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Title: ITER-EDA physics design requirements and plasma performance assessments

Abstract

Physics design guidelines, plasma performance estimates, and sensitivity of performance to changes in physics assumptions are presented for the ITER-EDA Interim Design. The overall ITER device parameters have been derived from the performance goals using physics guidelines based on the physics R&D results. The ITER-EDA design has a single-null divertor configuration (divertor at the bottom) with a nominal plasma current of 21 MA, magnetic field of 5.68 T, major and minor radius of 8.14 m and 2.8 m, and a plasma elongation (at the 95% flux surface) of {approximately}1.6 that produces a nominal fusion power of {approximately}1.5 GW for an ignited burn pulse length of {ge}1000 s. The assessments have shown that ignition at 1.5 GW of fusion power can be sustained in ITER for 1000 s given present extrapolations of H-mode confinement ({tau}{sub E} = 0.85 {times} {tau}{sub ITER93H}), helium exhaust ({tau}*{sub He}/{tau}{sub E} = 10), representative plasma impurities (n{sub Be}/n{sub e} = 2%), and beta limit [{beta}{sub N} = {beta}(%)/(I/aB) {le} 2.5]. The provision of 100 MW of auxiliary power, necessary to access to H-mode during the approach to ignition, provides for the possibility of driven burn operations at Q = 15. This enables ITER to fulfill itsmore » mission of fusion power ({approximately} 1--1.5 GW) and fluence ({approximately}1 MWa/m{sup 2}) goals if confinement, impurity levels, or operational (density, beta) limits prove to be less favorable than present projections. The power threshold for H-L transition, confinement uncertainties, and operational limits (Greenwald density limit and beta limit) are potential performance limiting issues. Improvement of the helium exhaust ({tau}*{sub He}/{tau}{sub E} {le} 5) and potential operation in reverse-shear mode significantly improve ITER performance.« less

Authors:
;  [1]; ; ; ; ;  [2]
  1. Oak Ridge National Lab., TN (United States)
  2. ITER San Diego Joint Work Site, CA (United States)
Publication Date:
Research Org.:
Oak Ridge National Lab., TN (United States)
Sponsoring Org.:
USDOE, Washington, DC (United States)
OSTI Identifier:
254953
Report Number(s):
CONF-9606116-53
ON: DE96012346; TRN: 96:016075
DOE Contract Number:  
AC05-96OR22464
Resource Type:
Conference
Resource Relation:
Conference: Annual meeting of the American Nuclear Society (ANS), Reno, NV (United States), 16-20 Jun 1996; Other Information: PBD: [1996]
Country of Publication:
United States
Language:
English
Subject:
70 PLASMA PHYSICS AND FUSION; ITER TOKAMAK; DESIGN; PLASMA; NUCLEAR PHYSICS; THERMONUCLEAR REACTIONS; PLASMA DENSITY; PERFORMANCE; MAGNETIC CONFINEMENT; BETA RATIO

Citation Formats

Uckan, N A, Galambos, J, Wesley, J, Boucher, D, Perkins, F, Post, D, and Putvinski, S. ITER-EDA physics design requirements and plasma performance assessments. United States: N. p., 1996. Web.
Uckan, N A, Galambos, J, Wesley, J, Boucher, D, Perkins, F, Post, D, & Putvinski, S. ITER-EDA physics design requirements and plasma performance assessments. United States.
Uckan, N A, Galambos, J, Wesley, J, Boucher, D, Perkins, F, Post, D, and Putvinski, S. Mon . "ITER-EDA physics design requirements and plasma performance assessments". United States. https://www.osti.gov/servlets/purl/254953.
@article{osti_254953,
title = {ITER-EDA physics design requirements and plasma performance assessments},
author = {Uckan, N A and Galambos, J and Wesley, J and Boucher, D and Perkins, F and Post, D and Putvinski, S},
abstractNote = {Physics design guidelines, plasma performance estimates, and sensitivity of performance to changes in physics assumptions are presented for the ITER-EDA Interim Design. The overall ITER device parameters have been derived from the performance goals using physics guidelines based on the physics R&D results. The ITER-EDA design has a single-null divertor configuration (divertor at the bottom) with a nominal plasma current of 21 MA, magnetic field of 5.68 T, major and minor radius of 8.14 m and 2.8 m, and a plasma elongation (at the 95% flux surface) of {approximately}1.6 that produces a nominal fusion power of {approximately}1.5 GW for an ignited burn pulse length of {ge}1000 s. The assessments have shown that ignition at 1.5 GW of fusion power can be sustained in ITER for 1000 s given present extrapolations of H-mode confinement ({tau}{sub E} = 0.85 {times} {tau}{sub ITER93H}), helium exhaust ({tau}*{sub He}/{tau}{sub E} = 10), representative plasma impurities (n{sub Be}/n{sub e} = 2%), and beta limit [{beta}{sub N} = {beta}(%)/(I/aB) {le} 2.5]. The provision of 100 MW of auxiliary power, necessary to access to H-mode during the approach to ignition, provides for the possibility of driven burn operations at Q = 15. This enables ITER to fulfill its mission of fusion power ({approximately} 1--1.5 GW) and fluence ({approximately}1 MWa/m{sup 2}) goals if confinement, impurity levels, or operational (density, beta) limits prove to be less favorable than present projections. The power threshold for H-L transition, confinement uncertainties, and operational limits (Greenwald density limit and beta limit) are potential performance limiting issues. Improvement of the helium exhaust ({tau}*{sub He}/{tau}{sub E} {le} 5) and potential operation in reverse-shear mode significantly improve ITER performance.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1996},
month = {7}
}

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