US2592115A

US2592115A - Neutron source

Info

Publication number: US2592115A
Application number: US36925A
Authority: US
Inventors: Clayton C Carroll
Original assignee: United States Radium Corp
Current assignee: United States Radium Corp
Priority date: 1948-07-03
Filing date: 1948-07-03
Publication date: 1952-04-08
Anticipated expiration: 1969-04-08

Description

April 8, 1952 crc. CARROLL 2,592,115

NEUTRON a SOURCE Filed July s, 194s BY famelMM/WM ATTORNEYS Patented Apr. 8, i952 NEU'rRoN SOURCE Clayton C. Carroll, Madison, N. J., assigner to United States Radium Corporation, New York, N. Y., a corporation of Delaware Application July 3, 1948, Serial No. 36,925

(Cl. Z50-106) 34 Claims. 1

This invention relates to the production of neutrons and especially to neutron sources and the method of manufacturing them.

One of the most convenient and economical means of producing neutrons comprises a nuclear reaction of radium with beryllium. This reaction may be expressed by the following nuclear equation:

Neutron emission also results from the bombardment of beryllium by gamma rays which produces alpha particles and neutrons according to the equation:

The following nuclear reactions also may occur as a result of delayed radioactivity, but they probably represent only a small increment in the total neutron emission:

Ideally, a homogeneous dispersion of monoatomioradium throughout an iniinite number of beryllium atoms will produce a maximum of neutrons. The nearest approach to such a relation would result from an alloy of radium and beryllium metals. However, a true alloy of this nature has never been produced due, in part, to the facts that beryllium has an extremely high melting point and that both beryllium and radium are readily oxidized.

YThe nearest practical approach to an actual alloy has been achieved by the intimate dispersion of radioactive metal salts in powdered beryllium. This dispersion has Yheretofore been produced by the evaporation of a solution of a salt, such as an aqueous solution of radium chloride or bromide in the presence of beryllium powder. The resultant mixture was then dried and compressed into a pellet and sealed in a container, usually somewhat larger than the pellet.

i Several disadvantages are inherent in such a method, although some of them have not heretofore been appreciated. While it is possible to produce microscopic crystal deposits of the radiuml salt on the surface of the beryllium partif neutron emission. Also,l the emission efficiency is low because of the absorption function of the radium salt crystals which will intercept and stop part of the alpha radiation before it collides with the beryllium surface. It is impossible to prevent localized deposits of crystals at the time when the mixture approaches the dry state. Additionally, most of the soluble radium salts are hygroscopic, from which it follows that extreme precaution must be used to seal the containersso as to exclude moisture. The presence of water vapor in the lclosed container with a radio-active substance eventually results in the development of dangerous gas pressures due to decomposition of the water by radium, and also the free oxygen causes oxidation of the beryllium metal. Lastly, the mechanical difficulties of keeping a suspension of metal powder in a radium solution agitated during evaporation renders the operation hazardous to the operator. The foregoing and other factors have heretofore contributed to such non-uniformity of neutron emission that any two sources intended to have like emission would vary over a wide range, and even these would vary over a period of time.

On the other hand, the neutron source of the present invention is extremely stable; and any number of such sources may be made to provide the same emission and to maintain it. The invention includes an improved neutron-emitting dispersion product and method of manufacture ing it, as well as an improvedv capsule or container for the product. In combination, these components provide all the advantages here set forth.

In accordance with the method of the present invention extremely fine beryllium particles are individually coated and combined with a radium salt to form a new radium-beryllium dispersion product, and a quantity of this product is then preferably encased within or surrounded Yby a layer or jacket of non-radioactive beryllium metal so as to increase the chances that each alpha `particle emitted by the radium will collide with a beryllium nucleus to produce a neu tron. For this purpose it is preferable that the jacket be in contact with as many as possible of the adjacent radium-coated particles. The product thus encased is placed within a suitable capsule which is then preferably heated toa temperature of about 1500 F. to reduce the radium salt to radium metal, with the result that the dispersion of radium in the beryllium is considerably increased. The capsule is then lermetically sealed and may be readily transported and inanipulated as required.

In addition to radium, other radioactive materials may be employed as sources of alpha particles in accordance with the invention, such materials including actinium-X, thorium-X and mesothorium. While the latter is not an alpha emitter, it is a radium isotope and rapidly decays into alpha-emitting products.

