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Lindquist EG, Gebhart TE, Elliott D, Garren EW, He Z, Kafle N, Smith CD, Thomas CE, Zinkle SJ, Biewer TM. Reconfiguration of an Electrothermal-Arc Plasma Source for In Situ PMI Studies. Fusion Science and Technology 2021. [DOI: 10.1080/15361055.2021.1909989] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [What about the content of this article? (0)] [Affiliation(s)] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/20/2022]
Affiliation(s)
- E. G. Lindquist
- University of Tennessee, Nuclear Engineering Department, Knoxville, Tennessee
| | - T. E. Gebhart
- Oak Ridge National Laboratory, Fusion Energy Division, Oak Ridge, Tennessee
| | - D. Elliott
- Oak Ridge National Laboratory, Fusion Energy Division, Oak Ridge, Tennessee
| | - E. W. Garren
- Oak Ridge National Laboratory, Fusion Energy Division, Oak Ridge, Tennessee
| | - Z. He
- University of Tennessee, Mechanical Aerospace and Biological Engineering Department, Knoxville, Tennessee
| | - N. Kafle
- Oak Ridge National Laboratory, Fusion Energy Division, Oak Ridge, Tennessee
| | - C. D. Smith
- University of Tennessee, Mechanical Aerospace and Biological Engineering Department, Knoxville, Tennessee
| | - C. E. Thomas
- Third Dimension Technologies LLC, Oak Ridge, Tennessee
| | - S. J. Zinkle
- University of Tennessee, Nuclear Engineering Department, Knoxville, Tennessee
- Oak Ridge National Laboratory, Fusion Energy Division, Oak Ridge, Tennessee
| | - T. M. Biewer
- Oak Ridge National Laboratory, Fusion Energy Division, Oak Ridge, Tennessee
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Beers CJ, Jaramillo C, Reid NC, Schamis H, Allain JP, Caughman JBO, Meitner SJ, Rapp J, Zinkle SJ. Development of the materials analysis and particle probe for Proto-MPEX. Rev Sci Instrum 2021; 92:045108. [PMID: 34243379 DOI: 10.1063/5.0043111] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [What about the content of this article? (0)] [Affiliation(s)] [Abstract] [Track Full Text] [Subscribe] [Scholar Register] [Received: 01/06/2021] [Accepted: 03/31/2021] [Indexed: 06/13/2023]
Abstract
The Prototype Material Plasma Exposure eXperiment (Proto-MPEX) is a linear plasma device being used in plasma source research and development (R&D) for the proposed MPEX. Once the R&D is completed, this device can also be used to perform plasma-material interaction studies. To perform these studies, a new materials analysis and particle probe (MAPP) has been constructed. The MAPP's components are a sample holder and manipulator and a custom vacuum chamber with ports to facilitate surface chemistry diagnostics. The MAPP's overall design enables rapid sample turnaround and in vacuo surface characterization. The surface analysis vacuum chamber has ports for x-ray photoelectron spectroscopy, thermal desorption spectroscopy, back-scatter ion scattering spectroscopy, forward-scatter ion scattering spectroscopy, and direct recoil spectroscopy. The sample manipulator and holder is a Lesker/UHV Multi-Centre Analytical Stage, which is used to place the samples in the exposure region of the Proto-MPEX or the analysis position in the MAPP vacuum chamber. The sample holder has a heating capability of up to 1200 °C for heated exposure and for desorption studies. In this work, we present the MAPP's design and the first tungsten sample exposure with ex situ analysis that shows a surface deposition layer on the exposed target, highlighting the need for additional in situ measurements on the Proto-MPEX.
