Approximate Determination of Enrichment of Reactor Fuel Element Plates with Improvised Gamma Ray Spectrometer

G. Bradley

doi:10.1520/STP42015S

SYMPOSIA PAPER Published: 01 January 1958

STP42015S

Approximate Determination of Enrichment of Reactor Fuel Element Plates with Improvised Gamma Ray Spectrometer

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It is often of great convenience to be able to determine quickly the amount of enrichment of a particular fuel element specimen. This is especially true in the fabricating and testing of elements where errors, even though unlikely, may occur at great cost in refabricating the materials. The technique described is a simple one requiring no other equipment than a scintillation detector equipped with a sodium iodide (thallium-activated) crystal, an oscilloscope, and camera attachment.

Author Information

Bradley, G., E.

Argonne National Laboratory, Lemont, Ill.

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Details

Developed by Committee: E07

Pages: 373–374

DOI: 10.1520/STP42015S

ISBN-EB: 978-0-8031-5948-8

ISBN-13: 978-0-8031-6102-3

Approximate Determination of Enrichment of Reactor Fuel Element Plates with Improvised Gamma Ray Spectrometer

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