B01D2251/408

SYSTEMS AND METHODS FOR PREVENTING CHROMIUM CONTAMINATION OF SOLID OXIDE FUEL CELLS
20170187048 · 2017-06-29 ·

In some embodiments, a solid oxide fuel system is provided. The solid oxide fuel cell system may include a chromium-getter material. The chromium-getter material may react with chromium to remove chromium species from chromium vapor. The solid oxide fuel cell system may also include an inert substrate. The chromium-getter material may be coated onto the inert substrate. The coated substrate may remove chromium species from chromium vapor before the chromium species can react with a cathode in the solid oxide fuel cell system.

METHODS AND SYSTEMS FOR TOTAL ORGANIC CARBON REMOVAL
20170173531 · 2017-06-22 ·

A hydrocarbons removal system and methods and uses thereof are described. The hydrocarbons removal system can comprise at least one sulfur trap and an oxidation catalyst.

Method for maturing meat

The invention concerns a method for the storage and/or aging of meat in which raw meat is stored in the presence of an alkaline and/or alkaline earth metal carbonate, which is made available in a matrix (1) of aligned and/or non-aligned fibers (2), and an element for use in the storage and/or aging of meat, which comprises a layer of ordered and/or unordered fibers and optionally further layers, which element contains alkaline and/or alkaline earth metal carbonates and/or hydrogen carbonates. By means of the claimed method, aging of raw meat can be carried out in a simple manner without having to give up the taste quality achieved by dry aging.

Exhaust system having N2O catalyst in EGR circuit

An exhaust system for an internal combustion engine is disclosed. The exhaust system comprises a particulate filter, one or more NO.sub.x reduction catalysts, and a low pressure exhaust gas recirculation (EGR) circuit for connecting the exhaust system downstream of the filter and the one or more NO.sub.x reduction catalysts to an intake of the engine. The EGR circuit comprises a N.sub.2O-producing catalyst.

Carbon dioxide adsorbent

Provided is a carbon dioxide adsorbent with which large quantities of carbon dioxide can be adsorbed and removed even under conditions having low carbon dioxide concentrations such as when under subatmospheric pressure or when under an environment having a carbon dioxide partial pressure of less than atmospheric pressure, said carbon dioxide adsorbent exhibiting excellent adsorption activity. A carbon dioxide adsorbent including at least a ZSM-5 zeolite including barium (Ba) or strontium (Sr) is characterized in that the ZSM-5 zeolite includes M-O-M bonds (M being Ba or Sr, and O being oxygen). The M-O-M bonds interact strongly with carbon dioxide, and thus carbon dioxide can be adsorbed effectively and in large volumes even under conditions having low carbon dioxide concentrations.

Systems and methods for preventing chromium contamination of solid oxide fuel cells
09559366 · 2017-01-31 · ·

In some embodiments, a solid oxide fuel system is provided. The solid oxide fuel cell system may include a chromium-getter material. The chromium-getter material may react with chromium to remove chromium species from chromium vapor. The solid oxide fuel cell system may also include an inert substrate. The chromium-getter material may be coated onto the inert substrate. The coated substrate may remove chromium species from chromium vapor before the chromium species can react with a cathode in the solid oxide fuel cell system.

Methods for Extracting Radioisotopes from Radiologically Contaminated Waste

Methods are provided for separating radioisotopes from spent ion exchange resins used to process nuclear waste. In some embodiments, the resin is contacted with an aqueous solution including one or more acids to elute the radioisotopes into an enriched solution. In some embodiments, the resin is contacted with an aqueous solution including one or more salts, such as a sulfate or nitrate salt solution, to elute the radioisotopes into an enriched salt solution. The enriched solution can include at least 80%, or at least 95%, of the activity of radioisotopes such as Sr-90, Co-60, Ni-63, Cs-137, C-14, Co-58, and/or Mn-54 originally present in the resin. In some embodiments, a mixed bed resin is separated into cation and anion components, and the anion resin is treated to release C-14 as carbon dioxide gas which is captured and purified to obtain a C-14 product.

Methods for extracting radioisotopes from radiologically contaminated waste

Methods are provided for separating radioisotopes from spent ion exchange resins used to process nuclear waste. In some embodiments, the resin is contacted with an aqueous solution including one or more acids to elute the radioisotopes into an enriched solution. In some embodiments, the resin is contacted with an aqueous solution including one or more salts, such as a sulfate or nitrate salt solution, to elute the radioisotopes into an enriched salt solution. The enriched solution can include at least 80%, or at least 95%, of the activity of radioisotopes such as Sr-90, Co-60, Ni-63, Cs-137, C-14, Co-58, and/or Mn-54 originally present in the resin. In some embodiments, a mixed bed resin is separated into cation and anion components, and the anion resin is treated to release C-14 as carbon dioxide gas which is captured and purified to obtain a C-14 product.

Method for treating carbon dioxide contained in natural gas and aqueous dispersion used therein
12516261 · 2026-01-06 · ·

There is provided with a carbon dioxide treating method capable of suppressing a decrease in the content of a hydrocarbon contained in natural gas before and after removal of carbon dioxide. A method for treating carbon dioxide contained in natural gas comprises: preparing an aqueous dispersion containing magnesium hydroxide and acetonitrile; bringing the aqueous dispersion and the natural gas into contact with each other; and making the magnesium hydroxide and the carbon dioxide react with each other, wherein the aqueous dispersion further contains metal hydroxides, and the metal hydroxides include barium hydroxide, zinc hydroxide, sodium hydroxide, and calcium hydroxide.

Methods for Extracting Radioisotopes from Radiologically Contaminated Waste

Methods are provided for separating radioisotopes from spent ion exchange resins used to process nuclear waste. In some embodiments, the resin is contacted with an aqueous solution including one or more acids to elute the radioisotopes into an enriched solution. In some embodiments, the resin is contacted with an aqueous solution including one or more salts, such as a sulfate or nitrate salt solution, to elute the radioisotopes into an enriched salt solution. The enriched solution can include at least 80%, or at least 95%, of the activity of radioisotopes such as Sr-90, Co-60, Ni-63, Cs-137, C-14, Co-58, and/or Mn-54 originally present in the resin. In some embodiments, a mixed bed resin is separated into cation and anion components, and the anion resin is treated to release C-14 as carbon dioxide gas which is captured and purified to obtain a C-14 product.