An apparatus for dehalogenating an aqueous salt solution may include a tank, an electrode pair positioned at least partially within the tank, and an aerator positioned at least partially below an anode of the electrode pair. An inlet of the tank may be configured to introduce the aqueous salt solution into the tank, and as the aqueous salt solution contacts the electrode pair that may include a voltage potential between the anode and cathode, electrolysis occurs and the halogens in the aqueous salt solution, e.g. chloride, may be oxidized at the anode. The aerator may be configured to sweep the halogens to the top of the tank.

The present invention pertains to a process for treating waste water from mining. The process involves contacting the mining waste water with an emulsion of a nano scale compound comprising iron, magnesium, or both. Mixing results in a substantially foam-like layer at the surface of the mixture which may be further oxidized to form treated water.

The present invention pertains to a process for treating waste water from mining. The process involves contacting the mining waste water with an emulsion of a nano scale compound comprising iron, magnesium, or both. Mixing results in a substantially foam-like layer at the surface of the mixture which may be further oxidized to form treated water.

Improved methods for the removal of heavy metals, in particular cadmium, from an aqueous phosphoric acid containing composition, wherein an organothiophosphorous heavy metal precipitating agent and an ionic polymeric surfactant, particularly a cationic polyacrylamide copolymer surfactant, are both added to a phosphoric acid containing composition, particularly under vigorous mixing conditions, such as between 500 and 700 rpm. The ionic polymeric surfactant promotes the precipitation of the heavy metals. More in particular, the phosphoric acid containing composition is obtained by the acid digestion of phosphate rock, preferably by nitric acid, sulfuric acid, or a combination thereof.

A waste treatment process utilizes a two-stage digestion process with a thermophilic digester, a heat exchanger, and a mesophilic digester. The pH of the thermophilic digestate is increased by removal of carbon dioxide with an air stripper, or by adding a pH increasing reagent upstream of the heat exchanger. The pH adjustment of the digestate protects the heat exchanger and downstream equipment and processes from struvite formation. A struvite reactor may be located in various locations downstream of the heat exchanger to produce a treated digestate or effluent that contains struvite, which can optionally be recovered for beneficial use.

The present disclosure relates to a solid and hydrolyzable tablet for treating contaminated water. The tablet comprises at least one an active ingredient chosen from a precipitating agent, alone or in combination with an agglomerating agent. The disclosure also relates to the use of a tablet for treating contaminated water. The disclosure also relates to a method and a device for treating contaminated water. The method comprises placing water laden with contaminant in contact with a precipitating agent and/or an agglomerating agent, dissolving these agents, mixing these dissolved agents with the water laden with contaminant so as to precipitate and/or agglomerate the contaminant, then separating said contaminant so as to obtain treated water.

The invention relates to technology for processing liquid radioactive waste containing, inter alia, tritium isotopes, which are formed in various nuclear industry plants, and also during decommissioning of such plants. The technical result of the claimed invention consists in simplifying the technological procedure for processing liquid radioactive waste containing, inter alia, tritium isotopes by excluding complicated and lengthy operations associated with testing a concrete mixture produced from deactivated liquid radioactive waste, and also in increasing the ecological safety by reducing the size of areas for storage of the waste produced during the processing of the liquid radioactive waste. The claimed technical result is achieved in that a method for processing liquid radioactive waste containing, inter alia, tritium isotopes involves removing radioactive substances from the liquid radioactive waste so as to produce a low-level waste solution, and introducing a binder into the low-level waste solution produced in order to prepare a concrete mixture which complies with structural, radioecological, and sanitary and hygiene requirements, wherein components that have a negative effect on the technical characteristics of the concrete mixture being produced are removed from the low-level waste solution before the binder is added.

Embodiments of the present invention are generally related to a system and method to remove hydrogen sulfide from sour water and sour oil. Particularly, hydrogen sulfide is removed from sour water and sour oil without the need for special chemicals, such as catalyst chemicals, scavenger chemicals, hydrocarbon sources, or a large-scale facility. The system and method in the present invention is particularly useful in exploratory oil and gas fields, where large facilities to remove hydrogen sulfide may be inaccessible. The present invention addresses the need for safe and cost-effective transport of the deadly neurotoxin. Particular embodiments involve a system and method that can be executed both on a small and large scale to sweeten sour water and sour oil.

A system and method for treating reverse-osmosis (RO) concentrated water with high temporary hardness. The system includes a crystallization unit, a precipitation unit, a dewatering unit, and a programmable logic controller (PLC) system. The crystallization unit, precipitation unit and dewatering unit are connected in series, and the PLC system is configured to control pumps, valves, and displays in the crystallization unit, precipitation unit and dewatering unit. The crystallization unit includes a storage tank and a crystallization reactor communicated therewith. The crystallization reactor is provided with a pH meter, a liquid-level gauge, and a stirrer. A connection pipe between the crystallization reactor and the RO concentrated water is provided with an inlet pump and a inlet valve. A connection pipe between the crystallization reactor and the storage tank is provided with a feeding pump and a feeding valve.

A condensate chamber is a housing having an inlet, an outlet, a base, a top wall, and upstanding sidewalls. The upstanding sidewalls include a first end sidewall, a second end sidewall, a first side sidewall, and a second side sidewall. A divider is disposed within the housing and includes a proximal end disposed against the first end sidewall and extends towards the second end sidewall. A gap is defined in between a distal end of the divider and the second end sidewall. The divider defines a serpentine channel within the housing starting at the inlet and ending at the outlet.