[en] The result of work on accelerator based transmutation in VNIITF (Chelyabinsk-70) according to the ISTC Project 017 are presented. The goal is to develop a conceptual project of the facility for accelerator-based transmutation and conversion of military plutonium. The key elements of the concept being developed are application of active target multiplying neutrons, graphite blanket with molten salt fuel, combined fuel cycle at which weapon-grade plutonium is used for burning out of long-lived radioactive waste from commercial reactors. As the next stage of work it is proposed to build an experimental model of blanket at Chelyabinsk-70. It will be an experimental loop with forced pumping of the molten salt fuel. Recently, the appropriate project has been submitted to the ISTC. 10 refs., 2 tabs

[en] Consideration is given to the possibility of radical reduction in power requirements to the proton accelerator of the electronuclear reactor due to neutron multiplication both in the blanket and the target of an active material. The target is supposed to have the fast-neutron spectrum, and the blanket-the thermal one. The blanket and the target are separated by the thermal neutrons absorber, which is responsible for the neutron decoupling of the active target and blanket. Also made are preliminary estimations which illustrate that the realization of the idea under consideration can lead to significant reduction in power requirements to the proton beam and, hence considerably improve economic characteristics of the electronuclear reactor

[en] The report presents the results of the molten salt blanket neutronics calculations performed for researchers of a facility for accelerator-driven transmutation of long-lived radioactive wastes and plutonium conversion. Heterogeneous structure effect on molten salt blanket neutronics was studied through computation. 4 refs., 1 fig., 1 tab

[en] The corrosion situation in the 'structural materials melt' system was investigated at ORNL and at the I.V. Kurchatov Institute of Atomic Energy. However, presence of plutonium in the fuel composition can essentially change the corrosion processes of structural materials. Configuration of ampoule corrosion experiments with fuel composition on the basis of PuF₃ and test experiments with melts on basis of UF₄ will allow to receive the valuable information and to identify features of behavior of the candidat materials in fluorides media containing plutonium. The methodics of such experiment is presented in this report. 2 figs., 2 tabs

[en] Preliminary identification of the components and efficiency estimations for the proposed (by Chelyabinsk-70) concept of active target for electronuclear reactor are goals of this work. (The electronuclear reactor comprises a high-energy proton acclerator, a high-atomic-number target (lead, tungsten) which produces neutrons from the protons, and a subcritical blanket.) Results of preliminary neutron and thermal-hydraulic simulations of the target are represented in the paper and preliminary detailing of the active target components is performed. It is shown that the use of active target can lead to an essential reduction of the requirements to the accelerator power without deterioration of the safety of the system

[en] This report is devoted to the conception of demonstration ABC/ATW - facility. The proposal of facility location and design solutions in general are presented. 7 figs., 1 tab

[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.)