FIELD: analytical methods. SUBSTANCE: invention relates to nuclear power engineering and consists in measuring gamma-emission of americium-plutonium mixture placed in thin-wall container made from material permeable for low- energy gamma-emission. Thickness of the layer of mixture should be at least 2 mm. Between bottom of container and gamma-emission detector, screen is placed to reduce gamma-emission with energy 60 keV by no more than 2-3 times and to filter off emissions with energies 17 and 60 keV coming from periphery regions of container. Relative concentration of americium C is determined from equation C = KN, wherein N is power of the dose of gamma-emission detected and K is calibration coefficient taking into account geometric dimensions of detection unit and gamma- emission detector efficiency. EFFECT: accelerated determination. 2 dwg
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Authors
Dates
1999-11-27—Published
1998-01-06—Filed