN have been incorporated into the zirconium metal matrix. Mechanical particle–particle and chemical particle–matrix interactions have been observed during the preliminary characterization of as-fabricated M3 specimens. Irradiation of three M3 rodlets with surrogate coated fuel particles was carried out at mean rod temperature of 400 °C to 4.6 dpa in the zirconium metal matrix. Due to absence of texture in the metal matrix no irradiation growth strain (<0.09%) was detected during the post-irradiation examination.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.jnucmat.2012.04.010Additional details
Identifiers
- DOI
- 10.1016/j.jnucmat.2012.04.010;
- PII
- S0022-3115(12)00181-X;
Publishing Information
- Journal Title
- Journal of Nuclear Materials
- Journal Volume
- 427
- Journal Issue
- 1-3
- Journal Page Range
- p. 79-86
- ISSN
- 0022-3115
- CODEN
- JNUMAM
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 43086179
- Subject category
- S36: MATERIALS SCIENCE;
- Descriptors DEI
- ATOMIC DISPLACEMENTS; COATED FUEL PARTICLES; EVALUATION; EXTRUSION; HOT PRESSING; INTERACTIONS; IRRADIATION; LAYERS; NUCLEAR FUELS; POST-IRRADIATION EXAMINATION; PYROLYTIC CARBON; SILICON CARBIDES; TEMPERATURE RANGE 0400-1000 K; TEMPERATURE RANGE 1000-4000 K; TITANIUM NITRIDES; WATER COOLED REACTORS; ZIRCONIUM; ZIRCONIUM CARBIDES
- Descriptors DEC
- CARBIDES; CARBON; CARBON COMPOUNDS; ELEMENTS; ENERGY SOURCES; FABRICATION; FUEL PARTICLES; FUELS; MATERIALS; MATERIALS WORKING; METALS; NITRIDES; NITROGEN COMPOUNDS; NONMETALS; PHYSICAL RADIATION EFFECTS; PNICTIDES; PRESSING; RADIATION EFFECTS; REACTOR MATERIALS; REACTORS; SILICON COMPOUNDS; TEMPERATURE RANGE; TITANIUM COMPOUNDS; TRANSITION ELEMENT COMPOUNDS; TRANSITION ELEMENTS; ZIRCONIUM COMPOUNDS
Optional Information
- Copyright
- Copyright (c) 2012 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.