Physics of Atomic Nuclei最新文献

筛选
英文 中文
Analysis of the Behavior of Al–AlN–TiB2 Composite under Heating and Plasma Irradiation Al-AlN-TiB2复合材料在加热和等离子体辐照下的行为分析
IF 0.5 4区 物理与天体物理
Physics of Atomic Nuclei Pub Date : 2026-08-30 DOI: 10.1134/S1063778826140048
T. Solarevic, Yu. M. Gasparyan, V. S. Efimov, A. S. Umerenkova, N. Ostojic, N. S. Sergeev, D. N. Sinelnikov, N. E. Efimov, V. E. Loryan
{"title":"Analysis of the Behavior of Al–AlN–TiB2 Composite under Heating and Plasma Irradiation","authors":"T. Solarevic,&nbsp;Yu. M. Gasparyan,&nbsp;V. S. Efimov,&nbsp;A. S. Umerenkova,&nbsp;N. Ostojic,&nbsp;N. S. Sergeev,&nbsp;D. N. Sinelnikov,&nbsp;N. E. Efimov,&nbsp;V. E. Loryan","doi":"10.1134/S1063778826140048","DOIUrl":"10.1134/S1063778826140048","url":null,"abstract":"<p>This study investigates the behavior of an Al–AlN–TiB<sub>2</sub> ceramic composite during heating and provides a preliminary assessment of its compatibility with hydrogen plasma. The study included an analysis of the atomic flux from the surface during heating, sample mass loss, and deuterium retention during plasma irradiation. It was found that free aluminum diffuses to the surface at approximately 600°C and evaporates from the material at temperatures above 900°C. Regular surface breakdowns and microparticle emission were observed during exposure to deuterium plasma. Deuterium retention in the material was relatively low and varied little with fluence at low irradiation temperatures.</p>","PeriodicalId":728,"journal":{"name":"Physics of Atomic Nuclei","volume":"89 2","pages":"S256 - S263"},"PeriodicalIF":0.5,"publicationDate":"2026-08-30","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"148853894","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
Boron Carbide Ceramics as Neutron Shielding for ITER Port Plugs 碳化硼陶瓷在ITER端口塞中的中子屏蔽作用
IF 0.5 4区 物理与天体物理
Physics of Atomic Nuclei Pub Date : 2026-08-30 DOI: 10.1134/S1063778826140036
A. A. Shoshin, A. V. Burdakov, M. V. Ivantsivskiy, S. V. Polosatkin, Yu. S. Sulyaev, A. M. Semenov, D. E. Gavrilenko, S. Yu. Taskaev, D. A. Kasatov, D. E. Kravtsov, N. V. Sorokina, A. I. Ovsienko, V. I. Rumyantsev
{"title":"Boron Carbide Ceramics as Neutron Shielding for ITER Port Plugs","authors":"A. A. Shoshin,&nbsp;A. V. Burdakov,&nbsp;M. V. Ivantsivskiy,&nbsp;S. V. Polosatkin,&nbsp;Yu. S. Sulyaev,&nbsp;A. M. Semenov,&nbsp;D. E. Gavrilenko,&nbsp;S. Yu. Taskaev,&nbsp;D. A. Kasatov,&nbsp;D. E. Kravtsov,&nbsp;N. V. Sorokina,&nbsp;A. I. Ovsienko,&nbsp;V. I. Rumyantsev","doi":"10.1134/S1063778826140036","DOIUrl":"10.1134/S1063778826140036","url":null,"abstract":"<p>During the work on integrating the diagnostics into the ITER ports, a problem arose with providing the required radiation protection. It was proposed that a large amount of a neutron-absorbing material, boron carbide, be placed in the vacuum chamber in the port plug. The chemical composition and the thermal and vacuum properties of various B<sub>4</sub>C ceramics from several manufacturers were studied. Sintered ceramics in the form of blocks with holes were selected. A specification for the production of ceramics for ITER ports was agreed upon. Experiments on irradiation of ceramics with neutrons at the VITA accelerator were carried out. The degradation of mechanical properties after prolonged fast neutron irradiation was investigated. Serial production of sintered ceramics was started. The ITER Organization has approved the End of Manufacturing reports on the serial batches of ceramics.</p>","PeriodicalId":728,"journal":{"name":"Physics of Atomic Nuclei","volume":"89 2","pages":"S218 - S225"},"PeriodicalIF":0.5,"publicationDate":"2026-08-30","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"148853893","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
Method for Controlling the Straightness of the Channels of the Cooling System of the ITER Fusion Reactor Diagnostic Ports ITER聚变反应堆诊断口冷却系统通道直线度控制方法
