442 results on '"NINOKATA, HISASHI"'
Search Results
2. Lessons Learned from Fukushima Daiichi Nuclear Power Plant Accident
3. 7 - Heat transfer in nuclear thermal hydraulics
4. 18 - Subchannel modeling and codes
5. Computational fluid dynamics study on cross flow pressure drop for triangular array rod assemblies with wire
6. A calculation methodology proposed for liquid droplet impingement erosion
7. A numerical study on turbulence attenuation model for liquid droplet impingement erosion
8. Development of analysis method for sodium void reactivity of step type FBR cores by using group-wise Monte Carlo code
9. A numerical study of impact force caused by liquid droplet impingement onto a rigid wall
10. Numerical investigation of bent pipe flows at transitional Reynolds number
11. Simulation of two regime sodium flows in a parallel plate channel during buoyancy-driven flow
12. Feasibility study of the application of exotic pin for tight-lattice fuel assembly
13. Application of adjoint-based sensitivity analysis to natural circulation of high-Pr fluid inside heat transport system
14. Numerical study of a single blade row in turbomolecular pump
15. Investigation of ALPHA experiment by severe accident analysis code SAMPSON
16. Anisotropic Turbulence and Coherent Structures in Eccentric Annular Channels
17. Adjoint‐based sensitivity analysis of circulating liquid fuel system for the multiphysics model of molten salt reactor
18. Risk-informed design of IRIS using a level-1 probabilistic risk assessment from its conceptual design phase
19. The pumping performances of the turbomoleculae pump simulated by direct simulation monte carlo method
20. A study on reactivity insertion controlled LMR cores with metallic fuel
21. Multi-dimensional analysis of two-phase flow inside subchannels of nuclear fuel assembly
22. A modified equilibrium void distribution model applicable to subchannel-scale vapor–liquid cross flow model for conventional square and tight lattice BWR fuel bundles
23. Nuclear Engineering Education in Polytechnic University of Milano, Italy
24. Foreword
25. Foreword: Selected papers from the 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17)
26. Double-strata high burnup fuel performance in light water reactors
27. Potential to approach the long-life core in a light water reactor with uranium oxide fuel
28. List of contributors
29. List of contributors
30. The concept and neutronic characteristics of a multipurpose fast reactor (MPFR)
31. Safety characteristics of the multipurpose fast reactor (MPFR)
32. Multi-fluid multi-phase subchannel analysis of subassembly accidents of LMFRs
33. Characteristics of fuel melting and relocation in metallic-fueled fast reactor core and its feasibility for eliminating recriticality
34. Modelling of Multi-Physics Phenomena in Fast Reactor Design: Safety and Experimental Validation
35. Preliminary Considerations from the 2nd Phase of Experiments at the SIET/SWAM Facility
36. A Comparative Overview of Thermal Hydraulic Characteristics of Integrated Primary System Nuclear Reactors
37. A Three-Dimensional DSMC Simulation of Single-Stage Turbomolecular Pump Adopting Accurate Intermolecular Collision Models
38. An overview of the microscopic approaches to thermal hydraulics computations of fluid transport phenomena in energy exchanges
39. A turbulence model study for simulating tight lattice rod bundles
40. Multi-dimensional analysis of two-phase flow inside subchannels of nuclear fuel assembly
41. Numerical SImulation of Sodium Pool Fire
42. Calculation of Heat Transfer Coefficients on a Flat Plate by Pseudo Direct Numerical Simulation of Turbulence
43. Simulation of Boiling Water Reactor One-Pump Trip Transient by TRAC/BF1-ENTREE
44. Double-strata high burnup fuel performance in LWRs
45. A robust approach to uncertainty in nuclear reactor thermal-hydraulic analysis
46. Multi-scale viscosity model of turbulence
47. Analytical study on detailed void distributions inside BWR fuel bundle under turbine trip event considering realistic pin power distribution
48. Concept of erbium dopted uranium oxide fuel cycle in light water reactors
49. Evaluation of self-controllability of LMFBRs against ATWS
50. On void reacitity limitation for nitride-fueled LMFR core
Catalog
Books, media, physical & digital resources
Discovery Service for Jio Institute Digital Library
For full access to our library's resources, please sign in.