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GeneTech 知识引擎共收录 1018 篇相关科研实体，横跨 26 个垂直领域。数据来自 OpenAlex、arXiv、Crossref、PubMed、Europe PMC 等公开学术源，全部可溯源到原文。

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代表性文献（按质量分排序，前 60 条）

• Rab10 Promotes Atlastin-Mediated Endoplasmic Reticulum Membrane Fusion.
  2026 · 生命科学 · Intracellular membrane fusion typically involves two distinct classes of GTPases. Dynamin-like GTPases mediate homotypic fusion between organelles, such as mitochondria and the endoplasmic reticulum (ER), while Rab GTPas…
• Metal foil infrared bolometer for measurement of toroidal radiation asymmetry during plasma disruption mitigation experiments in ADITYA-U tokamak.
  2026 · 核能 · A metal foil infrared (IR) bolometer has been developed and installed at multiple toroidal locations in the ADITYA-U tokamak to study toroidal radiation asymmetry during plasma disruption mitigation scenarios. The diagno…
• Simulation and Comparative Analysis of Advanced Scenarios for High- and Low-Temperature Superconducting Tokamak Using METIS Code
  2026 · 核能 · The development of steady-state advanced operation modes with high fusion gain (Q) is a primary objective of magnetic confinement fusion research. The advancement of high-temperature superconducting (HTS) magnet technolo…
• Axisymmetric Eigenmodes Excited by Alpha Particle Energy Gradients in JET D-T Plasmas.
  2026 · 核能 · Axisymmetric Alfvén eigenmodes have been observed at the plasma edge in deuterium-tritium (D-T) tokamak plasmas externally heated only by neutral beam injection in JET. The modes were detected only in D-T plasmas, n…
• Utilizing the deuterium-tritium fusion resonance to diagnose thermal runaway in igniting plasmas.
  2026 · 核能 · For high-efficiency inertial confinement fusion implosions, it is predicted that a burning hot spot will successfully encompass all surrounding fuel and then transition into a thermal runaway where the internal energy in…
• Comparison of Turbulence and Transport Characteristics between Global Flux-driven and Gradient-driven Gyrofluid Simulations in Tokamak Plasmas
  2025 · 核能 · Abstract We perform global nonlinear simulations of ion temperature gradient (ITG) turbulence in a concentric circular tokamak geometry with the gyrofluid code \textsc{GF2-BOUT++} and compare the dynamics in flux-driven …
• Neutral particle analyzer for plasma diagnostics on tokamak ST40.
  2025 · 核能 · A neutral particle analyzer was designed and implemented for plasma diagnostics on the spherical tokamak ST40. The diagnostic aims to measure both the bulk ion temperature (0.5–10 keV) and the energy distribution of fast…
• Comprehensive understanding of the Greenwald density limit and disruption in tokamak fusion plasmas
  2025 · 核能 · Abstract The output power of a fusion reactor scales with the square of the plasma density. Achieving high economic performance thus necessitates operation at high plasma density. However, existing devices rarely sustain…
• Stable Small Plasmas at the Density Limit in the W7-X Stellarator.
  2025 · 核能 · Experiments in the Wendelstein 7-X (W7-X) stellarator with plasma density beyond the established density limit in stellarators [Scalings of energy confinement and density limit in stellarator/heliotron devices, Nucl. Fus…
• Ion-beam plasma interaction in ion fast ignition nuclear fusion scheme: A systematic study of the hot-spot properties and gains.
  2025 · 核能 · Ion fast ignition by laser-driven ion beams is an interesting approach within the inertial confinement fusion scheme to achieve nuclear fusion. In the ion fast ignition, once the precompression of the target is finished,…
• Catalytic Oxidation-like Nuclear Nano-Fusion; Fractal Involving of Room Temperature Magnetically Induced μ-Catalyzed Fusion
  2025 · 核能 · The nuclear fusion reaction can be catalyzed in a suitable fusion fuel by muons (heavy electrons).“For the fractal relations, ranging from DNA knots to solar neutrino flux signals”, ever derived of scale-invariant proper…
• Validation of an integrated modeling framework for investigating 3D plasma responses in tokamak plasmas
  2026 · 核能 · Abstract As contemporary experimental tokamaks are pushed toward reactor-relevant operation, they provide essential testbeds for demonstrating and exploring edge-localized mode (ELM) control strategies for deployment in …
• Gkeyll TCV Miller Geometry Parameter Scan Dataset
  2026 · 核能 · This dataset provides results from a systematic three-parameter scan of gyrokinetic turbulence simulations for TCV tokamak-like plasma conditions, covering 256 Gkeyll simulations that explore the effects of plasma shapin…
• Gkeyll TCV Miller Geometry Parameter Scan Dataset
  2026 · 核能 · This dataset provides results from a systematic three-parameter scan of gyrokinetic turbulence simulations for TCV tokamak-like plasma conditions, covering 256 Gkeyll simulations that explore the effects of plasma shapin…
• PREFER (Polarization for Fusion Experiments and Reactors: what is happening with regard to fusion with polarized fuel?
