0000000000652987

AUTHOR

L. Petrizzi

showing 3 related works from this author

Three-Dimensional Neutronics and Shielding Analyses for the ITER Divertor

1996

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.

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 engineeringNeutronHeliumFusion Technology
researchProduct

3-D Shielding Analyses of the Vertical and Mid-Plane Ports in ITER

1996

A three dimensional (3-D) shielding analysis of the International Thermonuclear Experimental Reactor (ITER) has been performed with the aim of calculating the nuclear heating on the magnet system, correlating it to the existing vertical and horizontal ports. When these openings are left unshielded, more than 50 kW are calculated for the upper half of Toroidal Field Coil system and two of the Poloidal Field Coils. A simple plug, with same thickness as of the vacuum vessel can lower the heating to meet the imposed requirements. 5 refs., 6 figs., 4 tabs.

PhysicsThermonuclear fusionNuclear heatingPlane (geometry)020209 energyNuclear engineeringMonte Carlo methodGeneral Engineering02 engineering and technology01 natural sciences010305 fluids & plasmaslaw.inventionNuclear physicsElectromagnetic coillawMagnet0103 physical sciencesElectromagnetic shielding0202 electrical engineering electronic engineering information engineeringSpark plugFusion Technology
researchProduct

Overview of the JET results with the ITER-like wall

2013

Following the completion in May 2011 of the shutdown for the installation of the beryllium wall and the tungsten divertor, the first set of JET campaigns have addressed the investigation of the retention properties and the development of operational scenarios with the new plasma-facing materials. The large reduction in the carbon content (more than a factor ten) led to a much lower Zeff (1.2-1.4) during L- and H-mode plasmas, and radiation during the burn-through phase of the plasma initiation with the consequence that breakdown failures are almost absent. Gas balance experiments have shown that the fuel retention rate with the new wall is substantially reduced with respect to the C wall. T…

Nuclear and High Energy PhysicsMaterials scienceREGIMENuclear engineeringchemistry.chemical_element-Condensed Matter PhysicEffective radiated powerTungstenNuclear and High Energy Physics; Condensed Matter PhysicsPedestalPLASMA-FACING COMPONENTSTOKAMAK PLASMASJet (fluid)TUNGSTENDivertorperfomancePlasmaPERFORMANCECondensed Matter PhysicsSettore FIS/07 - Fisica Applicata(Beni Culturali Ambientali Biol.e Medicin)chemistryBeta (plasma physics)DIVERTORBerylliumAtomic physics
researchProduct