메뉴 건너뛰기




Volumn 37, Issue 2, 1997, Pages 261-286

Beryllium application in ITER plasma facing components

Author keywords

Armour lifetime; Fabrication; ITER; Sputtering erosion; Vaporisation

Indexed keywords

ARMOR; EROSION; SERVICE LIFE; SPUTTERING; TOKAMAK DEVICES; VAPORIZATION;

EID: 0031221257     PISSN: 09203796     EISSN: None     Source Type: Journal    
DOI: 10.1016/S0920-3796(97)00052-5     Document Type: Article
Times cited : (23)

References (46)
  • 2
    • 0346873235 scopus 로고
    • Physics basis and design of the ITER divertor and of pumping-fuelling system
    • IAEA-CN-60/E-P6
    • G. Janeschitz, A. Antipenkov, S. Chiocchio, et al., Physics basis and design of the ITER divertor and of pumping-fuelling system, Plasma Phys. Control Fus., IAEA-CN-60/E-P6 (1995) 549-560.
    • (1995) Plasma Phys. Control Fus. , pp. 549-560
    • Janeschitz, G.1    Antipenkov, A.2    Chiocchio, S.3
  • 7
    • 0347505114 scopus 로고
    • Structure, properties and performance of plasma sprayed beryllium for fusion application
    • Jackson Hole, Sep. CONF-9509218
    • R.G. Castro, P.W. Stanek, K.E. Elliot et al., Structure, properties and performance of plasma sprayed beryllium for fusion application, Proc. of 2nd IEA Beryllium Workshop, Jackson Hole, (Sep. 1995), CONF-9509218, pp. 164-184.
    • (1995) Proc. of 2nd IEA Beryllium Workshop , pp. 164-184
    • Castro, R.G.1    Stanek, P.W.2    Elliot, K.E.3
  • 8
    • 85033119658 scopus 로고    scopus 로고
    • High heat flux exposure tests on beryllium monoblocks brazed to a copper swirltube
    • in press
    • H.D. Falter, D. Ciric, D.J. Godden, C. Ibbot, High heat flux exposure tests on beryllium monoblocks brazed to a copper swirltube, JET Report (in press).
    • JET Report
    • Falter, H.D.1    Ciric, D.2    Godden, D.J.3    Ibbot, C.4
  • 9
    • 0343562283 scopus 로고
    • Low cycle thermal fatigue testing of Be grades for ITER plasma facing components
    • Jackson Hole, Sept. CONF-9509218
    • R.D. Watson, D.L. Youchison, D.E. Dombrowski, R.N. Giniatouline, Low cycle thermal fatigue testing of Be grades for ITER plasma facing components, Proc. 2nd IEA Beryllium Workshop, Jackson Hole, (Sept. 1995), CONF-9509218, pp. 7-38.
    • (1995) Proc. 2nd IEA Beryllium Workshop , pp. 7-38
    • Watson, R.D.1    Youchison, D.L.2    Dombrowski, D.E.3    Giniatouline, R.N.4
  • 12
    • 0030264604 scopus 로고    scopus 로고
    • Neutron irradiated beryllium: Tensile strength, swelling and helium content
    • F. Moons, L. Sannen, J.-L. Puzzolante, A. Rahn, J. van de Velde, Neutron irradiated beryllium: tensile strength, swelling and helium content, J. Nucl. Mater. 233-237 (1996) 823-827.
    • (1996) J. Nucl. Mater. , vol.233-237 , pp. 823-827
    • Moons, F.1    Sannen, L.2    Puzzolante, J.-L.3    Rahn, A.4    Van De Velde, J.5
  • 14
    • 85033102529 scopus 로고    scopus 로고
    • High heat flux exposure tests on 10-mm Be tiles brazed to an actively cooled vapotron made from CuCrZr
    • in press
    • H.D. Falter, D. Ciric, D.J. Godden, C. Ibbot, High heat flux exposure tests on 10-mm Be tiles brazed to an actively cooled vapotron made from CuCrZr, JET Report (in press).
    • JET Report
    • Falter, H.D.1    Ciric, D.2    Godden, D.J.3    Ibbot, C.4
  • 15
    • 85033101185 scopus 로고    scopus 로고
    • Net Internal Note N/I/3340/1/A, Garching
    • H.D. Pacher, I. Smid, Net Internal Note N/I/3340/1/A, Garching, 1996.
    • (1996)
    • Pacher, H.D.1    Smid, I.2
  • 16
    • 0031120989 scopus 로고    scopus 로고
    • RACLETTE: A model for evaluating the thermal response of plasma facing components to slow high power plasma transients - Part I: Theory and description of model capabilities
    • A.R. Raffray, G. Federici, RACLETTE: a model for evaluating the thermal response of plasma facing components to slow high power plasma transients - Part I: Theory and description of model capabilities, J. Nucl. Mater. 244 (1997) 85-100.
    • (1997) J. Nucl. Mater. , vol.244 , pp. 85-100
    • Raffray, A.R.1    Federici, G.2
  • 17
    • 0031124453 scopus 로고    scopus 로고
    • RACLETTE: A model for evaluating the thermal response of plasma facing components to slow high power plasma transients - Part II: Analysis of ITER plasma facing components
    • G. Federici, A.R. Raffray, RACLETTE: A model for evaluating the thermal response of plasma facing components to slow high power plasma transients - Part II: Analysis of ITER plasma facing components, J. Nucl. Mater. 244 (1997) 101-130.
    • (1997) J. Nucl. Mater. , vol.244 , pp. 101-130
