Measurement of the Modified Conversion Ratio of 238U by Gamma-Ray Spectrometry on AN Irradiated Fuel Pin

Details Measurement of the Modified Conversion Ratio of 238U by Gamma-Ray Spectrometry on AN Irradiated Fuel Pin Measurement of the Modified Conversion Ratio of 238U by Gamma-Ray Spectrometry on AN Irradiated Fuel Pin

Jun 2003

adsabs.harvard.edu/cgi-bin/nph-data_query?bibcode=2003cgrs.conf..690h&link_type=abstract

CAPTURE GAMMA-RAY SPECTROSCOPY AND RELATED TOPICS. Proceedings of the Eleventh International Symposium. Held 2-6 September 2002

Physics

Scientific paper

Within the frameworks of plutonium recycling, of transmutation, of waste management and of the increase of fuel loading length, controlling and improving the accuracy on 238U conversion ratio becomes necessary. Indeed, 238U neutron capture generates transuranian elements as for instance the isotopes of plutonium, americium or curium. This study focuses on a new technique for measuring by gamma-spectrometry, the modified conversion ratio of 238U defined as the ratio of the capture rate of 238U to the total fission rate, in an irradiated fuel pin of a critical assembly.

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