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

Abstract

The affordable, robust, compact (ARC) reactor is the product of a conceptual design study focused on reducing the size, cost, and complexity of a combined fusion nuclear science facility (FNSF) and demonstration fusion Pilot power plant. ARC is a ~200–250 MWe tokamak reactor with a major radius of 3.3 m, a minor radius of 1.1 m, and an on-axis magnetic field of 9.2 T. ARC has rare earth barium copper oxide (REBCO) superconducting toroidal field coils, which have joints to enable disassembly. This enables the vacuum vessel to be replaced quickly, mitigating first wall survivability concerns, and permits a single device to test many vacuum vessel designs and divertor materials. The design point has a plasma fusion gain of Qp ≈ 13.6, yet is fully non-inductive, with a modest bootstrap fraction of only ~63%. Thus ARC offers a high power gain with relatively large external control of the current profile. This highly attractive combination is enabled by the ~23 T peak field on coil achievable with newly available REBCO superconductor technology. External current drive is provided by two innovative inboard RF launchers using 25 MW of lower hybrid and 13.6 MW of ion cyclotron fast wave power. The concluding efficientmore » current drive provides a robust, steady state core plasma far from disruptive limits. ARC uses an all-liquid blanket, consisting of low pressure, slowly flowing fluorine lithium beryllium (FLiBe) molten salt. The liquid blanket is low-risk technology and provides effective neutron moderation and shielding, excellent heat removal, and a tritium breeding ratio ≥ 1.1. The large temperature range over which FLiBe is liquid permits an output blanket temperature of 900 K, single phase fluid cooling, and a high efficiency helium Brayton cycle, which allows for net electricity generation when operating ARC as a Pilot power plant.« less

Authors:
 [1];  [1];  [1];  [1];  [1];  [1];  [1];  [1];  [1];  [1];  [1];  [1];  [1]
  1. Massachusetts Inst. of Technology (MIT), Cambridge, MA (United States)
Publication Date:
Research Org.:
Massachusetts Inst. of Technology (MIT), Cambridge, MA (United States)
Sponsoring Org.:
USDOE Office of Science (SC), Fusion Energy Sciences (FES); National Science Foundation (NSF)
OSTI Identifier:
1548312
Alternate Identifier(s):
OSTI ID: 1252044
Grant/Contract Number:  
FG02-94ER54235; SC008435; FC02-93ER54186
Resource Type:
Accepted Manuscript
Journal Name:
Fusion Engineering and Design
Additional Journal Information:
Journal Volume: 100; Journal Issue: C; Journal ID: ISSN 0920-3796
Publisher:
Elsevier
Country of Publication:
United States
Language:
English
Subject:
70 PLASMA PHYSICS AND FUSION TECHNOLOGY; Compact pilot reactor; High magnetic field; Fusion nuclear science facility; Liquid immersion blanket; Superconducting joints; Tokamak; High-field launch

