Abstract: An objective of the present disclosure is to provide a method of producing metal compound particle group for an electricity storage device electrode that has an improved rate characteristic, the metal compound particle group, and an electrode formed of the metal compound particle group. The method of producing metal compound particle group applied for an electrode of an electricity storage device, the method includes a step of combining a precursor of metal compound particle with a carbon source to obtain a first composite material, a step of producing the metal compound particle by heat processing the first composite material under a non-oxidizing atmosphere to obtain a second composite material having the metal compound particle combined with carbon, and a step of eliminating carbon by heat processing the second composite material under an oxygen atmosphere to obtain the metal compound particle group having the metal compound particle coupled in a three-dimensional mesh structure.

Abstract: A method for preparing a powder of a solid solution of dioxide of uranium and of at least one other actinide and/or lanthanide element comprising combusting a solution that comprises uranyl nitrate and at least one nitrate of the other actinide and/or lanthanide element and glycine, with the glycine being used in a predetermined amount so as to form, at the end of the combustion, the solid solution.

Abstract: A method for removing sulfate from a wastewater stream includes mixing gibbsite and a calcium source to precipitate Ettringite from the wastewater stream and produce an effluent with a reduced sulfate concentration. The gibbsite in the precipitated Ettringite is regenerated by mixing an acid with the Ettringite and precipitating gibbsite particles, after which the gibbsite particles are subjected to a crystallization process to increase the size of the gibbsite particles which are recycled back to the main stream.

Abstract: A polishing slurry can include zirconia particles. The polishing slurry can be used to polish conductive and insulating materials, and is particularly well suited for polishing oxide materials as well as metals. The characteristics of the zirconia particles can affect the polishing of workpieces. By selecting the proper characteristics, the polishing slurry can have a good material removal rate while still providing an acceptable surface finish. The zirconia particles can be used as a replacement for, or in conjunction with, ceria or other abrasive particles. The content of zirconia particles in the polishing slurry may be less than a comparable polishing slurry having silica or alumina particles.

Abstract: A metal hexaboride nanowire such as LaB6 with the formed metal-terminated (100) plane at the tip has a small work function, and can emit a very narrow electron beam from the (100) plane. In such emitters, contamination occurs in a very short time period, and the output current greatly decreases when used under low temperature. The cold field emitter of the present invention overcomes this problem with a stabilization process that exposes the metal-terminated (100) plane of the tip to hydrogen at low temperature, and can stably operate over extended time periods.

Abstract: The present invention includes a composition of LiF—ThF4—UF4—PuF3 for use as a fuel in a nuclear engine.

Abstract: Method of producing anhydrous thorium(IV) tetrahalide complexes, utilizing Th(NO3)4(H2O)x, where x is at least 4, as a reagent; method of producing thorium-containing complexes utilizing ThCl4(DME)2 as a precursor; method of producing purified ThCl4(ligand)x compounds, where x is from 2 to 9; and novel compounds having the structures:

Abstract: One embodiment of the present disclosure provides a method of making a ceramic material that contains boron and a metal. A metal source, an oxidizer, a boron source, and a fuel source are combined. These reactants are then heated at, or to, a temperature sufficient to initiate a combustion reaction. The combustion reaction produces a ceramic material that includes boron and the metal. The present disclosure also provides materials formed by the disclosed method, as well as methods and systems using such materials.

Abstract: A cubic compound may comprise thorium borate or, in the alternative cerium borate, and may possess a porous supertetrahedral cationic framework with extraframework borate anions. These anions are readily exchanged with a variety of environmental contaminants, especially those from the nuclear industry, including chromate and pertechnetate.

Abstract: A process of producing a ceramic powder including providing a plurality of precursor materials in solution, wherein each of the plurality of precursor materials in solution further comprises at least one constituent ionic species of a ceramic powder, combining the plurality of precursor materials in solution with an onium dicarboxylate precipitant solution to cause co-precipitation of the ceramic powder precursor in a combined solution; and separating the ceramic powder precursor from the combined solution. The process may further include calcining the ceramic powder precursor.

Abstract: Process for manufacturing an electrochemical device including a cathode, an anode and at least one electrolyte membrane disposed between the anode and the cathode, wherein at least one of the cathode, the anode and the electrolyte membrane, contains at least a ceramic material.