The preferred method of manufacturing the radium-beryllium dispersion product together with several modifications in accordance with the invention is described below. The construction of a capsule andthe contents thereof arranged in accordance with the invention is illustrated in the drawing wherein:

Fig. 1 shows in cross sectionya capsule corn-` prising a neutron source according to the invention, this section being taken along the line l-l of Fig. 2;

Fig. 2 is a plan view of the capsule of Figfl;

and

Fig. 3 shows an alternative modification of the capsule of Fig. 1 in which the bottom is removable.

As above indicated, it has heretofore been proposed to employ as a neutron source a mixture of powdered beryllium and a radioactive salt such as radium chloride or radium bromide. The product of the present invention differs in several important respects from such previous mixtures, including the fact that an insoluble radium salt is directly deposited on the surface of and chemically combined with each beryllium particle. As a result, the physical association of the beryllium and radium salt is more intimate by a considerable degree than in any product heretofore known. Furthermore, the radium salt crystals are more uniform and are smaller than in the previous mixtures so that a given alpha particle is less likely to be wasted by being intercepted by a salt crystal and prevented from collision with a beryllium surface. `Since the absorption of alpha particles by the crystal compounds is approximately in proportion to the square root of their molecular weights, the stopping power of radium bromide, for example, is nearly 1.2 times that of the carbonate. Also, the dispersion product made by the method of this invention is mechanically stable because the radium salt is rmly attached to the beryllium surface. To this end, the anion should be so chosen that its combination with beryllium likewise forms an insoluble salt. For this reason, the carbonate is preferred because it forms with both radium and beryllium, salts which are substantially insoluble. The particle size of the beryllium and the radioactive material are, in general, to be as small as'practicable, for example, the beryllium particles should be of a size which should pass through a 325 mesh screen, viz., should be not substantially larger than 325 mesh.y If the particles are thus graded by a 325 mesh screen the average particle size will be somewhat less than 44 microns. The radioactive particles should be no larger than of the order of one-twentieth as large as the beryllium particles, and hence may be of the order of 2 microns, and preferably smaller. By employing radioactive particles of this extremely small order of magnitude, a more uniform and intimate dispersion is attained, and also the chances of interception and absorption of radiations from adjacent radioactive particles are minimized. Precipitation from alcoholic solution results in the formation of nner crystals (viz., less than one micron thick, Yand 4 approaching molecular thickness) and decreases the solubility of radium carbonate and hence is preferred in the method of the invention.

An important aspect of the present invention resides in the discovery that a closer approach to an ideal dispersion is achieved when a mixture of radium carbonate and beryllium, as above described, is heated to a temperature at which radium has appreciable vapor pressure, viz., between 1400 F. and 1500 F. In the presence of beryllium metal, the reaction is believed to be as follows:

RaCO3+5Be 3BeO+Be2C+Ra (6) From this equation, it will be noted that the carbide of beryllium, but not the carbide of radium, is formed. The fact that elemental radium metal but no radium carbide is formed has been ascertained experimentally. In this manner metallic radium may be deposited on the surfaces of beryllium particles, which results in a highly efficient neutron source comprising beryllium particles a substantial portion of the surface area of which is coated with a lm of elemental radium of substantially uniform thickness. If the process is carefully carried out, the beryllium particles will be substantially enveloped with a film of metallic radium. As is pointed out below, it is preferable that such radium-coated or radium-enveloped beryllium particles be interspersed with uncoated, non-radioactive beryllium particles to increase the eilciency of the source.

It has also been found that at a temperature of about 1850" F. and more, radium carbonate decomposes into radium oxide and carbon dioxide.

In the presence of beryllium metal, this reaction proceeds to produce beryllium oxide and radium metal. These reactions may be written as follows:

RaCOa-RaO-l-COz (7) RaO-i-Be-BeO-i-Ra (8) However, because of the difficulties introduced by the high temperature and other considerations connected with reactions (7) and (8), thereaction indicated in Equation 6 is preferred.

