PUMA - a new mathematical model for the rapid calculation of steady-state concentration profiles in mixer-settler extraction, partitioning, and stripping contactors using the Purex process

Journal Article · Sat Nov 01 00:00:00 EST 1986 · Nucl. Technol.; (United States)

OSTI ID:7147699

Geldard, J F

The mathematical basis for a computer code PUMA (Plutonium-Uranium-Matrix-Algorithm) is described. The code simulates steady-state concentration profiles of solvent extraction contactors used in the Purex process, directly without first generating the transient behavior. The computational times are reduced, with no loss of accuracy, by about tenfold over those required by codes that generate the steady-state profiles via transient state conditions. Previously developed codes that simulate the steady-state conditions directly are not applicable to partitioning contactors, whereas PUMA is applicable to all contactors in the Purex process. Since most difficulties are encountered with partitioning contactors when simulating steady-state profiles via transient state conditions, it is with these contactors that the greatest saving in computer times is achieved.

• Research Organization: Los Alamos National Lab., Los Alamos, NM 87545
• DOE Contract Number: W-7405-ENG-36
• OSTI ID: 7147699
• Journal Information: Nucl. Technol.; (United States), Vol. 75:2
• Country of Publication: United States
• Language: English

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
MIXER-SETTLERS
COMPUTERIZED SIMULATION
P CODES
PUREX PROCESS
MATHEMATICAL MODELS
PARTITION
SOLVENT EXTRACTION
STEADY-STATE CONDITIONS
STRIPPING
TIME DEPENDENCE
TRANSIENTS
COMPUTER CODES
DIRECT REACTIONS
EXTRACTION
EXTRACTION APPARATUSES
NUCLEAR REACTIONS
REPROCESSING
SEPARATION EQUIPMENT
SEPARATION PROCESSES
SIMULATION
TRANSFER REACTIONS
050800* - Nuclear Fuels- Spent Fuels Reprocessing