CN105148732B - One kind separation short-lived nuclide141Ba method - Google Patents
One kind separation short-lived nuclide141Ba method Download PDFInfo
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Abstract
The present invention relates to one kind to separate short-lived nuclide141Ba method.Using from parent141The method that Cs is initially separated, realize short-lived nuclide in fission product141Ba separation；Using decay separation, the method being centrifuged at a high speed, realize141Cs and more short life Cs isotopes, such as142Cs、143Cs separation；Using the method for decay separation, precipitation separation, realize141Ba and more long-life Cs isotopes, such as140Cs separation.This method flow is simple, and obtained target product purity is high, can effectively avoid being mixed into other impurities.
Description
Technical field
The present invention relates to short-lived nuclide separation field, and short-lived nuclide is separated in particular to one kind141Ba method.
Background technology
141Ba is one of short-lived nuclide that yield is higher in complicated fission product, and the core is directly purified from fission product
It is plain inevitable because the interference of its isotope has certain difficulty, fast separating process need to be used from its parent141Cs is initially separated.
Cs is typical first main group alkali metal, and chemical property is active, and conventional Cs method for separating and analyzing includes the precipitation method, molten
Agent extraction, ion-exchange, gamma energy spectrum method and mass spectrography etc., such as separated using the Tricesium dodecatungstophosphate precipitation method137Cs(T1/2=
30.07y), using two-step precipitation and a step solvent extraction and separation138Cs (T1/2=33.2min), using inorganic ion exchanger
Basic zirconium phosphate and Anion exchange resin separation135Cs(T1/2=2.3 × 106Y), due to141Cs half-life period only 24.9s, the above method
Still it is difficult to meet to require.
In view of drawbacks described above, creator of the present invention obtains the present invention finally by prolonged research and practice.
The content of the invention
To solve above-mentioned technological deficiency, the technical solution adopted by the present invention is, there is provided one kind separation short-lived nuclide141Ba method, the separation method comprise the following steps:
S1：Open reactor；
S2：Make after irradiation caused fission product carry to one from the target chamber to be centrifuged at a high speed control system, control
Fission product transmits the time to the control system that is centrifuged at a high speed in t from the target chamber1~t2Scope, complete141Cs with it is short
The separation of life-span isotope, Centrifugical extraction simultaneously collect product；
S3:Precipitating reagent is added into the product makes generation141Ba is precipitated；
S4:Dissolving141Ba is precipitated, and must contain target species141Ba solution.
Preferably, extractant described in the step S2 can be tetraphenylboron sodium-isoamyl acetate, 4- sec-butyls -2- (α -
Methylbenzyl) phenol, 2- TTAs or picric acid.
Preferably, precipitating reagent described in the step S3 can be chromate, nitrate, oxalates, sulfate, chloride or
Corallinate.
Compared with the prior art the beneficial effects of the present invention are：(1) use from parent141The method that Cs is initially separated,
Realize short-lived nuclide in fission product141Ba separation.(2) using decay separation, the method being centrifuged at a high speed, realize
141Cs and more short life Cs isotopes, such as142Cs、143Cs separation.(3) it is real using the method for decay separation, precipitation separation
It is existing141Ba and more long-life Cs isotopes, such as140Cs separation.This method flow is simple, obtained target product purity pole
It is high.
Brief description of the drawings
Technical scheme in order to illustrate the embodiments of the present invention more clearly, make required in being described below to embodiment
Accompanying drawing is briefly described.
Fig. 1 is a kind of separation short-lived nuclide141The flow chart of Ba method.
Embodiment
Below in conjunction with accompanying drawing, the forgoing and additional technical features and advantages are described in more detail.
Uranium is put into target chamber can produce a variety of radioactive particles by irradiation, the same position of isotope, Ba including Cs
The isotope of element and other multiple elements, in order to obtain Ba isotope141Ba, for its own decay feature and chemical characteristic,
Design the flow of a set of separation and Extraction.
