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Title: Thermal-hydraulic design issues and analysis for the ITER (International Thermonuclear Experimental Reactor) divertor

Abstract

Critical Heat Flux (CHF), also called burnout, is one of the major design limits for water-cooled divertors in tokamaks. Another important design issue is the correct thermal modeling of the divertor plate geometry where heat is applied to only one side of the plate and highly subcooled flow boiling in internal passages is used for heat removal. This paper discusses analytical techniques developed to address these design issues, and the experimental evidence gathered in support of the approach. Typical water-cooled divertor designs for the International Thermonuclear Experimental Reactor (ITER) are analyzed, and design margins estimated. Peaking of the heat flux at the tube-water boundary is shown to be an important issue, and design concerns which could lead to imposing large design safety margins are identified. The use of flow enhancement techniques such as internal twisted tapes and fins are discussed, and some estimates of the gains in the design margin are presented. Finally, unresolved issues and concerns regarding hydraulic design of divertors are summarized, and some experiments which could help the ITER final design process identified. 23 refs., 10 figs.

Authors:
;  [1];  [2];  [3];  [4]
  1. Sandia National Labs., Albuquerque, NM (USA)
  2. Argonne National Lab., IL (USA)
  3. Oak Ridge National Lab., TN (USA). Fusion Engineering Design Center
  4. EG and G Energy Measurements Group, Inc., Albuquerque, NM (USA). Special Projects
Publication Date:
Research Org.:
Sandia National Labs., Albuquerque, NM (USA)
Sponsoring Org.:
DOE/DP
OSTI Identifier:
6398541
Report Number(s):
SAND-90-2503C; CONF-901007-16
ON: DE91001264
DOE Contract Number:  
AC04-76DP00789
Resource Type:
Conference
Resource Relation:
Conference: 9. topical meeting on technology of fusion energy, Oak Brook, IL (USA), 7-11 Oct 1990
Country of Publication:
United States
Language:
English
Subject:
70 PLASMA PHYSICS AND FUSION TECHNOLOGY; DIVERTORS; HEAT TRANSFER; HYDRAULICS; COOLING SYSTEMS; CRITICAL HEAT FLUX; DESIGN; ITER TOKAMAK; CLOSED PLASMA DEVICES; ENERGY SYSTEMS; ENERGY TRANSFER; FLUID MECHANICS; HEAT FLUX; MECHANICS; THERMONUCLEAR DEVICES; TOKAMAK DEVICES; 700204* - Fusion Power Plant Technology- Cooling Systems; 700202 - Fusion Power Plant Technology- Magnet Coils & Fields

Citation Formats

Koski, J A, Watson, R D, Hassanien, A M, Goranson, P L, and Salmonson, J C. Thermal-hydraulic design issues and analysis for the ITER (International Thermonuclear Experimental Reactor) divertor. United States: N. p., 1990. Web.
Koski, J A, Watson, R D, Hassanien, A M, Goranson, P L, & Salmonson, J C. Thermal-hydraulic design issues and analysis for the ITER (International Thermonuclear Experimental Reactor) divertor. United States.
Koski, J A, Watson, R D, Hassanien, A M, Goranson, P L, and Salmonson, J C. Mon . "Thermal-hydraulic design issues and analysis for the ITER (International Thermonuclear Experimental Reactor) divertor". United States. https://www.osti.gov/servlets/purl/6398541.
@article{osti_6398541,
title = {Thermal-hydraulic design issues and analysis for the ITER (International Thermonuclear Experimental Reactor) divertor},
author = {Koski, J A and Watson, R D and Hassanien, A M and Goranson, P L and Salmonson, J C},
abstractNote = {Critical Heat Flux (CHF), also called burnout, is one of the major design limits for water-cooled divertors in tokamaks. Another important design issue is the correct thermal modeling of the divertor plate geometry where heat is applied to only one side of the plate and highly subcooled flow boiling in internal passages is used for heat removal. This paper discusses analytical techniques developed to address these design issues, and the experimental evidence gathered in support of the approach. Typical water-cooled divertor designs for the International Thermonuclear Experimental Reactor (ITER) are analyzed, and design margins estimated. Peaking of the heat flux at the tube-water boundary is shown to be an important issue, and design concerns which could lead to imposing large design safety margins are identified. The use of flow enhancement techniques such as internal twisted tapes and fins are discussed, and some estimates of the gains in the design margin are presented. Finally, unresolved issues and concerns regarding hydraulic design of divertors are summarized, and some experiments which could help the ITER final design process identified. 23 refs., 10 figs.},
doi = {},
url = {https://www.osti.gov/biblio/6398541}, journal = {},
number = ,
volume = ,
place = {United States},
year = {1990},
month = {1}
}

Conference:
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