1. NAME AND TITLE
PREDEX-1: U, Pu, Nitric Acid Distribution in Counter Current Solvent Extraction.
2. CONTRIBUTOR
Mm.
Dollfus Cantin, Courbevoie, France through the OECD Nuclear Energy Agency Data
Bank, Issy-les-Moulineaux, France.
3. CODING LANGUAGE AND COMPUTER
Fortran IV; IBM 370 Series (P00597I037000).
4. NATURE OF PROBLEM SOLVED
PREDEX-1 provides distribution profiles of uranium, nitric acid and plutonium in counter-current solvent extraction and washing (scrubbing) pluristage equipment. The program is especially applied to prediction calculations for solvent extraction equipment in inactive or active uranium treatment plants.
5. METHOD OF SOLUTION
Calculation made stage by stage (up to 20 stages), considering:
- the equilibrium modelisation of uranium distribution for any acid
concentration;
- the equilibrium modelisation of nitric acid distribution for any uranium
concentration;
- the percentage of tributylphosphate and diluent;
- the temperature effect;
- the real flow-rate corrections.
Several bucklings ensure a complete balance along the equipment.
6. RESTRICTIONS OR LIMITATIONS
It is assumed that the plutonium concentration is relatively low and does not change the balance of other constituents.
7. TYPICAL RUNNING TIME
The mean running time is about 40 seconds for one case (on IBM 370).
8. COMPUTER HARDWARE REQUIREMENTS
IBM 370 (150k bytes of main storage).
9. COMPUTER SOFTWARE REQUIREMENTS
IBM 370 Operating System.
10. REFERENCES
a) Included Documentation:
An Uranium-Plutonium Concentration Profile Calculation Code PREDEX. User's Notice Ref. R/TC-JD/MLD No.184 129 (July 9, 1976).
b) Background Documentation:
Chauve Perot Jorgensen, Calcul automatique d'extraction liquide-liquide, CHISA (September 1969).
11. CONTENTS OF CODE PACKAGE
The package is distributed on a CD with a compressed zip file including source files, documentation, sample input and output.
12. DATE OF ABSTRACT
December 2013.
KEYWORDS: DISTRIBUTION, NITRIC ACID, PLUTONIUM, SOLVENT EXTRACTION, URANIUM