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Devi VG, Kannan A, Yadav D, Sircar A. Low-pressure adsorption of hydrogen isotopologues on LTA4A zeolites - A grand canonical Monte Carlo simulation study. FUSION ENGINEERING AND DESIGN 2023. [DOI: 10.1016/j.fusengdes.2022.113401] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 12/27/2022]
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2
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Influence of the orientation of the magnetic field on the MHD unaligned isothermal flows. FUSION ENGINEERING AND DESIGN 2021. [DOI: 10.1016/j.fusengdes.2021.112806] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/18/2022]
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Kumar P, Thakur A, Saha SK, Sharma A, Sharma D, Chaudhuri P. CFD Investigation of helium gas flow in sphere packed (Pebble bed) in a rectangular canister using OpenFOAM. FUSION ENGINEERING AND DESIGN 2021. [DOI: 10.1016/j.fusengdes.2021.112858] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/20/2022]
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Rajan K, Aruna B, Anju S, Pedada P, Verma S, Bhattacharyay R. Design development and testing of mutual inductance type level sensor for molten lead-lithium alloy. FUSION ENGINEERING AND DESIGN 2021. [DOI: 10.1016/j.fusengdes.2021.112650] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/21/2022]
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Yadav B, Sandeep K, Gandhi A, Saraswat A, Sharma D, Chaudhuri P. Design updates for helium cooling system of Indian LLCB blanket. FUSION ENGINEERING AND DESIGN 2021. [DOI: 10.1016/j.fusengdes.2021.112342] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/29/2022]
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de les Valls EM, Cegielski A, Jaros M, Pérez-Ferragut M, Batet L, Sandeep T, Chaudhari V, Freixa J. Development of flow regime maps for lead lithium eutectic–helium flows. FUSION ENGINEERING AND DESIGN 2020. [DOI: 10.1016/j.fusengdes.2020.111691] [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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Sharma D, Ranjithkumar S, Chaudhuri P, Kumar ER. Thermal-hydraulics and structural analyses of LLCB TBM set. FUSION ENGINEERING AND DESIGN 2020. [DOI: 10.1016/j.fusengdes.2019.111372] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/15/2022]
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Kumar M, Patel A, Jaiswal A, Ranjan A, Mohanta D, Sahu S, Saraswat A, Rao P, Rao T, Mehta V, Ranjith kumar S, Bhattacharyay R, Rajendrakumar E, Malhotra S, Satyamurthy P. Engineering design and development of lead lithium loop for thermo-fluid MHD studies. FUSION ENGINEERING AND DESIGN 2019. [DOI: 10.1016/j.fusengdes.2018.09.016] [Citation(s) in RCA: 6] [Impact Index Per Article: 1.2] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/28/2022]
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Design, development and testing of prototype cold trap for Pb-16Li purification. FUSION ENGINEERING AND DESIGN 2018. [DOI: 10.1016/j.fusengdes.2018.08.021] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/19/2022]
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Swami H, Sharma S, Shaw A, Danani C. Neutronic design optimization of ITER TBM port#2 bio-shield plug. FUSION ENGINEERING AND DESIGN 2018. [DOI: 10.1016/j.fusengdes.2018.08.015] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/29/2022]
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Atchutuni SS, Agravat HS, Chauhan J, E. RK. Corrosion behavior of IN-RAFM steel with stagnant lead-lithium at 550 °C up to 9000 h. FUSION ENGINEERING AND DESIGN 2018. [DOI: 10.1016/j.fusengdes.2018.07.015] [Citation(s) in RCA: 6] [Impact Index Per Article: 1.0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/29/2022]
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12
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Data-acquisition, control & interlock system design for corrosion experiments of IN-RAFM steel with flowing Pb-Li in presence of magnetic field. FUSION ENGINEERING AND DESIGN 2018. [DOI: 10.1016/j.fusengdes.2018.05.067] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/21/2022]
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Atchutuni SS, Saraswat A, Sasmal CS, Verma S, Prajapati AK, Jaiswal A, Gupta S, Chauhan J, Pandya KB, Makwana M, Tailor H, Agravat HS, P. PR, E. RK. Corrosion experiments on IN-RAFM steel in flowing lead-lithium for Indian LLCB TBM. FUSION ENGINEERING AND DESIGN 2018. [DOI: 10.1016/j.fusengdes.2018.05.020] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.2] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/16/2022]
