Patent Number: 052563383
Section: claims

1. A solidifying material for disposal of radioactive wastes in solidified waste form which comprises a mixture of a cement type hydraulic solidifying material and a fibrous material having a property to adsorb radioactive nuclides in the radioactive waste in the form of ion and/or molecule onto its surface, and to increase retention of the radioactive wastes within said waste form; the fibrous material also having a property to increase the tensile strength of the waste form, thereby increasing the waste loading within said waste form. 2. A structure for disposal of radioactive wastes at least a part of which is made of a cement type hydraulic solidifying material wherein said cement type hydraulic solidifying material contains a fibrous material having a property to adsorb radioactive nuclides in the radioactive wastes in the form of ion and/or molecule onto its surface, and to increase retention of the radioactive wastes in said structure; said fibrous material also having property to increase the tensile strength of said structure, thereby increasing the waste loading in said structure. 3. A structure according to claim 2, wherein the structure is a waste container for radioactive wastes at least a part of which is composed of the cement type hydraulic solidifying material. 4. A structure according to claim 2, wherein said structure is a structure in a disposal site for radioactive wastes at least a part of which is composed of the cement type hydraulic solidifying material. 5. A solidifying material according to claim 1, wherein the fibrous material having a property to adsorb radioactive nuclides in the form of ion and/or molecule onto its surface is at least one member selected from the group consisting of fibrous active carbon, ion exchange fibers, and alkali metal titanate fibers. 6. A structure according to claim 2, wherein the fibrous material having a property to adsorb radioactive nuclides in the form of ion and/or molecule onto its surface is at least one member selected from the group consisting of fibrous active carbon, ion exchange fibers, and alkali metal titanate fibers. 7. A solidifying material according to claim 1, wherein the fibrous material having a property to adsorb radioactive nuclides in the form of ion and/or molecule onto its surface is fibrous active carbon and has an aspect ratio of 200-300. 8. A structure according to claim 2, wherein the fibrous material having a property to adsorb radioactive nuclides in the form of ion and/or molecule onto its surface is fibrous active carbon and has an aspect ratio of 200-300. 9. A solidifying material according to claim 1, wherein the fibrous material having a property to adsorb radioactive nuclides in the form of ion and/or molecule onto its surface is fibrous active carbon having micropores on its surface. 10. A structure according to claim 2, wherein the fibrous material having a property to adsorb radioactive nuclides in the form of ion and/or molecule onto its surface is fibrous active carbon having micropores on its surface. 11. A solidifying material according to claim 9, wherein the micropores have an average pore diameter of 10-25 .ANG.. 12. A structure according to claim 10, wherein the micropores have an average pore diameter of 10-25 .ANG.. 13. A solidifying material according to claim 1, wherein the fibrous material having a property to adsorb radioactive nuclides in the form of ion and/or molecule onto its surface is fibrous active carbon having a diameter on the order of about 10 to 15 .mu.m and a fiber length of about 3 mm. 14. A structure according to claim 2, wherein the fibrous material having a property to adsorb radioactive nuclides in the form of ion and/or molecule onto its surface is fibrous active carbon having a diameter on the order of about 10 to 15 .mu.m and a fiber length of about 3 mm. 15. A solidifying material according to claim 1, wherein an amount of the fibrous material having a property to adsorb radioactive nuclides in the form of ion and/or molecule onto its surface is about 5% by weight or less of said solidifying material. 16. A structure according to claim 2, wherein an amount of the fibrous material having a property to adsorb radioactive nuclides in the form of ion and/or molecule onto its surface is about 5% by weight or less of said structure. 17. A solidifying material for disposal of radioactive wastes in solidified waste form which comprises an admixture of a cement type hydraulic solidifying material and fibrous active carbon having micropores on its surface. 18. A structure for disposal of radioactive wastes at least a part of which structure is composed of a cement type hydraulic solidifying material wherein said cement type hydraulic solidifying material contains fibrous active carbon having micropores on its surface. 19. A process for solidifying radioactive wastes which comprises a step of feeding the waste into a kneading tank, a step of pouring a cement type hydraulic solidifying material into the kneading tank, a step of adding to the kneading tank a fibrous material having a property to adsorb radioactive nuclides in the radioactive wastes in the form of ion and/or molecule onto its surface, a step of adding water to the kneading tank, a step of kneading the wastes, the hydraulic solidifying material, the fibrous material and water in the kneading tank, and a step of pouring the kneading product obtained at the kneading step into a waste container to solidify the kneaded product; the fibrous material also having properties to increase retention of the radioactive wastes in the solidified kneaded product and to increase the tensile strength of the solidified kneaded product thereby increasing the waste loading therein. 20. A process for solidifying radioactive wastes which comprise a step of feeding the wastes into a waste container, a step of kneading a cement type hydraulic solidifying material, a fibrous material having a property to adsorb radioactive nuclides in the wastes in the form of ion and/or molecule onto its surface and water in a kneading tank, a step of pouring the kneaded product obtained in the kneading step into said waste container to solidify the product within said waste container, the fibrous material also having properties to increase retention of the radioactive wastes within the waste form and to increase the tensile strength of the product, thereby increasing the waste loading therein. 21. A process for solidifying radioactive wastes which comprises a step of feeding the wastes into a waste container, a step of pouring a cement type hydraulic solidifying material into the waste container, a step of pouring into the waste container a fibrous material having a property to adsorb radioactive nuclides in the wastes in the form of ion and/or molecule onto its surface, a step of adding water to the waste container, and a step of kneading and curing the wastes, the hydraulic solidifying material, the fibrous material and water in the waste container thereby to set the kneaded and cured product; the fibrous material also having properties to increase retention of the radioactive wastes within the waste form and to increase the tensile strength of the product, thereby increasing the waste loading therein. 