Physics of Atomic Nuclei最新文献_第6页

Verification of the VVER-1200 Reactor Dynamic Model Consisting of a Single Fuel Node Adjacent to Two Coolant Nodes

IF 0.3 4区物理与天体物理

Physics of Atomic Nuclei Pub Date : 2025-02-01 DOI: 10.1134/S1063778824100375

S. S. Pravosud, D. S. Maslakov, Ya. O. Yakubov, A. A. Ovcherenko

{"title":"Verification of the VVER-1200 Reactor Dynamic Model Consisting of a Single Fuel Node Adjacent to Two Coolant Nodes","authors":"S. S. Pravosud, D. S. Maslakov, Ya. O. Yakubov, A. A. Ovcherenko","doi":"10.1134/S1063778824100375","DOIUrl":"10.1134/S1063778824100375","url":null,"abstract":"Since the modern automatic control theory imposes constraints on the mathematical models of control objects, further development and verification of mathematical models of nuclear power facilities suitable for the synthesis of automatic power control systems is a topical problem. This article deals with a low-order dynamic model with lumped parameters of the Russian-designed pressurized water reactor, as well as with its verification with experimental data from the full-size simulator of the VVER–1200 nuclear reactor in two tests involving the variation of the position of group 12 of CPS CR and the variation of the inlet coolant temperature. This model was created as a MATLAB S-function lv.2 model because of its capability to process any input signals. Within this approach, the equation describing the heating of the coolant is represented as a «two well-stirred tanks in series» model. The article demonstrates the advantage of the given approach over the conventional approach, where the average temperature of the coolant is determined as the arithmetic mean of the inlet and outlet coolant temperatures on the basis of a test with a sudden change in the reactor inlet coolant temperature. In the frequency domain, the authors carry out the stability analysis of the given model in the state-space form with respect to various external perturbations. Conclusions are drawn about the possibility of using the model as a fifth-order control object for the parametric synthesis of a controller for the automatic power control system of a nuclear power facility.","PeriodicalId":728,"journal":{"name":"Physics of Atomic Nuclei","volume":"87 9","pages":"1195 - 1203"},"PeriodicalIF":0.3,"publicationDate":"2025-02-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143107842","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Analysis and Optimization of Intrafuel Assembly Nonuniform Power Density and Burnup of WWER-1000 Fuel

IF 0.3 4区物理与天体物理

Physics of Atomic Nuclei Pub Date : 2025-02-01 DOI: 10.1134/S1063778824100284

A. A. Lapkis, A. S. Starchenko, D. V. Trishechkin, I. Yu. Popova

{"title":"Analysis and Optimization of Intrafuel Assembly Nonuniform Power Density and Burnup of WWER-1000 Fuel","authors":"A. A. Lapkis, A. S. Starchenko, D. V. Trishechkin, I. Yu. Popova","doi":"10.1134/S1063778824100284","DOIUrl":"10.1134/S1063778824100284","url":null,"abstract":"This paper considers and systematizes fuel assembly variants for the WWER-1000 reactor. A fuel assembly of infinite height with six U49G6-type U–Gd fuel rods used in large-capacity WWER-1000 fuel loads is simulated in the Serpent neutronic code. As a result of the calculations, U–Gd fuel rod arrangement with less uneven power density along the fuel assembly is selected, and the effect of the number of U–Gd fuel rods and their arrangement on reactivity is assessed. It is shown that the arrangement of U–Gd fuel rods in the fourth ring is optimal in terms of uneven power density per fuel rod and burnup. The effect of fuel assembly arrangement on the fuel burnup for individual groups of U–Gd fuel rods is considered. An option is proposed for reducing the cost of computing resources by identifying the groups of fuel rods with the greatest differences in power density and burnup. The studied assemblies are compared with the existing U49G6 fuel assembly. A method is proposed for estimating the underproduction of thermal energy in a fuel assembly due to the uneven burnup of fuel rods, while maintaining the maximum burnup for individual fuel rods. Based on the analysis of underproduction, an option is proposed for improving the fuel assembly layout with six U–Gd fuel rods to equalize the power density field and reduce unproductive fuel losses. For this purpose, enrichment in the first, second, and tenth fuel rod rings, counting from the central fuel assembly tube, can be reduced. As a result of such profiling, the burnup of the most burnt fuel rods in the fuel assembly can be reduced to 1.015 of the average burnup.","PeriodicalId":728,"journal":{"name":"Physics of Atomic Nuclei","volume":"87 9","pages":"1204 - 1212"},"PeriodicalIF":0.3,"publicationDate":"2025-02-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143107843","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Coatings on a First Wall Plasma-Facing Surface: Analysis and High Heat Flux Testing on the Tsefey-M E-Beam Facility

