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Patel P, Patel R, Shroff J, Parekh R. Survival strategies to live on interplanetary system MARS. PROCEEDINGS OF THE INDIAN NATIONAL SCIENCE ACADEMY 2023. [DOI: 10.1007/s43538-022-00136-8] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 03/28/2023]
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2
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Changes in the structure and D desorptive release from W-D co-deposit layers caused by thermal annealing. NUCLEAR MATERIALS AND ENERGY 2023. [DOI: 10.1016/j.nme.2023.101371] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 02/04/2023]
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3
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Flynn HB, Larsen G. Fusion Fuel Cycle Inventory Reduction Studies Using a Processing-Time–Based Discrete-Time Interval Model. FUSION SCIENCE AND TECHNOLOGY 2022. [DOI: 10.1080/15361055.2022.2115833] [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)
- H. B. Flynn
- Savannah River National Laboratory, Aiken, South Carolina 29808
| | - George Larsen
- Savannah River National Laboratory, Aiken, South Carolina 29808
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4
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Flynn H, Larsen G. Investigating the application of Kalman Filters for real-time accountancy in fusion fuel cycles. FUSION ENGINEERING AND DESIGN 2022. [DOI: 10.1016/j.fusengdes.2022.113037] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.5] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/24/2022]
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5
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Ananyev SS, Ivanov BV, Kuteev BV. Analysis of promising technologies of DEMO-FNS fuel cycle. FUSION ENGINEERING AND DESIGN 2020. [DOI: 10.1016/j.fusengdes.2020.111940] [Citation(s) in RCA: 4] [Impact Index Per Article: 1.0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/23/2022]
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6
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Liu L, Tong R, Cai J, Yao Y, Song J, Chen C, Luo D, Yao W. Analysis of the whole process tritium transport based on fuel cycle modeling for CFETR. FUSION ENGINEERING AND DESIGN 2020. [DOI: 10.1016/j.fusengdes.2020.112060] [Citation(s) in RCA: 3] [Impact Index Per Article: 0.8] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/29/2022]
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7
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Fierro A, Sordo F, Carbajal-Ramos I, Perlado J, Rivera A. Conceptual design of a ceramic breeding blanket for laser fusion power plants with online tunable tritium breeding ratio based on a variable neutron reflector: Remarkable no need of isotopic enrichment. FUSION ENGINEERING AND DESIGN 2020. [DOI: 10.1016/j.fusengdes.2020.111648] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/24/2022]
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8
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Experimental measurements and modeling of the deuterium release from tungsten co-deposited layers. NUCLEAR MATERIALS AND ENERGY 2020. [DOI: 10.1016/j.nme.2020.100743] [Citation(s) in RCA: 4] [Impact Index Per Article: 1.0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/19/2022]
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9
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Lee SY, Chang MH, Lee JU, Ha JK, Yun SH, Lee IB, Lee ES. Mathematical Modeling to Minimize Tritium Inventory of the Fuel Cycle of ITER. FUSION SCIENCE AND TECHNOLOGY 2020. [DOI: 10.1080/15361055.2020.1712980] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/25/2022]
Affiliation(s)
- Suh-Young Lee
- Pohang University of Science and Technology, Department of Chemical Engineering, San 31, Pohang 790-784, Korea
| | - Min Ho Chang
- National Fusion Research Institute, 169-148-gil Kwahak-ro, Yusong-gu, Daejon 34133, Korea
| | - Jae-Uk Lee
- National Fusion Research Institute, 169-148-gil Kwahak-ro, Yusong-gu, Daejon 34133, Korea
| | - Jin-Kuk Ha
- Dongguk University, Department of Chemical and Biochemical Engineering, Seoul 100-715, Korea
| | - Sei-Hun Yun
- National Fusion Research Institute, 169-148-gil Kwahak-ro, Yusong-gu, Daejon 34133, Korea
| | - In-Beum Lee
