Validation of the Onsite Used Operational Code Against Burnup Measurement-Reference-Cited by-同舟云学术

Validation of the Onsite Used Operational Code Against Burnup Measurement

Published:2016-12-20 Issue:1 Volume:3 Page:
ISSN:2332-8983
Container-title:Journal of Nuclear Engineering and Radiation Science
language:en
Short-container-title:

Author:

Koleška Michal¹,Šunka Michal²,Ernest Jaroslav²

Affiliation:

1. Centrum výzkumu Řež, Hlavní 130, Husinec-Řež 25068, Czech Republic e-mail:

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

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.

Publisher

ASME International

Subject

Nuclear Energy and Engineering,Radiation

Link

http://asmedigitalcollection.asme.org/nuclearengineering/article-pdf/doi/10.1115/1.4034570/6067942/ners_3_1_014502.pdf

Reference14 articles.

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3. The Application and Comparison of Zr-97 and Sr-92 in the Absolute Determination of the Contribution of Power Density and Cladding Activation in a VVER-1000 Mock-Up on the LR-0 Research Reactor;Nucl. Instrum. Method. Phys. Res. Sec. A,2014

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5. Determination of IRT-2M Fuel Burnup by Gamma Spectrometry;Appl. Radiat. Isotopes,2016

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