  2026 · 核能 · The PREFER (Polarization REsearch for Fusion Experiments and Reactors) collaboration aimsto address the know-hows in different fields and techniques to the challenging bet on energyproduction by nuclear fusion with polar…
• Prestress load distribution modeling for containment digital twin model
  2025 · 数字孪生 · This paper examines the prestress load distribution in the ducts of the prestressing tendons of a VVER-type nuclear reactor containment. It introduces a method for distributing the simplified linear load from the prestre…
• A simple, accurate model for detachment access
  2025 · 核能 · Abstract In next-step fusion tokamaks such as SPARC and ITER, achieving high levels of scrape-off-layer power dissipation will be essential to protect the divertor while maintaining good core plasma performance. The Leng…
• Fast ion confinement in quasi-axisymmetric stellarator equilibria
  2025 · 核能 · Abstract This report presents an initial analysis of the fast ion confinement and losses within quasi-axisymmetric stellarator equilibria in consideration by Thea Energy. The equilibria have not yet been explicitly optim…
• Confinement of fusion alpha-particles and Alfven eigenmode stability in STEP
  2025 · 核能 · Abstract The Spherical Tokamak for Energy Production (STEP) programme is focused on designing and building a prototype fusion power plant that will generate approximately 1.5–1.8 GW of deuterium-tritium fusion power. To …
• Large radiation back-flux from Monte Carlo simulations of fusion neutron–material interactions
  2025 · 核能 · Abstract Fusion power reactors will generate intense neutron fluxes into plasma-facing and structural materials (SMs). Radiation back-fluxes, generated from neutron–material interactions under these fluxes, can dramatica…
• SICAS, a new integrated divertor-SOL-pedestal-core framework for self-consistent modeling of ion and impurity transport in fusion devices
  2025 · 核能 · Abstract We present a new framework for core-edge integration studies named SICAS (SOLPS-ITER coupled to ASTRA-STRAHL) which enables high fidelity simulations of the core, edge, and divertor regions encompassing the tran…
• Axial confinement in the Novatron mirror machine
  2025 · 核能 · Abstract The Novatron magnetic mirror fusion reactor concept features significant advantages. These include stability against MHD interchange and kinetic drift cyclotron loss cone modes, axisymmetry, and minimized radial…
• Trapped electron mode in a quasi-isodynamic stellarator
  2025 · 核能 · Abstract Global gyrokinetic simulations find a strongly unstable trapped electron mode excited by a density gradient in a quasi-isodynamic stellarator. The eigenmode structure localizes on the inner side of the torus wit…
• Accuracy assessment of the calorimetric system for measurement of ITER’s fusion energy output
  2025 · 核能 · Abstract The calorimetric system of ITER is designed to measure the time-integrated fusion power output of the tokamak by analysing thermal flows and calculating the energy balance. While too slow for real-time control, …
• Coil optimization methods for a planar coil stellarator
  2025 · 核能 · Abstract The planar coil stellarator design is a novel approach to producing the confining magnetic field of a stellarator plasma. The work presented here details the optimization of the two types of planar coils that ar…
• Assessing the risk of proliferation via fissile breeding in ARC-class fusion power plants
  2025 · 核能 · Abstract Construction of a nuclear weapon requires access to kilogram-scale quantities of fissile material, which can be bred from fertile material like U-238 and Th-232 via neutron capture. Future fusion power plants, w…
• Impact of trapping on tritium self-sufficiency and tritium inventories in fusion power plant fuel cycles
  2025 · 核能 · Abstract The dynamic analysis of fusion power plant (FPP) fuel cycles highlights the challenge of achieving tritium self-sufficiency in future FPPs. While state-of-the-art fuel cycle models offer valuable insights into t…
• Bremsstrahlung radiation power in non-Maxwellian plasmas
  2025 · 核能 · Abstract In plasmas, bremsstrahlung includes electron–ion (e–i) bremsstrahlung and electron–electron (e–e) bremsstrahlung. Bremsstrahlung radiation power loss is one of the most significant losses in fusion plasmas, whic…
• Physics feasibility study of a collective Thomson scattering diagnostic for SPARC
  2025 · 核能 · Abstract The SPARC tokamak is a compact high-field device that will operate at high plasma density with the aim to demonstrate net fusion energy. The experimentally unexplored plasma conditions in SPARC will require a ca…
• On the possibility of reducing the size of a fusion reactor by increasing the plasma density
  2025 · 核能 · Abstract A zero-dimensional analysis based on available scaling laws for the global energy confinement time of tokamak plasmas is presented, in order to consistently compute the fusion power as a function of the plasma d…
• [MGA::NUTM1 fused sarcoma in children: report of a case].