22. A solidifying material for disposal of radioactive wastes and for making a solidified waste form which comprises an admixture of a cement type hydraulic solidifying material and fibrous material exhibiting the ability to increase the distribution coefficient of the radioactive wastes in the waste form, and the ability to increase the tensile strength of the waste form, thereby increasing the waste loading in the waste form. 23. A solidifying material according to claim 22, wherein the fibrous material comprises ion exchange fibers having functional groups, said fibers adsorbing at least anion of radioactive nuclides dissolved in liquid by ion exchange reaction with said functional groups. 24. A solidifying material according to claim 23, wherein said fibrous material comprises fibrous active carbon, having a property to adsorb nuclides in the form of at least anion or molecule onto its surface and having micropores on its surface. 25. A solidifying material according to claim 22, wherein said fibrous material is at least one member selected from the group consisting of fibrous active carbon, at least anion exchange fibers and alkali metal titanate fibers. 26. A solidified waste form, which comprises radioactive wastes and a mixture of a cement type hydraulic solidifying material and a fibrous active carbon, said waste form containing the radioactive wastes in an amount of 25-60 wt. %. 27. A solidified waste form according to claim 26, wherein said waste form also has a distribution coefficient of carbon-14 which increases with addition of the fibrous active carbon. 28. A solidified waste form comprising radioactive wastes admixed with a solidifying cement material and a fibrous material, said fibrous material having a property to increase both the distribution coefficient of said radioactive wastes in said waste form and the packing rate of the wastes within said waste form, the radioactive wastes constituting at least 25% by weight of the waste form and the fibrous material constituting no more than 10% by weight of the solidifying cement material. 29. A solidified waste form containing radioactive wastes, solidifying cement material and fibrous material, said fibrous material having a property to adsorb radioactive nuclides in the radioactive wastes in the form at least anion and/or molecule onto its surface and an average micropore diameter of 10-25 .ANG. on its surface, or a property to adsorb at least anion of said radioactive nuclides dissolved in liquid by ion exchange reaction with functional groups contained in the fibrous material; said fibrous material also having the properties to increase the distribution coefficient of the radioactive waste within said waste form, the tensile strength of the waste form and the packing rate of the wastes within said waste form. 30. A solidifying material according to claim 1, wherein the waste form exhibits a compressive strength of at least 30 kg/cm.sup.2 after the waste form is cured for one month and is dipped in water for one month. 31. A solidifying material according to claim 22, wherein the waste form exhibits a compressive strength of at least 30 kg/cm.sup.2 after the waste form is cured for one month and is dipped in water for one month. 32. A solidifying waste form according to claim 26, wherein the waste form exhibits a compressive strength of at least 30 kg/cm.sup.2 after the waste form is cured for one month and is dipped in water for one month. 33. A solidified waste form comprising radioactive wastes admixed with a solidifying cement material and a fibrous material, the fibrous material having a property to increase both the distribution coefficient of the radioactie wastes in the waste form and a packing rate of the wastes within said waste form. 34. A process for solidifying radioactive wastes which comprises a step of feeding the wastes into a kneading tank, a step of pouring a cement type hydraulic solidifying material into the kneading tank, a step of adding to the kneading tank a fibrous material having a property to adsorb radioactive nuclides in the wastes in the form of ion and/or molecule onto its surface, a step of adding water to the kneading tank, a step of kneading the wastes, the hydraulic solidifying material, the fibrous material and water in the kneading tank, and a step of pouring the kneading product obtained at the kneading step into a waste container to solidify the kneaded product; the fibrous material both increasing the tensile strength of the product and increasing the distribution coefficient of the radioactive nuclides in said product, thereby increasing the waste loading in the product. 35. A process for solidifying radioactive wastes which comprises a step of feeding the wastes into a waste container, a step of kneading a cement type hydraulic solidifying material, a fibrous material having a property to adsorb radioactive nuclides in the wastes in the form of ion and/or molecule onto its surface and water in a kneading tank, a step of pouring the kneaded product obtained in the kneading step into said waste container to solidify the product within said waste container, the fibrous material both increasing the tensile strength of the product, and increasing the distribution coefficient of the radioactive nuclides in said product, thereby increasing the waste loading in said product. 36. A process for solidifying radioactive wastes which comprises a step of feeding the wastes into a waste container, a step of pouring a cement type hydraulic solidifying material into the waste container, a step of pouring into the waste container a fibrous material having a property to adsorb radioactive nuclides in the wastes in the form of ion and/or molecule onto its surface, a step of adding water to the waste container, and a step of kneading and curing the wastes, the hydraulic solidifying material, the fibrous material and water in the waste container thereby to set the kneaded and cured product; the fibrous material both increasing the tensile strength of the product and increasing the distribution coefficient of the radioactive nuclides in said product, thereby increasing the waste loading in said product. 37. A process for producing a structure for disposal of radioactive wastes which comprises the steps of mixing a fibrous material having a property to adsorb radioactive nuclides in the wastes in the form of ion and/or molecule onto its surface, a cement-type hydraulic solidifying material and water and solidifying the resultant admixture to form said structure.