Method for producing a sealed 210Pb—210Po alpha particle emitter

Abstract

The present invention provides a method for producing a sealed 210Pb—210Po α source (α particle emitter) and an apparatus thereof, which can be used as an α particle source for a random pulse generator. The method for producing a sealed 210Pb—210Po α source (α particle emitter) includes the steps of: collecting 210Pb—210Po with a 210Pb collector using radon collection; precipitating the hydroxides of the collected 210Pb—210Po and collecting the precipitates by a polycarbonate (PC) filter; dissolving the 210Pb—210Po hydroxide precipitate to form a 210Pb—210Po radioactive thin film; and sealing the 210Pb—210Po radioactive thin film for protection.

Description

This application is a 371 of international application PCT/JP2004/008407, which claims priority based on Japanese patent application No. 2003-174296 filed on Jun. 19, 2003, which is incorporated herein by reference.

TECHNICAL FIELD

The present invention relates to a method for producing an α particle emitter, and an apparatus thereof, which can be used as an α source for a random pulse generator by trapping atoms generated from a naturally existing decaying radioactive substance, wherein control of the number of atoms is carried out to set these trapped atoms to a certain intensity.

BACKGROUND ART

A conventional method for producing an α particle emitter involves sandwiching an α emitter between cover members to seal for use in a smoke detector, rolling and stretching it with the cover members and cutting them into a predetermined shape to complete when a predetermined density in the number of atoms was reached. Other methods have been proposed (see, for example, Patent Document 1: Method for Collecting Radon), in which metal atoms serving as an α emitter are trapped in a solution state by cooling trapped radon gas with liquid nitrogen to cooling trapped radon gas with liquid nitrogen to liquefy it.

Patent Document 1: Japanese Patent Application Laid-Open No. 2002-265206

DISCLOSURE OF THE INVENTION

However, these conventional methods required a step of controlling the density of the α emitter in which the α emitter was sandwiched between gold material and silver material then rolled until a certain radiation source intensity was reached, meaning that a special apparatus was necessary. This had the drawback that costs would inevitably rise.

It is an object of the present invention to provide a method for producing a sealed α emitter source, and an apparatus thereof, which uses already established reliable technology that is easy to use and low-cost.

The present invention relates to a method for producing a sealed ²¹⁰Pb—²¹⁰Po α source (α particle emitter) which comprises the steps of: collecting ²¹⁰Pb—²¹⁰Po with a ²¹⁰Pb collector using radon collection; precipitating the hydroxides of the collected ²¹⁰Pb—²¹⁰Po and collecting the precipitates using a polycarbonate (PC) filter; dissolving the ²¹⁰Pb—²¹⁰Po hydroxide precipitates to form a ²¹⁰Pb—²¹⁰Po radioactive thin film; and sealing the ²¹⁰Pb—²¹⁰Po radioactive thin film for protection.

Specifically, the method for producing a sealed ²¹⁰Pb—²¹⁰Po α source (α particle emitter) according to the present invention comprises the following steps.

The first step is a process wherein a substance containing uranium series radioactive nuclides such as radium is used as a ²²²Rn source, ²²²Rn generated from the ²²²Rn source is passed along with a carrier gas such as nitrogen or dry air through a cold trap that is cooled to a temperature at or below the boiling point of ²²²Rn (−62° C.), to liquefy the ²²²Rn, and ²¹⁰Pb—²¹⁰Po among daughter nuclides generated by the decay of this liquefied ²²²Rn is collected by taking the ²¹⁰Pb—²¹⁰Po adhering to the cold trap wall sides or remaining in the cold trap, which has returned to room temperature, into a solution using a solvent such as a nitric acid solution for collecting.

The second step is a process in which a hydroxide precipitate is prepared by adding excess ammonium hydroxide solution to nitric acid, hydrochloric acid or sulfuric acid solution containing ²¹⁰Pb and ²¹⁰Po, which is a nuclide generated from decay of the ²¹⁰Pb, the precipitate is settled, and then the ²¹⁰Pb and ²¹⁰Po made into the hydroxide precipitate is collected using a polycarbonate (PC) filter.

