Oxide particle size distribution from shearing irradiated and unirradiated LWR fuels in Zircaloy and stainless steel cladding: significance for risk assessment (open access)

Oxide particle size distribution from shearing irradiated and unirradiated LWR fuels in Zircaloy and stainless steel cladding: significance for risk assessment

Sieve fractionation was performed with oxide particles dislodged during shearing of unirradiated or irradiated fuel bundles or single rods of UO/sub 2/ or 96 to 97% ThO/sub 2/--3 to 4% UO/sub 2/. Analyses of these data by nonlinear least-squares techniques demonstrated that the particle size distribution is lognormal. Variables involved in the numerical analyses include lognormal median size, lognormal standard deviation, and shear cut length. Sieve-fractionation data are presented for unirradiated bundles of stainless-steel-clad or Zircaloy-2-clad UO/sub 2/ or ThO/sub 2/--UO/sub 2/ sheared into lengths from 0.5 to 2.0 in. Data are also presented for irradiated single rods (sheared into lengths of 0.25 to 2.0 in.) of Zircaloy-2-clad UO/sub 2/ from BWRs and of Zircaloy-4-clad UO/sub 2/ from PWRs. Median particle sizes of UO/sub 2/ from shearing irradiated stainless-steel-clad fuel ranged from 103 to 182 ..mu..m; particle sizes of ThO/sub 2/--UO/sub 2/, under these same conditions, ranged from 137 to 202 ..mu..m. Similarly, median particle sizes of UO/sub 2/ from shearing unirradiated Zircaloy-2-clad fuel ranged from 230 to 957 ..mu..m. Irradiation levels of fuels from reactors ranged from 9,000 to 28,000 MWd/MTU. In general, particle sizes from shearing these irradiated fuels are larger than those from the unirradiated fuels; however, …
Date: March 22, 1979
Creator: Davis, W., Jr.; West, G. A. & Stacy, R. G.
System: The UNT Digital Library
Summary of mechanical properties for JBK-75 forgings (open access)

Summary of mechanical properties for JBK-75 forgings

Increased strengths can be achieved in precipitation-hardened stainless steels by deforming the steel and retaining a worked structure prior to aging. JBK-75 is one example of a superalloy which will respond to this type of thermomechanical processing. The present study was undertaken to determine the tensile properties of different forged shapes resulting from the combined effects of strain hardening and precipitation hardening. Various size bar stock was deformed by High Energy Rate Forging (HERF) and subsequently aged. Resultant tensile properties were quite variable, showing a wide range of strengths and ductilities, well below expected values. The tensile properties were strongly dependent upon forging geometry.
Date: March 22, 1979
Creator: Page, Robert L. & Krenzer, Robert W.
System: The UNT Digital Library
Highlights and setbacks - evaluation and planning program - February 1979 (open access)

Highlights and setbacks - evaluation and planning program - February 1979

None
Date: March 22, 1979
Creator: Taylor, C. J.
System: The UNT Digital Library