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This work is devoted to the development of new composite materials for immobilizing medium- and low-level radioactive wastes. The most promising existing methods of solidification are low-temperature processes because they do not require complicated equipment and are cost-effective. As a result...
Information concerning the development and performance of environmental protection work and measures for guaranteeing the safety of the production operations conducted at the All-Russia Scientific–Research Institute of Chemical Technology is presented. Data on monitoring the adherence to the...
Multiparameteric integrity/failure criteria are proposed for models of Zr–2.5% Nb alloy channel pipes under conditions which simulate a disruption of the regular heat-removal regime in RBMK reactors (LOCA, ATWS type accidents). The criteria permit real-time assesssment and prediction of the...
The possibility of using a neutron source based on a 10 MeV compact betatron and 1 kg heavy water or 3.3 kg beryllium in the betratron bremsstrahlung beam is investigated. The 235 U detection limit in a 358 mm in diameter and 782 mm high container with probability 0.997 in an experimental...
A method and relations are proposed for determining the optimal ratio of the parameters for putting a reactor into a critical state safely: the initial subcriticality before reactor startup, the reactivity variation step, the initial pulse frequency, the initial counting rate of the number of...
The results of a computational experiment with a neural-net model simulating the effect of the chemical composition on the plastic properties of ÉP-450 steel are presented. It is shown that computer-aided development of reactor steel with prescribed properties is, in principle, possible.
A simplified 1D model is developed to calculate and analyze the characteristics of a thermionic converter for converting laser radiation into electricy. The dependences of the generated voltage and power and the efficiency on the parameters of the energy converter and the optical discharge...
The results of a simulation of the behavior of vacancies and interstitial atoms in uranium-dioxide fuel at temperature corresponding to the conditions under which a fine-grain structure forms are presented. It is shown that the distribution of point defects near grain boundaries and near line...
Single (one-section) reactors, containing a neptunium–gallium or uranium–molybdenum alloy core, and coupled two-section systems, consisting of a single pulsed reactor and a driven subcritical assembly, consisting of a uranium–molybdenum alloy or dispersed uranium–graphite material, are...
The simplest approximations (1D and 2D reactor, one-group diffusion model of neutron transport) are used to study the insensitivity, due to undetermined local perturbations of the multiplication power, of neutron-flux sensor indications to reactor subcriticality. The analysis is based on the...
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