Dilute chemical decontamination program. Semi-annual report (quarters 6 and 7), January 1-June 30, 1979
An analytical procedure for determining oxalate and citrate in a solution was developed. The gamma dose rates from fuel bundles were determined at several locations. The radiolytic decomposition rates of oxalic and citric acids in solution were measured. Resins were evaluated for the regeneration of solutions of oxalic and citric acids containing Fe(III) and Co(II). Tests indicated the optimum condition for the preloaded anion-exchange resin was for the resin to be in equilibrium with the desired decontamination solution. The option of adding a small amount of cation-exchange resin to the preloaded anion-exchange resin to remove the divalent cations including Co-60 is feasible. Three VNC Test Loop Runs (3, 4 and 5) were completed using solutions of oxalic and citric acids and the preloaded anion-exchange regeneration process. Based on Runs 3 and 4, solvent and operation specifications were modified. The oxalate concentration was incrased from 0.01 to 0.012 M and the dissolved oxygen concentration was established at 0.75 +- 0.25 ppM. In Run 5, more than 85% of the Co-60 was removed from the Nine Mile Point pipe specimen in 12 hours using the new specifications.
- Research Organization:
- General Electric Co., San Jose, CA (USA). Nuclear Engineering Div.
- DOE Contract Number:
- AC02-76ET34203
- OSTI ID:
- 6405043
- Report Number(s):
- DOE/ET/34203-42; ON: DE81025691
- Country of Publication:
- United States
- Language:
- English
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Dilute chemical decontamination program. Quarterly report 5, October 1-December 31, 1978
Dilute chemical decontamination program. Quarterly report 2, January-March 1978
Related Subjects
210100* -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
ANIONS
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
BWR TYPE REACTORS
CARBOXYLIC ACIDS
CATIONS
CHARGED PARTICLES
CHEMICAL ANALYSIS
CHEMICAL RADIATION EFFECTS
CHEMICAL REACTIONS
CHEMISTRY
CITRIC ACID
CLEANING
COBALT 60
COBALT ISOTOPES
COOLANT LOOPS
COOLING SYSTEMS
CORROSION
CORROSION PRODUCTS
DECOMPOSITION
DECONTAMINATION
DICARBOXYLIC ACIDS
DISPERSIONS
DISSOLUTION
DOSE RATES
ELECTROMAGNETIC RADIATION
ENERGY SYSTEMS
ENRICHED URANIUM REACTORS
FILTRATION
FUEL ASSEMBLIES
FUEL ELEMENT CLUSTERS
GAMMA RADIATION
HYDROXY ACIDS
INTERMEDIATE MASS NUCLEI
INTERNAL CONVERSION RADIOISOTOPES
ION EXCHANGE MATERIALS
IONIZING RADIATIONS
IONS
ISOMERIC TRANSITION ISOTOPES
ISOTOPES
MATERIALS
MINUTES LIVING RADIOISOTOPES
MIXTURES
NINE MILE POINT-1 REACTOR
NUCLEI
ODD-ODD NUCLEI
OPTIMIZATION
ORGANIC ACIDS
ORGANIC COMPOUNDS
ORGANIC POLYMERS
OXALIC ACID
PETROCHEMICALS
PETROLEUM PRODUCTS
PH VALUE
PIPES
POLYMERS
POWER REACTORS
RADIATION CHEMISTRY
RADIATION EFFECTS
RADIATIONS
RADIOISOTOPES
RADIOLYSIS
REACTORS
REGENERATION
REMOVAL
RESEARCH PROGRAMS
RESINS
ROD BUNDLES
SEPARATION PROCESSES
SOLUTIONS
TESTING
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
YEARS LIVING RADIOISOTOPES