Method for MA/RE mutual separation in high-level waste

A polymer and nitrate technology, applied in ion exchange, radioactive purification, ion exchange regeneration, etc., can solve problems such as poor acid resistance and radiation resistance, concerns about post-treatment cycle safety, chemical instability, etc., and achieve selective adsorption Strong, safe and effective treatment and disposal, good separation effect

Inactive Publication Date: 2009-07-15
ZHEJIANG UNIV
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  • Abstract
  • Description
  • Claims
  • Application Information

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Problems solved by technology

[0007] However, the extraction agent used has limited solubility in common hydrocarbon diluents such as n-dodecane and kerosene, so diethylbenzene, tert-butylbenzene, or highly branched 1,1,2,2, Some toxic diluents such as 3,3,4,4,-octamethylbutane-based hydrogenated tetrapropylene mixture (TPH); or in order to suppress the third phase, 30% tributyl phosphate (TBP) must be added ) or 30% n-octanol and other organic phase reg

Method used

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  • Method for MA/RE mutual separation in high-level waste

Examples

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preparation example Construction

[0040] Experiment 1 Preparation of Adsorbent

[0041] Dissolve 100 grams of 2,6-bis-(5,6-di-n-butyl-1,2,4-triazin-3-yl)-pyridine in 1000 mL of dichloromethane and mix well; add 300 grams of coating polymer macroporous SiO 2 (SiO 2 -P) Stir evenly to volatilize most of the dichloromethane until the material is in a nearly dry state, and then vacuum-dry the nearly dry material at 45° C. for 24 hours.

[0042] Experiment 2 Preparation of Adsorbent

[0043] Dissolve 100 grams of 2,6-bis-(5,6-di-n-butyl-1,2,4-triazin-3-yl)-pyridine in 1500 mL of dichloromethane and mix well; add 600 grams of coating polymerization macroporous SiO 2 (SiO 2 -P) Stir evenly to volatilize most of the dichloromethane until the material is in a nearly dry state, and then vacuum-dry the nearly dry material at 45° C. for 24 hours.

[0044] Experiment 3 Preparation of Adsorbent

[0045] Dissolve 100 grams of 2,6-bis-(5,6-di-n-butyl-1,2,4-triazin-3-yl)-pyridine in 3000 mL of dichloromethane and mix we...

Embodiment 1

[0052] Example 1 Mutual separation of MA / RE in high-level radioactive waste (HLLW)

[0053] The adsorbent prepared in Experiment 1 was filled into a chromatographic separation column, and MA / RE in high-level radioactive waste (HLLW) were separated by liquid chromatography. The chromatographic column is a glass tube with an inner diameter of 1 cm and a height of 30 cm. The flow rate of the mobile phase is generally 1.0 ml / min and operated at room temperature.

[0054] HNO in the nitrate solution containing the minor actinides Am and Cm and rare earth elements was dissolved with concentrated nitric acid 3 The concentration is adjusted to 0.01 mol / liter, and the concentration of the rare earth element RE (the total concentration of the contained metal elements) in the system after adjustment is 5.0×10 -3 mol / L, the concentration of MA (the sum of Am and Cm) is 1.0×10 -5 mol / liter.

[0055] The nitrate solution after adjusting the concentration of nitric acid flows through the ...

Embodiment 2

[0060] Example 2 Mutual separation of MA / RE in high-level radioactive waste (HLLW)

[0061] Using the method of Example 1 to separate MA / RE from each other, the only difference is the NaNO in the eluent A 3 The molar concentration is 0.5mol / L; HNO 3 The molar concentration is 0.005mol / L.

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Abstract

The present invention discloses a method for performing MA/RE mutual separation to high-level waste, including: adjusting the nitrate concentration of the nitrate solution containing hypo-actinide element MA and rare-earth element RE; (2) the nitrates solution with adjusted nitrate concentration flowing through a chromatographic column filled with adsorbing substance; (3) using the eluent A to elute the chromatographic column to leach out the nitrates of rare-earth element, wherein, the eluate A is an aqueous solution containing NaNO3 and HNO3; (4) leaching the chromatographic column using the de-ionized water to leaching out the nitrate containing hypo-actinide element. The inventions has features of good separation effect, strong selection adsorbability of the adsorbing substance, capability of comparative thoroughly MA/RE mutual separation in the high-level waste, thoroughly security, economy and high efficiency.

Description

technical field [0001] The invention relates to the field of high-level radioactive waste treatment and disposal produced in nuclear industry spent fuel reprocessing flow, especially the mutual separation of MA / RE in high-level radioactive waste. Background technique [0002] As the high-level radioactive waste (HLLW) produced by spent fuel (SF) reprocessing, its safe treatment and disposal is one of the key links in nuclear fuel cycle technology. Spent fuel contains long-lived (millions of years) minor actinides (MA) and fragmentation products (FP) such as exothermic elements. The current status of reprocessing is: in addition to separating and recovering useful metals U and Pu, a part of Np and almost all FP elements went into the acidic HLLW. MA in HLLW is a long-lived fragment product, represented by trivalent Am and Cm, with a half-life of millions of years, and is considered to be the most dangerous potentially harmful element that causes long-term burdens on environm...

Claims

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Application Information

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IPC IPC(8): G21F9/04G21F9/12B01D15/08
Inventor 张安运
Owner ZHEJIANG UNIV
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