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Title: POSTIRRADIATION EVALUATION OF ZIRCALOY-2 PRTR PRESSURE TUBES. PART I.

Abstract

Three tubes were removed from the PRTR for detailed postirradiation tests and inspections. The room temperature burst properties, depth of fretting corrosion, changes in grain structure, and the extent of crevice corrosion were determined. The observations may be summarized as follows: (1.) Irradiatlon to 10/sup 20/ nvt (E > 1 Mev) produced a small increase in room temperature burst strength and a decrease in ductility. The uniform deformation of the specimen prior to the local bulging that precedes failure decreased to a negligible amount at the highest exposure. One tube failed when a short crack propagated through the wall nt a stress equivalent to about 85% of ultimate burst stress. The crack did not then propagate the length of the specimen under these severe circumstemces which indicates that the material is still behaving in a ductlle manner at room temperature. (2.) Close-up visual examination revealed thrt the fretting corrosion marks appeared much the same as in photos taken through the borescope. Depths of penetration from standard fuel element end brackets were found up to 6 mils deep. Outer wire wraps and, occasionally, individual rod wire wraps caused similar penetrations of the tube wall. Bands on Pu--Al elements did not causemore » any measurable penetration of the tube wall. Increasing the width of contact area of the fuel end bracket apparently decreased the penetration. (3.) The grain structure under the fretting corrosion marks was unchanged in many instances; however, local hydriding was found in a thin layer under three of the twelve corrosion defects that were examined. Visual appearance of the corrosion mark gave no indication of the presence of hydride. (4.) Crevice corrosion of the upper flange penetrated up to 4 mils. Heavy white corrosion product is present but little if any local hydriding has occurred since the first operating period. From the above observations it is concluded that even though the continued penetration of the tube wall by fretting corrosion would be detrimental to the integrity of the pressure tubes, the general behavior of the tubes to date has been superior to that anticipated when the tubes were designed. (auth)« less

Authors:
Publication Date:
Research Org.:
General Electric Co. Hanford Atomic Products Operation, Richland, Wash.
OSTI Identifier:
4735698
Report Number(s):
HW-73698(Rev.)
NSA Number:
NSA-17-008706
DOE Contract Number:  
AT(45-1)-1350
Resource Type:
Technical Report
Resource Relation:
Other Information: Orig. Receipt Date: 31-DEC-63
Country of Publication:
United States
Language:
English
Subject:
METALS, CERAMICS, AND OTHER MATERIALS; ALUMINUM ALLOYS; CORROSION; CRACKS; DEFECTS; DUCTILITY; FAILURES; GRAIN SIZE; HYDRIDES; IRRADIATION; LAYERS; MATERIALS TESTING; PLUTONIUM ALLOYS; PRESSURE; PRTR; RADIATION DOSES; REACTORS; STRESSES; TENSILE PROPERTIES; TUBES; ZIRCALOY

Citation Formats

Defferding, L J. POSTIRRADIATION EVALUATION OF ZIRCALOY-2 PRTR PRESSURE TUBES. PART I.. United States: N. p., 1962. Web. doi:10.2172/4735698.
Defferding, L J. POSTIRRADIATION EVALUATION OF ZIRCALOY-2 PRTR PRESSURE TUBES. PART I.. United States. doi:10.2172/4735698.
Defferding, L J. Thu . "POSTIRRADIATION EVALUATION OF ZIRCALOY-2 PRTR PRESSURE TUBES. PART I.". United States. doi:10.2172/4735698. https://www.osti.gov/servlets/purl/4735698.
@article{osti_4735698,
title = {POSTIRRADIATION EVALUATION OF ZIRCALOY-2 PRTR PRESSURE TUBES. PART I.},
author = {Defferding, L J},
abstractNote = {Three tubes were removed from the PRTR for detailed postirradiation tests and inspections. The room temperature burst properties, depth of fretting corrosion, changes in grain structure, and the extent of crevice corrosion were determined. The observations may be summarized as follows: (1.) Irradiatlon to 10/sup 20/ nvt (E > 1 Mev) produced a small increase in room temperature burst strength and a decrease in ductility. The uniform deformation of the specimen prior to the local bulging that precedes failure decreased to a negligible amount at the highest exposure. One tube failed when a short crack propagated through the wall nt a stress equivalent to about 85% of ultimate burst stress. The crack did not then propagate the length of the specimen under these severe circumstemces which indicates that the material is still behaving in a ductlle manner at room temperature. (2.) Close-up visual examination revealed thrt the fretting corrosion marks appeared much the same as in photos taken through the borescope. Depths of penetration from standard fuel element end brackets were found up to 6 mils deep. Outer wire wraps and, occasionally, individual rod wire wraps caused similar penetrations of the tube wall. Bands on Pu--Al elements did not cause any measurable penetration of the tube wall. Increasing the width of contact area of the fuel end bracket apparently decreased the penetration. (3.) The grain structure under the fretting corrosion marks was unchanged in many instances; however, local hydriding was found in a thin layer under three of the twelve corrosion defects that were examined. Visual appearance of the corrosion mark gave no indication of the presence of hydride. (4.) Crevice corrosion of the upper flange penetrated up to 4 mils. Heavy white corrosion product is present but little if any local hydriding has occurred since the first operating period. From the above observations it is concluded that even though the continued penetration of the tube wall by fretting corrosion would be detrimental to the integrity of the pressure tubes, the general behavior of the tubes to date has been superior to that anticipated when the tubes were designed. (auth)},
doi = {10.2172/4735698},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1962},
month = {11}
}