Overview of the fusion nuclear science facility, a credible break-in step on the path to fusion energy

Kessel, Charles E.; Blanchard, James P.; Davis, Andrew O.; El-Guebaly, Laila A.; Garrison, Lauren M.; Ghoniem, Nasr M.; Humrickhouse, Paul W.; Huang, Yue; Katoh, Yutai; Khodak, Andrei E.; Marriott, Edward P.; Malang, Siegfried; Morley, Neil B.; Neilson, George Hutch; Rapp, Juergen; Rensink, Marvin E.; Rognlien, T. D.; Rowcliffe, Arthur F.; Smolentsev, Sergey S.; Snead, Lance L.; Tillack, Mark S.; Titus, Peter H.; Waganer, Lester M.; Wallace, Gregory M.; Wukitch, Stephen J.; Ying, Alice Y.; Young, Kenneth M.; Zhai, Yuhu

doi:10.1016/j.fusengdes.2017.05.081

Title: Overview of the fusion nuclear science facility, a credible break-in step on the path to fusion energy

Abstract

Here the Fusion Nuclear Science Facility (FNSF) is examined as part of a two step program from ITER to commercial power plants. This first step is considered mandatory to establish the materials and component database in the real fusion in-service environment before proceeding to larger electricity producing facilities. The FNSF can be shown to make tremendous advances beyond ITER, toward a power plant, particularly in plasma duration and fusion nuclear environment. A moderate FNSF is studied in detail, which does not generate net electricity, but does reach the power plant blanket operating temperatures. The full poloidal Dual Coolant Lead Lithium (DCLL) blanket is chosen, with alternates being the Helium Cooled Lead Lithium (HCLL) and Helium Cooled Ceramic Breeder/Pebble Bed (HCCB/PB). Several power plant relevant choices are made in order to follow the philosophy of targeted technologies. Any fusion core component must be qualified by fusion relevant neutron testing and highly integrated non-nuclear testing before it can be installed on the FNSF in order to avoid the high probability of constant failures in a plasma-vacuum system. A range of missions for the FNSF, or any fusion nuclear facility on the path toward fusion power plants, are established and characterized by severalmore »« less

Authors:

Kessel, Charles E. ^[1]; Blanchard, James P. ^[2];

^[2]; El-Guebaly, Laila A. ^[2]; Garrison, Lauren M. ^[3]; Ghoniem, Nasr M. ^[4];

^[5]; Huang, Yue ^[4];

^[3]; Khodak, Andrei E. ^[1]; Marriott, Edward P. ^[2]; Malang, Siegfried ^[6]; Morley, Neil B. ^[4]; Neilson, George Hutch ^[1];

^[3]; Rensink, Marvin E. ^[7];

^[7]; Rowcliffe, Arthur F. ^[3]; Smolentsev, Sergey S. ^[4]; Snead, Lance L. ^[8] more »

Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)
Univ. of Wisconsin, Madison, WI (United States)
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Univ. of California, Los Angeles, CA (United States)
Idaho National Lab. (INL), Idaho Falls, ID (United States)
Fusion Nuclear Technology Consulting, Linkenheim-Hochstetten (Germany)
Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
Massachusetts Inst. of Technology (MIT), Cambridge, MA (United States)
Univ. of California, San Diego, La Jolla, CA (United States)
Consultant, O'Fallen, MO (United States)

Publication Date:: Wed May 31 00:00:00 EDT 2017

Research Org.:: Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

Sponsoring Org.:: USDOE National Nuclear Security Administration (NNSA)

OSTI Identifier:: 1874543

Report Number(s):: LLNL-JRNL-836543
Journal ID: ISSN 0920-3796; 1055949; TRN: US2307126

Grant/Contract Number:: AC52-07NA27344; AC02-09CH11466; FG02-86ER52123; FC02-99ER54512; AC05-00OR22725; FG02-98ER54462

Resource Type:: Accepted Manuscript

Journal Name:: Fusion Engineering and Design

Additional Journal Information:: Journal Volume: 135; Journal ID: ISSN 0920-3796

Publisher:: Elsevier

Country of Publication:: United States

Language:: English

Subject:: 70 PLASMA PHYSICS AND FUSION TECHNOLOGY; fusion; nuclear; plasma; blanket; divertor; systems

