47 results on '"Maldonado, G. Ivan"'
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2. Activation Analysis for the Inboard Region of FNSF Using SERPENT
3. Tritium Breeding Ratio Evaluation of Solid Breeder Concepts for the FESS-FNSF
4. Radiation Damage Analysis of FNSF Components Using McCad and MCNP
5. Modeling dose rate increase from the addition of Uranium-232 for use as a tracer in uranium fuels
6. Exploration of producing Uranium-232 for use as a tracer in uranium fuels
7. Demonstration of RELAP5-3D for transient analysis of a dual coolant lead lithium fusion blanket concept
8. Enhanced Accident-Tolerant Fuel Performance and Reliability for Aggressive iPWR/SMR Operation
9. Assessment of BISON capabilities for component-level prediction of tritium transport in fusion and fission applications
10. Implementation of two-phase gas transport into VERA for molten salt reactor analysis
11. Exponential Time Differencing Schemes for Fuel Depletion and Transport in Molten Salt Reactors: Theory and Implementation
12. A review of thermal hydraulics systems analysis for breeding blanket design and future needs for fusion engineering demonstration facility design and licensing
13. Evaluation of end of cycle plutonium isotopic content in a VVER-1000 reactor using a 3D full-core simulator
14. Thermal Safety Analyses for the Production of Plutonium-238 at the High Flux Isotope Reactor
15. Simulation of a NuScale core design with the CASL VERA code
16. Report on Reactor Physics Assessment of Candidate Accident Tolerant Fuel Cladding Materials in LWRs
17. 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”
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. Reactivity Accountability Attributed to Reflector Poisons in the High Flux Isotope Reactor
21. Validation of a Monte Carlo Based Depletion Methodology Using HFIR Post-Irradiation Measurements
22. Validating MCNP for LEU Fuel Design via Power Distribution Comparisons
23. Towards Development of Uncertainty Library for Nuclear Reactor Core Simulation
24. Two-Step Procedure for Liquid-Salt-Cooled-Reactor Analysis
25. VVER 1000 Khmelnitskiy benchmark analysis calculated by Serpent2
26. Two-dimensional hexagonal geometry discontinuity factors at the core periphery
27. Neutronic Evaluation of a Liquid Salt–Cooled Reactor Assembly
28. Implementation of the direct S(α,β) method in the KENO Monte Carlo code
29. Sensitivity Studies and Experimental Evaluation for Optimizing Transcurium Isotope Production
30. Comparative economic analysis of the Integral Molten Salt Reactor and an advanced PWR using the G4-ECONS methodology
31. Creation of problem-dependent Doppler-broadened cross sections in the KENO Monte Carlo code
32. BWROPT: A multi-cycle BWR fuel cycle optimization code
33. Preface: Special Issue on the PHYSOR 2012 International Conference on the Physics of Reactors
34. Increasing transcurium production efficiency through directed resonance shielding
35. Nuclear Transmutations in HFIR’s Beryllium Reflector and Their Impact on Reactor Operation and Reflector Disposal
36. Neutronics modeling of the High Flux Isotope Reactor using COMSOL
37. Editorial
38. Validation of a Monte Carlo based depletion methodology via High Flux Isotope Reactor HEU post-irradiation examination measurements
39. Power Distribution Analysis for the ORNL High Flux Isotope Reactor Critical Experiment 3
40. Neutronic Analysis of an Advanced Fuel Design Concept for the High Flux Isotope Reactor
41. Enhancement of a subcritical experimental facility via MCNP simulations
42. Speedup of Particle Transport Problems with a Beowulf Cluster
43. An Application of Linear Superposition to Estimating Lattice-Physics Parameters
44. Neural Network and Perturbation Theory Hybrid Models for Eigenvalue Prediction
45. Total Assessment Evaluation Of a Cupola-based to Electric Induction Furnace Replacement
46. Employing Nodal Generalized Perturbation Theory for the Minimization of Feed Enrichment during Pressurized Water Reactor In-Core Nuclear Fuel Management Optimization
47. Application of Nonlinear Nodal Diffusion Generalized Perturbation Theory to Nuclear Fuel Reload Optimization
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