Розрахунок флюенса нейтронів і тепловиділення в конструкційних елементах реактора ВВЕР-1000 методом Монте-Карло

The paper describes the methodology for the calculation of neutron fluence and energy release in WWER-1000 reactor cavity and baffle using the Monte Carlo MCNPX code. It formulates an approach to the simulation of a 3-D neutron source and conditions for the transport of neutrons and photons in the c...

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Bibliographic Details
Date:2018
Main Authors: Abdullaiev, A., Soldatov, S., Hann, V., Chernitskyi, S.
Format: Article
Language:English
Published: State Scientific and Technical Center for Nuclear and Radiation Safety 2018
Online Access:https://nuclear-journal.com/index.php/journal/article/view/85
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Journal Title:Nuclear and Radiation Safety

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Nuclear and Radiation Safety