Abstract: The present invention provides a nuclear fuel comprising an actinide nitride such as 233U, 234U, 235U, 236U, 238U, 232Th, 239Pu, 240Pu, 241Pu, 242Pu, 244Pu, 239Np, 239Am, 240Am, 241Am, 242Am, 243Am, 244Am, 245Am, 240Cm, 241Cm, 242Cm, 243Cm, 244Cm, 245Cm, 246Cm, 247Cm, 248Cm, 249Cm, 259Cm, 245Bk, 246Bk, 247Bk, 248Bk, 249Bk, 250Bk, 248Cf, 249Cf, 250Cf, 251Cf, 252Cf, 253Cf, 254Cf, 255Cf, 249Es, 250Es, 251Es, 252Es, 253Es, 254Es, 255Es, 251Fm, 252Fm, 253Fm, 254Fm, 255Fm, 256Fm, 257Fm, 255Md, 256Md, 257Md, 258Md, 259Md, 260Md, 253No, 254No, 255No, 256No, 257No, 258No and 259No, and optionally fission products such as 97Tc, 98Tc and 99Tc, suitable for use in nuclear reactors, including those based substantially on thermal fission, such as light and heavy water reactors, gas-cooled nuclear reactors, liquid metal fast breeders or molten salt fast breeders. The fuel contains nitrogen which has been isotopically enriched to at least about 50% 15N, most preferably above 95%.

Abstract: Multi-step metal compound oxidation process to produce compounds and enhanced metal oxides from various source materials, e.g. metal sulfides, carbides, nitrides and other metal containing materials with metal oxides from secondary reaction steps being utilized as an oxidation agent in the first reactions.

Abstract: Process for manufacturing an electrochemical device including a cathode, an anode and at least one electrolyte membrane disposed between the anode and the cathode, wherein at least one of the cathode, the anode and the electrolyte membrane, contains at least a ceramic material.

Abstract: Method for producing metal oxide nanoparticles. The method includes generating an aerosol of solid metallic microparticles, generating plasma with a plasma hot zone at a temperature sufficiently high to vaporize the microparticles into metal vapor, and directing the aerosol into the hot zone of the plasma. The microparticles vaporize in the hot zone into metal vapor. The metal vapor is directed away from the hot zone and into the cooler plasma afterglow where it oxidizes, cools and condenses to form solid metal oxide nanoparticles.

Abstract: The invention relates to a method of synthesizing high-temperature melting materials. More specifically the invention relates to a containerless method of synthesizing very high temperature melting materials such as carbides and transition-metal, lanthanide and actinide oxides, using an aerodynamic levitator and a laser. The object of the invention is to provide a method for synthesizing extremely high-temperature melting materials that are otherwise difficult to produce, without the use of containers, allowing the manipulation of the phase (amorphous/crystalline/metastable) and permitting changes of the environment such as different gaseous compositions.

Abstract: A method of producing metal chlorides is disclosed in which chlorine gas is introduced into liquid Cd. CdCl2 salt is floating on the liquid Cd and as more liquid CdCl2 is formed it separates from the liquid Cd metal and dissolves in the salt. The salt with the CdCl2 dissolved therein contacts a metal which reacts with CdCl2 to form a metal chloride, forming a mixture of metal chloride and CdCl2. After separation of bulk Cd from the salt, by gravitational means, the metal chloride is obtained by distillation which removes CdCl2 and any Cd dissolved in the metal chloride.

Abstract: The invention relates to a process for the preparation of a product based on a phosphate of at least one element M(IV), for example of thorium and/or of actinide(IV)(s). This process comprises the following stages: a) mixing a solution of thorium(IV) and/or of at least one actinide(IV) with a phosphoric acid solution in amounts such that the molar ratio PO 4 M ? ? ( IV ) ?is from 1.4 to 2, b) heating the mixture of the solutions in a closed container at a temperature of 50 to 250° C. in order to precipitate a product comprising a phosphate of at least one element M chosen from thorium(IV) and actinide(IV)s having a P/M molar ratio of 1.5, and c) separating the precipitated product from the solution. The precipitate can be converted to phosphate/diphosphate of thorium and of actinide(s). The process also applies to the separation of uranyl ions from other cations.

