Published 1997 | Version v1
Miscellaneous Open

Quantitative WDS analysis to determine plutonium homogeneity in CANDU mixed-oxide fuel

  • 1. Atomic Energy of Canada Limited, Chalk River, Ontario (Canada)

Description

As Part of AECL's mixed-oxide (MOX) fuel development program, a quantitative X-ray wavelength dispersive spectrometric (WDS) analysis was conducted to determine plutonium homogeneity in as-fabricated MOX fuel, using a shielded analytical scanning electron microscope. This paper describes the technique and some results of the analysis. The as-fabricated fuel exhibited a duplex microstructure: a matrix with randomly distributed plutonium-rich particles. The particle size ranged from 10 to 30 μm. To conduct the WDS analysis, PuO2 and UO2 standards were used; plutonium Mβ and uranium Mα lines were monitored. Point analysis with a 2-μm interval was conducted diametrically across the particles to obtain uranium and plutonium distribution profiles. The profiles all exhibited a similar shape; a compositional transition band was observed around each particle, indicating the occurrence of plutonium and uranium interdiffusion. Uncertainty and consistency of the determinations were examined, and the results are satisfactory. (author)

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Part of:
Proceedings of the fifth international conference on CANDU fuel. V.1,2

Additional details

Publishing Information

ISBN
0-919784-50-X
Imprint Title
Proceedings of the fifth international conference on CANDU fuel. V.1,2
Imprint Pagination
[923 p.]
Journal Page Range
(v.1) p. 279-288
Report number
INIS-CA--0072

Conference

Title
5. International conference on CANDU fuel
Dates
21-25 Sep 1997
Place
Toronto, ON (Canada)

Optional Information

Notes
6 refs., 2 tabs., 5 figs.