Neutronic assessment of candidate materials for TF coils shielding in a demo fusion reactor based on a dcll blanket

  1. Catalán, J.P.
  2. Sanz, J.
  3. Ogando, F.
  4. Pampin, R.
Revue:
Fusion Science and Technology

ISSN: 1536-1055

Année de publication: 2012

Volumen: 62

Número: 1

Pages: 190-195

Type: Communication dans un congrès

DOI: 10.13182/FST11-425 GOOGLE SCHOLAR