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Waldon C, Muldrew SI, Keep J, Verhoeven R, Thompson T, Kisbey-Ascott M. Concept design overview: a question of choices and compromise. PHILOSOPHICAL TRANSACTIONS. SERIES A, MATHEMATICAL, PHYSICAL, AND ENGINEERING SCIENCES 2024; 382:20230414. [PMID: 39183656 PMCID: PMC11423670 DOI: 10.1098/rsta.2023.0414] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Abstract] [Key Words] [Track Full Text] [Subscribe] [Scholar Register] [Received: 02/29/2024] [Revised: 06/08/2024] [Accepted: 06/15/2024] [Indexed: 08/27/2024]
Abstract
The Spherical Tokamak for Energy Production (STEP) programme hypothesizes that a compact machine offers a route to reduced capital cost that directly tackles the barrier to entry of this potentially transformative technology. History has shown that with an unsolved, complex and highly interdependent design challenge, there is a need to balance exploration of the problem with progress. Almost all complex systems arise from the evolutionary improvement of simpler systems which is an approach the programme has adopted by working through a virtual natural selection of design families towards a single concept consistent with the initiating hypothesis. Issues are uncovered and solved more rapidly this way because the effort is focused on an end. In this current phase, STEP has had to be an agile fast-moving programme to work with what emerges as well as what was planned, to sit with uncertainty and to embrace self-organizing principles. The complex decision-making and compromises in emerging trades have led to a concept respectful of the tight aspect ratio hypothesis which carefully balances cost, performance and deliverability. It remains a high-risk and high-reward programme, but the character of the challenge is better understood building confidence and enhancing capability to advance the evolving design further.This article is part of the theme issue 'Delivering Fusion Energy - The Spherical Tokamak for Energy Production (STEP)'.
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Affiliation(s)
- Chris Waldon
- United Kingdom Atomic Energy Authority, Culham Campus, Abingdon, OxfordshireOX14 3DB, UK
| | - Stuart I. Muldrew
- United Kingdom Atomic Energy Authority, Culham Campus, Abingdon, OxfordshireOX14 3DB, UK
| | - Jonathan Keep
- United Kingdom Atomic Energy Authority, Culham Campus, Abingdon, OxfordshireOX14 3DB, UK
| | - Roel Verhoeven
- United Kingdom Atomic Energy Authority, Culham Campus, Abingdon, OxfordshireOX14 3DB, UK
| | - Terry Thompson
- United Kingdom Atomic Energy Authority, Culham Campus, Abingdon, OxfordshireOX14 3DB, UK
| | - Mark Kisbey-Ascott
- United Kingdom Atomic Energy Authority, Culham Campus, Abingdon, OxfordshireOX14 3DB, UK
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2
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Chapman IT, Cowley SC, Wilson HR. The Spherical Tokamak for Energy Production: theme issue introduction. PHILOSOPHICAL TRANSACTIONS. SERIES A, MATHEMATICAL, PHYSICAL, AND ENGINEERING SCIENCES 2024; 382:20230416. [PMID: 39183653 DOI: 10.1098/rsta.2023.0416] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Abstract] [Key Words] [Track Full Text] [Subscribe] [Scholar Register] [Received: 05/15/2024] [Accepted: 05/16/2024] [Indexed: 08/27/2024]
Abstract
This theme issue collects together papers summarising the conceptual design of the Spherical Tokamak for Energy Production (STEP). In 2019, the UK government funded the first design stages of a prototype fusion powerplant based on a compact toroidal geometry, called STEP. The primary technical aims of STEP are to produce net energy, to be self-sufficient in tritium fuel and to demonstrate a maintenance regime that would extrapolate to appropriate availability for commercial powerplants. After 5 years and over 1000 person-years of detailed scientific and engineering conceptual design, this theme issue acts as a compendium of the current design basis for STEP, noting that this is a snapshot in time and that the design will continue to evolve. This article is part of the theme issue 'Delivering Fusion Energy - The Spherical Tokamak for Energy Production (STEP)'.
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Affiliation(s)
- I T Chapman
- UK Atomic Energy Authority, Culham Campus , Abingdon, Oxfordshire OX14 3DB, UK
| | - S C Cowley
- Princeton Plasma Physics Laboratory, 100 Stellarator Road , Princeton, NJ 08540, USA
| | - H R Wilson
- Oak Ridge National Laboratory , Oak Ridge, TN 37831, USA
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3
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Raj P, Ball JL, Carmichael J, Frenje JA, Gocht R, Gorini G, Holmes I, Johnson MG, Kennedy R, Mackie S, Nocente M, Panontin E, Petruzzo M, Rebai M, Reinke M, Rice J, Rigamonti D, Rosa MD, Saltos AA, Tardocchi M, Tinguely RA, Wang X. Overview of the neutron diagnostic systems for the SPARC tokamak. THE REVIEW OF SCIENTIFIC INSTRUMENTS 2024; 95:103507. [PMID: 39356194 DOI: 10.1063/5.0219538] [Citation(s) in RCA: 1] [Impact Index Per Article: 1.0] [Reference Citation Analysis] [Abstract] [Track Full Text] [Subscribe] [Scholar Register] [Received: 05/17/2024] [Accepted: 08/07/2024] [Indexed: 10/03/2024]
Abstract
Neutron measurement is the primary tool in the SPARC tokamak for fusion power (Pfus) monitoring, research on the physics of burning plasmas, validation of the neutronics simulation workflows, and providing feedback for machine protection. A demanding target uncertainty (10% for Pfus) and coverage of a wide dynamic range (>8 orders of magnitude going up to 5 × 1019 n/s), coupled with a fast-track timeline for design and deployment, make the development of the SPARC neutron diagnostics challenging. Four subsystems are under design that exploit the high flux of direct DT and DD plasma neutrons emanating from a shielded opening in a midplane diagnostic port. The systems comprise a set of ∼15 flux monitors, mainly ionization chambers and proportional counters for measurement of the neutron yield rate, two independent foil activation systems for measurement of the neutron fluence, a spectrometric radial neutron camera for poloidal profiling of the plasma emissivity, and a high-resolution magnetic proton recoil spectrometer for measurement of the core neutron spectrum. Together, the four systems ensure redundancy of sensors and methods and aim to provide high resolutions of time (10 ms), space (∼7 cm), and energy (<2% at 14 MeV). This paper presents the broader objectives behind the preliminary design of the SPARC neutron diagnostics and discusses the ongoing studies on neutronics, detector comparisons, prototyping, and integration with the unique infrastructure of SPARC. Engineering details of the four subsystems and the concepts for in situ neutron calibration are also highlighted.