  2025 · 核能 · NUTM1重排肉瘤是一种在分子水平上与NUT癌不同的实体肿瘤，其易位&#x4…
• OpenSTEP: public data release of the STEP Prototype Powerplant scenario SPP-001
  2025 · 核能 · This dataset contains a curated set of results from key physics simulations performed at UKAEA for the STEP Prototype Power Plant, version 1 (SPP-001). It includes the coilset, equilibrium, and kinetic profiles of the ST…
• Multi-functional code for hydrogen isotopes transport analyses: verification & validation against fusion-relevant applications
  2025 · 核能 · Abstract The management of hydrogen isotopes within a fusion reactor remains a key design issue, with many constraints concerning tritium. The fusion power plant should be self-sufficient with respect to its fuel, while …
• Amorphization and siliconization of silicon carbide as a first wall material
  2025 · 核能 · Abstract The understanding and prediction of silicon carbide (SiC) material evolution exposed to SOL plasma conditions is of prime interest because SiC represents a promising main chamber wall plasma-facing material for …
• Determining the validity of tokamak perturbed equilibrium modeling using nonlinear equilibria
  2025 · 核能 · Abstract The prediction of perturbed equilibrium models for tokamaks with small non-axisymmetric fields is strongly dependent on which reference frame for axisymmetry is assumed. This assumption directly affects the appl…
• Experimental demonstration of real-time electron temperature profile control in DIII-D
  2025 · 核能 · Abstract Future tokamak reactor operation will require the ability to maintain a given plasma scenario for extended periods of time. This will necessitate the capability to react to changes in the plasma state and return…
• A robust data-driven approach for modeling turbulent transport
  2025 · 核能 · Abstract Getting fast and reliable predictions of turbulent transport properties is an important challenge in magnetic fusion. Previous research (Heinonen and Diamond 2020 Phys. Rev. E 101 061201) proposed a data-driven …
• Predictive turbulence-driven flux model of scrape-off layer widths across confinement regimes in tokamaks
  2025 · 核能 · Abstract Reliable scrape-off layer (SOL) profile decay lengths predictions are needed to design and operate future tokamaks. The present manuscript describes a new model based on turbulent transport that is able to predi…
• Efficient calculation of self magnetic field, self-force, and self-inductance for electromagnetic coils with rectangular cross-section
  2025 · 核能 · Abstract For designing high-field electromagnets, the Lorentz force on coils needs to be computed in order to design suitable support structures, and the inductance should be computed to evaluate the stored energy and dy…
• Heating and current drive in STEP: why neutral beam injection is not desirable
  2025 · 核能 · Abstract Spherical Tokamak for Energy Production (STEP) is the UK’s prototype fusion power plant programme aiming to demonstrate net electrical output from a spherical tokamak. The plasma scenarios require a completely n…
• Effects of size of an oxide layer on the surface properties of lithium irradiated by deuterium plasma
  2025 · 核能 · Abstract We investigate how growth of an oxide film will influence the deuterium recycling properties of Li on plasma facing surfaces. Lithium films on the walls or plasma-facing material surfaces of a fusion vacuum vess…
• Integrated modeling of SPARC H-mode scenarios: exploration of the impact of modeling assumptions on predicted performance
  2025 · 核能 · Abstract In this paper an extensive database of SPARC H-modes confinement predictions has been provided, to assess its variability with respect to few input assumptions. The simulations have been performed within the AST…
• A model for Alfvén-eigenmode-induced transport of fast ions in stellarators
  2025 · 核能 · Abstract A novel model for Alfvén-eigenmode-induced transport of fast ions in stellarators is introduced. A variety of reduced transport models exists for tokamaks, but nothing comparable currently exists for stellarator…
• Parametric analysis of the TWA launcher for WEST using minority heating ICRH technique
  2025 · 核能 · Abstract This paper presents a parametric analysis of the conceptual design of the Travelling Wave Array (TWA) launcher for the WEST tokamak. Simulations were made using the EVE code to identify the optimal wavenumbers a…
• Upper limit of fusion reactivity in laser-driven <i>p</i>+¹¹B reaction
  2025 · 核能 · Abstract We explore the averaged fusion reactivity of the p + 11 B reaction in tabletop laser experiments using a plasma expansion model. We investigate the energy distribution of proton beams accelerated by lasers as a …
• High confinement regimes on SPARC: operational conditions for access and avoidance
  2025 · 核能 · Abstract This work examines H-mode and I-mode access on the SPARC tokamak, combining new simulations of core L-mode power balance with the best empirical scalings available for L–H and L–I thresholds. Scalings applied to…
• Development and validation of non-axisymmetric heat flux simulations with 3D fields using the HEAT code
  2025 · 核能 · Abstract A new comprehensive module to simulate heat fluxes from three-dimensional (3D) magnetic fields has been implemented in the HEAT code. Especially compact tokamaks like SPARC require tools to predict and manage la…
• Study of radial field dependent flows in inboard limited Aditya-U plasmas using EMC3-Eirene simulations
  2025 · 核能 · Abstract The intrinsically generated plasma rotation in magnetically confined tokamak plasmas has implications for a number of edge and core phenomena. In recent Aditya-U tokamak circular plasma discharges with plasma cu…
• An approach to create soft X-ray virtual arrays in tomography reconstruction considering non-rigid rotation of the plasma column in the tokamak
  2024 · 核能 · Abstract A method was proposed to create Soft X-ray virtual arrays in tomography to study the rigid versus non-rigid rotation of the plasma column in a tokamak. The coordinate reference of the tokamak was transformed int…
• The infrared thermography system on the MAST-U tokamak.