The third step is a dissolving process in which a preferably 1:1 liquid mixture of dichloroethane and dichloromethane is used to dissolve the filter made of polycarbonate material. Metal atoms trapped in the polycarbonate are taken into the solution by dissolution of the polycarbonate. The compounds dichloroethane and dichloromethane adhere (bond) around the metal atoms, and extraction of the metal atoms is possible by extracting the solution. The third step also involves a process for forming a thin film of 1 micron or less by dripping this solution and allowing it to air dry.

The fourth step is a process in which the ²¹⁰Pb—²¹⁰Po radioactive thin film formed in the above-described step is sealed by dissolving the PC filter in a preferably 1:1 liquid mixture of dichloroethane and dichloromethane, and then dripping the liquid onto the membrane formed in the above-described step to form a thin film of 1 micron or less for protection.

In the method for producing a sealed ²¹⁰Pb—²¹⁰Po α source (α particle emitter) according to the present invention, the atomic weight of the metals ²¹⁰Pb and ²¹⁰Po can be controlled by controlling the drip amount of the solution in which metal atoms are dissolved. The specific order of the procedures is as follows.

1. Measure the weight of the membrane filter;

2. Measure the number of atoms of the ²¹⁰Pb—²¹⁰Po trapped by the membrane filter;

This measurement is carried out by measuring gamma radiation that the trapped ²¹⁰Pb—²¹⁰Po emits, wherein the radon atomic weight trapped in the filter from the radon trapping start by the cold trap to the trapping end can be calculated (radon being a parent nuclide of ²¹⁰Pb—²¹⁰Po).

3. Measure the weight (mass) of the solution which dissolves the filter;

4. Determine the concentration of ²¹⁰Pb—²¹⁰Po in solution from the number of trapped atoms of the ²¹⁰Pb—²¹⁰Po and the weight of the solution;

5. Determine the necessary α particle number, calculate the solution amount which corresponds to this α particle number, and drip the equivalent amount onto a predetermined position using a pipette or the like;

6. Dry the dripped portion to evaporate off organic solvent.

The present invention further relates to a ²¹⁰Pb collector which uses radon collection for collecting ²¹⁰Pb—²¹⁰Po. This collector comprises a ²²²Rn source which includes a substance containing uranium series radioactive nuclides such as radium; a moisture trap for collecting ²²²Rn gas generated by the ²²²Rn source along with carrier gas such as nitrogen or dry air and sending only pure radon gas to a cold trap; and a ²²²Rn collector trap for liquefying the ²²²Rn gas by cooling to a temperature of a boiling point of ²²²Rn (−62° C.) or lower and then generating ²¹⁰Pb and ²¹⁰Po which have a relatively long half-life among daughter nuclides generated from decay of the ²²²Rn.

BRIEF DESCRIPTION OF THE DRAWINGS

FIG. 1 is a schematic view illustrating one example of a ²¹⁰Pb collector using radon collection used in the present invention;

FIG. 2 is a schematic view illustrating one example of a dissolving method for a PC filter according to the present invention;

FIG. 3 is a schematic view illustrating one example of the procedures from filter dissolution to thin film formation according to the present invention; and

FIG. 4 is a schematic view illustrating one example of a sealing method for a ²¹⁰Pb—²¹⁰Po thin film according to the present invention.

BEST MODE FOR CARRYING OUT THE INVENTION

Now, embodiments of the method for producing a sealed ²¹⁰Pb—²¹⁰Po α source (α particle emitter) in accordance with the present invention, and an apparatus thereof, will be described in detail with reference to the drawings.

The process of the first step will now be described.

As illustrated in FIG. 1, a substance containing uranium series radioactive nuclides such as natural uranium ore powder 1 or radium which serve as a ²²²Rn source is charged into a container. Uranium ore powder, left over soil from a uranium mine, left over soil generated during a uranium refining process and a radium source are effective as this substance. To introduce ²²²Rn generated by the ²²²Rn source into the cold trap, a carrier gas 2 such as nitrogen or dry air and a pump 7 for suction are used. The gas from the ²²²Rn source is first led to a moisture trap (water content trap) 3. The moisture trap is an apparatus which collects vapor and moisture released at the same time as the ²²²Rn to allow only pure radon gas to be sent to the cold trap. The moisture trap is an apparatus which has a function to freeze moisture released by the ²²²Rn source so that it adheres to the walls for removal by cooling using dry ice or methanol 4 to −20° C. or below. While not shown in the diagram, a honeycomb, thin pipe or mesh structure may be used, wherein an optimal combination can be achieved among the gas passage, the coolant temperature and conductance from the structure material. It is important that the cold trap operating temperature is set in a range below zero so that ²²²Rn is not trapped and above the boiling point temperature of ²²²Rn (−62° C.).

