G. Cambi

Publications23
h-index3
Citations30
Highly Influential Citations2
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Activated corrosion products in ITER first wall and shielding blanket heat transfer system
Corrosion and erosion phenomena play an important role in mobilising activated materials in fusion machines. This paper deals with the assessment of the activated corrosion products (ACPs) related to… Expand
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Helium-cooled lithium lead: Activation analysis of the test blanket module in ITER
Abstract The helium-cooled lithium lead (HCLL) test blanket module (TBM) is one of the European blanket concepts selected to be tested in ITER. The test is an important step towards the development… Expand
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  • 1
Neutron exposure characterisation of ITER divertor materials for source terms evaluation
The paper presents the results of the Sn neutron transport and activation calculation to evaluate the activated corrosion product source terms related to the ITER divertor primary heat transfer… Expand
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Simulation of an integrated system for maritime traffic control in cooperative environment
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The SCALENEA-1 multipurpose Sn calculation sequence for application in fusion field: main features and its validation based on experimental data from a low-level waste repository
The paper presents the main features of the Sn calculation sequence SCALENEA-1 that has been extensively used for radioactive inventories, source terms, wastes and dose rates calculation for ITER,… Expand
  • 7
CALCULATED-EXPERIMENT CROSS-CHECK FOR DOSE RATES OUTSIDE DRUMS CONTAINING CEMENTED LIQUID RADIOACTIVE WASTES
During the treatment campaigns, carried out in ITREC (Treatment and Remaking Fuel Elements Plant), near the Trisaia locality, Italy, liquid wastes of low and higher activity have been produced and… Expand
ANITA-2007 Activation code package: main features and validation
Neutron irradiation effects on the ITER-EDA and ITER-RC first wall/blanket materials
Safety relevant effects of neutron irradiation (material activation, decay heat, radiation damage, heat deposition and gas production) on the in-vessel components materials of the ITER-EDA and the… Expand
IFMIF Preliminary Safety Analysis Report
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Preliminary occupational radiation exposure evaluation related to NET II/ITER
The Occupational Radiation Exposure (ORE) evaluation is part of the safety analysis process that has the purpose to permit the optimisation of protection, according to the basic recommendations of… Expand
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