- Pohang University of Science and Technology, Department of Chemical Engineering, San 31, Pohang 790-784, Korea
| | - Euy Soo Lee
- Dongguk University, Department of Chemical and Biochemical Engineering, Seoul 100-715, Korea
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10
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Riva M, Ying A, Abdou M, Ahn MY, Cho S. Impact of Outer Fuel Cycle Tritium Transport on Initial Start-Up Inventory for Next Fusion Devices. FUSION SCIENCE AND TECHNOLOGY 2019. [DOI: 10.1080/15361055.2019.1643691] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.4] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/26/2022]
Affiliation(s)
- Marco Riva
- University of California, Los Angeles, Mechanical and Aerospace Engineering Department, Los Angeles, California
| | - Alice Ying
- University of California, Los Angeles, Mechanical and Aerospace Engineering Department, Los Angeles, California
| | - Mohamed Abdou
- University of California, Los Angeles, Mechanical and Aerospace Engineering Department, Los Angeles, California
| | - Mu-Young Ahn
- National Fusion Research Institute, Daejeon, Korea
| | - Seungyon Cho
- National Fusion Research Institute, Daejeon, Korea
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11
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Khripunov VI, Kuteev BV, Zhirkin AV. Enhanced tritium production in fusion-fission hybrids for the external consumption. FUSION ENGINEERING AND DESIGN 2019. [DOI: 10.1016/j.fusengdes.2019.02.130] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.2] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/25/2022]
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12
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Shi W, Zeng Q, Wang S, Chen H. Tritium transportation modeling and analysis for tritium extraction system of HCSB blanket. FUSION ENGINEERING AND DESIGN 2019. [DOI: 10.1016/j.fusengdes.2019.03.077] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.2] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/16/2022]
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13
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Coleman M, Hörstensmeyer Y, Cismondi F. DEMO tritium fuel cycle: performance, parameter explorations, and design space constraints. FUSION ENGINEERING AND DESIGN 2019. [DOI: 10.1016/j.fusengdes.2019.01.150] [Citation(s) in RCA: 15] [Impact Index Per Article: 3.0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/29/2022]
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14
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Coleman M, McIntosh S. BLUEPRINT: A novel approach to fusion reactor design. FUSION ENGINEERING AND DESIGN 2019. [DOI: 10.1016/j.fusengdes.2018.12.036] [Citation(s) in RCA: 13] [Impact Index Per Article: 2.6] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/30/2022]
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15
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Doerner R, Tynan G, Schmid K. Implications of PMI and wall material choice on fusion reactor tritium self-sufficiency. NUCLEAR MATERIALS AND ENERGY 2019. [DOI: 10.1016/j.nme.2018.12.006] [Citation(s) in RCA: 11] [Impact Index Per Article: 2.2] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/27/2022]
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16
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Ananyev SS, Spitsyn AV, Kuteev BV. Electronic model «FC-FNS» of the fusion neutron source DEMO-FNS fuel cycle and modeling hydrogen isotopes flows and inventories in fueling systems. FUSION ENGINEERING AND DESIGN 2019. [DOI: 10.1016/j.fusengdes.2018.12.003] [Citation(s) in RCA: 10] [Impact Index Per Article: 2.0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/27/2022]
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17
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Optimal scheduling model to minimize tritium inventory level in fuel cycle of tritium plant. FUSION ENGINEERING AND DESIGN 2018. [DOI: 10.1016/j.fusengdes.2018.04.003] [Citation(s) in RCA: 3] [Impact Index Per Article: 0.5] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/20/2022]
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18
