Preliminary fluid channel design and thermal-hydraulic analysis of glow discharge cleaning permanent electrode
- 1. Southwestern Institute of Physics, Chengdu (China)
- 2. ITER Organization, Route de Vinon-sur-Verdon, CS 90 046, 13067 St. Paul Lez Durance Cedex (France)
Description
Highlights: • The plasma facing closure cap has to survive after 30,000 thermal heat load cycles. • 0.35 MW/m2 radiation heat load plus nuclear heat load are very challenging for stainless steel. • Multilayer structure has been designed by using advanced welding and drilling technology to solve the neutron heating problem. • Accurate volumetric load application in analysis model by CFX has been mastered. - Abstract: Glow discharge cleaning (GDC) shall be used on ITER device to reduce and control impurity and hydrogenic fuel out-gassing from in-vessel plasma facing components. After first plasma, permanent electrode (PE) will be used to replace Temporary Electrode (TE) for subsequent operation. Two fundamental scenarios i.e., GDC and Plasma Operation State (POS) should be considered for electrode design, which requires the heat load caused by plasma radiation and neutron heating must be taken away by cooling water flowing inside the electrode. In this paper, multilayer cooling channels inside PE are preliminarily designed, and snakelike route in each layer is adopted to improve the heat exchange. Detailed thermal-hydraulic analyses have been done to validate the design feasibility or rationality. The analysis results show that during GDC the cooling water inlet and outlet temperature difference is far less than the allowable temperature rise under water flow rate 0.15 kg/s compromised by many factors. For POS, the temperature rise and pressure drop are within the design goals, but high thermal stress occurs on the front surface of closure cap of electrode. After several iterations of optimization of the closure cap, the equivalent strain range after 30,000 loading cycles for POS is well below 0.3% design goals.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.fusengdes.2016.01.060Additional details
Identifiers
- DOI
- 10.1016/j.fusengdes.2016.01.060;
- PII
- S0920-3796(16)30053-9;
Publishing Information
- Journal Title
- Fusion Engineering and Design
- Journal Volume
- 109-111
- Journal Issue
- Part A
- Journal Page Range
- p. 866-871
- 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
- 48067836
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CLEANING; CLOSURES; CONTAINERS; DEGASSING; ELECTRODES; FIRST WALL; FLOW RATE; GLOW DISCHARGES; HEATING LOAD; IMPURITIES; ITER TOKAMAK; NEUTRONS; OPTIMIZATION; PLASMA; PRESSURE DROP; RADIATION HEATING; STAINLESS STEELS; THERMAL HYDRAULICS; THERMAL STRESSES; WATER; WELDING
- Descriptors DEC
- ALLOYS; BARYONS; CARBON ADDITIONS; CLOSED PLASMA DEVICES; ELECTRIC DISCHARGES; ELEMENTARY PARTICLES; FABRICATION; FERMIONS; FLUID MECHANICS; HADRONS; HEATING; HIGH ALLOY STEELS; HYDRAULICS; HYDROGEN COMPOUNDS; IRON ALLOYS; IRON BASE ALLOYS; JOINING; MECHANICS; NUCLEONS; OXYGEN COMPOUNDS; STEELS; STRESSES; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTOR WALLS; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS; TRANSITION ELEMENT ALLOYS
Optional Information
- Copyright
- Copyright (c) 2016 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.