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Shao L. Effect of Carbon on Void Nucleation in Iron. MATERIALS (BASEL, SWITZERLAND) 2024; 17:3375. [PMID: 38998455 PMCID: PMC11243433 DOI: 10.3390/ma17133375] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Abstract] [Key Words] [Grants] [Track Full Text] [Subscribe] [Scholar Register] [Received: 04/14/2024] [Revised: 06/23/2024] [Accepted: 06/26/2024] [Indexed: 07/14/2024]
Abstract
The study reports the significance of carbon presence in affecting void nucleation in Fe. Without carbon, void nucleation rates decrease gradually at high temperatures but remain significantly high and almost saturated at low temperatures. With carbon present, even at 1 atomic parts per million, void nucleation rates show a low-temperature cutoff. With higher carbon levels, the nucleation temperature window becomes narrower, the maximum nucleation rate becomes lower, and the temperature of maximum void nucleation shifts to a higher temperature. Fundamentally, this is caused by the change in effective vacancy diffusivity due to the formation of carbon-vacancy complexes. The high sensitivity of void nucleation to carbon comes from the high sensitivity of void nucleation to the vacancy arrival rate in a void. The void nucleation is calculated by first obtaining the effective vacancy diffusivity considering the carbon effect, then calculating the defect concentration and defect flux change considering both carbon effects and pre-existing dislocations, and finally calculating the void nucleation rate based on the recently corrected homogeneous void nucleation theory. The study is important not only in the fundamental understanding of impurity effects in ion/neutron irradiation but also in alloy engineering for judiciously introducing impurities to increase swelling resistance, as well as in the development of simulation and modeling methodologies applicable to other metals.
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Affiliation(s)
- Lin Shao
- Accelerator Laboratory, Department of Nuclear Engineering, Texas A&M University, College Station, TX 77843, USA
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2
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An Z, Qiu W, Jiang W, Yang G, Li X, Liao Z, Zhuang Z, Zhang X, Chen S, Guo C, Xiao E, Fang X, Li X, Wang H, Hu X, Jiang B, Shen W, Wang J, Ren J, Ruan X, Wang D, Zhang SY, Luo W, Zhu Z, Lan H, Cao Z, Ma X, Liu Y, Wang P, Yang Y, Su P, Deng X, He W, Ma Y, Ma C, Wang Y, He P, Tang R, Zhou T, Wang J, Yi H, Zhang Y, Chen Y, Fan R, Gao K, Li Q, Sun K, Tan Z, Gu M, Jing H, Tang J. Measurement of the [Formula: see text]Ta([Formula: see text]) cross sections up to stellar s-process temperatures at the CSNS Back-n. Sci Rep 2023; 13:12657. [PMID: 37542076 PMCID: PMC10403622 DOI: 10.1038/s41598-023-39603-7] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Abstract] [Key Words] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Received: 04/06/2023] [Accepted: 07/27/2023] [Indexed: 08/06/2023] Open
Abstract
The neutron capture cross section of [Formula: see text]Ta is relevant to s-process of nuclear astrophysics, extraterrestrial samples analysis in planetary geology and new generation nuclear energy system design. The [Formula: see text]Ta([Formula: see text]) cross section had been measured between 1 eV and 800 keV at the back-streaming white neutron facility (Back-n) of China spallation neutron source(CSNS) using the time-of-flight (TOF) technique and [Formula: see text] liquid scintillator detectors. The experimental results are compared with the data of several evaluated libraries and previous experiments in the resolved and unresolved resonance region. Resonance parameters are extracted using the R-Matrix code SAMMY in the 1-700 eV region. The astrophysical Maxwell average cross section(MACS) from kT = 5 to 100 keV is calculated over a sufficiently wide range of neutron energies. For the characteristic thermal energy of an astrophysical site, at kT = 30keV the MACS value of [Formula: see text]Ta is 834 ± 75 mb, which shows an obvious discrepancy with the Karlsruhe Astrophysical Database of Nucleosynthesis in Stars (KADoNiS) recommended value 766 ± 15 mb. The new measurements strongly constrain the MACS of [Formula: see text]Ta([Formula: see text]) reaction in the stellar s-process temperatures.
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Affiliation(s)
- Zhendong An
- School of Physics and Astronomy, Sun Yat-sen University, Zhuhai, 519082 China
- Sino-French Institute of Nuclear Engineering and Technology, Sun Yat-sen University, Zhuhai, 519082 China
- State Key Laboratory of Lunar and Planetary Sciences, Macau University of Science and Technology, Macau, 999078 China
- CNSA Macau Center for Space Exploration and Science, Macau, 999078 China
- Shanghai Institute of Applied Physics, Chinese Academy of Sciences, Shanghai, 201800 China
| | - Weiwei Qiu
- Sino-French Institute of Nuclear Engineering and Technology, Sun Yat-sen University, Zhuhai, 519082 China
- State Key Laboratory of Lunar and Planetary Sciences, Macau University of Science and Technology, Macau, 999078 China
- CNSA Macau Center for Space Exploration and Science, Macau, 999078 China
| | - Wei Jiang
- Institute of High Energy Physics, Chinese Academy of Sciences, Beijing, 100049 China
- Spallation Neutron Source Science Center, Dongguan, 523803 China
| | - Gaole Yang
- School of Physics and Astronomy, Sun Yat-sen University, Zhuhai, 519082 China
| | - Xiankai Li
- School of Physics and Astronomy, Sun Yat-sen University, Zhuhai, 519082 China
- School of Nuclear Science and Technology, University of South China, Hengyang, 421001 China
| | - Zhengfa Liao
- Sino-French Institute of Nuclear Engineering and Technology, Sun Yat-sen University, Zhuhai, 519082 China
- State Key Laboratory of Lunar and Planetary Sciences, Macau University of Science and Technology, Macau, 999078 China
- CNSA Macau Center for Space Exploration and Science, Macau, 999078 China
| | - Ziyue Zhuang
- Sino-French Institute of Nuclear Engineering and Technology, Sun Yat-sen University, Zhuhai, 519082 China
- State Key Laboratory of Lunar and Planetary Sciences, Macau University of Science and Technology, Macau, 999078 China
- CNSA Macau Center for Space Exploration and Science, Macau, 999078 China
| | - Xiaoping Zhang
- State Key Laboratory of Lunar and Planetary Sciences, Macau University of Science and Technology, Macau, 999078 China
- CNSA Macau Center for Space Exploration and Science, Macau, 999078 China
| | - Shengli Chen
- Sino-French Institute of Nuclear Engineering and Technology, Sun Yat-sen University, Zhuhai, 519082 China
| | - Chenchen Guo
- Sino-French Institute of Nuclear Engineering and Technology, Sun Yat-sen University, Zhuhai, 519082 China
| | - Erxi Xiao
- Sino-French Institute of Nuclear Engineering and Technology, Sun Yat-sen University, Zhuhai, 519082 China
| | - Xiao Fang
- Sino-French Institute of Nuclear Engineering and Technology, Sun Yat-sen University, Zhuhai, 519082 China
| | - Xinxiang Li
- School of Nuclear Science and Technology, University of South China, Hengyang, 421001 China
- University of Chinese Academy of Sciences, Beijing, 100049 China
| | - Hongwei Wang
- Shanghai Institute of Applied Physics, Chinese Academy of Sciences, Shanghai, 201800 China
- University of Chinese Academy of Sciences, Beijing, 100049 China
- Shanghai Advanced Research Institute, Chinese Academy of Sciences, Shanghai, 201210 China
| | - Xinrong Hu
- Shanghai Institute of Applied Physics, Chinese Academy of Sciences, Shanghai, 201800 China
- University of Chinese Academy of Sciences, Beijing, 100049 China
| | - Bing Jiang
- Shanghai Institute of Applied Physics, Chinese Academy of Sciences, Shanghai, 201800 China
- University of Chinese Academy of Sciences, Beijing, 100049 China
| | - Wenqing Shen
- Shanghai Institute of Applied Physics, Chinese Academy of Sciences, Shanghai, 201800 China
- University of Chinese Academy of Sciences, Beijing, 100049 China
- Shanghai Advanced Research Institute, Chinese Academy of Sciences, Shanghai, 201210 China
| | - Jincheng Wang
- Key Laboratory of Nuclear Data, China Institute of Atomic Energy, Beijing, 102413 China
| | - Jie Ren
- Key Laboratory of Nuclear Data, China Institute of Atomic Energy, Beijing, 102413 China
| | - Xichao Ruan
- Key Laboratory of Nuclear Data, China Institute of Atomic Energy, Beijing, 102413 China
