title: Determination of IRT-2M fuel burnup by gamma spectrometry.
abstract: A spectrometric system was developed for evaluating spent fuel in the LVR-15 research reactor, which employs highly enriched (36%) IRT-2M-type fuel. Such system allows the measurement of detailed fission product profiles. Within these measurements, nuclides such as (137)Cs, (134)Cs, (144)Ce, (106)Ru and (154)Eu may be detected in fuel assemblies with different cooling times varying between 1.67 and 7.53 years. Burnup calculations using the MCNPX Monte Carlo code data showed good agreement with measurements, though some discrepancies were observed in certain regions. These discrepancies are attributed to the evaluation of irradiation history, reactor regulation pattern and buildup schemes.
authors.affiliation: Research centre Rez, Hlavni 130, 25068 Husinec-Rez, Czech Republic. Electronic address: Michal.koleska@cvrez.cz.
authors.forename: Michal
authors.initials: M
authors.lastname: Koleška
authors.affiliation: Research centre Rez, Hlavni 130, 25068 Husinec-Rez, Czech Republic.
authors.forename: Ladislav
authors.initials: L
authors.lastname: Viererbl
authors.affiliation: Research centre Rez, Hlavni 130, 25068 Husinec-Rez, Czech Republic.
authors.forename: Milan
authors.initials: M
authors.lastname: Marek
authors.affiliation: Research centre Rez, Hlavni 130, 25068 Husinec-Rez, Czech Republic.
authors.forename: Jaroslav
authors.initials: J
authors.lastname: Ernest
authors.affiliation: Research centre Rez, Hlavni 130, 25068 Husinec-Rez, Czech Republic.
authors.forename: Michal
authors.initials: M
authors.lastname: Šunka
authors.affiliation: Research centre Rez, Hlavni 130, 25068 Husinec-Rez, Czech Republic.
authors.forename: Miroslav
authors.initials: M
authors.lastname: Vinš
keywords: (106)Ru; (134)Cs; (137)Cs; (144)Ce; (154)Eu; Burnup measurement; Fuel cooling time; IRT-2M; LVR-15; MCNPX code burnup calculation