Published May 2014 | Version v1
Book

Determination of 241Am in PuO2 product in the spent fuel reprocessing of a power reactor by γ-spectrum

  • 1. The Third Branch of the 404 Company Limited, China National Nuclear Corporation, Lanzhou (China)

Description

The determination method of 241Am in PLiO2 product in the spent fuel reprocessing of a power reactor with gamma spectrometer is developed. The influences of 237U and Pu on the determination of 241Am was studied. The results showed that for these samples which the absolute values of 241Am were l0 ng to l00 ng, the precision of this method was superior to 5% and the recovery rate was 92.33%∼114.42%, while the plutonium concentration was less than 0.5 g/L. (authors)

Part of:
Progress report on nuclear science and technology in China (Vol.3). Proceedings of academic annual meeting of China Nuclear Society in 2013, No.4--Nuclear chemistry and radiation chemistry sub-volume

Additional details

Publishing Information

Publisher
China Nuclear Physics Society
Imprint Place
Beijing (China)
ISBN
978-7-5022-6126-9
Imprint Title
Progress report on nuclear science and technology in China (Vol.3). Proceedings of academic annual meeting of China Nuclear Society in 2013, No.4--Nuclear chemistry and radiation chemistry sub-volume
Imprint Pagination
155 p.
Journal Page Range
p. 112-118

Conference

Title
2013 academic annual meeting of China Nuclear Society
Dates
10-14 Sep 2013
Place
Harbin (China)

Optional Information

Notes
3 figs., 6 tabs., 10 refs.