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Affiliation(s)
- C J Beers
- Department of Energy Science and Engineering, University of Tennessee, Knoxville, Tennessee 37996, USA
| | - C Jaramillo
- Ken and Mary Lindquist Department of Nuclear Engineering, Penn State University, State College, Pennsylvania 16801, USA
| | - N C Reid
- Department of Nuclear, Plasma and Radiological Engineering, University of Illinois, Urbana, Illinois 61801, USA
| | - H Schamis
- Ken and Mary Lindquist Department of Nuclear Engineering, Penn State University, State College, Pennsylvania 16801, USA
| | - J P Allain
- Ken and Mary Lindquist Department of Nuclear Engineering, Penn State University, State College, Pennsylvania 16801, USA
| | - J B O Caughman
- Oak Ridge National Laboratory, Oak Ridge, Tennessee 37831, USA
| | - S J Meitner
- Oak Ridge National Laboratory, Oak Ridge, Tennessee 37831, USA
| | - J Rapp
- Oak Ridge National Laboratory, Oak Ridge, Tennessee 37831, USA
| | - S J Zinkle
- Department of Energy Science and Engineering, University of Tennessee, Knoxville, Tennessee 37996, USA
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Wong C, Malang S, Sawan M, Smolentsev S, Majumdar S, Merrill B, Sze DK, Morley N, Sharafat S, Dagher M, Peterson P, Zhao H, Zinkle SJ, Abdou M, Youssef M. Assessment of First Wall and Blanket Options with the Use of Liquid Breeder. Fusion Science and Technology 2017. [DOI: 10.13182/fst05-a734] [Citation(s) in RCA: 23] [Impact Index Per Article: 3.3] [Reference Citation Analysis] [What about the content of this article? (0)] [Affiliation(s)] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/12/2022]
Affiliation(s)
- C.P.C. Wong
- General Atomics, P.O. Box 85608, San Diego, California 92186-5608
| | - S. Malang
- Fusion Nuclear Technology Consulting, Linkenheim, Germany
| | - M Sawan
- University of Wisconsin, Madison, Wisconsin
| | | | - S. Majumdar
- Argonne National Laboratory, Argonne, Illinois
| | | | - D. K. Sze
- University of California, San Diego, California
| | - N. Morley
- University of California, Los Angeles, California
| | - S Sharafat
- University of California, Los Angeles, California
| | - M. Dagher
- University of California, Los Angeles, California
| | - P. Peterson
- University of California, Berkeley, California
| | - H Zhao
- University of California, Berkeley, California
| | - S. J. Zinkle
- Oak Ridge National Laboratory, Oak Ridge, Tennessee
| | - M. Abdou
- University of California, Los Angeles, California
| | - M Youssef
- University of California, Los Angeles, California
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Sun C, Zheng S, Wei CC, Wu Y, Shao L, Yang Y, Hartwig KT, Maloy SA, Zinkle SJ, Allen TR, Wang H, Zhang X. Superior radiation-resistant nanoengineered austenitic 304L stainless steel for applications in extreme radiation environments. Sci Rep 2015; 5:7801. [PMID: 25588326 PMCID: PMC4295098 DOI: 10.1038/srep07801] [Citation(s) in RCA: 68] [Impact Index Per Article: 7.6] [Reference Citation Analysis] [What about the content of this article? (0)] [Affiliation(s)] [Abstract] [Track Full Text] [Download PDF] [Figures] [Journal Information] [Subscribe] [Scholar Register] [Received: 08/08/2014] [Accepted: 11/28/2014] [Indexed: 11/17/2022] Open
Abstract
Nuclear energy provides more than 10% of electrical power internationally, and the increasing engagement of nuclear energy is essential to meet the rapid worldwide increase in energy demand. A paramount challenge in the development of advanced nuclear reactors is the discovery of advanced structural materials that can endure extreme environments, such as severe neutron irradiation damage at high temperatures. It has been known for decades that high dose radiation can introduce significant void swelling accompanied by precipitation in austenitic stainless steel (SS). Here we report, however, that through nanoengineering, ultra-fine grained (UFG) 304L SS with an average grain size of ~100 nm, can withstand Fe ion irradiation at 500°C to 80 displacements-per-atom (dpa) with moderate grain coarsening. Compared to coarse grained (CG) counterparts, swelling resistance of UFG SS is improved by nearly an order of magnitude and swelling rate is reduced by a factor of 5. M23C6 precipitates, abundant in irradiated CG SS, are largely absent in UFG SS. This study provides a nanoengineering approach to design and discover radiation tolerant metallic materials for applications in extreme radiation environments.