It is important that the pipe from the moisture trap to the ²²²Rn collector trap 5 is protected as much as possible with insulation material so that the exit gas temperature of the moisture trap 3 does not rise during the distance to the ²²²Rn collector trap. This is an important factor in raising cooling efficiency of the ²²²Rn collector trap. Gas which has exited the moisture trap enters a cold trap, which is the ²²²Rn collector trap 5. The cold trap uses liquid nitrogen 6 to cool the temperature below the boiling point of ²²²Rn (−62° C.). Gas mainly comprising ²²²Rn that has had moisture removed by the moisture trap is liquefied in the cold trap of the ²²²Rn collector trap. The same structures used for the moisture trap, honeycomb, fine pipe and mesh, may be used to allow efficient cooling for liquefying.

The collecting period is preferably carried out continuously for roughly 12 days to 1 month, in view of the half-lives of ²²²Rn (3.82 days) and ²¹⁰Pb (22.3 years) (the radioactivity amount of the ²¹⁰Pb generated by the decay of ²²²Rn is about 1/2000th that of the total radioactivity amount of ²²²Rn), although this can be adjusted depending on the required ²¹⁰Pb source intensity and the ²²²Rn gas generation rate.

Daughter nuclides (²¹⁸Po, ²¹⁴Pb, ²¹⁴Bi, ²¹⁴Po, ²¹⁰Pb, ²¹⁰Bi, ²¹⁰Po) are generated from the decay of this liquefied ²²²Rn and the decay of the gas inside the cold trap in the ²²²Rn solution and on the wall surface. These daughter nuclides also decay according to their half-life, so that mainly ²¹⁰Pb and ²¹⁰Po, which have a relatively long half-life, are generated. The above-described cold trap in which collection was carried out for a fixed period is maintained for approximately 40 days at low temperature in view of the 3.82 day half-life of ²²²Rn. After allowing 99.9% or more of the ²²²Rn to dissipate away, the temperature is gradually returned to room temperature, wherein the extremely minute amount of remaining radon is released in the gas-phase and the ²¹⁰Pb—²¹⁰Po adhering to the cold trap walls or remaining ²¹⁰Pb—²¹⁰Po is dissolved with a solvent such as a nitric acid solution. This is a ²¹⁰Pb—²¹⁰Po collecting process characterized in that this solution is extracted along with ²¹⁰Pb—²¹⁰Po contained in the solution.

In place of natural uranium ore, radon or radon-generating radium can be used. Radon may be a gas which includes ²²²Rn, or may be a gas which can be trapped in a basement, a cave, a uranium deposit and the like. It is not necessary for the radon to be 100% radon. Further, radium which generates ²²²Rn (²²⁶Ra) and radon which is generated from minerals or rocks containing radium are also acceptable.

Polonium, bismuth and lead that are generated from the decay of radon are part of the uranium series and are inevitably formed. Each of the generated atoms is made to decay to ²¹⁰Pb without splitting, and allowed to progress for 1.5 to 2 years to set up a ²¹⁰Pb—²¹⁰Po radioactive equilibrium in which the half-life of the α particles released from the ²¹⁰Po is shortened to 22.3 years as though it was the half-life of ²¹⁰Pb. This ²¹⁰Pb—²¹⁰Po serves as the α emitter.

Next, the process of the second step will be described.

A hydroxide precipitate is prepared by adding excess ammonium hydroxide solution to a nitric acid solution containing the ²¹⁰Pb prepared in the above-described step and ²¹⁰Po which is a nuclide generated from the decay of ²¹⁰Pb (the following explanation will use a nitric acid solution as a representative example). The nitric acid solution containing ²¹⁰Pb and ²¹⁰Po, which is a nuclide generated from the decay thereof, may be prepared by dissolution with a nitric acid solution in order to extract the ²¹⁰Pb—²¹⁰Po metal atoms trapped in the process of the first step. Alternatively, a ²²⁶Ra ampule source, which has long been used as a radiation source in medicine, may be used, wherein the ²¹⁰Pb—²¹⁰Po generated within the ampule is dissolved with a nitric acid solution.