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Affiliation(s)
- P Raj
- Commonwealth Fusion Systems, 117 Hospital Road, Devens, Massachusetts 01434, USA
| | - J L Ball
- Massachusetts Institute of Technology, Cambridge, Massachusetts 02139, USA
| | - J Carmichael
- Commonwealth Fusion Systems, 117 Hospital Road, Devens, Massachusetts 01434, USA
| | - J A Frenje
- Massachusetts Institute of Technology, Cambridge, Massachusetts 02139, USA
| | - R Gocht
- Commonwealth Fusion Systems, 117 Hospital Road, Devens, Massachusetts 01434, USA
| | - G Gorini
- Commonwealth Fusion Systems, 117 Hospital Road, Devens, Massachusetts 01434, USA
| | - I Holmes
- Commonwealth Fusion Systems, 117 Hospital Road, Devens, Massachusetts 01434, USA
| | - M Gatu Johnson
- Massachusetts Institute of Technology, Cambridge, Massachusetts 02139, USA
| | - R Kennedy
- Commonwealth Fusion Systems, 117 Hospital Road, Devens, Massachusetts 01434, USA
| | - S Mackie
- Massachusetts Institute of Technology, Cambridge, Massachusetts 02139, USA
| | - M Nocente
- University of Milano-Bicocca, Milan, Italy
| | - E Panontin
- Massachusetts Institute of Technology, Cambridge, Massachusetts 02139, USA
| | - M Petruzzo
- University of Milano-Bicocca, Milan, Italy
| | - M Rebai
- Institute for Plasma Science and Technology ISTP, CNR, Milan, Italy
| | - M Reinke
- Commonwealth Fusion Systems, 117 Hospital Road, Devens, Massachusetts 01434, USA
| | - J Rice
- Massachusetts Institute of Technology, Cambridge, Massachusetts 02139, USA
| | - D Rigamonti
- Institute for Plasma Science and Technology ISTP, CNR, Milan, Italy
| | | | - A A Saltos
- Commonwealth Fusion Systems, 117 Hospital Road, Devens, Massachusetts 01434, USA
| | - M Tardocchi
- Institute for Plasma Science and Technology ISTP, CNR, Milan, Italy
| | - R A Tinguely
- Massachusetts Institute of Technology, Cambridge, Massachusetts 02139, USA
| | - X Wang
- Massachusetts Institute of Technology, Cambridge, Massachusetts 02139, USA
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4
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Vezinet D, Perks CJ, Panontin E, Normile S, Tinguely RA, Rice J, Reinke M, Cario M, Raimond J, Hoffmann A, Dubas E, Saltos A, Kennedy R. SPARC x-ray diagnostics: Technical and functional overview. THE REVIEW OF SCIENTIFIC INSTRUMENTS 2024; 95:093515. [PMID: 39248617 DOI: 10.1063/5.0219486] [Citation(s) in RCA: 1] [Impact Index Per Article: 1.0] [Reference Citation Analysis] [Abstract] [Track Full Text] [Subscribe] [Scholar Register] [Received: 05/17/2024] [Accepted: 08/22/2024] [Indexed: 09/10/2024]
Abstract
An overview is given of SPARC's three main x-ray diagnostics, with a focus on the functions they fulfill with respect to tokamak operation. The first is an in-vessel soft x-ray tomography diagnostic, aimed at providing early campaign information on plasma position, MHD activity, and impurity content. The second is an ex-vessel set of hard x-ray scintillators aimed at detecting the presence of runaway electrons, in particular during plasma startup phases. The third is a set of x-ray Bragg spectrometers, located outside of the tokamak hall, aimed at informing on the ion temperature as an indirect constraint to reduce uncertainties on the fusion power, on providing plasma rotation velocity estimates, and on observing impurity emission. Finally, more technical details are given on the beamlines at the end of which the spectrometers are located. It explains how their design allows us to ensure tritium containment and limit neutron radiation while providing a straight view into the plasma that can also be used for testing new innovative sensors.
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Affiliation(s)
- D Vezinet
- Commonwealth Fusion Systems, Devens, Massachusetts 01434, USA
| | - C J Perks
- Plasma Science and Fusion Center, MIT, Cambridge, Massachusetts 02139, USA
| | - E Panontin
- Plasma Science and Fusion Center, MIT, Cambridge, Massachusetts 02139, USA
| | - S Normile
- Plasma Science and Fusion Center, MIT, Cambridge, Massachusetts 02139, USA
| | - R A Tinguely
- Plasma Science and Fusion Center, MIT, Cambridge, Massachusetts 02139, USA
| | - J Rice
- Plasma Science and Fusion Center, MIT, Cambridge, Massachusetts 02139, USA
| | - M Reinke
- Commonwealth Fusion Systems, Devens, Massachusetts 01434, USA
| | - M Cario
- Commonwealth Fusion Systems, Devens, Massachusetts 01434, USA
| | - J Raimond
- Commonwealth Fusion Systems, Devens, Massachusetts 01434, USA
| | - A Hoffmann
- Commonwealth Fusion Systems, Devens, Massachusetts 01434, USA
| | - E Dubas
- Commonwealth Fusion Systems, Devens, Massachusetts 01434, USA
| | - A Saltos
- Commonwealth Fusion Systems, Devens, Massachusetts 01434, USA
| | - R Kennedy
- Commonwealth Fusion Systems, Devens, Massachusetts 01434, USA
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5
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Weaver C, Stapelberg M, Short MP, Wylie A, Artalejo EB. Automated transient grating spectroscopy mapping and signal control for large samples. THE REVIEW OF SCIENTIFIC INSTRUMENTS 2024; 95:074902. [PMID: 38984885 DOI: 10.1063/5.0202262] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Abstract] [Track Full Text] [Subscribe] [Scholar Register] [Received: 02/02/2024] [Accepted: 06/21/2024] [Indexed: 07/11/2024]
Abstract
We present developments for the mapping of large areas using transient grating spectroscopy (TGS) that allow for smoother, larger, autonomous measurements of material samples. The addition of a precise linear stage in the direction parallel to laser sampling coupled with signal optimizing control allows for hands free, self-correcting measurements. In addition, the simplification of the sample holding design to a form that is small enough to mount directly to the linear stage exhibits a straightforward, low-cost solution for automated TGS applications. This capability is demonstrated by taking large uninterrupted maps of gradient wafers, and the results are validated on calibrated tungsten samples and control TGS samples from gradient wafers.
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Affiliation(s)
- Colin Weaver
- Department of Nuclear Science and Engineering, Massachusetts Institute of Technology, Cambridge, Massachusetts 02139, USA
| | - Myles Stapelberg
- Department of Nuclear Science and Engineering, Massachusetts Institute of Technology, Cambridge, Massachusetts 02139, USA
| | - Michael P Short
- Department of Nuclear Science and Engineering, Massachusetts Institute of Technology, Cambridge, Massachusetts 02139, USA
| | - Angus Wylie
- Department of Nuclear Science and Engineering, Massachusetts Institute of Technology, Cambridge, Massachusetts 02139, USA
| | - Elena Botica Artalejo
- Department of Nuclear Science and Engineering, Massachusetts Institute of Technology, Cambridge, Massachusetts 02139, USA
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6
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Devitre AR, Fischer DX, Woller KB, Clark BC, Short MP, Whyte DG, Hartwig ZS. A facility for cryogenic ion irradiation and in situ characterization of rare-earth barium copper oxide superconducting tapes. THE REVIEW OF SCIENTIFIC INSTRUMENTS 2024; 95:063907. [PMID: 38921059 DOI: 10.1063/5.0200936] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Abstract] [Track Full Text] [Subscribe] [Scholar Register] [Received: 01/29/2024] [Accepted: 06/03/2024] [Indexed: 06/27/2024]
Abstract
Superconducting magnets based on Rare Earth Barium Copper Oxides (REBCO) offer transformative capabilities in the fields of fusion energy, high energy physics, and space exploration. A challenge shared by these applications is the limited lifetime of REBCO due to radiation damage sustained during operation. Here we present a new ion-beam facility that enables simultaneous cryogenic irradiation and in situ characterization of commercial REBCO tapes. The ion source provides spatially uniform fluxes up to 1018 protons/m2s with kinetic energies up to 3.4 MeV, in addition to helium and higher-Z species. Using this facility, we can induce uniform damage profiles in the first 10-20 µm of REBCO tapes with less than 0.25 appm of hydrogen implanted in REBCO after a dose of 1020 protons/m2. The tape can be held between 20 and 300 K with an accuracy of ±0.1 K and is connected to a four-point probe measuring the critical current, Ic, and critical temperature, Tc, before, during, and after irradiation with transport current ranging from 100 nA to 100 A, and a typical voltage noise less than 0.1 μV. These capabilities are presently used to study the effect of irradiation temperature on REBCO performance change during and after proton bombardment, to assess the possibility of Ic and Tc recovery after irradiation through thermal annealing, and to explore the instantaneous and recoverable suppression of Ic and Tc observed during irradiation.