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Affiliation(s)
- C Sun
- 1] Department of Materials Science and Engineering, Texas A&M University, College Station, TX 77843 [2] Materials Science and Technology Division, Los Alamos National Laboratory, Los Alamos, NM 87545
| | - S Zheng
- Materials Science and Technology Division, Los Alamos National Laboratory, Los Alamos, NM 87545
| | - C C Wei
- Department of Nuclear Engineering, Texas A&M University, College Station, TX 77843
| | - Y Wu
- Department of Materials Science and Engineering, Nuclear Engineering Program, University of Florida, Gainesville, FL 32611
| | - L Shao
- Department of Nuclear Engineering, Texas A&M University, College Station, TX 77843
| | - Y Yang
- Department of Materials Science and Engineering, Nuclear Engineering Program, University of Florida, Gainesville, FL 32611
| | - K T Hartwig
- Department of Materials Science and Engineering, Texas A&M University, College Station, TX 77843
| | - S A Maloy
- Materials Science and Technology Division, Los Alamos National Laboratory, Los Alamos, NM 87545
| | - S J Zinkle
- Department of Nuclear Engineering, The University of Tennessee, Knoxville, TN, 37996, USA
| | - T R Allen
- Department of Engineering Physics, University of Wisconsin, Madison, WI 53706, USA
| | - H Wang
- Department of Electrical and Computer Engineering, Texas A&M University, College Station, TX 77843
| | - X Zhang
- 1] Department of Materials Science and Engineering, Texas A&M University, College Station, TX 77843 [2] Department of Mechanical Engineering, Texas A&M University, College Station, TX 77843
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Shikama T, Yano T, Ukai J, Onose S, Itoh M, Zinkle SJ, Snead LL, Maruyama T, Nagata S, Tsuchiya B, Toh K. Gas Nuclear Transmutation Effects in Aluminum Nitride. Fusion Science and Technology 2003. [DOI: 10.13182/fst03-a385] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.0] [Reference Citation Analysis] [What about the content of this article? (0)] [Affiliation(s)] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/12/2022]
Affiliation(s)
- Tatsuo Shikama
- Institute for Materials Research, Tohoku University, Sendai, 980-8577 Japan, Tel. +81-22-215-2060
| | - T. Yano
- Tokyo Institute of Technology, Meguroku, Tokyo, 152-8550 Japan
| | - J. Ukai
- Japan Institute of Nuclear Fuel Cycle, Oarai, Ibaraki, 311-1394 Japan
| | - S. Onose
- Japan Institute of Nuclear Fuel Cycle, Oarai, Ibaraki, 311-1394 Japan
| | - M. Itoh
- Japan Institute of Nuclear Fuel Cycle, Oarai, Ibaraki, 311-1394 Japan
| | - S. J. Zinkle
- Oak Ridge National Laboratory, Tennessee, 37831-6138 USA
| | - L. L. Snead
- Oak Ridge National Laboratory, Tennessee, 37831-6138 USA
| | - T. Maruyama
- The Wakasawan Energy Research Center, Tsuruga, 914-0192 Japan
| | - S. Nagata
- Institute for Materials Research, Tohoku University, Sendai, 980-8577 Japan
| | - B. Tsuchiya
- Institute for Materials Research, Tohoku University, Sendai, 980-8577 Japan
| | - K. Toh
- Institute for Materials Research, Tohoku University, Sendai, 980-8577 Japan
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Singh BN, Eldrup M, Zinkle SJ, Golubov SI. On grain-size-dependent void swelling in pure copper irradiated with fission neutrons. ACTA ACUST UNITED AC 2002. [DOI: 10.1080/01418610208240021] [Citation(s) in RCA: 38] [Impact Index Per Article: 1.7] [Reference Citation Analysis] [What about the content of this article? (0)] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/23/2022]
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Zinkle SJ, Haltom CP, Jenkins LC, DuBose CK. Technique for preparing cross-section transmission electron microscope specimens from ion-irradiated ceramics. J Electron Microsc Tech 1991; 19:452-60. [PMID: 1797990 DOI: 10.1002/jemt.1060190407] [Citation(s) in RCA: 17] [Impact Index Per Article: 0.5] [Reference Citation Analysis] [What about the content of this article? (0)] [Affiliation(s)] [Abstract] [MESH Headings] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 12/28/2022]
Abstract
The general techniques necessary to produce a high-quality cross-sectioned ceramic specimen for transmission electron microscope observation are outlined. A particularly important point is that the width of the glued region between faces of the ceramic specimen must be less than 0.2 micron to prevent loss of the near-surface region during ion milling. A recently developed vise for gluing ceramic cross-section specimens is described, and some examples of the effect of glue thickness on specimen quality are shown.
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Affiliation(s)
- S J Zinkle
- Metals and Ceramics Division, Oak Ridge National Laboratory, Tennessee 37831-6376
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