If the heating is carried on under reduced pressure the radium may be deposited on the inside of the container or on other objects placed within it, which may be desirable for .some purposes. However, to retain the radium metal within the mixture, it is desirable to heat the mixture at atmospheric pressure or above. Since both beryllium and radium are readily oxidized, the reaction must be carried out in either a neutral or a reducing atmosphere. Radium forms a volatile hydride and beryllium forms a nitride at the temperature of the reaction, so neither aY hydrogen nor a nitrogen atmosphere is appropriate in this case. Suitable neutral atmospheres may be provided by the inert gases: helium, argon, n'eon, etc. Because of the high degree of purity Yobtainable, argon is here preferred. Th stoichiometric quantity of beryllium required in accordance with the Equation 6 is 0.16 mg. of beryllium metal per milligram of radium. If substantially more than this quantity is used for precipitation and then an additional amount of beryllium is ground in with the mixture in accordance with the procedure below described,a minimum of self-absorption of alpha particles results, and the chances of collision between an outwardly projected particle with a fresh'beryllium surface are increased.

The inal mixture may then be pressed into a, pellet by a suitable die and plunger arrangement, or preferably it may be pressed into a container directly. -An advantage in the latter procedure results from the fact that it permits the use of a beryllium-coated foil of a metal, such asl silver or platinum, between the walls of the container and the active mass. By this means,

the alpha particles which normally would be lost in the ywalls of the container are made to collide with a beryllium surface thus again to increase the4 chances of producing neutrons. The advantages just described will result from the use of any of the other alpha-emitting radioactive materials among which are thorium, polonlum and plutonium.

The mentioned compression of the powdered -constituents results, as is well known in the art of powder metallurgy, -in a smaller and more stable product. This may be important in connection with various applications requiring a neutronsource of minimum dimensions, and especially in measurements depending on an assumed point source. For this reason a sphere lwould be preferred, because it has the smallest surface area per unit volume, and should have 'uniform radiation in all directions, but inasmuch a 'invention comprises placing the precipitated mixture in the center of an inactive mass oi beryllium powder which in turn is contained in a capsule comprising a cylinder of stainless steel or other non-corrosive metal such as an alloy essentially of nichel and copper with a small proportion of iron, known as MoneL then subjecting 'the entire mass to pressure and thereafter heating it to approximately 1500 F. in an vinert atmosphere, cooling in the same atmosphere and then sealing the capsule hermetically. By this process the radium as a metal is 'made to diffuse throughout the Iberyllium mass to a greater degree, and with more uniformity, than has heretofore been achieved with radium a compounds.

vThe v following examples will illustrate the method of the invention more generally discussed above.

To a neutral or an alkaline solution (viz., one

`having a pH greater than about 6) of 300 mg. of 'radium element as a soluble salt such as the bromide' or chloride dissolved in approximately 15 Inl.- of water, is added 30 ml. of 95% ethyl alcohol,fa weighed quantity consisting of approxi- 'mately one gram of high purity beryllium powder of approximately 325 mesh, or smaller if obtainable, is carefully added with stirring. The radium is' then precipitated by the slow addition 'with stirring of a solution of 600 mg. of ammonium carbonate in ml. of water. The mixture-is stirred intermittently for one-half to one .hour and then allowed to stand for twelve or more hours.

An additional 100 mg. of beryllium powder is then' weighed on the mat of a tared 30 ml. fine porosity fritted Pyrex glass Crucible. A few milliliters of 50% ethyl alcohol are added. and the.

mixture is swirled'until the Iberyllium is in suspension. The powder is allowed to settle for a few minutes and then the alcohol is drawn through with suction. The active material -prepared as outlined in the last preceding paragraph is then ltered through the resultant mat and washed with 50% alcohol until the ltrate shows no chloride ion when tested with silver nitrate. The mixture is heated for approximately one hour at 110 C. to drive off the alcohol.

If the mixture is to be sealed without further heat treatment, suflicient beryllium powder to bring the total used to 2500 mg. is weighed into a boron carb-ide mortar. The active material is transferred to the mortar and ground for minutes using a boron carbide pestle. The -active material thus ground is then ready for transfer to the container or capsule of which a suitable i'orm in accordance with the invention is il lustrated in the drawing.

Referring to Fig. l, the capsule may comprise a container or shell i having a central cavity therein. The upper portion of the inside surface of the shell is threaded to receive a plug 2. By way of example, the cavity might 'be l inch long by 5- inch in diameter, and the'walls of the shell about fle inch thick, although any desired dimensions may be' used. In accordance with the invention it is preferable that the core of the active material be completely surrounded by beryllium metal. Consequently, before any of the active mixture is inserted into the cavity, a cylinder 3 of a foil of suitable metal, such as platinum or silver, of which a surface has been coated with a layer of beryllium powder, is inserted within the cavity so as to line the same. A layer of beryllium powder 4 is then deposited in the bottom of the cavity within the foil cylinder, and is pressed in place. The radiumberyllium mixture is then transferred to the tared container in three cr-four portions, each portion .being pressed down before the next one is added so as to form a co-mpact mass 5. After the last portion or" active material has been pressed down, a quantity, for example approximately 200 mg., of non-radioactive beryllium square inch is a suitable pressure.