Once the precipitate has been allowed to settle, ²¹⁰Pb—²¹⁰Po in the form of a hydroxide precipitate is passed through a polycarbonate (PC) membrane filter to trap the precipitate in the filter. Sufficiently precipitated hydroxide is poured along with the solution into a container that is equipped with a PC filter, wherein the hydroxide is separated from the solution by the filter through suction from the filter exit side.

A surface collection type 0.1 μm Nuclepore polycarbonate filter is used as the polycarbonate filter. This filter may be used by mounting on an upper surface of a filter unit made of Nalgen Nunc International or the like (a nitrocellulose filter having an effective filtration surface diameter of 45 mm and an aperture diameter of 0.2 μm).

Next, the process of the third step will be described.

The third step is a dissolving method which uses a preferably 1:1 liquid mixture of dichloroethane and dichloromethane to dissolve the filter made from polycarbonate material.

A PC filter 8 which trapped the ²¹⁰Pb and ²¹⁰Po as a hydroxide precipitate is dissolved by a preferably 1:1 liquid mixture 9 of dichloroethane and dichloromethane. Metal atoms trapped in the hydroxide are taken into the solution by dissolving the polycarbonate. Extraction of the metal atoms is made possible by the compounds dichloroethane and dichloromethane adhering (bonding) around the metal atoms to extract the solution. Dissolution of the PC filter is illustrated in FIG. 2.

A solution 10 in which the PC filter that trapped the hydroxide is dissolved contains ²¹⁰Pb—²¹⁰Po, which is extracted by a pipette 11 or the like, dripped onto an aluminum plate or an inner side of a cap of a detector and allowed to air dry to form a thin film of 1 μm or less. This procedure is illustrated in FIG. 3.

Next, the process of the fourth step will be described.

The fourth step comprises a process in which a radioactive thin film is sealed for protection, wherein first a new PC filter is dissolved in a preferably 1:1 mixed solvent 12 of dichloroethane and dichloromethane. This is then adequately dried for sealing until an interference fringe ring of a coating 13 can be observed. Once drying has been confirmed, the solution is dripped onto the ²¹⁰Pb—²¹⁰Po thin film 14 formed in the above-described step and simultaneously adequately dried to form a thin film of 1 micron or lower. The specific procedure of this method is illustrated in FIG. 4.

In the production method of a sealed ²¹⁰Pb—²¹⁰Po α source (α particle emitter) according to the present invention, the metallic atomic weight of the ²¹⁰Pb and ²¹⁰Po can be controlled by controlling the drip amount of the solution in which metal atoms are dissolved. The specific order of procedures is as follows.

1. Measure the weight of the membrane filter;

2. Measure the number of the ²¹⁰Pb—²¹⁰Po atoms trapped by the membrane filter;

This measurement is carried out by measuring gamma radiation that the trapped ²¹⁰Pb—²¹⁰Po emits.

3. Measure the weight (mass) of the solution which dissolves the filter;

4. Determine the concentration of ²¹⁰Pb—²¹⁰Po in solution from the number of trapped atoms of the ²¹⁰Pb—²¹⁰Po and the weight of the solution;

5. Determine the necessary α particle number, calculate the amount of solution which corresponds to this α particle number, and drip the equivalent amount onto a predetermined position using a pipette or the like;

6. Dry the dripped portion to evaporate off organic solvent.

The present invention can be practiced in a large number of aspects without departing from its essential characteristics. Therefore, the above-described embodiments are only illustrative of the present invention, and is in no way restrictive thereto.

Advantages

The present invention can provide a method for producing a sealed α emitter source, and an apparatus thereof, which uses already established reliable technology which is easy to use and low-cost. For this reason, the inevitable rise in costs can be remarkably suppressed.