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Palermo I, Villari R, Ibarra A. Divertor options impact on DEMO nuclear performances. FUSION ENGINEERING AND DESIGN 2018. [DOI: 10.1016/j.fusengdes.2018.03.020] [Citation(s) in RCA: 3] [Impact Index Per Article: 0.5] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/25/2022]
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19
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Lee SY, Chang MH, Yun SH, Ha JK, Lee IB, Lee ES. Hypothetical daily operation model of fuel cycle in tritium plant. FUSION ENGINEERING AND DESIGN 2018. [DOI: 10.1016/j.fusengdes.2018.03.012] [Citation(s) in RCA: 4] [Impact Index Per Article: 0.7] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 12/01/2022]
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20
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Konishi S, Kasada R, Okino F. Myth of initial loading tritium for DEMO—Modelling of fuel system and operation scenario. FUSION ENGINEERING AND DESIGN 2017. [DOI: 10.1016/j.fusengdes.2017.05.138] [Citation(s) in RCA: 7] [Impact Index Per Article: 1.0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/19/2022]
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21
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Perevezentsev A, Bell A, Brennan PD, Gibbons C, Hemmerich J, Knipe S, Miller A, Stead M, Walsh P, Yorkshades J. Dedicated Facility and Glovebox for Tritium Recovery from Carbon Flakes. FUSION SCIENCE AND TECHNOLOGY 2017. [DOI: 10.13182/fst02-a22699] [Citation(s) in RCA: 3] [Impact Index Per Article: 0.4] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/12/2022]
Affiliation(s)
- A. Perevezentsev
- EURATOM/UKAEA Fusion Association, Culham Science Centre, Abingdon, 0X14 3DB, UK (01235)464484
| | - A. Bell
- EURATOM/UKAEA Fusion Association, Culham Science Centre, Abingdon, 0X14 3DB, UK (01235)464484
| | - P. D. Brennan
- EURATOM/UKAEA Fusion Association, Culham Science Centre, Abingdon, 0X14 3DB, UK (01235)464484
| | - C. Gibbons
- EURATOM/UKAEA Fusion Association, Culham Science Centre, Abingdon, 0X14 3DB, UK (01235)464484
| | | | - S. Knipe
- EURATOM/UKAEA Fusion Association, Culham Science Centre, Abingdon, 0X14 3DB, UK (01235)464484
| | - A. Miller
- EURATOM/UKAEA Fusion Association, Culham Science Centre, Abingdon, 0X14 3DB, UK (01235)464484
| | - M. Stead
- EURATOM/UKAEA Fusion Association, Culham Science Centre, Abingdon, 0X14 3DB, UK (01235)464484
| | - P. Walsh
- EURATOM/UKAEA Fusion Association, Culham Science Centre, Abingdon, 0X14 3DB, UK (01235)464484
| | - J. Yorkshades
- EURATOM/UKAEA Fusion Association, Culham Science Centre, Abingdon, 0X14 3DB, UK (01235)464484
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22
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Matsuura H, Yasumoto T, Kouchi S, Nakaya H, Shimakawa S, Nakao Y, Goto M, Nakagawa S, Nishikawa M. Study of Tritium Production for Fusion Reactors Using High-Temperature Gas-Cooled Reactors. FUSION SCIENCE AND TECHNOLOGY 2017. [DOI: 10.13182/fst12-a13431] [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)
- H. Matsuura
- Applied Quantum Physics and Nuclear Engineering, Kyushu University, 744 Motooka, Fukuoka 819-0395, Japan
| | - T. Yasumoto
- Applied Quantum Physics and Nuclear Engineering, Kyushu University, 744 Motooka, Fukuoka 819-0395, Japan
| | - S. Kouchi
- Applied Quantum Physics and Nuclear Engineering, Kyushu University, 744 Motooka, Fukuoka 819-0395, Japan
| | - H. Nakaya
- Applied Quantum Physics and Nuclear Engineering, Kyushu University, 744 Motooka, Fukuoka 819-0395, Japan
| | - S. Shimakawa
- Japan Atomic Energy Agency, 4002 Oarai, Ibaraki 319-1393, Japan
| | - Y. Nakao
- Applied Quantum Physics and Nuclear Engineering, Kyushu University, 744 Motooka, Fukuoka 819-0395, Japan
| | - M. Goto
- Japan Atomic Energy Agency, 4002 Oarai, Ibaraki 319-1393, Japan
| | - S. Nakagawa
- Japan Atomic Energy Agency, 4002 Oarai, Ibaraki 319-1393, Japan
| | - M. Nishikawa
- Graduate School of Engineering Science, Kyushu University, 6-10-1 Hakozaki, Fukuoka 812-8581, Japan
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23
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Abdou MA, Tillack MS, Raffray AR. Thermal, Fluid Flow, and Tritium Release Problems in Fusion Blankets. ACTA ACUST UNITED AC 2017. [DOI: 10.13182/fst90-a29293] [Citation(s) in RCA: 13] [Impact Index Per Article: 1.9] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/12/2022]
