Published October 1987 | Version v1
Journal article Metadata-only

Irradiation behavior of low-enriched U6Fe-Al dispersion fuel elements

Creators

  • 1. Argonne National Lab., IL (USA)
  • 2. Oak Ridge National Lab., TN (USA)

Description

An irradiation test of miniature fuel plates containing low-enriched (20% 235U)U6Fe dispersed and clad in Al was performed. The postirradiation examination shows U6Fe to form extensive fission gas bubbles at burnups of only ≅ 20% of the original 20% fuel enrichment. Plate failure by fission gas-driven pillowing occurred at ≅ 40% burnup. This places U6FE at the lowest burnup capability among low enriched dispersion fuels that have been tested for use in research and test reactors. (orig.)

Additional details

Publishing Information

Journal Title
J. Nucl. Mater.
Journal Volume
150
Journal Issue
2
Series
J. Nucl. Mater.
Journal Page Range
238-243
ISSN
0022-3115
CODEN
JNUMA

INIS

Country of Publication
Netherlands
Country of Input or Organization
Netherlands
INIS RN
19041710
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS; S36: MATERIALS SCIENCE;
Resource subtype / Literary indicator
Numerical Data
Descriptors DEI
ALUMINIUM; BUBBLE GROWTH; BURNUP; CHEMICAL COMPOSITION; CLADDING; DISPERSION NUCLEAR FUELS; EXPERIMENTAL DATA; FRACTOGRAPHY; FUEL PLATES; INTERMETALLIC COMPOUNDS; IRON ALLOYS; IRRADIATION; MICROSTRUCTURE; NEUTRON FLUENCE; SCANNING ELECTRON MICROSCOPY; SWELLING; THICKNESS; URANIUM ALLOYS; X-RAY EMISSION ANALYSIS
Descriptors DEC
ACTINIDE ALLOYS; ALLOYS; CHEMICAL ANALYSIS; CRYSTAL STRUCTURE; DATA; DEFORMATION; DEPOSITION; DIMENSIONS; ELECTRON MICROSCOPY; ELEMENTS; ENERGY SOURCES; FUEL ELEMENTS; FUELS; INFORMATION; MATERIALS; METALS; MICROSCOPY; NONDESTRUCTIVE ANALYSIS; NUCLEAR FUELS; NUMERICAL DATA; REACTOR COMPONENTS; REACTOR MATERIALS; SOLID FUELS; SURFACE COATING

Optional Information

Contract/Grant/Project number
Contract W-31-109-Eng-38
Notes
Letter-to-the-editor.