[en] Statistical shell model of a dense high-temperature plasma is suggested. Apparent representation for the descrete electron energy levels was obtained. Model simplicity and efficiency of calculations enabled to generalize easily the method for calculating thermodynamic functions of multicomponent systems, composed of atoms of various chemical elements. Modifications of Kopyshev model are used for taking into account the imperfect character of nuclear component

No abstract available

No abstract available

[en] It is now widely recognized that further progress toward a commercial fusion reactor critically depends on the availability of low activated materials to be operated for many years in the fusion neutron environment without degradation of their properties. Therefore, high power neutron source (NS) for extensive material tests is in great demand. The realistic NS can be built on the basis of the gas dynamic trap (GDT) which is one of the simplest system for magnetic plasma confinement. GDT is an axisymmetric mirror machine of the Budker-Post type, but with a high mirror ratio (R>10), and operated with warm and relatively dense plasma. Thus, due to frequent collisions, the plasma confined in a trap is very close to isotropic Maxwellian, and hence many instabilities are not excited and plasma behavior is similar to a classical one. It is proposed to use the oblique injection of neutral tritium and deuterium beams with an energy of the order of 100 keV into the GDT 'warm' target plasma (electron temperature T_e≥750 eV) to produce high intensity neutron flux. In this case, due to the ionization and charge-exchange collisions with plasma particles the energetic atoms will turn into ions confined in the trap. The axial density profile of these anisotropic energetic ions will be strongly inhomogeneous. Namely, the maximum of the fast ion density will be located in the vicinities of mirrors and the minimum--at the middle plane of the device. Thus, a strongly inhomogeneous fusion neutron flux, mostly generated in the fast deuterium-tritium (D-T) ion collisions will appear. GDT NS looks to be rather flexible system. It enables to construct the source stepwise, starting from rather moderate parameters. Increasing the testing zone length and neutral beam power one can increase both neutron flux and the flux density. Calculations show that even in the modest version of the NS with T_e∼250 eV quite appreciable neutron flux density in the range of 0.2-0.3 MW/m² can be produced. At present, the maximum temperature about 130 eV is obtained in the experiments at the model GDT device at Budker INP. Further increase of the electron temperature in the device requires higher neutral beam power and now is considered to be straightforward

[en] Paper describes the results of the experiments to study angular distribution and spectrum of fast ions when deuterated polyethylene targets are irradiated by the SOKOL-P laser facility picosecond radiation with up to 2x10¹⁸ W/cm² intensity. The parameters of ion flow were measured by means of semiconducting detector base time-of-flight spectrometers

[en] Short communication

[en] The paper reviews some results of conceptual design of the 14 MeV D-T neutron source dedicated for fusion reactor materials and components testing. The source is based on use of the so called 'gas dynamic trap' (GDT) which was first proposed and studied at the Budker Institute of Nuclear Physics (Novosibirsk). The neutron flux in the test zone of the source makes up 2-2.5 MW m^-2 under realistic assumptions on achievable plasma parameters and amounts of tritium circulating in the system. An alternative application of using the proposed neutron source as a basis of pilot facility for long-lived radioactive waste transmutation is studied. It is shown that incineration of minor actinides in the transmutator provides a drastic reduction of amount and activity of long-lived waste. (orig.)

[en] Experimental results on fast neutron generation in D(d,n)He³ and T(d,n)He⁴ reactions in the SOKOL-P laser facility are presented. Solid targets were irradiated by 1.054 μm, s- or p-polarized laser pulses of energy 5-8 J on target and duration 0.85-2 ps. The peak laser intensity was 0.5 - 2.10¹⁸ W/cm². Flat deuterated plastic (CD₂)_n targets and TiD_αT_β targets were used in experiments. Some experiments were carried out with additional targets placed in front of and behind the laser target. The used (TOF) time-of-flight technique helped identify neutrons from D(d,n)He³ and T(d,n)He⁴ reactions. Yields up to 10⁶ DD-neutrons and 10⁷ DT-neutrons were measured. Interaction of the fast ion beam with the target can explain the observed yield. (authors)