Abstract: Provided are a silicotitanate molded body having high strength and reduced generation of fine powder, a production method thereof, an adsorbent comprising the silicotitanate molded body, and a decontamination method of radioactive cesium and/or radioactive strontium by using the adsorbent. The silicotitanate molded body comprises: crystalline silicotitanate particles that have a particle size distribution in which 90% or more, on volume basis, of the particles have a particle size within a range of 1 ?m or more and 10 ?m or less and that are represented by a general formula of A2Ti2O3(SiO4).nH2O wherein A represents one or two alkali metal elements selected from Na and K, and n represents a number of 0 to 2; and an oxide of one or more elements selected from the group consisting of aluminum, zirconium, iron, and cerium.

Abstract: There is provided a regenerated member of a nickel-based alloy member for use in a turbine. The nickel-based alloy member is in a used condition. The regenerated member is a nickel-based alloy cast article including a ? phase as a matrix and a ?? phase precipitating in the ? phase in a volume fraction of equal to or more than 30 vol % in an operational environment of the turbine. In a microstructure of the regenerated member, no recrystallized grains of the ? phase are present. And, when a GROD value of crystal grains of the ? phase of the used part undergone the solution/non-recrystallization heat treatment step is measured by electron back scattering diffraction analysis, the GROD value is equal to or more than 0.4° and equal to or less than 0.6°.

Abstract: Provided is a particulate alkaline earth metal ion adsorbent having a large adsorption capacity. The particulate alkaline earth metal ion adsorbent comprising: a potassium hydrogen dititanate hydrate represented by a chemical formula K2-xHxO.2TiO2.nH2O, wherein x is 0.5 or more and 1.3 or less, and n is greater than 0; and no binder, wherein the particulate alkaline earth metal ion adsorbent has a particle size range of 150 ?m or more and 1000 ?m or less.

Abstract: An adsorbent is provided to adsorb ruthenium from aqueous solution for recovery and/or reuse or removal of said ruthenium, and a method for purifying, for example, sea water and/or water containing sodium ions, magnesium ions, calcium ions, chlorine ions or other ions, polluted with a radioactive element, using said adsorbent. The ruthenium adsorbent includes manganese in the form of oxides thereof. The adsorbent can further include at least one additional transition metal element other than manganese, such as copper. The adsorbent soaked in water removes radioactive ruthenium or the like through adsorption, and thereby can purify, for example, sea water and/or water containing sodium ions, magnesium ions, calcium ions, chlorine ions or other ions.

Abstract: Provided are an adsorbent capable of removing radioactive water liquid including iodine compounds and/or antimony by means of a water passing treatment, and a method and an apparatus for treating radioactive waste liquid by using the adsorbent. The adsorbent includes a polymer resin and 10 parts by weight or more of a hydrous hydroxide of a rare earth element based on 100 parts by weight of the polymer resin, in which the hydrous hydroxide of the rare earth element has a water content of 1 part by weight to 30 parts by weight based on 100 parts by weight of a dry product thereof, and adsorbs iodine compounds and/or antimony.

Abstract: There is provided a regenerated member of a nickel-based alloy member for use in a turbine. The nickel-based alloy member is a used member having been operated for a predetermined period of time in the turbine. The regenerated member is a nickel-based alloy unidirectional solidification article or single crystalline solidification article including a ? phase as a matrix and a ?? phase precipitating in the ? phase in a volume fraction of 30 volume % or more in an operational environment of the turbine. In a microstructure of the regenerated member, no recrystallized grains of the ? phase are present. And, when a rocking curve of a predetermined crystal face of the ? phase crystal grain of the used member undergone the solution/non-recrystallization heat treatment step is measured by an XRD technique, a FWHM of the rocking curve is within a range from 0.25° to 0.30°.

