285 results on '"Yamano, Hidemasa"'
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2. Visualization Experiments of Radiation Heating on the Eutectic Reaction Between B4C-SS and Its Relocation Behavior
3. Development of failure mitigation technologies for improving resilience of nuclear structures
4. Development of Safety Design Technologies for Sodium-Cooled Fast Reactor Coupled to Thermal Energy Storage System with Sodium-Molten Salt Heat Exchanger
5. Study on the difference between B4C powder and B4C pellet regarding the eutectic reaction with stainless steel
6. Eutectic melting and relocation behavior of B4C pellet-stainless steel under radiative heating
7. Validation of the fast reactor plant dynamics analysis code Super-COPD using FFTF loss of flow without scram test #13
8. Raman spectroscopy of eutectic melting between boride granule and stainless steel for sodium-cooled fast reactors
9. A quantitative method of eutectic reaction study between boron carbide and stainless steel
10. Normal spectral emissivity, specific heat capacity, and thermal conductivity of type 316 austenitic stainless steel containing up to 10 mass% B4C in a liquid state
11. Effect of B4C addition on the solidus and liquidus temperatures, density and surface tension of type 316 austenitic stainless steel in the liquid state
12. Viscosities of Molten B4C-Stainless Steel Alloys
13. Key technologies for future sodium-cooled fast reactors
14. Contributors
15. Viscosity Measurements of Molten Metal Using an Improved Oscillating Crucible Method
16. Chapter 6 - Mitigation studies carried out for the French SFR demonstrator
17. Chapter 5 - Severe accident calculation tools used for severe accident and mitigation studies
18. Chapter 8 - Severe accident mitigation approach and studies for JSFR and other recent SFRs
19. Density, Surface Tension, and Viscosity of Molten Ni‐Based Superalloys Using the Maximum Bubble Pressure and Oscillating Crucible Methods
20. Development of Failure Mitigation Technologies for Improving Resilience of Nuclear Structures
21. Thinning behavior of solid boron carbide immersed in molten stainless steel for core disruptive accident of sodium-cooled fast reactor.
22. Core and safety design for France–Japan common concept on sodium-cooled fast reactor
23. Development of Risk Assessment Methodology Against External Hazards for Sodium-Cooled Fast Reactors
24. Development of probabilistic risk assessment methodology against extreme snow for sodium-cooled fast reactor
25. France–Japan synthesis concept on sodium-cooled fast reactor review of a joint collaborative work
26. Contributors
27. Editorial: Experimental and numerical studies on liquid metal cooled fast reactors
28. Verification of fuel assembly bowing analysis model for core deformation reactivity evaluation
29. EFFECTIVENESS EVALUATION METHODOLOGY OF THE MEASURES FOR IMPROVING RESILIENCE OF NUCLEAR STRUCTURES AGAINST EXCESSIVE EARTHQUAKE
30. DEVELOPMENT OF TRANSIENT BEHAVIOR ANALYSIS CODE FOR METAL FUEL FAST REACTOR DURING INITIATING PHASE OF CORE DISRUPTIVE ACCIDENT
31. EFFECTIVENESS EVALUATION METHODOLOGY OF THE MEASURES FOR IMPROVING RESILIENCE OF NUCLEAR STRUCTURES AT ULTRA-HIGH TEMPERATURE
32. IMPROVEMENT OF REACTIVITY MODEL OF CORE DEFORMATION IN PLANT DYNAMICS ANALYSIS CODE DURING UNPROTECTED LOSS OF HEAT SINK EVENT IN EBR-II
33. MITIGATION STRATEGIES FROM STRUCTURAL MECHANICS FOR BEYOND DESIGN BASIS EVENTS
34. ACTIVITIES OF THE GIF SAFETY AND OPERATION PROJECT OF SODIUM-COOLED FAST REACTOR SYSTEMS
35. Validation of Feedback Reactivity Evaluation Models for Plant Dynamics Analysis Code During Unprotected Loss of Heat Sink Event in Sodium-Cooled Fast Reactors
36. Evaluation of debris bed self-leveling behavior: A simple empirical approach and its validations
37. Raman spectroscopy of eutectic melting between boride granule and stainless steel for sodium-cooled fast reactors
38. An experimental investigation on self-leveling behavior of debris beds using gas-injection
39. CHARACTERISTICS OF SELF-LEVELING BEHAVIOR OF DEBRIS BEDS IN A SERIES OF EXPERIMENTS
40. Development of technical basis in the initiating and transition phases of unprotected events for Level-2 PSA methodology in sodium-cooled fast reactors
41. Coolability Evaluation of the Debris Bed on Core Catcher in a Sodium-Cooled Fast Reactor With a Whole Vessel Model
42. Application of 1D-CFD Coupling Method to Unprotected Loss of Heat Sink Event in EBR-II Focusing on Thermal Stratification in Cold Pool
43. Event Tree Analysis for Material Relocation on Core Catcher in a Sodium-Cooled Fast Reactor
44. Structural Analysis of a Reactor Vessel in a Sodium-Cooled Fast Reactor Under Extremely High Temperature Conditions
45. 5 - Key technologies for future sodium-cooled fast reactors
46. Experimental investigation of bubbling in particle beds with high solid holdup
47. Detailed analyses of key phenomena in core disruptive accidents of sodium-cooled fast reactors by the COMPASS code
48. Development of flow-induced vibration evaluation methodology for large-diameter piping with elbow in Japan sodium-cooled fast reactor
49. A finite element LES for high- Re flow in a short-elbow pipe with undisturbed inlet velocity
50. Matched refractive-index PIV visualization of complex flow structure in a three-dimentionally connected dual elbow
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