| | - Dexin Wang
- College of Mathematics and Physics, Inner Mongolia Minzu University, Tongliao, 028000 China
- Institute of Nuclear Physics, Inner Mongolia Minzu University, Tongliao, 028000 China
| | - Su-Yalatu Zhang
- College of Mathematics and Physics, Inner Mongolia Minzu University, Tongliao, 028000 China
- Institute of Nuclear Physics, Inner Mongolia Minzu University, Tongliao, 028000 China
| | - Wen Luo
- School of Nuclear Science and Technology, University of South China, Hengyang, 421001 China
| | - Zhichao Zhu
- School of Nuclear Science and Technology, University of South China, Hengyang, 421001 China
| | - Haoyang Lan
- School of Nuclear Science and Technology, University of South China, Hengyang, 421001 China
| | - Zongwei Cao
- School of Nuclear Science and Technology, University of South China, Hengyang, 421001 China
| | - Xu Ma
- Key Laboratory of Nuclear Data, China Institute of Atomic Energy, Beijing, 102413 China
- Shool of Materials Science and Engineering, Xiangtan University, Xiangtan, 411100 China
| | - Yingdu Liu
- Shool of Materials Science and Engineering, Xiangtan University, Xiangtan, 411100 China
| | - Pusen Wang
- Shool of Materials Science and Engineering, Xiangtan University, Xiangtan, 411100 China
| | - Yi Yang
- Key Laboratory of Nuclear Physics and Ion-beam Application (MOE), Institute of Modern Physics, Department of Nuclear Science and Technology, Fudan University, Shanghai, 200433 China
| | - Ping Su
- Key Laboratory of Nuclear Physics and Ion-beam Application (MOE), Institute of Modern Physics, Department of Nuclear Science and Technology, Fudan University, Shanghai, 200433 China
| | - Xiangai Deng
- Key Laboratory of Nuclear Physics and Ion-beam Application (MOE), Institute of Modern Physics, Department of Nuclear Science and Technology, Fudan University, Shanghai, 200433 China
| | - Wanbing He
- Key Laboratory of Nuclear Physics and Ion-beam Application (MOE), Institute of Modern Physics, Department of Nuclear Science and Technology, Fudan University, Shanghai, 200433 China
| | - Yugang Ma
- Shanghai Institute of Applied Physics, Chinese Academy of Sciences, Shanghai, 201800 China
- Key Laboratory of Nuclear Physics and Ion-beam Application (MOE), Institute of Modern Physics, Department of Nuclear Science and Technology, Fudan University, Shanghai, 200433 China
| | - Chunwang Ma
- Institute of Particle and Nuclear Physics, Henan Normal University, Xinxiang, 453007 China
- School of Physics, Henan Normal University, Xinxiang, 453007 China
| | - Yuting Wang
- Institute of Particle and Nuclear Physics, Henan Normal University, Xinxiang, 453007 China
- School of Physics, Henan Normal University, Xinxiang, 453007 China
| | - Pengqin He
- School of Physics and Astronomy, Sun Yat-sen University, Zhuhai, 519082 China
| | - Renguang Tang
- School of Physics and Astronomy, Sun Yat-sen University, Zhuhai, 519082 China
| | - Tao Zhou
- School of Physics and Astronomy, Sun Yat-sen University, Zhuhai, 519082 China
| | - Jing Wang
- School of Physics and Astronomy, Sun Yat-sen University, Zhuhai, 519082 China
| | - Han Yi
- Institute of High Energy Physics, Chinese Academy of Sciences, Beijing, 100049 China
- Spallation Neutron Source Science Center, Dongguan, 523803 China
| | - Yue Zhang
- Institute of High Energy Physics, Chinese Academy of Sciences, Beijing, 100049 China
- Spallation Neutron Source Science Center, Dongguan, 523803 China
| | - Yonghao Chen
- Institute of High Energy Physics, Chinese Academy of Sciences, Beijing, 100049 China
- Spallation Neutron Source Science Center, Dongguan, 523803 China
| | - Ruirui Fan
- Institute of High Energy Physics, Chinese Academy of Sciences, Beijing, 100049 China
- Spallation Neutron Source Science Center, Dongguan, 523803 China
| | - Keqing Gao
- Institute of High Energy Physics, Chinese Academy of Sciences, Beijing, 100049 China
- Spallation Neutron Source Science Center, Dongguan, 523803 China
| | - Qiang Li
- Institute of High Energy Physics, Chinese Academy of Sciences, Beijing, 100049 China
- Spallation Neutron Source Science Center, Dongguan, 523803 China
| | - Kang Sun
- Institute of High Energy Physics, Chinese Academy of Sciences, Beijing, 100049 China
- Spallation Neutron Source Science Center, Dongguan, 523803 China
| | - Zhixin Tan
- Institute of High Energy Physics, Chinese Academy of Sciences, Beijing, 100049 China
- Spallation Neutron Source Science Center, Dongguan, 523803 China
| | - Minhao Gu
- Institute of High Energy Physics, Chinese Academy of Sciences, Beijing, 100049 China
- Spallation Neutron Source Science Center, Dongguan, 523803 China
| | - Hantao Jing
- Institute of High Energy Physics, Chinese Academy of Sciences, Beijing, 100049 China
- Spallation Neutron Source Science Center, Dongguan, 523803 China
| | - Jingyu Tang
- School of Nuclear Science and Technology, University of Science and Technology of China, Hefei, 230027 China
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Ghoniem N, Patel S, Ghazari A, Nadvornick W, Dickstein D, Williams B, Hughes D. Design, fabrication, and testing of a water-cooled tungsten-foam high-heat flux plasma-facing module. FUSION ENGINEERING AND DESIGN 2023. [DOI: 10.1016/j.fusengdes.2023.113633] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 03/30/2023]
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4
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Setyawan W, Dasgupta D, Blondel S, Nandipati G, Hammond KD, Maroudas D, Wirth BD. Equation of state for He bubbles in W and model of He bubble growth and bursting near W{100} surfaces derived from molecular dynamics simulations. Sci Rep 2023; 13:9601. [PMID: 37311783 DOI: 10.1038/s41598-023-35803-3] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Abstract] [Grants] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Received: 04/06/2023] [Accepted: 05/24/2023] [Indexed: 06/15/2023] Open
Abstract
Molecular dynamics (MD) simulations are performed to derive an equation of state (EOS) for helium (He) bubbles in tungsten (W) and to study the growth of He bubbles under a W(100) surface until they burst. We study the growth as a function of the initial nucleation depth of the bubbles. During growth, successive loop-punching events are observed, accompanied by shifts in the depth of the bubble towards the surface. Subsequently, the MD data are used to derive models that describe the conditions that cause the loop punching and bursting events. Simulations have been performed at 500, 933, 1500, 2000, and 2500 K to fit the parameters in the models. To compute the pressure in the bubble at the loop punching and bursting events from the models, we derive an EOS for He bubbles in tungsten with an accompanying volume model to compute the bubble volume for a given number of vacancies ([Formula: see text]), He atoms ([Formula: see text]), and temperature (T). To derive the bubble EOS, we firstly derive the EOS for a free He gas. The derived free-gas EOS can accurately predict all MD data included in the analysis (which span up to 54 GPa at 2500 K). Subsequently, the bubble EOS is derived based on the free-gas EOS by correcting the gas density to account for the interaction between He and W atoms. The EOS for the bubbles is fitted to data from MD simulations of He bubbles in bulk W that span a wide range of gas density and sizes up to about 3 nm in diameter. The pressure of subsurface bubbles at the loop punching events as calculated using the bubble-EOS and the volume model agrees well with the pressure obtained directly from the MD simulations. In the loop punching model, for bubbles consisting of [Formula: see text] vacancies and [Formula: see text] helium atoms, the [Formula: see text] ratio that causes the event, the resulting increase in [Formula: see text], and the associated shift of the bubble depth are formulated as a function of [Formula: see text] and T. In the bursting model, a bubble must simultaneously reach a certain depth and [Formula: see text] ratio in order to burst. The burst depth and [Formula: see text] are also modeled as a function of [Formula: see text] and T. The majority of the loop punching events occur at bubble pressures between 20 and 60 GPa, depending on the bubble size and temperature. The larger the bubble and the higher the temperature, the lower the bubble pressure. Furthermore, our results indicate that at a higher temperature, a bubble can burst from a deeper region.