Abstract: The present invention provides a composition that includes a silicotitanate that has a sitinakite structure, the composition having higher cesium adsorptivity than conventional compositions. The present invention also provides a production method for the composition that includes a silicotitanate that has a sitinakite structure. The production method does not require the use of hazardous or deleterious materials, can generate a product using a compound that is easily acquired, and can use a general-purpose autoclave. Also provided is a silicotitanate composition that has higher strontium adsorptivity than the present invention. Provided is a silicotitanate composition that contains niobium and a silicotitanate that has a sitinakite structure, the composition having at least two or more diffraction peaks selected from the group consisting of 2?=8.8°±0.5°, 2?=10.0°±0.5°, and 2?=29.6°±0.5°.

Abstract: The present invention provides a treatment method of a radioactive iodine-containing fluid, comprising passing the radioactive iodine-containing fluid through an adsorbent for iodine consisting of a silver-containing binderless zeolite molded body having a silver content of 50 mass % or less, to adsorb the radioactive iodine on the adsorbent for iodine.

Abstract: The present invention provides a treatment method of radioactive waste water containing radioactive cesium and radioactive strontium, comprising passing the radioactive waste water containing radioactive cesium and radioactive strontium through an adsorption column packed with an adsorbent for cesium and strontium, to adsorb the radioactive cesium and radioactive strontium on the adsorbent, wherein the adsorbent for cesium and strontium comprises: at least one selected from crystalline silicotitanates represented by the general formulas: Na4Ti4Si3O16.nH2O, (NaxK(1-x))4Ti4Si3O16.mH2O and K4Ti4Si3O16.lH2O wherein x represents a number of more than 0 and less than 1, and n, m and l each represents a number of 0 to 8; and at least one selected from titanate salts represented by the general formulas: Na4Ti9O20.qH2O, (NayK(1-y))4Ti9O20.rH2O and K4Ti9O20.

Abstract: An adsorbent capable of adsorbing radioactive antimony, radioactive iodine and radioactive ruthenium, the adsorbent containing cerium(IV) hydroxide in a particle or granular form having a particle size of 250 ?m or more and 1200 ?m or less; and a treatment method of radioactive waste water containing radioactive antimony, radioactive iodine and radioactive ruthenium, the treatment method comprising passing the radioactive waste water containing radioactive antimony, radioactive iodine and radioactive ruthenium through an adsorption column packed with the adsorbent, to adsorb the radioactive antimony, radioactive iodine and radioactive ruthenium on the adsorbent, wherein the absorbent is packed to a height of 10 cm or more and 300 cm or less of the adsorption column, and wherein the radioactive waste water is passed through the adsorption column at a linear velocity (LV) of 1 m/h or more and 40 m/h or less and a space velocity (SV) of 200 h?1 or less.

Abstract: A treatment method of radioactive waste water containing radioactive cesium and radioactive strontium, comprising passing the radioactive waste water containing radioactive cesium and radioactive strontium through an adsorption column packed with an adsorbent for cesium and strontium, to adsorb the radioactive cesium and radioactive strontium on the adsorbent, wherein the adsorbent for cesium or strontium comprises a crystalline silicotitanate having a crystallite diameter of 60 ? or more and having a half width of 0.9° or less of the diffraction peak in the lattice plane (100), the crystalline silicotitanate represented by the general formula: A4Ti4Si3O16.nH2O.

Abstract: A purification method for spent fuel pool water from nuclear power generation, the method comprising: passing the water at a linear flow velocity of 50 m/h or less through a purification apparatus for the water comprising an ion exchange resin layer and a metal-doped resin layer which is laid at a bed height of 2 cm or more on a surface layer of the ion exchange resin layer wherein the water to be treated is contacted with the metal-doped resin layer to decompose a pro-oxidant contained in the water; and subsequently contacting the water with the ion exchange resin.

Abstract: A method for purifying water in a spent fuel pool in a nuclear power plant, the method including passing the water at a linear flow velocity of 50 m/h or less through a purification apparatus. The apparatus includes an ion exchange resin layer and a metal-doped resin layer laid at a bed height of 2 cm or more on a surface layer of the ion exchange resin layer. The method includes contacting the water with the metal-doped resin layer to decompose a pro-oxidant contained in the water and subsequently contacting the water with the ion exchange resin to produce purified water.

