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Volumn 54, Issue 1, 2008, Pages 39-44

Tritium in fusion: R&D in the EU

Author keywords

[No Author keywords available]

Indexed keywords

BREEDING BLANKETS; FUSION REACTIONS; FUSION REACTORS;

EID: 49749102397     PISSN: 15361055     EISSN: None     Source Type: Journal    
DOI: 10.13182/FST08-A1761     Document Type: Conference Paper
Times cited : (8)

References (37)
  • 2
    • 33846022357 scopus 로고    scopus 로고
    • The European power plant conceptual study: Helium-cooled lithium-lead reactor concept
    • P. SARDAIN et al, "The European power plant conceptual study: Helium-cooled lithium-lead reactor concept", Fus. Eng. Des. 81 (2006) 2673-2678.
    • (2006) Fus. Eng. Des , vol.81 , pp. 2673-2678
    • SARDAIN, P.1
  • 3
    • 0036564838 scopus 로고    scopus 로고
    • Hydrogen isotopes permeability in Eurofer 97 martensitic steel
    • A. AIELLO et al, "Hydrogen isotopes permeability in Eurofer 97 martensitic steel", Fus. Sci. Tech. 41 (2002) 872-876.
    • (2002) Fus. Sci. Tech , vol.41 , pp. 872-876
    • AIELLO, A.1
  • 4
    • 0031168737 scopus 로고    scopus 로고
    • Influence of traps on the deuterium behavior in the low activation martensitic steels F82H and Batman
    • E. SERRA et al, "Influence of traps on the deuterium behavior in the low activation martensitic steels F82H and Batman", J. Nucl. Mater. 245 (1997) 108-114.
    • (1997) J. Nucl. Mater , vol.245 , pp. 108-114
    • SERRA, E.1
  • 5
    • 34748924224 scopus 로고    scopus 로고
    • Hydrogen transport and trapping in EUROFER'97
    • Santa Barbara, California
    • G.A. ESTEBAN et al, Hydrogen transport and trapping in EUROFER'97, Proc. ICFRM-12, Santa Barbara, California, 2005.
    • (2005) Proc. ICFRM-12
    • ESTEBAN, G.A.1
  • 6
    • 49749109205 scopus 로고    scopus 로고
    • In-pile Tritium release behaviour of Lithium Metatitanate produced by Extrusion-spheroidisation-sintering process in EXOTIC-9/1 in the High Flux Reactor Petten
    • M.M.W. PEETERS et al: In-pile Tritium release behaviour of Lithium Metatitanate produced by Extrusion-spheroidisation-sintering process in EXOTIC-9/1 in the High Flux Reactor Petten, Proc SOFT Warsaw 2006.
    • Proc SOFT Warsaw 2006
    • PEETERS, M.M.W.1
  • 7
    • 27744514615 scopus 로고    scopus 로고
    • Behaviour of tritium in breeding materials
    • G. KIZANE et al, "Behaviour of tritium in breeding materials" Fus. Eng. Des. 15-19 (2005) 896-901.
    • (2005) Fus. Eng. Des , vol.15-19 , pp. 896-901
    • KIZANE, G.1
  • 8
    • 0000854608 scopus 로고
    • Solubility and diffusivity of hydrogen isotopes in liquid Pb-17Li
    • F. REITER, "Solubility and diffusivity of hydrogen isotopes in liquid Pb-17Li", Fus. Eng. Des. 14 (1991) 207-211.
    • (1991) Fus. Eng. Des , vol.14 , pp. 207-211
    • REITER, F.1
  • 9
    • 31744449229 scopus 로고    scopus 로고
    • Determination of hydrogen solubility in lead lithium using sole device
    • A. AIELLO et al, "Determination of hydrogen solubility in lead lithium using sole device", Fus. Eng. Des. 81 (2006) 639-644.
    • (2006) Fus. Eng. Des , vol.81 , pp. 639-644
    • AIELLO, A.1
  • 10
    • 49749143839 scopus 로고    scopus 로고
    • 2D element modelling of tritium permeation for the HCLL DEMO blanket module
    • Warsaw
    • F. GABRIEL et al, "2D element modelling of tritium permeation for the HCLL DEMO blanket module", Proc SOFT, Warsaw 2006.
    • (2006) Proc SOFT
    • GABRIEL, F.1
  • 11
    • 3342890497 scopus 로고    scopus 로고
    • Corrosion behavior of EUROFER steel in flowing eutectic Pb-17Li alloy
    • J. KONYS et al, Corrosion behavior of EUROFER steel in flowing eutectic Pb-17Li alloy", J. Nucl. Mater. 329-333 (2004) 1379-1383.
    • (2004) J. Nucl. Mater , vol.329-333 , pp. 1379-1383
    • KONYS, J.1
  • 12
    • 34447559815 scopus 로고    scopus 로고