Citation Formats

Sorbom, B. N., Ball, J., Palmer, T. R., Mangiarotti, F. J., Sierchio, J. M., Bonoli, P., Kasten, C., Sutherland, D. A., Barnard, H. S., Haakonsen, C. B., Goh, J., Sung, C., and Whyte, D. G. ARC: A compact, high-field, fusion nuclear science facility and demonstration power plant with demountable magnets. United States: N. p., 2015. Web. doi:10.1016/j.fusengdes.2015.07.008.
Sorbom, B. N., Ball, J., Palmer, T. R., Mangiarotti, F. J., Sierchio, J. M., Bonoli, P., Kasten, C., Sutherland, D. A., Barnard, H. S., Haakonsen, C. B., Goh, J., Sung, C., & Whyte, D. G. ARC: A compact, high-field, fusion nuclear science facility and demonstration power plant with demountable magnets. United States. https://doi.org/10.1016/j.fusengdes.2015.07.008
Sorbom, B. N., Ball, J., Palmer, T. R., Mangiarotti, F. J., Sierchio, J. M., Bonoli, P., Kasten, C., Sutherland, D. A., Barnard, H. S., Haakonsen, C. B., Goh, J., Sung, C., and Whyte, D. G. Tue . "ARC: A compact, high-field, fusion nuclear science facility and demonstration power plant with demountable magnets". United States. https://doi.org/10.1016/j.fusengdes.2015.07.008. https://www.osti.gov/servlets/purl/1548312.
@article{osti_1548312,
title = {ARC: A compact, high-field, fusion nuclear science facility and demonstration power plant with demountable magnets},
author = {Sorbom, B. N. and Ball, J. and Palmer, T. R. and Mangiarotti, F. J. and Sierchio, J. M. and Bonoli, P. and Kasten, C. and Sutherland, D. A. and Barnard, H. S. and Haakonsen, C. B. and Goh, J. and Sung, C. and Whyte, D. G.},
abstractNote = {The affordable, robust, compact (ARC) reactor is the product of a conceptual design study focused on reducing the size, cost, and complexity of a combined fusion nuclear science facility (FNSF) and demonstration fusion Pilot power plant. ARC is a ~200–250 MWe tokamak reactor with a major radius of 3.3 m, a minor radius of 1.1 m, and an on-axis magnetic field of 9.2 T. ARC has rare earth barium copper oxide (REBCO) superconducting toroidal field coils, which have joints to enable disassembly. This enables the vacuum vessel to be replaced quickly, mitigating first wall survivability concerns, and permits a single device to test many vacuum vessel designs and divertor materials. The design point has a plasma fusion gain of Qp ≈ 13.6, yet is fully non-inductive, with a modest bootstrap fraction of only ~63%. Thus ARC offers a high power gain with relatively large external control of the current profile. This highly attractive combination is enabled by the ~23 T peak field on coil achievable with newly available REBCO superconductor technology. External current drive is provided by two innovative inboard RF launchers using 25 MW of lower hybrid and 13.6 MW of ion cyclotron fast wave power. The concluding efficient current drive provides a robust, steady state core plasma far from disruptive limits. ARC uses an all-liquid blanket, consisting of low pressure, slowly flowing fluorine lithium beryllium (FLiBe) molten salt. The liquid blanket is low-risk technology and provides effective neutron moderation and shielding, excellent heat removal, and a tritium breeding ratio ≥ 1.1. The large temperature range over which FLiBe is liquid permits an output blanket temperature of 900 K, single phase fluid cooling, and a high efficiency helium Brayton cycle, which allows for net electricity generation when operating ARC as a Pilot power plant.},
doi = {10.1016/j.fusengdes.2015.07.008},
journal = {Fusion Engineering and Design},
number = C,
volume = 100,
place = {United States},
year = {Tue Jul 14 00:00:00 EDT 2015},
month = {Tue Jul 14 00:00:00 EDT 2015}
}

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Cited by: 280 works
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Works referenced in this record:

The ARIES-I Tokamak Reactor Study
journal, May 1991

  • Najmabadi, F.; Conn, R. W.; Bathke, C. G.
  • Fusion Technology, Vol. 19, Issue 3P2A
  • DOI: 10.13182/FST91-A29440

The ARIES-AT advanced tokamak, Advanced technology fusion power plant
journal, January 2006


Overview of the ARIES-RS reversed-shear tokamak power plant study
journal, December 1997

  • Najmabadi, Farrokh; Bathke, Charles G.; Billone, Michael C.
  • Fusion Engineering and Design, Vol. 38, Issue 1-2
  • DOI: 10.1016/S0920-3796(97)00110-5

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


Vulcan: A steady-state tokamak for reactor-relevant plasma–material interaction science
journal, March 2012


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


A new look at density limits in tokamaks
journal, December 1988


MHD-Limits to Plasma Confinement
journal, January 1984


The lower hybrid current drive system for steady-state operation of the Vulcan tokamak conceptual design
journal, March 2012


Chapter 2: Plasma confinement and transport
journal, December 1999

  • Transport, ITER Physics Expert Group on Confin; Database, ITER Physics Expert Group on Confin; Editors, ITER Physics Basis
  • Nuclear Fusion, Vol. 39, Issue 12
  • DOI: 10.1088/0029-5515/39/12/302

An initial study of demountable high-temperature superconducting toroidal field magnets for the Vulcan tokamak conceptual design
journal, March 2012


Assessing the feasibility of a high-temperature, helium-cooled vacuum vessel and first wall for the Vulcan tokamak conceptual design
journal, March 2012


Edge safety factor at the onset of plasma disruption during VDEs in JT-60U
journal, September 2004