Affiliation(s)
- Mohamed A. Abdou
- University of California, Los Angeles Department of Mechanical, Aerospace, and Nuclear Engineering Los Angeles, California 90024
| | - M. S. Tillack
- University of California, Los Angeles Department of Mechanical, Aerospace, and Nuclear Engineering Los Angeles, California 90024
| | - A. René Raffray
- University of California, Los Angeles Department of Mechanical, Aerospace, and Nuclear Engineering Los Angeles, California 90024
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24
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Youssef MZ, Abdou MA. Uncertainties in Prediction of Tritium Breeding in Candidate Blanket Designs Due to Present Uncertainties in Nuclear Data Base. ACTA ACUST UNITED AC 2017. [DOI: 10.13182/fst86-a24716] [Citation(s) in RCA: 30] [Impact Index Per Article: 4.3] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/12/2022]
Affiliation(s)
- M. Z. Youssef
- University of California School of Engineering and Applied Science Department of Mechanical, Aerospace, and Nuclear Engineering Los Angeles, California 90024
| | - M. A. Abdou
- University of California School of Engineering and Applied Science Department of Mechanical, Aerospace, and Nuclear Engineering Los Angeles, California 90024
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25
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Stacey WM, Abbasi Z, Boyd CJ, Bridges AH, Burgett EA, Cymbor MW, Fowler SW, Jones AT, Kelm RS, Kern BJ, Lassiter DB, Maddox JA, Murphy WB, Park H, Pounders JM, Preston JR. A Subcritical, Helium-Cooled Fast Reactor for the Transmutation of Spent Nuclear Fuel. NUCL TECHNOL 2017. [DOI: 10.13182/nt06-a3777] [Citation(s) in RCA: 13] [Impact Index Per Article: 1.9] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/12/2022]
Affiliation(s)
- W. M. Stacey
- Georgia Institute of Technology, Nuclear and Radiological Engineering Program Atlanta, Georgia 30332-0425
| | - Z. Abbasi
- Georgia Institute of Technology, Nuclear and Radiological Engineering Program Atlanta, Georgia 30332-0425
| | - C. J. Boyd
- Georgia Institute of Technology, Nuclear and Radiological Engineering Program Atlanta, Georgia 30332-0425
| | - A. H. Bridges
- Georgia Institute of Technology, Nuclear and Radiological Engineering Program Atlanta, Georgia 30332-0425
| | - E. A. Burgett
- Georgia Institute of Technology, Nuclear and Radiological Engineering Program Atlanta, Georgia 30332-0425
| | - M. W. Cymbor
- Georgia Institute of Technology, Nuclear and Radiological Engineering Program Atlanta, Georgia 30332-0425
| | - S. W. Fowler
- Georgia Institute of Technology, Nuclear and Radiological Engineering Program Atlanta, Georgia 30332-0425
| | - A. T. Jones
- Georgia Institute of Technology, Nuclear and Radiological Engineering Program Atlanta, Georgia 30332-0425
| | - R. S. Kelm
- Georgia Institute of Technology, Nuclear and Radiological Engineering Program Atlanta, Georgia 30332-0425
| | - B. J. Kern
- Georgia Institute of Technology, Nuclear and Radiological Engineering Program Atlanta, Georgia 30332-0425
| | - D. B. Lassiter
- Georgia Institute of Technology, Nuclear and Radiological Engineering Program Atlanta, Georgia 30332-0425
| | - J. A. Maddox
- Georgia Institute of Technology, Nuclear and Radiological Engineering Program Atlanta, Georgia 30332-0425
| | - W. B. Murphy
- Georgia Institute of Technology, Nuclear and Radiological Engineering Program Atlanta, Georgia 30332-0425
| | - H. Park
- Georgia Institute of Technology, Nuclear and Radiological Engineering Program Atlanta, Georgia 30332-0425
| | - J. M. Pounders
- Georgia Institute of Technology, Nuclear and Radiological Engineering Program Atlanta, Georgia 30332-0425
| | - J. R. Preston
- Georgia Institute of Technology, Nuclear and Radiological Engineering Program Atlanta, Georgia 30332-0425
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26
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Nishikawa M. Tritium Breeding Ratio Required to Keep Tritium Balance in a D-T Fusion Reactor. FUSION SCIENCE AND TECHNOLOGY 2017. [DOI: 10.13182/fst11-a12601] [Citation(s) in RCA: 3] [Impact Index Per Article: 0.4] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/12/2022]
Affiliation(s)
- Masabumi Nishikawa
- Graduate School of Engineering Science, Kyushu University, Fukuoka 812-8581, Japan
