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Title: Processing of Non-PFP Plutonium Oxide in Hanford Plants

Abstract

Processing of non-irradiated plutonium oxide, PuO2, scrap for recovery of plutonium values occurred routinely at Hanford’s Plutonium Finishing Plant (PFP) in glovebox line operations. Plutonium oxide is difficult to dissolve, particularly if it has been high-fired; i.e., calcined to temperatures above about 400°C and much of it was. Dissolution of the PuO2 in the scrap typically was performed in PFP’s Miscellaneous Treatment line using nitric acid (HNO3) containing some source of fluoride ion, F-, such as hydrofluoric acid (HF), sodium fluoride (NaF), or calcium fluoride (CaF2). The HNO3 concentration generally was 6 M or higher whereas the fluoride concentration was ~0.5 M or lower. At higher fluoride concentrations, plutonium fluoride (PuF4) would precipitate, thus limiting the plutonium dissolution. Some plutonium-bearing scrap also contained PuF4 and thus required no added fluoride. Once the plutonium scrap was dissolved, the excess fluoride was complexed with aluminum ion, Al3+, added as aluminum nitrate, Al(NO3)3•9H2O, to limit collateral damage to the process equipment by the corrosive fluoride. Aluminum nitrate also was added in low quantities in processing PuF4.

Authors:
;
Publication Date:
Research Org.:
Pacific Northwest National Lab. (PNNL), Richland, WA (United States)
Sponsoring Org.:
USDOE
OSTI Identifier:
1015907
Report Number(s):
PNNL-20246
830403000; TRN: US1102968
DOE Contract Number:
AC05-76RL01830
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; 36 MATERIALS SCIENCE; ALUMINIUM; CALCIUM FLUORIDES; DISSOLUTION; FLUORIDES; HYDROFLUORIC ACID; NITRATES; NITRIC ACID; OXIDES; PLUTONIUM; PLUTONIUM ADDITIONS; PLUTONIUM FLUORIDES; PLUTONIUM OXIDES; PROCESSING; REPROCESSING; SCRAP; SODIUM FLUORIDES; SOLVENT EXTRACTION; STORAGE FACILITIES; TANKS; URANIUM; WASTE PROCESSING; WASTE STORAGE

Citation Formats

Jones, Susan A., and Delegard, Calvin H. Processing of Non-PFP Plutonium Oxide in Hanford Plants. United States: N. p., 2011. Web. doi:10.2172/1015907.
Jones, Susan A., & Delegard, Calvin H. Processing of Non-PFP Plutonium Oxide in Hanford Plants. United States. doi:10.2172/1015907.
Jones, Susan A., and Delegard, Calvin H. Thu . "Processing of Non-PFP Plutonium Oxide in Hanford Plants". United States. doi:10.2172/1015907. https://www.osti.gov/servlets/purl/1015907.
@article{osti_1015907,
title = {Processing of Non-PFP Plutonium Oxide in Hanford Plants},
author = {Jones, Susan A. and Delegard, Calvin H.},
abstractNote = {Processing of non-irradiated plutonium oxide, PuO2, scrap for recovery of plutonium values occurred routinely at Hanford’s Plutonium Finishing Plant (PFP) in glovebox line operations. Plutonium oxide is difficult to dissolve, particularly if it has been high-fired; i.e., calcined to temperatures above about 400°C and much of it was. Dissolution of the PuO2 in the scrap typically was performed in PFP’s Miscellaneous Treatment line using nitric acid (HNO3) containing some source of fluoride ion, F-, such as hydrofluoric acid (HF), sodium fluoride (NaF), or calcium fluoride (CaF2). The HNO3 concentration generally was 6 M or higher whereas the fluoride concentration was ~0.5 M or lower. At higher fluoride concentrations, plutonium fluoride (PuF4) would precipitate, thus limiting the plutonium dissolution. Some plutonium-bearing scrap also contained PuF4 and thus required no added fluoride. Once the plutonium scrap was dissolved, the excess fluoride was complexed with aluminum ion, Al3+, added as aluminum nitrate, Al(NO3)3•9H2O, to limit collateral damage to the process equipment by the corrosive fluoride. Aluminum nitrate also was added in low quantities in processing PuF4.},
doi = {10.2172/1015907},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Thu Mar 10 00:00:00 EST 2011},
month = {Thu Mar 10 00:00:00 EST 2011}
}

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