Technical Brief

Validation of the Onsite Used Operational Code Against Burnup Measurement

[+] Author and Article Information
Michal Koleška

Centrum výzkumu Řež,
Hlavní 130,
Husinec-Řež 25068, Czech Republic
e-mail: Michal.koleska@cvrez.cz

Michal Šunka, Jaroslav Ernest

Centrum výzkumu Řež,
Hlavní 130,
Husinec-Řež 25068, Czech Republic

Manuscript received November 16, 2015; final manuscript received August 15, 2016; published online December 20, 2016. Assoc. Editor: Juan-Luis Francois.

ASME J of Nuclear Rad Sci 3(1), 014502 (Dec 20, 2016) (4 pages) Paper No: NERS-15-1230; doi: 10.1115/1.4034570 History: Received November 16, 2015; Accepted August 15, 2016

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.

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Grahic Jump Location
Fig. 1

History of selected fuel assemblies

Grahic Jump Location
Fig. 2

Calculated axial burnup profiles

Grahic Jump Location
Fig. 3

Relative fission product activity axial profile distributions

Grahic Jump Location
Fig. 4

C/E-1 ratio of relative axial profiles




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