IF 0.5 4区 物理与天体物理
Physics of Atomic Nuclei Pub Date : 2026-08-30 DOI: 10.1134/S1063778826140024
D. E. Gavrilenko, A. V. Burdakov, M. V. Ivantsivskiy, L. E. Serdakov, A. V. Polyanskiy, V. S. Krapivin, A. A. Shoshin, Yu. S. Sulyaev
{"title":"Method for Controlling the Straightness of the Channels of the Cooling System of the ITER Fusion Reactor Diagnostic Ports","authors":"D. E. Gavrilenko,&nbsp;A. V. Burdakov,&nbsp;M. V. Ivantsivskiy,&nbsp;L. E. Serdakov,&nbsp;A. V. Polyanskiy,&nbsp;V. S. Krapivin,&nbsp;A. A. Shoshin,&nbsp;Yu. S. Sulyaev","doi":"10.1134/S1063778826140024","DOIUrl":"10.1134/S1063778826140024","url":null,"abstract":"<p>The article describes a method for controlling the geometric parameters of the cooling system channels of the diagnostic shielding modules of the equatorial port no. 11 of the ITER nuclear installation made using counter deep drilling technology. The technique is based on the use of an angular reflector moving through the test channel and a laser tracker. The results of the qualification of the methodology on a full-size test product modeling the deepest channels in the diagnostic shielding module are presented.</p>","PeriodicalId":728,"journal":{"name":"Physics of Atomic Nuclei","volume":"89 2","pages":"S226 - S234"},"PeriodicalIF":0.5,"publicationDate":"2026-08-30","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"148856726","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
Concept of the T-15MD Tokamak Diamagnetic Measurement System T-15MD托卡马克抗磁测量系统的概念
IF 0.5 4区 物理与天体物理
Physics of Atomic Nuclei Pub Date : 2026-08-30 DOI: 10.1134/S1063778826140073
V. I. Tepikin, A. M. Belov, A. V. Sushkov
{"title":"Concept of the T-15MD Tokamak Diamagnetic Measurement System","authors":"V. I. Tepikin,&nbsp;A. M. Belov,&nbsp;A. V. Sushkov","doi":"10.1134/S1063778826140073","DOIUrl":"10.1134/S1063778826140073","url":null,"abstract":"<p>The classic method of evaluating the plasma energy content <i>W</i><sub>dia</sub> and the poloidal beta β<sub>p</sub> is to perform and analyze diamagnetic measurements. This article discusses a preliminary version of the T-15MD tokamak (<i>R</i> = 1.48 m, <i>a</i> = 0.67 m, <i>B</i><sub>0</sub> = 2.0 T, <i>I</i><sub>p</sub> = 2 MA) diamagnetic measurement system. The results of modeling the signals of the diamagnetic measurement system are analyzed, and the algorithm for obtaining the plasma-related toroidal magnetic flux from experimental data is presented. The composition, design, and arrangement of the primary sensors of diamagnetic loops and compensation coils proposed for installation on the T-15MD tokamak are considered.</p>","PeriodicalId":728,"journal":{"name":"Physics of Atomic Nuclei","volume":"89 2","pages":"S210 - S217"},"PeriodicalIF":0.5,"publicationDate":"2026-08-30","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"148856724","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
Upgrading the SMOLA Helical Open Trap for Experiments in the Low Coulomb Collisionality Regime 在低库仑碰撞区改进SMOLA螺旋开阱实验
IF 0.5 4区 物理与天体物理
Physics of Atomic Nuclei Pub Date : 2026-08-30 DOI: 10.1134/S106377882614005X
A.V. Sudnikov, A.A. Inzhevatkina, M.S. Tolkachev
{"title":"Upgrading the SMOLA Helical Open Trap for Experiments in the Low Coulomb Collisionality Regime","authors":"A.V. Sudnikov,&nbsp;A.A. Inzhevatkina,&nbsp;M.S. Tolkachev","doi":"10.1134/S106377882614005X","DOIUrl":"10.1134/S106377882614005X","url":null,"abstract":"<p>The SMOLA facility was built at the Institute of Nuclear Physics, Siberian Branch of the Russian Academy of Sciences (INP SB RAS) to experimentally test the concept of helical confinement. This method is a development of the multiple‑bounce confinement scheme. A stream of rotating plasma flows out of the open trap through a magnetic field with helical symmetry that is periodically modulated along the field line. Confinement