Similar Items: Peaking factors of nuclear heating due to void ducts in the 80 percent SS-20 percent H2O shielding blanket of fusion experimental reactors.
- Shielding analysis of the ITER/EDA NBI duct.
- A simplified method to estimate beryllium burn up in breeder blankets of a fusion reactor and its impact on a tritium breeding.
- Conceptual design of iter shielding blanket.
- Convertible shielding to ceramic breeding blanket.
- Pre-analyses of SS316 and SS316/Water bulk shielding experiments.
- A mössbauer study of single-crystal Zr-0.065 at percent 57Fe.
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.
Author: Sato, Satoshi
- 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.
- Test program development for iter blanket design.
- Conceptual design of iter shielding blanket.
- Convertible shielding to ceramic breeding blanket.
- Trasient thermal and stress analyses of the ITER [International Thermonuclear Experimental Reactor] shielding blanket/first wall under off-normal conditions.