Published June 2006 | Version v1
Journal article

Electrodeposition of 237Np for Alpha Spectrometry and Application to Spent Nuclear Fuel Samples

  • 1. Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

Description

Alpha spectrometry was studied for the determination of 237Np in spent nuclear fuel samples. The optimum condition for the electrodeposition of 237Np was obtained as follows : for 1 - 1.5 hour of deposition time, at the current intensity of 1.2 - 1.5 A and at sodium sulfate electrolyte without organic additive. The deposition yield and its reproducibility on 237Np was decreased as the amount of 237Np decreased from 4.16 Bq down to 0.0264 Bq(1ng). The recovery yield of 237Np determined by alpha spectrometry after separation in synthetic solution was 98.8 ± 5.1% (n=4). The contents of 237Np in spent nuclear fuel samples were determined and the result showed an agreement within 10% of a difference between the measurement and the calculation.

Additional details

Publishing Information

Journal Title
Journal of the Korean Radioactive Waste Society
Journal Volume
4
Journal Issue
2
Series
18 refs, 6 figs, 4 tabs
Journal Page Range
p. 95-102
ISSN
1738-1894