D
David A. Petti
Researcher at Idaho National Laboratory
Publications - 107
Citations - 4311
David A. Petti is an academic researcher from Idaho National Laboratory. The author has contributed to research in topics: Nuclear fission product & Advanced Test Reactor. The author has an hindex of 28, co-authored 107 publications receiving 3725 citations.
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Journal ArticleDOI
Handbook of SiC properties for fuel performance modeling
TL;DR: In this paper, a compilation of non-irradiated and irradiated properties of SiC are provided and reviewed and analyzed in terms of application to TRISO fuels, specifically in the high-temperature irradiation regime.
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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.
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Materials challenges for nuclear systems
TL;DR: The Advanced Test Reactor National Scientific User Facility (ATSUF) as mentioned in this paper allows researchers from across the United States to test their ideas for improved fuels and materials, which can be used to improve the safety and economical operation of any nuclear power system.
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The ARIES-AT advanced tokamak, Advanced technology fusion power plant
Farrokh Najmabadi,A. Abdou,Leslie Bromberg,Thomas Brown,V.C. Chan,M.C. Chu,F. Dahlgren,Laila El-Guebaly,P.J. Heitzenroeder,Douglass L. Henderson,H.E. St. John,C.E. Kessel,L. L. Lao,G. R. Longhurst,S. Malang,T. K. Mau,Brad J. Merrill,Ronald L. Miller,E. A. Mogahed,R. L. Moore,T.W. Petrie,David A. Petti,P. A. Politzer,A.R. Raffray,Don Steiner,I.N. Sviatoslavsky,P. Synder,G.M. Syaebler,A. D. Turnbull,Mark S. Tillack,Lester M. Waganer,X. R. Wang,P. West,Paul P. H. Wilson +33 more
TL;DR: The ARIES-AT as discussed by the authors is a simple low-pressure design consisting of SiC composite boxes with a SiC insert for flow distribution that does not carry any structural load.
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Key differences in the fabrication, irradiation and high temperature accident testing of US and German TRISO-coated particle fuel, and their implications on fuel performance
TL;DR: In this paper, the authors examined the TRISO-coated fuel fabrication processes in the US and Germany and the associated irradiation database with a goal of understanding why the German fuel behaves acceptably, why the US fuel has not faired as well, and what process/production parameters impart the reliable performance to this fuel form.