Published January 2004 | Version v1
Report

Development and application of computer code SIMPSEX for simulation of FBR fuel reprocessing flowsheets. III. additional benchmarking results for HAN and U(IV) based U-Pu partitioning and a HAN based alternate partitioning step for FBTR fuel reprocessing

  • 1. Reprocessing R and D Div., Indira Gandhi Centre for Atomic Research, Kalpakkam (India)

Description

For indigenously developed computer code SIMPSEX, published flowsheets were simulated for benchmarking of partitioning of uranium and plutonium. Benchmarks included classical U(IV) batch partition data, recently published HAN batch partitioning data and several counter-current extraction runs reported in open literature. The agreement between SIMPSEX simulation and reported experimental values was excellent. Based on the HAN based partitioning results for high Pu flowsheets of ORNL, a conceptual HAN based alternate partitioning step was proposed for FBTR fuel reprocessing. (author)

Availability note (English)

Available from Indira Gandhi Centre for Atomic Research, Kalpakkam (IN)

Additional details

Publishing Information

Imprint Pagination
32 p.
Report number
IGC--257

Optional Information

Notes
41 refs., 19 figs., 4 tabs.