7th International
Conference on
Structural Mechanics
in Reactor Technology
|
7th International
Conference on |
|
DIVISION N: MECHANICAL AND
THERMAL PROBLEMS OF
FUTURE FUSION REACTOR POWER PLANTS
N1 - International Tokamak Reactor/Fusion Energy Device
| N1/1 |
The FED-INTOR Activity |
| N1/2 | INTOR Mechanical Configuration
Concept F. Farfaletti-Casali, T.G. Brown, T.E. Shannon, G. Churahov, D. Serebrennikov, S. Nishio, P. Reynolds, T. Uchida |
| N1/3 | Structural Design Procedures
for FED/INTOR Magnet Systems R.J. Hooper, B.L. Hunter |
| N1/4 | Japanese Contributions to Structural
Mechanical and Stress Analysis of INTOR S. Nisho, T. Honda, Y. Sawada |
| N1/5 | Thermal and Structural Limitations
for Impurity Control Components in FED/INTOR S. Majumdar, Y. Cha, R. Mattas, M. Abodou, B. Cramer, J. Haines |
N2 - Fusion Reactor R&D and Safety Programs
| N2/1 |
Overview of Current Research in Fusion First Wall,
Blanket and Shield Technology |
| N2/2 | Safety Considerations in the
Design of the Fusion Engineering Device R.J. Barrett |
| N2/3 | The Fusion Technology Programme
of the European Community A. Malein |
| N2/4 | Mechanical/Structural Considerations
for Design of a Fusion Breeder J.S. Karbowski |
| N2/5 | Progress in Inertial Fusion Reactor Design W.R. Meier |
N3 - Fusion Reactors Vessel and First Wall
| N3/1 |
Design and Analysis of the Big Dee Vacuum Vessel |
| N3/3 | Structural Analysis of First
Wall/Blanket Vessel for a Tokamak Power Reactor A. Minato, T. Tone, K. Miya |
| N3/4 | General Theory of Electrically
Conducting Orthotropic Toroidal Shells for Tokmak Fusion Reactor E.S. Bobrov |
| N3/5 | Global Inelastic Structural Analysis of the
MARS Tandem Mirror Blanket Tubes Including Radiation Effects J. Blanchard, N.M. Ghoniem |
| N3/6 | Stress Analysis of a Light
Ion Beam Fusion Facility Target Chamber R.L. Engelstad, E.G. Lovell |
| N3/7 | Low Activation Metallic Structural Alloys
for Future Fusion Reactors R.C. Maninger, E.N.C. Dalder |
| N3/8 | Advanced High Heat Flux Components for Ions
Pulse Fusion Device R.S. Blewer, J.B. Whitley, R.D. Watson, M.J. Davis |
| N3/9 | Sructural Design Issues of High Heat Flux
Components n Magnetic Fusion Reactors R.D. Watson, J.B. Whitley |
N4 - Fusion Reactor Blanket and Materials
| N4/1 |
Thermo-Structural and Thermal-Hydraulic Aspects of
the STAR-FIRE/DEMO Tritium Breeding Blanket |
| N4/2 | Thermomechanical Analysis of
a Blanket with Liquid Li17Pb83 Breeder for an Experimental
Fusion Reactor M. Biggio, C. Piana |
| N4/3 | Pebble Bed Blanket Design for
Deuterium Burning Tandem Mirror Reactors S.P. Grotz, V.K. Dhir |
| N4/4 | Compatibility of Structural
Materials for Fusion Reactors with Candidate Blankets and Coolants F. Casteels, Ja. De Keyser, M. Soenen, H. Tas, J. Dresselaers |
| N4/5 | Swelling Tolerant Design for
a Fusion Blanket Structure R.L. Creedon |
N5 - Magnets for Fusion Systems
| N5/1 |
Structural Design and Analysis of the Superconducting Magnets for
the Mirror Fusion Test Facility (MFTF-B) |
| N5/2 | Approximate Description of
Local Deformations of Large Super-conducting Toroidal Field Coils H. Zehlein |
| N5/3 | Structural Analysis of Large
Nonplanar Coils for Fusion Experiments U.B. Brossmann, S.B. Mukherjee |
| N5/4 | Application of the Finite Element
Method in the Modelling of Coil Bundles M. Shibui, I.J. Zatz, J.M. Bialek |
| N5/6 | The Forming of a Superconductor
Cable During the Winding of a Large Toroidal Field Coil G. Messemer, H. Zehlein |
| N5/7 | Analyses of Eddy Current Loadings in Fusion
Engineering Structures J.M. Bialek, D.W. Weissenburger |