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ISSN:
1818-331X (Print), 2074-0565 (Online) |
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Calculation of spectrum and neutron flux density in experimental channels of WWR-M reactor
O. G. Diakov, ². À. Maliuk, D. P. Stratilat, Ì. V. Strilchuk*, V. V. Tryshyn
Institute for Nuclear Research, National Academy of Sciences of Ukraine, Kyiv, Ukraine
*Corresponding author. E-mail address:
myst@kinr.kiev.ua
Abstract: A program for calculating the spectra and densities of neutron fluxes in the experimental channels of the research reactor WWR-M was developed. To do this, the reactor core was modeled. Irradiation of neutron activation detectors was performed. The obtained experimental rates of nuclear reactions are consistent with the calculated within 10 %.
Keywords: research reactor, Geant4, neutron spectrum, neutron flux density, neutron activation detector, reaction rate.
References:1. S. Agostinelli et al. Geant4 – a simulation toolkit. Nucl. Instrum. Meth. A 506(3) (2003) 250. https://doi.org/10.1016/S0168-9002(03)01368-8
2. Neutron activation cross section measurements from threshold to 20 MeV for the validation of nuclear models and their parameters. Report number: NEA/WPEC-19. International Evaluation Co-operation, Vol. 19 (Nuclear Energy Agency, OECD Publications, 2005). Report