https://iris.unipa.it/bitstream/10447/355244/1/10%20-%20Notaro%20et%20al%20Procedia%202014%20Urban%20flooding.pdf

The Effect of Damage Functions on Urban Flood Damage Appraisal

Design and preliminary analyses of the new Water Cooled Lithium Lead TBM for ITER

Hydrogen isotope permeation through and inventory in the first wall of the water cooled Pb-17Li blanket for DEMO

Uncertainty evaluation of design rainfall for urban flood risk analysis.

Tritium permeation through the first wall of the EU-HCPB blanket

On the influence of the supporting frame on the nuclear response of the Helium-Cooled Lithium Lead Test Blanket Module for ITER

Neutronic and photonic analysis of the single box water-cooled lithium lead blanket for a DEMO reactor

Within the European Fusion Technology Programme, the Helium-Cooled Lithium Lead (HCLL) breeding blanket concept is one of the two EU lines to be developed for a long term fusion reactor, in particular with the aim of manufacturing a test blanket module (TBM) to be implemented in ITER. The HCLL-TBM is foreseen to be located in an ITER equatorial port, being housed inside a steel-supporting frame, actively cooled by pressurized water. This supporting frame has been designed to house two different TBMs providing two cavities separated by a dividing plate 20 cm thick. As the nuclear response of HCLL-TBM could vary with the supporting frame configuration and composition, a parametric study has been launched to investigate such an influence. Previous works dealt with the dependence of the nuclear response of HCLL-TBM on the configuration of an homogeneous frame while the present one has been focussed on the investigation of the influence of coolant distribution within the frame. A detailed parametric study of HCLL-TBM nuclear response has been performed by means of 3D-Monte Carlo neutronic and photonic analyses, simulating the frame in a semi-heterogeneous way. Three-dimensional heterogeneous models of HCLL-TBM and of the supporting frame have been set-up considering both the usual poloidal lay-out and a toroidal one and taking into account 9% Cr martensitic steel (EUROFER) as structural material. The models have been inserted into an existing 3D semi-heterogeneous ITER-FEAT one, simulating realistically the reactor lay-out up to the cryostat and providing for a proper D-T neutron source. The analyses have been performed by means of the MCNP-4C code, running a large number of histories (2·108) in such a way that results obtained are affected by statistical uncertainties lower than 1%. The results obtained are reported and critically discussed.

A study of the potential influence of frame coolant on HCLL-TBM nuclear response

The Helium Cooled Pebble Bed (HCPB) Blanket for fusion power reactors and the ITER breeding blanket are based on the use of pebble beds of lithium ceramics as breeder and beryllium as neutron multiplier. Experimental activities were performed at Forschungszentrum Karlsruhe concerning the measurement of pebble bed heat transfer parameters. At the Department of Nuclear Engineering of the University of Palermo, the experimental results have been reproduced by means of the ABAQUS finite element code. Moreover, a thermal-mechanical theoretical model has been developed for single size beryllium pebble beds. In the paper the results from the numerical and theoretical analyses and the comparison with experimental data are presented and critically discussed.

E. Oliveri

Papers

On the influence of the supporting frame on the nuclear response of the Helium-Cooled Lithium Lead Test Blanket Module for ITER

Neutronic and photonic analysis of the single box water-cooled lithium lead blanket for a DEMO reactor

A study of the potential influence of frame coolant on HCLL-TBM nuclear response

Modelling of the thermal-mechanical behaviour of a single size beryllium pebble bed

On the effects of the supporting frame on the radiation-induced damage of HCLL-TBM structural material