Abstract: The invention relates to a method of synthesizing high-temperature melting materials. More specifically the invention relates to a containerless method of synthesizing very high temperature melting materials such as borides, carbides and transition-metal, lanthanide and actinide oxides, using an Aerodynamic Levitator and a laser. The object of the invention is to provide a method for synthesizing extremely high-temperature melting materials that are otherwise difficult to produce, without the use of containers, allowing the manipulation of the phase (amorphous/crystalline/metastable) and permitting changes of the environment such as different gaseous compositions.

Abstract: The invention includes a method of separating isotopes from a mixture containing at least two isotopes in a solution. A first isotope is precipitated and is collected from the solution. A daughter isotope is generated and collected from the first isotope. The invention includes a method of producing an actinium-225/bismuth-213 product from a material containing thorium-229 and thorium-232. A solution is formed containing nitric acid and the material and iodate is added to form a thorium iodate precipitate. A supernatant is separated from the thorium iodate precipitate and a second volume of nitric acid is added to the precipitate. The precipitate is stored and a decay product comprising actinium-225 and bismuth-213 is generated in the second volume of nitric acid which is then separated from the thorium iodate precipitate, filtered, and treated using at least one chromatographic procedure. The invention also includes a system for producing an actinium-225/bismuth-213 product.

Abstract: The synthesis of actinide tetraborides including uranium tetraboride (UB4), plutonium tetraboride (PuB4) and thorium tetraboride (ThB4) by a solid-state metathesis reaction are demonstrated. The present method significantly lowers the temperature required to ≦850° C. As an example, when UCl4 is reacted with an excess of MgB2, at 850° C., crystalline UB4 is formed. Powder X-ray diffraction and ICP-AES data support the reduction of UCl3 as the initial step in the reaction. The UB4 product is purified by washing water and drying.

Abstract: A perovskite feedstock (powder or preform) is placed in a high-pressure cell of a high pressure/high temperature (HP/HT) apparatus and subjected to pressures in excess of about 2 kbar and temperatures above about 800° C. for a time adequate to increase the density of the preform.

Abstract: Ammonia for use in the manufacture of a GaN-type compound semiconductor, filled in a charging container 18 such that at least a part of the ammonia is liquid and the liquid phase ammonia has a water concentration determined by a Fourier-transform infrared spectroscopy (FT-IR) of 0.5 vol ppm or less, is introduced in the gaseous state into a reaction chamber 11 housing therein a substrate 1, and a layer comprising a GaN-type compound started from this ammonia is formed on the substrate 1.

Abstract: Described are preferred polymerized organic-inorganic processes for producing mixed metal oxide powders suitable for use in the ceramics and related industries. The preferred processes employ a non-chelating polymer such as polyvinyl alcohol or polyalkylene glycol as a carrier and can provide single-phase, mixed oxide powders in high yields at relatively low temperatures.

Abstract: The invention relates to a silicon carbide or metal carbide foam to be used as a catalyst or catalyst support for the chemical or petrochemical industry or for silencers, as well as the process for producing the same. The foam is in the form of a three-dimensional network of interconnected cages, whose edge length is between 50 and 500 micrometres, whose density is between 0.03 and 0.1 g/cm3 and whose BET surface is between 20 and 100 m2/g. The carbide foam contains no more than 0.1% by weight residual metal and the size of the carbide crystallites is between 40 and 400 Angstroms. The production process consists of starting with a carbon foam, increasing its specific surface by an activation treatment using carbon dioxide and then contacting the thus activated foam with a volatile compound of the metal, whose carbide it is wished to obtain.

Abstract: A method has been developed for the solution-based metal exchange of carboxylato-alumoxanes [Al(O)x(OH)y(O2CR)z]n with a wide range of metal cations. Metal-exchanged carboxylato-alumoxanes are new, particularly those in which about 10% to about 50% or more of the Al ions are exchanged for other metal ions. Additionally, the carboxylic acid ligands can be stripped from the boehmite core of metal-exchanged carboxylato-alumoxanes at low temperature leading to the formation of metal-exchanged boebmite particles. These new material phases can be used as intermediates for preparation of mixed metal aluminum oxide materials. Thermolysis of the metal-exchanged carboxylato-alumoxanes or metal-exchanged boehmite particles results in doped aluminas (M/Al2O3), binary (MAlOx), ternary (MM′AlOx) and even more complex metal aluminum oxide compounds, where M and M′ are metal ions other than those of aluminum and are preferably those of Lanthanide metals or transition metals.

