By Saadia Amiel
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Extra resources for Nondestructive Activation Analysis: With Nuclear Reactors and Radioactive Neutron Sources
Sample text
The counting efficiency of delayed neutrons from fission and 17 N is about 10%. B. Photoneutrons To obtain the maximum output of photoneutrons from a source, it is necessary to surround it with a sufficiently thick layer of beryllium or deuterium, depending on the energy of the gamma-rays sought. The counting assembly is similar to that used for delayed neutron counting (Fig. 1), but additional lead shielding (a single row of standard lead bricks) is necessary to shield against gamma-ray background.
AMIEL and M. MANTEL Nuclear Chemistry Department, Soreq Nuclear Research Centre, Yavne (Israel) I. INTRODUCTION The measurement of very short-lived nuclides (viz. half-lives of less than several seconds) for the determination of various elements by activation analysis is in itself, due to the very short time intervals involved, a nondestructive technique. There are two particular instances where this technique is specially advantageous: (i) When the short-lived radioisotope is the only one obtained following neutron capture (fluorine and lead are specific examples).
However, due to the physical size of the magnet there is a considerable distance between the sample and the detector and thus a reduction in the 32 M O O keV Fig. 4. Spectra obtained from a sample containing 1 mg Cr and 50 mg phosphate irradiated for 30 min in the reactor core, counted for 10 h. (a) without magnet; (b) with magnet. X-ray activity measured. (Obviously this geometric factor is specific to every experimental set-up). All these factors have to be taken into account in choosing between magnets and perspex absorbers for the reduction of the background due to beta radiation.