. venience in handling the capsule, a rod 8 terminating in a handle 9 may be screwed into a smaller threaded hole, as shown, in the top of plug 2. Although the dimensions of the capsule and of the active material within it may be of any values desired, satisfactory capsules have been made pursuant to the invention in which the cylinders of compressed radium-beryllium mixture have varied in height from about once to twice their diameters. In these instances the diameters of the cylinders varied from Tag inch to inch.

It is well known that radon, which is a gas, resuits from decay of radium, and thatv the decay of radium, of radon, and also of some of the decay products of radon, is accompanied by emission of alpha particles. Consequently, it is of importance to retain within the capsule-of this invention all of the products resulting from the decay of the radium and so to-locatethe beryllium within the capsule as vto assure' the 7 maximum opportunity for collision of these alpha particles with a beryllium surface.

An alternative construction is illustrated in Fig. 3 which shows a bottom plug I0 sealed with a solder seal H similar to the seal 'l at the top of the plug. Although in general it is preferable to form capsules for the present lpurpose with as few openings as possible, a removable bottom plug is in .some instances desirable to facilitate emptying the capsule, as for example, if it be desired to recover the radium in the mixture. In that levent by removing the topfand bottom plugs the contents of the capsule can be pushed out and the capsule cavity washed if desired. Otherwise the contents can most readily be removed by cuttingout the bottom of the capsule.

In the foregoing description referring to Fig. 1, the layer 3 surrounding the mass 5 of radiumv,beryllium has been stated to comprise a suitable 4metal foil coated with beryllium metal. An alternative embodiment and one which in many instances is preferable, comprises the substitution of a layer of powdered beryllium metal for the mentioned foil. In this event the capsule may be loaded as follows: First a layer 4 of beryllium 4metal powder' is placed inv the bottom of the capsule and pressed down. Next, a rod or plug, yhaving the diameter of the final compacted mass or pellet 5 of the radium-beryllium mixture is centered in the cavity of the capsule and beryl- 4*lium metal powder is poured in the space between lthe plug and the inside wall of the capsule l to form a sleeve 3 of powdered metal. This pow- 'dered metal sleeve is compacted from time to time during the filling process by pressing on the top of it a length of metal tubing which is of size suitable to fit snugly within the space around the central plug. After this sleeve of metal powder has been compacted around the central plug it will remain in place, so the plug is withdrawn and a suitable quantity of the radium-beryllium powder mixture is poured into the cavity within the beryllium sleeve, and tamped periodicallyV during the filling process, as above described. Thereafter the inactive top layer 6 of beryllium is added, compacted under high pressure, andthe capsule sealed, as before. The construction resulting from either of the embodiments above described provides a core or pellet of radiumy beryllium completely surrounded by a layer or jacket of beryllium metal, which as above explained, increases the neutron emission and thus the efficiency of the capsule as a neutron source.

Various alternative constructions and variations of the embodiments above described, all within the invention, will occur to those skilled in the art. Three such variations comprise the substitution for the

layers

4 and 6 of powdered beryllium metal, a disc of solid berylliumv metal, or the plugs 2 and I0 may be formed of beryllium, or the inner ends of such plugs may becoated with beryllium. In any event, the object is to lform a beryllium jacket enclosing and preferably in contact with the radium-beryllium mixture. The thickness of the beryllium jacket is unimportant so long as it is thick enough to intercept substantially all of the alpha particles.