With141Decay chain related Ba is as follows:
A kind of as shown in figure 1, separation short-lived nuclide141The key step of Ba method is as follows：
S1：Open reactor；
S2：Make after irradiation caused fission product carry to one from the target chamber to be centrifuged at a high speed control system, control
Fission product is transmitted to the time for the control system that is centrifuged at a high speed in t1~t2 scope, completion from the target chamber141Cs with it is short
The separation of life-span isotope, Centrifugical extraction simultaneously collect product；The extractant used that extracts is tetraphenylboron sodium-acetic acid isoamyl
Ester, 4- sec-butyls -2- (α-methylbenzyl) phenol, 2- TTAs or picric acid；
S3:Precipitating reagent is added into the product makes generation141Ba is precipitated；The precipitating reagent can be chromate, nitrate,
Oxalates, sulfate, chloride or corallinate；
S4:Dissolving141Ba is precipitated, and must contain target species141Ba solution；The lytic agent is hydrochloric acid or nitric acid.
A kind of as shown in figure 1, separation short-lived nuclide141The flow chart of Ba method.Among the flow, what is be related to is each
Device has：Gas cylinder, electric tube furnace and its load sample boat included, target chamber, gas delivery system, be centrifuged at a high speed control system,
The high pure nitrogen or helium of carrier gas are saved as in the gas cylinder；Load sample boat is provided with the electric tube furnace, in the load sample boat
KCl powder is held, sets target substance and its bombardment device, the gas delivery system to include a gas flow in the target chamber
Meter, can strictly control the transmission speed and transmission quantity of gas in gas cylinder, and the control system that is centrifuged at a high speed can be entered simultaneously
Row sample centrifuges and extraction, target substance is separated.The gas cylinder, electric tube furnace, target chamber, the control that is centrifuged at a high speed are
System, ion exchange system pass sequentially through corresponding transmission pipeline connection.
Separate short-lived nuclide141Ba idiographic flow is as follows：
Step a. opens the electric tube furnace, adjusts the temperature to 650 DEG C, makes the solid KCl powder shapes in the load sample boat
Into aerosol；At 650 DEG C, KCl can form aerosol, and the too low KCl of temperature can not form aerosol state or form state
It is undesirable, temperature it is too high by when KCl decompose reaction, KCl aerosols can carry fission product and be transferred to other from target chamber
Process chamber, without influenceing the putting performance of fission product in itself；
The radiation parameter of target substance, to be irradiated in step b. adjustment target chambers；The radiation parameter of target substance is according to different material
Set different radiation parameters；
Step c. opens gas delivery system, adjusts gas cylinder initial pressure, and control KCl aerosols are transmitted at a high speed from target chamber
Centrifuge scope of the time in 20~100s of control system；It is 0.3MPa to adjust the gas pressure in the bottle, makes high pure nitrogen or helium
Gas enters electric tube furnace by pipeline, and high pure nitrogen or helium form pressure, the KCl aerosols in electric tube furnace is transmitted to target
Interior, and the control system that is centrifuged at a high speed is re-transmitted to out of target chamber, KCl aerosols will carry after opening reactor141Cs from target indoor transmissions to the control system that is centrifuged at a high speed because140Cs、141Cs、142Cs、143Cs half-life period is respectively
78.7s, 24.9s, 1.8s, 1.78s, and chemical property is close, if transmission time is too short142Cs、143Cs can not complete to decay,
It will eventually be mixed into and carry141Among Cs solution, it is difficult to separated by chemical method, the time is longer than 100s then140Cs completes to decline
It will eventually be mixed into and carry after change141Among Cs solution, it is therefore desirable to which the controlling transmission time is 20~100s；
Step d. opens the control system that is centrifuged at a high speed, regulation extractant, Cs carrier solutions, Ba carrier solutions and lemon
The flow velocity of lemon acid sodium solution, two-phase outlet solution is clarified, export in aqueous phase and adulterated without organic phase；The extractant is used to extract
Cs, the Cs carrier solutions and the Ba carrier solutions can carry Cs isotope and Ba isotope respectively；The extractant
Tetraphenylboron sodium-isoamyl acetate, BAMBP (4- sec-butyls -2- (α-methylbenzyl) phenol), TTA (2- thenoyl trifluoros can be selected
Acetone), picric acid etc., preferentially from tetraphenylboron sodium-isoamyl acetate, BAMBP etc.；
Step e. opens reactor, adjusts neutron flux, irradiates shutdown after 10min, completes141Cs decay separation；Target
Indoor target substance caused particle after irradiation is carried to being centrifuged at a high speed in 20~100s by the KCl aerosols
Control system, the short life Cs isotopes among this transmitting procedure142Cs、143Cs decays totally, is formed142Ba、143Ba, it will fission
Product is carried to Cs carrier solutions and Ba carrier solutions, by High-speed centrifugal extraction, now141Cs is stored in aqueous phase, collects water
Mutually make its 2~3min that decays,141Cs half-life period is 24.9s, by the decay of 2~3 minutes,141Cs will be decayed into all141Ba；Complete in this process141Cs with142Cs、143Cs decay separation；
Step f. closes gas delivery system, closing high-speed centrifuges control system；
Step g. precipitation separation141Ba；Precipitating reagent is added into aqueous phase precipitates generation Ba, centrifuges Ba precipitations；Heavy
Precipitating reagent is added again in the aqueous phase after separating of forming sediment, is centrifuged again, to ensure that Ba is all precipitated；The optional chromic acid of Ba precipitating reagents
Salt, nitrate, oxalates, sulfate, chloride and corallinate etc. are precipitated, preferentially from chromate, chloride form；
Precipitation separation141Ba can make141Ba and other more long-lives140Cs etc. is separated；
Step h. dissolving Ba precipitations, must contain target species141Ba solution；The Ba precipitations of gained are used into 1mol/L HCl
Solution is completely dissolved precipitation.
