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Actively cooled plasma facing components for long pulse high power operationNYGREN, R. E.Fusion engineering and design. 2002, Vol 60, Num 4, pp 547-564, issn 0920-3796Article

High heat flux testing of a helium-cooled tungsten tube with porous foamYOUCHISON, D. L; LUTZ; WILLIAMS, B et al.Fusion engineering and design. 2007, Vol 82, Num 15-24, pp 1854-1860, issn 0920-3796, 7 p.Conference Paper

Brazing of the Tore Supra actively-cooled Phase III limiterNYGREN, R. E; WALKER, C. A; LUTZ, T. J et al.Journal of nuclear materials. 1994, Vol 212-15, Num B, pp 1621-1626, issn 0022-3115Conference Paper

Radiation-enhanced sublimation experiments using the sandia high-heat-flux test facilityHAASZ, A. A; DAVIS, J. W; CROESSMANN, C. D et al.Journal of nuclear materials. 1990, Vol 173, Num 1, pp 108-111, issn 0022-3115, 4 p.Article

How braze flaws affect the thermal-hydraulic performance of the Tore Supra phase-III outboard pump limiter : A case study of the effects of nonuniform thermal resistance on the peak heat flux to the coolant for tubes with one-sided heating : Special section : Thermal hydraulicsNYGREN, R. E; MILLER, J. D.Fusion technology. 1996, Vol 29, Num 4, pp 529-544, issn 0748-1896Article

The Sandia Plasma Materials Test Facility in 2007MCDONALD, J. M; LUTZ, T. J; YOUCHISON, D. L et al.Fusion engineering and design. 2008, Vol 83, Num 7-9, pp 1087-1091, issn 0920-3796, 5 p.Conference Paper

Safety assessment of two advanced ferritic steel molten salt blanket design conceptsMERRILL, B. J; SAWAN, M; WONG, C. P. C et al.Fusion engineering and design. 2004, Vol 72, Num 1-3, pp 277-306, issn 0920-3796, 30 p.Article

High heat flux tests on heat sinks armored with tungsten rodsNYGREN, R. E; YOUCHISON, D. L; WATSON, R. D et al.Fusion engineering and design. 2000, Vol 49-50, pp 303-308, issn 0920-3796Conference Paper

Lithium coatings on NSTX plasma facing components and its effects on boundary control, core plasma performance, and operationKUGEL, H. W; BELL, M. G; NYGREN, R. E et al.Fusion engineering and design. 2010, Vol 85, Num 6, pp 865-873, issn 0920-3796, 9 p.Conference Paper

Helium-cooled refractory alloys first wall and blanket evaluationWONG, C. P. C; NYGREN, R. E; SHARAFAT, S et al.Fusion engineering and design. 2000, Vol 49-50, pp 709-717, issn 0920-3796Conference Paper

Low energy data on radiation enhanced sublimation of graphiteNYGREN, R. E; BOHDANSKY, J; POSPIESZCZYK, A et al.Journal of nuclear materials. 1990, Vol 176-77, pp 445-449, issn 0022-3115, 5 p.Conference Paper

In situ spectroscopic measurements of erosion behavior of Tokamak Fusion Test Reactor-redeposited carbon materials under high-flux plasma bombardment in PISCES-A (Plasma Interactive Surface Component Experimental Station-A)HIROOKA, Y; POSPIESZCZYK, A; CONN, R. W et al.Journal of vacuum science and technology. A. Vacuum, surfaces, and films. 1989, Vol 7, Num 5, pp 2935-2942, issn 0734-2101, 8 p.Article

Making tungsten work - ICFRM-14 session T26 paper 501 Nygren et al. making tungsten workNYGREN, R. E; RAFFRAY, R; WHYTE, D et al.Journal of nuclear materials. 2011, Vol 417, Num 1-3, pp 451-456, issn 0022-3115, 6 p.Conference Paper

ITER first wall module 18- : The US effortNYGREN, R. E; ULRICKSON, M. A; TANAKA, T. J et al.Fusion engineering and design. 2006, Vol 81, Num 1-7, pp 387-392, issn 0920-3796, 6 p.Conference Paper

Liquid metal integrated test system (LIMITS)TANAKA, T. J; BAUER, F. J; LUTZ, T. J et al.Fusion engineering and design. 2004, Vol 72, Num 1-3, pp 83-92, issn 0920-3796, 10 p.Article

Design integration of liquid surface divertorsNYGREN, R. E; COWGILL, D. F; ULRICKSON, M. A et al.Fusion engineering and design. 2004, Vol 72, Num 1-3, pp 223-244, issn 0920-3796, 22 p.Article

Summary of results from the TEXTOR helium self-pumping experimentBROOKS, J. N; KRAUSS, A; NYGREN, R. E et al.Journal of nuclear materials. 1992, Vol 196-98, pp 664-669, issn 0022-3115Conference Paper

Measurement of the melting point temperature of several lithium-sodium-beryllium fluoride salt (flinabe) mixturesMCDONALD, J. M; NYGREN, R. E; LUTZ, T. J et al.Fusion science and technology. 2005, Vol 47, Num 3, pp 554-558, 5 p.Conference Paper

Thermal modeling of W rod armorNYGREN, R. E.Fusion engineering and design. 2005, Vol 75-79, pp 319-323, issn 0920-3796, 5 p.Conference Paper

Effects of ion beam assisted deposition, beam sharing and pivoting in EB-PVD processing of graded thermal barrier coatingsYOUCHISON, D. L; GALLIS, M. A; NYGREN, R. E et al.Surface & coatings technology. 2004, Vol 177-78, pp 158-164, issn 0257-8972, 7 p.Conference Paper

A fusion reactor design with a liquid first wall and divertorNYGREN, R. E; ROGNLIEN, T. D; SZE, D. K et al.Fusion engineering and design. 2004, Vol 72, Num 1-3, pp 181-221, issn 0920-3796, 41 p.Article

Assessing braze quality in the actively cooled Tore Supra phase III outboard pump limiterNYGREN, R. E; LUTZ, T. L; MILLER, J. D et al.Fusion engineering and design. 1995, Vol 28, pp 113-118, issn 0920-3796Conference Paper

High quality actively cooled plasma-facing components for fusionNYGREN, R. E.Fusion engineering and design. 1995, Vol 28, pp 3-12, issn 0920-3796Conference Paper

The TEXTOR helium self-pumping experiment : design, plans, and supporting ion-beam data on helium retention in nickelBROOKS, J. N; NYGREN, R. E; WALSH, D et al.Journal of nuclear materials. 1990, Vol 176-77, pp 635-639, issn 0022-3115, 5 p.Conference Paper

Preparation of the liquid lithium divertor plates for NSTXNYGREN, R. E; MCKEE, G. R; FORDHAM, J. A et al.Journal of nuclear materials. 2011, Vol 417, Num 1-3, pp 592-596, issn 0022-3115, 5 p.Conference Paper

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