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Affiliation(s)
- A R Devitre
- Plasma Science and Fusion Center, Massachusetts Institute of Technology Cambridge, Massachusetts 02139, USA
| | - D X Fischer
- Plasma Science and Fusion Center, Massachusetts Institute of Technology Cambridge, Massachusetts 02139, USA
| | - K B Woller
- Plasma Science and Fusion Center, Massachusetts Institute of Technology Cambridge, Massachusetts 02139, USA
| | - B C Clark
- Plasma Science and Fusion Center, Massachusetts Institute of Technology Cambridge, Massachusetts 02139, USA
| | - M P Short
- Plasma Science and Fusion Center, Massachusetts Institute of Technology Cambridge, Massachusetts 02139, USA
| | - D G Whyte
- Plasma Science and Fusion Center, Massachusetts Institute of Technology Cambridge, Massachusetts 02139, USA
| | - Z S Hartwig
- Plasma Science and Fusion Center, Massachusetts Institute of Technology Cambridge, Massachusetts 02139, USA
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7
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Wan B, Xu G. Steady-state burning plasma: a new stage in the development of magnetic confinement fusion energy. Natl Sci Rev 2023; 10:nwad217. [PMID: 37954196 PMCID: PMC10632788 DOI: 10.1093/nsr/nwad217] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Abstract] [Key Words] [Grants] [Track Full Text] [Figures] [Journal Information] [Subscribe] [Scholar Register] [Received: 06/01/2023] [Revised: 07/11/2023] [Accepted: 08/12/2023] [Indexed: 11/14/2023] Open
Abstract
Over the past 20 years, advances in tokamak physics and technology have prepared the field of magnetic confinement fusion research for the next step toward a steady-state burning plasma.
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Affiliation(s)
- Baonian Wan
- Institute of Plasma Physics, Chinese Academy of Sciences, China
| | - Guosheng Xu
- Institute of Plasma Physics, Chinese Academy of Sciences, China
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8
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Molodyk A, Larbalestier DC. The prospects of high-temperature superconductors. Science 2023; 380:1220-1222. [PMID: 37347860 DOI: 10.1126/science.abq4137] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Abstract] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 06/24/2023]
Abstract
Overcoming cost barriers could make high-temperature superconductors pervasive.
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Affiliation(s)
- Alexander Molodyk
- Faraday Factory Japan, 2-3-19 Hashimotodai, Midori-ku, Sagamihara, Kanagawa, Japan
| | - David C Larbalestier
- Applied Superconductivity Center, National High Magnetic Field Laboratory, Florida State University, Tallahassee, FL, USA
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9
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Embedded conductors in solidified molten metal for winding packs for high-field stellarators. FUSION ENGINEERING AND DESIGN 2023. [DOI: 10.1016/j.fusengdes.2023.113495] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 02/10/2023]
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10
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Kembleton R. Technological features of a commercial fusion power plant, and the gap from DEMO. FUSION ENGINEERING AND DESIGN 2023. [DOI: 10.1016/j.fusengdes.2023.113544] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 02/12/2023]
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11
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Badalassi V, Sircar A, Solberg JM, Bae JW, Borowiec K, Huang P, Smolentsev S, Peterson E. FERMI: Fusion Energy Reactor Models Integrator. FUSION SCIENCE AND TECHNOLOGY 2023. [DOI: 10.1080/15361055.2022.2151818] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 04/03/2023]
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12
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Thomas M, Salvador H, Clark T, Lang E, Hattar K, Mathaudhu S. Thermal and Radiation Stability in Nanocrystalline Cu. NANOMATERIALS (BASEL, SWITZERLAND) 2023; 13:1211. [PMID: 37049305 PMCID: PMC10096574 DOI: 10.3390/nano13071211] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Abstract] [Key Words] [Track Full Text] [Figures] [Subscribe] [Scholar Register] [Received: 03/01/2023] [Revised: 03/22/2023] [Accepted: 03/23/2023] [Indexed: 06/19/2023]
Abstract
Nanocrystalline metals have presented intriguing possibilities for use in radiation environments due to their high grain boundary volume, serving as enhanced irradiation-induced defect sinks. Their promise has been lessened due to the propensity for nanocrystalline metals to suffer deleterious grain growth from combinations of irradiation and/or elevated homologous temperature. While approaches for stabilizing such materials against grain growth are the subject of current research, there is still a lack of central knowledge on the irradiation-grain boundary interactions in pure metals despite many studies on the same. Due to the breadth of available reports, we have critically reviewed studies on irradiation and thermal stability in pure, nanocrystalline copper (Cu) as a model FCC material, and on a few dilute Cu-based alloys. Our study has shown that, viewed collectively, there are large differences in interpretation of irradiation-grain boundary interactions, primarily due to a wide range of irradiation environments and variability in materials processing. We discuss the sources of these differences and analyses herein. Then, with the goal of gaining a more overarching mechanistic understanding of grain size stability in pure materials under irradiation, we provide several key recommendations for making meaningful evaluations across materials with different processing and under variable irradiation conditions.
