Inventories of Iodine-129 and Cesium-137 in the Gaps and Grain Boundaries of LWR Spent Fuels

Author:

Gray W. J.

Abstract

AbstractPerformance assessment calculations that support geologic disposal of spent nuclear fuel in a potential repository at Yucca Mountain, Nevada, are based in part on the assumption that 2% of the total inventories of 135Cs, 129I, and 99Tc are located in the gap and grain-boundary regions where they could dissolve rapidly if the spent fuel were to be contacted by groundwater. Actual measured values reported here for a few light-water reactor (LWR) spent fuels show that the combined gap and grain-boundary inventories of 129I approximately equaled the fission-gas release fractions. For 137Cs, the combined gap and grain-boundary inventories were approximately one third of the fission-gas release fractions. These measured values can be used to replace the 2% estimate and thus reduce the uncertainties in the calculations.

Publisher

Springer Science and Business Media LLC

Subject

General Engineering

Reference14 articles.

1. 14. Taylor P. , Behnke R. , Bruneau D. L. , Nye C. D. , and Wood D. D. , A Second Examination of Fragments of Unirradiated and Irradiated CANDU Fuel, and Irradiated L WR Fuel, Oxidized in Air at 130°C and 170°Cfor Approximately One Thousand Days. EPRI Report In Press. Palo Alto, California 94304.

2. Measurements of instant-release source terms for 137Cs, 90Sr, 99Tc, 129I and 14C in used CANDU fuels

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