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Curing treatment additive, curing formula and process for radioactive boron-containing waste liquid

A solidification treatment and radioactive technology, applied in the field of solidification treatment additives for radioactive boron-containing waste liquid, can solve the problems of undisclosed key points of the technical solution, prone to crystallization, loose structure, etc., achieve good volume reduction effect and improve compression resistance Strength, fluidity-enhancing effect

Active Publication Date: 2018-01-30
NUCLEAR POWER INSTITUTE OF CHINA
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

The cured body has a low inclusion rate of boric acid, loose structure, and prone to crystallization problems
Regarding the solidification technology of high-concentration radioactive boron-containing waste liquid, there is no relevant research in China. Although there are related reports worldwide, the key points of the technical solution have not been disclosed.

Method used

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  • Curing treatment additive, curing formula and process for radioactive boron-containing waste liquid

Examples

Experimental program
Comparison scheme
Effect test

Embodiment 1

[0031] a. The addition ratio of polymeric borate solution and curing agent in this formula is 28:9. Configure 280g of polymerized borate solution (boron concentration 160000mg / kg, use 252.51g of boric acid), 60g of cement, 15g of fly ash, 5g of silica fume, 5g of zeolite, 2.5g of sodium metaaluminate, 2.5g of sodium silicate, carbon fiber powder 1g.

[0032] b. Mixing materials: Add the curing agent into the polymerized borate solution, and stir for 10 minutes with a mixer at a speed of 500 r / min.

[0033] c. Grouting: Pour the stirred cement slurry into the curing bucket and let it cool naturally.

Embodiment 2

[0035]a. The addition ratio of polymeric borate solution and curing agent in this formula is 28:20. Prepare 280g of polymerized borate solution (boron concentration 140000mg / kg, use 221.92g of boric acid), 100g of cement, 60g of fly ash, 15g of silica fume, 15g of zeolite, 5g of sodium metaaluminate, 5g of sodium silicate, and 2g of carbon fiber powder.

[0036] b. Mixing materials: Add the curing agent into the polymerized borate solution, and stir for 10 minutes with a mixer at a speed of 500 r / min.

[0037] c. Grouting: Pour the stirred cement slurry into the curing bucket and let it cool naturally.

Embodiment 3

[0039] a. The addition ratio of polymeric borate solution and curing agent in the formulation of this research is 25:16. Configure 500g of polymerized borate solution (boron concentration 140000mg / kg, use boric acid 394.55g), Portland cement 140g, fly ash 120g, silica fume 25g, zeolite 25g, sodium metaaluminate 5g, sodium silicate 5g, carbon fiber Powder 2g.

[0040] b. Mixing materials: Add the curing agent into the polymerized borate solution, and stir for 10 minutes with a mixer at a speed of 500 r / min.

[0041] c. Grouting: Pour the stirred cement slurry into the curing bucket and let it cool naturally.

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Abstract

The invention discloses a solidification treatment additive, a solidification formula and a process for radioactive boron-containing waste liquid, which can greatly improve the containment rate of the solidification treatment of radioactive boron-containing waste liquid. Heat, use zeolite powder to reduce cesium leaching and promote hydration, use silica fume to reduce strontium and cesium leaching, use sodium metaaluminate to accelerate cement hardening and coagulation, use sodium silicate to increase strength, use carbon fiber powder to increase strength, and use boron The boric acid inclusion rate of the prepared cured body can reach 49.5% by preparing a polymeric borate salt and then adding a curing agent for curing.

Description

technical field [0001] The invention relates to the field of cementation of radioactive boron-containing waste liquid used in nuclear facilities, in particular to a solidification treatment additive, curing formula and process for radioactive boron-containing waste liquid. Background technique [0002] During the operation, refueling and overhaul of the reactor, a large amount of radioactive boron-containing waste liquid will be produced. Its main components are boric acid and borates. These radioactive boron-containing waste liquids need to be solidified and then transported to disposal sites for long-term storage. Taking the M310 model as an example, a nuclear reactor and supporting facilities produce 2,800 tons of radioactive boron-containing waste liquid every year. By 2014, my country will have more than 28,000 tons of radioactive boron-containing waste liquid to be treated every year, and by 2020, this number will reach 64,400 tons. , with the rapid development of the...

Claims

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Application Information

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Patent Type & Authority Patents(China)
IPC IPC(8): G21F9/16C04B28/04
CPCC04B28/04G21F9/165C04B18/08C04B18/146C04B14/04C04B22/08C04B14/386
Inventor 张劲松王亚光陈云明李兵梁邦宏曹骐李新政孙鹏胡银刘东彬
Owner NUCLEAR POWER INSTITUTE OF CHINA
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