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Title: "PIN-CUSHION" IRRADIATION OF CAST URANIUM-PLUTONIUM ALLOY SPECIMENS

Abstract

BS> The irradiation behavior of small pin specimens of chill-cast U-10 wt.% Pu and U-15 wt.% Pu specimens projecting from heat transfer cushions is described. The specimens were coated with a thin layer of carbonyl-deposited nickel. The 15 wt.% Pu pins showed excellent dimensional stability at 1/3 at.% total burnup. The 10 wt.% Pu specimens were somewhat inferior, failure of one of them indicating that the improvement in performane over unalloyed uranium may be due to the restraint imposed by the cladding. (auth)

Authors:
;
Publication Date:
Research Org.:
Argonne National Lab., Lemont, Ill.
OSTI Identifier:
4301907
Report Number(s):
ANL-5795
NSA Number:
NSA-13-000921
DOE Contract Number:
W-31-109-ENG-38
Resource Type:
Technical Report
Resource Relation:
Other Information: Orig. Receipt Date: 31-DEC-59
Country of Publication:
United States
Language:
English
Subject:
RADIATION EFFECTS ON MATERIALS; BURNUP; CANNING; CARBONYLS; FILMS; FUEL SLURRIES; HEAT TRANSFER; MECHANICAL PROPERTIES; NICKEL; PLUTONIUM ALLOYS; RADIATION EFFECTS; RODS; STABILITY; URANIUM ALLOYS

Citation Formats

Paine, S.H., and Brown, F.L.. "PIN-CUSHION" IRRADIATION OF CAST URANIUM-PLUTONIUM ALLOY SPECIMENS. United States: N. p., 1958. Web. doi:10.2172/4301907.
Paine, S.H., & Brown, F.L.. "PIN-CUSHION" IRRADIATION OF CAST URANIUM-PLUTONIUM ALLOY SPECIMENS. United States. doi:10.2172/4301907.
Paine, S.H., and Brown, F.L.. Wed . ""PIN-CUSHION" IRRADIATION OF CAST URANIUM-PLUTONIUM ALLOY SPECIMENS". United States. doi:10.2172/4301907. https://www.osti.gov/servlets/purl/4301907.
@article{osti_4301907,
title = {"PIN-CUSHION" IRRADIATION OF CAST URANIUM-PLUTONIUM ALLOY SPECIMENS},
author = {Paine, S.H. and Brown, F.L.},
abstractNote = {BS> The irradiation behavior of small pin specimens of chill-cast U-10 wt.% Pu and U-15 wt.% Pu specimens projecting from heat transfer cushions is described. The specimens were coated with a thin layer of carbonyl-deposited nickel. The 15 wt.% Pu pins showed excellent dimensional stability at 1/3 at.% total burnup. The 10 wt.% Pu specimens were somewhat inferior, failure of one of them indicating that the improvement in performane over unalloyed uranium may be due to the restraint imposed by the cladding. (auth)},
doi = {10.2172/4301907},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Wed Oct 01 00:00:00 EDT 1958},
month = {Wed Oct 01 00:00:00 EDT 1958}
}

Technical Report:

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  • ABS>An irradiation test of 1/16 in. diameter x 3/16 in. long U/sup 235/ and U/sup 235/-Zr alloy specimens, in the range 2 to 20 wt.% Zr, is described. The small pins were mounted in heat transfer blocks, or ''cushions,'' in such a way that suriace roughening and length changes could be observed, recorded, and compared for five stabilizing heat treatments up to exposure levels of approximately 1% total atom burnup. Addition of 2% Zr was found to be very beneficial, but the behavior of the alloys underwent distinct changes in going from 2 to 4 wt.% Zr. Material, both as-castmore » and subsequently isothermally treated, changed from minus to plus elongation, whereas wrought materials, either gamma-slow cooled or isothermally treated, changed from plus to minus behavior. Data-quenched wrought material varied unpredictably. Addition of Zr up to 20% showed further improvement in stability for all treatments. Factors which may have contributed to this behavior are discussed. (auth)« less
  • Irradiation tests on small pins of wrought and heattreated U/sup 235/-Cr alloys mounted in special heat transfer blocks or ''cushions'' are described. Three compositions, estimatsd at 0.03, 0.07, and 0.22 wt.% Cr, were tested in three metallurgical conditions: alphaannealed, beta-quenched, and isothermally transformed. Radiation damage to the specimens having the first two heat treatments was very similar to that observed in unalloyed uranium of comparable history, and the isothermally treated specimens were similar to betaannealed uranium in behavior. In spite of this essentially null result, which is associated with failure to obtain grain refinement in the specimens, there is evidencemore » that under proper conditions chromium additions to uranium may be beneficial. (auth)« less
  • the manufacture of 25 aluminum-clad, 10 wt. % Al-Pu alloy and 5 wt. % Al-Pu alloy cored specimens is described. Steps in the manufacturing procedure include preparation of cores and cladding material, assembly and welding of compacts, out-gassing, roll bonding, shearing, identification marking, and final fabrication into napkin "rings." (auth)