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Affiliation(s)
- Marie Thomas
- Metallurgical and Materials Engineering Department, Colorado School of Mines, Golden, CO 80401, USA
| | - Heather Salvador
- Mechanical Engineering Department, University of California, Riverside, CA 92521, USA
| | - Trevor Clark
- Materials Science and Engineering Program, University of California, Riverside, CA 92521, USA
- Center for Integrated Nanotechnologies, Sandia National Laboratories, Albuquerque, NM 87185, USA
| | - Eric Lang
- Center for Integrated Nanotechnologies, Sandia National Laboratories, Albuquerque, NM 87185, USA
- Department of Nuclear Engineering, University of New Mexico, Albuquerque, NM 87131, USA
| | - Khalid Hattar
- Center for Integrated Nanotechnologies, Sandia National Laboratories, Albuquerque, NM 87185, USA
- Department of Nuclear Engineering, University of Tennessee, Knoxville, TN 37996, USA
| | - Suveen Mathaudhu
- Metallurgical and Materials Engineering Department, Colorado School of Mines, Golden, CO 80401, USA
- Mechanical Engineering Department, University of California, Riverside, CA 92521, USA
- Materials Science and Engineering Program, University of California, Riverside, CA 92521, USA
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13
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Weisberg DB, Leuer J, McClenaghan J, Yu JH, Wehner W, McLaughlin K, Abrams T, Barr J, Grierson B, Lyons B, MacDonald JR, Meneghini O, Petty CC, Pinsker RI, Sinclair G, Solomon WM, Taylor T, Thackston K, Thomas D, van Compernolle B, VanZeeland M, Zeller K. An Integrated Design Study for an Advanced Tokamak to Close Physics Gaps in Energy Confinement and Power Exhaust. FUSION SCIENCE AND TECHNOLOGY 2023. [DOI: 10.1080/15361055.2022.2149210] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 02/25/2023]
Affiliation(s)
- D. B. Weisberg
- General Atomics, PO Box 85608, San Diego, California 92186-5608
| | - J. Leuer
- General Atomics, PO Box 85608, San Diego, California 92186-5608
| | - J. McClenaghan
- General Atomics, PO Box 85608, San Diego, California 92186-5608
| | - J. H. Yu
- General Atomics, PO Box 85608, San Diego, California 92186-5608
| | - W. Wehner
- General Atomics, PO Box 85608, San Diego, California 92186-5608
| | - K. McLaughlin
- General Atomics, PO Box 85608, San Diego, California 92186-5608
| | - T. Abrams
- General Atomics, PO Box 85608, San Diego, California 92186-5608
| | - J. Barr
- General Atomics, PO Box 85608, San Diego, California 92186-5608
| | - B. Grierson
- General Atomics, PO Box 85608, San Diego, California 92186-5608
| | - B. Lyons
- General Atomics, PO Box 85608, San Diego, California 92186-5608
| | - J. R. MacDonald
- General Atomics, PO Box 85608, San Diego, California 92186-5608
| | - O. Meneghini
- General Atomics, PO Box 85608, San Diego, California 92186-5608
| | - C. C. Petty
- General Atomics, PO Box 85608, San Diego, California 92186-5608
| | - R. I. Pinsker
- General Atomics, PO Box 85608, San Diego, California 92186-5608
| | - G. Sinclair
- General Atomics, PO Box 85608, San Diego, California 92186-5608
| | - W. M. Solomon
- General Atomics, PO Box 85608, San Diego, California 92186-5608
| | - T. Taylor
- General Atomics, PO Box 85608, San Diego, California 92186-5608
| | - K. Thackston
- General Atomics, PO Box 85608, San Diego, California 92186-5608
| | - D. Thomas
- General Atomics, PO Box 85608, San Diego, California 92186-5608
| | | | - M. VanZeeland
- General Atomics, PO Box 85608, San Diego, California 92186-5608
| | - K. Zeller
- General Atomics, PO Box 85608, San Diego, California 92186-5608
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Aimetta A, Abrate N, Dulla S, Froio A. A Nonintrusive Nuclear Data Uncertainty Propagation Study for the ARC Fusion Reactor Design. NUCL SCI ENG 2023. [DOI: 10.1080/00295639.2022.2153638] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 02/11/2023]
Affiliation(s)
- Alex Aimetta
- NEMO Group, Politecnico di Torino, Dipartimento Energia, Corso Duca degli Abruzzi, 24 - 10129, Torino, Italy
| | - Nicolò Abrate
- NEMO Group, Politecnico di Torino, Dipartimento Energia, Corso Duca degli Abruzzi, 24 - 10129, Torino, Italy
| | - Sandra Dulla
- NEMO Group, Politecnico di Torino, Dipartimento Energia, Corso Duca degli Abruzzi, 24 - 10129, Torino, Italy
| | - Antonio Froio
- NEMO Group, Politecnico di Torino, Dipartimento Energia, Corso Duca degli Abruzzi, 24 - 10129, Torino, Italy
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15
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Bohm TD, Lindley BA. Initial Neutronics Investigation of a Chlorine Salt-Based Breeder Blanket. FUSION SCIENCE AND TECHNOLOGY 2023. [DOI: 10.1080/15361055.2022.2136923] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 01/27/2023]
Affiliation(s)
- Tim D. Bohm
- University of Wisconsin-Madison, Department of Engineering Physics, 1500 Engineering Drive, Madison, Wisconsin
| | - Ben A. Lindley
- University of Wisconsin-Madison, Department of Engineering Physics, 1500 Engineering Drive, Madison, Wisconsin
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16
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Teyber R, Weiss J, Marchevsky M, Prestemon S, van der Laan D. Current distribution monitoring enables quench and damage detection in superconducting fusion magnets. Sci Rep 2022; 12:22503. [PMID: 36577760 PMCID: PMC9797567 DOI: 10.1038/s41598-022-26592-2] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Abstract] [Key Words] [Track Full Text] [Figures] [Journal Information] [Subscribe] [Scholar Register] [Received: 07/26/2022] [Accepted: 12/16/2022] [Indexed: 12/29/2022] Open
Abstract
Fusion magnets made from high temperature superconducting ReBCO CORC® cables are typically protected with quench detection systems that use voltage or temperature measurements to trigger current extraction processes. Although small coils with low inductances have been demonstrated, magnet protection remains a challenge and magnets are typically operated with little knowledge of the intrinsic performance parameters. We propose a protection framework based on current distribution monitoring in fusion cables with limited inter-cable current sharing. By employing inverse Biot-Savart techniques to distributed Hall probe arrays around CORC® Cable-In-Conduit-Conductor (CICC) terminations, individual cable currents are recreated and used to extract the parameters of a predictive model. These parameters are shown to be of value for detecting conductor damage and defining safe magnet operating limits. The trained model is then used to predict cable current distributions in real-time, and departures between predictions and inverse Biot-Savart recreated current distributions are used to generate quench triggers. The methodology shows promise for quality control, operational planning and real-time quench detection in bundled CORC® cables for compact fusion reactors.
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Affiliation(s)
- Reed Teyber
- grid.184769.50000 0001 2231 4551Lawrence Berkeley National Laboratory, Berkeley, CA 94720 USA
| | - Jeremy Weiss
- grid.455110.4Advanced Conductor Technologies, Boulder, CO 80309 USA ,grid.266190.a0000000096214564Department of Physics, University of Colorado, Boulder, CO 80309 USA
| | - Maxim Marchevsky
- grid.184769.50000 0001 2231 4551Lawrence Berkeley National Laboratory, Berkeley, CA 94720 USA
| | - Soren Prestemon
- grid.184769.50000 0001 2231 4551Lawrence Berkeley National Laboratory, Berkeley, CA 94720 USA
| | - Danko van der Laan
- grid.455110.4Advanced Conductor Technologies, Boulder, CO 80309 USA ,grid.266190.a0000000096214564Department of Physics, University of Colorado, Boulder, CO 80309 USA
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17
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Segantin S, Meschini S, Testoni R, Zucchetti M. Preliminary investigation of neutron shielding compounds for ARC-class tokamaks. FUSION ENGINEERING AND DESIGN 2022. [DOI: 10.1016/j.fusengdes.2022.113335] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/17/2022]
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18
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The corrosion effects of neutron activation of 2LiF-BeF2 (FLiBe). NUCLEAR MATERIALS AND ENERGY 2022. [DOI: 10.1016/j.nme.2022.101289] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/25/2022]
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19
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Xu H, Kim SY, Chen D, Monchoux J, Voisin T, Sun C, Li J. Materials Genomics Search for Possible Helium-Absorbing Nano-Phases in Fusion Structural Materials. ADVANCED SCIENCE (WEINHEIM, BADEN-WURTTEMBERG, GERMANY) 2022; 9:e2203555. [PMID: 36180389 PMCID: PMC9661827 DOI: 10.1002/advs.202203555] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Abstract] [Key Words] [MESH Headings] [Grants] [Track Full Text] [Figures] [Subscribe] [Scholar Register] [Received: 06/19/2022] [Revised: 08/07/2022] [Indexed: 06/16/2023]
Abstract
Civilian fusion demands structural materials that can withstand the harsh environments imposed inside fusion plasma reactors. The structural materials often transmute under 14.1 MeV fast neutrons, producing helium (He), which embrittles the grain boundary (GB) network. Here, it is shown that neutron-friendly and mechanically strong nano-phases with atomic-scale free volume can have low He-embedding energy E emb ${\mathcal{E}}_{\mathrm{emb}}$ and >10 at.% He-absorbing capacity, and can be especially advantageous for soaking up He on top of resisting radiation damage and creep, provided they have thermodynamic compatibility with the matrix phase, satisfactory equilibrium wetting angle, as well as a high enough melting point. The preliminary experimental demonstration proves that E emb ${\mathcal{E}}_{\mathrm{emb}}$ is a good ab initio predictor of He shielding potency in nano-heterophase materials, and thus, E emb ${\mathcal{E}}_{\mathrm{emb}}$ is used as a key feature for computational screening. In this context, a list of viable compounds expected to be good He-absorbing nano-phases is presented, taking into account E emb ${\mathcal{E}}_{\mathrm{emb}}$ , the neutron absorption and activation cross-sections, the elastic moduli, melting temperature, the thermodynamic compatibility, and the equilbrium wetting angle of the nano-phases with the Fe matrix as an example.