IF 0.3 4区物理与天体物理

Physics of Atomic Nuclei Pub Date : 2025-01-23 DOI: 10.1134/S1063778824130076

P. Yu. Piskarev, R. V. Rulev, I. V. Mazul, A. V. Krasilnikov, A. A. Pisarev, B. V. Kuteev, M. S. Kolesnik, V. V. Dushik, S. V. Bobrov, N. V. Montak, A. A. Rybikov, T. N. Bukatin

{"title":"Coatings on a First Wall Plasma-Facing Surface: Analysis and High Heat Flux Testing on the Tsefey-M E-Beam Facility","authors":"P. Yu. Piskarev, R. V. Rulev, I. V. Mazul, A. V. Krasilnikov, A. A. Pisarev, B. V. Kuteev, M. S. Kolesnik, V. V. Dushik, S. V. Bobrov, N. V. Montak, A. A. Rybikov, T. N. Bukatin","doi":"10.1134/S1063778824130076","DOIUrl":"10.1134/S1063778824130076","url":null,"abstract":"Some aspects of the use of coatings for various functional purposes on the first wall plasma-facing surface of a thermonuclear reactor are considered. An important characteristic of coatings is adhesive and fatigue strength under cyclic impact of quasi-stationary heat loads, as well as resistance to high pulsed thermal loads. This paper describes thermal cyclic tests with surface thermal load of water-cooled mockups with various coatings on the heat-receiving surface. The B4C coating, made by atmospheric plasma spraying on a tungsten substrate, demonstrated excellent durability over 1400 thermal cycles at 4.7 MW/m2. CVD tungsten coating on a copper substrate demonstrated good results after 1000 thermal cycles at 3.3 MW/m2, but after a similar number of cycles at 5 MW/m2, cracks were detected on the surface. The stainless steel coating on a copper substrate demonstrated resistance to loads up to 11.9 MW/m2, as well as excellent durability over 1000 thermal cycles at 8.2 MW/m2.","PeriodicalId":728,"journal":{"name":"Physics of Atomic Nuclei","volume":"87 1 supplement","pages":"S118 - S128"},"PeriodicalIF":0.3,"publicationDate":"2025-01-23","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143109028","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Numerical Simulation of Melt Metal Layer Movement under Conditions Relevant to ITER Transient Regimes

IF 0.3 4区物理与天体物理

Physics of Atomic Nuclei Pub Date : 2025-01-23 DOI: 10.1134/S1063778824130015

I. A. Aliabev, V. Yu. Tsybenko, I. M. Poznyak, E. Z. Biryulin, Z. I. Novoselova, E. D. Fedulaev, A. B. Putrik

{"title":"Numerical Simulation of Melt Metal Layer Movement under Conditions Relevant to ITER Transient Regimes","authors":"I. A. Aliabev, V. Yu. Tsybenko, I. M. Poznyak, E. Z. Biryulin, Z. I. Novoselova, E. D. Fedulaev, A. B. Putrik","doi":"10.1134/S1063778824130015","DOIUrl":"10.1134/S1063778824130015","url":null,"abstract":"Armor materials of the ITER divertor and the first wall will be subjected to intense plasma-thermal impact during reactor operation. One of the prevalent types of metal protective coating erosion is due to displacement of the molten surface layer. In order to obtain solid interpretations of physical processes, development and verification of numerical models are required. The aim of this paper is to outline initial development of the numerical model, which describes the motion of a metal molten layer under the impact of an intense plasma stream. Numerical calculations are based on experimental data obtained at the quasi-stationary high current plasma accelerator QSPA-T. The motion of the molten metal is described by a system of coupled heat transfer and Navier–Stokes equations. In the case of consideration of an external magnetic field, Maxwell’s equations are included in the system. It is assumed that a metal target is exposed to a pulsed plasma stream with specified temporal and spatial distributions of power and pressure. Plasma exposure causes melting and subsequent motion of the surface layer of the material. Thermophysical properties of the metal are considered temperature dependent. Material evaporation from the exposed surface is taken into account in the model. The metal layer displacement was obtained for various values of the plasma stream incident to the surface. It is shown that the melt motion observed in the experiment cannot be explained by the action of the plasma pressure stream gradient alone. The friction force between the near-surface plasma and the molten metal was implemented in the numerical model, whereby a quantitative agreement between the calculation results and experimental data was achieved. In addition, magnetic field conditions were applied in the model. The influence of both the stagnation pressure and power dynamics on the resulting profile of the target surface was studied.","PeriodicalId":728,"journal":{"name":"Physics of Atomic Nuclei","volume":"87 1 supplement","pages":"S80 - S90"},"PeriodicalIF":0.3,"publicationDate":"2025-01-23","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143109084","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Influence of Annealing Temperature on the Microstructure Features and Microhardness of Carbide-Strengthened V–Cr–W–Zr Alloy

