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Moscow, Russia

Ananyev S.S.,NRC Kurcharov Institute | Spitsyn A.V.,NRC Kurcharov Institute | Kuteev B.V.,NRC Kurcharov Institute
Fusion Engineering and Design | Year: 2016

The paper describes the concept of a deuterium-tritium fuel cycle of a steady-state thermonuclear reactor with a fusion power over 10 MW. Parameters of fuel cycle for nuclear facility (JET scale) with different types of fuel mixtures for neutral beam injection system are presented.Optimization of fuel cycle characteristics was aimed at reducing flows and inventory of hydrogen isotopes and tritium in fuel cycle subsystems. The calculations were carried out using computer code TC-FNS to estimate tritium distribution in fusion reactor systems and components of "tritium plant". The code enables calculations of tritium flows and inventory in the tokamak systems. Calculations of tritium flows and accumulation have been carried out for two different cases of the fuel mixture for neutral beam injection (NBI) system. The amounts of tritium which is required for operation of all fuel cycle systems in two different cases of the fuel mixture for NBI are 0.45 "". kg (D:T = 1:0) and 0.9. kg (D:T = 1:1) respectively. © 2016 Elsevier B.V.


Anan'ev S.S.,NRC Kurcharov Institute | Spitsyn A.V.,NRC Kurcharov Institute | Kuteev B.V.,NRC Kurcharov Institute | Shirnin P.N.,Federal State Unitary Enterprise | And 2 more authors.
Fusion Science and Technology | Year: 2015

A concept of DT-fusion neutron source (FNS) with the neutron yield higher than 1018 neutrons per second is under designe in Russia. Such a FNS is of interest for many applications: (i) basic and applied research (neutron scattering, etc); (ii) testing the structural materials for fusion reactors; (iii) control of sub-critical nuclear systems and (iv) nuclear waste processing (including transmutation of minor actinides). This paper describes of fuel cycle concept of a compact fusion neutron source based on a small spherical tokamak (FNS-ST) with a MW range of DT fusion power and considers the key physics issues of this device. The major and minor radii are ∼ 0.5 and ∼0.3m, magnetic field ∼1.5 T, heating power less than 15MW and plasma current 1-2 MA. The system provides the fuel mixture with equal fractions of D and T (D:T = 1:1) for all FNS technology systems.


Hatano Y.,University of Toyama | Alimov V.Kh.,University of Toyama | Alimov V.Kh.,Max Planck Institute for Plasma Physics (Garching) | Spitsyn A.V.,NRC Kurcharov Institute | And 11 more authors.
Fusion Science and Technology | Year: 2015

The effects of displacement damage, plasma exposure and heat loads on T retention in reduced-activation ferritic/martensitic (RAFM) steels were investigated by exposing the steels to DT gas at 473 K. Despite enormous change in surface morphology, T retention in the heat-loaded specimen was comparable with that in the unloaded specimen. The exposure to plasma resulted in a drastic increase in T retention at the surface and/or sub surface. However, the T trapped at the surface/subsurface was easily removed by maintaining the specimens in air at ∼300 K. Formation of radiation-induced defects led to a significant increase in T retention, and T trapped in the defects was not removed at ∼300 K. These observations suggest that displacement damages have the largest effects on T retention at ∼473 K.


Bobyr N.P.,NRC Kurcharov Institute | Alimov V.K.,Max Planck Institute for Plasma Physics (Garching) | Alimov V.K.,University of ToyamaToyama | Khripunov B.I.,NRC Kurcharov Institute | And 5 more authors.
Journal of Nuclear Materials | Year: 2015

Abstract Hydrogen isotopes exchange in tungsten was investigated after sequential exposures to low energy deuterium (D) and helium-seeded protium (He-seeded H) plasmas at sample temperatures of 403 and 533 K. Deuterium depth profiles were measured by the D(3He, p)4He nuclear reaction with 3He+ energies between 0.69 and 4.5 MeV allowing determination of the D concentration up to a depth of 8 μm. It was found that a significant part of the deuterium initially retained in tungsten after D plasma exposure was released during sequential exposure to a protium plasma. However, exposure of the D-plasma-exposed W samples to the He-seeded H plasma reduces the amount of released deuterium as compared to pure H plasma exposure. © 2014 Elsevier B.V.

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