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Affiliation(s)
- Haowei Xu
- Department of Nuclear Science and EngineeringMassachusetts Institute of TechnologyCambridgeMA02139USA
| | - So Yeon Kim
- Department of Materials Science and EngineeringMassachusetts Institute of TechnologyCambridgeMA02139USA
| | - Di Chen
- Department of Physics and Texas Center for SuperconductivityUniversity of HoustonHoustonTX77204USA
| | - Jean‐Phillippe Monchoux
- Centre for Materials Elaboration and Structural StudiesUniversity of ToulouseFrench National Centre for Scientific ResearchToulouse31055France
| | - Thomas Voisin
- Materials Science DivisionLawrence Livermore National LaboratoryLivermoreCA94550USA
| | - Cheng Sun
- Characterization and Advanced PIE DivisionIdaho National LaboratoryIdaho FallsID83415USA
| | - Ju Li
- Department of Nuclear Science and EngineeringMassachusetts Institute of TechnologyCambridgeMA02139USA
- Department of Materials Science and EngineeringMassachusetts Institute of TechnologyCambridgeMA02139USA
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20
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Smolentsev S. Modeling of Transport Processes in Liquid-Metal Fusion Blankets: Past, Present, and Future. FUSION SCIENCE AND TECHNOLOGY 2022. [DOI: 10.1080/15361055.2022.2116905] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/04/2022]
Affiliation(s)
- S. Smolentsev
- Oak Ridge National Laboratory, 1 Bethel Valley Road, Oak Ridge, Tennessee 37830
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21
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Ferrero G, Meschini S, Testoni R. A Preliminary CFD and Tritium Transport Analysis for ARC Blanket. FUSION SCIENCE AND TECHNOLOGY 2022. [DOI: 10.1080/15361055.2022.2096365] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/04/2022]
Affiliation(s)
- Gabriele Ferrero
- Politecnico di Torino, Dipartimento Energia “Galileo Ferraris,” Corso Duca degli Abruzzi, 24, Torino, Italy
| | - Samuele Meschini
- Politecnico di Torino, Dipartimento Energia “Galileo Ferraris,” Corso Duca degli Abruzzi, 24, Torino, Italy
| | - Raffaella Testoni
- Politecnico di Torino, Dipartimento Energia “Galileo Ferraris,” Corso Duca degli Abruzzi, 24, Torino, Italy
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22
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Langford L, Winner N, Hwang A, Williams H, Vergari L, Scarlat RO, Asta M. Constant-Potential Molecular Dynamics Simulations of Molten-Salt Double Layers for FLiBe and FLiNaK. J Chem Phys 2022; 157:094705. [DOI: 10.1063/5.0097697] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Abstract] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/14/2022] Open
Abstract
We report the results of constant-potential molecular dynamics simulations of the double- layer interface between molten FLiBe and FLiNaK fluoride mixtures and idealized solid electrodes. Employing methods similar to those used in studies of chloride double layers, we compute the structure and differential capacitance of molten fluoride electric double layers as a function of applied voltage. The role of molten salt structure is probed through comparisons between FLiBe and FLiNaK, which serve as models for strong and weak associate- forming salts, respectively. In FLiBe, screening involves changes in Be-F-Be angles and alignment of the oligomers parallel to the electrode, while in FLiNaK the electric field is screened mainly by rearrangement of individual ions, predominantly the polarizable potassium cation.
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Affiliation(s)
- Luke Langford
- Materials Science and Engineering, University of California Berkeley, United States of America
| | | | - Andrea Hwang
- University of California Berkeley, United States of America
| | - Haley Williams
- University of California Berkeley, United States of America
| | - Lorenzo Vergari
- Nuclear Engineering, University of California Berkeley, United States of America
| | | | - Mark Asta
- Department of Materials Science and Engineering, University of California Berkeley, United States of America
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23
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Ferry SE, Woller KB, Peterson EE, Sorensen C, Whyte DG. The LIBRA Experiment: Investigating Robust Tritium Accountancy in Molten FLiBe Exposed to a D-T Fusion Neutron Spectrum. FUSION SCIENCE AND TECHNOLOGY 2022. [DOI: 10.1080/15361055.2022.2078136] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/04/2022]
Affiliation(s)
- Sara E. Ferry
- Massachusetts Institute of Technology Plasma Science and Fusion Center, 175 Albany Street, Cambridge, Massachusetts 02139
| | - Kevin B. Woller
- Massachusetts Institute of Technology Plasma Science and Fusion Center, 175 Albany Street, Cambridge, Massachusetts 02139
| | - Ethan E. Peterson
- Massachusetts Institute of Technology Plasma Science and Fusion Center, 175 Albany Street, Cambridge, Massachusetts 02139
| | - Caroline Sorensen
- Massachusetts Institute of Technology Plasma Science and Fusion Center, 175 Albany Street, Cambridge, Massachusetts 02139
| | - Dennis G. Whyte
- Massachusetts Institute of Technology Plasma Science and Fusion Center, 175 Albany Street, Cambridge, Massachusetts 02139
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24
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Al Isawi WA, Zeller M, Mezei G. Supramolecular Incarceration and Extraction of Tetrafluoroberyllate from Water by Nanojars. Inorg Chem 2022; 61:8611-8622. [PMID: 35617675 DOI: 10.1021/acs.inorgchem.2c01198] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Abstract] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/29/2022]
Abstract
The previously unexplored noncovalent binding of the highly toxic tetrafluoroberyllate anion (BeF42-) and its extraction from water into organic solvents are presented. Nanojars resemble anion-binding proteins in that they also possess an inner anion binding pocket lined by a multitude of H-bond donors (OH groups), which wrap around the incarcerated anion and completely isolate it from the surrounding medium. The BeF4-binding propensity of [BeF4⊂{CuII(OH)(pz)}n]2- (pz = pyrazolate; n = 27-32) nanojars of different sizes is investigated using an array of techniques including mass spectrometry, paramagnetic 1H, 9Be, and 19F NMR spectroscopy, and X-ray crystallography, along with thermal stability studies in solution and chemical stability studies toward acidity and Ba2+ ions. The latter is found to be unable to precipitate the insoluble BaBeF4 from nanojar solutions, indicating a very strong binding of the BeF42- anion by nanojars. 9Be and 19F NMR spectroscopy allows for the unprecedented direct probing of the incarcerated anion in a nanojar and, along with 1H NMR studies, reveals the fluxional structure of nanojars and their inner anion-binding pockets. Single-crystal X-ray diffraction provides the crystal and molecular structures of (Bu4N)2[BeF4⊂{Cu(OH)(pz)}32], which contains a novel Cux-ring combination (x = 9 + 14 + 9), (Bu4N)2[BeF4⊂{Cu(OH)(pz)}8+14+9], and (Bu4N)2[BeF4⊂{Cu(OH)(pz)}6+12+10] and offers detailed structural parameters related to the supramolecular binding of BeF42- in these nanojars. The extraction of BeF42- from water into organic solvents, including the highly hydrophobic solvent n-heptane, demonstrates that nanojars are efficient binding and extracting agents not only for oxoanions but also for fluoroanions.
