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1
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0039130384
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ITER in-vessel system design and performance
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to be publ. Yokahama, Japan, October 19-25
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Parker, R., "ITER In-Vessel System Design and Performance", to be publ. in Proc. of 17th IAEA Fusion Energy Conference, Yokahama, Japan, October 19-25, 1998.
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(1998)
Proc. of 17th IAEA Fusion Energy Conference
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Parker, R.1
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2
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-
0039130385
-
Conclusion about use tungsten in the divertor of ASDEX upgrade
-
to be publ. San Diego, US, May 18-22
-
Krieger, K., Maier, H. and Neu, R., "Conclusion About Use Tungsten in the Divertor of ASDEX Upgrade", to be publ. in Proc. of 13th Plasma Surface Interaction Conference, San Diego, US, May 18-22, 1998.
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(1998)
Proc. of 13th Plasma Surface Interaction Conference
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-
Krieger, K.1
Maier, H.2
Neu, R.3
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3
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-
0040314572
-
ITER divertor issues and R&D
-
to be publ. Marseille, France, Sept 7-11
-
Tivey, R. et al., "ITER Divertor Issues and R&D", to be publ. in Proc. of 20th Symp. on Fusion Technology, Marseille, France, Sept 7-11, 1998.
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(1998)
Proc. of 20th Symp. on Fusion Technology
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-
Tivey, R.1
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4
-
-
0010237045
-
Joining technologies for the plasma facing components of ITER
-
to be publ. Marseille, France, Sept 7-11
-
Barabash, V. et al., "Joining Technologies for the Plasma Facing Components of ITER" to be publ. in Proc. of 20th Symp. on Fusion Technology, Marseille, France, Sept 7-11, 1998.
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(1998)
Proc. of 20th Symp. on Fusion Technology
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Barabash, V.1
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5
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0031272057
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Roth, J., Eckstein, W. and Guseva, M., Fusion Eng. Design, 37, 465 (1997).
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Fusion Eng. Design
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Roth, J.1
Eckstein, W.2
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0031273306
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Brooks, J. N., Ruzic, D. N. and Hayden, D. V., Fusion Eng. Design, 37, 455 (1997).
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Fusion Eng. Design
, vol.37
, pp. 455
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Brooks, J.N.1
Ruzic, D.N.2
Hayden, D.V.3
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7
-
-
0040908711
-
Erosion/redeposition analysis: Status of modeling and code validation for semi-detached edge plasmas
-
to be publ. San Diego, 18-22 May
-
Brooks, J. N. et al., "Erosion/redeposition Analysis: Status of Modeling and Code Validation for Semi-detached Edge Plasmas", to be publ. in Proc. of 13th Plasma Suraface Interaction Conference, San Diego, 18-22 May, 1998.
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Proc. of 13th Plasma Suraface Interaction Conference
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Brooks, J.N.1
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8
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0040908712
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private communication
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Hassainen, A., private communication.
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Hassainen, A.1
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13
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0039130379
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Response of beryllium to severe thermal shocks - Simulation of disruptions and vertical displacement events in further thermonuclear devices
-
Mito, Japan, Oct. 22-24
-
Linke, J. et al., "Response of Beryllium to Severe Thermal Shocks - Simulation of Disruptions and Vertical Displacement Events in Further Thermonuclear Devices", Proc. 3d IEA Int. Workshop on Berylium Technology for Fusion, Mito, Japan, Oct. 22-24, 1997, p.189.
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(1997)
Proc. 3d IEA Int. Workshop on Berylium Technology for Fusion
, pp. 189
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-
Linke, J.1
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14
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-
0040314568
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Effect of runaway electrons and VDE's on ITER first wall
-
to be publ. Marseille, France, Sept 7-11
-
Raffray, A. R. et al., "Effect of Runaway Electrons and VDE's on ITER First Wall", to be publ. in Proc. of 20th Symp. on Fusion Technology, Marseille, France, Sept 7-11, 1998.