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Affiliation(s)
- Wahyu Setyawan
- Pacific Northwest National Laboratory, Richland, WA, 99352, USA.
| | - Dwaipayan Dasgupta
- Department of Nuclear Engineering, University of Tennessee, Knoxville, TN, 37996, USA
| | - Sophie Blondel
- Department of Nuclear Engineering, University of Tennessee, Knoxville, TN, 37996, USA
| | | | - Karl D Hammond
- Department of Chemical and Biomedical Engineering, University of Missouri, Columbia, MO, 65211, USA
| | - Dimitrios Maroudas
- Department of Chemical Engineering, University of Massachusetts, Amherst, MA, 01003, USA
| | - Brian D Wirth
- Department of Nuclear Engineering, University of Tennessee, Knoxville, TN, 37996, USA
- Fusion Energy Division, Oak Ridge National Laboratory, Oak Ridge, TN, 37830, USA
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5
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Galatanu M, Enculescu M, Galatanu A, Ticos D, Dumitru M, Ticos C. Microengineering Design for Advanced W-Based Bulk Materials with Improved Properties. NANOMATERIALS (BASEL, SWITZERLAND) 2023; 13:1012. [PMID: 36985906 PMCID: PMC10056536 DOI: 10.3390/nano13061012] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Abstract] [Key Words] [Track Full Text] [Figures] [Subscribe] [Scholar Register] [Received: 02/01/2023] [Revised: 02/28/2023] [Accepted: 03/07/2023] [Indexed: 06/18/2023]
Abstract
In fusion reactors, such as ITER or DEMO, the plasma used to generate nuclear reactions will reach temperatures that are an order of magnitude higher than in the Sun's core. Although the plasma is not supposed to be in contact with the reactor walls, a large amount of heat generated by electromagnetic radiation, electrons and ions being expelled from the plasma will reach the plasma-facing surface of the reactor. Especially for the divertor part, high heat fluxes of up to 20 MW/m2 are expected even in normal operating conditions. An improvement in the plasma-facing material (which is, in the case of ITER, pure Tungsten, W) is desired at least in terms of both a higher recrystallization temperature and a lower brittle-to-ductile transition temperature. In the present work, we discuss three microengineering routes based on inclusions of nanometric dispersions, which are proposed to improve the W properties, and present the microstructural and thermophysical properties of the resulting W-based composites with such dispersions. The materials' behavior after 6 MeV electron irradiation tests is also presented, and their further development is discussed.
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Affiliation(s)
- Magdalena Galatanu
- National Institute of Materials Physics, Atomistilor Street 405 A, Magurele, 077125 Ilfov, Romania
| | - Monica Enculescu
- National Institute of Materials Physics, Atomistilor Street 405 A, Magurele, 077125 Ilfov, Romania
| | - Andrei Galatanu
- National Institute of Materials Physics, Atomistilor Street 405 A, Magurele, 077125 Ilfov, Romania
| | - Dorina Ticos
- National Institute for Laser, Plasma and Radiation Physics, Atomistilor Street 409, Magurele, 077125 Ilfov, Romania
| | - Marius Dumitru
- National Institute for Laser, Plasma and Radiation Physics, Atomistilor Street 409, Magurele, 077125 Ilfov, Romania
| | - Catalin Ticos
- National Institute for Laser, Plasma and Radiation Physics, Atomistilor Street 409, Magurele, 077125 Ilfov, Romania
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Lang E, Taylor CN, Madden N, Marchhart T, Smith C, Wang X, Krogstad J, Allain JP. Examination of Early-Stage Helium Retention and Release in Dispersion-Strengthened Tungsten Alloys. FUSION SCIENCE AND TECHNOLOGY 2023. [DOI: 10.1080/15361055.2022.2164444] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 03/12/2023]
Affiliation(s)
- Eric Lang
- University of Illinois at Urbana-Champaign, Department of Nuclear, Plasma, and Radiological Engineering, Urbana, Illinois
- University of New Mexico, Department of Nuclear Engineering, Albuquerque, New Mexico
| | - Chase N. Taylor
- Idaho National Laboratory, Fusion Safety Program, Idaho Falls, Idaho
| | - Nathan Madden
- University of Illinois at Urbana-Champaign, Materials Science and Engineering Department, Urbana, Illinois
| | - Trevor Marchhart
- Pennsylvania State University, Ken and Mary Alice Lindquist Department of Nuclear Engineering, State College, Pennsylvania
| | - Charles Smith
- University of Illinois at Urbana-Champaign, Materials Science and Engineering Department, Urbana, Illinois
| | - Xing Wang
- Pennsylvania State University, Ken and Mary Alice Lindquist Department of Nuclear Engineering, State College, Pennsylvania
| | - Jessica Krogstad
- University of Illinois at Urbana-Champaign, Materials Science and Engineering Department, Urbana, Illinois
| | - J. P. Allain
- Pennsylvania State University, Ken and Mary Alice Lindquist Department of Nuclear Engineering, State College, Pennsylvania
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Wang T, Zhu T, Wang D, Zhang P, Song Y, Ye F, Wang Q, Jin S, Yu R, Liu F, Kuang P, Wang B, Li L, Cao X. Effect of Vacancy Behavior on Precipitate Formation in a Reduced-Activation V-Cr-Mn Medium-Entropy Alloy. MATERIALS (BASEL, SWITZERLAND) 2022; 16:153. [PMID: 36614492 PMCID: PMC9821738 DOI: 10.3390/ma16010153] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Abstract] [Key Words] [Track Full Text] [Figures] [Subscribe] [Scholar Register] [Received: 12/02/2022] [Revised: 12/15/2022] [Accepted: 12/21/2022] [Indexed: 06/17/2023]
Abstract
In this work, we studied the evolution of vacancy-like defects and the formation of brittle precipitates in a reduced-activation V-Cr-Mn medium-entropy alloy. The evolution of local electronic circumstances around Cr and Mn enrichments, the vacancy defects, and the CrMn3 precipitates were characterized by using scanning electron microscopy with energy-dispersive spectroscopy, X-ray diffraction, and positron annihilation spectroscopy. The microstructure measurements showed that the Mn and Cr enrichments in the as-cast sample significantly evolved with temperature, i.e., from 400 °C, the Cr/Mn-segregated regions gradually dissolved into the matrix and then disappeared, and from 900 °C to 1000 °C, they existed as CrMn3 precipitates. The crystallite size of the phase corresponding to CrMn3 precipitates was about 29.4 nm at 900 °C and 43.7 nm at 1000 °C. The positron annihilation lifetime results demonstrated that the vacancies mediated the migration of Cr and Mn, and Cr and Mn segregation finally led to the formation of CrMn3 precipitates. The coincidence Doppler broadening results showed that the characteristic peak moved to the low-momentum direction, due to an increase in the size of the vacancy defects at the interface and the formation of CrMn3 precipitates.