Citation Formats


                    Kessel, Charles E., Blanchard, James P., Davis, Andrew O., El-Guebaly, Laila A., Garrison, Lauren M., Ghoniem, Nasr M., Humrickhouse, Paul W., Huang, Yue, Katoh, Yutai, Khodak, Andrei E., Marriott, Edward P., Malang, Siegfried, Morley, Neil B., Neilson, George Hutch, Rapp, Juergen, Rensink, Marvin E., Rognlien, T. D., Rowcliffe, Arthur F., Smolentsev, Sergey S., Snead, Lance L., Tillack, Mark S., Titus, Peter H., Waganer, Lester M., Wallace, Gregory M., Wukitch, Stephen J., Ying, Alice Y., Young, Kenneth M., and Zhai, Yuhu. Overview of the fusion nuclear science facility, a credible break-in step on the path to fusion energy.  United States: N. p., 2017. 
Web.  doi:10.1016/j.fusengdes.2017.05.081.

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                    Kessel, Charles E., Blanchard, James P., Davis, Andrew O., El-Guebaly, Laila A., Garrison, Lauren M., Ghoniem, Nasr M., Humrickhouse, Paul W., Huang, Yue, Katoh, Yutai, Khodak, Andrei E., Marriott, Edward P., Malang, Siegfried, Morley, Neil B., Neilson, George Hutch, Rapp, Juergen, Rensink, Marvin E., Rognlien, T. D., Rowcliffe, Arthur F., Smolentsev, Sergey S., Snead, Lance L., Tillack, Mark S., Titus, Peter H., Waganer, Lester M., Wallace, Gregory M., Wukitch, Stephen J., Ying, Alice Y., Young, Kenneth M., & Zhai, Yuhu. Overview of the fusion nuclear science facility, a credible break-in step on the path to fusion energy.  United States.  https://doi.org/10.1016/j.fusengdes.2017.05.081

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                    Kessel, Charles E., Blanchard, James P., Davis, Andrew O., El-Guebaly, Laila A., Garrison, Lauren M., Ghoniem, Nasr M., Humrickhouse, Paul W., Huang, Yue, Katoh, Yutai, Khodak, Andrei E., Marriott, Edward P., Malang, Siegfried, Morley, Neil B., Neilson, George Hutch, Rapp, Juergen, Rensink, Marvin E., Rognlien, T. D., Rowcliffe, Arthur F., Smolentsev, Sergey S., Snead, Lance L., Tillack, Mark S., Titus, Peter H., Waganer, Lester M., Wallace, Gregory M., Wukitch, Stephen J., Ying, Alice Y., Young, Kenneth M., and Zhai, Yuhu. Wed .  
"Overview of the fusion nuclear science facility, a credible break-in step on the path to fusion energy".  United States.  https://doi.org/10.1016/j.fusengdes.2017.05.081.  https://www.osti.gov/servlets/purl/1874543.

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@article{osti_1874543,

  title        = {Overview of the fusion nuclear science facility, a credible break-in step on the path to fusion energy},

  author       = {Kessel, Charles E. and Blanchard, James P. and Davis, Andrew O. and El-Guebaly, Laila A. and Garrison, Lauren M. and Ghoniem, Nasr M. and Humrickhouse, Paul W. and Huang, Yue and Katoh, Yutai and Khodak, Andrei E. and Marriott, Edward P. and Malang, Siegfried and Morley, Neil B. and Neilson, George Hutch and Rapp, Juergen and Rensink, Marvin E. and Rognlien, T. D. and Rowcliffe, Arthur F. and Smolentsev, Sergey S. and Snead, Lance L. and Tillack, Mark S. and Titus, Peter H. and Waganer, Lester M. and Wallace, Gregory M. and Wukitch, Stephen J. and Ying, Alice Y. and Young, Kenneth M. and Zhai, Yuhu},

