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1. Numerical investigation of two-dimensional buoyancy-driven eddies in liquid metal magnetohydrodynamic flows in breeding blankets* NSTL国家科技图书文献中心

Suarez, Daniel |  Iraola, Eduardo... -  《Plasma physics and controlled fusion》 - 2025,67(4) - 共15页

摘要: design of tokamak breeding blanket concepts such as the |  the tokamak plasma heats the breeding blanket |  breeding blanket. We conclude by discussing the relevance |  heat and tritium across the blanket. Blankets |  blanket and suggest a possible solution.
关键词: magnetohydrodynamics |  breeding blanket |  tritium transport |  fusion technology

2. Numerical investigation of liquid metal magneto-convection at high Grashof and Hartmann number in a prototypical water-cooled breeding blanket for fusion reactors NSTL国家科技图书文献中心

Simone Siriano |  Alessandro Tassone... -  《International Journal of Heat and Mass Transfer》 - 2025,242(Jun.) - 126840.1~126840.21 - 共21页

摘要:The breeding blanket is one of the critical |  dual tasks of producing tritium through the breeding |  developing the Water-Cooled Lead Lithium (WCIX) breeding |  blanket concept for the European DEMOnstrator fusion |  the blanket. In this study, the WCLL elementary cell
关键词: DEMO |  Magneto-convection |  MHD |  Liquid metal blanket |  PbLi |  WCLL

3. A novel methodology to estimate the optimal cooling of the first wall in a DEMO fusion reactor NSTL国家科技图书文献中心

Jose A. Nogueron |  Ivan Fernandez-Berce...... -  《International Journal of Heat and Mass Transfer》 - 2025,239(Apr.) - 126543.1~126543.16 - 共16页

摘要:The breeding blanket (BB) is the system that |  jeopardize the blanket thermal efficiency and the |  extracts the power and regenerates the fuel in a fusion |  reactor. One of the most promising BB designs is the |  Dual Coolant Lithium Lead (DCLL), which is meant to
关键词: Fusion reactor |  Breeding blanket |  First wall |  Thermal-hydraulics |  DCLL

4. Modified cryogenic distillation for tritium enrichment in the tritium accountancy system of helium cooled ceramic breeding test blanket system NSTL国家科技图书文献中心

Min Chen |  Ming Wen... -  《Separation and Purification Technology》 - 2025,354P8 - 129452~7 - 共7页

摘要: accountancy system(TAS)of Helium-Cooled Ceramic Breeding |  blanket(HCCB-TBS), as an input. The design of this | Given the prevalence of scenarios involving |  low-abundance and large-volume hydrogen isotope |  batch separation in the tritium extraction and
关键词: Quasi-continuous distillation |  Cryogenic batch distillation |  Hydrogen isotopes separation |  Tritium verification experiment

5. Engineering concept of the VNS - a beam-driven tokamak for component testing NSTL国家科技图书文献中心

Bachmann, C. |  Siccinio, M.... -  《Fusion engineering and design》 - 2025,211(Feb.) - 1.1~1.10 - 共10页

摘要: particular that of the tritium breeding blanket (BB | . Approximately 25 m(2) are available for blanket testing | The qualification of in-vessel components for |  a fusion power plant requires a test environment |  with a high flux of 14 MeV neutrons over a
关键词: VNS |  Volumetric neutron source |  Breeding blanket testing |  Demo |  Tokamak |  Remote maintenance |  LITHIUM-LEAD BLANKET |  NEUTRON SOURCE |  DESIGN

6. Optimization of Poloidal Coil System for the Volumetric Neutron Source (VNS) Fusion Reactor NSTL国家科技图书文献中心

L. Giannini |  C. Luongo... -  《IEEE Transactions on Applied Superconductivity》 - 2025,35(5 Pt.2) - 1~6 - 共6页

摘要: to advance Tritium Breeding Blanket (TBM | The Volumetric Neutron Source (VNS) is a |  facility designed to replicate DEMO-relevant conditions | ) technology in fusion reactors. This study focuses on |  optimizing the superconducting Poloidal Field (PF) magnet
关键词: Coils |  Plasmas |  Superconducting magnets |  Toroidal magnetic fields |  Neutrons |  High-temperature superconductors |  Magnetic flux |  Tokamak devices |  Magnetic shielding |  Magnetic separation

7. Physics and technology maturity level required for the K-DEMO design points NSTL国家科技图书文献中心

Kang, J. S. |  Jo, G.... -  《Fusion engineering and design》 - 2025,211(Feb.) - 1.1~1.9 - 共9页

摘要: carbide (WC) shield, a tritium breeding blanket concept | The conceptual design study for the Korean |  fusion demonstration reactor (K-DEMO) has been |  conducted, placing an emphasis on the imperative to reduce |  the reactor's dimension as a means to cost
关键词: Conceptual design |  K-DEMO |  Physics level |  Technology level |  Minimum major radius algorithm |  FUSION POWER-PLANTS |  SYSTEMS CODE

8. A neutronic comparative study of reflectors in radially and axially heterogeneous cores for the ABR-1000 sodium cooled fast reactor NSTL国家科技图书文献中心

Niloy M.H.H. |  Ahmed M.T.... -  《Annals of nuclear energy》 - 2025,211(Feb.) - 1.1~1.18 - 共18页

摘要:, isotope evolution, breeding ratio, sodium void |  the radial model due to axial blanket placement | © 2024 Elsevier LtdIn continuation of previous |  research work, this study investigated the neutronic |  behavior of ABR-1000 using OpenMC simulations with nine
关键词: Axial and radial model |  Breeding ratio |  Fast reactor |  Leakage |  Reflector |  SFR

9. Novel high temperature tritium blanket designs for confined spaces in spherical tokamak fusion reactors NSTL国家科技图书文献中心

Anderton M.D. |  Davis T.P.... -  《Fusion engineering and design》 - 2025,210(Jan.) - 1.1~1.16 - 共16页 - 被引量:1

摘要: breeding materials could involve interesting design |  central column breeding space. In this paper, we present |  side of the breeder blanket in a confined space, such | © 2024Tritium self-sufficiency is one of the |  fundamental challenges for commercially viable
关键词: Central column breeding |  Fusion neutron shielding |  Nuclear fusion |  Tritium breeding |  Tungsten heavy alloys

10. Influence of full-cycle heat treatment on microstructure and mechanical properties of CLF-1 steel NSTL国家科技图书文献中心

Wan J.S. |  Yang G.P.... -  《Fusion engineering and design》 - 2025,211(Feb.) - 1.1~1.8 - 共8页

摘要: requirements of tritium breeding blankets for fusion reactors | © 2024 Elsevier B.V.Based on the manufacturing | , it is valuable to study the microstructure |  evolution and mechanical properties of CLF-1 steel, a |  candidate structural material, during the full-cycle heat
关键词: CLF-1 steel |  Enhanced impact toughness |  Full-cycle heat treatment |  Grain refinement
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