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Numerical and experimental MHD studies of Lead-Lithium liquid metal flows in multichannel test-section at high magnetic fields. FUSION ENGINEERING AND DESIGN 2018. [DOI: 10.1016/j.fusengdes.2018.04.125] [Citation(s) in RCA: 13] [Impact Index Per Article: 2.2] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/18/2022]
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Saraswat SP, Munsh P, Khanna A, Allison C. Thermal Hydraulic Safety Assessment of LLCB Test Blanket System in ITER Using Modified relap/scdapsim/mod4.0 Code. JOURNAL OF NUCLEAR ENGINEERING AND RADIATION SCIENCE 2018. [DOI: 10.1115/1.4038823] [Citation(s) in RCA: 10] [Impact Index Per Article: 1.7] [Reference Citation Analysis] [Abstract] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/08/2022]
Abstract
This work attempts to investigate the thermal hydraulic safety of lithium lead ceramic breeder (LLCB) test blanket system (TBS) in International Thermonuclear Experimental Reactor (ITER) with the help of modified thermal hydraulic code relap/scdapsim/mod4.0. The design basis accidents, in-vessel and ex-vessel loss of coolant of first wall (FW) of test blanket module (TBM) are analyzed for this safety assessment. The sequence of accidents analyzed was started with postulated initiating events (PIEs). A detailed modeling of first wall helium cooling system (FWHCS) loop and lithium lead cooling system (LLCS) is presented. The analysis of steady-state normal operation along with 10 s power excursion before the accident is also discussed in order to better understanding of initial condition of accidents. The analysis discusses a number of safety concerns and issues that may result from the TBM component failure, such as vacuum vessel (VV) pressurization, TBM FW temperature profile, passive decay heat removal capability of TBM structure, pressurization of port cell and Tokomak cooling water system vault annex (TCWS-VA) and to check the capability of passive safety system (vacuum vessel pressure suppression system (VVPSS)). The analysis shows that in these accident scenarios, the critical parameters have reasonable safety margins.
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Affiliation(s)
- S. P. Saraswat
- Nuclear Engineering and Technology Programme, Indian Institute of Technology Kanpur, Kanpur 208016, India e-mails:
| | - P. Munsh
- Nuclear Engineering and Technology Programme, Indian Institute of Technology Kanpur, Kanpur 208016, India e-mail:
| | - A. Khanna
- Nuclear Engineering and Technology Programme, Indian Institute of Technology Kanpur, Kanpur 208016, India e-mail:
| | - C. Allison
- Innovative Systems Software, Idaho Falls, ID 83406 e-mail:
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Devi VG, Sircar A, Yadav D, Parmar J. Analysis of trace levels of impurities and hydrogen isotopes in helium purge gas using gas chromatography for tritium extraction system of an Indian lead lithium ceramic breeder test blanket module. J Sep Sci 2018; 41:1798-1804. [PMID: 29327466 DOI: 10.1002/jssc.201700911] [Citation(s) in RCA: 4] [Impact Index Per Article: 0.7] [Reference Citation Analysis] [Abstract] [Key Words] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Received: 08/16/2017] [Revised: 12/18/2017] [Accepted: 12/30/2017] [Indexed: 11/06/2022]
Abstract
In the fusion fuel cycle, the accurate analysis and understanding of the chemical composition of any gas mixture is of great importance for the efficient design of a tritium extraction and purification system or any tritium handling system. Methods like laser Raman spectroscopy and gas chromatography with thermal conductivity detector have been considered for hydrogen isotopes analyses in fuel cycles. Gas chromatography with a cryogenic separation column has been used for the analysis of hydrogen isotopes gas mixtures in general due to its high reliability and ease of operation. Hydrogen isotopes gas mixture analysis with cryogenic columns has been reported earlier using different column materials for percentage level composition. In the present work, trace levels of hydrogen isotopes (∼100 ppm of H2 and D2 ) have been analyzed with a Zeolite 5A and a modified γ-Al2 O3 column. Impurities in He gas (∼10 ppm of H2 , O2 , and N2 ) have been analyzed using a Zeolite 13-X column. Gas chromatography with discharge ionization detection has been utilized for this purpose. The results of these experiments suggest that the columns developed were able to separate ppm levels of the desired components with a small response time (<6 min) and good resolution in both cases.
