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.
Journal:
Fusion Science and Technology

ISSN: 1536-1055

Year of publication: 2012

Volume: 62

Issue: 1

Pages: 190-195

Type: Conference paper

DOI: 10.13182/FST11-425 GOOGLE SCHOLAR

Sustainable development goals

Data source: Scopus