Presently preferred embodiments of the present invention is the foregoing is only, is merely illustrative for the purpose of the present invention, and it is non-limiting
's.Those skilled in the art understands, many changes can be carried out to it in the spirit and scope that the claims in the present invention are limited
And modification, or even it is equivalent, but fall within protection scope of the present invention.
Claims (4)
1. one kind separation short-lived nuclide141Ba method, it is characterized in that, separation method comprises the following steps：
S1：Open reactor；
S2：Make after irradiation caused fission product carry to one from target chamber to be centrifuged at a high speed control system, control fission product
The time to the control system that is centrifuged at a high speed is transmitted in t from the target chamber1~t2Scope, pass through be centrifuged at a high speed control
System fading margin extractant, Cs carrier solutions, the flow velocity of Ba carrier solutions and sodium citrate solution, clarify two-phase outlet solution,
Export in aqueous phase and adulterated without organic phase, completed141Cs and short-lived isotope separation, Centrifugical extraction simultaneously collect product；
S3:Precipitating reagent is added into the product makes generation141Ba is precipitated；
S4:Dissolving141Ba is precipitated, and must contain target species141Ba solution.
2. separation short-lived nuclide according to claim 1141Ba method, it is characterized in that, extract described in the step S2
It is tetraphenylboron sodium-isoamyl acetate, 4- sec-butyls -2- (α-methylbenzyl) phenol, 2- thenoyl trifluoropropyls to take the extractant used
Ketone or picric acid.
3. separation short-lived nuclide according to claim 1141Ba method, it is characterized in that, sunk described in the step S3
Shallow lake agent is chromate, nitrate, oxalates, sulfate, chloride or corallinate.
4. separation short-lived nuclide according to claim 1141Ba method, it is characterized in that, described in the step S4
For dissolving141The solvent of Ba precipitations is hydrochloric acid or nitric acid.
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Citations (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| BE676090A (en) * | 1965-02-10 | 1966-06-16 | ||
| DE1300533B (en) * | 1963-11-08 | 1969-08-07 | Saint Gobain Techn Nouvelles | Process for the preparation of a solution containing 137/56 + Ba |
| US3663177A (en) * | 1968-08-28 | 1972-05-16 | Union Carbide Corp | Radioactive barium-137 |
| CN101323906A (en) * | 2008-07-31 | 2008-12-17 | 浙江大学 | Method for separating heating element Sr and metal element Ba from high-level waste |
-
2015
- 2015-08-12 CN CN201510492821.6A patent/CN105148732B/en active Active
Patent Citations (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| DE1300533B (en) * | 1963-11-08 | 1969-08-07 | Saint Gobain Techn Nouvelles | Process for the preparation of a solution containing 137/56 + Ba |
| BE676090A (en) * | 1965-02-10 | 1966-06-16 | ||
| US3663177A (en) * | 1968-08-28 | 1972-05-16 | Union Carbide Corp | Radioactive barium-137 |
| CN101323906A (en) * | 2008-07-31 | 2008-12-17 | 浙江大学 | Method for separating heating element Sr and metal element Ba from high-level waste |
Non-Patent Citations (1)
| Title |
|---|
| 三步分离法制备高丰度的142La;丁有钱;《原子能科学技术》;20141031;第1740页第1栏第2段-第1栏第2段，第1742页第2栏第2段,附图1 * |
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