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(1998)
Proc. of 20th Symp. on Fusion Technology
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-
Raffray, A.R.1
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16
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-
0032108071
-
Evidence for hydrogen flux dependence of the apparent chemical erosion yield of graphite under high flux conditions
-
accepted for publication
-
Kallenbach, A. et al., "Evidence for Hydrogen Flux Dependence of the Apparent Chemical Erosion Yield of Graphite Under High Flux Conditions", Nucl. Fusion, accepted for publication.
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Nucl. Fusion
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Kallenbach, A.1
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17
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-
0040314567
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Chemical sputtering yeild of carbon based materials at high ion flux densities
-
to be publ. San Diego, 18-22 May
-
Grote, H. et al., "Chemical Sputtering Yeild of Carbon Based Materials at High Ion Flux Densities", to be publ. in Proc. of 13th Plasma Surface Interaction Conference, San Diego, 18-22 May, 1998.
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(1998)
Proc. of 13th Plasma Surface Interaction Conference
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-
Grote, H.1
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18
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-
0039130381
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Carbon fiber composites application in ITER plasma facing components
-
to be publ. Sendai, Japan, Oct.
-
Barabash, V. et al., "Carbon Fiber Composites Application in ITER Plasma Facing Components", to be publ. in proc. of ICFRM-8, Sendai, Japan, Oct. 1997.
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(1997)
Proc. of ICFRM-8
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-
Barabash, V.1
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19
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-
0039722728
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In-vessel tritium retention and removal in ITER
-
to be publ. San Diego, 18-22 May
-
Federici, G. et al., "In-vessel Tritium Retention and Removal in ITER", to be publ. in Proc. of 13th Plasma Suraface Interaction Conference, San Diego, 18-22 May, 1998.
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(1998)
Proc. of 13th Plasma Suraface Interaction Conference
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-
Federici, G.1
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20
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0032631018
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Hydrogen isotope retention in beryllium for tokamak plasma facing applications
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to be publ.
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Anderl, R. A. et al., "Hydrogen Isotope Retention in Beryllium for Tokamak Plasma Facing Applications", to be publ. in J. Nucl. Mater.
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J. Nucl. Mater.
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Anderl, R.A.1
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21
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0040908709
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Growth of redeposited carbon and its impact on isotope retention properties on tungsten in a high-flux deuterium plasma
-
to be publ. San Diego, 18-22 May
-
Sze, F. C. et al., "Growth of Redeposited Carbon and its Impact on Isotope Retention Properties on Tungsten in a High-Flux Deuterium Plasma", to be publ. in Proc. of 13th Plasma Suraface Interaction Conference, San Diego, 18-22 May, 1998.
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(1998)
Proc. of 13th Plasma Suraface Interaction Conference
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Sze, F.C.1
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22
-
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0040314562
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Tritium retention in tungsten exposed to intense fluxes of 100eV tritions
-
to be publ. San Diego, 18-22 May
-
Causey, R. A., Wilson, K. L., Wampler, W. R. and Venhaus, T., "Tritium Retention in Tungsten Exposed to Intense Fluxes of 100eV Tritions", to be publ. in Proc. of 13th Plasma Suraface Interaction Conference, San Diego, 18-22 May, 1998.
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(1998)
Proc. of 13th Plasma Suraface Interaction Conference
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-
Causey, R.A.1
Wilson, K.L.2
Wampler, W.R.3
Venhaus, T.4
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27
-
-
0003054169
-
ITER tokamak dust-limits, production, removal, surveying
-
San Diego, October 6-10
-
Piet, S.J. et al. "ITER Tokamak Dust-Limits, Production, Removal, Surveying", Proceedings of the 17th IEEE/NPSS Symposium on Fusion Engineering, San Diego, October 6-10, 1997.