  2024 · 核能 · Power loading from plasma in the scrape-off layer limits the lifetime of plasma-facing components in tokamak-based power plants. The Mega Ampere Spherical Tokamak Upgrade [W. Morris et al., IEEE Trans. Plasma Sci. 46(5),…
• Advances, Challenges, and Future Perspectives of Microwave Reflectometry for Plasma Position and Shape Control on Future Nuclear Fusion Devices.
  2023 · 核能 · Providing energy from fusion and finding ways to scale up the fusion process to commercial proportions in an efficient, economical, and environmentally benign way is one of the grand challenges for engineering. Controlli…
• Modelling of blast furnace ironmaking process based on digital twin
  2024 · 数字孪生 · Abstract The blast furnace ironmaking process is a crucial step in the steel industry. Effectively modelling the blast furnaces is significant in ensuring smooth operation and accelerating the digitalisation transformati…
• Effects of Injected Current Streams on MHD Equilibrium Reconstruction of Local Helicity Injection Plasmas in a Spherical Tokamak
  2024 · 核能 · Abstract Open field line currents are intrinsic to DC helicity injection plasma startup and pose a challenge for inferring the plasma equilibrium with standard reconstruction analysis. Local helicity injection (LHI) is a…
• Corrigendum: Tritium burn efficiency in deuterium–tritium magnetic fusion (2023 Nucl. Fusion 63 126019)
  2024 · 核能 · Abstract The controlling parameters regarding tritium burn efficiency (TBE) are derived from first principles and shown to depend fundamentally on the permitted He gas fraction in the divertor and effective pumping speed…
• Numerical modelling of sawteeth and sawtooth-free regime
  2024 · 核能 · Abstract To better understand the sawteeth physics and the sawtooth-free regime associated with the hybrid scenario in tokamak experiments, numerical calculations up to quasi-steady state have been carried out for realis…
• Simultaneous enhancement of tritium burn efficiency and fusion power with low-tritium spin-polarized fuel
  2024 · 核能 · Abstract This study demonstrates that using spin-polarized deuterium-tritium (D-T) fuel with more deuterium than tritium can increase tritium burn efficiency (TBE) by at least an order of magnitude without compromising f…
• Resistive wall tearing mode disruptions
  2024 · 核能 · Abstract This paper deals with resistive wall tearing mode (RWTM) disruptions. RWTMs are closely related to resistive wall modes. RWTMs are tearing modes whose linear and nonlinear behavior is strongly dependent on the r…
• Analysis and design of fast flow liquid Li divertor for fusion nuclear science facility (FNSF) using coupled plasma boundary and LM MHD/heat transfer codes ^*
  2024 · 核能 · Abstract The SOLPS-ITER code is utilized to analyze the boundary plasma associated with a fast-flow lithium (Li) divertor configuration in the fusion nuclear science facility (FNSF) tokamak and identify operational regim…
• Summary of presentations reported in EXperiment confinement (EX-C) session at the 29th IAEA fusion energy conference
  2024 · 核能 · Abstract This is a summary paper of the research activities presented in the magnetic fusion EXperiment Confinement (EX-C) session at the 29th International Atomic Energy Agency (IAEA) Fusion Energy Conference (FEC 2023)…
• Quasilinear theory and modelling of gyrokinetic turbulent transport in tokamaks
  2024 · 核能 · Abstract The theory, development, and validation of reduced quasilinear models of gyrokinetic turbulent transport in the closed flux surface core of tokamaks is reviewed. In combination with neoclassical collisional tran…

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