Patent Application
20070098606
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.
A conventional method for producing an a particle emitter involves sandwiching an a 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
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 a 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.
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
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
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
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
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.
| Number | Date | Country | Kind |
|---|---|---|---|
| 2003-174296 | Jun 2003 | JP | national |
| Filing Document | Filing Date | Country | Kind | 371c Date |
|---|---|---|---|---|
| PCT/JP04/08407 | 6/9/2004 | WO | 12/15/2005 |
