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Making tungsten work – ICFRM-14 session T26 paper 501 Nygren et al. making tungsten work

Journal of nuclear materials, 2011-10, Vol.417 (1-3), p.451-456

2011

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High heat flux Langmuir probe array for the DIII-D divertor plates

Review of scientific instruments, 2008-10, Vol.79 (10), p.10F125-10F125-4

2008

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Lithium coatings on NSTX plasma facing components and its effects on boundary control, core plasma performance, and operation

Fusion engineering and design, 2010-11, Vol.85 (6), p.865-873

2010

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Physics design requirements for the National Spherical Torus Experiment liquid lithium divertor

Fusion engineering and design, 2009-06, Vol.84 (7), p.1125-1129

2009

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Preparation of the liquid lithium divertor plates for NSTX

Journal of nuclear materials, 2011-10, Vol.417 (1-3), p.592-596

2011

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Fusion materials science and technology research opportunities now and during the ITER era

Fusion engineering and design, 2014-10, Vol.89 (7-8), p.1579-1585

2014

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High heat flux testing of a helium-cooled tungsten tube with porous foam

Fusion engineering and design, 2007-10, Vol.82 (15), p.1854-1860

2007

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Failure of a lithium-filled target and some implications for fusion components

Fusion engineering and design, 2021-10, Vol.171 (C), p.112664, Article 112664

2021

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Features of plasma sprayed beryllium armor for the ITER first wall

Journal of nuclear materials, 2007-08, Vol.367, p.1325-1329

2007

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The Sandia Plasma Materials Test Facility in 2007

Fusion engineering and design, 2008-12, Vol.83 (7), p.1087-1091

2008

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Thermal modeling of W rod armor

Fusion engineering and design, 2005-11, Vol.75, p.319-323

Nygren, R.E.

2005

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Recent sheath physics studies on DIII-D

Journal of nuclear materials, 2015-08, Vol.463 (C), p.436-439

2015

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Testing of a high temperature radiatively cooled Li/Ta heat pipe in Magnum-PSI

Fusion engineering and design, 2019-09, Vol.146 (PA), p.482-485

2019

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Comparison of heat flux measurement techniques during the DIII-D metal ring campaign

Physica scripta, 2017-12, Vol.T170 (1), p.14007

2017

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Post-test examination of a Li-Ta heat pipe exposed to H plasma in Magnum PSI

Fusion engineering and design, 2019-09, Vol.146, p.2603-2607

2019

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Thermal management of tungsten leading edges in DIII-D

Fusion engineering and design, 2017-11, Vol.124, p.271-275

2017

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A fusion reactor design with a liquid first wall and divertor

Fusion engineering and design, 2004-11, Vol.72 (1), p.181-221

2004

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Actively cooled plasma facing components for long pulse high power operation

Fusion engineering and design, 2002-07, Vol.60 (4), p.547-564

Nygren, R.E.

2002

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Thermal Modeling of the Sandia Flinabe (LiF-BeF2-NaF) Experiments

Fusion science and technology, 2005-04, Vol.47 (3), p.549-553

Nygren, R. E.

2005

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Considerations in testing of ITER first wall mockups

Fusion engineering and design, 2007-10, Vol.82 (15), p.1884-1892

2007

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Effects of ion beam assisted deposition, beam sharing and pivoting in EB-PVD processing of graded thermal barrier coatings

Surface & coatings technology, 2004-01, Vol.177, p.158-164

2004

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Safety assessment of two advanced ferritic steel molten salt blanket design concepts

Fusion engineering and design, 2004-11, Vol.72 (1), p.277-306

2004

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Measurement and modeling of surface temperature dynamics of the NSTX liquid lithium divertor

Journal of nuclear materials, 2013-07, Vol.438, p.S397-S400

2013

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Flow instabilities in refractory metal, porous media, helium-cooled plasma facing components

2015 IEEE 26th Symposium on Fusion Engineering (SOFE), 2015, p.1-6

2015

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Liquid surfaces for fusion plasma facing components—A critical review. Part I: Physics and PSI

Nuclear materials and energy, 2016-12, Vol.9 (C), p.6-21

2016

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Making tungsten work – ICFRM-14 session T26 paper 501 Nygren et al. making tungsten work

High heat flux Langmuir probe array for the DIII-D divertor plates

Lithium coatings on NSTX plasma facing components and its effects on boundary control, core plasma performance, and operation

Physics design requirements for the National Spherical Torus Experiment liquid lithium divertor

Preparation of the liquid lithium divertor plates for NSTX

Fusion materials science and technology research opportunities now and during the ITER era

High heat flux testing of a helium-cooled tungsten tube with porous foam

Failure of a lithium-filled target and some implications for fusion components

Features of plasma sprayed beryllium armor for the ITER first wall

The Sandia Plasma Materials Test Facility in 2007

Thermal modeling of W rod armor

Recent sheath physics studies on DIII-D

Testing of a high temperature radiatively cooled Li/Ta heat pipe in Magnum-PSI

Comparison of heat flux measurement techniques during the DIII-D metal ring campaign

Post-test examination of a Li-Ta heat pipe exposed to H plasma in Magnum PSI

Thermal management of tungsten leading edges in DIII-D

A fusion reactor design with a liquid first wall and divertor

Actively cooled plasma facing components for long pulse high power operation

Thermal Modeling of the Sandia Flinabe (LiF-BeF2-NaF) Experiments

Considerations in testing of ITER first wall mockups

Effects of ion beam assisted deposition, beam sharing and pivoting in EB-PVD processing of graded thermal barrier coatings

Safety assessment of two advanced ferritic steel molten salt blanket design concepts

Measurement and modeling of surface temperature dynamics of the NSTX liquid lithium divertor

Flow instabilities in refractory metal, porous media, helium-cooled plasma facing components

Liquid surfaces for fusion plasma facing components—A critical review. Part I: Physics and PSI

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