Ion exchange and electrodialysis in liquid radioactive-waste decontamination

Rauzen, F. V.; Kuleshov, N. F.; Trushkov, N. P.; Dudnik, S. N.

doi:10.1007/bf01120594

Cited by 4 publications

(1 citation statement)

References 1 publication

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“…This process replaces high molecular weight organic ion-exchange resins with partially sulfurated bitumen and various inorganic sorbents. Although this technique will give solutions that are activity free to acceptable standards, it has a number of shortcomings--one of which is the need to reprocess a large volume of regeneration solutions if the content of the salts in the initial solutions is greater than 0.5 to 1 g/l (Rauzen and Trushkov 1972).…”

Section: Foam Separationmentioning

confidence: 99%

Decontamination Processes for Restorative Operations and as a Precursor to Decommissioning: A Literature Review

Nelson¹,

Divine²

1981

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Pacific Northwest Laboratory (PNL) conducted an comprehensive literature review of actual reactor decontamination processes that are currently available. In general, any decontamination process should be based on the following criteria: effectiveness, efficiency, safety, and waste production. The information that was collected and analyzed has been divided into three major categories of decontamination: chemical, mechanical, and electrochemical. Chemical methods can be further classified as either low-concentration, singlestep processes or high-concentration, single-or multistep processes. Numerous chemical decontamination methods are detailed. Mechanical decontamination methods are usually restricted to the removal of a contaminated surface layer, whlch limits their versatility; several mechanical decontamination methods are described. Electrochemical decontamination. is both fast and easily controlled, and numerous processes that have been used in industry for many years are discussed. Information obtained from this work is tabulated in Appendix A for easy access, and a bibliography and a glossary have been provided. v SUMMARY There is an increasing realization by the public and the nuclear industry that decontamination of nuclear facilities is necessary for both continued operations and decommissioning. Processes used as a precursor to decommissioning may include more destructive measures than allowable for facilities that will be restored to operation; however, they are expected to have the potential for a greater degree of decontamination.This report is the result of a comprehensive literature review wherein the authors have collected and analyzed information on actual decontamination processes that are currently available. Processes that are acceptable for the primary system are reviewed, as are those that are acceptable for interior structural members (such as concrete or painted surfaces) and for exterior locations (such as concrete or soil). Applicability is based on such factors as extent of decontamination, corrosiveness, waste produced, and time required for application. Decontamination of activated materials such as fuel-cladding and bio-shield components is beyond the scope of this program except for possible removal of loose surface deposits.The information presented in this report is also tabulated in Appendix A for easy access. The information has been divided into three major groups: chemical decontamination methods, mechanical decontamination methods, and electrochemical decontamination methods.Chemical methods are further subdivided into low-concentration, singlestep processes and high-concentration, single-or multistep processes. Within these classifications the chemical processes can be summarized into six groups:• high pH oxidation and dissolution • high pH oxidation followed by low pH dissolution • low pH oxidation and dissolution • low pH oxidation followed by low pH dissolution • low pH dissolution • low pH reduction and dissolution.vii Mechanical decontamination methods usually...

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Section: Foam Separationmentioning

confidence: 99%

Decontamination Processes for Restorative Operations and as a Precursor to Decommissioning: A Literature Review

Nelson¹,

Divine²

1981

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Electrodialysis

Delyannis

1980

Seawater and Desalting

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A low-waste technology for treating discharged water from Mayak pond No. 9

Мартынов¹,

Tugolukov²,

Egorov³

et al. 1998

At Energy

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66.064At present, there are several open stores for liquid radioactive wastes in the region of the Mayak organization. The stores for low-activity wastes are certain ponds in the valley of the R. Tech. However, the main hazard is represented by liquid wastes stored in Lake Karachai (pool No. 9), to which medium-activity solutions have been discharged since 1951. The water leaking from pool No. 9 causes a danger of radioactive pollution in water-supply sources and represents a hazard on passage to the open river network [1]. This hazard can be avoided by halting the motion of the polluted water towards the pools or trapping it and purifying it from radionuclides and dissolved salts until it meets discharge standards.These infiltrating waters from pool No. 9 constitute a multicomponent system having total salt contents up to 80 g/liter, 90% of which is accounted for by sodium nitrate. The radioisotopes are mainly 9~ 137Cs, and 6~ The total radioactivity is up to 1.5-105 Bq/liter. There are difficulties in using standard treatment methods [2, 3] for liquid radioactive wastes in these waters because they do not provide the necessary degree of purification, consume large amounts of reagents and energy, and are complicated to implement. It has been shown [4] that electromembrane methods in combination with others are effective for treating radioactive wastes produced at the nuclear fleet installations.We consider that electromembrane technology is best for treating these waters, which includes electrochemical precipitation of the hardness salts and polyvalent metals, electroosmotic concentration, and electrodialysis desalination. Experience exists in treating radioactive wastes by electromembrane methods, which suggests that one should include an electromembrane apparatus of EKhO type intended for the electrochemical precipitation of hydroxides and carbonates, which enables one to eliminate hardness salts and heavy-metal ions from the wastes by means of electrochemical processes. Figure 1 shows the block diagram of a laboratory apparatus handling 2 liter/la for treating liquid wastes whose composition is given in Table 1.The cathode chamber of the EKhO apparatus accumulates hydroxyl ions by the electrolysis of water: H20 + 2e ---H 2 + OH, and the bicarbonate ions become carbonate ones HCO 3 + OH --, CO 3-2 + H20, and sparingly soluble calcium carbonates (SPcacO 3 4.3" 10 -9) and magnesium hydroxide (SPMg(OH) 2 5.5-10 -12) are precipitated along with the carbonate and hydroxides of other heavy metals.

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Ion exchange and electrodialysis in liquid radioactive-waste decontamination

Cited by 4 publications

References 1 publication

Decontamination Processes for Restorative Operations and as a Precursor to Decommissioning: A Literature Review

Decontamination Processes for Restorative Operations and as a Precursor to Decommissioning: A Literature Review

Electrodialysis

A low-waste technology for treating discharged water from Mayak pond No. 9

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