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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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References

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Koleška, M., Viererbl, L., Marek, M., Ernest, J., Šunka, M., and Vinš, M., 2016, “Determination of IRT-2M Fuel Burnup by Gamma Spectrometry,” Appl. Radiat. Isotopes, 107, pp. 92–97. [CrossRef]
Antes, M., et al. , 2010, “Předprovozní Bezpečnostní Zpráva Reaktoru LVR-15,” Centrum výzkumu Řež, Řež.
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Koleska, M., Viererbl, L., and Marek, M., 2014, “Calibration of Spent Fuel Measurement Assembly,” Radiat. Phys. Chem., 104(Nov.), pp. 420–423. [CrossRef]
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Ernest, J., 2006, “Abstrakt výpočtového programu NODERRev.1,” , ÚJV Řež, Řež, Czech Republic.
Chadwick, M., et al. , 2011, “ENDF/B-VII.1 Nuclear Data for Science and Technology: Cross Sections, Covariances, Fission Product Yields and Decay Data,” Nucl. Data Sheets, 112(12), pp. 2887–2996. [CrossRef]
Pelowitz, D. B., 2011, MCNPX User’s Manual, Version 2.7.0, LANL, Los Alamos.
Koleška, M., et al. , 2015, “Capabilities of the LVR-15 Research Reactor for Production of Medical and Industrial Radioisotopes,” J. Radioanal. Nucl. Chem., 305(1), 51–59. 0236-5731 10.1007/s10967-015-4025-5

Figures

Grahic Jump Location
Fig. 1

History of selected fuel assemblies

Grahic Jump Location
Fig. 4

C/E-1 ratio of relative axial profiles

Grahic Jump Location
Fig. 3

Relative fission product activity axial profile distributions

Grahic Jump Location
Fig. 2

Calculated axial burnup profiles

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