Similar Items: Shielding analysis of the ITER/EDA NBI duct.
- The plasma position control of iter eda plasma.
- Peaking factors of nuclear heating due to void ducts in the 80 percent SS-20 percent H2O shielding blanket of fusion experimental reactors.
- Two-Dimensional over-all neutronics analysis of the iter device.
- Conceptual design of iter shielding blanket.
- Some ITER shield problems examination.
- Magnetohydrodynamic flows in ducts with insulating coatings.
Author: Zimin, Sergei
- A simplified method to estimate beryllium burn up in breeder blankets of a fusion reactor and its impact on a tritium breeding.
- Two-Dimensional over-all neutronics analysis of the iter device.
- Hydrogen formation in metals and alloys during fusion reactor operation.
- Shielding analysis of the ITER/EDA NBI duct.
- Peaking factors of nuclear heating due to void ducts in the 80 percent SS-20 percent H2O shielding blanket of fusion experimental reactors.
- Design study on a 1MeV, 12,5 MW neutral beam injector module for iter.