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contributor authorKoleška, Michal
contributor authorŠunka, Michal
contributor authorErnest, Jaroslav
date accessioned2017-11-25T07:18:48Z
date available2017-11-25T07:18:48Z
date copyright2016/20/12
date issued2017
identifier issn2332-8983
identifier otherners_3_1_014502.pdf
identifier urihttp://138.201.223.254:8080/yetl1/handle/yetl/4235421
description abstractA spectrometric system was developed for spent fuel burnup evaluations at the LVR-15 research reactor, which employed highly enriched (36%) IRT-2M-type fuel. Such a system allows the measurement of fission product axial distribution by measuring certain nuclides, such as Cs137, Cs134, and their ratios, respectively. Within the paper, a comparison between experimental data provided by the spectrometric system and calculations in operational code called NODER is provided.
publisherThe American Society of Mechanical Engineers (ASME)
titleValidation of the Onsite Used Operational Code Against Burnup Measurement
typeJournal Paper
journal volume3
journal issue1
journal titleJournal of Nuclear Engineering and Radiation Science
identifier doi10.1115/1.4034570
journal fristpage14502
journal lastpage014502-4
treeJournal of Nuclear Engineering and Radiation Science:;2017:;volume( 003 ):;issue: 001
contenttypeFulltext


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