Validation of the Onsite Used Operational Code Against Burnup Measurement

dc.contributor.author	Koleška, Michal
dc.contributor.author	Šunka, Michal
dc.contributor.author	Ernest, Jaroslav
dc.date.accessioned	2017-11-25T07:18:48Z
dc.date.available	2017-11-25T07:18:48Z
dc.date.copyright	2016/20/12
dc.date.issued	2017
dc.identifier.issn	2332-8983
dc.identifier.other	ners_3_1_014502.pdf
dc.identifier.uri	http://138.201.223.254:8080/yetl1/handle/yetl/4235421
dc.description.abstract	A 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.
dc.publisher	The American Society of Mechanical Engineers (ASME)
dc.title	Validation of the Onsite Used Operational Code Against Burnup Measurement
dc.type	Journal Paper
dc.journal.volume	3
dc.journal.issue	1
dc.journal.title	Journal of Nuclear Engineering and Radiation Science
dc.identifier.doi	10.1115/1.4034570
dc.journal.fristpage	14502
dc.journal.lastpage	014502-4
dc.tree	Journal of Nuclear Engineering and Radiation Science:;2017:;volume( 003 ):;issue: 001
dc.contenttype	Fulltext