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97119 LABORATORY SIMULATION OF SALT DISSOLUTION DURING WASTE REMOVAL

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Product Number: 51300-97119-SG
ISBN: 97119 1997 CP
Author: B. J. Wlersma, W. R. Parish
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Laboratory experiments were performed to support the field demonstration of improved techniques for salt dissolution in tanks containing radioactive waste at the Savannal River Site. The tests were designed to investigate three density driven techniques for salt dissolution: (1) Drain-Add-Sit-Remove, (2) Modified Density Gradient, and (3) Continuous Salt Mining. Salt dissolution was observed to be a very rapid process as saturated salt solutions, with a density of approximately 1.4, were frequently removed. Slower addition and removal rates and locating the outlet line at deeper levels below the top of the saltcake provided the best contact between the dissolution water and the saltcake. It was observed that dissolution with 1 M sodium hydroxide solution resulted in salt solutions that were within the current inhibitor requirements for the prevention of stress corrosion cracking. This result was independent of the density driven technique. However, if inhibited water (0.01 M sodium hydroxide and 0.011 M sodium nitrite) was utilized, the salt solutions were frequently outside the inhibitor requirements. Corrosion testing at conditions similar to the environments expected during waste removrd was recommended. Keywords Radioactive waste, carbon steel, stress corrosion cracking
Laboratory experiments were performed to support the field demonstration of improved techniques for salt dissolution in tanks containing radioactive waste at the Savannal River Site. The tests were designed to investigate three density driven techniques for salt dissolution: (1) Drain-Add-Sit-Remove, (2) Modified Density Gradient, and (3) Continuous Salt Mining. Salt dissolution was observed to be a very rapid process as saturated salt solutions, with a density of approximately 1.4, were frequently removed. Slower addition and removal rates and locating the outlet line at deeper levels below the top of the saltcake provided the best contact between the dissolution water and the saltcake. It was observed that dissolution with 1 M sodium hydroxide solution resulted in salt solutions that were within the current inhibitor requirements for the prevention of stress corrosion cracking. This result was independent of the density driven technique. However, if inhibited water (0.01 M sodium hydroxide and 0.011 M sodium nitrite) was utilized, the salt solutions were frequently outside the inhibitor requirements. Corrosion testing at conditions similar to the environments expected during waste removrd was recommended. Keywords Radioactive waste, carbon steel, stress corrosion cracking
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