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Affiliation(s)
- Tianjiao Wang
- School of Physics and Engineering, Henan University of Science and Technology, Luoyang 471023, China
- Institute of High Energy Physics, CAS, Beijing 100049, China
| | - Te Zhu
- Institute of High Energy Physics, CAS, Beijing 100049, China
- Department of Mechanical Engineering, The University of Hong Kong, Pokfulam Road, Hong Kong, China
| | - Dandan Wang
- School of Physics and Engineering, Henan University of Science and Technology, Luoyang 471023, China
| | - Peng Zhang
- Institute of High Energy Physics, CAS, Beijing 100049, China
| | - Yamin Song
- Institute of High Energy Physics, CAS, Beijing 100049, China
| | - Fengjiao Ye
- Institute of High Energy Physics, CAS, Beijing 100049, China
| | - Qianqian Wang
- Institute of High Energy Physics, CAS, Beijing 100049, China
| | - Shuoxue Jin
- Institute of High Energy Physics, CAS, Beijing 100049, China
| | - Runsheng Yu
- Institute of High Energy Physics, CAS, Beijing 100049, China
| | - Fuyan Liu
- Institute of High Energy Physics, CAS, Beijing 100049, China
| | - Peng Kuang
- Institute of High Energy Physics, CAS, Beijing 100049, China
| | - Baoyi Wang
- Institute of High Energy Physics, CAS, Beijing 100049, China
| | - Liben Li
- School of Physics and Engineering, Henan University of Science and Technology, Luoyang 471023, China
| | - Xingzhong Cao
- Institute of High Energy Physics, CAS, Beijing 100049, China
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Sinclair G, Abrams T, Holland L. Computational Assessment on Impurity Sourcing and Transport Using High-Temperature Graphite and Silicon Carbide Plasma-Facing Walls in a Tokamak Environment. FUSION SCIENCE AND TECHNOLOGY 2022. [DOI: 10.1080/15361055.2022.2099506] [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)
| | - T. Abrams
- General Atomics, San Diego, California
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Reliability research of hypervapotron under steady-state thermal load. FUSION ENGINEERING AND DESIGN 2022. [DOI: 10.1016/j.fusengdes.2022.113191] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/19/2022]
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10
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Effect on impact properties of adding tantalum to V-4Cr-4Ti ternary vanadium alloy. NUCLEAR MATERIALS AND ENERGY 2022. [DOI: 10.1016/j.nme.2022.101198] [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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Laptev R, Stepanova E, Pushilina N, Svyatkin L, Krotkevich D, Lomygin A, Ognev S, Siemek K, Doroshkevich A, Uglov V. Distribution of Hydrogen and Defects in the Zr/Nb Nanoscale Multilayer Coatings after Proton Irradiation. MATERIALS 2022; 15:ma15093332. [PMID: 35591666 PMCID: PMC9104290 DOI: 10.3390/ma15093332] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.5] [Reference Citation Analysis] [Abstract] [Track Full Text] [Download PDF] [Figures] [Subscribe] [Scholar Register] [Received: 04/19/2022] [Revised: 04/29/2022] [Accepted: 05/04/2022] [Indexed: 02/01/2023]
Abstract
Radiation damage is one of the significant factors limiting the operating time of many structural materials working under extreme conditions. One of the promising directions in the development of materials that are resistant to radiation damage and have improved physical and mechanical properties is the creation of nanoscale multilayer coatings (NMCs). The paper is devoted to the experimental comprehension of changes in the defect structure and mechanical properties of nanoscale multilayer coatings (NMCs) with alternating layers of Zr and Nb under irradiation. Series of Zr/Nb NMCs with different thicknesses of individual layers were fabricated by magnetron sputtering and subjected to H+ irradiation. The evolution of structure and phase states, as well as the defect state under proton irradiation, was studied using the methods of high-resolution transmission electron microscopy (HRTEM), X-ray diffraction analysis (XRD), glow discharge optical emission spectroscopy (GDOES), and positron annihilation spectroscopy (PAS). The layer-by-layer analysis of structural defects was carried out by Doppler broadening spectroscopy (DBS) using a variable-energy positron beam. To estimate the binding energy and the energy paths for the hydrogen diffusion in Zr/Nb NMCs, calculations from the first principles were used. When the thickness of individual layers is less than 25 nm, irradiation causes destruction of the interfaces, but there is no significant increase in the defect level, the S parameter (open volume defects amount) before and after irradiation is practically unchanged. After irradiation of NMC Zr/Nb with a thickness of layers 50 and 100 nm, the initial microstructure is retained, and the S parameter is significantly reduced. The GDOES data reveal the irregular H accumulation at the interface caused by significant differences in H diffusion barriers in the bulk of Zr and Nb multilayers as well as near the interface’s region.
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Affiliation(s)
- Roman Laptev
- Division for Experimental Physics, National Research Tomsk Polytechnic University, 634050 Tomsk, Russia; (E.S.); (N.P.); (L.S.); (D.K.); (A.L.); (S.O.)
- Correspondence: ; Tel.: +7-913-852-3733
| | - Ekaterina Stepanova
- Division for Experimental Physics, National Research Tomsk Polytechnic University, 634050 Tomsk, Russia; (E.S.); (N.P.); (L.S.); (D.K.); (A.L.); (S.O.)
| | - Natalia Pushilina
- Division for Experimental Physics, National Research Tomsk Polytechnic University, 634050 Tomsk, Russia; (E.S.); (N.P.); (L.S.); (D.K.); (A.L.); (S.O.)
| | - Leonid Svyatkin
- Division for Experimental Physics, National Research Tomsk Polytechnic University, 634050 Tomsk, Russia; (E.S.); (N.P.); (L.S.); (D.K.); (A.L.); (S.O.)
| | - Dmitriy Krotkevich
- Division for Experimental Physics, National Research Tomsk Polytechnic University, 634050 Tomsk, Russia; (E.S.); (N.P.); (L.S.); (D.K.); (A.L.); (S.O.)
| | - Anton Lomygin
- Division for Experimental Physics, National Research Tomsk Polytechnic University, 634050 Tomsk, Russia; (E.S.); (N.P.); (L.S.); (D.K.); (A.L.); (S.O.)
| | - Sergei Ognev
- Division for Experimental Physics, National Research Tomsk Polytechnic University, 634050 Tomsk, Russia; (E.S.); (N.P.); (L.S.); (D.K.); (A.L.); (S.O.)
