DECONTAMINATION OF PRESSURIZED-WATER SYSTEMS. (thesis)

Technical Report · Mon Jan 01 04:00:00 EST 1962

OSTI ID:4817422

Weed, R D

Submitted to Washington. Univ., Seattle. Pressurized water-cooled reactors require periodic decontamination for continuity of operation and maintenance. A general decontamination procedure was developed involving an oxidizing hydrogen peroxide solution for dissolution of the uranium oxides, an alkaline permanganate solution for film conditioning, and an acidic solution for film removal. The procedure evaluated utilized the following solutions: a peroxide-bicarbonate solution, an alkaline permanganate solution, and a dibasic ammonium citrate solution. The decontamination process, as it was developed during the evaluations. is an effective procedure for decontaminating stainless steel, carbon steel, or mixed carbon steel-stainless steel reactor systems. Laboratory studies, ex-reactor loop studied. and in-reactor loop studies were conducted with this decontamination procedure. Decontamination effectiveness and corrosivity of the process are discussed. A review of decontamination and a discussion of the equipment. test procedures, samples, sample preparation, and basic limitations set for the evaluations are included. Research areas for further process improvement are given. (auth)

• Research Organization: General Electric Co. Hanford Atomic Products Operation, Richland, Wash.
• DOE Contract Number: AT(45-1)-1350
• NSA Number: NSA-16-024939
• OSTI ID: 4817422
• Report Number(s): HW-SA-2548
• Country of Publication: United States
• Language: English

Related Subjects

AMMONIUM COMPOUNDS
CARBONATES
CITRIC ACID
CLEANING
CONTAMINATION
COOLANT LOOPS
CORROSION
DECONTAMINATION
EFFICIENCY
HYDROGEN PEROXIDES
IN PILE LOOPS
MAINTENANCE
MANGANESE COMPOUNDS
OPERATION
ORGANIC COMPOUNDS
POWER PLANTS
PRESSURE
REACTOR TECHNOLOGY
REACTORS
SAMPLING
STAINLESS STEELS
STEELS
TESTING
URANIUM OXIDES
WATER COOLANT
WATER MODERATOR