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Affiliation(s)
- Wisam A Al Isawi
- Department of Chemistry, Western Michigan University, Kalamazoo, Michigan 49008, United States
| | - Matthias Zeller
- Department of Chemistry, Purdue University, West Lafayette, Indiana 47907, United States
| | - Gellert Mezei
- Department of Chemistry, Western Michigan University, Kalamazoo, Michigan 49008, United States
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25
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Development of an object-oriented, thermal-hydraulics model for ARC FLiBe loop safety assessment. FUSION ENGINEERING AND DESIGN 2022. [DOI: 10.1016/j.fusengdes.2022.113095] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/22/2022]
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26
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Zhang D, Richardson P, Tu H, O’Connor J, Kisi E, Zhang H, Shi L. Radiation damage of MoAlB at elevated temperatures: Investigating MAB phases as potential neutron shielding materials. Ann Ital Chir 2022. [DOI: 10.1016/j.jeurceramsoc.2021.11.017] [Citation(s) in RCA: 2] [Impact Index Per Article: 1.0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/30/2022]
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27
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Aimetta A, Abrate N, Dulla S, Froio A. Neutronic Analysis of the Fusion Reactor ARC: Monte Carlo Simulations with the Serpent Code. FUSION SCIENCE AND TECHNOLOGY 2022. [DOI: 10.1080/15361055.2021.2003151] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/04/2022]
Affiliation(s)
- Alex Aimetta
- Politecnico di Torino, Dipartimento Energia, NEMO Group, Corso Duca degli Abruzzi, Torino 24 – 10129, Italy
| | - Nicolò Abrate
- Politecnico di Torino, Dipartimento Energia, NEMO Group, Corso Duca degli Abruzzi, Torino 24 – 10129, Italy
| | - Sandra Dulla
- Politecnico di Torino, Dipartimento Energia, NEMO Group, Corso Duca degli Abruzzi, Torino 24 – 10129, Italy
| | - Antonio Froio
- Politecnico di Torino, Dipartimento Energia, NEMO Group, Corso Duca degli Abruzzi, Torino 24 – 10129, Italy
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28
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Power conversion from spherical tokamak test reactor with helium-cooled and water-cooled blanket. FUSION ENGINEERING AND DESIGN 2022. [DOI: 10.1016/j.fusengdes.2022.113024] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/24/2022]
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29
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Linden Y, Iliffe WR, He G, Danaie M, Fischer DX, Eisterer M, Speller SC, Grovenor CRM. Analysing neutron radiation damage in YBa 2 Cu 3 O 7-x high temperature superconductor tapes. J Microsc 2021; 286:3-12. [PMID: 34879153 DOI: 10.1111/jmi.13078] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Abstract] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Received: 08/17/2021] [Revised: 10/27/2021] [Accepted: 11/29/2021] [Indexed: 11/30/2022]
Abstract
Superconducting windings will be necessary in future fusion reactors to generate the strong magnetic fields needed to confine the plasma, and these superconducting materials will inevitably be exposed to neutron damage. It is known that this exposure results in the creation of isolated damage cascades, but the presence of these defects alone is not sufficient to explain the degradation of macroscopic superconducting properties and a quantitative method is needed to assess the subtle lattice damage in between the clusters. We have studied REBCO coated conductors irradiated with neutrons to a cumulative dose of 3.3×1022 n*m-2 that show a degradation of both Tc and Jc values, and use HRTEM analysis to show that this irradiation introduces ∼10 nm amorphous collision cascades. In addition we introduce a new method for the analysis of these images to quantify the degree of lattice disorder in the apparently perfect matrix between these cascades. This method utilises Fast Fourier and Discrete Cosine Transformations of a statistically-relevant number of HRTEM images of pristine, neutron-irradiated, and amorphous samples, and extracts the degree of randomness in terms of entropy values. Our results show that these entropy values in both mid-frequency band FFT and DCT domains correlate with the expected level of lattice damage, with the pristine samples having the lowest and the fully amorphous regions the highest entropy values. Our methodology allows us to quantify 'invisible' lattice damage to and correlate these values to the degradation of superconducting properties, and also has relevance for a wider range of applications in the field of electron microscopy where small changes in lattice perfection need to be measured. This article is protected by copyright. All rights reserved.
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Affiliation(s)
- Y Linden
- Department of Materials, University of Oxford, Parks Rd, Oxford, OX1 3PH, UK
| | - W R Iliffe
- Department of Materials, University of Oxford, Parks Rd, Oxford, OX1 3PH, UK
| | - G He
- Department of Materials, University of Oxford, Parks Rd, Oxford, OX1 3PH, UK
| | - M Danaie
- Electron Physical Sciences Imaging Centre (ePSIC), Diamond Light Source, Didcot, UK
| | - D X Fischer
- Plasma Science and Fusion Center, Massachusetts Institute of Technology, Cambridge, MA, USA
| | - M Eisterer
- Atominstitut, TU Wien, Stadionallee2, A-1020, Vienna, Austria
| | - S C Speller
- Department of Materials, University of Oxford, Parks Rd, Oxford, OX1 3PH, UK
| | - C R M Grovenor
- Department of Materials, University of Oxford, Parks Rd, Oxford, OX1 3PH, UK
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30
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Conceptual design of a liquid-metal divertor for the European DEMO. FUSION ENGINEERING AND DESIGN 2021. [DOI: 10.1016/j.fusengdes.2021.112812] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.7] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/23/2022]
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31
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Kessel CE, Bohm T, Tillack MS, Titus P, Zhai Y. The Compactness and Inboard Radial Build of Fusion Nuclear Devices. FUSION SCIENCE AND TECHNOLOGY 2021. [DOI: 10.1080/15361055.2021.1909988] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/20/2022]
Affiliation(s)
- C. E. Kessel
- Oak Ridge National Laboratory, P.O. Box 2008, Oak Ridge, Tennessee 37831-6169
| | - T. Bohm
- University of Wisconsin, Madison, Wisconsin
| | | | - P. Titus
- Princeton Plasma Physics Laboratory, Princeton, New Jersey
| | - Y. Zhai
- Princeton Plasma Physics Laboratory, Princeton, New Jersey
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32
