Published November 1989 | Version v1
Journal article

Metal spikes isotope dilution mass spectrometric analysis of spent-fuel solutions

Description

A sufficiently homogeneous alloy of 235U and 239Pu enriched isotopes should now permit the achievement of precisions and accuracies of the order of 0.1 to 0.2% in the IDMS of uranium and plutonium in solutions of highly irradiated spent fuels under routine field conditions. The use of an internal standard with multicollection could also further improve the accuracy of the IDMS assays if the relative efficiencies of the detectors and the isotopic composition of the internal standard could be calibrated to a few 10-4

Additional details

Publishing Information

Journal Title
Transactions of the American Nuclear Society
Journal Volume
60
Series
Trans. Am. Nucl. Soc.
Journal Page Range
230-232
ISSN
0003-018X
CODEN
TANSA

Conference

Title
Winter meeting of the American Nuclear Society (ANS) and nuclear power and technology exhibit.
Dates
26-30 Nov 1989.
Place
San Francisco, CA (USA).

Optional Information

Secondary number(s)
CONF-891103--.