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Title: Implications of PMI and wall material choice on fusion reactor tritium self-sufficiency

Abstract

Tritium self-sufficiency is a critical issue for the production of nuclear fusion energy. Here we quantify the impact of co-deposition of eroded wall material and fuel on the tritium particle balance in a hypothetical reactor system. The expected ITER plasma parameters and geometry are used to estimate the amount of eroded material from a full tungsten, beryllium or carbon device. Measured D concentrations in co-deposits are extrapolated to the wall temperature expected in future reactors and used along with these eroded flux estimates to determine the net loss probability of tritium from the device due to co-deposition. The use of liquid divertor surfaces is also considered with the amount of tritium residing in the recirculating liquid estimated. The general conclusion, from a tritium self-sufficiency viewpoint, is that one should avoid low-Z materials that readily form hydrogen bonds, in favor of high-Z non-hydride forming materials.

Authors:
; ;
Publication Date:
Research Org.:
Univ. of California, San Diego, CA (United States)
Sponsoring Org.:
USDOE Office of Science (SC)
OSTI Identifier:
1494198
Alternate Identifier(s):
OSTI ID: 1609930
Grant/Contract Number:  
FG02-07ER54912
Resource Type:
Published Article
Journal Name:
Nuclear Materials and Energy
Additional Journal Information:
Journal Name: Nuclear Materials and Energy Journal Volume: 18 Journal Issue: C; Journal ID: ISSN 2352-1791
Publisher:
Elsevier
Country of Publication:
Netherlands
Language:
English
Subject:
70 PLASMA PHYSICS AND FUSION TECHNOLOGY; Nuclear Science & Technology; Plasma-material interactions; Co-deposition; Tritium; Self-sufficiency

Citation Formats

Doerner, R. P., Tynan, G. R., and Schmid, K. Implications of PMI and wall material choice on fusion reactor tritium self-sufficiency. Netherlands: N. p., 2018. Web. doi:10.1016/j.nme.2018.12.006.
Doerner, R. P., Tynan, G. R., & Schmid, K. Implications of PMI and wall material choice on fusion reactor tritium self-sufficiency. Netherlands. doi:https://doi.org/10.1016/j.nme.2018.12.006
Doerner, R. P., Tynan, G. R., and Schmid, K. Tue . "Implications of PMI and wall material choice on fusion reactor tritium self-sufficiency". Netherlands. doi:https://doi.org/10.1016/j.nme.2018.12.006.
@article{osti_1494198,
title = {Implications of PMI and wall material choice on fusion reactor tritium self-sufficiency},
author = {Doerner, R. P. and Tynan, G. R. and Schmid, K.},
abstractNote = {Tritium self-sufficiency is a critical issue for the production of nuclear fusion energy. Here we quantify the impact of co-deposition of eroded wall material and fuel on the tritium particle balance in a hypothetical reactor system. The expected ITER plasma parameters and geometry are used to estimate the amount of eroded material from a full tungsten, beryllium or carbon device. Measured D concentrations in co-deposits are extrapolated to the wall temperature expected in future reactors and used along with these eroded flux estimates to determine the net loss probability of tritium from the device due to co-deposition. The use of liquid divertor surfaces is also considered with the amount of tritium residing in the recirculating liquid estimated. The general conclusion, from a tritium self-sufficiency viewpoint, is that one should avoid low-Z materials that readily form hydrogen bonds, in favor of high-Z non-hydride forming materials.},
doi = {10.1016/j.nme.2018.12.006},
journal = {Nuclear Materials and Energy},
number = C,
volume = 18,
place = {Netherlands},
year = {2018},
month = {12}
}

Journal Article:
Free Publicly Available Full Text
Publisher's Version of Record
DOI: https://doi.org/10.1016/j.nme.2018.12.006

Citation Metrics:
Cited by: 1 work
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