  • Sugihara, Masayoshi; Lukash, Victor; Khayrutdinov, Rustam
  • Plasma Physics and Controlled Fusion, Vol. 46, Issue 10
  • DOI: 10.1088/0741-3335/46/10/004

Physics basis for a tokamak fusion power plant
journal, September 2000


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


Creating an Asymmetric Plasma Resistivity with Waves
journal, September 1980


Bootstrap current in a tokamak
journal, September 1994


I-mode: an H-mode energy confinement regime with L-mode particle transport in Alcator C-Mod
journal, August 2010


Edge energy transport barrier and turbulence in the I-mode regime on Alcator C-Mod
journal, May 2011

  • Hubbard, A. E.; Whyte, D. G.; Churchill, R. M.
  • Physics of Plasmas, Vol. 18, Issue 5
  • DOI: 10.1063/1.3582135

Regime of Improved Confinement and High Beta in Neutral-Beam-Heated Divertor Discharges of the ASDEX Tokamak
journal, November 1982


Edge localized mode physics and operational aspects in tokamaks
journal, November 2003


Threshold conditions for transitions to I-mode and H-mode with unfavourable ion grad B drift direction
journal, October 2012


Edge-localized mode avoidance and pedestal structure in I-mode plasmas
journal, May 2014

  • Walk, J. R.; Hughes, J. W.; Hubbard, A. E.
  • Physics of Plasmas, Vol. 21, Issue 5
  • DOI: 10.1063/1.4872220

ELMs and constraints on the H-mode pedestal: peeling–ballooning stability calculation and comparison with experiment
journal, January 2004


Efficiency of current drive by fast waves
journal, January 1985

  • Karney, Charles F. F.; Fisch, Nathaniel J.
  • Physics of Fluids, Vol. 28, Issue 1
  • DOI: 10.1063/1.865191

Modelling of lower hybrid current drive in self-consistent elongated tokamak equilibria
journal, May 1992


Hydromagnetic equilibria and force-free fields
journal, September 1958


Physics basis for the advanced tokamak fusion power plant, ARIES-AT
journal, January 2006


Preparing ITER ICRF: development and analysis of the load resilient matching systems based on antenna mock-up measurements
journal, April 2009


Access to sustained high-beta with internal transport barrier and negative central magnetic shear in DIII-D
journal, May 2006

  • Garofalo, A. M.; Doyle, E. J.; Ferron, J. R.
  • Physics of Plasmas, Vol. 13, Issue 5
  • DOI: 10.1063/1.2185010

High performance stationary discharges in the DIII-D tokamak
journal, May 2004

  • Luce, T. C.; Wade, M. R.; Ferron, J. R.
  • Physics of Plasmas, Vol. 11, Issue 5
  • DOI: 10.1063/1.1704644

Neoclassical conductivity and bootstrap current formulas for general axisymmetric equilibria and arbitrary collisionality regime
journal, July 1999

  • Sauter, O.; Angioni, C.; Lin-Liu, Y. R.
  • Physics of Plasmas, Vol. 6, Issue 7
  • DOI: 10.1063/1.873240

Active-passive waveguide array for wave excitation in plasmas
journal, February 1980


Coupling characteristics of the ITER-relevant lower hybrid antenna in Tore Supra: experiments and modelling
journal, January 2011


Biaxially Textured IBAD-MgO Templates for YBCO-Coated Conductors
journal, August 2004


Physical properties of Hastelloy ® C-276™ at cryogenic temperatures
journal, March 2008

  • Lu, J.; Choi, E. S.; Zhou, H. D.
  • Journal of Applied Physics, Vol. 103, Issue 6
  • DOI: 10.1063/1.2899058

Structure Improvement and Joint Resistance Estimation in Demountable Butt and Edge Joints of a Stacked REBCO Conductor Within a Metal Jacket
journal, June 2013

  • Ito, S.; Ohinata, T.; Bromberg, L.
  • IEEE Transactions on Applied Superconductivity, Vol. 23, Issue 3
  • DOI: 10.1109/TASC.2013.2244197

Tensile, Fracture, Fatigue Life, and Fatigue Crack Growth Rate Behavior of Structural Materials for the ITER Magnets: The European Contribution
conference, January 2004

  • Nyilas, A.
  • ADVANCES IN CRYOGENIC ENGINEERING: Transactions of the International Cryogenic Materials Conference - ICMC, AIP Conference Proceedings
  • DOI: 10.1063/1.1774567