IF 0.3 4区物理与天体物理

Physics of Atomic Nuclei Pub Date : 2025-01-23 DOI: 10.1134/S1063778824130210

I. V. Smirnov, I. A. Ditenberg, K. V. Grinyaev, A. N. Tyumentsev, Yu. P. Pinzhin, D. A. Osipov, A. D. Korotaev, V. M. Chernov, M. M. Potapenko

{"title":"Influence of Annealing Temperature on the Microstructure Features and Microhardness of Carbide-Strengthened V–Cr–W–Zr Alloy","authors":"I. V. Smirnov, I. A. Ditenberg, K. V. Grinyaev, A. N. Tyumentsev, Yu. P. Pinzhin, D. A. Osipov, A. D. Korotaev, V. M. Chernov, M. M. Potapenko","doi":"10.1134/S1063778824130210","DOIUrl":"10.1134/S1063778824130210","url":null,"abstract":"A study of the influence of annealing in the range from 700 to 1600°С on the microstructure features and microhardness values of the V–Cr–W–Zr alloy after thermomechanical treatment was carried out. It was found that, as a result of rolling in the V–Cr–W–Zr alloy, texture fibers α, γ, θ are formed. It has been established that the structural state after thermomechanical treatment is stable up to 800°С. At 900°С, primary recrystallization is activated, which at 1000°С covers the entire volume of the material. Collective recrystallization processes occur in the temperature range of 1100–1400°С. Secondary recrystallization is activated at 1500°С. Under conditions of primary, collective, and secondary recrystallization, against the background of orientational grain growth, the disappearance of the texture components of the θ-fiber is observed. It was established that, in the temperature range of 1500–1600°С, a partial redistribution of W occurs. The influence of the average grain size on the microhardness values of the alloy was analyzed. The main mechanisms of material strengthening are discussed.","PeriodicalId":728,"journal":{"name":"Physics of Atomic Nuclei","volume":"87 1 supplement","pages":"S192 - S201"},"PeriodicalIF":0.3,"publicationDate":"2025-01-23","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143108818","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Effect of Plasma-Facing Material Selection on Hydrogen Accumulation in Fusion Devices

IF 0.3 4区物理与天体物理

Physics of Atomic Nuclei Pub Date : 2025-01-23 DOI: 10.1134/S1063778824130040

Yu. M. Gasparyan, S. A. Krat

引用次数: 0

Alternative Approach in the Technology of Initial Conditioning of a Tokamak Discharge Chamber for Plasma Experiments Using the Examples of TSP and T-11M

IF 0.3 4区物理与天体物理

Physics of Atomic Nuclei Pub Date : 2025-01-23 DOI: 10.1134/S1063778824130271

V. A. Morozov, A. N. Shcherbak, S. V. Mirnov

引用次数: 0

Effect of Tungsten Shielding with Bismuth under the Influence of Powerful Flow of Hydrogen Plasma

IF 0.3 4区物理与天体物理

Physics of Atomic Nuclei Pub Date : 2025-01-23 DOI: 10.1134/S1063778824130222

D. A. Toporkov, D. A. Burmistrov, V. A. Barsuk, V. V. Gavrilov, S.V. Karelov, N. S. Klimov, S. D. Lidzhigoriaev, A. V. Pushina

