Characterization of spent fuel approved testing material: ATM-103

Abstract

Printed in the UnitedGJ/kgM(28 MWd/kgM) and expected fission gas release of about i%. Characterizationdata includeI) descriptionsof as-fabricatedfuel design, irradiation history, and subsequentstorage and handling;2) isotopicgamma scans;3) fission gas analyses;4) ceramographyof the fuel and metallographyof the clac_ding; 5) special fuel studies involvinganalyticaltransmissionelectron microscopy (AEM); 6) calculatednuclide inventoriesand radioactivitiesin th,afuel and cladding;and 7) radiochemicalanalyses of the fuel and cladd"Jng. Additionalanalysesof the fuel are being conducted and will be _,ncluded in planned revisionsof this report.iii ACKNOWLEDGMENTS

Corrosion Mechanisms of Spent Fuel Under Oxidizing Conditions

“…The "interval release fraction" for a given radionuclide is defined as the ratio ( F W ) where R is the amount of radionuclide collected in a given interval, Le., the total amount in the leachate and the acid strip, and T is the amount of radionuclide calculated [ 1,2] to be in the fuel. Since material incorporated into alteration products, adsorbed on the Zircaloy sample holder, and…”

Validation of SCALE (SAS2H) Isotopic Predictions for BWR Spent Fuel

“…The &el rod lattice data and other fuel assembly design and operating characteristics, obtained from refs. 10 and 16-19, are listed in Table 2. A fuel bundle map and a partial loading diagram of assembly CZ346 are shown in Figs.…”

“…The initial weight fraction of 235U was obtai'ned from ref. 10; the fractions of the remaining uranium isotopes were estimated from the wt % 235U value by empirical relationships developed in earlier ion validation work.I6 Although the Cooper design (like most BWR fuel assemblies) contained multiple enrichments, the depletion calculational procedure in the SAS2H control module does not accommodate more than a single initial composition. Therefore, it was also assumed that the assembly contained a uniform loading corresponding to the enrichment of the sample pin.…”

Yucca Mountain Project - Argonne National Laboratory annual progress report, FY 1994

“…The experimental configuration and initial results for these tests have been reported elsewhere [6,7]. The two fuels are well-characterized [8,9] occurred this fiscal year.…”