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Oct 13 – 18, 2014
Hotel Park Inn Pribaltiyskaya
Europe/Moscow timezone

The Neutronics Analysis of Blankets for the Hybrid Fusion Neutron Source

Oct 17, 2014, 8:30 AM
4h
Green 8-9 (Hotel Park Inn Pribaltiyskaya)

Green 8-9

Hotel Park Inn Pribaltiyskaya

Saint Petersburg, Russian Federation
Poster Poster 7

Speaker

Mr Alexey Zhirkin (Russian Federation)

Description

In this work it is investigated the capabilities of hybrid fusion neutron source (FNS) blankets in reprocessing of spent nuclear fuel and generation of nuclides 233U, 239Pu and tritium. The basic kinds of blankets are considered. There are the blanket with use of heavy water solutions of salts and oxides of uranium and thorium, solid-state and molten salt blanket. The structure and geometrical parameters of blankets, moderator and fertile materials are optimized to obtain the ultimate nuclear fuel yield at the least accumulation of radiation toxic wastes. The neutronics comparative analysis of the different blanket models is presented. In the result, the optimal FNS blanket models are chosen.
Paper Number FNS/P7-25
Country or International Organisation Russian Federation

Primary author

Mr Alexey Zhirkin (Russian Federation)

Co-authors

Boris Chukbar (Russian Federation) Dr Boris Kuteev (Russian Federation) Dr Mikhail Gurevich (Russian Federation)

Presentation materials