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27
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Song Y, Huang Q, Ni M, Chen X. Analysis on Initial Tritium Supply for Starting Up Fusion Power Reactor FDS-II. FUSION SCIENCE AND TECHNOLOGY 2017. [DOI: 10.13182/fst11-a12612] [Citation(s) in RCA: 5] [Impact Index Per Article: 0.7] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/12/2022]
Affiliation(s)
- Yong Song
- Institute of Plasma Physics, Chinese Academy of Sciences, Hefei, Anhui, 230031, China
| | - Qunying Huang
- Institute of Plasma Physics, Chinese Academy of Sciences, Hefei, Anhui, 230031, China
- School of Nuclear Science and Technology, University of Science and Technology of China, Hefei, Anhui, 230027, China
| | - Muyi Ni
- Institute of Plasma Physics, Chinese Academy of Sciences, Hefei, Anhui, 230031, China
| | - Xiaoqiang Chen
- Institute of Plasma Physics, Chinese Academy of Sciences, Hefei, Anhui, 230031, China
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28
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Nishikawa M. Study on Tritium Balance in a D-T Fusion Reactor. FUSION SCIENCE AND TECHNOLOGY 2017. [DOI: 10.13182/fst10-a9366] [Citation(s) in RCA: 13] [Impact Index Per Article: 1.9] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/12/2022]
Affiliation(s)
- Masabumi Nishikawa
- Kyushu University, Graduate School of Engineering Science Hakozaki 6-10-1, Higashi-ku, Fukuoka 812-8581, Japan
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29
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Stacey WM, Mandrekas J, Hoffman EA, Kessler GP, Kirby CM, Mauer AN, Noble JJ, Stopp DM, Ulevich DS. A Fusion Transmutation of Waste Reactor. FUSION SCIENCE AND TECHNOLOGY 2017. [DOI: 10.13182/fst02-a207] [Citation(s) in RCA: 33] [Impact Index Per Article: 4.7] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/12/2022]
Affiliation(s)
- W. M. Stacey
- Georgia Institute of Technology Nuclear and Radiological Engineering Program and Fusion Research Center, Atlanta, Georgia 30332
| | - J. Mandrekas
- Georgia Institute of Technology Nuclear and Radiological Engineering Program and Fusion Research Center, Atlanta, Georgia 30332
| | - E. A. Hoffman
- Georgia Institute of Technology Nuclear and Radiological Engineering Program and Fusion Research Center, Atlanta, Georgia 30332
| | - G. P. Kessler
- Georgia Institute of Technology Nuclear and Radiological Engineering Program and Fusion Research Center, Atlanta, Georgia 30332
| | - C. M. Kirby
- Georgia Institute of Technology Nuclear and Radiological Engineering Program and Fusion Research Center, Atlanta, Georgia 30332
| | - A. N. Mauer
- Georgia Institute of Technology Nuclear and Radiological Engineering Program and Fusion Research Center, Atlanta, Georgia 30332
| | - J. J. Noble
- Georgia Institute of Technology Nuclear and Radiological Engineering Program and Fusion Research Center, Atlanta, Georgia 30332
| | - D. M. Stopp
- Georgia Institute of Technology Nuclear and Radiological Engineering Program and Fusion Research Center, Atlanta, Georgia 30332
| | - D. S. Ulevich
- Georgia Institute of Technology Nuclear and Radiological Engineering Program and Fusion Research Center, Atlanta, Georgia 30332
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30
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Şarer B, Günay M, Korkmaz ME, Hançerlioğullari A. Three-Dimensional Neutronic Calculations for the Fusion Breeder APEX Reactor. FUSION SCIENCE AND TECHNOLOGY 2017. [DOI: 10.13182/fst07-a1490] [Citation(s) in RCA: 20] [Impact Index Per Article: 2.9] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/12/2022]
Affiliation(s)
- B. Şarer
- Gazi Üniversitesi Fen-Edebiyat Fakültesi Fizik Bölömü, Ankara, Turkey
| | - M. Günay
- İnönü Üniversitesi Fen-Edebiyat Fakültesi Fizik Bölömü, Malatya, Turkey
| | - M. E. Korkmaz
- Gazi Üniversitesi Fen-Edebiyat Fakültesi Fizik Bölömü, Ankara, Turkey
| | - A. Hançerlioğullari
- Kastamonu Üniversitesi Kastamonu Fen-Edebiyat Fakültesi Fizik Bölömü Kastamonu, Turkey
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31
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Affiliation(s)
- Nishikawa Masabumi
- Kyushu University, Graduate School of Engineering Science, Hakozaki 6-10-1, Higashi-ku, Fukuoka 812-8581, Japan