| | - Krzysztof Siemek
- Department of Structural Research, Institute of Nuclear Physics Polish Academy of Sciences, 31342 Krakow, Poland;
- Dzhelepov Laboratory of Nuclear Problems, Joint Institute for Nuclear Research, 141980 Dubna, Russia
| | - Aleksandr Doroshkevich
- Frank Laboratory of Neutron Physics, Joint Institute for Nuclear Research, 141980 Dubna, Russia;
| | - Vladimir Uglov
- Department of Solid State Physics, Belarusian State University, 220006 Minsk, Belarus;
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12
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Effect of tungsten matrix on the mechanical property of SiC fiber reinforced tungsten composites with foils fabricated at 1700 °C. NUCLEAR MATERIALS AND ENERGY 2022. [DOI: 10.1016/j.nme.2022.101142] [Citation(s) in RCA: 2] [Impact Index Per Article: 1.0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/19/2022]
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13
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Hidalgo-Salaverri J, Cano-Megias P, Chacartegui R, Ayllon-Guerola J, Viezzer E. Analysis of supercritical carbon dioxide Brayton cycles for a helium-cooled pebble bed blanket DEMO-like fusion power plant. FUSION ENGINEERING AND DESIGN 2021. [DOI: 10.1016/j.fusengdes.2021.112860] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/20/2022]
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14
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Irradiation hardening and ductility loss of Eurofer97 steel variants after neutron irradiation to ITER-TBM relevant conditions. FUSION ENGINEERING AND DESIGN 2021. [DOI: 10.1016/j.fusengdes.2021.112935] [Citation(s) in RCA: 3] [Impact Index Per Article: 1.0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/30/2022]
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15
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Reid NC, Garrison L, Gussev M, Allain JP. Design and Analysis of an Advanced Three-Point Bend Test Approach for Miniature Irradiated Disk Specimens. FUSION SCIENCE AND TECHNOLOGY 2021. [DOI: 10.1080/15361055.2021.1925032] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/21/2022]
Affiliation(s)
- Nathan Clark Reid
- University of Illinois at Urbana-Champaign, Department of Nuclear, Plasma, and Radiological Engineering, Urbana, Illinois 61820
| | - Lauren Garrison
- Oak Ridge National Laboratory, Materials Science and Technology Division, Oak Ridge, Tennessee 37831
| | - Maxim Gussev
- Oak Ridge National Laboratory, Nuclear Energy and Fuel Cycle Division, Oak Ridge, Tennessee 37831
| | - Jean Paul Allain
- The Pennsylvania State University, Department of Nuclear Engineering, University Park, Pennsylvania 16801
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16
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17
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Effect of tantalum addition on the tensile properties of V-Ta-4Cr-4Ti quaternary alloys. FUSION ENGINEERING AND DESIGN 2021. [DOI: 10.1016/j.fusengdes.2020.112191] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/21/2022]
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18
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Quantifying erosion and retention of silicon carbide due to D plasma irradiation in a high-flux linear plasma device. NUCLEAR MATERIALS AND ENERGY 2021. [DOI: 10.1016/j.nme.2021.100939] [Citation(s) in RCA: 3] [Impact Index Per Article: 1.0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/23/2022]
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19
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High-Entropy Alloys for Advanced Nuclear Applications. ENTROPY 2021; 23:e23010098. [PMID: 33440904 PMCID: PMC7827623 DOI: 10.3390/e23010098] [Citation(s) in RCA: 17] [Impact Index Per Article: 5.7] [Reference Citation Analysis] [Abstract] [Key Words] [Track Full Text] [Download PDF] [Figures] [Subscribe] [Scholar Register] [Received: 12/15/2020] [Revised: 01/08/2021] [Accepted: 01/08/2021] [Indexed: 12/03/2022]
Abstract
The expanded compositional freedom afforded by high-entropy alloys (HEAs) represents a unique opportunity for the design of alloys for advanced nuclear applications, in particular for applications where current engineering alloys fall short. This review assesses the work done to date in the field of HEAs for nuclear applications, provides critical insight into the conclusions drawn, and highlights possibilities and challenges for future study. It is found that our understanding of the irradiation responses of HEAs remains in its infancy, and much work is needed in order for our knowledge of any single HEA system to match our understanding of conventional alloys such as austenitic steels. A number of studies have suggested that HEAs possess ‘special’ irradiation damage resistance, although some of the proposed mechanisms, such as those based on sluggish diffusion and lattice distortion, remain somewhat unconvincing (certainly in terms of being universally applicable to all HEAs). Nevertheless, there may be some mechanisms and effects that are uniquely different in HEAs when compared to more conventional alloys, such as the effect that their poor thermal conductivities have on the displacement cascade. Furthermore, the opportunity to tune the compositions of HEAs over a large range to optimise particular irradiation responses could be very powerful, even if the design process remains challenging.
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20
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He W, Zhou L, Gao X, Wang D, Shen T, Wang Z, Yang D, Li Y, Liu J, Liu Z. The influences of migration behaviors on annihilation of point defects trapped into grain boundaries in Tungsten. J NUCL SCI TECHNOL 2020. [DOI: 10.1080/00223131.2020.1817809] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/23/2022]
Affiliation(s)
- Wenhao He
- School of Nuclear Science and Technology, Lanzhou University, Lanzhou, China
| | - Liangfu Zhou
- School of Nuclear Science and Technology, Lanzhou University, Lanzhou, China
| | - Xing Gao
- Institute of Modern Physics, Chinese Academy of Sciences, Lanzhou, China
| | - Dong Wang
- Science and Technology on Reactor Fuel and Materials Laboratory, Nuclear Power Institute of China, Chengdu, China
| | - Tielong Shen
- Institute of Modern Physics, Chinese Academy of Sciences, Lanzhou, China
| | - Zhiguang Wang
- Institute of Modern Physics, Chinese Academy of Sciences, Lanzhou, China
| | - Dongyan Yang
- School of Nuclear Science and Technology, Lanzhou University, Lanzhou, China
| | - Yuhong Li
- School of Nuclear Science and Technology, Lanzhou University, Lanzhou, China
| | - Juntao Liu
- School of Nuclear Science and Technology, Lanzhou University, Lanzhou, China
| | - Zhiyi Liu
- School of Nuclear Science and Technology, Lanzhou University, Lanzhou, China
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21
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Shah V, van Maris M, van Dommelen J, Geers M. Experimental investigation of the microstructural changes of tungsten monoblocks exposed to pulsed high heat loads. NUCLEAR MATERIALS AND ENERGY 2020. [DOI: 10.1016/j.nme.2019.100716] [Citation(s) in RCA: 10] [Impact Index Per Article: 2.5] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/26/2022]
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22
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Das S. Recent advances in characterising irradiation damage in tungsten for fusion power. SN APPLIED SCIENCES 2019. [DOI: 10.1007/s42452-019-1591-0] [Citation(s) in RCA: 12] [Impact Index Per Article: 2.4] [Reference Citation Analysis] [Abstract] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/25/2022] Open
Abstract
AbstractTungsten is the front-runner candidate for building the plasma-facing armour components for future fusion reactors. However, in-service irradiation by fusion-neutrons and helium will create lattice-defects in the material, compromising its properties and lifetime. Improving the component’s resilience to radiation damage and accurately predicting the lifetime of irradiated components is key for commercial feasibility of the reactor. For this purpose, understanding the creation and evolution of radiation damage is essential. This paper reviews recent advances in characterising radiation damage through experimental and modelling techniques. Tungsten-ion- and helium-ion-implantation are commonly used to mimic the damage created by neutron- and helium-irradiation respectively. Defects (> 1.5 nm) can be directly imaged using transmission electron microscopy while all defects (size-independent), may be indirectly probed by measuring lattice strains induced by them (using diffraction techniques; synchrotron X-rays or high-resolution electron-backscatter). Neutron-irradiation produces mainly ½〈111〉 prismatic loops. Loop-interaction and structural organisation evolves with changing implantation dose and temperature. Helium-irradiation, < 573 K, induces formation of small helium-vacancy clusters, which evolve into bubbles, blisters and “fuzz” structure with changing temperature and dose. Nano-indentation or micro-cantilever bending tests can be used to examine mechanical properties of ion-implanted layers. Both helium- and neutron-implantation defects induce increased hardening often followed by subsequent strain-softening and localised deformation. Such irradiation-induced alterations are detrimental to material ductility and long-term structural integrity of tungsten-based components. Development of physically-based material models that capture the physics of underlying irradiation-induced changes, inspire confidence of reliably using simulations to predict mechanical behaviour and in-service performance of irradiated engineering components in future.
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23
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Reliability evaluation of secondary support structure in hypothetical drop of reactor core barrel assembly. NUCLEAR ENGINEERING AND DESIGN 2019. [DOI: 10.1016/j.nucengdes.2019.110219] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.2] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/15/2022]
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24
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Igitkhanov Y, Bazylev B, Boccaccini L. Vapor Shielding Effect on DEMO Divertor. FUSION SCIENCE AND TECHNOLOGY 2019. [DOI: 10.1080/15361055.2019.1610291] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/26/2022]
Affiliation(s)
| | - Boris Bazylev
- Karlsruhe Institute of Technology, Karlsruhe, Germany
- South Ural State University, Lenin Prospect 76, 454080 Chelyabinsk, Russian Federation
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25
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Hardie CD, London AJ, Lim JJH, Bamber R, Tadić T, Vukšić M, Fazinić S. Exploitation of thermal gradients for investigation of irradiation temperature effects with charged particles. Sci Rep 2019; 9:13541. [PMID: 31537827 PMCID: PMC6753122 DOI: 10.1038/s41598-019-49585-0] [Citation(s) in RCA: 5] [Impact Index Per Article: 1.0] [Reference Citation Analysis] [Abstract] [Track Full Text] [Download PDF] [Figures] [Journal Information] [Subscribe] [Scholar Register] [Received: 01/15/2019] [Accepted: 08/27/2019] [Indexed: 11/16/2022] Open
Abstract
The effects of radiation damage on materials are strongly dependant on temperature, making it arguably the most significant parameter of concern in nuclear engineering. Owing to the challenges and expense of irradiating and testing materials, material property data is often limited to few irradiation conditions and material variants. A new technique has been developed which enables the investigation of radiation damage of samples subject to a thermal gradient, whereby a wealth of data over a range of irradiation temperatures is produced from a single irradiation experiment. The results produced are practically inaccessible by use of multiple conventional isothermal irradiations. We present a precipitation-hardened copper alloy (CuCrZr) case-study irradiated with a linear temperature gradient between 125 and 440 °C. Subsequent micro-scale post irradiation characterisation (nanoindentation, transmission electron microscopy and atom probe tomography) highlight the capability to observe mechanical and microstructural changes over a wide range of irradiation temperatures. We observed irradiation-softening in CuCrZr that did not occur due to irradiation-enhanced aging of the Cr-precipitates. Excellent reproducibility of the new technique was demonstrated and replicated irradiation-hardening data from several isothermal neutron irradiation studies. Our new technique provides this data at a fraction of the time and cost required by conventional irradiation experiments.