    • Production and characterization of titanium beryllides for HIDOBE irradiation
    • A. MÖSLANG et al, "Production and characterization of titanium beryllides for HIDOBE irradiation", J. Nucl. Mater. 367-370 (2007) 1069-1072.
    • (2007) J. Nucl. Mater , vol.367-370 , pp. 1069-1072
    • MÖSLANG, A.1
  • 13
    • 49749152856 scopus 로고    scopus 로고
    • Fus. Sci. Tech. 41 (2002) 303-1174;
    • (2002) Fus. Sci. Tech , vol.41 , pp. 303-1174
  • 14
    • 49749122235 scopus 로고    scopus 로고
    • 1-806
    • (2005) 1-806.
  • 16
    • 49749089422 scopus 로고    scopus 로고
    • The Test Blanket Modules project in Europe: From the strategy to the technical plan over next ten years
    • Warsaw
    • Y. POITEVIN et al, "The Test Blanket Modules project in Europe: From the strategy to the technical plan over next ten years", Proc SOFT, Warsaw 2006.
    • (2006) Proc SOFT
    • POITEVIN, Y.1
  • 17
    • 49749123552 scopus 로고    scopus 로고
    • Overview of the last progresses for the European test blanket modules projects
    • Warsaw
    • J-F. SALAVY et al, "Overview of the last progresses for the European test blanket modules projects", Proc. SOFT, Warsaw 2006.
    • (2006) Proc. SOFT
    • SALAVY, J.-F.1
  • 18
    • 49749084450 scopus 로고    scopus 로고
    • M. DALLE DONNE et al, European HCPB Test Blanket. ITER Design Description Document, Dec. 1996, FZKA 5891, April 1997, FZK Karlsruhe.
    • M. DALLE DONNE et al, "European HCPB Test Blanket. ITER Design Description Document", Dec. 1996, FZKA 5891, April 1997, FZK Karlsruhe.
  • 19
    • 0842283378 scopus 로고    scopus 로고
    • Extraction of hydrogen from water vapour by hydrogen pump using ceramic protonic conductor
    • Y. KAWAMURA et al, "Extraction of hydrogen from water vapour by hydrogen pump using ceramic protonic conductor", Fus. Sci. Tech. 45 (2004) 33-40.
    • (2004) Fus. Sci. Tech , vol.45 , pp. 33-40
    • KAWAMURA, Y.1
  • 20
    • 0035517557 scopus 로고    scopus 로고
    • Cold trapping of traces of tritiated water from the helium loops of a fusion breeder blanket
    • N. BEKRIS et al, "Cold trapping of traces of tritiated water from the helium loops of a fusion breeder blanket", Fus. Eng. Des. 58-59 (2001) 423-428.
    • (2001) Fus. Eng. Des , vol.58-59 , pp. 423-428
    • BEKRIS, N.1
  • 21
    • 23044433331 scopus 로고    scopus 로고
    • Semi-technical cryogenic molecular sieve bed for the tritium extraction system of the TBM for ITER
    • S. BELOGLAZOV et al, Semi-technical cryogenic molecular sieve bed for the tritium extraction system of the TBM for ITER, Fus. Sci. Tech. 48 (2005) 662-665.
    • (2005) Fus. Sci. Tech , vol.48 , pp. 662-665
    • BELOGLAZOV, S.1
  • 22
    • 49749105695 scopus 로고    scopus 로고
    • TRIEX facility: An experimental loop to test tritium extraction systems from lead lithium
    • Warsaw
    • A. AIELLO et al, "TRIEX facility: an experimental loop to test tritium extraction systems from lead lithium" Proc SOFT, Warsaw 2006.
    • (2006) Proc SOFT
    • AIELLO, A.1
  • 23
    • 49749129342 scopus 로고    scopus 로고
    • th SOFT, Lisbon, Portugal, Fus. Tech. 1996, 1335-1338.
    • th SOFT, Lisbon, Portugal, Fus. Tech. 1996, 1335-1338.
  • 24
    • 32444433083 scopus 로고    scopus 로고
    • Helium Loop Karlsruhe (HELOKA): A valuable tool for testing and qualifying ITER components and their He cooling circuits
    • B.E. GHIDERSA et al, "Helium Loop Karlsruhe (HELOKA): A valuable tool for testing and qualifying ITER components and their He cooling circuits", Fus. Eng. Des. 81, 8-14 (2006) 1471-1476.
    • (2006) Fus. Eng. Des , vol.81 , Issue.8-14 , pp. 1471-1476
    • GHIDERSA, B.E.1
  • 25
    • 49749101756 scopus 로고    scopus 로고
    • th SOFT, Lisbon, Portugal, Fus. Tech. 1996, 1193.
    • th SOFT, Lisbon, Portugal, Fus. Tech. 1996, 1193.
  • 26
    • 0030074138 scopus 로고    scopus 로고
    • Ultrahigh Tritium Decontamination of Simulated Fusion Fuel Exhaust using a 2-Stage Palladium Membrane Reactor
