Thermoviscoplastic Analysis of First Walls Subjected to Fusion Power Transients

[+] Author and Article Information
H. L. Schreyer

Department of Mechanical Engineering, University of New Mexico, Albuquerque, N.M. 87131

J. M. Kennedy

Reactor Analysis and Safety Division, Argonne National Laboratory, Argonne, Ill. 60439

D. F. Schoeberle

Department of Mechanical Engineering, University of Illinois at Chicago Circle, Chicago, Ill. 60680

J. Pressure Vessel Technol 105(1), 42-51 (Feb 01, 1983) (10 pages) doi:10.1115/1.3264238 History: Received July 27, 1982; Revised September 28, 1982; Online November 05, 2009


Abrupt thermal fluxes on the first walls of fusion reactors represent a loading environment that requires advanced analytical capabilities. Solutions are needed to a wide range of postulated conditions to provide guidance for safety features and design modifications. A brief outline is given of a computer code that provides an integrated procedure for handling thermal stresses and large deformations under dynamic conditions. The code includes a new thermoviscoplastic constitutive equation that incorporates thermal softening, failure and strain rate. Solutions to several verification and illustrative problems are given.

Copyright © 1983 by ASME
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