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Электронный каталог: Reda, S. M. - Effect of MOX Fuel and the ENDF/B-VIII on the AP1000 Neutronic Parameters Calculations by Using M...
Reda, S. M. - Effect of MOX Fuel and the ENDF/B-VIII on the AP1000 Neutronic Parameters Calculations by Using M...
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Статья
Автор: Reda, S. M.
Nuclear Technology & Radiation Protection: Effect of MOX Fuel and the ENDF/B-VIII on the AP1000 Neutronic Parameters Calculations by Using M...
б.г.
ISBN отсутствует
Автор: Reda, S. M.
Nuclear Technology & Radiation Protection: Effect of MOX Fuel and the ENDF/B-VIII on the AP1000 Neutronic Parameters Calculations by Using M...
б.г.
ISBN отсутствует
Статья
Reda, S.M.
Effect of MOX Fuel and the ENDF/B-VIII on the AP1000 Neutronic Parameters Calculations by Using MCNP6 / S.M.Reda, [et al.] // Nuclear Technology & Radiation Protection. – 2020. – Vol.34, No.4. – p.325-335. – URL: http://ntrp.vinca.rs/2019_4/Reda_2019_4.pdf. – Bibliogr.:20.
Спец.(статьи,препринты) = С 348 а - Теория и расчет ядерных реакторов
Reda, S.M.
Effect of MOX Fuel and the ENDF/B-VIII on the AP1000 Neutronic Parameters Calculations by Using MCNP6 / S.M.Reda, [et al.] // Nuclear Technology & Radiation Protection. – 2020. – Vol.34, No.4. – p.325-335. – URL: http://ntrp.vinca.rs/2019_4/Reda_2019_4.pdf. – Bibliogr.:20.
Спец.(статьи,препринты) = С 348 а - Теория и расчет ядерных реакторов