skip to main content
OSTI.GOV title logo U.S. Department of Energy
Office of Scientific and Technical Information

Title: Boundary plasma modelling for ITER

Abstract

Computer programs were developed to model the effect of nonaxisymmetric magnetic perturbations upon divertor heat load, and have explored what kind of externally applied perturbations are the most effective for heat load reduction without destroying core plasma confinement. We find that a carefully tuned set of coils located about 0.3 m outside the separatrix can be used to spread the heat load over about 0.1 m perpendicular to flux surfaces at the ITER divertor plate, even at a very low level of anomalous cross-field heat transport. As such a spreading would significantly extend the permissible regime of operation for ITER, we recommend that this study be pursued at the level of detail required for engineering design. In other work under this grant we are in the process of modifying the B2 code to handle correctly a non-orthogonal geometry.

Authors:
Publication Date:
Research Org.:
New York Univ., NY (United States). Courant Inst. of Mathematical Sciences
Sponsoring Org.:
USDOE; USDOE, Washington, DC (United States)
OSTI Identifier:
7009859
Report Number(s):
DOE/ER/54165-1
ON: DE93007963
DOE Contract Number:  
FG02-92ER54165
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
70 PLASMA PHYSICS AND FUSION TECHNOLOGY; DIVERTORS; HEATING; ITER TOKAMAK; MAGNETIC FIELD CONFIGURATIONS; COMPUTER CODES; COMPUTERIZED SIMULATION; PROGRESS REPORT; CLOSED PLASMA DEVICES; DOCUMENT TYPES; SIMULATION; THERMONUCLEAR DEVICES; TOKAMAK DEVICES; 700430* - Fusion Technology- Magnet Coils & Fields- (1992-)

Citation Formats

Braams, B J. Boundary plasma modelling for ITER. United States: N. p., 1993. Web. doi:10.2172/7009859.
Braams, B J. Boundary plasma modelling for ITER. United States. https://doi.org/10.2172/7009859
Braams, B J. Fri . "Boundary plasma modelling for ITER". United States. https://doi.org/10.2172/7009859. https://www.osti.gov/servlets/purl/7009859.
@article{osti_7009859,
title = {Boundary plasma modelling for ITER},
author = {Braams, B J},
abstractNote = {Computer programs were developed to model the effect of nonaxisymmetric magnetic perturbations upon divertor heat load, and have explored what kind of externally applied perturbations are the most effective for heat load reduction without destroying core plasma confinement. We find that a carefully tuned set of coils located about 0.3 m outside the separatrix can be used to spread the heat load over about 0.1 m perpendicular to flux surfaces at the ITER divertor plate, even at a very low level of anomalous cross-field heat transport. As such a spreading would significantly extend the permissible regime of operation for ITER, we recommend that this study be pursued at the level of detail required for engineering design. In other work under this grant we are in the process of modifying the B2 code to handle correctly a non-orthogonal geometry.},
doi = {10.2172/7009859},
url = {https://www.osti.gov/biblio/7009859}, journal = {},
number = ,
volume = ,
place = {United States},
year = {1993},
month = {1}
}