DocumentCode
2755584
Title
Determination of Pu-239 for nuclear material safeguards verification purposes
Author
El-Mongy, S.A.M. ; El-Gamal, W.A.M.
Author_Institution
Atomic Energy Authority, Cairo, Egypt
fYear
1999
fDate
23-25 Feb 1999
Abstract
This work aims at measurement of Pu-239 for nuclear materials safeguards verification purposes. The work was carried out at Los-Alamos National Lab, (USA). Due to the strategic nature of the element, few samples were available to be assayed. The gamma spectrometric non-destructive assay technique was used for determining amount of Pu in the samples. A correction factor for self-attenuation due to the Pu matrix was made. The results show that the declared (certified) and measured (verified) values of Pu-239 agree with an average precision of about 0.40%
Keywords
nuclear materials safeguards; plutonium; radioisotopes; spectrochemical analysis; 239Pu; Pu; Pu matrix; Pu-239; amount determination; correction factor; gamma spectrometric nondestructive assay technique; nuclear material safeguards verification; self-attenuation; Atomic measurements; Attenuation measurement; Chromium; Data acquisition; Gamma ray detection; Gamma ray detectors; Inductors; Isotopes; Nuclear measurements; Spectroscopy;
fLanguage
English
Publisher
ieee
Conference_Titel
Radio Science Conference, 1999. NRSC '99. Proceedings of the Sixteenth National
Conference_Location
Cairo
Print_ISBN
977-5031-62-1
Type
conf
DOI
10.1109/NRSC.1999.760953
Filename
760953
Link To Document