  abstractNote = {Here the Fusion Nuclear Science Facility (FNSF) is examined as part of a two step program from ITER to commercial power plants. This first step is considered mandatory to establish the materials and component database in the real fusion in-service environment before proceeding to larger electricity producing facilities. The FNSF can be shown to make tremendous advances beyond ITER, toward a power plant, particularly in plasma duration and fusion nuclear environment. A moderate FNSF is studied in detail, which does not generate net electricity, but does reach the power plant blanket operating temperatures. The full poloidal Dual Coolant Lead Lithium (DCLL) blanket is chosen, with alternates being the Helium Cooled Lead Lithium (HCLL) and Helium Cooled Ceramic Breeder/Pebble Bed (HCCB/PB). Several power plant relevant choices are made in order to follow the philosophy of targeted technologies. Any fusion core component must be qualified by fusion relevant neutron testing and highly integrated non-nuclear testing before it can be installed on the FNSF in order to avoid the high probability of constant failures in a plasma-vacuum system. A range of missions for the FNSF, or any fusion nuclear facility on the path toward fusion power plants, are established and characterized by several metrics. A conservative physics strategy is pursued to accommodate the transition to ultra-long plasma pulses, and parameters are chosen to represent the power plant regime to the extent possible. An operating space is identified, and from this, one point is chosen for further detailed analysis, with R = 4.8 m, a = 1.2 m, IP = 7.9 MA, BT = 7.5 T, βN < 2.7, n/nGr = 0.9, fBS = 0.52, q95 = 6.0, H98 ~1.0, and Q = 4.0. The operating space is shown to be robust to parameter variations. A program is established for the FNSF to show how the missions for the facility are met, with a He/H, a DD and 5 DT phases. The facility requires ~25 years to complete its DT operation, including 7.8 years of neutron production, and the remaining spent on inspections and maintenance. The DD phase is critical to establish the ultra-long plasma pulse lengths. The blanket testing strategy is examined, and shows that many sectors have penetrations for heating and current drive (H/CD), diagnostics, or Test Blanket Modules (TBMs). The hot cell is a critical facility element in order for the FNSF to perform its function of developing the in-service material and component database. The pre-FNSF R&D is laid out in terms of priority topics, with the FNSF phases driving the time-lines for R&D completion. A series of detailed technical assessments of the FNSF operating point are reported in this issue, showing the credibility of such a step, and more detailed emphasis on R&D items to pursue. These include nuclear analysis, thermo-mechanics and thermal-hydraulics, liquid metal thermal hydraulics, transient thermo-mechanics, tritium analysis, maintenance assessment, magnet specification and analysis, materials assessments, core and scrape-off layer (SOL)/divertor plasma examinations.},

  doi          = {10.1016/j.fusengdes.2017.05.081},

  journal      = {Fusion Engineering and Design},

  number       = ,

  volume       = 135,

  place        = {United States},

  year         = {Wed May 31 00:00:00 EDT 2017},

  month        = {Wed May 31 00:00:00 EDT 2017}

}

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Kessel, C. E.; Tillack, M. S.; Najmabadi, F.
Fusion Science and Technology, Vol. 67, Issue 1
DOI: 10.13182/FST14-794

Recent US activities on advanced He-cooled W-alloy divertor concepts for fusion power plants
journal, January 2011

Tillack, M. S.; Raffray, A. R.; Wang, X. R.
Fusion Engineering and Design, Vol. 86, Issue 1
DOI: 10.1016/j.fusengdes.2010.08.015

An example pathway to a fusion power plant system based on lead–lithium breeder: Comparison of the dual-coolant lead–lithium (DCLL) blanket with the helium-cooled lead–lithium (HCLL) concept as initial step
journal, December 2009

Malang, S.; Raffray, A. R.; Morley, N. B.
Fusion Engineering and Design, Vol. 84, Issue 12
DOI: 10.1016/j.fusengdes.2009.02.049

Tritium aspects of the fusion nuclear science facility
journal, October 2018

Humrickhouse, Paul W.; Merrill, Brad J.
Fusion Engineering and Design, Vol. 135
DOI: 10.1016/j.fusengdes.2017.04.099

Physics Basis for a Conservative Physics and Conservative Technology Tokamak Power Plant: ARIES-ACT2
journal, January 2015

Kessel, C. E.; Poli, F. M.
Fusion Science and Technology, Vol. 67, Issue 1
DOI: 10.13182/FST14-793

Core plasma physics basis and its impacts on the FNSF
journal, October 2018

Kessel, C. E.; Batchelor, D. B.; Bonoli, P. T.
Fusion Engineering and Design, Vol. 135
DOI: 10.1016/j.fusengdes.2017.06.003

Physics Basis for an Advanced Physics and Advanced Technology Tokamak Power Plant Configuration: ARIES-ACT1
journal, January 2015

Kessel, C. E.; Poli, F. M.; Ghantous, K.
Fusion Science and Technology, Vol. 67, Issue 1
DOI: 10.13182/FST14-795

Fusion nuclear science facilities and pilot plants based on the spherical tokamak
journal, August 2016

Menard, J. E.; Brown, T.; El-Guebaly, L.
Nuclear Fusion, Vol. 56, Issue 10
DOI: 10.1088/0029-5515/56/10/106023

