Actions for SOLUTION CORROSION GROUP QUARTERLY REPORT FOR THE PERIOD ENDING JULY 31, 1957

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SOLUTION CORROSION GROUP QUARTERLY REPORT FOR THE PERIOD ENDING JULY 31, 1957

Author
Griess, J. C.
Published
United States : [publisher not identified], 1957.
[Oak Ridge, Tennessee] : [U.S. Atomic Energy Commission], 1957.
Physical Description
microopaque : positive ; 8 x 13 cm
Additional Creators
Buxton, S. R., English, J. L., Hess, D. N., Mauney, T. H., Neumann, P. D., Savage, H. C., Ulrich, W. C., and Greeley, R. S.

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Summary
The second All-Ti loop, 1OOA loop H, was placed in operation for more than 400 hr with UO/sub 2/SO/sub 4/ solution at 250 deg C and -- 1000 psi. A fourth test of the mockup of the Zircaloy-2--stainless steel transition joint used in the HRT reactor vessel was completed. The joint and bellows functioned properly and were leaktight. The series of long-term runs at 200, 250, and 300 deg C with solution proposed for use in the HRT was concluded. Stainless steel and Ti stress specimens exposed during the latter 13,000 hr of these tests gave no evidence of stress-corrosion cracking. Results of a study of the effect of heat treatment on corrosion of type 347 stainless steel are presented. Pretreatment of stainless steel for 100 hr at 250 deg C with oxygenated H/sub 2/O containing 100 or 200 ppm Cr/sup 6+/ as CrO/sub 3/ decreased initial weight losses on subsequent exposures to UO/sub 2/SO/sub 4/ solutions. Stress-corrosion cracking of stainless steel in UO/sub 2/SO/sub 4/ solutions is described. A number of alloys of Zr were corrosion tested in simulated HRT core solutions at 300 deg C. Type 347 stainless steel, surface hardened either by malcomizing or Thermospray 16-C, corroded excessively in UO/sub 2/SO/sub 4/ solutions. Hastelloy R-235, Multimet, and Timken 16-25-6 demonstrated a high degree of corrosion resistance to simulated core solution at 300 deg C. Under the sanne conditions types 431 and 414 stainless steel corroded excessively. Type 420 stainless steel hardened at 50 to 52 Rockwell C corroded badly in 90 deg C UO/sub 2/SO/sub 4/ solution of the composition used in in-pile loops. (W.L.H.)
Report Numbers
CF-57-7-121
Other Subject(s)
Collection
U.S. Atomic Energy Commission depository collection.
Note
DOE contract number: W-7405-ENG-26
NSA number: NSA-12-000228
OSTI Identifier 4312148
Research organization: Oak Ridge National Lab., Tenn..
View MARC record | catkey: 39680872