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2. R&D Activities for Fusion DEMO in the QST Rokkasho Fusion Institute

3. Power exhaust concepts and divertor designs for Japanese and European DEMO fusion reactors

4. Conceptual design study of pellet fueling system for DEMO

6. Safety research on fusion DEMO in Japan: Toward development of safety strategy of a water-cooled DEMO

7. Analysis of plasma position control for DEMO reactor

8. Thermohydraulic Analysis of Accident Scenarios of a Fusion DEMO Reactor Based on Water-Cooled Ceramic Breeder Blanket: Analysis of LOCAs and LOVA

9. Design concept of conducting shell and in-vessel components suitable for plasma vertical stability and remote maintenance scheme in DEMO reactor

10. Development of plant concept related to tritium handling in the water-cooling system for JA DEMO

11. Design study of blanket structure based on a water-cooled solid breeder for DEMO

12. Comparative evaluation of remote maintenance schemes for fusion DEMO reactor

13. Management Strategy for Radioactive Waste in the Fusion DEMO Reactor

14. Simulation study of power load with impurity seeding in advanced divertor 'short super-X divertor' for a tokamak reactor

15. Evaluation of remote maintenance schemes by plasma equilibrium analysis in Tokamak DEMO reactor

16. Study of safety features and accident scenarios in a fusion DEMO reactor

17. Waste management scenario in the hot cell and waste storage for DEMO

18. Application of inter-linked superconducting coils for central solenoid and advanced divertor configuration of DEMO

19. Relationship between net electric power and radial build of DEMO based on ITER steady-state scenario parameters

21. Investigation of Advanced Divertor Magnetic Configuration for DEMO Tokamak Reactor

22. Overview of the JET results in support to ITER

23. Conceptual study of vertical sector transport maintenance for DEMO fusion reactor

24. Waste management strategy focused on maintenance, storage and recycling

25. Nuclear analysis of DEMO water-cooled blanket based on sub-critical water condition

26. Design studies of innovatively small fusion reactor based on biomass-fusion hybrid concept: GNOME

27. Simplification of blanket system for SlimCS fusion DEMO reactor

28. Search for reality of solid breeder blanket for DEMO

29. TBR comparison of water-cooled blanket based on PWR and SCWR water conditions

30. Studies of power exhaust and divertor design for a 1.5 GW-level fusion power DEMO

31. Conceptual Design of Temporally Storage Area in Hot Cell for Fusion DEMO Reactor

32. Thermohydraulic responses of a water-cooled tokamak fusion DEMO to loss-of-coolant accidents

33. Conceptual design study of the moderate size superconducting spherical tokamak power plant

36. Key Aspects of the Safety Study of a Water-Cooled Fusion DEMO Reactor

37. Critical design factors for sector transport maintenance in DEMO

38. Use of an ‘Inter-Linked' Central Solenoid for Plasma Current Ramp-Up in a Tokamak Fusion Reactor

39. Comparison of Coolant Conditions in the Blanket for a Water-Cooled DEMO Reactor SlimCS

40. Blanket Concept of Water-Cooled Lithium Lead with Beryllium for the SlimCS Fusion DEMO Reactor

41. Japan’s Efforts to Develop the Concept of JA DEMO During the Past Decade

42. Safety studies of plasma-wall events with AINA code for Japanese DEMO

43. Progress in Thermohydraulic Analysis of Accident Scenarios of a Water-Cooled Fusion Demo Reactor

44. Deep neural networks for plasma tomography with applications to JET and COMPASS

45. Conceptual design study of the moderate size superconducting spherical tokamak power plant.

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