'Liquid lithium' presentation slideshows

Development of a new liquid lithium limiter with a re-filling system in HT-7

Development of a new liquid lithium limiter with a re-filling system in HT-7. G. Z. Zuo, J. S. Hu, Z.S, J. G. Li,HT-7 team July 19-20, 2011 Institute of Plasma Physics, Chinese Academy of Sciences, China. HT-7 Data Meeting and Workshop . Hefei, China July 19-20, 2011. Outline. Introduction

1.9k views • 179 slides

Target Developments for the U.S. Rare Isotope Accelerator

Target Developments for the U.S. Rare Isotope Accelerator. Conference on High Power Targetry For Future Accelerators Jerry Nolen Physics Division September 11, 2003. What is RIA?. RIA is a next-generation facility for basic research in nuclear physics

563 views • 42 slides

Target Developments for the U.S. Rare Isotope Accelerator

Target Developments for the U.S. Rare Isotope Accelerator. Conference on High Power Targetry For Future Accelerators Jerry Nolen Physics Division September 11, 2003. What is RIA?. RIA is a next-generation facility for basic research in nuclear physics

426 views • 42 slides

Lithium experiments on HT-7 and EAST tokamak G. Z. Zuo, J. S. Hu, Z.S, J. G. Li, EAST team

Lithium experiments on HT-7 and EAST tokamak G. Z. Zuo, J. S. Hu, Z.S, J. G. Li, EAST team Institute of Plasma Physics, Chinese Academy of Sciences, China D.K. Mansfield, L.E. Zakharov Princeton Plasma Physics Laboratory, Princeton, USA Jan. 23, 2010. Outline. Introduction

353 views • 35 slides

Masayuki Ono NSTX-U Project Director PPPL, Princeton University

NSTX-U. Supported by. Plasma-Wall Boundary Control With Lithium Divertor and Associated Plasma Confinement Improvements in NSTX. Culham Sci Ctr U St. Andrews York U Chubu U Fukui U Hiroshima U Hyogo U Kyoto U Kyushu U Kyushu Tokai U NIFS Niigata U Tsukuba U U Tokyo JAEA

469 views • 29 slides

Masayuki Ono NSTX-U Project Director PPPL, Princeton University

NSTX-U. Supported by. Plasma-Wall Boundary Control With Lithium Divertor and Associated Plasma Confinement Improvements in NSTX. Culham Sci Ctr U St. Andrews York U Chubu U Fukui U Hiroshima U Hyogo U Kyoto U Kyushu U Kyushu Tokai U NIFS Niigata U Tsukuba U U Tokyo JAEA

296 views • 29 slides

NSTX-U

NSTX-U. Supported by. Overview of Strategy for Boundary Physics and Materials/PFC Programs. R. Maingi V.A. Soukhanovskii, M.A. Jaworski, A. Diallo, J.M. Canik, J.E. Menard, for the NSTX Research Team NSTX-U 5 Year Plan Review PPPL, Princeton, NJ 21-23 May 2013. Coll of Wm & Mary

428 views • 28 slides

Masayuki Ono NSTX-U Project Director PPPL, Princeton University

NSTX-U. Supported by. Plasma-wall boundary control with lithium divertor and associated plasma confinement improvements in NSTX ???. Culham Sci Ctr U St. Andrews York U Chubu U Fukui U Hiroshima U Hyogo U Kyoto U Kyushu U Kyushu Tokai U NIFS Niigata U Tsukuba U U Tokyo JAEA

469 views • 24 slides

Masayuki Ono NSTX-U Project Director PPPL, Princeton University

NSTX-U. Supported by. Plasma-wall boundary control with lithium divertor and associated plasma confinement improvements in NSTX ???. Culham Sci Ctr U St. Andrews York U Chubu U Fukui U Hiroshima U Hyogo U Kyoto U Kyushu U Kyushu Tokai U NIFS Niigata U Tsukuba U U Tokyo JAEA

250 views • 24 slides

Comments on FESAC charge #2 (perspective on a flat MFE budget for 10 years

Comments on FESAC charge #2 (perspective on a flat MFE budget for 10 years. S. Prager Princeton Plasma Physics Laboratory In consultation with R. Goldston , H. Neilson, J. Menard, R. Wilson, M. Zarnstorff. An MFE domestic program at flat-funding (~ $260M, excluding GPS, HEDP). Criteria:

306 views • 23 slides

Edge and Scrape-off Layer Diagnostics for the NSTX Liquid Lithium Divertor

NSTX. Supported by. Edge and Scrape-off Layer Diagnostics for the NSTX Liquid Lithium Divertor. College W&M Colorado Sch Mines Columbia U Comp-X General Atomics INEL Johns Hopkins U LANL LLNL Lodestar MIT Nova Photonics New York U Old Dominion U ORNL PPPL PSI Princeton U

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Session VII. Panel Discussion

329 views • 17 slides

Lithiumization of Plasma-Facing components in Next-Gen Fusion reactors

October 7, 2011. Lithiumization of Plasma-Facing components in Next-Gen Fusion reactors. Anupama Khan. Why develop fusion energy?. Fusion energy deployment scenarios match long-term carbon mitigation projections. Fusion Development Plan.

302 views • 17 slides

Lithiumization of Plasma-Facing components in Next-Gen Fusion reactors

October 7, 2011. Lithiumization of Plasma-Facing components in Next-Gen Fusion reactors. Anupama Khan. Why develop fusion energy?. Fusion energy deployment scenarios match long-term carbon mitigation projections. Fusion Development Plan.

286 views • 17 slides

Flowing Liquid Lithium Limiter for HT-7

Flowing Liquid Lithium Limiter for HT-7. Utilizing TEMHD to maintain a clean Li surface, keep it below 400C, and prevent ejection. Conceptual Design. Heat flux. Hot. Li flow. Cooling channels. Inlet. Outlet. Lithium reservoir.

270 views • 15 slides

NSTX Team Meeting

NSTX-U. Supported by. NSTX Team Meeting. Culham Sci Ctr U St. Andrews York U Chubu U Fukui U Hiroshima U Hyogo U Kyoto U Kyushu U Kyushu Tokai U NIFS Niigata U U Tokyo JAEA Hebrew U Ioffe Inst RRC Kurchatov Inst TRINITI NFRI KAIST POSTECH Seoul National U ASIPP

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Some additions to liquid lithium divertor spectroscopy in FY 2010: LADA and DIMS

Some additions to liquid lithium divertor spectroscopy in FY 2010: LADA and DIMS. V. A. Soukhanovskii (LLNL) Acknowledgements: J. Abramson, R. E. Bell, A. L. Roquemore, R. Kaita, H. W. Kugel, G. Tchilinguirian, P. Sichta, G. Zimmer (PPPL), K. Tritz (JHU).

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NSTX-U Collaboration Status and Plans for: Johns Hopkins University

NSTX-U. Supported by. NSTX-U Collaboration Status and Plans for: Johns Hopkins University. Coll of Wm & Mary Columbia U CompX General Atomics FIU INL Johns Hopkins U LANL LLNL Lodestar MIT Lehigh U Nova Photonics ORNL PPPL Princeton U Purdue U SNL Think Tank, Inc. UC Davis

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138 views • 5 slides