Published November 1, 2016 | Version v1
Journal article

Draining and drying process development of the Tokamak Cooling Water System of ITER

  • 1. US ITER, Oak Ridge National Laboratory, Oak Ridge, TN (United States)
  • 2. University of Palermo, Viale delle Scienze, Palermo 90128 (Italy)
  • 3. Reactor and Nuclear Systems Division, ORNL, Oak Ridge, TN (United States)
  • 4. ITER Organization, 13067 St Paul Lez Durance (France)

Description

Highlights: • A thermal-hydraulic model using RELAP was developed for the ITER FW/BLK modules to determine design parameters for the nitrogen blowout flow rate and pressure. • The analysis indicates that as low as 2 MPa of pressure difference over the blanket modules will sufficiently evacuate the water in blankets. • A limited validation study indicates that the analysis yields less conservative results to compare against data collected from experiments. Therefore, the designed blow out flow of the drying system was selected with a large margin above the measured values to ensure the blow out operation. - Abstract: The ITER Organization (IO) developed a thermal-hydraulic (TH) model of the complex first wall and blanket (FW/BLK) cooling channels to determine gas flow rate and pressure required to effectively blow out the water in the FW/BLK. In addition, US ITER conducted experiments for selected geometries of FW/BLK flow channels to predict the blowout parameters. The analysis indicates that as low as 2 MPa of pressure difference over the blanket modules will ensure substantial evacuation of the water in blankets with just a few percent remaining in the blanket flow channels. A limited validation study indicates that the analysis yields less conservative results to compare against data collected from experiments. Therefore, the designed blow out flow of the drying system was selected with a large margin above the measured values to ensure the blow out operation.

Availability note (English)

Available from http://dx.doi.org/10.1016/j.fusengdes.2016.03.013

Additional details

Identifiers

DOI
10.1016/j.fusengdes.2016.03.013;
PII
S0920-3796(16)30209-5;

Publishing Information

Journal Title
Fusion Engineering and Design
Journal Volume
109-111
Journal Issue
Part A
Journal Page Range
p. 272-277
ISSN
0920-3796
CODEN
FEDEEE

Conference

Title
12. international symposium on fusion nuclear technology
Acronym
ISFNT-12
Dates
14-18 Sep 2015
Place
Jeju Island (Korea, Republic of)

Optional Information

Copyright
Copyright (c) 2016 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.