The ARIES-CS Compact Stellarator Fusion Power Plant
journal, October 2008

Najmabadi, F.; Raffray, A. R.; Abdel-Khalik, S. I.
Fusion Science and Technology, Vol. 54, Issue 3
DOI: 10.13182/FST54-655

HTS Wind Power Generator: Electromagnetic Force Between No-Insulation and Insulation Coils Under Time-Varying Conditions
journal, June 2014

Song, Jung-Bin; Hahn, Seungyong; Kim, Youngjae
IEEE Transactions on Applied Superconductivity, Vol. 24, Issue 3
DOI: 10.1109/TASC.2013.2285725

ITER safety and licensing update
journal, August 2012

Taylor, Neill; Ciattaglia, Sergio; Cortes, Pierre
Fusion Engineering and Design, Vol. 87, Issue 5-6
DOI: 10.1016/j.fusengdes.2012.01.001

Overview of JT-60U results towards the establishment of advanced tokamak operation
journal, September 2009

Oyama, N.
Nuclear Fusion, Vol. 49, Issue 10
DOI: 10.1088/0029-5515/49/10/104007

Experimental and Numerical Investigation of Prototypical Multi-Jet Impingement (HEMJ) Helium-Cooled Divertor Modules
journal, July 2009

Crosatti, L.; Weathers, J. B.; Sadowski, D. L.
Fusion Science and Technology, Vol. 56, Issue 1
DOI: 10.13182/FST09-30

He-cooled divertor for DEMO: Status of development and HHF tests
journal, December 2010

Norajitra, Prachai; Giniyatulin, Radmir; Kuznetsov, Vladimir
Fusion Engineering and Design, Vol. 85, Issue 10-12
DOI: 10.1016/j.fusengdes.2010.09.006

Plasma vertical control with internal and external coils in next step tokamaks
journal, July 2001

Kessel, C. E.; Heitzenroeder, P.; Jun, C.
Nuclear Fusion, Vol. 41, Issue 7
DOI: 10.1088/0029-5515/41/7/316

Fusion Nuclear Science Facility Candidates
journal, February 2011

Stambaugh, R. D.; Chan, V. S.; Garofalo, A. M.
Fusion Science and Technology, Vol. 59, Issue 2
DOI: 10.13182/FST59-279

ELM-averaged power exhaust on JET
journal, August 2005

Fundamenski, W.; Pitts, R. A.; Matthews, G. F.
Nuclear Fusion, Vol. 45, Issue 8
DOI: 10.1088/0029-5515/45/8/024

Aspect ratio scaling of ideal no-wall stability limits in high bootstrap fraction tokamak plasmas
journal, February 2004

Menard, J. E.; Bell, M. G.; Bell, R. E.
Physics of Plasmas, Vol. 11, Issue 2
DOI: 10.1063/1.1640623

Scaling of the tokamak near the scrape-off layer H-mode power width and implications for ITER
journal, August 2013

Eich, T.; Leonard, A. W.; Pitts, R. A.
Nuclear Fusion, Vol. 53, Issue 9
DOI: 10.1088/0029-5515/53/9/093031

Magnetic drift kinetic damping of the resistive wall mode in large aspect ratio tokamaks
journal, September 2008

Liu, Yueqiang; Chu, M. S.; Gimblett, C. G.
Physics of Plasmas, Vol. 15, Issue 9
DOI: 10.1063/1.2978091

Radiation Effects on Superconducting Fusion Magnet Components
journal, June 2011

Weber, Harald W.
International Journal of Modern Physics E, Vol. 20, Issue 06
DOI: 10.1142/S0218301311018526

Gas-cooled high performance divertor for a power plant
journal, November 2002

Hermsmeyer, S.; Malang, S.
Fusion Engineering and Design, Vol. 61-62
DOI: 10.1016/S0920-3796(02)00174-6

The effect of divertor magnetic balance on H-mode performance in DIII-D
journal, March 2001

Petrie, T. W.; Greenfield, C. M.; Grobener, R. J.
Journal of Nuclear Materials, Vol. 290-293
DOI: 10.1016/S0022-3115(00)00492-X

Conceptual magnet design study for fusion nuclear science facility
journal, October 2018

Zhai, Yuhu; Titus, Peter; Kessel, Charles
Fusion Engineering and Design, Vol. 135
DOI: 10.1016/j.fusengdes.2017.06.028

Spherical torus concept as power plants—the ARIES-ST study
journal, February 2003

Najmabadi, F.
Fusion Engineering and Design, Vol. 65, Issue 2
DOI: 10.1016/S0920-3796(02)00302-2

