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Title: Is Carbon a Realistic Choice for ITER's Divertor?

Abstract

Tritium retention by co-deposition with carbon on the divertor target plate is predicted to limit ITER's DT burning plasma operations (e.g. to about 100 pulses for the worst conditions) before the in-vessel tritium inventory limit, currently set at 350 g, is reached. At this point, ITER will only be able to continue its burning plasma program if technology is available that is capable of rapidly removing large quantities of tritium from the vessel with over 90% efficiency. The removal rate required is four orders of magnitude faster than that demonstrated in current tokamaks. Eighteen years after the observation of co-deposition on JET and TFTR, such technology is nowhere in sight. The inexorable conclusion is that either a major initiative in tritium removal should be funded or that research priorities for ITER should focus on metal alternatives.

Authors:
;
Publication Date:
Research Org.:
Princeton Plasma Physics Lab., Princeton, NJ (US)
Sponsoring Org.:
USDOE Office of Science (SC) (US)
OSTI Identifier:
840424
Report Number(s):
PPPL-4072
TRN: US0502038
DOE Contract Number:  
AC02-76CH03073
Resource Type:
Technical Report
Resource Relation:
Other Information: PBD: 13 May 2005
Country of Publication:
United States
Language:
English
Subject:
70 PLASMA PHYSICS AND FUSION TECHNOLOGY; CARBON; DIVERTORS; EFFICIENCY; PLASMA; PLATES; REMOVAL; RETENTION; TARGETS; TRITIUM; PLASMA-WALL INTERACTION; MATERIALS

Citation Formats

Skinner, C H, and Federici, G. Is Carbon a Realistic Choice for ITER's Divertor?. United States: N. p., 2005. Web. doi:10.2172/840424.
Skinner, C H, & Federici, G. Is Carbon a Realistic Choice for ITER's Divertor?. United States. doi:10.2172/840424.
Skinner, C H, and Federici, G. Fri . "Is Carbon a Realistic Choice for ITER's Divertor?". United States. doi:10.2172/840424. https://www.osti.gov/servlets/purl/840424.
@article{osti_840424,
title = {Is Carbon a Realistic Choice for ITER's Divertor?},
author = {Skinner, C H and Federici, G},
abstractNote = {Tritium retention by co-deposition with carbon on the divertor target plate is predicted to limit ITER's DT burning plasma operations (e.g. to about 100 pulses for the worst conditions) before the in-vessel tritium inventory limit, currently set at 350 g, is reached. At this point, ITER will only be able to continue its burning plasma program if technology is available that is capable of rapidly removing large quantities of tritium from the vessel with over 90% efficiency. The removal rate required is four orders of magnitude faster than that demonstrated in current tokamaks. Eighteen years after the observation of co-deposition on JET and TFTR, such technology is nowhere in sight. The inexorable conclusion is that either a major initiative in tritium removal should be funded or that research priorities for ITER should focus on metal alternatives.},
doi = {10.2172/840424},
journal = {},
number = ,
volume = ,
place = {United States},
year = {2005},
month = {5}
}