引用次数: 0

Testing of Tungsten Plasma-Facing Components of a Divertor in PLM Plasma Device

IF 0.3 4区物理与天体物理

Physics of Atomic Nuclei Pub Date : 2025-01-23 DOI: 10.1134/S1063778824130143

V. P. Budaev, S. D. Fedorovich, A. V. Dedov, D. I. Kavyrshin, A. V. Karpov, M. V. Lukashevsky, A. V. Zakharenkov, M. V. Gubkin, Q. V. Tran, K. A. Rogozin, A. A. Konkov, A. I. Gubanova

{"title":"Testing of Tungsten Plasma-Facing Components of a Divertor in PLM Plasma Device","authors":"V. P. Budaev, S. D. Fedorovich, A. V. Dedov, D. I. Kavyrshin, A. V. Karpov, M. V. Lukashevsky, A. V. Zakharenkov, M. V. Gubkin, Q. V. Tran, K. A. Rogozin, A. A. Konkov, A. I. Gubanova","doi":"10.1134/S1063778824130143","DOIUrl":"10.1134/S1063778824130143","url":null,"abstract":"The created plasma device PLM-M is used to test the heat-shielding lining of the in-vessel components of a thermonuclear reactor with steady-state plasma having parameters similar to the near-wall and divertor plasma of a tokamak. The PLM-M is a linear magnetic trap with a multi-cusp magnetic field. A special feature of the device is the many hours of steady-state operation with magnetized plasma of high parameters. Tungsten modules manufactured using ITER divertor technology have been tested with high-heat loads from ~1 to ~5 MW/m2. There were no significant macroscopic surface changes, large-scale cracks or splits on the surface, or significant erosion of the tungsten layout during plasma tests. For additional load on the tungsten during plasma tests, a laser with a power simulating the level of ELMs was used. Traces of arcs were detected on the plasma-facing tungsten surface of the model during plasma tests. Additional tests of cooled tungsten modules of in-vessel components are planned in order to estimate their erosion in the ITER and develop recommendations for in-vessel component design for the FNS.","PeriodicalId":728,"journal":{"name":"Physics of Atomic Nuclei","volume":"87 1 supplement","pages":"S91 - S98"},"PeriodicalIF":0.3,"publicationDate":"2025-01-23","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143108914","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Tokamak Tritium Cycle System with Reactor Technologies

IF 0.3 4区物理与天体物理

Physics of Atomic Nuclei Pub Date : 2025-01-23 DOI: 10.1134/S106377882413012X

A. S. Anikin, A. A. Semenov, A. V. Lizunov, M. B. Rozenkevich, N. B. Rodionov, A. R. Khayrov, A. V. Rudov, V. N. Kondrashov

{"title":"Tokamak Tritium Cycle System with Reactor Technologies","authors":"A. S. Anikin, A. A. Semenov, A. V. Lizunov, M. B. Rozenkevich, N. B. Rodionov, A. R. Khayrov, A. V. Rudov, V. N. Kondrashov","doi":"10.1134/S106377882413012X","DOIUrl":"10.1134/S106377882413012X","url":null,"abstract":"In this article, on the basis of world experience in the field of handling tritium-containing media and on the basis of our own experimental data, a scheme of the tritium cycle system for a tokamak with reactor technologies is proposed. When calculating the characteristics of the tokamak tritium cycle system, it was assumed that the total volume of tritium in the facility is 20 g, and 0.1 g of tritium is consumed per pulse. The proposed scheme provides a complete recycling of tritium and consists of a subsystem for the sorption storage of deuterium and tritium on intermetallic compounds based on zirconium; a subsystem for the chemical purification of the exhaust gas mixture from the toroidal chamber of the tokamak trapping nitrogen, oxygen and carbon ions; a subsystem for the membrane separation of hydrogen isotopes from the gas mixtures; subsystems for the separation of hydrogen isotopes by thermal diffusion; subsystems for the purification of waste process streams by the method of phase isotope exchange, which provides for the preliminary catalytic oxidation of hydrogen isotopes to water; and a subsystem for the concentration of tritium-containing water by the method of chemical isotope exchange in the “water–hydrogen” system. Requirements are provided and analytical and radiometric equipment is proposed to ensure control of the necessary parameters and reliable protection of personnel, the public, and the environment from the effects of tritium.","PeriodicalId":728,"journal":{"name":"Physics of Atomic Nuclei","volume":"87 1 supplement","pages":"S166 - S172"},"PeriodicalIF":0.3,"publicationDate":"2025-01-23","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143108958","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0