Methodology for first wall design

J. D. Galambos; D. L. Conner; P. L. Goranson; D. C. Lousteau; D. E. Williamson; B. E. Nelson; F. C. Davis

Methodology for first wall design

J. D. Galambos, D. L. Conner, P. L. Goranson, D. C. Lousteau, D. E. Williamson, B. E. Nelson, F. C. Davis

Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review

Abstract

An analytic parametric scoping tool has been developed for application to first wall (FW) design problems. Both thermal and disruption force effects are considered. For the high heat flux and high disruption load conditions expected in the International Thermonuclear Experimental Reactor (ITER) device, Vanadium alloy and dispersion-strengthened copper offer the best stress margins using a somewhat flattened plasma-facing configuration. Ferritic steels also appear to have an acceptable stress margin, whereas the conventional stainless steel 316 does not appear feasible. If a full semicircle shape FW is required, only the Vanadium and ferritic steel alloy have acceptable solutions.

Original language	English
Title of host publication	Proceedings - Symposium on Fusion Engineering
Publisher	Publ by IEEE
Pages	1177-1180
Number of pages	4
ISBN (Print)	0780314131
State	Published - 1993
Event	Proceedings of the 15th IEEE/NPSS Symposium on Fusion Engineering. Part 2 (of 2) - Hyannis, MA, USA Duration: Oct 12 1993 → Oct 12 1993

Publication series

Name	Proceedings - Symposium on Fusion Engineering
Volume	2

Conference

Conference	Proceedings of the 15th IEEE/NPSS Symposium on Fusion Engineering. Part 2 (of 2)
City	Hyannis, MA, USA
Period	10/12/93 → 10/12/93

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This output contributes to the following UN Sustainable Development Goals (SDGs)

Cite this

@inproceedings{380377647cf2492fb8d07468af28988a,

title = "Methodology for first wall design",

abstract = "An analytic parametric scoping tool has been developed for application to first wall (FW) design problems. Both thermal and disruption force effects are considered. For the high heat flux and high disruption load conditions expected in the International Thermonuclear Experimental Reactor (ITER) device, Vanadium alloy and dispersion-strengthened copper offer the best stress margins using a somewhat flattened plasma-facing configuration. Ferritic steels also appear to have an acceptable stress margin, whereas the conventional stainless steel 316 does not appear feasible. If a full semicircle shape FW is required, only the Vanadium and ferritic steel alloy have acceptable solutions.",

author = "Galambos, {J. D.} and Conner, {D. L.} and Goranson, {P. L.} and Lousteau, {D. C.} and Williamson, {D. E.} and Nelson, {B. E.} and Davis, {F. C.}",

year = "1993",

language = "English",

isbn = "0780314131",

series = "Proceedings - Symposium on Fusion Engineering",

publisher = "Publ by IEEE",

pages = "1177--1180",

booktitle = "Proceedings - Symposium on Fusion Engineering",

note = "Proceedings of the 15th IEEE/NPSS Symposium on Fusion Engineering. Part 2 (of 2) ; Conference date: 12-10-1993 Through 12-10-1993",

}

Galambos, JD, Conner, DL, Goranson, PL, Lousteau, DC, Williamson, DE, Nelson, BE & Davis, FC 1993, Methodology for first wall design. in Proceedings - Symposium on Fusion Engineering. Proceedings - Symposium on Fusion Engineering, vol. 2, Publ by IEEE, pp. 1177-1180, Proceedings of the 15th IEEE/NPSS Symposium on Fusion Engineering. Part 2 (of 2), Hyannis, MA, USA, 10/12/93.

TY - GEN

T1 - Methodology for first wall design

AU - Galambos, J. D.

AU - Conner, D. L.

AU - Goranson, P. L.

AU - Lousteau, D. C.

AU - Williamson, D. E.

AU - Nelson, B. E.

AU - Davis, F. C.

PY - 1993

Y1 - 1993

N2 - An analytic parametric scoping tool has been developed for application to first wall (FW) design problems. Both thermal and disruption force effects are considered. For the high heat flux and high disruption load conditions expected in the International Thermonuclear Experimental Reactor (ITER) device, Vanadium alloy and dispersion-strengthened copper offer the best stress margins using a somewhat flattened plasma-facing configuration. Ferritic steels also appear to have an acceptable stress margin, whereas the conventional stainless steel 316 does not appear feasible. If a full semicircle shape FW is required, only the Vanadium and ferritic steel alloy have acceptable solutions.

AB - An analytic parametric scoping tool has been developed for application to first wall (FW) design problems. Both thermal and disruption force effects are considered. For the high heat flux and high disruption load conditions expected in the International Thermonuclear Experimental Reactor (ITER) device, Vanadium alloy and dispersion-strengthened copper offer the best stress margins using a somewhat flattened plasma-facing configuration. Ferritic steels also appear to have an acceptable stress margin, whereas the conventional stainless steel 316 does not appear feasible. If a full semicircle shape FW is required, only the Vanadium and ferritic steel alloy have acceptable solutions.

UR - http://www.scopus.com/inward/record.url?scp=0027743964&partnerID=8YFLogxK

M3 - Conference contribution

AN - SCOPUS:0027743964

SN - 0780314131

T3 - Proceedings - Symposium on Fusion Engineering

SP - 1177

EP - 1180

BT - Proceedings - Symposium on Fusion Engineering

PB - Publ by IEEE

T2 - Proceedings of the 15th IEEE/NPSS Symposium on Fusion Engineering. Part 2 (of 2)

Y2 - 12 October 1993 through 12 October 1993

ER -

Methodology for first wall design

Abstract

Publication series

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UN SDGs

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