Calculation of spectrum and neutron flux density in experimental channels of WWR-M reactor
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 ar...
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| Main Authors: | , , , , |
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| Format: | Article |
| Language: | English |
| Published: |
Institute for Nuclear Research, National Academy of Sciences of Ukraine
2021-09-01
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| Series: | Ядерна фізика та енергетика |
| Subjects: | |
| Online Access: | http://jnpae.kinr.kiev.ua/22.3/html/22.3.0243.html |
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| Summary: | 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 %. |
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| ISSN: | 1818-331X 2074-0565 |