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32
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Hoffman EA, Stacey WM. Nuclear Design and Analysis of the Fusion Transmutation of Waste Reactor. FUSION SCIENCE AND TECHNOLOGY 2017. [DOI: 10.13182/fst04-a425] [Citation(s) in RCA: 9] [Impact Index Per Article: 1.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/12/2022]
Affiliation(s)
- E. A. Hoffman
- Georgia Institute of Technology Fusion Research Center and Nuclear & Radiological Engineering Program, Atlanta, GA 30332
| | - W. M. Stacey
- Georgia Institute of Technology Fusion Research Center and Nuclear & Radiological Engineering Program, Atlanta, GA 30332
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33
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Jackson GL, Chan VS, Stambaugh RD. An Analytic Expression for the Tritium Burnup Fraction in Burning-Plasma Devices. FUSION SCIENCE AND TECHNOLOGY 2017. [DOI: 10.13182/fst13-a17042] [Citation(s) in RCA: 10] [Impact Index Per Article: 1.4] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/12/2022]
Affiliation(s)
- G. L. Jackson
- General Atomics, P.O. Box 85608, San Diego, California 92186-5608
| | - V. S. Chan
- General Atomics, P.O. Box 85608, San Diego, California 92186-5608
| | - R. D. Stambaugh
- General Atomics, P.O. Box 85608, San Diego, California 92186-5608
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34
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Zhao P, Yang W, Li Y, Ge Z, Nie X, Gao Z. Tritium transport analysis for CFETR WCSB blanket. FUSION ENGINEERING AND DESIGN 2017. [DOI: 10.1016/j.fusengdes.2016.11.009] [Citation(s) in RCA: 9] [Impact Index Per Article: 1.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/24/2022]
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35
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Günay M, Şeker G. Three-dimensional Monte Carlo calculation of some nuclear parameters. EPJ WEB OF CONFERENCES 2017. [DOI: 10.1051/epjconf/201715401026] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/14/2022] Open
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36
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37
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Sensitivity analysis of tritium breeding ratio and startup inventory for CFETR. FUSION ENGINEERING AND DESIGN 2016. [DOI: 10.1016/j.fusengdes.2016.08.026] [Citation(s) in RCA: 4] [Impact Index Per Article: 0.5] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/21/2022]
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38
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Chen H, Pan L, Lv Z, Li W, Zeng Q. Tritium fuel cycle modeling and tritium breeding analysis for CFETR. FUSION ENGINEERING AND DESIGN 2016. [DOI: 10.1016/j.fusengdes.2016.02.100] [Citation(s) in RCA: 11] [Impact Index Per Article: 1.4] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/22/2022]
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39
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Günay M. Monte Carlo calculations of the nuclear effects of certain fluids in a hybrid reactor. PROGRESS IN NUCLEAR ENERGY 2016. [DOI: 10.1016/j.pnucene.2015.10.017] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/30/2022]
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40
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Abdou M, Morley NB, Smolentsev S, Ying A, Malang S, Rowcliffe A, Ulrickson M. Blanket/first wall challenges and required R&D on the pathway to DEMO. FUSION ENGINEERING AND DESIGN 2015. [DOI: 10.1016/j.fusengdes.2015.07.021] [Citation(s) in RCA: 193] [Impact Index Per Article: 21.4] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/17/2022]
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41
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Kasada R, Kwon S, Konishi S, Sakamoto Y, Yamanishi T, Tobita K. A system dynamics model for stock and flow of tritium in fusion power plant. FUSION ENGINEERING AND DESIGN 2015. [DOI: 10.1016/j.fusengdes.2015.03.047] [Citation(s) in RCA: 7] [Impact Index Per Article: 0.8] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/23/2022]
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42