    • Federici, G.1    Raffray, A.R.2
  • 19
  • 25
  • 26
    • 0030260070 scopus 로고    scopus 로고
    • Lifetime of Be-, CFC- and W-armoured ITER divertor plates
    • I. Smid, H.D. Pacher, G. Vieider, et al., Lifetime of Be-, CFC- and W-armoured ITER divertor plates, J. Nucl. Mater. 233-237 (1996) 701-707.
    • (1996) J. Nucl. Mater. , vol.233-237 , pp. 701-707
    • Smid, I.1    Pacher, H.D.2    Vieider, G.3
  • 27
    • 0030259381 scopus 로고    scopus 로고
    • Design requirements for plasma facing materials in ITER
    • R. Matera, G. Federici, et al., Design requirements for plasma facing materials in ITER, J. Nucl. Mater. 233-237 (1996) 17-25.
    • (1996) J. Nucl. Mater. , vol.233-237 , pp. 17-25
    • Matera, R.1    Federici, G.2
  • 32
    • 0020206806 scopus 로고
    • Dynamics of melting, evaporation and resolidification of materials exposed to plasma disruptions
    • A.M. Hassanein, G.L. Kulcinski, W.G. Wolfer, Dynamics of melting, evaporation and resolidification of materials exposed to plasma disruptions, J. Nucl. Mater. 111-112 (1982) 554-559.
    • (1982) J. Nucl. Mater. , vol.111-112 , pp. 554-559
    • Hassanein, A.M.1    Kulcinski, G.L.2    Wolfer, W.G.3
  • 34
    • 0031546516 scopus 로고    scopus 로고
    • The influence of key operation parameters and material properties on the quantification of tritium inventory and permeation in the plasma facing components of ITER
    • G. Federici, D. Holland, G. Janeschitz, C.H. Wu, The influence of key operation parameters and material properties on the quantification of tritium inventory and permeation in the plasma facing components of ITER, J. Nucl. Mater. 241-243 (1997) 260-267.
    • (1997) J. Nucl. Mater. , vol.241-243 , pp. 260-267
    • Federici, G.1    Holland, D.2    Janeschitz, G.3    Wu, C.H.4
  • 35
    • 0026974573 scopus 로고
    • Interpretation of deuterium pumping by plasma-facing beryllium surfaces
    • P.L. Andrew, A.T. Peacock, M.A. Pick, Interpretation of deuterium pumping by plasma-facing beryllium surfaces, J. Nucl. Mater. 196-198 (1992) 997-1001.
    • (1992) J. Nucl. Mater. , vol.196-198 , pp. 997-1001
    • Andrew, P.L.1    Peacock, A.T.2    Pick, M.A.3
  • 36
    • 0025531386 scopus 로고
    • Hydrogen recycling coefficient in beryllium: Experimental determination and a test simulation of the density evolution in a JET plasma discharge
    • G. Saibene, R. Sartori, A. Tanga, A. Peacock, M. Pick, P. Gaze, Hydrogen recycling coefficient in beryllium: experimental determination and a test simulation of the density evolution in a JET plasma discharge, J. Nucl. Mater. 176-177 (1990) 618-623.
    • (1990) J. Nucl. Mater. , vol.176-177 , pp. 618-623
    • Saibene, G.1    Sartori, R.2    Tanga, A.3    Peacock, A.4    Pick, M.5    Gaze, P.6
  • 37
    • 0031546673 scopus 로고    scopus 로고
    • Measurements of tritium retention in beryllium using the Tritium Plasma Experiment
    • R.A. Causey, W. Harbin, R.A. Anderl, Measurements of tritium retention in beryllium using the Tritium Plasma Experiment, J. Nucl. Mater. 241-243 (1997) 1041-1046.
    • (1997) J. Nucl. Mater. , vol.241-243 , pp. 1041-1046
    • Causey, R.A.1    Harbin, W.2    Anderl, R.A.3
  • 38
    • 0030084780 scopus 로고    scopus 로고
    • Gas swelling and deuterium distribution in Be implanted with deuterium ions
    • V.N. Chernikov, V.Kh. Alimov, A.P. Zakharov, Gas swelling and deuterium distribution in Be implanted with deuterium ions, J. Nucl. Mater. 228-1 (1996) 47-60.
    • (1996) J. Nucl. Mater. , vol.228 , Issue.1 , pp. 47-60
    • Chernikov, V.N.1    Alimov, V.Kh.2    Zakharov, A.P.3
  • 39
    • 0346873231 scopus 로고    scopus 로고
    • Tritium inventory in the ITER PFC's: Predictions, uncertainties, R&D status and priority needs, presented at ISFNT-4, Tokyo
    • in press
    • G. Federici, R.A. Anderl, J.N. Brooks, et al., Tritium inventory in the ITER PFC's: predictions, uncertainties, R&D status and priority needs, presented at ISFNT-4, Tokyo (1997), Fus. Eng. Design (in press).
    • (1997) Fus. Eng. Design
    • Federici, G.1    Anderl, R.A.2    Brooks, J.N.3
  • 41
    • 8544279990 scopus 로고    scopus 로고
    • Assessment of erosion and surface inventory issues for the ITER divertor
    • J.N. Brooks, R. Causey, G. Federici, D.N. Ruzic, Assessment of erosion and surface inventory issues for the ITER divertor, J. Nucl. Mater. 241-243 (1997) 294-298.
    • (1997) J. Nucl. Mater. , vol.241-243 , pp. 294-298
    • Brooks, J.N.1    Causey, R.2    Federici, G.3    Ruzic, D.N.4


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.