Адаптація розрахункових моделей HELIOS паливних касет ВВЕР‑440 для використання програмою TRACE/PARCS
The preparation of a few-group neutron cross-section library is an important step in implementation of the computer packages that are based on solution of the neutron transport equation in the few-group diffusion approximation into the safety analysis practices. The accuracy of modelling the physica...
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| Date: | 2019 |
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| Main Authors: | , , , |
| Format: | Article |
| Language: | English |
| Published: |
State Scientific and Technical Center for Nuclear and Radiation Safety
2019
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| Online Access: | https://nuclear-journal.com/index.php/journal/article/view/147 |
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| Journal Title: | Nuclear and Radiation Safety |