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Affiliation(s)
- Chris D Hardie
- United Kingdom Atomic Energy Authority, Culham Centre for Fusion Energy, Culham Science Centre, Abingdon, Oxon, OX14 3DB, UK.
| | - Andrew J London
- United Kingdom Atomic Energy Authority, Culham Centre for Fusion Energy, Culham Science Centre, Abingdon, Oxon, OX14 3DB, UK
| | - Joven J H Lim
- United Kingdom Atomic Energy Authority, Culham Centre for Fusion Energy, Culham Science Centre, Abingdon, Oxon, OX14 3DB, UK
| | - Rob Bamber
- United Kingdom Atomic Energy Authority, Culham Centre for Fusion Energy, Culham Science Centre, Abingdon, Oxon, OX14 3DB, UK
| | - Tonči Tadić
- Ruđer Bošković Institute, Bijenička c.54, 10000, Zagreb, Croatia
| | - Marin Vukšić
- Ruđer Bošković Institute, Bijenička c.54, 10000, Zagreb, Croatia
| | - Stjepko Fazinić
- Ruđer Bošković Institute, Bijenička c.54, 10000, Zagreb, Croatia
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26
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Coenen J, Mao Y, Sistla S, Müller A, Pintsuk G, Wirtz M, Riesch J, Hoeschen T, Terra A, You JH, Greuner H, Kreter A, Broeckmann C, Neu R, Linsmeier C. Materials development for new high heat-flux component mock-ups for DEMO. FUSION ENGINEERING AND DESIGN 2019. [DOI: 10.1016/j.fusengdes.2019.02.098] [Citation(s) in RCA: 14] [Impact Index Per Article: 2.8] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/28/2022]
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27
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Lang E, Madden N, Smith C, Krogstad J, Allain J. Deciphering the role of second phase precipitates on early-stage surface morphology development of dispersion-strengthened W alloys under low energy He irradiation. NUCLEAR MATERIALS AND ENERGY 2019. [DOI: 10.1016/j.nme.2019.01.016] [Citation(s) in RCA: 8] [Impact Index Per Article: 1.6] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/27/2022]
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28
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High-temperature defect recovery in self-ion irradiated W-5 wt% Ta. NUCLEAR MATERIALS AND ENERGY 2019. [DOI: 10.1016/j.nme.2018.12.014] [Citation(s) in RCA: 5] [Impact Index Per Article: 1.0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/22/2022]
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29
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Exploring complex high heat flux geometries for fusion applications enabled by additive manufacturing. FUSION ENGINEERING AND DESIGN 2018. [DOI: 10.1016/j.fusengdes.2018.02.097] [Citation(s) in RCA: 8] [Impact Index Per Article: 1.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/22/2022]
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30
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Characterization of ODS steel friction stir welds and their abnormal grain growth behaviour. FUSION ENGINEERING AND DESIGN 2018. [DOI: 10.1016/j.fusengdes.2018.07.021] [Citation(s) in RCA: 7] [Impact Index Per Article: 1.2] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/17/2022]
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31
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Liu R, Xie Z, Yang J, Zhang T, Hao T, Wang X, Fang Q, Liu C. Recent progress on the R&D of W-ZrC alloys for plasma facing components in fusion devices. NUCLEAR MATERIALS AND ENERGY 2018. [DOI: 10.1016/j.nme.2018.07.002] [Citation(s) in RCA: 24] [Impact Index Per Article: 4.0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/28/2022]
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32
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Pornphatdetaudom T, Yano T, Yoshida K. Physical property changes of neutron-irradiated aluminum nitride and their recovery behavior by annealing using a step-heating dilatometer. NUCLEAR MATERIALS AND ENERGY 2018. [DOI: 10.1016/j.nme.2018.05.027] [Citation(s) in RCA: 5] [Impact Index Per Article: 0.8] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/14/2022]
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33
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Measurements of the total neutron cross sections of 93Nb by using the filtered neutron beams. ANN NUCL ENERGY 2018. [DOI: 10.1016/j.anucene.2017.11.035] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.2] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/17/2022]
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34
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Wong C, Barlcon L, Corradini M, Fogarty P, Ghoniem N, Majumdar S, Malang S, Mattas R, McCarthy K, Merrill B, Murphy J, Nelson B, Nygren R, Sawan M, Sharafat S, Sviatoslavsky I, Zinkle S. Evaluation of the Tungsten Alloy Vaporizing Lithium First Wall and Blanket Concept. ACTA ACUST UNITED AC 2018. [DOI: 10.13182/fst01-a11963340] [Citation(s) in RCA: 17] [Impact Index Per Article: 2.8] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/12/2022]
Affiliation(s)
- C.P.C. Wong
- General Atomics, P.O. Box 85608, San Diego, California 92186-5608
| | - L. Barlcon
- General Atomics, P.O. Box 85608, San Diego, California 92186-5608
| | | | - P. Fogarty
- Oak Ridge National Laboratory, Oak Ridge, Tennessee
| | | | - S. Majumdar
- Argonne National Laboratory, Argonne, Illinois
| | - S. Malang
- Forschungszentrum Karlsruhe GmbH (FZK), Germany
| | - R. Mattas
- University of California, Los Angeles
| | - K. McCarthy
- Idaho National Engineering Environmental Laboratory (INEEL), Idaho
| | - B. Merrill
- Idaho National Engineering Environmental Laboratory (INEEL), Idaho
| | - J. Murphy
- University of Wisconsin, Madison, Wisconsin
| | - B. Nelson
- Oak Ridge National Laboratory, Oak Ridge, Tennessee
| | - R. Nygren
- Sandia National Laboratories, Albuquerque, New Mexico
| | - M. Sawan
- University of Wisconsin, Madison, Wisconsin
| | | | | | - S. Zinkle
- Oak Ridge National Laboratory, Oak Ridge, Tennessee
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35
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Nicholas JR, Ireland PT, Hancock D, Robertson D. Manufacture and Initial Thermo-Fluid Measurements on a Heat Sink Module for Potential Applications in a DEMO. FUSION SCIENCE AND TECHNOLOGY 2017. [DOI: 10.1080/15361055.2017.1350483] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/18/2022]
Affiliation(s)
- J. R. Nicholas
- University of Oxford, Department of Engineering Science, Osney Thermo-Fluids Laboratory, Southwell Building, Osney Mead, Oxfordshire OX2 0ES, United Kingdom
| | - P. T. Ireland
- University of Oxford, Department of Engineering Science, Osney Thermo-Fluids Laboratory, Southwell Building, Osney Mead, Oxfordshire OX2 0ES, United Kingdom
| | - D. Hancock
- Culham Science Centre, Culham Centre for Fusion Energy, Abingdon, Oxfordshire OX14 3DB, United Kingdom
| | - D. Robertson
- Rolls-Royce Plc., Atlantic House, P.O. Box 2000, Derby, Derbyshire DE21 7XX, United Kingdom
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36
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Thermal Evolution of the Proton Irradiated Structure in Tungsten–5 wt% Tantalum. JOURNAL OF FUSION ENERGY 2017. [DOI: 10.1007/s10894-017-0145-y] [Citation(s) in RCA: 6] [Impact Index Per Article: 0.9] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/18/2022]
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37
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Coenen J, Mao Y, Almanstötter J, Calvo A, Sistla S, Gietl H, Jasper B, Riesch J, Rieth M, Pintsuk G, Klein F, Litnovsky A, Mueller A, Wegener T, You JH, Broeckmann C, Garcia-Rosales C, Neu R, Linsmeier C. Advanced materials for a damage resilient divertor concept for DEMO: Powder-metallurgical tungsten-fibre reinforced tungsten. FUSION ENGINEERING AND DESIGN 2017. [DOI: 10.1016/j.fusengdes.2016.12.006] [Citation(s) in RCA: 35] [Impact Index Per Article: 5.0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/29/2022]
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38
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Nemati N, Bozorg M, Penkov OV, Shin DG, Sadighzadeh A, Kim DE. Functional Multi-Nanolayer Coatings of Amorphous Carbon/Tungsten Carbide with Exceptional Mechanical Durability and Corrosion Resistance. ACS APPLIED MATERIALS & INTERFACES 2017; 9:30149-30160. [PMID: 28803468 DOI: 10.1021/acsami.7b08565] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Abstract] [Key Words] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 06/07/2023]
Abstract
A novel functional multilayer coating with periodically stacked nanolayers of amorphous carbon (a:C)/tungsten carbide (WC) and an adhesion layer of chromium (Cr) was deposited on 304 stainless steel using a dual magnetron sputtering technique. Through process optimization, highly densified coatings with high elasticity and shear modulus, excellent wear resistance, and minimal susceptibility to corrosive and caustic media could be acquired. The structural and mechanical properties of the optimized coatings were studied in detail using a variety of analytical techniques. Furthermore, finite element method simulations indicated that the stress generated due to contact against a steel ball was distributed well within the coating, which allowed the stresses to be lower than the yield threshold of the coating. Thus, an ultralow wear rate of ∼10-12mm3/N mm could be achieved in dry sliding conditions under relatively high Hertzian contact pressures of ∼0.4-0.9 GPa. The amorphous and pinhole-free structure of the individual layers, sufficient number of pairs, and the relatively dense stacked layers resulted in significant polarization resistance (Z″ = 5.5 × 106 Ω cm2) and increased the corrosion resistance of the coating by 10-fold compared to that of recently reported corrosion-resistant coatings.
