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NTIS 바로가기Fusion engineering and design, v.158, 2020년, pp.111674 -
Giancarli, Luciano M. (ITER Organization) , Bravo, Xavier (ITER Organization) , Cho, Seungyon (NFRI) , Ferrari, Marco (Fusion for Energy) , Hayashi, Takumi (QST) , Kim, Byoung-Yoon (ITER Organization) , Leal-Pereira, Artur (ITER Organization) , Martins, Jean-Pierre (ITER Organization) , Merola, Mario (ITER Organization) , Pascal, Romain (ITER Organization) , Schneiderova, Iva (ITER Organization) , Sheng, Qian (ITER China Domestic Agency) , Sircar, Amit (Institute for Plasma Research) , Strebkov, Yuri , van der Laan, Jaap (ITER Organization) , Ying, Alice (University of California, Los Angeles (UCLA))
Abstract The ITER Test Blanket Module (TBM) Program has significantly evolved since 2018. The number of equatorial ports allocated for operating the Test Blanket Systems (TBSs) has been reduced from three to two. As consequence, four TBSs can be simultaneously installed and operated, versus six pre...
Fus. Eng. and Des. Giancarli 109-111 1491 2016 10.1016/j.fusengdes.2015.11.046 Progress and challenges of the ITER TBM Program from the IO Perspective
Fus. Eng. and Des. Giancarli 136 815 2018 10.1016/j.fusengdes.2018.04.014 ITER TBM Program and associated system engineering
J. Aubert, J. Vallory, et al., Design and Preliminary Analyses of the New Water Cooled Lithium Lead TBM for ITER, ISFNT-14 proceeding, this conference.
Fus. Eng. and Des. Zmitko 136 1376 2018 10.1016/j.fusengdes.2018.05.014 Development and qualification of functional materials for the European HCPB TBM
Fusion Eng. Des. Tanigawa 136 1221 2018 10.1016/j.fusengdes.2018.04.105 Cylindrical breeding blankets for fusion reactors
Y. Kawamura, H. Gwon, H. Tanigawa, T. Hayashi, et al., Progress of Water Cooled Ceramic Breeder Test Blanket Module System, ISFNT-14 proceeding, this conference.
Fus. Eng. and Des. 136, Part A Cho 190 2018 10.1016/j.fusengdes.2018.01.050 Investigation of technical gaps between DEMO blanket and HCCR TBM
Nucl. Fusion Wang 59 2019 10.1088/1741-4326/ab0c32 Current design and R&D progress of the Chinese helium cooled ceramic breeder test blanket system
Fus. Eng. and Des. Overview of LLCB TBM design and R&D activities in India E 109-111 1522 2016 Vyas and T. Jayakumar
Fus. Eng. and Des. Wong 85 1129 2010 10.1016/j.fusengdes.2010.02.021 An overview of the US DCLL ITER TBM program
Fus. Eng. Des. Chaudhuri 88 209 2013 10.1016/j.fusengdes.2013.02.023 Overview of design and thermal-hydraulic analysis of Indian solid breeder blanket concept
Fus. Eng. Des. Sharma 129 40 2018 10.1016/j.fusengdes.2018.01.075 Design and analysis of manifolds for Indian HCCB blanket module
Plasma Sci. Technol. Chaudhuri 19 125604 2017 10.1088/2058-6272/aa8807 Comparative studies for two different orientations of pebble bed in an HCCB blanket
Fus. Eng. and Des. Zmitko 124 767 2017 10.1016/j.fusengdes.2017.04.051 The European ITER Test Blanket Modules: EUROFER97 material and TBM’s fabrication technologies development and qualification
Fus. Eng. and Des. Lee 98-99 1821 2015 10.1016/j.fusengdes.2015.06.141 Integrated design and performance analysis of KO HCCR TBM for ITER
Nucl. Fusion Huang 57 2017 10.1088/1741-4326/aa763f Status and improvement of CLAM for nuclear application
Mater. Sci. Eng. A Zhao 735 260 2018 10.1016/j.msea.2018.08.048 Experimental and numerical simulation analysis on creep crack growth behaviour of CLAM steel
J. Nucl. Mater. Liang 510 437 2018 10.1016/j.jnucmat.2018.08.032 Effect of tempering time on fatigue crack growth behavior of CLAM steel
J. Nucl. Mater. Huang 500 33 2018 10.1016/j.jnucmat.2017.12.011 Microstructure anisotropy and its effect on mechanical properties of reduced activation ferritic/martensitic steel fabricated by selective laser melting
Fus. Eng. and Des Luo 109-111 Part A 416 2016 10.1016/j.fusengdes.2016.02.089 Recent progress of China HCCB TBM tritium system
M. Utili, Characterisation of Tritium Extraction Unit from liquid Pb-16Li alloy of WCLL-TBM in TRIEX-II facility, ISFNT-14 proceeding, this conference.
Trans. Am. Nucl. Soc. Gabriele 114 1 June 281 2016 Experimental activities with the IELLLO lithium-lead facility
Dofek 2016 Description of the MELILOO - Stand Test Facility and Test Matrix
Fus. Sci. Technol. Shrivastav 65 319 2014 10.13182/FST13-658 Preparation and characterization of the Lithium metatitanate ceramics by solution-combustion method for indian LLCB TBM
Fus. Eng. Des. Yadav 124 710 2017 10.1016/j.fusengdes.2017.05.097 Helium cooling systems for Indian LLCB TBM testing in ITER
Flow Meas. Instrum. Sahu 66 190 2019 10.1016/j.flowmeasinst.2019.03.008 Development of an optimized magnetic field source for flow meter applications
Fus. Eng. and Des. Kumar 138 1 2019 10.1016/j.fusengdes.2018.09.016 Engineering design and development of lead lithium loop for thermo-fluid MHD studies
J. Sep. Sci. Gayathri Devi 41 1798 2018 10.1002/jssc.201700911 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
Int. J. Hydrogen Energy Chippar 43 8007 2018 10.1016/j.ijhydene.2018.03.017 Numerical investigation of hydrogen absorption in a stackable metal hydride reactor utilizing compartmentalization
Fus. Eng. Des. Park 2019 10.1016/j.fusengdes.2019.03.052 Hydrogen adsorption performance for large-scale cryogenic molecular sieve bed
Fus. Eng. Des. Gwon 2019 10.1016/j.fusengdes.2019.03.057 Tritium Breeding capability of water cooled breeder blanket with different container designs
Fus. Eng. and Des Kim 109-111 Part A 996 2016 10.1016/j.fusengdes.2016.01.036 Design and manufacturing feasibility of ITER TBM frame and dummy TBMs
Bigot 2016 Paper OV/1-2, Proc. 26th IAEA Fusion Energy Conf
L. Forest, L.V. Boccaccini, M. Zmitko, et al., Test Blanket Modules (ITER) and Breeding Blanket (DEMO): history of major fabrication technologies development of HCLL and HCPB and status, ISFNT-14 proceeding, this conference.
Fus. Eng. and Des. Zmitko 109-111 1687 2016 10.1016/j.fusengdes.2015.10.029 The European ITER test blanket modules: progress in development of fabrication technologies towards standardization
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