Author: M. C. FraserPublisher:
ISBN:
Category : Zirconium alloys
Languages : en
Pages : 26
Book Description
Postirradiation Evaluation of Zircaloy-2 PRTR Pressure Tubes
Author: Postirradiation Evaluation of Zircaloy-2 PRTR Pressure Tubes
Author: M. C. FraserPublisher:
ISBN:
Category : Zirconium alloys
Languages : en
Pages : 26
Book Description
POSTIRRADIATION EVALUATION OF ZIRCALOY-2 PRTR PRESSURE TUBES.
Author: Postirradiation Evaluation of Zircaloy-2 PRTR Pressure Tubes
Author: Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
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).
Postirradiation Evaluation of Zircaloy Pressure Tubes from KER-1 and KER-2
Author: R. C. AungstPublisher:
ISBN:
Category : Zircaloy-2
Languages : en
Pages : 26
Book Description
Postirradiation Evaluation of Zircaloy-2 Pressure Tube from KER-3, Preliminary Report
Author: R. C. AungstPublisher:
ISBN:
Category : Metallurgy
Languages : en
Pages : 74
Book Description
POSTIRRADIATION EVALUATION OF ZIRCALOY PRESSURE TUBES FROM KER-1-AND KER-2
Author: Evaluation of Properties of Irradiated Zircaloy-2 Pressure Tube from KER Loop 1
Author: L. J. DefferdingPublisher:
ISBN:
Category : Carbon steel
Languages : en
Pages : 56
Book Description
Strength and Metallurgical Properties of the Zircaloy-2 Pressure Tubes for the PRTR
Author: R. L. KnechtPublisher:
ISBN:
Category : Plutonium
Languages : en
Pages : 52
Book Description
In-reactor Monitoring of Zircaloy-2 PRTR Pressure Tubes
Author: D. R. DomanPublisher:
ISBN:
Category : Metallurgy
Languages : en
Pages : 68
Book Description