Heating and current drive actuators study for FNSF in the ion cyclotron and lower hybrid range of frequency
journal, October 2018

Wallace, G. M.; Bonoli, P. T.; Wukitch, S. J.
Fusion Engineering and Design, Vol. 135
DOI: 10.1016/j.fusengdes.2017.06.025

Tungsten monoblock concepts for the Fusion Nuclear Science Facility (FNSF) first wall and divertor
journal, October 2018

Huang, Y.; Tillack, M. S.; Ghoniem, N. M.
Fusion Engineering and Design, Vol. 135
DOI: 10.1016/j.fusengdes.2017.06.026

Works referencing / citing this record:

Investigation of light ion fusion reactions with plasma discharges
journal, November 2019

Schenkel, T.; Persaud, A.; Wang, H.
Journal of Applied Physics, Vol. 126, Issue 20
DOI: 10.1063/1.5109445

Thermal and Electromagnetic Transients in Liquid Metal Surfaces of the FNSF
journal, May 2019

Blanchard, James; Martin, Carl
Fusion Science and Technology, Vol. 75, Issue 8
DOI: 10.1080/15361055.2019.1602399

Critical Exploration of Liquid Metal Plasma-Facing Components in a Fusion Nuclear Science Facility
journal, June 2019

Kessel, C. E.; Andruczyk, D.; Blanchard, J. P.
Fusion Science and Technology, Vol. 75, Issue 8
DOI: 10.1080/15361055.2019.1610685

Design and Analysis of the Liquid Metal Free-Surface Divertor Cooling System
journal, November 2019

Khodak, A.; Kessel, C.; Tillack, M.
Fusion Science and Technology, Vol. 75, Issue 8
DOI: 10.1080/15361055.2019.1643689

Theoretical analysis of key factors achieving reversed magnetic shear q -profiles sustained with lower hybrid waves on EAST
journal, February 2019

Zhai, X. M.; Xiang, N.; Chen, J. L.
Plasma Physics and Controlled Fusion, Vol. 61, Issue 4
DOI: 10.1088/1361-6587/aaffe5

Potential Impacts of Liquid-Metal Plasma-Facing Components on Heating and Current Drive Actuators for a Fusion Nuclear Science Facility
journal, July 2019

Wallace, G. M.; Kessel, C. E.; Hosea, J.
Fusion Science and Technology, Vol. 76, Issue 1
DOI: 10.1080/15361055.2019.1629253

Insights into fuel start‐up and self‐sufficiency for fusion energy: The case of CFETR
journal, February 2019

Nie, Baojie; Ran, Guangming; Zeng, Qin
Energy Science & Engineering, Vol. 7, Issue 2
DOI: 10.1002/ese3.291

The Impacts of Liquid Metal Plasma-Facing Components on Fusion Reactor Safety and Tritium Management
journal, November 2019

Humrickhouse, Paul W.; Merrill, Brad J.; Yoon, Su-Jong
Fusion Science and Technology, Vol. 75, Issue 8
DOI: 10.1080/15361055.2019.1658464

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Similar Records

Title: Overview of the fusion nuclear science facility, a credible break-in step on the path to fusion energy

Abstract

Citation Formats

Relation of vertical stability and aspect ratio in tokamaks journal, September 1992

European development of He-cooled divertors for fusion power plants journal, October 2005

Materials challenges for the fusion nuclear science facility journal, October 2018

Materials degradation in fission reactors: Lessons learned of relevance to fusion reactor systems journal, August 2007

Breeding blanket design and systems integration for a helium-cooled lithium–lead fusion power plant journal, February 2006

Power plant conceptual studies in Europe journal, October 2007

Overview of JT-60U progress towards steady-state advanced tokamak journal, September 2005

Development in the DIII-D tokamak of advanced operating scenarios and associated control techniques for ITER journal, September 2007

ARC: A compact, high-field, fusion nuclear science facility and demonstration power plant with demountable magnets journal, November 2015

Self-cooled blanket concepts using Pb7Li as liquid breeder and coolant journal, April 1991

Progress toward fully noninductive, high beta conditions in DIII-D journal, May 2006

Japanese endeavors to establish technological bases for DEMO journal, November 2016

Performance of high triangularity plasmas as the volume of the secondary divertor is varied in DIII-D journal, March 2001

Multiphysics modeling of the FW/Blanket of the U.S. fusion nuclear science facility (FNSF) journal, October 2018

Progress in IFMIF Engineering Validation and Engineering Design Activities journal, October 2013