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Affiliation(s)
| | - Amit Sircar
- Institute for Plasma Research, Gandhinagar, India
| | - Deepak Yadav
- Institute for Plasma Research, Gandhinagar, India
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Yadav B, Gandhi A, Verma A, Sandeep K, Chaudhari V, Kumar ER. Helium cooling systems for Indian LLCB TBM testing in ITER. FUSION ENGINEERING AND DESIGN 2017. [DOI: 10.1016/j.fusengdes.2017.05.097] [Citation(s) in RCA: 5] [Impact Index Per Article: 0.7] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/16/2022]
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Brahmbhatt P, Sircar A, Patel R, RajendraKumar E, Mohan S, Bhanja K. Estimation of Tritium Release from LLCB TBM and Its Ancillary Systems and Tritium Management in Different Locations of ITER. FUSION SCIENCE AND TECHNOLOGY 2017. [DOI: 10.1080/15361055.2017.1289580] [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)
| | - Amit Sircar
- Institute for Plasma Research, Gandhinagar, Gujarat, India
| | - Rudreksh Patel
- Institute for Plasma Research, Gandhinagar, Gujarat, India
| | | | - Sadhana Mohan
- Bhabha Atomic Research Centre, Mumbai, Maharashtra, India
| | - Kalyan Bhanja
- Bhabha Atomic Research Centre, Mumbai, Maharashtra, India
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Shrivastava A, Makwana M, Chaudhuri P, Rajendrakumar E. Preparation and Characterization of the Lithium Metatitanate Ceramics by Solution-Combustion Method for Indian LLCB TBM. FUSION SCIENCE AND TECHNOLOGY 2017. [DOI: 10.13182/fst13-658] [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)
- A. Shrivastava
- Institute for Plasma Research, Gandhinagar, Gujarat, India
| | - M. Makwana
- Institute for Plasma Research, Gandhinagar, Gujarat, India
| | - P. Chaudhuri
- Institute for Plasma Research, Gandhinagar, Gujarat, India
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Saraswat SP, Munshi P, Khanna A, Allison C. Thermal Hydraulic and Safety Assessment of First Wall Helium Cooling System of a Generalized Test Blanket System in ITER Using RELAP/SCDAPSIM/MOD4.0 Code. JOURNAL OF NUCLEAR ENGINEERING AND RADIATION SCIENCE 2016. [DOI: 10.1115/1.4034680] [Citation(s) in RCA: 5] [Impact Index Per Article: 0.6] [Reference Citation Analysis] [Abstract] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/08/2022]
Abstract
The key objective of the test blanket module (TBM) program is to develop the design technology for DEMO and future power-producing fusion reactors. The proposed first wall of the test blanket system (TBS) is a generalized concept for testing in ITER, an experimental fusion reactor under construction in France presently. The first wall of TBM (TBM FW) directly faces the plasma and is cooled by the first wall helium cooling system (FWHCS), which is considered as a critical component from an ITER safety point of view. The scope of this work comprises thermal hydraulic analysis of the FWHCS of a generalized TBS and the assessment of postulated initiating events (PIEs) on the ITER safety with the help of thermal-hydraulic code RELAP/SCDAPSIM/MOD4.0. The three reference accidents: in-vacuum vessel (VV) loss of coolant accident (in-vessel LOCA), ex-vessel LOCA, and loss of flow accident (LOFA) in FWHCS are selected for the safety assessment. This safety assessment addresses safety concerns resulting from FWHCS component failure, such as VV pressurization, TBM FW temperature profile, pressurization of port cell (PC) and Tokomak cooling water system vault annex (TCWS-VA), and passive decay heat removal capability. The analysis shows that the critical parameters are under the design limit and have large safety margins, in the investigated accident scenarios. A comparative analysis is also carried out with the previous results to validate the results.