It has already been explained that greater distribution of the radium in the radium-beryllium mixture is achieved by heating the mixture. If

vthe mixture is to be heated in accordance with theinvention it is first transferred to a mortar `without addition of further beryllium powder ,and ground forl aboutominutes'. A piece of annealed platinum foil, of. say, 0.005 inch thickness, is then cut to such dimensions that it may later serve as a cylindrical liner or sleeve 3 (Fig. 1) for the capsule intended to be used. By bending upward two or three millimeters of each edge of this piece of foil a small boat is formed into which a uniform layer of inactive beryllium metal powder is placed so as to cover the bottom and sides of Vthe boat. The active material is then transferred from the mortar to this boat which is placed on a support in a quartz tube of which one end is closed. The air in the quartz tube is displaced by alternately evacuating to, say, 20 mm., and filling it with argon gas at a pressure of approximately one pound in excess of atmospheric pressure, five or more times. The tube is then placed in a combustion furnace the temperature of which has previously been raised to approximately 1500 F. and is heated under pressure for one to two hours. After heating, the tube is removed from the furnace and allowed to cool to room temperature in an argon atmosphere. As before, sufficient beryllium powder to bring the total, including the radium-beryllium mixture cooled as just mentioned, to approximately 2500 mg. is weighed into a boron carbide mortar and the contents of the mortar ground for approximately 30 minutes, preferably in an argon atmosphere. The platinum boat may then be flattened, formed into a cylinder on a suitable mandrel, and inserted into the capsule, active side in, to form the cylinder 3 above mentioned. The ground mixture of active and inactive material is then added, pressed in as before, and the container sealed.

l.Tn the event that the capsule structure includes a beryllium sleeve 3 of powdered beryllium metal, and it is to be heated, the procedure above described may be modified as follows: After the entire mass, comprising a radium-beryllium core within a powdered beryllium jacket, has been subjected to a high pressure such as that of 25 tons per square inch above mentioned, the top plug is screwed into place and the capsule is placed in the closed quartz tube as above described. The air is then displaced by pumping argon in and out, as mentioned, after which the capsule containing the mixture is heated at about 1500 F. lfor approximately 2 hours, and the capsule is sealed with solder as before.

The mentioned operation of grinding the radium-beryllium mixture with additional beryllium powder results in a more uniform mixture and one in' which the radium is dispersed in more intimate contact with the beryllium, both being desirable. The grinding does not detach the radium compound from the surface of the beryllium metal= particles to any appreciable degree except in the event that the crystal deposit is unusually thick. Thick crystal deposits, if any, are likely to be broken off by the grinding, and this is an advantage, because it decreases the probability that any given alpha particle will be intercepted by an undesirable thickness of salt which might prevent it from striking a beryllium surface. The reason for the unusually strong adhesion between the beryllium particles and the radium carbonate crystals attached to the surface thereof as a result of the present method is not clearly understood, but it is evident that the radium carbonate is chemically attached to the beryllium. The surface of the beryllium particles is chemically active, even in a water slurry, and since this metal forms an insoluble carbonate whenlcarbonate ion is added to solutions of its salts, an actual system of coordinate valence obtains when radium carbonate is precipitated in the presence of beryllium powder.

What I claim is:

1. A neutron source comprising a mass of minute beryllium metal particles substantially completely coated with radium carbonate crystals in rm adherence to the surface of said particles and of a thickness not exceeding approximately one micron. s

2. A neutron source comprising a mass o1 beryllium metal particles not substantially larger than 325 mesh coated with radium carbonate crystals deposited thereon as an insoluble precipitate.

3. A neutron source comprising a compacted mass of beryllium particles, the surfaces of said particles comprising carbonate ions chemically combined with radium and beryllium.

4. A neutron source comprising a mass of minute beryllium metal particles each of which is substantially coated with radium carbonate crystals in rm adherence to the surface of saidzparticles, intimately mixed with an approximately equal weight of uncoated beryllium metal particles.

5. The method of making a neutron source which comprises compressing in a capsule a mixture of beryllium powder and radium carbonate, heating said compressed mixture in an'atmosphere of inert gas at a temperature sufficient .to form beryllium oxide and radium, cooling the capsule and its contents in said atmosphere .and hermetically sealing said capsule.

6. The method of making a neutron source which comprises compressing in a capsule a mixture of beryllium powder and a radioactive substance, heating said compressed mixture to approximately 1500" F. in an atmosphere of inert gas, cooling the capsule and its contents irl-said atmosphere, and hermetically sealing the capsule.

7. The method of making a neutron source which comprises compressing in a capsule a mixture of beryllium powder and a mass of beryllium particles each of which is substantially coated with crystals of a radioactive substance, heating said compressed mixture to approximately 1500o F. in an atmosphere of inert gas, cooling the capsule and its contents in said atmosphere, and hermetically sealing the capsule.

