Calculation of Uranium Inventories in Mixer-Settlers During Solvent Extraction with 7.5% TBP

Technical Report · Thu Aug 01 04:00:00 EDT 1974

DOI:https://doi.org/10.2172/4260855· OSTI ID:4260855

Thompson, M. C. ^[1]; Shankle, R. L. ^[2]

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1. Du Pont de Nemours (E.I.) and Co., Aiken, SC (United States). Savannah River Lab.
2. Du Pont de Nemours (E.I.) and Co., Aiken, SC (United States). Savannah River Lab.; Univ. of Tennessee, Knoxville, TN (United States)

The computer program TRANSIENTS was used to determine the total uranium inventory in each bank of mixer-settlers during solvent extraction processing of uranium fuels with 7.5% TBP in kerosene. The resulting data were used to derive general equations for calculating the total uranium inventory in the mixer-settler banks under various operating conditions. These equations can be used in conjunction with the enrichment of the fuel being processed to calculate the inventory of fissile ²³⁵U in the banks and to establish nuclear safety controls.

• Research Organization: Du Pont de Nemours (E.I.) and Co., Aiken, SC (United States). Savannah River Lab.
• Sponsoring Organization: US Atomic Energy Commission (AEC); USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
• NSA Number: NSA-30-031714
• OSTI ID: 4260855
• Report Number(s): DP--1357
• Country of Publication: United States
• Language: English

Related Subjects

*SPENT FUELS-- REPROCESSING
*URANIUM-- SOLVENT EXTRACTION
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
38 RADIATION CHEMISTRY, RADIOCHEMISTRY, AND NUCLEAR CHEMISTRY
COMPUTER CODES
CRITICALITY
FLOWSHEETS
Fuel
INVENTORIES
MIXER-SETTLERS
N40140 --Chemistry--Separation Procedures
N40450* --Chemistry--Radiochemistry & Nuclear Chemistry-- Reactor Fuel Processing
NUCLEAR MATERIALS MANAGEMENT
Nuclear Criticality Safety Program (NCSP)
T CODES
TBP
URANIUM 235
Uranium