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Title: Advanced Gas Cooled Nuclear Reactor Materials Evaluation and Development Program. Progress report, January 1, 1981-March 31, 1981

Technical Report ·
OSTI ID:5947751

Objectives are to evaluate candidate alloys for very high temperature reactor (VHTR) applications, particularly nuclear process heat (NPH) applications, in terms of the effect of simulated reactor primary coolant (helium containing small amounts of various other gases), high temperatures, and long time exposures on the mechanical properties and structural and surface stability. Work covered in this report includes the activities associated with the status of the simulated reactor helium supply systems and testing equipment. Progress in the screening test program is described; this includes: screening creep results and metallographic analysis for materials thermally exposed or tested at 750, 850, 950, and 1050/sup 0/C. Status of controlled purity helium and air creep-rupture testing in the intensive screening test program is discussed. Results of metallographic studies of screening alloys exposed in controlled purity helium from 1000 hours at 1050/sup 0/C and 3000 hours at 850/sup 0/C are presented.

Research Organization:
General Electric Co., Schenectady, NY (USA). Energy Systems Programs Dept.
DOE Contract Number:
AC02-76ET34202
OSTI ID:
5947751
Report Number(s):
DOE/ET/34202-54; ON: DE82001001
Country of Publication:
United States
Language:
English