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Günay M. Neutronic performance calculations with alternative fluids in a hybrid reactor by using the Monte Carlo method. KERNTECHNIK 2015. [DOI: 10.3139/124.110479] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Abstract] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/20/2022]
Abstract
Abstract
In this study, salt-heavy metal mixtures consisting of 93–85% Li20Sn80 + 5% SFG-PuO2 and 2–10% UO2, 93–85% Li20Sn80 + 5% SFG-PuO2 and 2–10% NpO2, and 93–85% Li20Sn80 + 5% SFG-PuO2 and 2–10% UCO were used as fluids. The fluids were used in the liquid first wall, blanket, and shield zones of a fusion–fission hybrid reactor system. A beryllium (Be) zone with a width of 3 cm was used for neutron multiplicity between the liquid first wall and the blanket. 9Cr2WVTa ferritic steel with the width of 4 cm was used as the structural material. The contributions of each isotope in the fluids to the nuclear parameters, such as tritium breeding ratio (TBR), energy multiplication factor (M), and heat deposition rate, of the fusion–fission hybrid reactor were calculated in the liquid first wall, blanket, and shield zones. Three-dimensional analyses were performed using the Monte Carlo code MCNPX-2.7.0 and nuclear data library ENDF/B-VII.0.
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Affiliation(s)
- M. Günay
- İnönü University , Science and Art Faculty, Physics Department, Malatya , Turkey. E-mail:
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Tritium Breeding Ratio Calculation for ITER Tokamak Using Developed Helium Cooled Pebble Bed Blanket (HCPB). JOURNAL OF FUSION ENERGY 2015. [DOI: 10.1007/s10894-015-9847-1] [Citation(s) in RCA: 4] [Impact Index Per Article: 0.4] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/24/2022]
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44
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Möller S, Kreter A, Linsmeier C, Samm U. Thermally activated reaction–diffusion-controlled chemical bulk reactions of gases and solids. NUCLEAR MATERIALS AND ENERGY 2015. [DOI: 10.1016/j.nme.2014.11.002] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.1] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/24/2022]
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45
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Preliminary Shielding Design and Analysis of Liquid Lead–Lithium Blanket for Chinese Fusion Engineering Testing Reactor. JOURNAL OF FUSION ENERGY 2014. [DOI: 10.1007/s10894-014-9819-x] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.2] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/30/2022]
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46
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Wong C, Merrill B. Use of system code to estimate equilibrium tritium inventory in fusion DT machines, such as ARIES-AT and components testing facilities. FUSION ENGINEERING AND DESIGN 2014. [DOI: 10.1016/j.fusengdes.2014.03.001] [Citation(s) in RCA: 7] [Impact Index Per Article: 0.7] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/30/2022]
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47
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Morgan L, Packer L. A neutron poison tritium breeding controller applied to a water cooled fusion reactor model. FUSION ENGINEERING AND DESIGN 2014. [DOI: 10.1016/j.fusengdes.2014.04.061] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.1] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/25/2022]
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Stacey WM, Stewart CL, Floyd JP, Wilks TM, Moore AP, Bopp AT, Hill MD, Tandon S, Erickson AS. Resolution of Fission and Fusion Technology Integration Issues: An Upgraded Design Concept for the Subcritical Advanced Burner Reactor. NUCL TECHNOL 2014. [DOI: 10.13182/nt13-96] [Citation(s) in RCA: 14] [Impact Index Per Article: 1.4] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/12/2022]
Affiliation(s)
- W. M. Stacey
- Georgia Institute of Technology, Nuclear & Radiological Engineering Program Atlanta, Georgia 30332-0745
| | - C. L. Stewart
- Georgia Institute of Technology, Nuclear & Radiological Engineering Program Atlanta, Georgia 30332-0745
| | - J.-P. Floyd
- Georgia Institute of Technology, Nuclear & Radiological Engineering Program Atlanta, Georgia 30332-0745
| | - T. M. Wilks
- Georgia Institute of Technology, Nuclear & Radiological Engineering Program Atlanta, Georgia 30332-0745