8.,The method of making a neutron source which comprises chemically precipitating crystals 'of radium carbonate on the surfaces of minute particles of beryllium, grinding the coated particles together with additional uncoated beryllium particles to form a powdel` mixture, compressing a quantity of, said mixture within a casing of non-radioactive beryllium, and sealing the resulting product within a capsule.

9. The method or" making a neutron source which comprises chemically precipitating crystals of radium carbonate on the surfaces of minute particles of beryllium, grinding the coated particles together with additional uncoated beryllium particles to form a powder mixture, compressing a quantity of said mixture within a capsule, and sealing the capsule.

1D. The method of making a neutron source which comprises chemically precipitating crystals of radium carbonate on the surface of minute particles of beryllium, grinding the coated particles together with additional uncoated beryllium particles to form a powder mixture,

and1 sealing a quantity of said mixture in a capsule.

- ll. In the method of making a neutron source, the step which comprises precipitating radium in the form of a carbonate in situ on nely divided particles of metallic beryllium whereby the surfaces of said particles are coated with a tenacious radioactive lm.

12. In the method of making a neutron source, the steps which comprise, precipitating radium rom a non-acidic alcoholic solution of a soluble salt of radium by the addition of ammonium carbonate while stirring into the solution a. quantity of minute particlesl of beryllium metal, whereby radium in the form of a carbonate is precipitated in situ on the surfaces of said particles and forms a tenacious radioactive coating thereon.

13. The method of making la, neutron source which comprises enclosing in a container a mixture of beryllium particles and radium carbonate, and heating said mixture to a temperature between approximately 14:00o F. and approximately 1500 F., whereby the radium carbonate is decomposed to metallic radium and the` metallic radium is dispersed among and deposited on surfaces of said beryllium particles.

14. The method according to claim 13 charactcrized in that said mixture is heated in an inert gas atmosphere and is subsequently cooled in the same atmosphere.

v15. The method according to claim 13 characterized in that the radium carbonate is admixed with the beryllium by precipitating it on the beryllium particles.

16. The method 0f making a neutron source which comprises enclosing in a container a mixture of beryllium particles and radium carbonate, and heating said mixture to a temperature between approximately 1400 F. and approximately 1500 F. whereby the radium carbonate is decomposed and particles of beryllium oxide and beryllium carbide are formed and whereby metallic radium is deposited on surfaces 0f said particles. 17. A neutron source including a mass of a nely divided radioactive substance intimately dispersed among particles of a material which emits neutrons when exposed to the radioactivity of such substance, the particles of said radioactive substance being of a size not substantially larger than two microns. and the particles of said material being not substantially larger than twenty times the size of said radioactive particles, and a jacket completely surrounding said mass, said jacket being formed of a non-radio, active material which emits neutrons when exposed to radioactivity of said substance.

18. A neutron source including a mass of finely A divided alpha-emitting radioactive substance intimately dispersed among particles of-a material which emits neutrons when exposed to alpha radiation, the particles of said material being not substantially larger than forty microns, and the particles 0f said radioactive substance being not substantially larger than two microns, whereby minimum interception of alpha radiation occurs in the particles of said radioactive substance.

19. A neutron source including a mass of a iinely divided radioactive substance intimately and uniformly dispersed among particles of beryllium, the particles of said radioactive substance being of a size not substantially larger than two microns and the particles of said beryllium being not substantially larger than forty microns, and a jacket completely surrounding said mass, said jacket being formed of a non-radioactive lll , 11- material which emits neutrons when exposed to the radioactivity of said substance.

20. A neutron source comprising a mass of a finely divided radioactive substance which includes a form of radium intimately dispersed among particles of beryllium. the size of said particles of beryllium being not substantially larger than forty microns, and the size of the particles of said radioactive substance being not substantially larger than two microns whereby minimum absorption of alpha radiation occurs in the particles of said radioactive substance, and a jacket completely surrounding said mass, said jacket .being formed of a non-radioactive material which emits neutrons when exposed to the radioactivity of said substance.

21. A neutron source including a mass of finely divided radioactive substance intimately dispersed among particles of beryllium, said substance comprising a salt of a metal selected from the radioactive group which includes radium, actinium-X, thorium-X and mesothorium, the particles of said radioactive substance being of a size not substantially larger than two microns and the particles of said beryllium being not substantially larger than forty microns, and a jacket completely surrounding said mass, said jacket being formed of a non-radioactive material Which emits neutrons when exposed to the radioactivity of said substance.