Mechanical and Thermal Characteristics of Insulation Materials for the KSTAR Magnet System at Cryogenic Temperature
conference, January 2004

  • Chung, Wooho
  • ADVANCES IN CRYOGENIC ENGINEERING: Transactions of the International Cryogenic Materials Conference - ICMC, AIP Conference Proceedings
  • DOI: 10.1063/1.1774582

Reversible tensile strain dependence of the critical current in YBCO coated conductor tapes
journal, October 2007

  • Shin, H. S.; Dizon, J. R. C.; Ko, R. K.
  • Physica C: Superconductivity and its Applications, Vol. 463-465
  • DOI: 10.1016/j.physc.2007.04.319

Electrical resistivity of copper, gold, palladium, and silver
journal, October 1979

  • Matula, R. A.
  • Journal of Physical and Chemical Reference Data, Vol. 8, Issue 4, p. 1147-1298
  • DOI: 10.1063/1.555614

Plasma-material interactions in current tokamaks and their implications for next step fusion reactors
journal, December 2001


The IFMIF test facilities design
journal, February 2006


Options for the use of high temperature superconductor in tokamak fusion reactor designs
journal, February 2001


Toward the ultimate goal of tritium self-sufficiency: Technical issues and requirements imposed on ARIES advanced power plants
journal, December 2009


Impact of armor materials on tritium breeding ratio in the fusion reactor blanket
journal, March 2003


Molten fluorides for nuclear applications
journal, December 2010


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


Reactor similarity for plasma–material interactions in scaled-down tokamaks as the basis for the Vulcan conceptual design
journal, March 2012


The Joint European Torus: installation, first results and prospects
journal, September 1985


H mode confinement in Alcator C-Mod
journal, June 1997


Chapter 3: MHD stability, operational limits and disruptions
journal, December 1999

  • Mhd, ITER Physics Expert Group on Disrup; Editors, ITER Physics Basis
  • Nuclear Fusion, Vol. 39, Issue 12
  • DOI: 10.1088/0029-5515/39/12/303

Retention of implanted hydrogen and helium in martensitic stainless steels and their effects on mechanical properties
journal, July 2001


Effect of helium implantation on the mechanical properties and the microstructure of the martensitic 12% Cr-steel 1.4914
journal, July 1988


Nuclear performance assessment of ARIES-AT
journal, January 2006


Conceptual design activities and key issues on LHD-type reactor FFHR
journal, November 2006


High Performance Corrosion Resistance of Nickel-Based Alloys in Molten Salt Flibe
journal, July 2009

  • Kondo, Masatoshi; Nagasaka, Takuya; Muroga, Takeo
  • Fusion Science and Technology, Vol. 56, Issue 1
  • DOI: 10.13182/FST09-A8900

On the exploration of innovative concepts for fusion chamber technology
journal, February 2001


Toward the ultimate goal of tritium self-sufficiency: Technical issues and requirements imposed on ARIES advanced power plants
journal, December 2009


Tensile, Fracture, Fatigue Life, and Fatigue Crack Growth Rate Behavior of Structural Materials for the ITER Magnets: The European Contribution
conference, January 2004

  • Nyilas, A.
  • ADVANCES IN CRYOGENIC ENGINEERING: Transactions of the International Cryogenic Materials Conference - ICMC, AIP Conference Proceedings
  • DOI: 10.1063/1.1774567

Coupling characteristics of the ITER relevant lower hybrid antenna in Tore Supra: experiments and modelling
conference, January 2011

  • Preynas, M.; Ekedahl, A.; Fedorczak, N.
  • AIP Conference Proceedings
  • DOI: 10.1063/1.3664953

Plasma heating by fast magnetosonic waves in Tokamaks
conference, January 1994

  • Porkolab, Miklos
  • Advances in plasma physics, AIP Conference Proceedings
  • DOI: 10.1063/1.46754

Neoclassical conductivity and bootstrap current formulas for general axisymmetric equilibria and arbitrary collisionality regime
journal, July 1999

  • Sauter, O.; Angioni, C.; Lin-Liu, Y. R.
  • Physics of Plasmas, Vol. 6, Issue 7
  • DOI: 10.1063/1.873240

Active-passive waveguide array for wave excitation in plasmas
journal, February 1980