efficiency depends strongly on the ratio of the ion mean free path to the period of the magnetic‑field modulation. Experiments on the SMOLA facility confirmed improved plasma confinement both in the regime dominated by Coulomb collisions and at reduced collision frequency. Simulation of plasma flow regimes for next‑generation facilities requires a further reduction of the dimensionless Coulomb collisionality. For this purpose a SMOLA* installation is being constructed at INP SB RAS. The paper discusses the new magnetic configuration with mirror‑symmetric helical end‑plugs, an auxiliary ion‑cyclotron resonance (ICR) heating system, methods for generating plasma rotation, and features of the diagnostic suite.</p>","PeriodicalId":728,"journal":{"name":"Physics of Atomic Nuclei","volume":"89 2","pages":"S247 - S255"},"PeriodicalIF":0.5,"publicationDate":"2026-08-30","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"148856725","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
Impact of Peripheral D–Li-Plasma on Electrical Insulating Ceramics in the T-11M Tokamak and Its Thermodynamic Modeling 外围d - li等离子体对T-11M托卡马克中电绝缘陶瓷的影响及其热力学模型
IF 0.5 4区 物理与天体物理
Physics of Atomic Nuclei Pub Date : 2026-08-30 DOI: 10.1134/S1063778826140012
N. T. Dzhigaylo, D. I. Dzhigaylo, V. B. Lazarev, A. N. Scherbak
{"title":"Impact of Peripheral D–Li-Plasma on Electrical Insulating Ceramics in the T-11M Tokamak and Its Thermodynamic Modeling","authors":"N. T. Dzhigaylo,&nbsp;D. I. Dzhigaylo,&nbsp;V. B. Lazarev,&nbsp;A. N. Scherbak","doi":"10.1134/S1063778826140012","DOIUrl":"10.1134/S1063778826140012","url":null,"abstract":"<p>The interaction of peripheral D–Li-plasma with the protective ceramic elements of electrical porcelain, EP (<i>x</i>Al<sub>2</sub>O<sub>3</sub>⋅<i>y</i>SiO<sub>2</sub>), on the limiter of the T-11M tokamak has been studied. The calculated theoretical estimate of the maximum possible lithium capture is 6 mg (5 μg/discharge). The authors’ experimental method, based on the acid leaching with formic acid of the products of the interaction of EP with elemental lithium from the surface of dismantled protective ceramic elements, allowed us to obtain a practical estimate of Li-sorption equal to 3 mg (2.5 μg/discharge) (~50% of the theoretically calculated value) and to conclude that lithium chemisorption by the EP surface is irreversible. Li chemisorption is accompanied by the formation of lithium meta-aluminate (LiAlO<sub>2</sub>) and by the occurrence of the chemical transport reaction (CTR) due to the transfer of reduced aluminum vapors by the plasma flow (practical estimation of Al emission—4 mg (3 μg/discharge)) with the subsequent formation of Li–Al intermetallic compounds (mainly, AlLi<sub>5</sub>), mainly on the surface of the vertical limiter. The assessment of Li removal from the in-chamber circulation due to the formation of intermetallic compounds with Al is 2.5 mg (2 μg/discharge). Thus, the practical assessment of the total irreversible binding (and removal from circulation) of Li is 5.5 mg (4.5 μg/discharge). The thermodynamic model has been created and tested, which is adapted to the high (<i>T</i> &gt;&gt; Θ<sub>D</sub>) temperatures typical of plasma, and which permits the prediction of in-chamber processes in tokamaks. To adapt the model, the authors were the first to substitute polynomial dependences of heat capacities (<i>C</i><sub>p</sub>) on temperature <i>T</i> by their calculations according to Joule–Kopp’s law. The practical value of the work is that the long-term use of the protective ceramic elements promotes the growth of the chemically inert film of γ-LiAlO<sub>2</sub> on the EP surface in situ.</p>","PeriodicalId":728,"journal":{"name":"Physics of Atomic Nuclei","volume":"89 2","pages":"S235 - S246"},"PeriodicalIF":0.5,"publicationDate":"2026-08-30","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"148856727","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 Analysis of Experiments with a Diverter on T‑15MD TOKAMAK T - 15MD托卡马克转流器实验数值分析
