A platform for research: civil engineering, architecture and urbanism
A platform for research: civil engineering, architecture and urbanism
Neutronics Features of a Dual Coolant Lithium Lead Test Blanket Module for ITER
Neutronics analysis was performed for a dual coolant lithium lead blanket module to be tested in ITER. The total radial depth of the TBM is 41.3 cm followed by a 30 cm thick inlet/outlet piping zone. The calculated local tritium breeding ratio in the DCLL TBM is 0.741. The annual tritium production in the TBM is 2.4 g. The total nuclear heating in the TBM is 0.982 MW. The total thermal power to be removed from the TBM is 1.357 MW.
Neutronics Features of a Dual Coolant Lithium Lead Test Blanket Module for ITER
Neutronics analysis was performed for a dual coolant lithium lead blanket module to be tested in ITER. The total radial depth of the TBM is 41.3 cm followed by a 30 cm thick inlet/outlet piping zone. The calculated local tritium breeding ratio in the DCLL TBM is 0.741. The annual tritium production in the TBM is 2.4 g. The total nuclear heating in the TBM is 0.982 MW. The total thermal power to be removed from the TBM is 1.357 MW.
Neutronics Features of a Dual Coolant Lithium Lead Test Blanket Module for ITER
Sawan, M.E. (author) / Youssef, M.Z. (author)
2005-09-01
4085078 byte
Conference paper
Electronic Resource
English
| TIBKAT | 1965
| NTIS | 1965