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Meschini S, Zucchetti M, Pagliuca E. Development of an Advanced-Fuel Nuclear Fusion Experiment. FUSION SCIENCE AND TECHNOLOGY 2021. [DOI: 10.1080/15361055.2021.1921461] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/20/2022]
Affiliation(s)
- S. Meschini
- Politecnico di Torino, Department of Energy, Corso Duca Degli Abruzzi 24, 10129 Torino, Italy
| | - M. Zucchetti
- Politecnico di Torino, Department of Energy, Corso Duca Degli Abruzzi 24, 10129 Torino, Italy
- Massachusetts Institute of Technology, Cambridge, Massachusetts
| | - Enrico Pagliuca
- Politecnico di Torino, Department of Energy, Corso Duca Degli Abruzzi 24, 10129 Torino, Italy
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33
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Fradera J, Sádaba S, Calvo F, Ha S, Merriman S, Gordillo P, Connell J, Elfaraskoury A, Echeveste B. Pre-conceptual design of an encapsulated breeder commercial blanket for the STEP fusion reactor. FUSION ENGINEERING AND DESIGN 2021. [DOI: 10.1016/j.fusengdes.2021.112909] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/28/2022]
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34
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High temperature superconductors for fusion applications and new developments for the HTS CroCo conductor design. FUSION ENGINEERING AND DESIGN 2021. [DOI: 10.1016/j.fusengdes.2021.112739] [Citation(s) in RCA: 5] [Impact Index Per Article: 1.7] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/15/2022]
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35
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Boullon R, Jaboulay JC, Aubert J. Molten salt breeding blanket: Investigations and proposals of pre-conceptual design options for testing in DEMO. FUSION ENGINEERING AND DESIGN 2021. [DOI: 10.1016/j.fusengdes.2021.112707] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.7] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/30/2022]
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36
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Meschini S, Testoni R, Segantin S, Zucchetti M. ARC reactor: A preliminary tritium environmental impact study. FUSION ENGINEERING AND DESIGN 2021. [DOI: 10.1016/j.fusengdes.2021.112340] [Citation(s) in RCA: 3] [Impact Index Per Article: 1.0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/24/2022]
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37
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Robertson SG, Short MP. Design and performance of a molten fluoride salt-compatible optical thermophysical property measurement system. THE REVIEW OF SCIENTIFIC INSTRUMENTS 2021; 92:064905. [PMID: 34243588 DOI: 10.1063/5.0049727] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.7] [Reference Citation Analysis] [Abstract] [Track Full Text] [Subscribe] [Scholar Register] [Received: 03/08/2021] [Accepted: 05/27/2021] [Indexed: 06/13/2023]
Abstract
Accurate knowledge of molten salt thermophysical properties is crucial to optimize the efficiency, safety, and reliability of molten salt based energy applications. For molten fluorides, currently of high interest for fission and fusion reactors, data regarding these properties are either poor or non-existent. Thermal diffusivity and sound speed in particular play important roles in the modeling of a reactor's steady state, transient, and accident scenarios. Fluoride salt-compatible property measurement systems have thus far been the bottleneck in accurately obtaining these properties. We present the design of an optical system optimized for molten fluoride salt thermophysical property measurement, along with characterization of its thermal performance. Demonstration of system capabilities is achieved through acquisition of sound speed and thermal diffusivity in lithium chloride (LiCl), showing excellent agreement with literature data.
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Affiliation(s)
- Sean G Robertson
- Department of Nuclear Science and Engineering, Massachusetts Institute of Technology, Cambridge, Massachusetts 02139, USA
| | - Michael P Short
- Department of Nuclear Science and Engineering, Massachusetts Institute of Technology, Cambridge, Massachusetts 02139, USA
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38
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Wade MR, Leuer JA. Cost Drivers for a Tokamak-Based Compact Pilot Plant. FUSION SCIENCE AND TECHNOLOGY 2021. [DOI: 10.1080/15361055.2020.1858670] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/22/2022]
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39
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Molodyk A, Samoilenkov S, Markelov A, Degtyarenko P, Lee S, Petrykin V, Gaifullin M, Mankevich A, Vavilov A, Sorbom B, Cheng J, Garberg S, Kesler L, Hartwig Z, Gavrilkin S, Tsvetkov A, Okada T, Awaji S, Abraimov D, Francis A, Bradford G, Larbalestier D, Senatore C, Bonura M, Pantoja AE, Wimbush SC, Strickland NM, Vasiliev A. Development and large volume production of extremely high current density YBa 2Cu 3O 7 superconducting wires for fusion. Sci Rep 2021; 11:2084. [PMID: 33483553 PMCID: PMC7822827 DOI: 10.1038/s41598-021-81559-z] [Citation(s) in RCA: 12] [Impact Index Per Article: 4.0] [Reference Citation Analysis] [Abstract] [Key Words] [Track Full Text] [Download PDF] [Figures] [Journal Information] [Subscribe] [Scholar Register] [Received: 09/17/2020] [Accepted: 01/05/2021] [Indexed: 01/30/2023] Open
Abstract
The fusion power density produced in a tokamak is proportional to its magnetic field strength to the fourth power. Second-generation high temperature superconductor (2G HTS) wires demonstrate remarkable engineering current density (averaged over the full wire), JE, at very high magnetic fields, driving progress in fusion and other applications. The key challenge for HTS wires has been to offer an acceptable combination of high and consistent superconducting performance in high magnetic fields, high volume supply, and low price. Here we report a very high and reproducible JE in practical HTS wires based on a simple YBa2Cu3O7 (YBCO) superconductor formulation with Y2O3 nanoparticles, which have been delivered in just nine months to a commercial fusion customer in the largest-volume order the HTS industry has seen to date. We demonstrate a novel YBCO superconductor formulation without the c-axis correlated nano-columnar defects that are widely believed to be prerequisite for high in-field performance. The simplicity of this new formulation allows robust and scalable manufacturing, providing, for the first time, large volumes of consistently high performance wire, and the economies of scale necessary to lower HTS wire prices to a level acceptable for fusion and ultimately for the widespread commercial adoption of HTS.
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Affiliation(s)
- A Molodyk
- S-Innovations, Moscow, Russia.
- SuperOx, Moscow, Russia.