Claims

1. A method for producing a sealed 210Pb—210Po α source (α particle emitter) comprising the steps of: collecting 210Pb—210Po with a 210Pb collector using radon collection;precipitating the hydroxides of the collected 210Pb—210Po and collecting the precipitates using a polycarbonate (PC) filter;dissolving the 210Pb—210Po hydroxide precipitates to form a 210Pb—210Po radioactive thin film; andsealing the 210Pb—210Po radioactive thin film for protection.

2. The method for producing a sealed 210Pb—210Po α source (α particle emitter) according to claim 1, wherein the step of collecting 210Pb—210Po with a 210Pb collector using radon collection is a 210Pb—210Po collection process characterized in that a substance containing uranium series radioactive nuclides is used as a 222Rn source, 222Rn generated from the 222Rn source is passed along with a carrier gas through a cold trap that is cooled to a temperature at or below a boiling point of 222Rn (−62° C.) to liquefy the 222Rn, and 210Pb—210Po among daughter nuclides generated by the decay of the liquefied 222Rn is collected by taking the 210Pb—210Po adhering to the cold trap wall sides or remaining in the cold trap, which has returned to room temperature, into a solution using a solvent for collecting.

3. The production method according to claim 2, wherein the 222Rn source is selected from the group consisting of natural uranium ore powder and a radium source.

4. The production method according to claim 2, wherein the carrier gas is selected from the group consisting of nitrogen and dry air.

5. The production method according to claim 2, wherein the solvent for dissolving 210Pb—210Po is selected from the group consisting of nitric acid, sulfuric acid and hydrochloric acid solution.

6. The method for producing a sealed 210Pb—210Po α source (α particle emitter) according to claim 1, wherein the step of precipitating the hydroxides of the collected 210Pb—210Po and collecting the precipitates by a polycarbonate (PC) filter is a process in which the hydroxide precipitate is prepared by adding excess ammonium hydroxide solution to nitric acid, sulfuric acid or hydrochloric acid solution containing 210Pb and 210Po which is a nuclide generated from decay of 210Pb, the precipitate is settled, and then the 210Pb and 210Po made into a hydroxide precipitate is collected using the PC filter.

7. The method for producing a sealed 210Pb—210Po α source (α particle emitter) according to claim 1, wherein the step of dissolving the 210Pb—210Po hydroxide precipitate to form a 210Pb—210Po radioactive thin film is a process in which the PC filter that has collected 210Pb and 210Po as hydroxide precipitate is dissolved in a mixed solvent of dichloroethane and dichloromethane, and the resultant solution is dripped to form a thin film of 1 micron or less by natural evaporation of the solution.

8. The production method according to claim 7, wherein the mixing ratio of the dichloroethane and dichloromethane is 1:1.

9. A method for producing a sealed 210Pb—210Po α source (α particle emitter) comprising the steps of: collecting 210Pb—210Po with a 210Pb collector using radon collection;precipitating the hydroxides of the collected 210Pb—210Po and collecting the precipitates using a polycarbonate (PC) filter;dissolving the 210Pb—210Po hydroxide precipitates to form a 210Pb—210Po radioactive thin film; andsealing the 210Pb—210Po radioactive thin film for protection, wherein the step of sealing the 210Pb—210Po radioactive thin film for protection is a process in which a separate PC filter is dissolved in a mixed solvent of dichloroethane and dichloromethane, and the resultant solution is dripped onto a thin film prepared in accordance with the process of claim 7 to form a thin film of 1 micron or less.

10. The production method according to claim 9, wherein the mixing ratio of dichloroethane and dichloromethane is 1:1.

11. The method for producing a sealed 210Pb—210Po α source (α particle emitter) according to claim 7, characterized in that the content of 210Pb—210Po atoms is controlled by controlling the solution amount extracted for dripping.

12. The method for producing a sealed 210Pb—210Po α source (α particle emitter) according to claim 8, characterized in that the content of 210Pb—210Po atoms is controlled by controlling the solution amount extracted for dripping.

13. The method for producing a sealed 210Pb—210Po α source (α particle emitter) according to claim 9, characterized in that the content of 210Pb—210Po atoms is controlled by controlling the solution amount extracted for dripping.

14. The method for producing a sealed 210Pb—210Po α source (α particle emitter) according to claim 10, characterized in that the content of 210Pb—210Po atoms is controlled by controlling the solution amount extracted for dripping.