135 results on '"Pestchanyi, S."'
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2. Influence of pellet shielding on disruption mitigation in ITER
3. Development of an advanced magnetic equilibrium model for fusion reactor system codes
4. TOKES simulations to compare gas and pellet injection for disruption mitigation in ITER
5. Validation of TOKES vapor shield simulations against experiments in the 2MK-200 facility
6. Simulation of W diaphragm efficiency for mitigation of RE beam in ITER
7. Erratum: Integrated design strategy for EU-DEMO first wall protection from plasma transients (Fusion Engineering and Design (2022) 177, (113067) (S0920379622000679), (10.1016/j.fusengdes.2022.113067))
8. Analysis of energy cross-transport during MGI: JET experiments and TOKES simulations
9. Simulation of tungsten plasma transport along magnetic field under ELM-like heat loads
10. Dust generation mechanisms under powerful plasma impacts to the tungsten surfaces in ITER ELM simulation experiments
11. Verification of TOKES simulations against the MGI experiments in JET
12. Erosion simulation of first wall beryllium armour after ITER transient heat loads and runaway electrons action
13. Experimental study of PFCs erosion and eroded material deposition under ITER-like transient loads at the plasma gun facility QSPA-T
14. Simulation of residual thermostress in tungsten after repetitive ELM-like heat loads
15. Simulation of tungsten armour cracking due to small ELMs in ITER
16. Vapour shielding of liquid-metal CPS-based targets under ELM-like and disruption transient loading
17. Experimental verification of FOREV-2D simulations for the plasma shield
18. Experimental study of PFCs erosion under ITER-like transient loads at plasma gun facility QSPA
19. Behaviour of melted tungsten plasma facing components under ITER-like transient heat loads: Simulations and experiments
20. ELM induced carbon contamination of ITER core
21. Effects of ELMs on ITER divertor armour materials
22. Improvement of the CFC structure to withstand high heat flux
23. Modelling of thermal shock experiments of carbon based materials in JUDITH
24. Estimation of carbon fibre composites as ITER divertor armour
25. The plasma shield in ITER plasma wall interactions
26. 3-D simulation of macroscopic erosion of CFC under ITER off-normal heat loads
27. Plasma disruption management in ITER
28. Macroscopic erosion of divertor and first wall armour in future tokamaks
29. Macroscopic erosion in tokamak off normal events
30. Erosion of ITER-FEAT vertical targets during off-normal events
31. Vertical target and FW erosion during off-normal events and impurity production and transport during ELMs typical for ITER-FEAT
32. Development of an advanced magnetic equilibrium and confinement model for fusion reactor systems codes
33. Simulation of turbulent plasma heat flux to the DEMO first wall
34. Plasma shield dynamics and target erosion in disruption simulation experiments
35. Simulation of Heat Flux to the DEMO First Wall Due to Filamentary Transport in the Far SOL
36. Simulations with current constraints of ELM-induced tungsten melt motion in ASDEX Upgrade
37. Improved Fusion Reactor Designs as per Integration of Advanced Physics and Technology Systems Code Modules
38. TOKES studies of the thermal quench heat load reduction in mitigated ITER disruptions
39. Physics conclusions in support of ITER W divertor monoblock shaping
40. Simulation of Be armour cracking under ITER-like transient heat loads
41. Modelling of Material Damage and High Energy Impacts on Tokamak PFCs during Transient Loads
42. ITER-ELM control requirements, ELM control schemes and required R&D
43. Modeling of brittle destruction of ITER armour under repetitive loads
44. Modelling of boundary plasma in TOKES
45. Divertor armour issues: lifetime, safety and influence on ITER performance
46. Simulation of ITER first wall radiation heat load during the disruption
47. Optimization of MGI in JET using the TOKES code and mitigation of RE damage for the first wall
48. Specific Features of Mechanism for Dust Production from Tungsten Armor under Action of ELMs
49. Damage evaluation of vertical targets and first walls during ITER-FEAT off-normal events
50. Hot plasma target interaction and quantification of erosion of the ITER slot divertor during disruptions and ELMs
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