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RESULTS OF TENSILE TESTS PERFORMED ON MATERIALS EXPOSED IN THE HOMOGENEOUS REACTOR EXPERIMENT NO. 2 BLANKET AND LOW-FLUX-CORE REGION

Technical Report ·
DOI:https://doi.org/10.2172/4764466· OSTI ID:4764466
Tensile specimens of various alloys of zirconium and titanium and a variety of austenitic stainless steels and Incoloy were exposed in the blanket and low-flux core regions of the Homogeneous Reactor Experiment (HRE) No. 2. The purpose of this exposure was to determine the effect of HRE-2 environment on mechanical properties and to provide corrosion data. Specimens were exposed in the low-flux core region and in two blanket loadings. While the specimens were in the low-flux core region, a maximum estimated fast (> 1 Mev) neutron dose of 0.8 x 10/sup 16/ nvt was accumulated. The calculated doses in the first and second blanket loadings were 1.3 x 10/sup 17/ and 2.6 x 10/sup 17/ nvt, respectively. Only insignificant changes were observed in the mechanical properties as a result of the smallest exposure (i.e., 0.8 x 10/sup 16/ nvt). At 1.3 x 10/sup 17/ nvt, some small decreases in ductility for Zircaloy-2, type 347 stainless steel, and A-40 titanium were observed. At 2.6 x 10/sup 18/ nvt, small but definite changes in some of the mechanical properties were observed in all of the materials exposed, usually as small increases in the tensile and yield strengths and slight reduction in elongation, with the greatest changes occurring in the A-40 titanium. Negligible corrosion was observed during the three exposures. (auth)
Research Organization:
Oak Ridge National Lab., Tenn.
DOE Contract Number:
W-7405-ENG-26
NSA Number:
NSA-16-033519
OSTI ID:
4764466
Report Number(s):
ORNL-TM-337
Country of Publication:
United States
Language:
English