22. A neutron source comprising a. mixture of beryllium particles not substantially larger than 325 mesh and a salt of a radioactive metal divided into particles not substantially larger than one-twentieth as large as those of Athe beryllium, a layer of non-radioactive beryllium enclosing said mixture, and a hermetically sealed capsule enclosing the same.

23. A neutron source according to claim 22 characterized in that said beryllium particles are coated with a salt of a radioactive metal which comprises particles of the maximum dimension of which is less than one micron.

24. A neutron source comprising a mixture of beryllium particles not substantially larger than 325 mesh, and a radioactive substance divided into particles not substantially larger than onetwentieth as large as those of the beryllium, a layer of non-radioactive beryllium enclosing said mixture, and a sealed capsule enclosing the same.

25. A neutron source according to claim 24, characterized in that said beryllium particles are coated with a radioactive substance comprising particles Vof which the maximum thickness is less than one micron.

26. A neutron source according to claim 24, characterized in that said beryllium particles are coated with crystals of radium carbonate.

27. A neutron source comprising a quantity of divided beryllium substantially enveloped with a lm of elemental radium metal.

29. An article of manufacture comprising metallic beryllium substantially enveloped with a' film of metallic radium.

30. The method of depositing a radium-oontaining coating on an object which includes enclosing said object in a vessel with radium carbonate in contact with elemental beryllium and heating the contents of the vessel to a temperature suiiciently high to cause reduction of the radium carbonate to elemental radium and vaporization of radium metal. Y

3l. .The method of coating an object with metallic radium which comprises enclosing said object in a vessel with radium carbonate in contact with elemental beryllium and heating the radium-beryllium mixture to a temperature at which radium has an appreciable vapor pressure and of at least 1400 F., maintaining the mixture at said temperature at least until the amount of radium required for coating said article has been liberated from the radium carbonate, and cooling said vessel.

32. The method of coating an object with metallic radium which includes enclosing said object in a, vessel with radium carbonate in contact with elemental beryllium and in an inert atmosphere, and heating the contents of the vessel to a temperature suiciently high to vaporize radium.

33. The method of producing metallic radium which comprises heating radium carbonate in contact With metallic beryllium.

34. As an article of manufacture, an object a substantial portion of the surface area of which is coated with a nlm of elemental radium metal of substantially uniform thickness.

CLAYTON C. CARROLL.

REFERENCES CITED The following references are of record in the tile of this patent:

UNITED STATES PATENTS Number Name Date 1,061,674 Hoyt May 13, 1913 1,718,899 Fischer June25, 1929 2,326,631 Fischer Aug. 10, 1943 2,440,999 Anderson May 4, 1948 FOREIGN PATENTS Number Country Date 114,150 Australia May 2, 1940

Claims

4. A NEUTRON SOURCE COMPRISING A MASS OF MINUTE BERYLLIUM METAL PARTICLES EACH OF WHICH IS SUBSTANTIALLY COATED WITH RADIUM CARBONATE CRYSTALS IN FIRM ADHERENCE TO THE SURFACE OF SAID PARTICLES, INTIMATELY MIXED WITH AN APPROXIMATELY EQUAL WEIGHT OF UNCOATED BERYLLIUM METAL PARTICLES.
21. A NEUTRON SOURCE INCLUDING A MASS OF FINELY DIVIDED RADIOACTIVE SUBSTANCE INTIMATELY DISPERSED AMONG PARTICLES OF BERYLLIUM, SAID SUBSTANCE COMPRISING A SALT OF A METAL SELECTED FROM THE RADIOACTIVE GROUP WHICH INCLUDES RADIUM, ACTINIUM-X, THORIUM-X AND MESOTHORIUM, THE PARTICLES OF SAID RADIOACTIVE SUBSTANCE BEING OF A SIZE NOT SUBSTANTIALLY LARGER THAN TWO MICRONS AND THE PARTICLES OF SAID BERYLLIUM BEING NOT SUBSTANTIALLY LARGER THAN FORTY MICRONS, AND A JACKET COMPLETELY SURROUNDING SAID MASS, SAID JACKET BEING FORMED OF A NON-RADIOACTIVE MATERIAL WHICH EMITS NEUTRONS WHEN EXPOSED TO THE RADIOACTIVITY OF SAID SUBSTANCE.