Abstract: A thermal decomposition method useful in the nuclear industry for preparing a powdered mixture of metal oxides having suitable reactivity from nitrates thereof in the form of an aqueous solution or a mixture of solids. According to the method, the solution or the mixture of solids is thermomechanically contacted with a gaseous fluid in the contact area of a reaction chamber, said gaseous fluid being fed into the reaction chamber at the same time as the solution or mixture at a temperature no lower than the decomposition temperature of the nitrates, and having a mechanical energy high enough to generate a fine spray of the solution or a fine dispersion of the solid mixture, and instantly decompose the nitrates. The resulting oxide mixtures may be used to prepare nuclear fuels.

Abstract: The invention relates to novel thorium phosphates, their preparation process and their use for the storage of radioactive products.These novel thorium phosphates comply with the formulas Th.sub.4 P.sub.6 O.sub.23 (I) or Th.sub.4-x M.sub.4x/v P.sub.6 O.sub.23 (III) in which:M is a monovalent, divalent, trivalent or tetravalent cation,v represents the valency state of the cation and is equal to 1, 2, 3 or 4, andx is such that:0<x.ltoreq.3 when v=40<x.ltoreq.0.26 when v=30<x.ltoreq.0.1 when v=2, and0<x.ltoreq.0.036 when v=1.The cation M can in particular be a radioactive element.

Abstract: A more reactive thoria catalyst for the production of diaryl ethers from aromatic compounds, a process for making the catalyst and the use of the catalyst is taught. The thoria catalyst has a specified surface area, density and average crystal size.

Abstract: A method of removing particulate and other materials from the exhaust gases from an internal combustion engine in which the exhaust gas is passed through a bed of charged ferro-electric materials. Three forms of apparatus for carrying out the method are described.

Abstract: An off-gas quencher and solid recovery scrubber unit includes a wet flue gas scrubber which has the dual responsibilities of lowering the temperature of the inlet hot gas entering through the scrubber and trapping contaminants from the gas stream into the liquid stream. The hot exhaust gases are first cooled by evaporating the liquid scrubber solution. The contaminants of the exhaust gas are neutralized by a suitable reagent such as sodium hydroxide and the product is collected in the scrubbing solution. Since the solution is continuously recycled, the concentration of the scrubbing agent will be diminished as the scrubbing proceeds, while the concentration of the scrubbing product in the solution will rise to the solubility limit of the product. The scrubbing products start to precipitate and are collected at the bottom of the scrubber and are withdrawn. The scrubbing reagents are continuously replenished to the scrubber.

Abstract: A process for the treatment of a material which is or is suspected to contain or carry one or more actinides or compounds thereof to dissolve such actinides or compounds comprises contacting the material with an aqueous solution having a pH in the range 5.5 to 10.5 which is free of heavy metal ions and comprises ingredients which are naturally degradable to non-toxic products with or without mild physical assistance such as heat or ultra-violet radiation, said solution comprising:(a) carbonated water;(b) a conditioning agent;and (c) a complexing agent which comprises the anion of a carboxylic acid having from 2 to 6 carbon atoms.The process may be employed to separate spent nuclear fuel from its metal containment or it may be employed to decontaminate surface, e.g. concrete or soil or pipes carrying traces of actinides, or bulk materials such as soil or rubble.

Abstract: A process for separating a feed mixture of zirconium and petroleum coke containing traces amount of radioative materials by flotation process utilizing a plurality of flotation cells. The process comprises grinding the feed mixture, slurrying the ground feed mixture with water, treating the slurry with a flotation agent and a collector for the coke and subjecting the treated slurry to air sparging and agitation to create an overflow and an underflow. The overflow is then filtered to collect substantially zircon-free coke for further processing.

Abstract: A process of preparing an actinide compound of the formula An.sub.x Z.sub.y wherein An is an actinide metal atom selected from the group consisting of thorium, uranium, plutonium, neptunium, and americium, x is selected from the group consisting of one, two or three, Z is a main group element atom selected from the group consisting of nitrogen, phosphorus, oxygen and sulfur and y is selected from the group consisting of one, two, three or four, by admixing an actinide organometallic precursor wherein said actinide is selected from the group consisting of thorium, uranium, plutonium, neptunium, and americium, a suitable solvent and a protic Lewis base selected from the group consisting of ammonia, phosphine, hydrogen sulfide and water, at temperatures and for time sufficient to form an intermediate actinide complex, heating said intermediate actinide complex at temperatures and for time sufficient to form the actinide compound, and a process of depositing a thin film of such an actinide compound, e.g.