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Affiliation(s)
- Narguess Nemati
- School of Metallurgy and Materials Engineering, College of Engineering, University of Tehran , Tehran, Iran
| | - Mansoor Bozorg
- Department of Materials Science and Engineering, Shahrood University of Technology , Shahrood, Iran
| | | | | | - Asghar Sadighzadeh
- Nuclear Science and Technology Research Institute (NSTRI), A.E.O.I. , Tehran 14155-1339, Iran
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39
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Microstructural characterization of field assisted sintered bulk nanostructured V-4Cr-4Ti alloys. PARTICULATE SCIENCE AND TECHNOLOGY 2017. [DOI: 10.1080/02726351.2017.1322160] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/19/2022]
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40
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Pint BA, DiStefano JR, Tortorelli PF. High Temperature Compatibility Issues for Fusion Reactor Structural Materials. FUSION SCIENCE AND TECHNOLOGY 2017. [DOI: 10.13182/fst03-a373] [Citation(s) in RCA: 6] [Impact Index Per Article: 0.9] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/12/2022]
Affiliation(s)
- B. A. Pint
- Metals and Ceramics Division, Oak Ridge National Laboratory, P. O. Box 2008, Oak Ridge, TN, 37831-6156 865-576-2897
| | - J. R. DiStefano
- Metals and Ceramics Division, Oak Ridge National Laboratory, P. O. Box 2008, Oak Ridge, TN, 37831-6156 865-576-2897
| | - P. F. Tortorelli
- Metals and Ceramics Division, Oak Ridge National Laboratory, P. O. Box 2008, Oak Ridge, TN, 37831-6156 865-576-2897
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41
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Stankovsky AY, Artisyuk VV, Saito M. Heterogeneous Target to Reduce the Toxicity of Spallation Products in an Accelerator-Driven System. NUCL TECHNOL 2017. [DOI: 10.13182/nt03-a3392] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/12/2022]
Affiliation(s)
- Alexey Yu. Stankovsky
- Tokyo Institute of Technology Research Laboratory for Nuclear Reactors 2-12-1 O-okayama, Meguro-ku, Tokyo 152-8550, Japan
| | - Vladimir V. Artisyuk
- Tokyo Institute of Technology Research Laboratory for Nuclear Reactors 2-12-1 O-okayama, Meguro-ku, Tokyo 152-8550, Japan
| | - Masaki Saito
- Tokyo Institute of Technology Research Laboratory for Nuclear Reactors 2-12-1 O-okayama, Meguro-ku, Tokyo 152-8550, Japan
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42
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Stankovsky A, Saito M, Artissiouk VV, Shmelev AN, Sagara H. Transmutation of Long-Lived Fission Products Driven by D-T and D-D Fusion: Specific Neutronics and Radiological Consequences. FUSION SCIENCE AND TECHNOLOGY 2017. [DOI: 10.13182/fst03-a302] [Citation(s) in RCA: 8] [Impact Index Per Article: 1.1] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/12/2022]
Affiliation(s)
- Alexey Stankovsky
- Research Laboratory for Nuclear Reactors, Tokyo Institute of Technology, 2-12-1 O-okayama Meguro-ku, Tokyo 152, Japan
| | - Masaki Saito
- Research Laboratory for Nuclear Reactors, Tokyo Institute of Technology, 2-12-1 O-okayama Meguro-ku, Tokyo 152, Japan
| | - Vladimir V. Artissiouk
- Research Laboratory for Nuclear Reactors, Tokyo Institute of Technology, 2-12-1 O-okayama Meguro-ku, Tokyo 152, Japan
| | - Anatoly N. Shmelev
- Moscow Engineering Physics Institute, Kashirskoye Shosse 31, Moscow, Russia
| | - Hiroshi Sagara
- Research Laboratory for Nuclear Reactors, Tokyo Institute of Technology, 2-12-1 O-okayama Meguro-ku, Tokyo 152, Japan
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43
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Raffray AR, Malang S, El-Guebaly L, Wang X. Ceramic Breeder Blanket for ARIES-CS. FUSION SCIENCE AND TECHNOLOGY 2017. [DOI: 10.13182/fst05-a828] [Citation(s) in RCA: 8] [Impact Index Per Article: 1.1] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/12/2022]
Affiliation(s)
- A. R. Raffray
- Mechanical and Aerospace Engineering Department and Center for Energy Research, 460 EBU-II, University of California-San Diego, 9500 Gilman Drive, La Jolla, CA 92093-0438, USA,
| | - S. Malang
- Fusion Nuclear Technology Consulting, Fliederweg 3, 76351 Linkenheim, Germany
| | - L. El-Guebaly
- University of Wisconsin, Fusion Technology Institute, Madison, WI 53706, USA
| | - X. Wang
- Center for Energy Research, 460 EBU-II, University of California-San Diego, 9500 Gilman Drive, La Jolla, CA 92093-0438, USA
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44
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Raffray AR, El-Guebaly L, Malang S, Wang XR, Bromberg L, Ihli T, Merrill B, Waganer L. Engineering Design and Analysis of the ARIES-CS Power Plant. FUSION SCIENCE AND TECHNOLOGY 2017. [DOI: 10.13182/fst08-4] [Citation(s) in RCA: 50] [Impact Index Per Article: 7.1] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/12/2022]
Affiliation(s)
- A. R. Raffray
- Center for Energy Research, 460 EBU-II, University of California, San Diego, 9500 Gilman Drive La Jolla, California 92093-0417
| | - L. El-Guebaly
- University of Wisconsin, Fusion Technology Institute, Madison, Wisconsin 53706
| | - S. Malang
- Consultant, Fliederweg 3, D 76351 Linkenheim-Hochstetten, Germany
| | - X. R. Wang
- Center for Energy Research, 460 EBU-II, University of California, San Diego, 9500 Gilman Drive La Jolla, California 92093-0417
| | - L. Bromberg
- MIT Plasma Science and Fusion Center, Cambridge, Massachusetts 02139
| | - T. Ihli
- Forschungszentrum Karlsruhe, IKET, P.O. Box 36 40, 76012 Karlsruhe, Germany
| | - B. Merrill
- Idaho National Laboratory, Idaho Falls, Idaho
| | - L. Waganer
- The Boeing Company, Mail Code S270-3760, P.O. Box 516, St. Louis, Missouri 63166
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45
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Katsui H, Hasegawa A, Katoh Y, Hatano Y, Tanaka T, Nogami S, Hinoki T, Shikama T. Study on Compatibility Between Silicon Carbide and Solid Breeding Materials Under Neutron Irradiation. FUSION SCIENCE AND TECHNOLOGY 2017. [DOI: 10.13182/fst11-a12367] [Citation(s) in RCA: 8] [Impact Index Per Article: 1.1] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/12/2022]
Affiliation(s)
- H. Katsui
- Institute for Materials Research, Tohoku University, Sendai, Japan
