B. L. Doyle
Princeton University
7 Papers
115 Citations
B. L. Doyle is an academic researcher from Princeton University. The author has contributed to research in topics: Fusion power & Tokamak Fusion Test Reactor. The author has an hindex of 6, co-authored 7 publications.
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Papers
Plasma-material interactions in TFTR
H. F. Dylla,Team Tftr Team,M. G. Bell,W. R. Blanchard,P. P. Boody,N. Bretz,Robert Budny,C. E. Bush,Joseph L. Cecchi,Samuel A. Cohen,S.K. Combs,S. L. Davis,B. L. Doyle,P. C. Efthimion,A. C. England,H.P. Eubank,R. J. Fonck,E.D. Fredrickson,L. R. Grisham,Robert James Goldston,B. Grek,R. Groebner,R. J. Hawryluk,D.B. Heifetz,H. W. Hendel,K. W. Hill,S. Hiroe,R. A. Hulse,David W. Johnson,L. C. Johnson,S. J. Kilpatrick,P. H. LaMarche,R. Little,Dennis M. Manos,D. K. Mansfield,Dale Meade,S. S. Medley,S. L. Milora,D. R. Mikkelsen,D. Mueller,M. Murakami,E. Nieschmidt,O. K. Owens,Hyeon K. Park,A.E. Pontau,B. Prichard,A. T. Ramsey,M. H. Redi,J.F. Schivell,G. L. Schmidt,S. D. Scott,S. Sesnic,M. Shimada,J. E. Simpkins,J. Sinnis,F. Stauffer,Brentley Stratton,G. D. Tait,G. Taylor,M. Ulrickson,S. von Goeler,W. R. Wampler,K. Wilson,M. Williams,K. L. Wong,K. M. Young,M. C. Zarnstorff,S. J. Zweben +67 more
TL;DR: In this paper, a summary of plasma-material interactions which influence the operation of TFTR with high current (≤ 2.2 MA) ohmically heated, and high power (∼ 10 MW) neutral-beam heated plasmas is presented.
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Initial limiter and getter operation in TFTR
Joseph L. Cecchi,M. G. Bell,Manfred Bitter,W. R. Blanchard,N. Bretz,C. E. Bush,Samuel A. Cohen,J. Coonrod,S. L. Davis,D. Dimock,B. L. Doyle,H. F. Dylla,P. C. Efthimion,R. J. Fonck,Robert James Goldston,S. von Goeler,B. Grek,D.J. Grove,R. J. Hawryluk,D. Heifetz,H. W. Hendel,K. W. Hill,R. Hulse,J. Isaacson,David W. Johnson,L. C. Johnson,R. Kaita,Stanley Kaye,S. J. Kilpatrick,J. Kiraly,R. J. Knize,R. Little,D. McCarthy,Dennis M. Manos,D. C. McCune,K. McGuire,Dale Meade,S. S. Medley,D. R. Mikkelsen,D. Mueller,M. Murakami,E. Nieschmidt,D. K. Owens,A. T. Ramsey,A. L. Roquemore,N. R. Sauthoff,P. Stangeby,J.F. Schivell,S. D. Scott,S. Sesnic,J. Sinnis,J. Sredniawski,J. D. Strachan,G. D. Tait,George W. Taylor,F. Tenney,C. E. Thomas,J. Timberlake,H. H. Towner,M. Ulrickson,K. M. Young +60 more
TL;DR: In this paper, the movable limiter array, preliminary inner bumper limiter, and prototype ZrAl alloy bulk getter surface pumping system were brought into operation for TFTR.
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Tritium retention and removal on TFTR
D. Mueller,W. R. Blanchard,B. L. Doyle,J.C. Hosea,A. Nagy,G. Pearson,C.H. Skinner,M.A. Ulrickson,William R. Wampler,Stewart Zweben +9 more
- 06 Oct 1997
TL;DR: The Tokamak Fusion Test Reactor, TFTR, is the first fusion facility to afford the opportunity to study the tritium retention and removal over an extended period as mentioned in this paper.
Tritium Removal by CO2 Laser Heating
H. Kugel,D. Mueller,B. L. Doyle,W. R. Wamplerb +3 more
- 01 Jan 1998
TL;DR: In this article, the authors modeled the heat propagation into a surface layer and found that a multi-kW/cm2 flux with a exposure time of order 10 ms is suitable to heat a 50 micron co-deposited layer to 1,OOO- 2,000 degrees.
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Performance of the TFTR moveable limiter tiles
TL;DR: In this article, the movable limiter for the Tokamak Fusion Test Reactor (TFTR) is composed of an Inconel X-750 backing plate covered with titanium carbide coated graphite tiles.
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