Published August 2012 | Version v1
Journal article

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.2012.04.010

Additional 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

Optional Information

Copyright
Copyright (c) 2012 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.