PURIFICATION OF FAST REACTORS PRIMARY SODIUM COOLANT FROM CESIUM RADIONUCLIDES

The advantage of using cesium traps in the decommissioning of fast reactors is shown. The experience of their use on the BN‑350 is described and the possibility of purifying the sodium of the BN‑600 primary circuit in the same way is considered.Показано преимущество использования цезиевых ловушек при выводе из эксплуатации реакторов на быстрых нейтронах. Описан опыт их использования на БН‑350 и рассмотрена возможность очистки натрия первого контура БН‑600 аналогичным способом

THE PROBLEM STATEMENT OF THE SIMULATION OF SODIUM FLOW THROUGH A GRAPHITE FILTER BED

Рассмотрена постановка задачи моделирования течения натрия через насыпной слой графита ловушки для удаления радионуклидов цезия из теплоносителя реактора на быстрых нейтронах. Построена твердотельная модель ловушки. Произведен оценочный расчет движения жидкого натрия через ловушку

ABOUT THE PRODUCTION OF SELENIUM-75 ISOTOPES

В работе описаны свойства и применение изотопа селен-75. Рассмотрены проблемы получения этого изотопа в реакторе и в ускорителе элементарных частиц. Представлен вариант конструкции целевой капсулы для наработки селена-75. Сделан обзор химических формул материала гранул, содержащих прекурсор для образования селена-75.The properties and application of the isotope selenium-75 are described. The problems of obtaining this isotope in the reactor and in the particle accelerator are considered. A variant of the target capsule design for selenium-75 production is presented. The review of the chemical formulas of material of granules containing a precursor for formation of selenium-75 is made

EXPERIMENTAL RESEARCH OF THE LRW ION-SELECTIVE TREATMENT SORBENTS HYDRAULIC RESISTANCE

The technique and methodology for experimental research of packed equipment are pre-sented. The results of the LRW ion-selective treatment sorbents layer specific hydraulic re-sistance experimental measurements are shown

Analysis of the Possibility of Using Polyimide as a Binding Matrix for Radiation-Protective Materials Filled with Depleted Uranium

The article describes the use of polyimide as a binder and the search for a technology for encapsulating depleted uranium in various compounds. The results of modeling the protective properties of a composite material by the Monte Carlo method are presented

EXPERIMENTAL STUDY OF THE PROTECTIVE PROPERTIES OF POLYMER COMPOSITES WITH POZZOLAN AGAINST GAMMA RADIATION

The article summarizes the results of an experimental study of polymer composite materials as radiation protection against gamma radiation, the filler of which is a mixture of volcanic ash, tuff and pumice

SIMULATION AND EXPERIMENTAL STUDY OF HYDRODYNAMIC CHARACTERISTICS OF SORBENTS FOR ION-SELECTIVE TREATMENT OF LRW

Given are the results of experimental study of hydrodynamic resistance of a layer of sorbents used for cesium removal LRW. Conducted is a simulation of water flow through the sorbent layer with SolidWorks Flow Simulation program. The simulation results are com-pared with the experiments data

EVALUATION OF ICE CONDENSER EFFICIENCY DEPENDING ON ITS GEOMETRIC CONFIGURATION

In this paper, we studied the influence of geometric characteristics of an ice condenser, modeled in the COMSOL Multiphysics computational package, on the heat flux intensity. The calculation of the necessary refrigeration unit to maintain the ice condenser in the state of readiness was carried out

COMPUTATIONAL AND EXPERIMENTAL STUDIES OF HYDRODYNAMIC OPERATING CONDITIONS OF FILTER CONTAINERS FOR ION SELECTIVE PURIFICATION

The generation of radioactive waste (RW) is a specific feature of NPP operation. Liquid radioactive waste (LRW) is generated during the operation of reactor facilities, decontamination of equipment, premises and overalls. The main radionuclides in the distillation residues are 134,137Cs in the form of ions and isotopes 60Co, 54Mn in the form of complexons with substances that are used to decontaminate equipment. Among the known methods of conditioning, the largest reduction in the volume of LRW occurs with selective sorption. It is possible to increase the efficiency of using the volume of the filtering material by supplying the medium to be purified simultaneously into several layers of the sorbent. In the work, computer simulation of three proposed variants of improved designs of the filter container for ion-selective purification was carried out, which differ both in the ways of separating the flows of purified water and in the methods of their supply to the sorbent layers. All versions of the filter containers had the same cross-sectional area and height of the sorbent layers. Evaluation of the increase in the efficiency of sorption processes in the proposed designs was carried out using computer simulation in SolidWorks Flow Simulation. Three sorbents of NPP Eksorb were used. To determine the hydraulic resistance of the samples under study, a series of experimental studies of the flow through the sorbent layer was carried out. Experiments have shown that the hydraulic resistance of the layer increases in a quadratic dependence on the flow velocity, which is consistent with the Ergun equation. The obtained experimental data was added to the SolidWorks Flow Simulation engineering database to simulate the previously presented structures. Based on the simulation results, the characteristic parameters of the flow in the cavity of the filter containers were obtained. Modeling showed that, in all variants, the flow rate of the medium was distributed approximately equally among the layers. It was revealed that the third design option has the least hydraulic resistance. The chemical interaction of the filtered medium with the sorbent was not considered in the calculations. © 2022 Obninsk Institute for Nuclear Power Engineering, National Research Nuclear University 'MEPhI'. All rights reserved