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Affiliation(s)
- S. P. Saraswat
- Nuclear Engineering and Technology Programme, Indian Institute of Technology Kanpur, Kanpur 208016, India e-mail:
| | - P. Munshi
- Nuclear Engineering and Technology Programme, Indian Institute of Technology Kanpur, Kanpur 208016, India e-mail:
| | - A. Khanna
- Nuclear Engineering and Technology Programme, Indian Institute of Technology Kanpur, Kanpur 208016, India e-mail:
| | - C. Allison
- Innovative Systems Software, Idaho Falls, ID 83406 e-mail:
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Ranjithkumar S, Sharma D, Chaudhuri P, Danani C, Kumar ER, Khan I, Bhattacharya S, Vyas K. Engineering design and analysis of Indian LLCB TBM set. FUSION ENGINEERING AND DESIGN 2016. [DOI: 10.1016/j.fusengdes.2015.11.018] [Citation(s) in RCA: 9] [Impact Index Per Article: 1.1] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/22/2022]
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Accident analyses of selected postulated events for safety assessment of Indian LLCB TBS in ITER. FUSION ENGINEERING AND DESIGN 2016. [DOI: 10.1016/j.fusengdes.2015.11.031] [Citation(s) in RCA: 6] [Impact Index Per Article: 0.8] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/30/2022]
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Jakhar S, Abhangi M, Tiwari S, Makwana R, Chaudhari V, Swami H, Danani C, Rao C, Basu T, Mandal D, Bhade S, Kolekar R, Reddy P, Bhattacharyay R, Chaudhuri P. Tritium breeding mock-up experiments containing lithium titanate ceramic pebbles and lead irradiated with DT neutrons. FUSION ENGINEERING AND DESIGN 2015. [DOI: 10.1016/j.fusengdes.2015.04.003] [Citation(s) in RCA: 12] [Impact Index Per Article: 1.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/29/2022]
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Cheng J, Wu Y, Tian W, Su G, Qiu S. Neutronics and thermo-hydraulic design of supercritical-water cooled solid breeder TBM. FUSION ENGINEERING AND DESIGN 2015. [DOI: 10.1016/j.fusengdes.2015.01.054] [Citation(s) in RCA: 7] [Impact Index Per Article: 0.8] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/24/2022]
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Satyamurthy P, Swain P, Tiwari V, Kirillov I, Obukhov D, Pertsev D. Experiments and numerical MHD analysis of LLCB TBM Test-section with NaK at 1 T magnetic field. FUSION ENGINEERING AND DESIGN 2015. [DOI: 10.1016/j.fusengdes.2014.12.015] [Citation(s) in RCA: 11] [Impact Index Per Article: 1.2] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/24/2022]
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Qi S, Wang G, Chen C, Tang H. Thermal–Hydraulic Analysis and Optimization of HCPB Breeder Unit for Future Fusion Reactor. JOURNAL OF FUSION ENERGY 2015. [DOI: 10.1007/s10894-014-9768-4] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.1] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/29/2022]
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Trivedi A, Sandeep K, Allison C, Khanna A, Chaudhari V, Kumar E, Munshi P. Incorporation of lithium lead eutectic as a working fluid in RELAP5 and preliminary safety assessment of LLCS. FUSION ENGINEERING AND DESIGN 2014. [DOI: 10.1016/j.fusengdes.2014.08.002] [Citation(s) in RCA: 7] [Impact Index Per Article: 0.7] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/26/2022]
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Liquid metal MHD studies with non-magnetic and ferro-magnetic structural material. FUSION ENGINEERING AND DESIGN 2014. [DOI: 10.1016/j.fusengdes.2014.02.003] [Citation(s) in RCA: 3] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/21/2022]
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Chaudhuri P, Ranjithkumar S, Sharma D, Danani C, Swami H, Bhattacharya R, Patel A, Kumar ER, Vyas K. Progress in engineering design of Indian LLCB TBM set for testing in ITER. FUSION ENGINEERING AND DESIGN 2014. [DOI: 10.1016/j.fusengdes.2014.02.001] [Citation(s) in RCA: 24] [Impact Index Per Article: 2.4] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/25/2022]
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Chaudhuri P. Measurement of Thermal Diffusivity of Li 2TiO 3Pellets by the Laser Flash Method and Comparison with Finite Element Simulation. FUSION SCIENCE AND TECHNOLOGY 2014. [DOI: 10.13182/fst13-676] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/12/2022]
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Swain P, Satyamurthy P, Bhattacharyay R, Patel A, Shishko A, Platacis E, Ziks A, Ivanov S, Despande A. 3D MHD lead–lithium liquid metal flow analysis and experiments in a Test-Section of multiple rectangular bends at moderate to high Hartmann numbers. FUSION ENGINEERING AND DESIGN 2013. [DOI: 10.1016/j.fusengdes.2013.05.048] [Citation(s) in RCA: 13] [Impact Index Per Article: 1.2] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/26/2022]
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Tritium management and safety issues in ITER and DEMO breeding blankets. FUSION ENGINEERING AND DESIGN 2013. [DOI: 10.1016/j.fusengdes.2013.03.032] [Citation(s) in RCA: 33] [Impact Index Per Article: 3.0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 01/29/2023]
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