Search results for "HCLL"

Thermal analysis of the Helium-Cooled Lithium Lead Test Blanket Module to be irradiated in ITER

2009

On the nuclear response of the HCLL-TBM in ITER-FEAT

2003

On the nuclear impact of different coolants in the HCLL-TBM in ITER-FEAT

2003

A neutron point kinetic model for fusion relevant calculations

2012

Abstract In the framework of research activities on fusion reactors a great effort is dedicated by the scientific community to the development of tritium breeding blankets. One of the main goals is to assess the neutronic behaviour of such devices to analyse their tritium breeding performance and to evaluate the required data for their thermal–mechanic and thermal–hydraulic design. Many papers have been published on this topic considering some stationary condition to calculate such important quantities as heating power, gas production and dpa rates, tritium breeding ratio, etc., but not much attention has been focussed to neutronic transport analyses in transient conditions. The present pap…

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

2007

Abstract 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 st…

Assessment of the Possible Lay-Out Influence on the HCLL-TBM Nuclear Response

2009

The Department of Nuclear Engineering of the University of Palermo (DIN) was involved, since several years, in the study of the nuclear response of the helium-cooled lithium lead (HCLL) test blanket module (TBM) which will be tested in ITER. In this framework a research campaign was performed, at the DIN, to asses the nuclear response of the TBM in a toroidal lay-out, with the specific aim to investigate the possible lay-out influence on the module nuclear behaviour by comparing the results obtained with those presented in a similar previous work focussed on the most recent design of the poloidal HCLL-TBM. A computational approach based on the Monte Carlo method was followed and a realistic…

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

2006

Abstract Within the European Fusion Technology Programme, very intense research activities have been promoted on the Helium-Cooled Lithium Lead (HCLL) breeding blanket concept with the specific aim of manufacturing a Test Blanket Module (TBM) to be irradiated in ITER. HCLL-TBM is foreseen to be located in an ITER equatorial port, being housed inside a proper steel-supporting frame. In particular, since that frame has been designed to provide two cavities separated by a dividing plate and HCLL-TBM is foreseen to fill just one of them, its nuclear response could vary accordingly to the filling status of the other one, unless the dividing plate is thick enough to isolate the components housed …

Development of helium coolant DEMO first wall model for SYCOMORE system code based on HCLL concept

2018

Abstract The conceptual design of the demonstration fusion power reactor, known as DEMO, is ongoing and several reactor configurations have to be investigated by exploring different design parameters. For these reasons, within the European framework, systems codes like SYCOMORE (SYstem COde for MOdelling tokamak REactor) have been developed. SYCOMORE includes several specific modules, one of which is aimed to define a suitable design of the helium breeding blanket. The research activity has been devoted to improve the method to define automatically the First Wall design starting from thermal-hydraulic and thermo-mechanical considerations, using analytical design formulae and, also, taking i…