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Title of Journal: J Fusion Energ

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Abbravation: Journal of Fusion Energy

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Springer US

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DOI

10.1007/bf00477146

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ISSN

1572-9591

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Numerical Evaluation on Heat Shock Resistance of T

Authors: Shenghong Huang Yongqiang Zhao Weihua Wang
Publish Date: 2015/05/24
Volume: 34, Issue: 6, Pages: 1465-1477
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Abstract

The first wall of fusion reactor is a plasmafacing component and is a key link to maintain the integrity of the structure during thermal shock induced by plasma disruptions Previous researches on thermal shock resistance of the first wall lacks coupled thermal/mechanical analysis on heat shock process based on practical operating conditions such as material melting solidification and even evaporation etc which is significant to further understand the heat shock damage mechanism of first wall structures With the aim to lean more detailed mechanical mechanism of thermal shock damage and then to improve the thermal shock resistance performance of first wall design the coupled thermal/mechanical response of two typical structure of ITERlike first walls with different plasmafacing material one is traditionally Be the other is functionally graded W–Cu under the heat shock of 1–2 GW/m2 are computed by the finite element method Special considerations of elastic–plastic deformation material melting solidification are included in numerical models and methods The mechanical response behaviors of different structures and materials under normal servicing operation as well as plasma disruption conditions are analyzed and investigated comparatively It is concluded that 1 During the normal servicing operation state both kinds of first walls manifest a good thermal and mechanical performance However the first wall with graded W–Cu material presents a more complex distribution and larger values of interfacial thermal stress and deformation 2 In high energy shock pulse induced by plasma disruptions heat is mainly deposited on PFM layer complex thermal stress change as well as coupled melting and solidification processes in PFM layer are observed involving a mechanical irreversible damage of repeated thermal elastic and plastic expansion contraction and yielding 3 The mechanically irreversible damages for both mockups under the thermal shock with H0 = 1–2 GW/m2 are mainly limited in PFM layer the internal parts of both mockups are protected effectively 4 In view of thermal/mechanical performance the first wall with Be PFM mitigates the damages from heat shock at most only in PFM layer with cost of whole PFM layer plastic yielding while the first wall with graded W–Cu PFM is potential of higher heat shock resistance performance providing its material gradient as well as cooling capacity are well optimized under practical loading conditions


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Other Papers In This Journal:

  1. Erratum to: The Study of the Dynamics of Z Pinch Plasma Using Electromagnetic, Thermal and Circuital Coupling
  2. Design and Fabrication of a Data Acquisition System for Pulsed Neutron Flux Measurement of Plasma Focus Devices
  3. Investigation of Arc Regulation of Hot Cathode Ion Source with Langmuir Probe
  4. Comments to the Article “The Behavior of Radial Electric Field and Toroidal Rotation in the Edge Plasma of Divertor Tokamak” by A. H. Bekheit Published in J. Fusion Energy (2010) 29, p. 443–446
  5. Evaluation of Heat Transfer Augmentation in a Nanofluid-Cooled Microchannel Heat Sink
  6. Measurement of Plasma Energy Confinement Time in Presence of Resonant Helical Field in IR-T1 Tokamak
  7. On the Current Sharing Control of ITER Poloidal Field Converter
  8. Thermalization of Langmuir Wave Energy via the Stochastic Plasma Electron Acceleration
  9. Combined Effect of Ion Temperature and Magnetic Field on Collisionless Sheath Structure
  10. The Use of Plasma Actuators in Narrowband Active Noise Control
  11. Effect of Internal Breeding of Tritium and Helium-3 on the Ignition of an ICF Fuel Pellet
  12. Reaction Kinetics for the Synthesis of Li 4 SiO 4 by Solid State Reaction from Li 2 SiO 3 and Li 2 CO 3 for Tritium Breeder
  13. Condensed Atomic Hydrogen as a Possible Target in Inertial Confinement Fusion (ICF)
  14. Structure Analysis of High Current DC Disconnector Used in ITER Poloidal Field Converter
  15. Determination of Average Ion Temperature of the TVD Tokamak by a Simple Charge Exchange Analyzer Detector
  16. Application of High Energy Protons in Inertial Confinement Fusion by Using the Fast Ignitor Concept for DT Fusion
  17. The Plasma Liner Compression Experiment
  18. Spheromak Formation and Current Sustainment Using a Repetitively Pulsed Source
  19. Erratum to: Kilotesla Magnetic Assisted Fast Laser Ignited Boron-11 Hydrogen Fusion with Nonlinear Force Driven Ultrahigh Accelerated Plasma Blocks
  20. Plasma Magnetic Fluctuations Measurement on the Outer Surface of IR-T1 Tokamak
  21. Stability of Plasma Configurations During Compression
  22. Investigation on the Neutronic Performance of a Fusion Reactor Using Flibe with Heavy Metal Fluorides
  23. Calculation of Beam Extraction Pulse Duration for Beam Angular Divergence Measurement of EAST Neutral Beam Injection
  24. Electrical Parameter Measurement System of the Ion Source for EAST Neutral Beam Injector
  25. Magnetohydrodynamic Free Convective Flow Past an Infinite Vertical Porous Plate with Magnetic Induction
  26. Activation Analysis and Comparison of Bio-shield Under ITER and ASP Neutron Irradiation

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