Boron-containing radioactive spent resin cement solidification method

A technology for solidifying radioactive waste resin and cement, which is applied in the field of cement solidification of boron-containing radioactive waste resin and cement of boron-containing radioactive waste resin in pressurized water reactor nuclear power plants. Difficulties and other problems to achieve the effect of improving processing efficiency

Inactive Publication Date: 2009-06-17
TSINGHUA UNIV
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Problems solved by technology

Cement curing is an economical and safe curing method, but the current cement curing formula has disadvantages such as low inclusion capacity, high nuclide leaching rate, and large volume expansion ratio of the solidified body.
Because nuclear

Method used

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Embodiment 1

[0012] A method for solidifying boron-containing radioactive waste resin cement, which method is:

[0013] (1) Using boron-containing radioactive waste resin of pressurized water reactor nuclear power plant, ordinary Portland cement, UNF-5 non-entrained naphthalene superplasticizer, zeolite, lime and water as raw materials, according to the ratio of raw materials: pressurized water reactor Nuclear power plant boron-containing radioactive waste resin: Ordinary Portland cement: UNF-5 non-air-entrained naphthalene superplasticizer: Zeolite: Lime: Water = 450L (free water level and resin surface level, containing about 280 kg of free water ): 900kg: 4.5kg: 45kg: 27kg: 100kg Weigh the raw materials;

[0014] (2) Put the above-mentioned materials into a 1 cubic meter C1 standard cement curing barrel, stir evenly to obtain a cement cured body, and seal and maintain it at room temperature.

[0015] The invention reduces the leaching rate of radionuclides in the cement solidified body by a...

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Abstract

The invention discloses a method for cement solidification of a boron-containing radioactive waste resin, which belongs to the technical field of cement solidification of the boron-containing radioactive waste resin of a pressurized water reactor nuclear power station. The method comprises the following steps: the boron-containing radioactive waste resin of the pressurized water reactor nuclear power station, ordinary Portland cement, a water reducing agent, zeolite, lime and water are taken as raw materials, the mixture ratio of the raw materials comprises that the boron-containing radioactive waste resin of the pressurized water reactor nuclear power station: the ordinary Portland cement: the water reducing agent: the zeolite: the lime: the water is equal to 300-500L: 800-1,000kg: 4-5kg: 40-50kg: 25-30kg: 90-110kg, and the raw materials are weighed; and the materials are added into a C1 solidification barrel with a volume of 1 cubic meter and are stirred evenly to obtain a cement solidification body. The adoption of each solidification drum with the volume of 1 cubic meter can solidify 300 to 500L of radioactive resin, and remarkably improve the treatment efficiency of boron-containing radioactive waste resins of pressurized water reactors.

Description

Technical field [0001] The invention belongs to the technical field of cement curing of boron-containing radioactive waste resin in pressurized water reactor nuclear power plants, and particularly relates to a method for curing boron-containing radioactive waste resin in cement. Background technique [0002] The treatment and disposal of waste radioactive resin is a major problem that has long plagued the development of the nuclear industry. Cement curing is an economical and safe curing method, but the current cement curing formula has disadvantages such as low package capacity, high nuclide leaching rate, and large volume compatibilization ratio of the cured body. Because nuclear power plants use boric acid to adjust the reactivity, the waste radioactive resin produced has a large amount of boron adsorbed. The retardation effect of boron on the cement slurry brings greater difficulties to the cement solidification of the waste resin. [0003] At present, the boron-containing ra...

Claims

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Application Information

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IPC IPC(8): C04B28/04C04B18/16
CPCC04B2111/00784C04B28/02Y02W30/91
Inventor 李俊峰王建龙孙奇娜
Owner TSINGHUA UNIV
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