IF 0.5 4区 物理与天体物理
Physics of Atomic Nuclei Pub Date : 2026-08-30 DOI: 10.1134/S1063778826140061
D. Yu. Sychugov, D. V. Ryzhakov, V. F. Andreev, A. V. Gorbunov, N. A. Kirneva, D. A. Kislov, V. E. Lukash, G. E. Notkin, A. V. Sushkov, K. N. Tarasyan, D. A. Shelukhin, D. L. Ulasevich, R. R. Khairutdinov
{"title":"Numerical Analysis of Experiments with a Diverter on T‑15MD TOKAMAK","authors":"D. Yu. Sychugov,&nbsp;D. V. Ryzhakov,&nbsp;V. F. Andreev,&nbsp;A. V. Gorbunov,&nbsp;N. A. Kirneva,&nbsp;D. A. Kislov,&nbsp;V. E. Lukash,&nbsp;G. E. Notkin,&nbsp;A. V. Sushkov,&nbsp;K. N. Tarasyan,&nbsp;D. A. Shelukhin,&nbsp;D. L. Ulasevich,&nbsp;R. R. Khairutdinov","doi":"10.1134/S1063778826140061","DOIUrl":"10.1134/S1063778826140061","url":null,"abstract":"<p>Tokamak T‑15MD gradually reaches the design parameters. At the moment, an important task is to obtain stable discharges with diverter configurations and a plasma current of at least 500 kA with a pulse duration at the quasi‑stationary stage of the order of 1 s. To effectively solve this problem, it is necessary to support the experiments with numerical modeling both in the interval between the experimental campaigns and directly during the campaign. The use of numerical analysis of experiments in the 2025 T‑15MD campaign made it possible to optimize plasma discharge scenarios and work out an active feedback system in relation to the vertical and horizontal displacements of the plasma column. Stable discharges were obtained with a diverter and a plasma current of ~500 kA and a duration at the quasi‑stationary stage of the order of 1 s. The paper summarizes the experimental experience and numerical calculations obtained during the spring campaign of 2025 and provides recommendations for obtaining one of the discharge scenarios with a diverter on the T‑15MD tokamak unit.</p>","PeriodicalId":728,"journal":{"name":"Physics of Atomic Nuclei","volume":"89 2","pages":"S195 - S209"},"PeriodicalIF":0.5,"publicationDate":"2026-08-30","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"148853892","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 of Density Profile Peaking during On-Axis ECR-Heating in the T-10 Tokamak T-10托卡马克轴上ecr加热过程中密度曲线峰值分析
IF 0.5 4区 物理与天体物理
Physics of Atomic Nuclei Pub Date : 2026-08-02 DOI: 10.1134/S1063778826130016
V. F. Andreev, A. S. Aseev, A. A. Borshchegovskij, S. E. Lysenko, T. B. Myalton, I. N. Roy, D. S. Sergeev
{"title":"Analysis of Density Profile Peaking during On-Axis ECR-Heating in the T-10 Tokamak","authors":"V. F. Andreev,&nbsp;A. S. Aseev,&nbsp;A. A. Borshchegovskij,&nbsp;S. E. Lysenko,&nbsp;T. B. Myalton,&nbsp;I. N. Roy,&nbsp;D. S. Sergeev","doi":"10.1134/S1063778826130016","DOIUrl":"10.1134/S1063778826130016","url":null,"abstract":"<p>The article presents the results of the analysis of the density profile peaking factor and the inverse density gradient scale length (IDGSL) after switching-on the on-axis electron cyclotron resonance heating (ECRH) in the T-10 tokamak. Two series of experiments with different chord-averaged densities in the ohmic regime before the ECRH switching-on are considered. In each series, the total plasma current was changed from shot to shot at a fixed chord-averaged density and the ECRH power. In this case, the ECRH power was several times higher than the ohmic heating power. It was shown that at the ECRH stage, the density profile peaking factor and the IDGSL become almost the same in each series of experiments. This circumstance indicates the formation of the “stiff” IDGSL with high-power on-axis ECRH. Such property of stiffness for the IDGSL requires its consideration in transport models, when we analyzing the density evolution.</p>","PeriodicalId":728,"journal":{"name":"Physics of Atomic Nuclei","volume":"89 1","pages":"S1 - S15"},"PeriodicalIF":0.5,"publicationDate":"2026-08-02","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"148652186","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
