SX process-A code for solvent extraction processes in centrifugal contactors simulation

Abstract Solvent extraction processes have proven to be very efficient in the task of removing the long-lived radiotoxic nuclides from spent nuclear fuel. New separation systems are constantly developed and demonstrated in lab-scale process tests. The process optimisation and modelling is an important part of this work and for this purpose the SX Process software has been developed. The software is focused on lab-scale processes in miniature centrifugal contactors which are fully designed through the software interface, meaning that no change in the code is necessary for a new system. A relatively simple model has been developed and implemented to calculate the transfer between the phases in centrifugal contactors. With this model the americium profile from a previous SANEX process run could be calculated with good accuracy.

[1]  Ralph A. Leonard,et al.  A SPREADSHEET ALGORITHM FOR STAGEWISE SOLVENT EXTRACTION , 1994 .

[2]  Daryl R. Haefner,et al.  Survey of Dynamic Simulation Programs for Nuclear Fuel Reprocessing , 2008 .

[3]  G. Modolo,et al.  Towards an optimized flow-sheet for a SANEX demonstration process using centrifugal contactors , 2009 .

[4]  J. Glatz,et al.  Recovery of minor actinides from HLLW using the DIAMEX process , 2005 .

[5]  D. R. Prabhu,et al.  Demonstration of T2EHDGA Based Process for Actinide Partitioning Part II: Counter-Current Extraction Studies , 2010 .

[6]  A. Geist,et al.  A review of the demonstration of innovative solvent extraction processes for the recovery of trivalent minor actinides from PUREX raffinate , 2012 .

[7]  W. S. Groenier.  CALCULATION OF THE TRANSIENT BEHAVIOR OF A DILUTE-PUREX SOLVENT EXTRACTION PROCESS HAVING APPLICATION TO THE REPROCESSING OF LMFBR FUELS. , 1972 .

[8]  A. Geist,et al.  Demonstration of a SANEX Process in Centrifugal Contactors using the CyMe4‐BTBP Molecule on a Genuine Fuel Solution , 2009 .

[9]  C. Hill.  Development of highly selective compounds for solvent extraction processes: partitioning and transmutation of long-lived radionuclides from spent nuclear fuels , 2011 .

[10]  G. Modolo,et al.  Demonstration of a TODGA based Extraction Process for the Partitioning of Minor Actinides from a PUREX Raffinate , 2009 .

[11]  J. Galy,et al.  Impact limits of partitioning and transmutation scenarios on the radiotoxicity of actinides in radioactive waste , 2003 .

[12]  G. Modolo,et al.  Demonstration of a TODGA‐Based Continuous Counter‐Current Extraction Process for the Partitioning of Actinides from a Simulated PUREX Raffinate, Part II: Centrifugal Contactor Runs , 2008 .

[13]  E. M. González-Romero,et al.  Impact of partitioning and transmutation on the high level waste management , 2011 .

[14]  D. R. Prabhu,et al.  Counter-current extraction of uranium and lanthanides from simulated high-level waste using N,N,N′,N′-tetraoctyl diglycolamide , 2009 .

[15]  J. Glatz,et al.  Partitioning of minor actinides from HLLW using the DIAMEX process.Part 2 - ´´Hot´´ continuous counter-current experiment , 2000 .

[16]  R. Malmbeck,et al.  Development of a Solvent Extraction Model for Process Tests in Short Residence Time Centrifugal Contactors , 2012 .

[17]  R. Leonard,et al.  Design Principles and Applications of Centrifugal Contactors for Solvent Extraction , 2009 .

[18]  M. Nilsson,et al.  Review Article: A Review of the Development and Operational Characteristics of the TALSPEAK Process , 2007 .