10th International
Conference on
Structural Mechanics
in Reactor Technology
|
10th International
Conference on |
|
DIVISION N: MECHANICAL & THERMAL PROBLEMS OF FUSION REACTORS
(The papers with links are those received by the SMiRT 10 Secretariat at the
time the Transactions went to press)
N01: Blanket Design
|
Mechanical Design
of a Solid Breeder Blanket Canister for ITER |
| Thermal
and Structural Behaviour of a Double Containment Water Cooled BOT Ceramic
Blanket for "NET" P.G. Avanzini, N. Cerullo, E. Manfredi |
| Blanket
Concepts for the ARIES Commercial Tokamak Reactor Study S.P. Grotz, T. Hua, D.K. Sze, E.T. Cheng, R.L. Creedon, C.P.C. Wong, J.S. Herring, A. Klein, L. Snead, D. Steiner, N.M. Ghoniem, M.Z. Hasan, R.C. Martin, F. Najmabadi, S. Sharafat |
| Thermal-Hydraulic
Design of a Solid Particulate Fusion Reactor Blanket Clement P.C. Wong, Mohammad Z. Hasan |
N02: Magnet Design
| Optimization
of OH Coil Spiral Topology R.J. Witt |
| Non-Axisymmetric
Response of OH Coils to Lorentz Forces R.J. Witt, E.S. Bobrov |
| Non-Linear
Analysis of the TFTR Toroidal Field Coil Irvng J. Zatz |
| Structural
Analysis of Superconducting Coils for Fusion Reactors Taking into Account
the Slip Between Conductors Roberto E. Gori, Bernhard A. Schrefler |
| Experience
with the Plate Structure of the Westinghouse Coil for the Large Coil Task J.W. Lue, L. Dresner, M.S. Lubell, J.N. Luton, T.J. McManamy |
| Cryogenic
Tensile and Fracture Properties of Structural Materials for Superconducting
Magnets in Fusion Technology A. Nyilas, P. Komarek |
N03: In-Vessel Components
|
Thermomechanical
Implications of X-Point Sweeping for Divertor Target Elements |
| Mechanical
Design Aspects of the Fastening/Guiding Support System for the Tokamak First
Wall Components Subjected to Plasma Disruption Events Y.R. Crutzen, F. Farfaletti-Casali |
| ASME
and RCC-MR Comparison for the Prevention of Fatigue Analysis B. Autrusson, D. Acker |
| An
Expert System for Fusion First Wall Design Shinobu Yoshimura, Genki Yagawa, Yoshihiko Mochizuki |
| A
Nonvaporizing First Wall for Inertial-Confinement-Fusion Reactors John H. Pitts, Max Tabak |
N04: General
|
Design Optimization
of an Articulated Boom for NET In-Vessel Handling Unit |
| Calculation
and Comparative Measurement of a Manipulator Boom F.-O. Henkel, W. Breuer |
| Muon
Catalyzed Fusion Beam Window Mechanical Strength Testing and Analysis A.G. Ware, J.M. Zabriskie |
| Finite
Element Analysis of Magnetically Induced Vibrations of Conductive Plates
in TOKAMAK Reactors Jong S. Lee, Jean H. Prevost |
| Use
of Dissociating Gases as Primary Coolants and Working Fluids in Power Cycles
for Fusion Reactors M.Z. Hasan, R.C. Martin |
N05: Mechanical Behavior of Fusion Reactor Material
| Effect
of Electron Beam Irradiation on Fracture and Fatigue Characteristics of
TZM Takeshi Denda, Toshinori Nishimura, Tokuo Teramoto, Masakatsu Saito |
| Silicon-Carbide
Composite Materials for the ARIES-I Reactor Study S. Sharafat, N.M. Ghoniem, S.P. Grotz, L.Y. Lee, and The ARIES Team |
| Transient
Thermoelastic In-Plane and Bending Behaviors of Cross-Ply and Angle-Ply
Laminated Slabs Yoshihiro Ootao, Yoshinobu Tanigawa, Hidenori Murakami |
| Transient
Thermal Stress Analysis of Multi-Layered Composite Laminate Cylinder and
its Analyical Extension to Non-Homogeneous Materials Yoshinobu Tanigawa, Hidenori Murakami, Yoshihiro Ootao |
Return to SMiRT 10 TOC