On the nuclear response of the helium-cooled lithium lead test blanket module in ITER

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Abstract

The helium-cooled lithium lead (HCLL) concept has been recently selected as one of the two European reference designs foreseen for the breeding blanket of a demonstration fusion reactor. In particular, within the framework of the research and development activities on this blanket line, an HCLL test blanket module (TBM) has to be designed and manufactured to beimplemented in ITER.At the Department of Nuclear Engineering (DIN) of the University of Palermo, a research campaign has been carried out to investigate the nuclear response of HCLL-TBM inside ITER by a numerical approach based on the Monte Carlo method. A realistic 3D heterogeneous model of HCLL-TBM has been set-up and inserted into an ITER 3D semi-heterogeneous one that simulates realistically the reactor lay-out up to the cryostat. A Gaussian-shaped neutron source has been adopted for the calculations.The main features of the HCLL-TBM nuclear response have been determined, paying particular attention to the deposited power and the tritium production rate together with the spatial distribution of their volumetric densities. The radiation damage of the structural material has also been investigated through the evaluation of displacement per atom and helium and hydrogen production rate.
Lingua originaleEnglish
pagine (da-a)725-730
Numero di pagine6
RivistaFusion Engineering and Design
Volume75-79
Stato di pubblicazionePublished - 2005

All Science Journal Classification (ASJC) codes

  • Civil and Structural Engineering
  • Nuclear Energy and Engineering
  • Materials Science(all)
  • Mechanical Engineering

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