Keywords: چرخه سوخت; Fuel cycle; Metal hydride; Tritium; Storage; Depleted uranium;
مقالات ISI چرخه سوخت (ترجمه نشده)
مقالات زیر هنوز به فارسی ترجمه نشده اند.
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در صورتی که به ترجمه آماده هر یک از مقالات زیر نیاز داشته باشید، می توانید سفارش دهید تا مترجمان با تجربه این مجموعه در اسرع وقت آن را برای شما ترجمه نمایند.
Keywords: چرخه سوخت; Molten salt reactor; Fuel cycle; Enriched uranium; Thorium;
Keywords: چرخه سوخت; Minor actinides transmutation; Heterogeneous transmutation; Fuel cycle; Homogeneous transmutation; Curium fuel cycle;
Keywords: چرخه سوخت; Molten salt reactor; Fuel cycle; Spectral shift; Zirconium hydride;
Keywords: چرخه سوخت; Tritium; TAS; Fuel cycle; Fusion reactor; System dynamics;
Keywords: چرخه سوخت; Fluoride salt; FHRs; Molten salt reactors; Fuel cycle; Safety analysis; Advanced reactors;
Keywords: چرخه سوخت; Nuclear spent fuel reprocessing; Fast reactors; Plutonium; Uranium; CORAL; PUREX; THOREX; Solvent extraction; Indian nuclear power program; Fuel cycle;
Keywords: چرخه سوخت; Pressurised heavy water reactor; Prototype fast breeder reactor; Fuel cycle; Accelerator driven sub-critical system; Advanced heavy water reactor; Pressurised water reactor;
Keywords: چرخه سوخت; Bus and rail emissions; Greenhouse gases; Comparative assessment; Environmental impact; Fuel cycle; Vehicle life cycle; Australia;
Keywords: چرخه سوخت; Nuclear energy; Fast reactor; Breeder; Neutronic performance; Fuel cycle; Metal fuel; Technology development; Sodium facilities; Safety studies; Material development; FBR; Fast Breeder Reactor; FBTR; Fast Breeder Test Reactor; PFBR; Prototype Fast Breeder
Keywords: چرخه سوخت; Fast reactor; Thorium; Radiotoxicity; Fuel cycle; Decay heat; Transmutation;
Keywords: چرخه سوخت; TMC; Nuclear data uncertainty; Lead isotopes; Safety parameters; ELECTRA; Fuel cycle;
Keywords: چرخه سوخت; Fast reactor; Radiotoxicity; Transmutation; Fuel cycle; Decay heat; Spent nuclear fuel; CORAIL; LWR fuel assembly containing U-TRU fuel pins and LEU pins; EPR; European pressurized reactor; LEU; low enriched uranium; LWR; light water reactor; MA; minor ac
Keywords: چرخه سوخت; Greenhouse gases; Cumulative radiative forcing; Fossil fuels; Higher heating value; Fuel cycle;
Keywords: چرخه سوخت; Composite fuel; Fuel cycle; Zr matrix28.41.Bm; 81.05.Zx; 81.05.Rm; 81.30.Bx
Keywords: چرخه سوخت; Fuel cycle; Advanced reactor; Transmutation; Energy cost; Cost uncertainties
Keywords: چرخه سوخت; Fissile Assay; Slowing Down; Neutron Source; Fuel Cycle; Nuclear Material Utilization; Resolution; Radiation Measurement
Keywords: چرخه سوخت; Fuel cycle; Pyrochemical processing; Modeling; Electrorefining
Keywords: چرخه سوخت; Fast Reactor; Thorium; Fuel cycle; Safety; Fuel handling;
Keywords: چرخه سوخت; Nuclear power industry; Fuel cycle; Optimization; Natural uranium; Spent fuel; Cost;
Keywords: چرخه سوخت; Fuel cycle; Simulation; Modeling; Code; Scenario; Thermal reactor; Fast reactor; Nuclide composition; Recycling; Plutonium equivalenting; Store; Minor actinides
Keywords: چرخه سوخت; REMIX fuel; Fuel cycle; VVER-1000 light-water reactor; Uranium; Plutonium; Uranium recycling; Plutonium recycling; Isotopic composition; Equivalent dose rate; Spent nuclear fuel
Hypothetical daily operation model of fuel cycle in tritium plant
Keywords: چرخه سوخت; Scheduling; Fuel cycle; Optimal design; MILP; One-day operation;
Different techniques for reducing DLOFC fuel temperatures in a PBMR-DPP-400 core
Keywords: چرخه سوخت; Fuel cycle; DLOFC; Pebble bed reactor; Power density profile; Neutron poison; Thorium;
A scenario analysis of once-through thorium fuel cycles with pressure tube HWRs in Canada
Keywords: چرخه سوخت; Thorium; Heavy water reactor; Fuel Cycle; Scenario; Used Fuel; Once Through;
The use of representativity theory in the depletion calculations of SFR blankets
Keywords: چرخه سوخت; Depletion calculation; SFR; Representativity factor; DARWIN; PHENIX; Sensitivities; Fuel cycle; Uncertainty reduction; Transposition;
E-pO2â diagram for rare earth elements in molten salt
Keywords: چرخه سوخت; E-pO2â Diagram; molten salt; pyroprocessing; fuel cycle; rare earths;
Molten salt reactor neutronics and fuel cycle modeling and simulation with SCALE
