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- Data for: Hydrogen isotopes distribution modeling by "FC-FNS" code in fuel systems of fusion neutron source DEMO-FNSFusion neutron source is promising for research, testing of structural materials of future fission and fusion reactors, utilization of nuclear waste, fission fuel production and control of subcritical nuclear systems. Tokamak is one of the most promising systems for the creation of fusion neutron source with a power output exceeding 10 MW. The maintenance of plasma requires the injection of a fuel mixture of hydrogen isotopes (deuterium and tritium) into the vacuum vessel as well as fuel pumping and fuel processing. To simulate hydrogen isotope fluxes in fuel systems of fusion neutron source a fuel cycle model “FC-FNS” has been developed. In the paper the modification of model “FC-FNS” are present as well as the results of calculations of tritium fluxes for fusion neutron source DEMO-FNS for different T/D ratio in plasma are presented.
- Data for: Anisotropy of the Magnetic field of the TF coils in CFETRIn the CFETR magnetic system, HTS composite conductors containing stacked HTS tapes are considered to manufacture TF coils.The critical current is related to the direction of the magnetic field in HTS tapes. The anisotropy of magnetic field of the TF coils in three normal conditions and two fault condition are studied by the finite element method.
- Data for: Analysis of Fusion Propulsion System for Earth-to-Mars MissionIn this study, analysis has been conducted to investigate the technical requirements of the fusion propulsion system for the Earth-to-Mars mission. An analytical model based on Williams’s assumption was adopted and solved by using the MATLAB code. The original MATLAB code is shown in the attachment
- Data for: Concept design of the control method for the NBI acceleration grid power-conversion system of the CFETRthe steady pweformance of proposed AGPS
- Data for: Diffusion of hydrogen in China Reduced Activation Ferritic-martensitic steels at low temperaturesFig.2. The microstructure by OM and TEM of CLAM (a, c) and CLF-1 (b, d) steels Fig.3. The surface morphology of CLAM (a, b) and CLF-1 (c, d) steels coated with Pd membranes Fig.4. (a) Cross section microstructure of CLAM steel coated with Pd; (b) Cross section microstructure of CLF-1 steel coated with Pd membrane; (c) Element mapping of selected field in (a); (d) Element mapping of selected field in (b); (e) Element line scanning of A to B in (a); (f) Element line scanning of C to D in (b). Fig.5. Phase structure of CLAM and CLF-1 steels before and after coated with Pd membrane Fig.6. Typical hydrogen permeation curve as function of time for CLAM steel coated with Pd membrane at 303 K Fig.7. Hydrogen permeability through the CLAM-Pd and CLF-1-Pd membranes versus the inverse temperature Fig.8. SEM images of CLAM-Pd (a) and CLF-1-Pd (b) after hydrogen permeation
- Data for: Development of Superconducting Joint for TOKAMAK Feeder BusbarWe write a Fortran code to calculate AC losses of two types of joints, however the code is needed to furture improve, thus data of AC losses calculation is not uploaded.
- Data for: A Study on irradiated welding joints in ITER materials and its effects on FMECA analysis of ITER components.Excel sheet contained values of flux the figures show the coordinates of the weld which is the x,y z coordinates from CAD model configuration. This is transposed with ParaView configuration model so the neutron flux ar various energy levels are obtained., how we converted into DPA(displacement per atom) based on plant operation condition. Reports and literature made on various irritation effects on welding clear understanding have to be made on the irradiation effect on weldment and base metal, types of material used and types of welding used for this particular project. Various graphs used to correlate welding defects to reliability.the proof of linear correlation is evident from the literature survey. The book and literature considered have been uploaded. A detailed study has been carried out to understand the ITER(International thermonuclear experimental reactor) RAMI(Reliability, Availability,Maintainability, and inspectability) analysis and FMECA(Failure mode effect and criticality analysis) have been studied and detailed reports have been up loaded.data sets of mean time to failure based on various types of material and various types of welding have have been uploaded.
- Data for: Research Progress of HL-2M Distributed Timing SystemReferring to the design scheme of ITER (International Thermonuclear Experimental Reactor) Time Communication Network (TCN), combined with the actual situation of HL-2M, the distributed timing system based on IEEE 1588-2008 (Precision Time Protocol) has been studied, which can realize multiple triggering functions including single pulse, uniform pulse train, non-uniform pulse train and other arbitrary pulse types to meet the actual needs and improves the clock synchronization and triggering accuracy of HL-2M timing system from microsecond level to sub-microsecond level, and ultimately better than 100 nanoseconds.
- Data for: Simultaneous detection of neoclassical tearing mode and electron cyclotron current drive locations using electron cyclotron emission in DIII-DData shown in figures 1-3.
- Data for: Electromagnetic Analysis for Vacuum Vessel of CFQS Quasi-axisymmetric StellaratorFinite element analysis data for performing eddy current analysis in the CFQS
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