Claims
- 1. A method for forming a hardened product containing a radioactive ion exchanger resin in a condition for permanent, noncontaminating storage, comprising:
- providing, before fixing, a mass of such ion exchanger resin saturated in water, the resin being at least one resin selected from the group consisting of spherical resins and powdered resins;
- mixing the resin mass, with stirring, with a blast furnace cement having a composition which causes it to exhibit slow initial hardening, high sulfate resistance and low hydration heat and with a quantity of additional water equal in weight to 20% to 40% of the weight of the blast furnace cement; and
- allowing the resulting mixture to harden at room temperature.
- 2. A method as defined in claim 1 wherein the water in which the resin is saturated is composed of weakly to medium radioactive waste water.
- 3. A method as defined in claim 1 wherein the additional water is composed of weakly to medium radioactive waste water.
- 4. A method as defined in claim 1 wherein the resin consists of spherical resin in a quantity corresponding to a dry resin content of up to 25% by weight, in the hardened product.
- 5. A method as defined in claim 4 the quantity of resin corresponds to a dry resin content of at least 10%, by weight, in the hardened product.
- 6. A method as defined in claim 1 wherein the resin consists of powdered resin in a quantity corresponding to a dry resin content of up to 15%, by weight, in the hardened product.
- 7. A method as defined in claim 6 wherein the quantity of resin corresponds to a dry resin content of at least 6%, by weight, in the hardened product.
- 8. A method as defined in claim 1 wherein the blast furnace cement provides the only substances stabilizing the resin during hardening of the mixture.
- 9. The method as defined in claim 1, wherein the blast furnace cement comprises 15 to 69 parts by weight of Portland cement clinker and correspondingly, 85 to 31 parts by weight of rapidly cooled blast furnace slag.
- 10. The method as defined in claim 9, wherein the blast furnace cement contains less than 55 weight percent calcium oxide, SiO.sub.2 in an amount of 22 to 29 weight percent; Al.sub.2 O.sub.3 +TiO.sub.2 in an amount of 6 to 13 weight percent; Fe.sub.2 O.sub.3 (FeO) in an amount of 1 to 3 weight percent; MgO in an amount of 1 to 5 weight percent; and Mn.sub.2 O.sub.3 (MnO) in an amount of 0.2 to 1.5 weight percent.
- 11. The method as defined in claim 9, wherein the blast furnace cement has the designation 35 L/HS-NW.
- 12. A method as defined in claim 2 wherein the additional water is composed of weakly to medium radioactive waste water.
- 13. A method as defined in claim 1, wherein the resin is a spherical resin in a quantity corresponding to a dry resin content of 8.7 to 26.6%.
- 14. A method as defined in claim 13, wherein the resin is in a quantity corresponding to a dry resin content of 8.7% by weight, in the hardened product.
Priority Claims (1)
Number |
Date |
Country |
Kind |
2945007 |
Nov 1979 |
DEX |
|
Parent Case Info
This application is a continuation of application Ser. No. 203,678, filed Nov. 3, 1980.
Foreign Referenced Citations (1)
Number |
Date |
Country |
2717656 |
Oct 1978 |
DEX |
Non-Patent Literature Citations (2)
Entry |
Lerch et al. "Treatment and Immobilization of Intermediate Level Radioactive Wastes" in Carter et al., eds. Managment of Low-Level Radioactive Waste, vol. 1, 1979, pp. 513, 540-543. |
Rudolph et al. "Immobilization of Strontium . . ." in McCarthy et al., eds., Scientific Basis for Nuclear Waste Mgmt. vol. 1, 1979, pp. 467-470. |