Analysis, verification, and benchmarking of the transient thermal hydraulic ITERTHA code for the design of ITER divertor
- 1. Atomic Energy Authority, Cairo (Egypt)
- 2. Purdue University, West Lafayette, IN (United States)
Description
An analytical study for the International Thermonuclear Experimental Reactor Thermal Hydraulic Analysis code (ITERTHA) is carried out for a copper divertor with a 5 mm tungsten tile. The influence of the incident heat flux, swirl-tape insertion in cooling channels as well as the coolant flow velocity on the divertor thermal response is analyzed and discussed. The ITERTHA code results are verified by the commercial finite element code, COSMOS. The heat transfer coefficients at the nodes located on the cooling channel-wall are determined outside COSMOS code by the same methodology used in ITERTHA. A good agreement is achieved under different incident heat fluxes. The ITERTHA code is also benchmarked against the thermal-hydraulic calculation of the outer divertor of the Fusion Ignition Research Experiment, FIRE for an incident heat flux of 20 MW/m2 and coolant flow velocity of 10 m/s in a cooling channel of 8 mm diameter with swirl-tape inserts of 2 ratio and 1.5 mm thickness. The results show excellent agreement for both steady and transient states and prove the successful implementation of both the hydraulic and heated diameters of the swirl-tape channels in the used heat transfer correlations.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.fusengdes.2010.03.070Additional details
Identifiers
- DOI
- 10.1016/j.fusengdes.2010.03.070;
- PII
- S0920-3796(10)00144-4;
Publishing Information
- Journal Title
- Fusion Engineering and Design
- Journal Volume
- 85
- Journal Issue
- 5
- Journal Page Range
- p. 687-693
- ISSN
- 0920-3796
- CODEN
- FEDEEE
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 42013198
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Descriptors DEI
- COPPER; DIVERTORS; FINITE ELEMENT METHOD; HEAT FLUX; HEAT TRANSFER; ITER TOKAMAK; THERMAL HYDRAULICS; TRANSIENTS; VERIFICATION
- Descriptors DEC
- CALCULATION METHODS; CLOSED PLASMA DEVICES; ELEMENTS; ENERGY TRANSFER; FLUID MECHANICS; HYDRAULICS; MATHEMATICAL SOLUTIONS; MECHANICS; METALS; NUMERICAL SOLUTION; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS; TRANSITION ELEMENTS
Optional Information
- Copyright
- Copyright (c) 2010 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.