R
Richard E. Nygren
Researcher at Sandia National Laboratories
Publications - 97
Citations - 2381
Richard E. Nygren is an academic researcher from Sandia National Laboratories. The author has contributed to research in topics: Divertor & Heat flux. The author has an hindex of 23, co-authored 97 publications receiving 2156 citations.
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Journal ArticleDOI
On the exploration of innovative concepts for fusion chamber technology
Mohamed A. Abdou,Alice Ying,Neil B. Morley,K. Gulec,Sergey Smolentsev,Mike Kotschenreuther,S. Malang,Steven J. Zinkle,T.D. Rognlien,P.J. Fogarty,B.E. Nelson,Richard E. Nygren,K. McCarthy,Mahmoud Z. Youssef,Nasr M. Ghoniem,D.K. Sze,C.P.C. Wong,Mohamed E. Sawan,H.Y. Khater,R. Woolley,Richard F. Mattas,Ralph W. Moir,Shahram Sharafat,Jeffrey N. Brooks,Ahmed Hassanein,David A. Petti,Mark S. Tillack,M.A. Ulrickson,Tetsuya Uchimoto +28 more
TL;DR: In this paper, the authors explored novel concepts for fusion chamber technology that can substantially improve the attractiveness of fusion energy systems, including the potential for: (1) high power density capability; (2) higher plasma β and stable physics regimes if liquid metals are used; (3) increased disruption survivability; (4) reduced volume of radioactive waste; (5) reduced radiation damage in structural materials; and (6) higher availability.
Journal ArticleDOI
High heat flux components—Readiness to proceed from near term fusion systems to power plants
A.R. Raffray,Richard E. Nygren,D.G. Whyte,Said I. Abdel-Khalik,R.P. Doerner,Frederic Escourbiac,Todd Evans,Robert James Goldston,David T. Hoelzer,Satoshi Konishi,P. Lorenzetto,Mario Merola,R. Neu,Prachai Norajitra,R.A. Pitts,Michael Rieth,M. Roedig,T.D. Rognlien,Sadaaki Suzuki,Mark S. Tillack,C.P.C. Wong +20 more
TL;DR: In this article, the authors focus on the gap between near-term and long-term concepts for high heat flux components (HHFC), and in particular for divertors, with the aim of characterizing the international status of current HHFC design concepts.
Journal ArticleDOI
Physics conclusions in support of ITER W divertor monoblock shaping
R.A. Pitts,S. Bardin,B. Bazylev,M.A. van den Berg,P. Bunting,S. Carpentier-Chouchana,J. W. Coenen,Yann Corre,R. Dejarnac,Frederic Escourbiac,Jonathan Gaspar,James Paul Gunn,T. Hirai,S-H. Hong,J. Horacek,D. Iglesias,Matthias Komm,K. Krieger,C.J. Lasnier,G. F. Matthews,Thomas Morgan,S. Panayotis,S. Pestchanyi,A. Podolnik,Richard E. Nygren,Dmitry Rudakov,G. De Temmerman,Petr Vondracek,J.G. Watkins +28 more
TL;DR: In this article, the effect of edge power loading on the shape of the ITER divertor was investigated, and it was concluded that the geometrical approximation for leading edge power load on radially misaligned poloidal leading edges is indeed valid.
Journal ArticleDOI
Liquid surfaces for fusion plasma facing components—A critical review. Part I: Physics and PSI
TL;DR: A review of the potential of robust PFCs with liquid surfaces for applications in future D/T fusion device summarizes the critical issues for liquid surfaces and research being done worldwide in confinement facilities, and supporting R&D in plasma surface interactions as mentioned in this paper.
Journal ArticleDOI
ADX: a high field, high power density, advanced divertor and RF tokamak
Brian LaBombard,Earl Marmar,J. H. Irby,J.L. Terry,R.F. Vieira,Gregory Wallace,D.G. Whyte,S.M. Wolfe,S.J. Wukitch,Seung Gyou Baek,W. Beck,P.T. Bonoli,Dan Brunner,J. Doody,Robert Ellis,D.R. Ernst,C.L. Fiore,Jeffrey P. Freidberg,Theodore Golfinopoulos,Robert Granetz,Martin Greenwald,Z.S. Hartwig,Amanda Hubbard,J. W. Hughes,Ian H. Hutchinson,C.E. Kessel,Mike Kotschenreuther,R. Leccacorvi,Yu-Ming Lin,Bruce Lipschultz,Swadesh M Mahajan,Joseph Minervini,Robert Mumgaard,Richard E. Nygren,R.R. Parker,Francesca Poli,Miklos Porkolab,Matthew Reinke,J. E. Rice,T.D. Rognlien,W. L. Rowan,S. Shiraiwa,D. Terry,Christian Theiler,Peter Titus,Maxim Umansky,Prashant M Valanju,J.R. Walk,Anne White,James R. Wilson,G.M. Wright,Stewart Zweben +51 more
TL;DR: The Advanced Divertor and RF tokamak eXperiment (ADX) as discussed by the authors is designed to address critical gaps in the world fusion research programme on the pathway to next-step devices: fusion nuclear science facility (FNSF), fusion pilot plant (FPP) and/or demonstration power plant (DEMO).