Reactor integration of the helium cooled pebble bed blanket for DEMO journal, November 2005

DIII-D research towards resolving key issues for ITER and steady-state tokamaks journal, September 2013

Internal Tin ${\hbox {Nb}}_{3}{\hbox {Sn}}$ Conductors Engineered for Fusion and Particle Accelerator Applications journal, June 2009

Chapter 6: Steady state operation journal, June 2007

An overview of KSTAR results journal, September 2013

Stability of the resistive wall mode in JET journal, March 2009

Progress of long pulse and H-mode experiments in EAST journal, September 2013

Axisymmetric disruption dynamics including current profile changes in the ASDEX-Upgrade tokamak journal, July 2002

Prospects for pilot plants based on the tokamak, spherical tokamak and stellarator journal, August 2011

Prospects of High Temperature Superconductors for fusion magnets and power applications journal, October 2013

Progress in the ITER Physics Basis journal, June 2007

Physics basis and design of the ITER plasma-facing components journal, August 2011

ITER operational availability and fluence objectives journal, October 2011

High heat flux testing of a helium-cooled tungsten tube with porous foam journal, October 2007

Overview of the design approach and prioritization of R&D activities towards an EU DEMO journal, November 2016

Evaluation of irradiation facility options for fusion materials research and development journal, October 2013

Scrape-off layer plasma and neutral characteristics and their interactions with walls for FNSF journal, October 2018

Overview of the JT-60SA project journal, August 2011

Effect of ELMS and disruptions on FNSF plasma-facing components journal, October 2018

Variation of ${(J_{\rm c}/J_{{\rm c}0})}_{\max}$ of Binary and Ternary Alloyed RRP and PIT $\hbox{Nb}_{3}\hbox{Sn}$ Wires Exposed to Fast Neutron Irradiation at Ambient Reactor Temperature journal, June 2013

Partial detachment of high power discharges in ASDEX Upgrade journal, April 2015

The examination of the FNSF maintenance approach journal, October 2018

Design concept of K-DEMO for near-term implementation journal, April 2015

Stability and control of resistive wall modes in high beta, low rotation DIII-D plasmas journal, August 2007

Results of the international large coil task: a milestone for superconducting magnets in fusion power journal, September 1989

Physics and technology conditions for attaining tritium self-sufficiency for the DT fuel cycle journal, February 2006

Neutronics Analysis in Support of the Fusion Development Facility Design Evolution journal, August 2011

Targets for R&D on Nb 3 Sn Conductor for High Energy Physics journal, June 2015

Effect of magnetic geometry on ELM heat flux profiles journal, March 2001

Tritium Transport Issues for Helium-Cooled Breeding Blankets journal, July 2014

Plasma profile and shape optimization for the advanced tokamak power plant, ARIES-AT journal, January 2006

ITER, safety and licensing journal, October 2007

Divertor studies in nitrogen induced completely detached H-modes in full tungsten ASDEX Upgrade journal, February 2015

Remote Handling and Plasma Conditions to Enable Fusion Nuclear Science R&D Using a Component Testing Facility journal, August 2009

The ITER Magnets: Design and Construction Status journal, June 2012

Investigations of impurity seeding and radiation control for long-pulse and high-density H-mode plasmas in JT-60U journal, September 2009

MHD thermohydraulics analysis and supporting R&D for DCLL blanket in the FNSF journal, October 2018

The high-βN hybrid scenario for ITER and FNSF steady-state missionsa) journal, May 2015

Experimental Investigation of Fin Enhancement for Gas-Cooled Divertor Concepts journal, July 2011

ARIES-ACT1 System Configuration, Assembly, and Maintenance journal, January 2015

The Fusion Nuclear Science Facility, the Critical Step in the Pathway to Fusion Energy journal, September 2015

Steady state scenario development with elevated minimum safety factor on DIII-D journal, August 2014

DC electrical conductivity of silicon carbide ceramics and composites for flow channel insert applications journal, April 2009

The use of water in a fusion power core journal, February 2015

Continuous SiC fiber, CVI SiC matrix composites for nuclear applications: Properties and irradiation effects journal, May 2014

Thermal performance and flow instabilities in a multi-channel, helium-cooled, porous metal divertor module journal, November 2000

Critical questions in materials science and engineering for successful development of fusion power journal, August 2007

An advanced He-cooled divertor concept: Design, cooling technology, and thermohydraulic analyses with CFD journal, November 2005

