


Том 123, № 1 (2017)
- Год: 2017
- Статей: 12
- URL: https://journal-vniispk.ru/1063-4258/issue/view/15518
Articles
Computational and Experimental Studies of Mixing of a Light Gas in the ERCOSAM–SAMARA Projects
Аннотация
Severe accidents in NPP with VVER can be accompanied by hydrogen entering the containment space. The aim of the present work is an experimental and computational study of the possibility of hydrogen stratification in the containment in a scenario replicating the sequence of events occurring during a severe accident with hydrogen emission in a light-water reactor taking account of the impact of accident control on the distribution of a light gas. Euratom and the government corporation Rosatom performed the studies as part of two parallel projects – ERCOSAM and SAMARA. The experimental studies show that heat exchangers aand recombiners do bring about complete mixing of the light gas; a sprinkler system affords mixing of the stratified layer. The experimental studies confirm the results of numerical modeling.



Article
Some Results of Multicriterial and Robust Optimization of Nuclear Power Systems Structure
Аннотация
The possibility of applying multicriterial and robust optimization methods as well as stochastic methods of determining the effect of uncertainties in the parameters of a system to structural optimization of nuclear power is discussed for the example of a hypothetical nuclear-power system consisting of thermal and fast reactors. It is shown that the optimal structures of nuclear power systems obtained by such methods are balanced in terms of conflicting criteria and technologically more diversified than those determined by single-criterion deterministic optimization. Cost-based innovative technologies, which can be adopted only by imposing additional external limitations in a single-criterion problem, appear in such structures. The examined methods make it possible to determine on a systematic basis the structures of nuclear power that are balanced in terms of a set of conflicting criteria, since factors having both positive and negative effects on the development of nuclear-power systems are included in the calculations, and to find economically efficient directions of structural changes in the system in order to improve stability and efficiency.



Core Conversion of VVR-K Research Reactors
Аннотация
The conversion of the VVR-K research reactor to low-enrichment uranium fuel includes switching to a compact core with low-enrichment uranium and gradually transitioning from a light-water side reflector to a beryllium reflector with restoration of the working reactivity margin without makeup with fresh fuel. In 2015, the reactor was stopped in order to modernize the main elements of the core, the control and protection system for the channels of the working rods, and the emergency electric power source. First criticality of VVR-K with low-enrichment fuel followed by first start of the reactor occurred in spring 2016. The VVR-KN type FA specially developed for VVR-K make it possible to not only preserve but also improve the neutronphysical characteristics of the core. The design-basis reactivity margin of the working core load ~7%Δk/k is adequate for reactor operation for three 20-day cycles with ~10% average burnup reached in the central FA. The beryllium reflector is built up in stages starting at the fourth cycle. The beryllium reflector will make it possible to preserve the radial dimensions of the core and increase the neutron flux density in the central and peripheral irradiation channels.



Experimental Studies of Coolant Temperature and Velocity on an Integrated Water Model of a Fast Reactor in Different Operating Regimes
Аннотация
The results of experimental studies of a next-generation fast reactor performed using an integrated water model (scale 1:10) are presented: local velocity over height and radius of the top chamber in a plane in a direction from core center to the intermediate heat exchangers and coolant temperature in the top chamber and other elements of the circulation loop with forced circulation and emergency cool-down by natural convection. The data were obtained using a specially designed system for performing measurements which is incorporated in the bench and provides high accuracy and rate of acquisition. Stable temperature stratification of the coolant is observed in the top, cold, and pressure chambers of the reactor, elevator enclosure, and reactor vessel cooling system as well as at the exit from the intermediate and autonomous heat exchangers in different operating regimes.



Research on the Thermophysics of Next-Generation Nuclear Reactors
Аннотация
The results of scientific research on the thermophysics of next-generation nuclear reactors conducted at the Leipunskii Institute of Physics and Power Engineering are presented: integrated experimental and computational-theoretical studies to validate design and engineering solutions as well as the safety of fast reactors with sodium and heavy liquid-metal coolant, increasing the efficiency and safety of currently operating and future NPP with water-cooled reactors, software development and certification, pilot research on innovative nuclear power facilities (fast reactors with supercritical water and high-temperature sodium coolant).



Modeling of Gas Dynamic Processes in the Interelectrode Gap of a Multielement Thermionic Electricity Generating Channel by Solving the Kinetic Equation
Аннотация
This work is devoted to the application of a numerical method of solving Boltzmann’s equation for modeling the behavior of radionuclides (Kr, Xe, Rb, Sr, Cs, Ba) in the cavity of the interelectrode gap of a multielement electricity generating channel. Modeling methods were developed and software system implemented in the course of this work. Calculations were performed for two structural arrangements: with uni- and bilateral extraction of radionuclides into the vacuum-cesium system. Data on the pressure and flow distributions were obtained. The krypton and xenon pressure near the collector as functions of their flow and the cesium gas pressure at the gap exits were determined computationally.



Separating Stable Boron Isotopes in Uniflow Gas Centrifuges
Аннотация
A variant of a model of a uniflow gas centrifuge for separating a binary mixture of boron isotopes in the trifluoride form, taking account of the interaction of the rotating gas with a stationary cylindrical central body, is proposed. Expressions are obtained for the maximum admissible enrichment and separation factors and the optimal separative power as functions of the radius of the central body. It is shown that a cascade of uniflow gas centrifuges with more than 95% enrichment of boron trifluoride in terms of the 10B isotope in the requisite quantities for industry can be built in practice.



Measurement of Terbium Isotopes Yield in Irradiation of 151Eu Targets by 3He Nuclei
Аннотация
This article is devoted to obtaining the α-emitter 149Tb for radioimmunotherapy. A method for producing 149Tb based on the reaction 151Eu(3He, 5n)149Tb is proposed. It is proposed that europium with native isotopic composition (151Eu – 47.81%, 153Eu – 52.19%) or enriched 151Eu be used as the target. The 29 MeV threshold of the indicated reaction makes it possible to use accelerators with the initial 3He energy 40–70 MeV.



14C Entry into the Atmosphere
Аннотация
14C enters the atmosphere in amounts equivalent to 1.4 PBq/yr with total accumulation 140 PBq via cosmic radiation. As a result of nuclear explosions (1950–1969), its activity in the atmosphere exceeded 200 PBq. At present, 14C has been completely removed into bottom waters and sedimentary rocks in the ocean. The activity of the 14C entering the atmosphere from all operating nuclear reactors equals ~0.3 PBq/yr and the amount from all spent fuel reprocessing facilities equals ~0.06 PBq/yr. The admissible levels of 14C emissions must not exceed levels corresponding to peroral intake dose 10 μSv/yr. This is can be accomplished by means of a system of measures: reduction of the volume of technogenic gases and their 12CO2 content, combining high-efficiency purification with dispersion through high exhaust-stacks, and developing new technologies and reagents binding 14C in compact forms.



Lucky-a Code Verification on a Test Problem of Modeling Transients Accompanying LWR Reactivity Change



Correction



Scientific and Technical Communications
Atmospheric Fallout of 7Be in 2009–2014 in Tashkent and Samarkand


