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Neutronic model of a stellarator-mirror fusion-fission hybrid

Neutronic model of a stellarator-mirror fusion-fission hybrid

The MCNPX numerical code has been used to model a compact concept for a fusion-fission reactor based on a combined stellarator-mirror trap. Calculation results for the radial leakage of neutrons through the mantle surface of the fission reactor are presented.

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Bibliographic Details
Main Authors: Chernitskiy, S.V., Moiseenko, V.E., Noack, K., Ågren, O., Abdullayev, A.
Format: Article
Language:English
Published: Національний науковий центр «Харківський фізико-технічний інститут» НАН України 2012
Series:Вопросы атомной науки и техники
Subjects:
ИТЭР и приложения для термоядерного реактора
Online Access:http://dspace.nbuv.gov.ua/handle/123456789/109102
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Summary:The MCNPX numerical code has been used to model a compact concept for a fusion-fission reactor based on a combined stellarator-mirror trap. Calculation results for the radial leakage of neutrons through the mantle surface of the fission reactor are presented.

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