Development of Interfaces for Coupled Calculations for the Analysis of Hydrogen Safety of Tokamak Thermonuclear Facilities 用于托卡马克热核设施氢安全性分析的耦合计算界面的发展
IF 0.5 4区 物理与天体物理
Physics of Atomic Nuclei Pub Date : 2026-08-02 DOI: 10.1134/S1063778826130090
V. Yu. Glotov, N. D. Gembitsky, K. S. Dolganov, A. A. Kanaev, D. Yu. Tomashchik, A. I. Gavrikov
{"title":"Development of Interfaces for Coupled Calculations for the Analysis of Hydrogen Safety of Tokamak Thermonuclear Facilities","authors":"V. Yu. Glotov,&nbsp;N. D. Gembitsky,&nbsp;K. S. Dolganov,&nbsp;A. A. Kanaev,&nbsp;D. Yu. Tomashchik,&nbsp;A. I. Gavrikov","doi":"10.1134/S1063778826130090","DOIUrl":"10.1134/S1063778826130090","url":null,"abstract":"<p>During accidents at tokamak-like thermonuclear facilities (TNF) initiated by the loss of coolant from the cooling system of the first wall or divertor into the vacuum vessel (VV), steam ejected into the VV reacts exothermically with hot metal surfaces and dust. This is accompanied by the formation of hydrogen and produces a risk of explosion of the hydrogen-air mixture when hydrogen escapes outside the VV or when air enters the VV. Safety analysis of TNF requires numerical estimates of the amount and rate of hydrogen production, the composition of the gas atmosphere, and the possibility of hydrogen stratification. For these purposes, IBRAE RAS is developing the integral code PHAETON and the CFD code CABARET-T. The paper presents a description of interfaces for performing coupled calculations using these codes and provides the results of test calculations for a simplified model of the ITER VV.</p>","PeriodicalId":728,"journal":{"name":"Physics of Atomic Nuclei","volume":"89 1","pages":"S83 - S95"},"PeriodicalIF":0.5,"publicationDate":"2026-08-02","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"148652187","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
Experience in Licensing the ITER Fusion Project ITER核聚变项目许可经验
IF 0.5 4区 物理与天体物理
Physics of Atomic Nuclei Pub Date : 2026-08-02 DOI: 10.1134/S1063778826130181
A. A. Shoshin
{"title":"Experience in Licensing the ITER Fusion Project","authors":"A. A. Shoshin","doi":"10.1134/S1063778826130181","DOIUrl":"10.1134/S1063778826130181","url":null,"abstract":"<p>The history of preparing documentation and obtaining the construction license for the ITER fusion reactor in France is reviewed, and the evolution of the amount of tritium permitted in the ITER chamber is shown. The technical and organizational measures applied in the project that provide barriers to the spread of radioactive materials and their influence on the design of reactor systems are examined. Problems with demonstrating the design parameters claimed in the Safety Analysis Report are discussed, in particular the dose levels after reactor shutdown and methods to resolve them. One possible solution that could ease the development and construction of fusion reactors is the creation of regulatory requirements specifically for fusion installations.</p>","PeriodicalId":728,"journal":{"name":"Physics of Atomic Nuclei","volume":"89 1","pages":"S168 - S176"},"PeriodicalIF":0.5,"publicationDate":"2026-08-02","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"148652341","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
0
×
引用
GB/T 7714-2015
复制
MLA
复制
APA
复制
导出至
BibTeX EndNote RefMan NoteFirst NoteExpress
×
提示
您的信息不完整,为了账户安全,请先补充。
现在去补充
×
提示
您因"违规操作"
具体请查看互助需知
我知道了
×
提示
确定
请完成安全验证×
相关产品
×
本文献相关产品
联系我们:info@booksci.cn Book学术提供免费学术资源搜索服务,方便国内外学者检索中英文文献。致力于提供最便捷和优质的服务体验。 Copyright © 2023 布克学术 All rights reserved.
京ICP备2023020795号-1
ghs 京公网安备 11010802042870号
Book学术文献互助
Book学术文献互助群
群 号:604180095
Book学术官方微信
小红书