Static neutronic calculation of a fusion neutron source

The MCNPX numerical code has been used to model a fusion neutron source based on a combined stellarator-mirror trap. Calculation results for the neutron flux and spectrum inside the first wall are presented. Heat load and irradiation damage on the first wall are calculated.

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Bibliographic Details
Date:2014
Main Authors: Chernitskiy, S.V., Gann, V.V., Ågren, O.
Format: Article
Language:English
Published: Національний науковий центр «Харківський фізико-технічний інститут» НАН України 2014
Series:Вопросы атомной науки и техники
Subjects:
Online Access:http://dspace.nbuv.gov.ua/handle/123456789/81167
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Journal Title:Digital Library of Periodicals of National Academy of Sciences of Ukraine
Cite this:Static neutronic calculation of a fusion neutron source / S.V. Chernitskiy, V.V. Gann, O. Ågren // Вопросы атомной науки и техники. — 2014. — № 6. — С. 12-15. — Бібліогр.: 20 назв. — англ.

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Digital Library of Periodicals of National Academy of Sciences of Ukraine