A microprobe study of the retention of the fission gas xenon in irradiated uranium fuels dispersed in alumimum-clad nuclear reactor fuel plates

Conference · Sat Oct 31 00:00:00 EST 1970

OSTI ID:4141487

Zelezny, W. F.; Gibson, G. W.; Graber, M. J.

The purpose of this paper is to describe (a) techniques which have been found useful in the examination of irradiated and highly radioactive materials with a microprobe which was unshielded at first and later had a limited amount of shielding added and (b) applications of these techniques in a study of the relative degree of retention of the fission gas, xenon, by irradiated dispersion fuel elements. These techniques include the preparation of specimens of limited size to decrease the total radioactivity, "counting-over-the-peak" to decrease the lower limit of detectability with an accompanying increase in the sensitivity of detection of trace elements in the presence of high background levels and the introduction of a limited amount of shielding in the microprobe. The discussion of the shielding includes a number of considerations which have a bearing on the examination of highly radioactive specimens by microprobe.

• Research Organization: Idaho Nuclear Corp., Idaho Falls, ID (United States)
• Sponsoring Organization: US Atomic Energy Commission (AEC)
• DOE Contract Number: AT(10-1)-1230
• NSA Number: NSA-24-017389
• OSTI ID: 4141487
• Report Number(s): CONF-690910-
• Resource Relation: Conference: Developments in irradiation testing technology, Sandusky, OH (United States), 9-11 Sep 1969; Other Information: UNCL. Orig. Receipt Date: 31-DEC-70; Related Information: Part of the conference proceedings sponsored by USAEC/NASA, 806 pages
• Country of Publication: United States
• Language: English

Related Subjects

N30250* -Metals
Ceramics
& Other Materials-Ceramics & Cermets-Radiation Effects
N38700 -Reactor Components
Fuels & Accessories
ALUMINUM ALLOYS
DISTRIBUTION
FISSION PRODUCTS
FUELS
GASES
PARTICLES
TRAPS
URANIUM ALLOYS
URANIUM DIOXIDE
XENON U3O8
ALUMINUM ALLOYS AND SYSTEMS/Al-U$sub 3$O$sub 8$
fission gas retention by
effects of temperature on
REACTOR FUEL ELEMENTS/ fission product retention in
determination using microprobe
URANIUM OXIDES U$sub 3$O$sub 8$/Al-U$sub 3$O$sub 8$
fission gas retention by
effects of temperature on
ALUMINUM ALLOYS AND SYSTEMS/Al-UO$sub 2$
fission product distribution in
determination using microprobe
URANIUM OXIDES UO$sub 2$/Al- UO$sub 2$
fission product distribution in
determination using microprobe
ALUMINUM ALLOYS AND SYSTEMS/Al-U
fission gas retention by intermetallic UAl$sub 4$
effects of temperature on
RADIOACTIVE MATERIALS/analysis using microprobe
method for
XENON/determination of fission product
in fuels
microprobe method for
URANIUM ALLOYS AND SYSTEMS/Al-U
fission gas retention by intermetallic UAl$sub 4$
effects of temperature on