Abstract: Thorium and rare earth values are separated from a fluoride concentrate thereof, by decomposing such concentrate with aqueous sodium hydroxide under conditions such that the amount of sodium hydroxide is at least 1.4 times the stoichiometric amount and the initial sodium hydroxide/water ratio in the medium of decomposition ranges from 1 to 40% by weight, whereby a precipitate of thorium hydroxide and rare earth hydroxides is produced, together with a solution of sodium fluoride, and then separating the NaF solution therefrom.

Abstract: This invention provides a method for the preparation of ultrapure active metal fluorides of increased purity from their metal oxides by reacting an active metal with a predetermined amount of HF(aq) to form a solid reaction product which is dried under controlled heating to form a hydrated fluoride. This hydrated active metal fluoride is then subjected to reactive atmosphere processing comprising hydrofluoric acid vapor in a CO.sub.2 reactive carrier gas and a selected fluoride compound in the gas phase for a predetermined period of time to further increase anion purity.

Abstract: Method for recovery of actinides from nuclear waste material containing sintered and other oxides thereof using O.sub.2 F.sub.2 to generate the hexafluorides of the actinides present therein. The fluorinating agent, O.sub.2 F.sub.2, has been observed to perform the above-described tasks at sufficiently low temperatures that there is virtually no damage to the containment vessels. Moreover, the resulting actinide hexafluorides are not destroyed by high temperature reactions with the walls of the reaction vessel. Dioxygen difluoride is readily prepared, stored and transferred to the place of reaction.

Abstract: A reproducible method and stable binder composition for preserving the induced plasticity of a particulate ceramic material admixture comprising uranium dioxide and a fugitive binder, and product thereof, for subsequent compaction by compressing molding in the manufacture of nuclear fuel pellets.

Abstract: Substantially homogeneous, substantially spherical interdiffused metallic oxide particles, especially useful in plasma spraying applications, are readily and economically prepared from constituent metal oxide powders by the method of this invention which includes the step of heating a mass of discrete agglomerated particles under conditions of temperature and time sufficient to interdiffuse the constituent metallic oxides within the agglomerates, but insufficient to sinter the agglomerates together.

Abstract: A ThO.sub.2 catalyst having a high surface area of about 80-125 m.sup.2 /g is synthesized. The compound is synthesized by simultaneously mixing an aqueous solution of ThNO.sub.3 (NO.sub.3).sub.4.4H.sub.2 O with an aqueous solution of Na.sub.2 CO.sub.3.H.sub.2 O, to produce a solution and solid ThOCO.sub.3. The solid ThOCO.sub.3 is separated from the solution, and then calcined at a temperature of about 225.degree.-300.degree. C. for about 40-55 hours to produce ThO.sub.2. The ThO.sub.2 catalyst produced includes Na present as a substitutional cation in an amount equal to about 5-10 atom percent.

Abstract: The specification discloses a process for the preparation of ultrapure thorium fluoride (ThF.sub.4) having minimized water content and consequent maximized optical transmission of 10.6 micrometer radiation. First, thorium oxide is reacted with aqueous hydrofluoric acid to form a solid reaction product, which is then dried under controlled heating to form a hydrated thorium fluoride with a predetermined amount of hydration, namely ThF.sub.4.xH.sub.2 O where x is equal to 0.39. The hydrated thorium fluoride is exposed to a reactive atmosphere of hydrofluoric acid vapor and a selected fluoride compound in the gas phase at elevated temperature for a predetermined period of time. The reactive atmosphere removes substantially all of the water and water-derived impurities from the hydrated thorium fluoride to produce ultrapure thorium fluoride which is highly transmissive to 10.6 micrometer radiation.

Abstract: A method of chemically separating plutonium from thorium. Plutonium and thorium to be separated are dissolved in an aqueous feed solution, preferably as the nitrate salts. The feed solution is acidified and sodium nitrite is added to the solution to adjust the valence of the plutonium to the +4 state. A chloride salt, preferably sodium chloride, is then added to the solution to induce formation of an anionic plutonium chloride complex. The anionic plutonium chloride complex and the thorium in solution are then separated by ion exchange on a strong base anion exchange column.