A first-principles predictive model of the pedestal height and width: development, testing and ITER optimization with the EPED model
journal, August 2011


Equilibrium of a three-dimensional plasma filament in a longitudinal magnetic field under steady conditions
journal, January 1966

  • Shafranov, V. D.
  • Journal of Nuclear Energy. Part C, Plasma Physics, Accelerators, Thermonuclear Research, Vol. 8, Issue 2
  • DOI: 10.1088/0368-3281/8/2/312

Analysis and testing of high temperature fibrous insulation for reusable launch vehicles
conference, January 1999


Works referencing / citing this record:

Gyrokinetic investigation of the ASDEX Upgrade I-mode pedestal
journal, December 2019

  • Stimmel, K.; Bañón Navarro, A.; Happel, T.
  • Physics of Plasmas, Vol. 26, Issue 12
  • DOI: 10.1063/1.5124986

Cold plasma finite element wave model for helicon waves
journal, February 2019

  • Lau, C.; Berry, L. A.; Jaeger, E. F.
  • Plasma Physics and Controlled Fusion, Vol. 61, Issue 4
  • DOI: 10.1088/1361-6587/aafd04

Experimental energy confinement time scaling with dimensionless parameters in C-Mod I-mode plasmas
journal, October 2019


20 years of research on the Alcator C-Mod tokamaka)
journal, November 2014

  • Greenwald, M.; Bader, A.; Baek, S.
  • Physics of Plasmas, Vol. 21, Issue 11
  • DOI: 10.1063/1.4901920

On microinstabilities and turbulence in steep-gradient regions of fusion devices
journal, February 2019

  • Pueschel, M. J.; Hatch, D. R.; Ernst, D. R.
  • Plasma Physics and Controlled Fusion, Vol. 61, Issue 3
  • DOI: 10.1088/1361-6587/aaf8c1

UEDGE modelling of detached divertor operation for long-leg divertor geometries in ARC
journal, March 2018

  • Wigram, M.; LaBombard, B.; Umansky, M. V.
  • Contributions to Plasma Physics, Vol. 58, Issue 6-8
  • DOI: 10.1002/ctpp.201700178

Basic physical processes and reduced models for plasma detachment
journal, March 2018


Neutronics Scoping Studies for Experimental Fusion Devices
journal, May 2019


Access to pedestal pressure relevant to burning plasmas on the high magnetic field tokamak Alcator C-Mod
journal, September 2018


Integrated Tokamak modeling: When physics informs engineering and research planning
journal, May 2018


Compact steady-state tokamak performance dependence on magnet and core physics limits
journal, February 2019

  • Menard, J. E.
  • Philosophical Transactions of the Royal Society A: Mathematical, Physical and Engineering Sciences, Vol. 377, Issue 2141
  • DOI: 10.1098/rsta.2017.0440

Spatiotemporal evolution of runaway electrons from synchrotron images in Alcator C-Mod
journal, October 2018

  • Tinguely, R. A.; Granetz, R. S.; Hoppe, M.
  • Plasma Physics and Controlled Fusion, Vol. 60, Issue 12
  • DOI: 10.1088/1361-6587/aae6ba

Shielding materials in the compact spherical tokamak
journal, February 2019

  • Humphry-Baker, Samuel A.; Smith, George D. W.
  • Philosophical Transactions of the Royal Society A: Mathematical, Physical and Engineering Sciences, Vol. 377, Issue 2141
  • DOI: 10.1098/rsta.2017.0443

The dependence of divertor power sharing on magnetic flux balance in near double-null configurations on Alcator C-Mod
journal, May 2018


Observation of Efficient Lower Hybrid Current Drive at High Density in Diverted Plasmas on the Alcator C-Mod Tokamak
journal, August 2018


Maximizing specific energy by breeding deuterium
journal, September 2019


High field side lower hybrid wave launch for steady state plasma sustainment
journal, November 2018


Radio-frequency current drive for thermonuclear fusion reactors
journal, July 2018


The effect of background flow shear on gyrokinetic turbulence in the cold ion limit
journal, April 2019

  • Ball, Justin; Brunner, Stephan; McMillan, Ben F.
  • Plasma Physics and Controlled Fusion, Vol. 61, Issue 6
  • DOI: 10.1088/1361-6587/ab1320

Designing a tokamak fusion reactor—How does plasma physics fit in?
journal, July 2015

