Published September 1981 | Version v1
Report Restricted

Strontium and cesium capsule heat-transfer analysis

Description

As part of the Hanford Waste Management Program, strontium-90 and cesium-137 wastes from the reprocessing of nuclear fuel are separated, concentrated, and double-encapsulated in Hastelloy and stainless steel tubing. These capsules will be stored in water basins until a geologic repository is available. To date, no long-term corrosion data are available to assess capsule integrity after a period of storage in water basins (10 to 20 years) with subsequent long-term retrievable storage (50 to 100 years) in a geologic repository. Peak inner capsule wall temperatures calculated as a function of outer wall temperature and power level of the waste contained are presented in this report. An error in the calculations was discovered since this report was first issued. This revision contains the corrected results

Availability note (English)

MF available from INIS under the Report Number; Available from NTIS., PC A03/MF A01 as DE82009095.

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Additional details

Publishing Information

Imprint Pagination
31 p.
Report number
RHO-LD--167-Rev.1