Abstract: Dissolving hard-to-dissolve nuclear fuels such as ThO.sub.2 and PuO.sub.2 in a nitric acid fission material solution which contains nitric acid and a Pu-fluoride complex to provide free fluorine ions in a small catalytically active amount due to small dissociation of fluoride ions from the Pu-fluoride complex. This permits dissolving hard-to-dissolve nuclear fuels in normal metallic dissolving vessels and also eliminates need for using polytetrafluoroethylene.

Abstract: Spent nuclear fuels, including actinide fuels, volatile and non-volatile fission products, are reprocessed and separated in a molten metal solvent housed in a separation vessel made of a carbon-containing material. A first catalyst, which promotes the solubility and permeability of carbon in the metal solvent, is included. By increasing the solubility and permeability of the carbon in the solvent, the rate at which actinide oxides are reduced (carbothermic reduction) is greatly increased. A second catalyst, included to increase the affinity for nitrogen in the metal solvent, is added to increase the rate at which actinide nitrides form after carbothermic reduction is complete.

Abstract: A method for the heat treatment of a radioactive substance by microwave power comprising preparing a nitrate solution of uranium, thorium, plutonium or a mixture thereof, and applying to the nitrate solution microwave energy sufficient to directly convert the nitrate solution into an oxide powder of uranium, thorium, plutonium or a mixture thereof, respectively. Such oxide powder is suitable for the manufacture of nuclear fuel pellets.

Abstract: A method of treating a nuclear reactor fuel pellet which has been irradiated and is at least partially depleted of its initial fissile material content to substantially reduce the amount of fuel which would have to be reprocessed before it could be reused. The pellet is pulverized to a median particle size of less than about 300 microns and thereafter is separated into two fractions by size. In accordance with the present invention, it has been found that one of said fractions will contain a significantly greater proportion of the fissile content of the pellet than the other of said fractions. The fissile-rich fraction is suitable for reforming into pellets for use in a nuclear reactor with little or no further enrichment required. The method of the present invention is applicable to the metallic, oxide, and carboxide forms of nuclear reactor fuels such as uranium and thorium, which have been in service in a light water reactor or a fast breeder reactor.

Abstract: Process waste waters at a pH of about 7 contaminated with radioactive isotopes are decontaminated by (a) adjusting the pH to about 5.8, (b) adding CaO or Ca(OH).sub.2 to raise the pH to about 8.5, (c) agitating the mixture for at least 5 minutes to effect intimate contact and produce a suspension of solids containing radioactive contaminants, and (d) separating the suspension of solids from the water by centrifuging. Removal of radioactive uranium isotopes with an alpha emission is effected at a pH of about 10. The process provides a method for concentrating radioactive contaminants in water for subsequent ultimate storage and also purifies the contaminated water so it may be safe to discharge it into the sewer. The treatment may be carried out in a plurality of stages in series.

Abstract: A hydride of the gross formula AB.sub.n H.sub.m, in which A is calcium or one or more of the rare earth metals with or without thorium, zirconium, or hafnium, B is nickel and/or cobalt, with or without iron and/or copper, n has a value between about 3 and 8.5 and m has a value up to about 7.

Abstract: Novel compounds or compositions are provided capable of serving as solid electrolytes involving intercalated dichalcogenides having a combination of a tetravalent metal ion with a metal ion of lower oxidation state and a compensating amount of alkali metal ions to provide a substantially electrically neutral structure. The compositions have the formula:A.sub.x M.sub.x T.sub.1-x X.sub.2where A is an alkali metal ion, M is a metal ion of lower valence state than T, T is a metal capable of forming a stable substantially electrically non-conductive intercalatable chalcogenide and X is a chalogen. Also included are batteries employing the subject compositions as the solid electrolyte.

Abstract: A process and products produced thereby, e.g., alumina tools, in which ceramic powder particles are subjected to high transmissive energy milling under dry conditions and with given ratios of impacting media to powder, the milling being conducted for a period beyond the threshold point of the powder constituents, whereby dense, composite powder particles are obtained having an interdispersion of initial constituent particles, a large internal interfacial surface within individual product powder particles, etc.