Published November 2005 | Version v1
Journal article

The EVITA programme: Experimental and numerical simulation of a fluid ingress in the cryostat of a water-cooled fusion reactor

  • 1. EFDA Close Support Unit, Boltzmannstrasse 2, D-85748 Garching (Germany)
  • 2. CEA Cadarache DEN/DTN/STPA, F-13108 St. Paul lez Durance (France)
  • 3. Technicatome, BP 34000, 13791 Aix-en-Provence Cedex 3 (France)
  • 4. INEEL, Idaho Falls, ID (United Kingdom)
  • 5. ENEA, via Enrico Fermi 45, I000-44 Frascati, Rome (Italy)
  • 6. Universita di Roma, Vicolo Delle Palle n.25-25/b, I00-186 Rome (Italy)

Description

In the frame of the deterministic approach in the safety analysis of the ITER reactor, it is postulated that a helium cooling line from the cryogenic system and one coolant pipe of the first wall/blanket primary heat transport system are damaged simultaneously in the cryostat. This event is selected to bound possible damage to the systems in the cryostat. The computer codes, which are used for the assessment of ITER safety, can be validated against the EVITA experiment, which has been designed for the simulation of the physical phenomena occurring during a coolant ingress into the cryostat, namely ice formation on a cryogenic structure, heat transfer coefficient between walls and fluid, flashing, two-phase critical flow. The comparison between calculations and experiments allows the ability of the computer codes to treat the relevant physical phenomena to be assessed

Additional details

Identifiers

DOI
10.1016/j.fusengdes.2005.06.279;
PII
S0920-3796(05)00140-7;

Publishing Information

Journal Title
Fusion Engineering and Design
Journal Volume
75-79
Journal Page Range
p. 1265-1269
ISSN
0920-3796
CODEN
FEDEEE

Conference

Title
23. symposium of fusion technology
Acronym
SOFT 23
Dates
20-24 Sep 2004
Place
Venice (Italy)

Optional Information

Copyright
Copyright (c) 2005 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.