The GC computer code for flow sheet simulation of pyrochemical processing of spent nuclear fuels
Journal Article
·
· Nuclear Technology
OSTI ID:413388
- Argonne National Lab., IL (United States). Technology Development Div.
The GC computer code has been developed for flow sheet simulation of pyrochemical processing of spent nuclear fuel. It utilizes a robust algorithm SLG for analyzing simultaneous chemical reactions between species distributed across many phases. Models have been developed for analysis of the oxide fuel reduction process, salt recovery by electrochemical decomposition of lithium oxide, uranium separation from the reduced fuel by electrorefining, and extraction of fission products into liquid cadmium. The versatility of GC is demonstrated by applying the code to a flow sheet of current interest.
- OSTI ID:
- 413388
- Journal Information:
- Nuclear Technology, Vol. 116, Issue 2; Other Information: PBD: Nov 1996
- Country of Publication:
- United States
- Language:
- English
Similar Records
Pyrochemical recovery of actinide elements from spent light water reactor fuel
Electrorefining Experience For Pyrochemical Reprocessing of Spent EBR-II Driver Fuel
Pyrochemical processing of DOE spent nuclear fuel
Conference
·
Sat Jan 01 00:00:00 EST 1994
·
OSTI ID:413388
+1 more
Electrorefining Experience For Pyrochemical Reprocessing of Spent EBR-II Driver Fuel
Conference
·
Sat Oct 01 00:00:00 EDT 2005
·
OSTI ID:413388
+2 more
Pyrochemical processing of DOE spent nuclear fuel
Conference
·
Wed Feb 01 00:00:00 EST 1995
·
OSTI ID:413388