Open AccessSodium removal process development for LMFBR fuel subassemblies
Author(s) -
C.R. Simmons,
G.R. Taylor
Publication year - 1981
Language(s) - English
Resource type - Reports
DOI - 10.2172/707179
Subject(s) - plenum space , nuclear engineering , breeder reactor , corium , sodium cooled fast reactor , waste management , cladding (metalworking) , sodium , process (computing) , environmental science , materials science , process engineering , engineering , mechanical engineering , heat transfer , computer science , metallurgy , physics , operating system , thermodynamics
Two 37-pin scale models of Clinch River Breeder Reactor Plant fuel subassemblies were designed, fabricated and used at Westinghouse Advanced Reactors Division in the development and proof-testing of a rapid water-based sodium removal process for the ORNL Hot Experimental Facility, Liquid Metal Fast Breeder Reactor Fuel Reprocessing Cycle. Through a series of development tests on one of the models, including five (5) sodium wettings and three (3) high temperature sodium removal operations, optimum process parameters for a rapid water vapor-argon-water rinse process were identified and successfully proof-tested on a second model containing argon-pressurized, sodium-corroded model fuel pins simulating the gas plenum and cladding conditions expected for spent fuel pins in full scale subassemblies. Based on extrapolations of model proof test data, preliminary process parameters for a water vapor-nitrogen-water rinse process were calculated and recommended for use in processing full scale fuel subassemblies in the Sodium Removal Facility of the Fuel Receiving Cell, ORNL HEF