| | - S Samoilenkov
- S-Innovations, Moscow, Russia
- SuperOx, Moscow, Russia
| | | | - P Degtyarenko
- SuperOx, Moscow, Russia
- Joint Institute for High Temperature, Russian Academy of Sciences, Moscow, Russia
| | - S Lee
- SuperOx Japan, Kanagawa, Japan
| | | | | | | | - A Vavilov
- S-Innovations, Moscow, Russia
- SuperOx, Moscow, Russia
- SuperOx Japan, Kanagawa, Japan
| | - B Sorbom
- Commonwealth Fusion Systems, Cambridge, MA, USA
| | - J Cheng
- Commonwealth Fusion Systems, Cambridge, MA, USA
| | - S Garberg
- Commonwealth Fusion Systems, Cambridge, MA, USA
| | - L Kesler
- Commonwealth Fusion Systems, Cambridge, MA, USA
| | - Z Hartwig
- Massachusetts Institute of Technology, Cambridge, MA, USA
| | - S Gavrilkin
- P.N. Lebedev Physics Institute, Russian Academy of Sciences, Moscow, Russia
| | - A Tsvetkov
- P.N. Lebedev Physics Institute, Russian Academy of Sciences, Moscow, Russia
| | - T Okada
- Institute for Materials Research, Tohoku University, Sendai, Japan
| | - S Awaji
- Institute for Materials Research, Tohoku University, Sendai, Japan
| | - D Abraimov
- National High Magnetic Field Laboratory, Florida State University, Tallahassee, FL, USA
| | - A Francis
- National High Magnetic Field Laboratory, Florida State University, Tallahassee, FL, USA
| | - G Bradford
- National High Magnetic Field Laboratory, Florida State University, Tallahassee, FL, USA
| | - D Larbalestier
- National High Magnetic Field Laboratory, Florida State University, Tallahassee, FL, USA
| | - C Senatore
- University of Geneva, Geneva, Switzerland
| | - M Bonura
- University of Geneva, Geneva, Switzerland
| | - A E Pantoja
- Robinson Research Institute, Victoria University of Wellington, Wellington, New Zealand
| | - S C Wimbush
- Robinson Research Institute, Victoria University of Wellington, Wellington, New Zealand
| | - N M Strickland
- Robinson Research Institute, Victoria University of Wellington, Wellington, New Zealand
| | - A Vasiliev
- National Research Centre "Kurchatov Institute", Moscow, Russia
- Shubnikov Institute of Crystallography, Russian Academy of Sciences, Moscow, Russia
- Moscow Institute of Physics and Technology, Dolgoprudny, Russia
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40
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Zucchetti M, Hartwig Z, Meschini S, Segantin S, Testoni R, Whyte D. ARC reactor: Radioactivity safety assessment and preliminary environmental impact study. FUSION ENGINEERING AND DESIGN 2021. [DOI: 10.1016/j.fusengdes.2020.112132] [Citation(s) in RCA: 3] [Impact Index Per Article: 1.0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/26/2022]
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41
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Neutronic comparison of liquid breeders for ARC-like reactor blankets. FUSION ENGINEERING AND DESIGN 2020. [DOI: 10.1016/j.fusengdes.2020.112013] [Citation(s) in RCA: 4] [Impact Index Per Article: 1.0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/21/2022]
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42
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Segantin S, Testoni R, Zucchetti M. ARC reactor – Neutron irradiation analysis. FUSION ENGINEERING AND DESIGN 2020. [DOI: 10.1016/j.fusengdes.2020.111792] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.5] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/16/2022]
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43
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Manheimer W. Fusion breeding for mid-century, sustainable, carbon free power. Heliyon 2020; 6:e04923. [PMID: 32984613 PMCID: PMC7498859 DOI: 10.1016/j.heliyon.2020.e04923] [Citation(s) in RCA: 3] [Impact Index Per Article: 0.8] [Reference Citation Analysis] [Abstract] [Key Words] [Track Full Text] [Download PDF] [Figures] [Journal Information] [Subscribe] [Scholar Register] [Received: 03/08/2020] [Revised: 05/20/2020] [Accepted: 09/09/2020] [Indexed: 11/17/2022] Open
Abstract
Fusion has often been billed as the ultimate 21st century sustainable energy source. However, not only is the pace of the program glacially slow, it seems to recede further and further into the future. One way to speed up the delivery of economical fusion could be to change the objective from pure fusion, that is the use of the 14 MeV fusion neutron's kinetic energy to boil water; to fusion breeding, that is the former, but also making use of the neutrons 'potential energy' to breed ten times its energy in the form of nuclear fuel to be burned in separate reactors. The requirements of a fusion breeder are greatly relaxed from the requirements for a pure fusion reactor. For instance, ITER, the large tokamak being built by an international consortium in France, could well be the basis of an economical fusion breeder, but would have to clear many more scientific and technical hurdles before it could become the basis for a pure fusion reactor; hurdles it may or may not be able to clear. Even if it clears them, ITER is unlikely to evolve into an economical pure fusion power supply this century. A fusion breeder as could be alternate approach to speed the delivery of economical of fusion power.
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44
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Analysis of the Effects of Electrification of the Road Transport Sector on the Possible Penetration of Nuclear Fusion in the Long-Term European Energy Mix. ENERGIES 2020. [DOI: 10.3390/en13143634] [Citation(s) in RCA: 6] [Impact Index Per Article: 1.5] [Reference Citation Analysis] [Abstract] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/17/2022]
Abstract
The European Roadmap towards the production of electricity from nuclear fusion foresees the potential availability of nuclear fusion power plants (NFPPs) in the second half of this century. The possible penetration of that technology, typically addressed by using the global energy system EUROFusion TIMES Model (ETM), will depend, among other aspects, on its costs compared to those of the other available technologies for electricity production, and on the future electricity demand. This paper focuses on the ongoing electrification process of the transport sector, with special attention devoted to road transport. A survey on the present and forthcoming technologies, as foreseen by several manufacturers and other models, and an international vehicle database are taken into account to develop the new road transport module, then implemented and harmonized inside ETM. Following three different storylines, the computed results are presented in terms of the evolution of the road transport demand in the next decades, fleet composition and CO 2 emissions. The ETM results are in line with many other studies. On one hand, they highlight, for the European road transport energy consumption pattern, the need for dramatic changes in the transport market, if the most ambitious environmental goals are to be pursued. On the other hand, the results also show that NFPP adoption on a commercial scale could be justified within the current projection of the investment costs, if the deep penetration of electricity in the road transport sector also occurs.
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Lumsdaine A, Maingi R, Field KG, Gourlay S, Humphreys D, Katoh Y, Kessel C, Wang X. Perspectives on the FESAC transformative enabling capabilities: Priorities, plans, and Status. FUSION ENGINEERING AND DESIGN 2020. [DOI: 10.1016/j.fusengdes.2020.111529] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/25/2022]
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Segantin S, Bersano A, Falcone N, Testoni R. Exploration of power conversion thermodynamic cycles for ARC fusion reactor. FUSION ENGINEERING AND DESIGN 2020. [DOI: 10.1016/j.fusengdes.2020.111645] [Citation(s) in RCA: 4] [Impact Index Per Article: 1.0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/24/2022]
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Zohuri B, Lam S, Forsberg C. Heat-Pipe Heat Exchangers for Salt-Cooled Fission and Fusion Reactors to Avoid Salt Freezing and Control Tritium: A Review. NUCL TECHNOL 2019. [DOI: 10.1080/00295450.2019.1681222] [Citation(s) in RCA: 6] [Impact Index Per Article: 1.2] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/25/2022]
Affiliation(s)
| | - Stephen Lam
- Massachusetts Institute of Technology, 77 Massachusetts Avenue, Cambridge, Massachusetts 02139
| | - Charles Forsberg
- Massachusetts Institute of Technology, 77 Massachusetts Avenue, Cambridge, Massachusetts 02139
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Forsberg C, Zheng G(T, Ballinger RG, Lam ST. Fusion Blankets and Fluoride-Salt-Cooled High-Temperature Reactors with Flibe Salt Coolant: Common Challenges, Tritium Control, and Opportunities for Synergistic Development Strategies Between Fission, Fusion, and Solar Salt Technologies. NUCL TECHNOL 2019. [DOI: 10.1080/00295450.2019.1691400] [Citation(s) in RCA: 12] [Impact Index Per Article: 2.4] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/25/2022]
Affiliation(s)
- Charles Forsberg
- Massachusetts Institute of Technology, Department of Nuclear Science and Engineering, 77 Massachusetts Avenue, Cambridge, Massachusetts 02139
| | - Guiqiu (Tony) Zheng
- Massachusetts Institute of Technology, Department of Nuclear Science and Engineering, 77 Massachusetts Avenue, Cambridge, Massachusetts 02139
| | - Ronald G. Ballinger
- Massachusetts Institute of Technology, Department of Nuclear Science and Engineering, 77 Massachusetts Avenue, Cambridge, Massachusetts 02139
| | - Stephen T. Lam
- Massachusetts Institute of Technology, Department of Nuclear Science and Engineering, 77 Massachusetts Avenue, Cambridge, Massachusetts 02139
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