  • Freidberg, J. P.; Mangiarotti, F. J.; Minervini, J.
  • Physics of Plasmas, Vol. 22, Issue 7
  • DOI: 10.1063/1.4923266

Dipole Magnets Above 20 Tesla: Research Needs for a Path via High-Temperature Superconducting REBCO Conductors
journal, November 2019


On the Use of High Magnetic Field in Reactor Grade Tokamaks
journal, August 2018


Mixed-dimensional modeling of delamination in rare earth-barium-copper-oxide coated conductors composed of laminated high-aspect-ratio thin films
journal, June 2018

  • Gao, Peifeng; Chan, Wan-Kan; Wang, Xingzhe
  • Superconductor Science and Technology, Vol. 31, Issue 7
  • DOI: 10.1088/1361-6668/aac55c

On the size of tokamak fusion power plants
journal, February 2019

  • Zohm, Hartmut
  • Philosophical Transactions of the Royal Society A: Mathematical, Physical and Engineering Sciences, Vol. 377, Issue 2141
  • DOI: 10.1098/rsta.2017.0437

Exploration of a Fast Pathway to Nuclear Fusion: Thermal Analysis and Cooling Design Considerations for the ARC Reactor
journal, July 2019


Similarity of the coupled equations for RF waves in a tokamak
journal, January 2019

  • Lee, Jungpyo; Smithe, David; Jaeger, Erwin F.
  • Physics of Plasmas, Vol. 26, Issue 1
  • DOI: 10.1063/1.5066288

Summary of the FESAC Transformative Enabling Capabilities Panel Report
journal, March 2019


Influence of high magnetic field on access to stationary H-modes and pedestal characteristics in Alcator C-Mod
journal, February 2018


Performance assessment of long-legged tightly-baffled divertor geometries in the ARC reactor concept
journal, September 2019


Optimisation of confinement in a fusion reactor using a nonlinear turbulence model
text, January 2016


Spatiotemporal evolution of runaway electrons from synchrotron images in Alcator C-Mod
text, January 2018


The effect of background flow shear on gyrokinetic turbulence in the cold ion limit
text, January 2018


ARC reactor materials: Activation analysis and optimization
journal, May 2020


Radio-frequency current drive for thermonuclear fusion reactors
journal, July 2018


Upward shift of the vortex solid phase in high-temperature-superconducting wires through high density nanoparticle addition
journal, February 2016

  • Miura, Masashi; Maiorov, Boris; Balakirev, Fedor F.
  • Scientific Reports, Vol. 6, Issue 1
  • DOI: 10.1038/srep20436

Alpha channeling with high-field launch of lower hybrid waves
journal, November 2015

  • Ochs, I. E.; Bertelli, N.; Fisch, N. J.
  • Physics of Plasmas, Vol. 22, Issue 11
  • DOI: 10.1063/1.4935123

Spatiotemporal evolution of runaway electrons from synchrotron images in Alcator C-Mod
journal, October 2018

  • Tinguely, R. A.; Granetz, R. S.; Hoppe, M.
  • Plasma Physics and Controlled Fusion, Vol. 60, Issue 12
  • DOI: 10.1088/1361-6587/aae6ba

The effect of background flow shear on gyrokinetic turbulence in the cold ion limit
journal, April 2019

  • Ball, Justin; Brunner, Stephan; McMillan, Ben F.
  • Plasma Physics and Controlled Fusion, Vol. 61, Issue 6
  • DOI: 10.1088/1361-6587/ab1320

On the size of tokamak fusion power plants
journal, February 2019

  • Zohm, Hartmut
  • Philosophical Transactions of the Royal Society A: Mathematical, Physical and Engineering Sciences, Vol. 377, Issue 2141
  • DOI: 10.1098/rsta.2017.0437

Measurements of the Strain Dependence of Critical Current of Commercial REBCO Tapes at 15 T Between 4.2 and 40 K for High Field Magnets
journal, August 2019

  • Pierro, Federica; Delgado, Mario; Chiesa, Luisa
  • IEEE Transactions on Applied Superconductivity, Vol. 29, Issue 5
  • DOI: 10.1109/tasc.2019.2902458

Neutron diagnostics for the physics of a high-field, compact, $Q\geq1$ tokamak
preprint, January 2019


A high temperature W$_2$B cermet for compact neutron shielding
text, January 2019