304 results on '"G. Ivan"'
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2. A deep-learning-based grading system (ASAG) for reading comprehension assessment by using aphorisms as open-answer-questions
3. On the Use of Buck ICs in the Implementation of the Non-Inverting Buck-Boost Topology.
4. Modeling dose rate increase from the addition of Uranium-232 for use as a tracer in uranium fuels
5. Exploration of producing Uranium-232 for use as a tracer in uranium fuels
6. Demonstration of RELAP5-3D for transient analysis of a dual coolant lead lithium fusion blanket concept
7. Assessment of BISON capabilities for component-level prediction of tritium transport in fusion and fission applications
8. Implementation of two-phase gas transport into VERA for molten salt reactor analysis
9. A review of thermal hydraulics systems analysis for breeding blanket design and future needs for fusion engineering demonstration facility design and licensing
10. Non-linear coupling in the dark sector as a running vacuum model
11. Evaluation of end of cycle plutonium isotopic content in a VVER-1000 reactor using a 3D full-core simulator
12. Emergent Universe as an interaction in the dark sector
13. Perturbations in some models of tachyonic inflation
14. Power spectra in extended tachyon cosmologies
15. Simulation of a NuScale core design with the CASL VERA code
16. Extended tachyon field using form invariance symmetry
17. Dark matter interacts with variable vacuum energy
18. Benchmark evaluation of zero-power critical parameters for the Temelin VVER nuclear reactor using SERPENT & NESTLE and MCNP
19. Full-core analysis for FeCrAl enhanced accident tolerant fuel in boiling water reactors
20. Form invariance symmetry generates a large set of FRW cosmologies
21. Neutronics Analysis of Shielding Material Alternative to Tungsten Carbide in the FESS-FNSF Facility
22. Nanocrystal Assemblies: Current Advances and Open Problems.
23. History of PWR and BWR Development
24. Activation Analysis for the Inboard Region of FNSF Using SERPENT
25. The electrical double layer for a fully asymmetric electrolyte around a spherical colloid: an integral equation study
26. Tritium Breeding Ratio Evaluation of Solid Breeder Concepts for the FESS-FNSF
27. Radiation Damage Analysis of FNSF Components Using McCad and MCNP
28. Theoretical study: Electronic structure and receptor interaction of four type bis-1,4-dihydropyridine molecules
29. Implementation of the direct [formula omitted] method in the KENO Monte Carlo code
30. Comparative economic analysis of the Integral Molten Salt Reactor and an advanced PWR using the G4-ECONS methodology
31. Activation Analysis for the Inboard Region of FNSF Using SERPENT
32. Creation of problem-dependent Doppler-broadened cross sections in the KENO Monte Carlo code
33. Tritium Breeding Ratio Evaluation of Solid Breeder Concepts for the FESS-FNSF
34. Radiation Damage Analysis of FNSF Components Using McCad and MCNP
35. BWROPT: A multi-cycle BWR fuel cycle optimization code
36. Chronic prostatitis and its detrimental impact on sperm parameters: a systematic review and meta-analysis
37. Exponential Time Differencing Schemes for Fuel Depletion and Transport in Molten Salt Reactors: Theory and Implementation
38. Increasing transcurium production efficiency through directed resonance shielding
39. Approach to Development of a System for Speech Interaction with an Intelligent Robot
40. Exploration of producing Uranium-232 for use as a tracer in uranium fuels
41. Enhanced Accident-Tolerant Fuel Performance and Reliability for Aggressive iPWR/SMR Operation
42. Neutronics modeling of the High Flux Isotope Reactor using COMSOL
43. Gen Z and TV: An Analysis of Traditional Advertising Medium and Perception
44. The Seven Steps to Critical Thinking: A Practical Application of Critical Thinking Skills.
45. Online Higher-Order Error Correction of Nonlinear Diffusion Generalized Perturbation Theory Using Neural Networks.
46. Validation of a Monte Carlo based depletion methodology via High Flux Isotope Reactor HEU post-irradiation examination measurements
47. Exponential Time Differencing Schemes for Fuel Depletion and Transport in Molten Salt Reactors: Theory and Implementation
48. Full-core analysis for FeCrAl enhanced accident tolerant fuel in boiling water reactors
49. Modeling dose rate increase from the addition of Uranium-232 for use as a tracer in uranium fuels
50. Predicting neutron diffusion eigenvalues with a query-based adaptive neural architecture.
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