Keywords: چرخه سوخت; Molten salt reactors; Fuel cycle; Depletion; Salt treatment; Salt separations;
Concept of DT fuel cycle for a fusion neutron source DEMO-FNS
Keywords: چرخه سوخت; Fusion neutron source; Tokamak; Hybrid reactor; DEMO; Fuel cycle; Tritium; Calculation code;
New burnable absorber for long-cycle low boron operation of PWRs
Keywords: چرخه سوخت; 157Gd; 167Er; Burnable absorber; Fuel cycle; PWR fuel assembly; PWR type reactor;
Consequences of the technology survey and gap analysis on the EU DEMO R&D programme in tritium, matter injection and vacuum
Keywords: چرخه سوخت; Fuel cycle; DEMO; Vacuum; Tritium; Pellet injection;
A multi-dimensional well-to-wheels analysis of passenger vehicles in different regions: Primary energy consumption, CO2 emissions, and economic cost
Keywords: چرخه سوخت; Well-to-wheels; Fuel cycle; Petroleum use; Sustainable mobility; Exergy analysis; Passenger vehicles CO2 emissions;
Minimizing MTR reactor uranium load with the use of MOX fuel by employing ORIGEN-S and MCNP4C codes
Keywords: چرخه سوخت; MTR reactor; MOX fuel; Fuel cycle; ORIGEN-S code; MCNP4C code; PFCOM program;
Startup and burnup strategy for Th-U/U-Pu fuel cycles in an EM2 reactor
Keywords: چرخه سوخت; EM2; Fuel cycle; Breeding; Radio-toxicity;
MOX fuel enrichment prediction in PWR using polynomial models
Keywords: چرخه سوخت; PWR MOX; Nuclear fuel fabrication; Model; Fuel cycle;
Economics analysis of fuel cycle cost of fusion–fission hybrid reactors based on different fuel cycle strategies
Keywords: چرخه سوخت; Fusion–Fission hybrid reactor; Economics; Fuel cycle; Fuel cycle cost
SARCS cross section library generator: Part two: Fast and quasi transients evaluations
Keywords: چرخه سوخت; PARCS; Depleted cross section; Fuel cycle; Rod ejection; SARCS
An investigation of the thermal stability of NdxYyZr1âxâyO2âδ inert matrix fuel materials
Keywords: چرخه سوخت; X-ray absorption spectroscopy; Nuclear fuel; Yttria-stabilized zirconia; Structural characterization; Inert matrix; Fuel cycle;
PROPAGATION OF NUCLEAR DATA UNCERTAINTIES FOR PWR CORE ANALYSIS
Keywords: چرخه سوخت; Uncertainty Propagation; Nuclear Data; Fuel Cycle; Design and Acceptance Criteria; PWR
The closed thorium-transuranic fuel cycle in reduced-moderation PWRs and BWRs
Keywords: چرخه سوخت; Thorium; Reduced-moderation; PWR; BWR; Transuranic; Fuel cycle;
The results of the irradiation experiment MARIOS on americium transmutation
Keywords: چرخه سوخت; Fuel experiment; Transmutation; Minor actinide; MABB; Fuel cycle; Americium;
The Direct Internal Recycling concept to simplify the fuel cycle of a fusion power plant
Keywords: چرخه سوخت; Vacuum; Fuel cycle; Tritium; Inventory; Dir; Demo
Tritium management and safety issues in ITER and DEMO breeding blankets
Keywords: چرخه سوخت; Fuel cycle; Tritium management; Breeder blanket; Fuel cycle; Tritium accountancy; Tritium safety; Tritium permeation; Tritium inventory
A SCENARIO STUDY ON MIXING STRATEGIES OF FAST REACTOR WITH LOW AND HIGH CONVERSION RATIOS
Keywords: چرخه سوخت; Conversion Ratio; Fast Reactor; Spent Fuel; Transuranic Element; Fuel Cycle; Long-term Heat Load
Inactive commissioning of a micro channel catalytic reactor for highly tritiated water production in the CAPER facility of TLK
Keywords: چرخه سوخت; Fuel cycle; Highly trititated water; Micro-reactor
Development of a technical scale PERMCAT reactor for processing of highly tritiated water
Keywords: چرخه سوخت; Fuel cycle; Tritiated water; Catalytic membrane reactor; Palladium membrane
Design and analysis on tritium system of multi-functional experimental fusion–fission hybrid reactor (FDS-MFX)
Keywords: چرخه سوخت; Tritium system; Fusion–fission hybrid reactor; Fuel cycle
Tritium issues to be solved for establishment of a fusion reactor
Keywords: چرخه سوخت; Tritium; Inventory; Fuel cycle; Safety; Economy; Fusion reactor
Overview of R&D at TLK for process and analytical issues on tritium management in breeder blankets of ITER and DEMO
Keywords: چرخه سوخت; Breeder blanket; Fuel cycle; Pd and zeolite membrane; Catalytic membrane reactor; Raman and BIXS spectroscopy
A novel method for rapid comparative quantitative analysis of nuclear fuel cycles
Keywords: چرخه سوخت; Fuel cycle; Optimisation; Reactor model; Fast reactors; Thermal reactors;