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(1997)
Proceedings of the 17th IEEE/NPSS Symposium on Fusion Engineering
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Piet, S.J.1
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28
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0343562283
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Low cyclic fatigue of beryllium
-
Wyoming, USA, Sep. 6-8
-
Watson, R. et al., "Low Cyclic Fatigue of Beryllium", Proc. 2-nd IEA Int. Workshop on Berylium Technology for Fusion, Wyoming, USA, Sep. 6-8, 1995, p.7.
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(1995)
Proc. 2-nd IEA Int. Workshop on Berylium Technology for Fusion
, pp. 7
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Watson, R.1
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29
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0004575509
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Thermal shock tests with beryllium coupons in electron beam facility JUDITH
-
Wyoming, USA, Sep. 6-8
-
Roedig, M. R. et al., "Thermal Shock Tests with Beryllium Coupons in Electron Beam Facility JUDITH", Proc. 2-nd IEA Int. Workshop on Berylium Technology for Fusion, Wyoming, USA, Sep. 6-8, 1995, p.3.
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Proc. 2-nd IEA Int. Workshop on Berylium Technology for Fusion
, pp. 3
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Roedig, M.R.1
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31
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0040314557
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Characterisation of plasma sprayed beryllium ITER first wall mock-ups
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Mito, Japan, Oct. 22-24
-
Castro, R. G., Vaidya, R. U. and Mollis, K. J., "Characterisation of Plasma Sprayed Beryllium ITER First Wall Mock-ups". Proc. 3d IEA Int. Workshop on Berylium Technology for Fusion, Mito, Japan, Oct. 22-24, 1997, p. 137.
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Proc. 3d IEA Int. Workshop on Berylium Technology for Fusion
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Castro, R.G.1
Vaidya, R.U.2
Mollis, K.J.3
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32
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0039722679
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private communication, February
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Watson, R., private communication, February 1997.
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Watson, R.1
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33
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private communication, July
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Makhankov, A., private communication, July 1997.
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(1997)
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Makhankov, A.1
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34
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Material damage to beryllium. Carbon and tungsten under severe thermal shocks
-
to be publ. Sendai, Japan, 26-31 October
-
Roedig, M. et al., "Material damage to Beryllium. Carbon and Tungsten Under Severe Thermal Shocks", to be publ. in proc. of ICFRM-8, Sendai, Japan, 26-31 October, 1997.
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(1997)
Proc. of ICFRM-8
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Roedig, M.1
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35
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0040908652
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Assessment of tungsten for use in the ITER plasma facing components
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to be publ. Sendai, Japan, 26-31 October
-
Davis, J., Barabash, V. and Ploechl, L., "Assessment of Tungsten for Use in the ITER Plasma Facing Components", to be publ. in Proc. of ICFRM-8, Sendai, Japan, 26-31 October, 1997.
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(1997)
Proc. of ICFRM-8
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Davis, J.1
Barabash, V.2
Ploechl, L.3
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36
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0000632279
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Development and optimisation of tungsten armour geometry for ITER divertor
-
to be publ. Marseille, France, Sept 7-11
-
Makhankov, A. et al., "Development and Optimisation of Tungsten Armour Geometry for ITER Divertor", to be publ. in Proc. of 20th Symp. on Fusion Technology, Marseille, France, Sept 7-11, 1998.
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(1998)
Proc. of 20th Symp. on Fusion Technology
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Makhankov, A.1
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38
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0040314559
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Overview of the Japanese mock-up tests for ITER high heat flux components
-
to be publ. April 6-11, Tokyo, Japan
-
Akiba, M. et al., "Overview of the Japanese Mock-up Tests for ITER High Heat Flux Components", to be publ. in Proc. of Fourth Int. Symp. on Fusion Nuclear Technology, April 6-11, 1997, Tokyo, Japan.
