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Characterization of nuclear decontamination solutions at the Idaho Chemical Processing Plant from 1982-1990

Technical Report ·
DOI:https://doi.org/10.2172/236236· OSTI ID:236236
This report represents possibly the single largest collection of operational decontamination data from a nuclear reprocessing facility at the Idaho National Engineering Laboratory and perhaps anywhere in the world. The uniqueness of this data is due to the Idaho Chemical Processing Plant`s (ICPP`s) ability to process different types of highly enriched nuclear fuel. The report covers an 8-year period, during which six campaigns were conducted to dissolve nuclear fuel clad in stainless steel, aluminum, graphite, and zirconium. Each fuel type had a separate head-end process with unique dissolution chemistry, but shared the same extraction process equipment. This report presents data about decontamination activities of the ICPP`s First Cycle extraction vessels, columns, piping, and aluminum dissolution vessels. Operating data from 1982 through 1990 has been collected, analyzed, and characterized. Chemicals used in the decontamination processes are documented along with quantities used. The chemical solutions are analyzed to compare effectiveness. Radioisotopic analysis is recorded, showing and quantifying what nuclides were removed by the various solutions. The original data is also provided to make it possible for researchers to address questions and test other hypotheses not discussed in this report.
Research Organization:
Idaho National Engineering Lab., Idaho Falls, ID (United States)
Sponsoring Organization:
USDOE, Washington, DC (United States)
DOE Contract Number:
AC07-94ID13223
OSTI ID:
236236
Report Number(s):
INEL--96/0014; ON: DE96010361
Country of Publication:
United States
Language:
English