    • S.A. BIRDSELL et al, "Ultrahigh Tritium Decontamination of Simulated Fusion Fuel Exhaust using a 2-Stage Palladium Membrane Reactor", Fus. Tech. 30 (1996) 905.
    • (1996) Fus. Tech , vol.30 , pp. 905
    • BIRDSELL, S.A.1
  • 27
    • 31744441457 scopus 로고    scopus 로고
    • Study on tritium accountancy in fusion DEMO plant at JAERI
    • M. NISHI et al, "Study on tritium accountancy in fusion DEMO plant at JAERI", Fus. Eng. Des. 81 (2006) 745-751.
    • (2006) Fus. Eng. Des , vol.81 , pp. 745-751
    • NISHI, M.1
  • 28
    • 33846068471 scopus 로고    scopus 로고
    • Further insight into the mechanism of hydrocarbon layer formation below the divertor of ASDEX Upgrade
    • M. MAYER et al, "Further insight into the mechanism of hydrocarbon layer formation below the divertor of ASDEX Upgrade, Nucl. Fusion 46 (2006) 914-920.
    • (2006) Nucl. Fusion , vol.46 , pp. 914-920
    • MAYER, M.1
  • 29
    • 34248575562 scopus 로고    scopus 로고
    • Post mortem analysis of a JET quartz microbalance system
    • »
    • H.G. ESSER et al, "Post mortem analysis of a JET quartz microbalance system », J. Nucl. Mat. 363-365 (2007) 146-151.
    • (2007) J. Nucl. Mat , vol.363-365 , pp. 146-151
    • ESSER, H.G.1
  • 30
    • 0037343295 scopus 로고    scopus 로고
    • C.H.SKTNNER et al, Tritium removal from JET and THTR tiles by a scanning laser, J.NucLMater. 313-316 (2003) 499-503.
    • C.H.SKTNNER et al, "Tritium removal from JET and THTR tiles by a scanning laser", J.NucLMater. 313-316 (2003) 499-503.
  • 31
    • 13844317133 scopus 로고    scopus 로고
    • B.SCHWEER et al, Laser desorption of deuterium retained in re-deposited carbon layers at TEXTOR and JET, J.NucLMater. 337-339 (2005) 570-574.
    • B.SCHWEER et al, "Laser desorption of deuterium retained in re-deposited carbon layers at TEXTOR and JET, J.NucLMater. 337-339 (2005) 570-574.
  • 32
    • 13844316002 scopus 로고    scopus 로고
    • K.K.J. GIBSON et al, The removal of co-deposited hydrocarbon films from plasma facing components using high-power pulsed flaslamp irradiation, J.NucLMater. 337-339 (2005) 565-569.
    • K.K.J. GIBSON et al, "The removal of co-deposited hydrocarbon films from plasma facing components using high-power pulsed flaslamp irradiation", J.NucLMater. 337-339 (2005) 565-569.
  • 33
    • 34249029920 scopus 로고    scopus 로고
    • In-situ tokamak laser applications for detritiation and co-deposited layers studies
    • C. GRISOLLA et al, "In-situ tokamak laser applications for detritiation and co-deposited layers studies", J. Nucl. Mater. 363-365 (2007) 1138-1147.
    • (2007) J. Nucl. Mater , vol.363-365 , pp. 1138-1147
    • GRISOLLA, C.1
  • 34
    • 49749110130 scopus 로고    scopus 로고
    • IFMIF Comprehensive Design Report (CDR), printed January 2004.
    • IFMIF Comprehensive Design Report (CDR), printed January 2004.
  • 35
    • 3342959234 scopus 로고    scopus 로고
    • 7Be generation in the IFMIF lithium loop
    • 7Be generation in the IFMIF lithium loop", J. Nucl. Mater. 329-333 (2004) 213-217.
    • (2004) J. Nucl. Mater , vol.329-333 , pp. 213-217
    • SIMAKOV, S.P.1
  • 36
    • 0036564956 scopus 로고    scopus 로고
    • Detritiation processes needed for JET operations and their wider applicability
    • A. C. BELL et al, "Detritiation processes needed for JET operations and their wider applicability". Fus. Sci. Tech. 41 (2002) 626-631.
    • (2002) Fus. Sci. Tech , vol.41 , pp. 626-631
    • BELL, A.C.1
  • 37
    • 23144464212 scopus 로고    scopus 로고
    • Tritium related studies within the JET fusion technology work programme
    • S. ROSANVALLON et al, "Tritium related studies within the JET fusion technology work programme", Fus. Sci. Tech. 48 (2005) 268-273.
    • (2005) Fus. Sci. Tech , vol.48 , pp. 268-273
    • ROSANVALLON, S.1


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