| | - A. Hasegawa
- Department of Quantum Science and Energy Engineering, Tohoku University, Sendai, Japan
| | - Y. Katoh
- Materials Science and Technology Division, Oak Ridge National Laboratory, Oak Ridge, TN
| | - Y. Hatano
- Hydrogen Isotope Research Center, University of Toyama, Toyama, Japan
| | - T. Tanaka
- Department of Helical Plasma Research, National Institute for Fusion Science, Toki, Japan
| | - S. Nogami
- Department of Quantum Science and Energy Engineering, Tohoku University, Sendai, Japan
| | - T. Hinoki
- Institute of Advanced Energy, Kyoto University, Kyoto, Japan
| | - T. Shikama
- Institute for Materials Research, Tohoku University, Sendai, Japan
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46
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Sviatoslavsky IN, Raffray AR, Sawan ME, Wang X. A Lithium Self-Cooled Blanket for the HAPL Conceptual Inertial Confinement Reactor. FUSION SCIENCE AND TECHNOLOGY 2017. [DOI: 10.13182/fst05-a739] [Citation(s) in RCA: 8] [Impact Index Per Article: 1.1] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/12/2022]
Affiliation(s)
| | | | - M. E. Sawan
- University of Wisconsin-Madison, Madison, WI
| | - X. Wang
- University of California, San Diego, La Jolla, CA
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47
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Latkowski JF, Abbott RP, Aceves S, Anklam T, Cook AW, DeMuth J, Divol L, El-Dasher B, Farmer JC, Flowers D, Fratoni M, Heltemes T, Kane J, Kramer KJ, Kramer R, Lafuente A, Loosmore GA, Morris KR, Moses GA, Olson B, Pantano C, Reyes S, Rhodes M, Sawicki R, Scott H, Tabak M, Wilks S. Chamber Design for the Laser Inertial Fusion Energy (LIFE) Engine. FUSION SCIENCE AND TECHNOLOGY 2017. [DOI: 10.13182/fst10-318] [Citation(s) in RCA: 25] [Impact Index Per Article: 3.6] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/12/2022]
Affiliation(s)
| | - Ryan P. Abbott
- Lawrence Livermore National Laboratory, Livermore, CA 94550
| | - Sal Aceves
- Lawrence Livermore National Laboratory, Livermore, CA 94550
| | - Tom Anklam
- Lawrence Livermore National Laboratory, Livermore, CA 94550
| | - Andrew W. Cook
- Lawrence Livermore National Laboratory, Livermore, CA 94550
| | - James DeMuth
- Lawrence Livermore National Laboratory, Livermore, CA 94550
| | - Laurent Divol
- Lawrence Livermore National Laboratory, Livermore, CA 94550
| | | | | | - Dan Flowers
- Lawrence Livermore National Laboratory, Livermore, CA 94550
| | | | - Thad Heltemes
- Department of Engineering Physics, University of Wisconsin-Madison, WI 53706
| | - Jave Kane
- Lawrence Livermore National Laboratory, Livermore, CA 94550
| | | | - Richard Kramer
- Department of Mechanical Engineering, University of Illinois at Urbana-Champaign, 61801
| | - Antonio Lafuente
- Lawrence Livermore National Laboratory, Livermore, CA 94550
- ETSI Industriales, Universidad Politecnica de Madrid, Madrid, Spain
| | | | | | - Gregory A. Moses
- Department of Engineering Physics, University of Wisconsin-Madison, WI 53706
| | - Britton Olson
- Lawrence Livermore National Laboratory, Livermore, CA 94550
| | - Carlos Pantano
- Department of Mechanical Engineering, University of Illinois at Urbana-Champaign, 61801
| | - Susana Reyes
- Lawrence Livermore National Laboratory, Livermore, CA 94550
| | - Mark Rhodes
- Lawrence Livermore National Laboratory, Livermore, CA 94550
| | - Rick Sawicki
- Lawrence Livermore National Laboratory, Livermore, CA 94550
| | - Howard Scott
- Lawrence Livermore National Laboratory, Livermore, CA 94550
| | - Max Tabak
- Lawrence Livermore National Laboratory, Livermore, CA 94550
| | - Scott Wilks
- Lawrence Livermore National Laboratory, Livermore, CA 94550
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48
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Katoh Y, Snead L. Operating Temperature Window for SiC Ceramics and Composites for Fusion Energy Applications. FUSION SCIENCE AND TECHNOLOGY 2017. [DOI: 10.13182/fst09-a9049] [Citation(s) in RCA: 12] [Impact Index Per Article: 1.7] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/12/2022]
Affiliation(s)
- Yutai Katoh
- Materials Science and Technology Division, Oak Ridge National Laboratory P.O.Box 2008, Oak Ridge, TN 37831, USA
| | - Lance Snead
- Materials Science and Technology Division, Oak Ridge National Laboratory P.O.Box 2008, Oak Ridge, TN 37831, USA
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49
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Aoyagi M, Ito S, Ebara S, Muroga T, Hashizume H. Thermo-Fluid Simulation in a Liquid Metal Blanket with Three-Surface-Multi-Layered Channel. FUSION SCIENCE AND TECHNOLOGY 2017. [DOI: 10.13182/fst11-a12366] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.1] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/12/2022]
Affiliation(s)
- Mitsuhiro Aoyagi
- Tohoku University, Aramakiaza-Aoba 6-6-01-2, Aoba-ku, Sendai, Miyagi, Japan, 980-8579
| | - Satoshi Ito
- Tohoku University, Aramakiaza-Aoba 6-6-01-2, Aoba-ku, Sendai, Miyagi, Japan, 980-8579
| | - Shinji Ebara
- Tohoku University, Aramakiaza-Aoba 6-6-01-2, Aoba-ku, Sendai, Miyagi, Japan, 980-8579
| | - Takeo Muroga
- National Institute for Fusion Science, 322-6 Oroshi, Toki,Gifu, Japan
| | - Hidetoshi Hashizume
- Tohoku University, Aramakiaza-Aoba 6-6-01-2, Aoba-ku, Sendai, Miyagi, Japan, 980-8579
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50
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Raffray AR, El-Guebaly L, Malang S, Wang X. Attractive Design Approaches for a Compact Stellarator Power Plant. FUSION SCIENCE AND TECHNOLOGY 2017. [DOI: 10.13182/fst05-a724] [Citation(s) in RCA: 7] [Impact Index Per Article: 1.0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/12/2022]
Affiliation(s)
- A. R. Raffray
- Mechanical and Aerospace Engineering Department and Center for Energy Research, 460 EBU-II, University of California-San Diego, 9500 Gilman Drive, La Jolla, CA 92093-0438, USA
| | - L. El-Guebaly
- University of Wisconsin, Fusion Technology Institute, Madison, WI 53706, USA
| | - S. Malang
- Fusion Nuclear Technology Consulting, Fliederweg 3, 76351 Linkenheim, Germany
| | - X. Wang
- Center for Energy Research, 460 EBU-II, University of California-San Diego, 9500 Gilman Drive, La Jolla, CA 92093-0438, USA
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