6533b829fe1ef96bd128ab1a
RESEARCH PRODUCT
Three-Dimensional Neutronics and Shielding Analyses for the ITER Divertor
L. PetrizziR.t. SantoroMohamed E. SawanD. Valenzasubject
PhysicsNeutron transportNuclear heating020209 energyDivertorGeneral EngineeringIter tokamakchemistry.chemical_element02 engineering and technology01 natural sciences010305 fluids & plasmasNuclear physicschemistryHeat flux0103 physical sciencesElectromagnetic shielding0202 electrical engineering electronic engineering information engineeringNeutronHeliumdescription
3-D neutronics and shielding analyses have been performed for the divertor region of the ITER interim design. The peak neutron wall loading in the divertor region is 0.6 MW/m{sup 2} at the divertor cassette dome. The total nuclear heating in the 60 divertor cassettes is 102.4 MW. The peak helium production in the VV behind the pumping ducts is 0.5 He appm/FPY implying that rewelding might be feasible. The total nuclear heating in the parts of the TF coils in the divertor region is only 2.1 kW. 5 refs., 4 figs., 5 tabs.
| year | journal | country | edition | language |
|---|---|---|---|---|
| 1996-12-01 | Fusion Technology |