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Impact of swelling on fusion reactor first wall lifetime

Conference ·
OSTI ID:5383552
The impact of swelling in 20% cold-worked Type 316 stainless steel on first wall lifetime is assessed. Three separate predictive swelling correlations, two of which are empirically derived from available fission reactor data and one which is largely based upon a theoretical model, have been used. The swelling equations have been incorporated into a materials lifetime code that examines the temperature-stress-strain-radiation effects history of fusion components. The code has been applied to the INTOR, DEMO, and STARFIRE first wall designs.
Research Organization:
Argonne National Lab., IL (USA); Hanford Engineering Development Lab., Richland, WA (USA); Oak Ridge National Lab., TN (USA); California Univ., Santa Barbara (USA)
DOE Contract Number:
W-7405-ENG-26
OSTI ID:
5383552
Report Number(s):
CONF-830942-79; ON: DE84003268
Country of Publication:
United States
Language:
English