Assessment of neutron irradiation effects on RAFM steels journal, March 2013

Neutronics aspects of the FESS-FNSF journal, October 2018

The ARIES Advanced and Conservative Tokamak Power Plant Study journal, January 2015

Recent US activities on advanced He-cooled W-alloy divertor concepts for fusion power plants journal, January 2011

An example pathway to a fusion power plant system based on lead–lithium breeder: Comparison of the dual-coolant lead–lithium (DCLL) blanket with the helium-cooled lead–lithium (HCLL) concept as initial step journal, December 2009

Tritium aspects of the fusion nuclear science facility journal, October 2018

Physics Basis for a Conservative Physics and Conservative Technology Tokamak Power Plant: ARIES-ACT2 journal, January 2015

Core plasma physics basis and its impacts on the FNSF journal, October 2018

Physics Basis for an Advanced Physics and Advanced Technology Tokamak Power Plant Configuration: ARIES-ACT1 journal, January 2015

Fusion nuclear science facilities and pilot plants based on the spherical tokamak journal, August 2016

The ARIES-CS Compact Stellarator Fusion Power Plant journal, October 2008

HTS Wind Power Generator: Electromagnetic Force Between No-Insulation and Insulation Coils Under Time-Varying Conditions journal, June 2014

ITER safety and licensing update journal, August 2012

Overview of JT-60U results towards the establishment of advanced tokamak operation journal, September 2009

Relation of vertical stability and aspect ratio in tokamaks
journal, September 1992

European development of He-cooled divertors for fusion power plants
journal, October 2005

Materials challenges for the fusion nuclear science facility
journal, October 2018

Materials degradation in fission reactors: Lessons learned of relevance to fusion reactor systems
journal, August 2007

Breeding blanket design and systems integration for a helium-cooled lithium–lead fusion power plant
journal, February 2006

Power plant conceptual studies in Europe
journal, October 2007

Overview of JT-60U progress towards steady-state advanced tokamak
journal, September 2005

Development in the DIII-D tokamak of advanced operating scenarios and associated control techniques for ITER
journal, September 2007

ARC: A compact, high-field, fusion nuclear science facility and demonstration power plant with demountable magnets
journal, November 2015

Self-cooled blanket concepts using Pb7Li as liquid breeder and coolant
journal, April 1991

Progress toward fully noninductive, high beta conditions in DIII-D
journal, May 2006

Japanese endeavors to establish technological bases for DEMO
journal, November 2016

Performance of high triangularity plasmas as the volume of the secondary divertor is varied in DIII-D
journal, March 2001

Multiphysics modeling of the FW/Blanket of the U.S. fusion nuclear science facility (FNSF)
journal, October 2018

Progress in IFMIF Engineering Validation and Engineering Design Activities
journal, October 2013

Reactor integration of the helium cooled pebble bed blanket for DEMO
journal, November 2005

DIII-D research towards resolving key issues for ITER and steady-state tokamaks
journal, September 2013

Internal Tin ${\hbox {Nb}}_{3}{\hbox {Sn}}$ Conductors Engineered for Fusion and Particle Accelerator Applications
journal, June 2009

Chapter 6: Steady state operation
journal, June 2007

An overview of KSTAR results
journal, September 2013

Stability of the resistive wall mode in JET
journal, March 2009

Progress of long pulse and H-mode experiments in EAST
journal, September 2013

Axisymmetric disruption dynamics including current profile changes in the ASDEX-Upgrade tokamak
journal, July 2002

Prospects for pilot plants based on the tokamak, spherical tokamak and stellarator
journal, August 2011

Prospects of High Temperature Superconductors for fusion magnets and power applications
journal, October 2013

Progress in the ITER Physics Basis
journal, June 2007

Physics basis and design of the ITER plasma-facing components
journal, August 2011

ITER operational availability and fluence objectives
journal, October 2011

High heat flux testing of a helium-cooled tungsten tube with porous foam
journal, October 2007

Overview of the design approach and prioritization of R&D activities towards an EU DEMO
journal, November 2016

Evaluation of irradiation facility options for fusion materials research and development
journal, October 2013

Scrape-off layer plasma and neutral characteristics and their interactions with walls for FNSF
journal, October 2018

Overview of the JT-60SA project
journal, August 2011

Effect of ELMS and disruptions on FNSF plasma-facing components
journal, October 2018

Variation of ${(J_{\rm c}/J_{{\rm c}0})}_{\max}$ of Binary and Ternary Alloyed RRP and PIT $\hbox{Nb}_{3}\hbox{Sn}$ Wires Exposed to Fast Neutron Irradiation at Ambient Reactor Temperature
journal, June 2013

