34 results on '"Maldonado, G. Ivan"'
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2. Modeling dose rate increase from the addition of Uranium-232 for use as a tracer in uranium fuels
3. Exploration of producing Uranium-232 for use as a tracer in uranium fuels
4. Demonstration of RELAP5-3D for transient analysis of a dual coolant lead lithium fusion blanket concept
5. Assessment of BISON capabilities for component-level prediction of tritium transport in fusion and fission applications
6. Implementation of two-phase gas transport into VERA for molten salt reactor analysis
7. A review of thermal hydraulics systems analysis for breeding blanket design and future needs for fusion engineering demonstration facility design and licensing
8. Evaluation of end of cycle plutonium isotopic content in a VVER-1000 reactor using a 3D full-core simulator
9. Simulation of a NuScale core design with the CASL VERA code
10. Benchmark evaluation of zero-power critical parameters for the Temelin VVER nuclear reactor using SERPENT & NESTLE and MCNP
11. Full-core analysis for FeCrAl enhanced accident tolerant fuel in boiling water reactors
12. Neutronics Analysis of Shielding Material Alternative to Tungsten Carbide in the FESS-FNSF Facility
13. History of PWR and BWR Development
14. Implementation of the direct [formula omitted] method in the KENO Monte Carlo code
15. Comparative economic analysis of the Integral Molten Salt Reactor and an advanced PWR using the G4-ECONS methodology
16. Activation Analysis for the Inboard Region of FNSF Using SERPENT
17. Creation of problem-dependent Doppler-broadened cross sections in the KENO Monte Carlo code
18. Tritium Breeding Ratio Evaluation of Solid Breeder Concepts for the FESS-FNSF
19. Radiation Damage Analysis of FNSF Components Using McCad and MCNP
20. BWROPT: A multi-cycle BWR fuel cycle optimization code
21. Enhanced Accident-Tolerant Fuel Performance and Reliability for Aggressive iPWR/SMR Operation
22. Exponential Time Differencing Schemes for Fuel Depletion and Transport in Molten Salt Reactors: Theory and Implementation
23. Thermal Safety Analyses for the Production of Plutonium-238 at the High Flux Isotope Reactor
24. Report on Reactor Physics Assessment of Candidate Accident Tolerant Fuel Cladding Materials in LWRs
25. Exponential Time Differencing Schemes for Fuel Depletion and Transport in Molten Salt Reactors: Theory and Implementation
26. Editorial: A preface to the special issue on “PHYSOR-2018: Reactor Physics Paving the Way Towards More Efficient Systems, 22–26 April 2018, Cancun, Mexico”
27. VVER 1000 Khmelnitskiy benchmark analysis calculated by Serpent2
28. Two-dimensional hexagonal geometry discontinuity factors at the core periphery
29. Towards Development of Uncertainty Library for Nuclear Reactor Core Simulation
30. Two-Step Procedure for Liquid-Salt-Cooled-Reactor Analysis
31. Neutronic Evaluation of a Liquid Salt–Cooled Reactor Assembly
32. Implementation of the direct S(α,β) method in the KENO Monte Carlo code
33. Sensitivity Studies and Experimental Evaluation for Optimizing Transcurium Isotope Production
34. A RELAP5-3D Model of the Lobo Lead Loop.
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