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U.S. Department of Energy
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Palm content of production metal

Technical Report ·
DOI:https://doi.org/10.2172/10156261· OSTI ID:10156261

Purpose of this study was to determine the {sup 237}Np input to the Purex process. The {sup 237}Np content of 639 g Pu/ton U irradiated fuel was found to be 1.78 {plus_minus} .09 g/ton of uranium at the 95% confidence level. Standard recovery for the chemical method was 96.7%, 98.0% for the sampling.

Research Organization:
General Electric Co., Richland, WA (United States). Hanford Atomic Products Operation
Sponsoring Organization:
USDOE, Washington, DC (United States)
DOE Contract Number:
AC06-76RL01830
OSTI ID:
10156261
Report Number(s):
HW--62824; ON: DE94012682
Country of Publication:
United States
Language:
English