Partial detachment of high power discharges in ASDEX Upgrade
journal, April 2015

The examination of the FNSF maintenance approach
journal, October 2018

Design concept of K-DEMO for near-term implementation
journal, April 2015

Stability and control of resistive wall modes in high beta, low rotation DIII-D plasmas
journal, August 2007

Results of the international large coil task: a milestone for superconducting magnets in fusion power
journal, September 1989

Physics and technology conditions for attaining tritium self-sufficiency for the DT fuel cycle
journal, February 2006

Neutronics Analysis in Support of the Fusion Development Facility Design Evolution
journal, August 2011

Targets for R&D on Nb ₃ Sn Conductor for High Energy Physics
journal, June 2015

Effect of magnetic geometry on ELM heat flux profiles
journal, March 2001

Tritium Transport Issues for Helium-Cooled Breeding Blankets
journal, July 2014

Plasma profile and shape optimization for the advanced tokamak power plant, ARIES-AT
journal, January 2006

ITER, safety and licensing
journal, October 2007

Divertor studies in nitrogen induced completely detached H-modes in full tungsten ASDEX Upgrade
journal, February 2015

Remote Handling and Plasma Conditions to Enable Fusion Nuclear Science R&D Using a Component Testing Facility
journal, August 2009

The ITER Magnets: Design and Construction Status
journal, June 2012

Investigations of impurity seeding and radiation control for long-pulse and high-density H-mode plasmas in JT-60U
journal, September 2009

MHD thermohydraulics analysis and supporting R&D for DCLL blanket in the FNSF
journal, October 2018

The high-βN hybrid scenario for ITER and FNSF steady-state missionsa)
journal, May 2015

Experimental Investigation of Fin Enhancement for Gas-Cooled Divertor Concepts
journal, July 2011

ARIES-ACT1 System Configuration, Assembly, and Maintenance
journal, January 2015

The Fusion Nuclear Science Facility, the Critical Step in the Pathway to Fusion Energy
journal, September 2015

Steady state scenario development with elevated minimum safety factor on DIII-D
journal, August 2014

DC electrical conductivity of silicon carbide ceramics and composites for flow channel insert applications
journal, April 2009

The use of water in a fusion power core
journal, February 2015

Continuous SiC fiber, CVI SiC matrix composites for nuclear applications: Properties and irradiation effects
journal, May 2014

Thermal performance and flow instabilities in a multi-channel, helium-cooled, porous metal divertor module
journal, November 2000

Critical questions in materials science and engineering for successful development of fusion power
journal, August 2007

An advanced He-cooled divertor concept: Design, cooling technology, and thermohydraulic analyses with CFD
journal, November 2005

Assessment of neutron irradiation effects on RAFM steels
journal, March 2013

Neutronics aspects of the FESS-FNSF
journal, October 2018

The ARIES Advanced and Conservative Tokamak Power Plant Study
journal, January 2015

Recent US activities on advanced He-cooled W-alloy divertor concepts for fusion power plants
journal, January 2011

An example pathway to a fusion power plant system based on lead–lithium breeder: Comparison of the dual-coolant lead–lithium (DCLL) blanket with the helium-cooled lead–lithium (HCLL) concept as initial step
journal, December 2009

Tritium aspects of the fusion nuclear science facility
journal, October 2018

Physics Basis for a Conservative Physics and Conservative Technology Tokamak Power Plant: ARIES-ACT2
journal, January 2015

Core plasma physics basis and its impacts on the FNSF
journal, October 2018

Physics Basis for an Advanced Physics and Advanced Technology Tokamak Power Plant Configuration: ARIES-ACT1
journal, January 2015

Fusion nuclear science facilities and pilot plants based on the spherical tokamak
journal, August 2016

The ARIES-CS Compact Stellarator Fusion Power Plant
journal, October 2008

HTS Wind Power Generator: Electromagnetic Force Between No-Insulation and Insulation Coils Under Time-Varying Conditions
journal, June 2014

ITER safety and licensing update
journal, August 2012

Overview of JT-60U results towards the establishment of advanced tokamak operation
journal, September 2009

Experimental and Numerical Investigation of Prototypical Multi-Jet Impingement (HEMJ) Helium-Cooled Divertor Modules
journal, July 2009

He-cooled divertor for DEMO: Status of development and HHF tests
journal, December 2010

Plasma vertical control with internal and external coils in next step tokamaks
journal, July 2001