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:
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:
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:
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 μm or more and 1200 μm 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:
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 2θ=8.8°±0.5°, 2θ=10.0°±0.5°, and 2θ=29.6°±0.5°.
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 Å 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:
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 μm or more and 1000 μm or less.
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.tH2O wherein y represents a number of more than 0 and less than 1, and q, r and t each represents a number of 0 to 10; wherein the adsorbent is a granular adsorbent having a grain size of 250 μm or more and 1200 μm or less, wherein the absorbent is packed to a height of 10 cm or more and 300 cm or less in 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.