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(1997)
Proc. of Fourth Int. Symp. on Fusion Nuclear Technology
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Akiba, M.1
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39
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0039130321
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Development of W plasma spray coatings for ITER divertor components
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to be publ. San Diego, 6-9 October
-
Riccardi, B. et al., "Development of W Plasma Spray Coatings for ITER Divertor Components", to be publ. in Proc. of 17th Symp. on Fusion Engineering, San Diego, 6-9 October, 1997.
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(1997)
Proc. of 17th Symp. on Fusion Engineering
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Riccardi, B.1
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40
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0343807749
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Overview of EU CFCs development for plasma facing materials
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to be publ. Sendai, Japan, Oct.
-
Wu, C.H. et al., "Overview of EU CFCs Development for Plasma Facing Materials", to be publ. in Proc. of ICFRM-8, Sendai, Japan, Oct. 1997.
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(1997)
Proc. of ICFRM-8
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Wu, C.H.1
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41
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0000836888
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Development of 3D-based CFC with high thermal conductivity for fusion application
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Lisbon, Portugal, Sept. 16-20
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Araki, M. et al., "Development of 3D-based CFC with High Thermal Conductivity for Fusion Application", in Proc. of 19th Symp. on Fusion Technology, Lisbon, Portugal, Sept. 16-20, 1996, p.359.
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(1996)
Proc. of 19th Symp. on Fusion Technology
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Araki, M.1
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43
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Evaluation of an advanced silicon doped CFC for plasma facing materials
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Lisbon, Portugal, September 16-20
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Proc. of the 19th Symp. on Fusion Technology
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44
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0039130313
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Disruption and sputtering erosion of SiC doped CFC
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to be publ. Sendai, Japan, Oct 26-31
-
Nakamura, K. et al., "Disruption and Sputtering Erosion of SiC doped CFC", to be publ. in proc. of ICFRM-8, Sendai, Japan, Oct 26-31. 1997.
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(1997)
Proc. of ICFRM-8
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Nakamura, K.1
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45
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0039130310
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Beryllium assessment and recommendation for application in ITER plasma facing components
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Mito, Japan, Oct. 22-24
-
Barabash, V. et al., "Beryllium Assessment and Recommendation for Application in ITER Plasma Facing Components", Proc. 3d IEA Int. Workshop on Berylium Technology for Fusion, Mito, Japan, Oct. 22-24, 1997, p.2.
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Proc. 3d IEA Int. Workshop on Berylium Technology for Fusion
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Barabash, V.1
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46
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0039722671
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Tensile and fracture toughness test results of neutron irradiated brylliurn
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Mito, Japan, Oct. 22-24
-
Chaouadi, R., Moons, F. and Puzzolante, J. L., "Tensile and Fracture Toughness Test Results of Neutron Irradiated Brylliurn", Proc. 3d IEA Int. Workshop on Berylium Technology for Fusion, Mito, Japan, Oct. 22-24, 1997, p.241.
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Proc. 3d IEA Int. Workshop on Berylium Technology for Fusion
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Chaouadi, R.1
Moons, F.2
Puzzolante, J.L.3
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47
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Low-temperature low-dose neutron irradiation effects on Brush Wellman S65-C and Kawecki Berylco P0 beryllium
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Snead, L., "Low-temperature low-dose neutron irradiation effects on Brush Wellman S65-C and Kawecki Berylco P0 beryllium", to be publ. in J. Nucl. Mater.
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The effect of neutron irradiation on the structure and properties of carbon-carbon composites materials
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Burchell, T.D.1
Eatherly, W.P.2
Strizak, J.P.3
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52
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Departement de Mecanique et de Technologie (DMT). Report DMT N97/150, June
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Bonal, J. P., "Thermal Annealing of Irradiated Carbon Fibre Composites Used for Fusion Application", CEA, Direction des Reacteures Nucleares, Departement de Mecanique et de Technologie (DMT). Report DMT N97/150, June 1997.
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Bonal, J.P.1
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