@article{JRC31901,
	address = {Amsterdam (The Netherlands)},
	year = {2006},
	author = {Berndt R and Mortreau P},
	abstract = {CdTe detectors may be utilised as miniature instruments for the measurement of gamma spectra in safeguards applications  . This is applicable for measurements both to fresh fuel and irradiated nuclear fuel. The spectrum analysis, however, is more complicated than with Ge detectors. Some reasons are: the peaks are asymmetric, the peak/Compton ratio is low, peak parameters depend on the count rate and on the properties of individual detector crystals
		We developed a spectrum unfolding code for spectra obtained with CdTe detectors. The code makes use of a series of pattern spectra of the individual instrument. It is applied to fission product spectra and allows the coarse characterisation of the spent fuel in safeguards inspections.
		
		
		
		
		
		
		
		
		
		
		
		},
	title = {Spent Fuel Characterization with Small CZT Detectors},
	type = {},
	url = {},
	volume = {564},
	number = {},
	journal = {NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION A-ACCELERATORS SP},
	pages = {290-294},
	issn = {},
	publisher = {ELSEVIER SCIENCE BV},
	doi = {}
}