| | - A. P. Moore
- Georgia Institute of Technology, Nuclear & Radiological Engineering Program Atlanta, Georgia 30332-0745
| | - A. T. Bopp
- Georgia Institute of Technology, Nuclear & Radiological Engineering Program Atlanta, Georgia 30332-0745
| | - M. D. Hill
- Georgia Institute of Technology, Nuclear & Radiological Engineering Program Atlanta, Georgia 30332-0745
| | - S. Tandon
- Georgia Institute of Technology, Nuclear & Radiological Engineering Program Atlanta, Georgia 30332-0745
| | - A. S. Erickson
- Georgia Institute of Technology, Nuclear & Radiological Engineering Program Atlanta, Georgia 30332-0745
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Hartwig ZS, Barnard HS, Lanza RC, Sorbom BN, Stahle PW, Whyte DG. An in situ accelerator-based diagnostic for plasma-material interactions science on magnetic fusion devices. THE REVIEW OF SCIENTIFIC INSTRUMENTS 2013; 84:123503. [PMID: 24387430 DOI: 10.1063/1.4832420] [Citation(s) in RCA: 5] [Impact Index Per Article: 0.5] [Reference Citation Analysis] [Abstract] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 06/03/2023]
Abstract
This paper presents a novel particle accelerator-based diagnostic that nondestructively measures the evolution of material surface compositions inside magnetic fusion devices. The diagnostic's purpose is to contribute to an integrated understanding of plasma-material interactions in magnetic fusion, which is severely hindered by a dearth of in situ material surface diagnosis. The diagnostic aims to remotely generate isotopic concentration maps on a plasma shot-to-shot timescale that cover a large fraction of the plasma-facing surface inside of a magnetic fusion device without the need for vacuum breaks or physical access to the material surfaces. Our instrument uses a compact (~1 m), high-current (~1 milliamp) radio-frequency quadrupole accelerator to inject 0.9 MeV deuterons into the Alcator C-Mod tokamak at MIT. We control the tokamak magnetic fields--in between plasma shots--to steer the deuterons to material surfaces where the deuterons cause high-Q nuclear reactions with low-Z isotopes ~5 μm into the material. The induced neutrons and gamma rays are measured with scintillation detectors; energy spectra analysis provides quantitative reconstruction of surface compositions. An overview of the diagnostic technique, known as accelerator-based in situ materials surveillance (AIMS), and the first AIMS diagnostic on the Alcator C-Mod tokamak is given. Experimental validation is shown to demonstrate that an optimized deuteron beam is injected into the tokamak, that low-Z isotopes such as deuterium and boron can be quantified on the material surfaces, and that magnetic steering provides access to different measurement locations. The first AIMS analysis, which measures the relative change in deuterium at a single surface location at the end of the Alcator C-Mod FY2012 plasma campaign, is also presented.
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Affiliation(s)
- Zachary S Hartwig
- Plasma Science and Fusion Center, Massachusetts Institute of Technology, 77 Massachusetts Ave, Cambridge Massachusetts 02139, USA
| | - Harold S Barnard
- Plasma Science and Fusion Center, Massachusetts Institute of Technology, 77 Massachusetts Ave, Cambridge Massachusetts 02139, USA
| | - Richard C Lanza
- Plasma Science and Fusion Center, Massachusetts Institute of Technology, 77 Massachusetts Ave, Cambridge Massachusetts 02139, USA
| | - Brandon N Sorbom
- Plasma Science and Fusion Center, Massachusetts Institute of Technology, 77 Massachusetts Ave, Cambridge Massachusetts 02139, USA
| | - Peter W Stahle
- Plasma Science and Fusion Center, Massachusetts Institute of Technology, 77 Massachusetts Ave, Cambridge Massachusetts 02139, USA
| | - Dennis G Whyte
- Plasma Science and Fusion Center, Massachusetts Institute of Technology, 77 Massachusetts Ave, Cambridge Massachusetts 02139, USA
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Tritium supply assessment for ITER and DEMOnstration power plant. FUSION ENGINEERING AND DESIGN 2013. [DOI: 10.1016/j.fusengdes.2013.05.043] [Citation(s) in RCA: 31] [Impact Index Per Article: 2.8] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/22/2022]
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