Abstract: Provided are an adsorbent capable of removing radioactive water liquid including iodine compounds and/or antimony by means of a water passing treatment, and a method and an apparatus for treating radioactive waste liquid by using the adsorbent. The adsorbent includes a polymer resin and 10 parts by weight or more of a hydrous hydroxide of a rare earth element based on 100 parts by weight of the polymer resin, in which the hydrous hydroxide of the rare earth element has a water content of 1 part by weight to 30 parts by weight based on 100 parts by weight of a dry product thereof, and adsorbs iodine compounds and/or antimony.

Abstract: There is provided a regenerated member of a nickel-based alloy member for use in a turbine. The nickel-based alloy member is in a used condition. The regenerated member is a nickel-based alloy cast article including a ? phase as a matrix and a ?? phase precipitating in the ? phase in a volume fraction of equal to or more than 30 vol % in an operational environment of the turbine. In a microstructure of the regenerated member, no recrystallized grains of the ? phase are present. And, when a GROD value of crystal grains of the ? phase of the used part undergone the solution/non-recrystallization heat treatment step is measured by electron back scattering diffraction analysis, the GROD value is equal to or more than 0.4° and equal to or less than 0.6°.

Abstract: An adsorbent is provided to adsorb ruthenium from aqueous solution for recovery and/or reuse or removal of said ruthenium, and a method for purifying, for example, sea water and/or water containing sodium ions, magnesium ions, calcium ions, chlorine ions or other ions, polluted with a radioactive element, using said adsorbent. The ruthenium adsorbent includes manganese in the form of oxides thereof. The adsorbent can further include at least one additional transition metal element other than manganese, such as copper. The adsorbent soaked in water removes radioactive ruthenium or the like through adsorption, and thereby can purify, for example, sea water and/or water containing sodium ions, magnesium ions, calcium ions, chlorine ions or other ions.

Abstract: This method is a method for manufacturing a gas turbine blade, including: producing a gas turbine blade having a cooling pass inside thereof; and partially coating an inner surface of the cooling pass with Al. The step of partially coating an inner surface of the cooling pass with Al further including: a first step of specifying a temperature range which satisfies both of oxidation resistance and fatigue strength and the temperature distribution of the inner surface of the cooling pass based on an examination result or result of a numerical analysis; a second step of setting an Al-coating-applying portion of the inner surface of the cooling pass as the temperature range specified at the first step; and a third step of applying Al coating only into the set Al-coating-applying portion.

Abstract: A condensate demineralization method for a condensate treatment of a nuclear power generation plant, including: passing condensate at a linear flow rate ranging from 20 m/h to 200 m/h through a condensate demineralization apparatus comprising an ion exchange resin layer filled therein wherein the ion exchange resin layer includes a mixed bed of a strongly acidic cation resin and a strongly basic anion resin and a metal doped resin in a volume ratio ranging from 2% to 50% relative to the mixed bed.

Abstract: There is provided a method for forming an aluminide coating on a surface of a heat resistant superalloy substrate, comprising the steps of: exposing a base metal of the substrate in a selective area; forming a aluminum or an aluminum alloy film on the exposed base metal, by a non-aqueous electroplating; and conducting a heat treatment to the substrate on which the film is formed, in order to make a diffusion reaction between an aluminum component in the film and the base metal, and form the aluminide coating, wherein: there is used, as a plating liquid, a non-aqueous plating liquid containing a halide of the metal to be plated and an organic compound which forms an ion pair with the metal halide; and the electroplating is conducted by immersing the selective area into the plating liquid through the use of predetermined means for shielding the plating liquid from the atmosphere.

Abstract: A purification method for spent fuel pool water from nuclear power generation, the method comprising: passing the water at a linear flow velocity of 50 m/h or less through a purification apparatus for the water comprising an ion exchange resin layer and a metal-doped resin layer which is laid at a bed height of 2 cm or more on a surface layer of the ion exchange resin layer wherein the water to be treated is contacted with the metal-doped resin layer to decompose a pro-oxidant contained in the water; and subsequently contacting the water with the ion exchange resin.