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Title: A VISUAL STUDY OF THE CORROSION OF DEFECTED ZIRCALOY-2-CLAD FUEL SPECIMENS BY HOT WATER

Abstract

The failure of defected Zircaloy-2-clad uranium and uranium -2 wt.% zircorium fuel specimens in high-purity high-pressure water at 200 to 345 deg C was observed in a windowed antcclave. Time-lapse color motion pictures were taken to provide a record of the progressive changes ending in the complete disintegration of the core material in the specimens. Continuous measurement of the pressure increase caused by accumulation of hydrogen served to monitor the progress of the reaction when clouding of the water by corrosion products made visual observation impossible. The nature of the attack of all specimens was similar, although the time at which different stages occurred varied. Following an induction period, the first evidence of attack was the slow formation of a blister in the cladding area surrounding the defect. Eventually, a copions evolution of hydrogen occurried at the base of the swollen area. In general, a crack could be seen in the cladding at this stage. Catastrophic failure of the specimen followed swiftly. The time required for each phase of the reaction was reduced as the temperature was raised. Initial swelling occurred after about 24 min at 345 deg C but only after 8 hr at 200 deg C. Diffusion-treated uranium2more » wt.% zirconium-cored specimens were most resistant to attack. Specimens with beta-treated water-quenched natural-uranium cores were least resistant (auth)« less

Authors:
; ;
Publication Date:
Research Org.:
BAttelle Memorial Inst., Columbus, Ohio
OSTI Identifier:
4206337
Report Number(s):
BMI-1387
NSA Number:
NSA-14-002689
DOE Contract Number:  
W-7405-ENG-92
Resource Type:
Technical Report
Resource Relation:
Other Information: Orig. Receipt Date: 31-DEC-60
Country of Publication:
United States
Language:
English
Subject:
METALS, CERAMICS, AND MATERIALS; AUTOCLAVES; COLOR; CORROSION; CRACKS; DEFECTS; DIFFUSION; ENRICHMENT; FAILURES; FUEL CANS; HEAT TREATMENTS; HYDROGEN; INSPECTION; MONITORING; PRESSURE; PRESSURE VESSELS; RECORDING SYSTEMS; URANIUM; URANIUM ALLOYS; WATER; WINDOWS; ZIRCALOY; ZIRCONIUM ALLOYS

Citation Formats

Stephan, E.F., Miller, P.D., and Fink, F.W. A VISUAL STUDY OF THE CORROSION OF DEFECTED ZIRCALOY-2-CLAD FUEL SPECIMENS BY HOT WATER. United States: N. p., 1959. Web. doi:10.2172/4206337.
Stephan, E.F., Miller, P.D., & Fink, F.W. A VISUAL STUDY OF THE CORROSION OF DEFECTED ZIRCALOY-2-CLAD FUEL SPECIMENS BY HOT WATER. United States. doi:10.2172/4206337.
Stephan, E.F., Miller, P.D., and Fink, F.W. Mon . "A VISUAL STUDY OF THE CORROSION OF DEFECTED ZIRCALOY-2-CLAD FUEL SPECIMENS BY HOT WATER". United States. doi:10.2172/4206337. https://www.osti.gov/servlets/purl/4206337.
@article{osti_4206337,
title = {A VISUAL STUDY OF THE CORROSION OF DEFECTED ZIRCALOY-2-CLAD FUEL SPECIMENS BY HOT WATER},
author = {Stephan, E.F. and Miller, P.D. and Fink, F.W.},
abstractNote = {The failure of defected Zircaloy-2-clad uranium and uranium -2 wt.% zircorium fuel specimens in high-purity high-pressure water at 200 to 345 deg C was observed in a windowed antcclave. Time-lapse color motion pictures were taken to provide a record of the progressive changes ending in the complete disintegration of the core material in the specimens. Continuous measurement of the pressure increase caused by accumulation of hydrogen served to monitor the progress of the reaction when clouding of the water by corrosion products made visual observation impossible. The nature of the attack of all specimens was similar, although the time at which different stages occurred varied. Following an induction period, the first evidence of attack was the slow formation of a blister in the cladding area surrounding the defect. Eventually, a copions evolution of hydrogen occurried at the base of the swollen area. In general, a crack could be seen in the cladding at this stage. Catastrophic failure of the specimen followed swiftly. The time required for each phase of the reaction was reduced as the temperature was raised. Initial swelling occurred after about 24 min at 345 deg C but only after 8 hr at 200 deg C. Diffusion-treated uranium2 wt.% zirconium-cored specimens were most resistant to attack. Specimens with beta-treated water-quenched natural-uranium cores were least resistant (auth)},
doi = {10.2172/4206337},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1959},
month = {10}
}