Draining and drying process development of the Tokamak Cooling Water System of ITER
Creators
- 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.2016.03.013Additional 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)
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 48065300
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BLOWOUTS; COMPUTER CODES; COOLING; DRYING; FIRST WALL; FLOW RATE; GAS FLOW; GEOMETRY; ITER TOKAMAK; NITROGEN; PRESSURE RANGE MEGA PA; THERMAL HYDRAULICS; WATER
- Descriptors DEC
- ACCIDENTS; CLOSED PLASMA DEVICES; ELEMENTS; FLUID FLOW; FLUID MECHANICS; HYDRAULICS; HYDROGEN COMPOUNDS; MATHEMATICS; MECHANICS; NONMETALS; OXYGEN COMPOUNDS; PRESSURE RANGE; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTOR WALLS; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS
Optional Information
- Copyright
- Copyright (c) 2016 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.