279 results on '"Vosoughi, Naser"'
Search Results
2. Multi-physics analysis of SBLOCA by coupled Neutronics/Thermal-Hydraulics full plant model
3. Investigation of VVER-1000 fuel assembly bowing effect on power distribution during cycle using neutron noise adiabatic approximation
4. Application of CFD and nodal expansion method for simulation and analysis of boron dilution accident
5. Application of deep learning techniques for nuclear power plant transient identification
6. Investigation of nuclear reactor core thermal-hydraulic characteristics after partial loss of flow accident
7. Evaluation of the performance of different feature selection techniques for identification of NPPs transients using deep learning
8. Axial-offset analysis in iPWR by developing the neutronic/thermal-hydraulic core simulator based on coarse-mesh methods
9. Development of a calculation model to simulate the effect of bowing of the VVER-1000 reactor fuel assembly on power distribution
10. Modeling and optimization of respiratory-gated partial breast irradiation with proton beams - A Monte Carlo study
11. Applications of Soft Computing in nuclear power plants: A review
12. Preclinical evaluation of188Re-HYNIC-PSMA as a novel therapeutic agent
13. Target motion management in breast cancer radiation therapy
14. Development of SD-HACNEM neutron noise simulator based on high order nodal expansion method for rectangular geometry
15. Precise localization of neutron noise sources based on transport theory and comparison with diffusion theory
16. Single peak analysis of proton induced prompt gamma counts
17. A new Monte Carlo approach for solution of the time dependent neutron transport equation based on nodal discretization to simulate the xenon oscillation with feedback
18. A new approach for calculation of the neutron noise of power reactor based on Telegrapher's theory: Theoretical and comparison study between Telegrapher's and diffusion noise
19. A new approach for solution of time dependent neutron transport equation based on nodal discretization using MCNPX code with feedback
20. SGSD: A novel Sequential Gamma-ray Spectrum Deconvolution algorithm
21. Processing scintillation gamma-ray spectra by artificial neural network
22. Implementation of a dynamic Monte Carlo method for transients analysis with thermal-hydraulic feedbacks using MCNPX code
23. Analysis of complex gamma-ray spectra using particle swarm optimization
24. SN transport method for neutronic noise calculation in nuclear reactor systems: Comparative study between transport theory and diffusion theory
25. Neutron noise simulation using ACNEM in the hexagonal geometry
26. Higher order power reactor noise analysis: The multigroup diffusion model
27. Development and Experimental Validation of a Correlation Monitor Tool Based on the Endogenous Pulsed Neutron Source Technique
28. PCB Design Impact on GaN-Based Converter Operation
29. On the limitations of linear power reactor noise analysis: A point kinetics approach
30. Development and validation of an optimal GATE model for proton pencil-beam scanning delivery.
31. Development of 3D neutron noise simulator based on GFEM with unstructured tetrahedron elements
32. Enhanced finite difference scheme for the neutron diffusion equation using the importance function
33. Application of Deep Learning Techniques for Nuclear Power Plant Transient Identification
34. Quantitative Elemental Analysis Using Whole Spectral Information (with GA and MLR Methods) of Proton Induced Prompt Gamma-Rays Simulated Using Geant4 Toolkit
35. Design and fabrication of an in situ gamma radioactivity measurement system for marine environment and its calibration with Monte Carlo method
36. A sensitivity analysis of thermal lattices kinetic parameters with respect to the spectral weighting function using ultrafine BN method
37. On the spatiotemporal correlations in a linear stochastic field generated by non-interacting particles: Theory
38. Optimization of neutron energy-group structure in thermal lattices using ultrafine bilinear adjoint function
39. Investigating the propagation noise in PWRs via closed-loop neutron-kinetic/thermal-hydraulic noise calculations
40. Development of MCNPX-ESUT computer code for simulation of neutron/gamma pulse height distribution
41. Development of a 3D program for calculation of multigroup Dancoff factor based on Monte Carlo method in cylindrical geometry
42. Calculation and analysis of thermal–hydraulics fluctuations in pressurized water reactors
43. On the second moment of a stochastic radiation field
44. Propagation noise calculations in VVER-type reactor core
45. Development and validation of an optimal GATE model for proton pencil-beam scanning delivery
46. Development of a 3D multigroup program for Dancoff factor calculation in pebble bed reactors
47. Noise source reconstruction using ANN and hybrid methods in VVER-1000 reactor core
48. An alternative stochastic formulation for the point reactor
49. On-line reactivity calculation using Lagrange method
50. Development of An Embedded FPGA-Based Data Acquisition System Dedicated to Zero Power Reactor Noise Experiments
Catalog
Books, media, physical & digital resources
Discovery Service for Jio Institute Digital Library
For full access to our library's resources, please sign in.