40 results on '"Mori, Michitsugu"'
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2. Contributors
3. Preface
4. History of BWR development
5. BWR innovations
6. Level swell analysis of stagnant water pool in filtered containment venting systems
7. Dimensionless parameters controlling the spreading behaviors of free-falling molten metal on dry surface
8. Performance evaluation of decay heat removal systems of Fluoride-salt-cooled High-temperature Reactor (FHR)
9. Experimental study on molten metal spreading and deposition behaviors
10. Investigation of the supersonic steam injector operation mode
11. Experimental investigation of void fraction variation in subcooled boiling flow under horizontal forced vibrations
12. Scaling analysis of the spreading and deposition behaviors of molten-core-simulated metals
13. Experimental investigation of horizontal forced-vibration effect on air-water two-phase flow
14. Investigation of the thermal-hydraulic characteristics of supersonic steam injector
15. Assessment of the countermeasure improvement of ABWR using RETRAN-3D
16. Two-phase flow induced vibration in piping systems
17. Application of steam injector to improved safety of light water reactors
18. 5 - BWR innovations
19. 1 - History of BWR development
20. Corrigendum to “Effect of void fraction covariance on two-fluid model based code calculation in pipe flow” [Progress Nucl. Energy 108 (2018) 319–333]
21. Editorial: Thermal Hydraulics and Safety Analysis in Generation-IV Reactors
22. Improvement of Two-Fluid Model Based 1D Code with the State-of-the-Art Constitutive Equations for Two-Phase Flow in Rod Bundle
23. Evaluation of the in-vessel heat transfer for the debris removal of the Fukushima Daiichi nuclear power plant
24. Effect of void fraction covariance on two-fluid model based code calculation in pipe flow
25. Experimental study on molten metal spreading and deposition behaviors on wet surface
26. Heat transfer and CHF in subcooled flow boiling of aqueous surfactant solutions
27. Code performance with improved two-group interfacial area concentration correlation for one-dimensional forced convective two-phase flow simulation
28. Development of one-dimensional two-fluid model with consideration of void fraction covariance effect
29. Study on Operation Ranges and Discharge Performance of Steam Injector System
30. Future Nuclear Energy － Thinking of the US-Japan Seminars －
31. Analysis of Flow-Induced Vibration Due to Stratified Wavy Two-Phase Flow
32. Evaluation of the In-Vessel Heat Transfer Characteristics for the Debris Removal of the Fukushima Daiichi Nuclear Power Plant
33. B134 Classification of two-phase flow regimes based on force fluctuation signals and artificial neural network
34. ICONE23-2177 SEVERE ACCIDENT ANALYSIS OF LWR EQUIPPED WITH ISOLATION CONDENSERS EMPLOYING RETRAN/MOD4
35. Two-phase flow structure and operating characteristics of supersonic steam injector
36. ICONE23-2171 Design Considerations for Insulation System for Fluoride Salt Cooled High Temperature Reactor under Beyond Design Basis Accident Conditions
37. ICONE23-2188 MOLTEN CORE CONCRETE INTERACTION AT CONTAINMENT SUMP PIT UNDER SEVERE ACCIDENT
38. ICONE23-1854 ATMOSPHERIC DIFFUSION NUMERICAL SIMULATION ANALYSIS OF CESIUM THAT TAKES INTO ACCOUNT THE WET DEPOSITION
39. B232 Behaviors on Spreading Flow of Molten Metal at Elevated Temperatures
40. ICONE23-1650 OPERATING CRITERIA AND MECHANISMS OF SUPERSONIC STEAM INJECTOR
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