Hazards Review for Electrolytic Dissolver Installation, Hood 3, 236-Z Building

Technical Report · Tue Mar 13 00:00:00 EST 1973

DOI:https://doi.org/10.2172/7216126· OSTI ID:7216126

Anderson, R. D. ^[1]; Barney, G. S. ^[1]; Helbling, T. J. ^[1]; Kofoed, R. J. ^[1]

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1. Atlantic Richfield Hanford Co., Richland, WA (United States)

The installation of two electrolytic dissolvers in Hood 3, 236-Z Building, is now being completed. These dissolvers will be used to dissolve plutonium metal in nitric acid by application of an electric current. The resulting plutonium solution will then be delivered to a holding tank for use as feed to the solvent extraction columns. The dissolver system consists of the dissolver tank and electrodes, acid recirculation loop, primary and secondary heat exchangers, and off-gas system. To dissolve plutonium, the metal is placed between the cathode and anode of the dissolver and concentrated nitric acid is added. A potential of 15 to 24 volts is applied to the electrodes, causing the metal to dissolve on the cathodic side. Heat generated by the electrodes is removed from the system by circulating the acid through a heat exchanger. The water in this heat exchanger is cooled by a secondary heat exchanger. Gases produced by the electrolysis (NO_x and some H₂) are removed and diluted by a vacuum system. The off-gases are continuously monitored for combustible gases (H₂). The present method used to dissolve plutonium metal requires several steps. The metal must be burned to form PuO₂. This PuO₂ is screened, pulverized, and then dissolved in a nitric/hydrofluoric acid mixture in a batch pot dissolver. The oxide is difficult to dissolve and requires long heating and agitation times.

• Research Organization: Atlantic Richfield Hanford Co., Richland, WA (United States)
• Sponsoring Organization: USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP); US Atomic Energy Commission (AEC)
• DOE Contract Number: EY-76-C-06-2130
• OSTI ID: 7216126
• Report Number(s): ARH-2755
• Country of Publication: United States
• Language: English

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
37 INORGANIC
ORGANIC
PHYSICAL AND ANALYTICAL CHEMISTRY
CHEMICAL REACTORS
HAZARDS
CRITICALITY
DISSOLUTION
PLUTONIUM
PROCESSING
ACTINIDES
ELEMENTS
METALS
TRANSURANIUM ELEMENTS
Nuclear Criticality Safety Program (NCSP)
Electrolysis
Chemical Reactors
Off Gas System
Criticality
Plutonium
Experiment
054000* - Nuclear Fuels- Health & Safety
400400 - Electrochemistry