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INVENTION
Russian Federation Patent RU2113739
APPARATUS FOR PRODUCING ELECTRICITY FROM intraatomic due to radioactive alpha or beta decay
Name of the inventor: Stanislav Viktorovich Tsivinskii
The name of the patentee: Tsivinskii Stanislav Viktorovich
Address for correspondence:
Starting date of the patent: 1997.05.23
The device consists of two closed metallic shells (emitter and collector). Emitter thin layer of radioactive metal. Between the emitter and the collector in the vacuum is a metal mesh. The mesh is attached to the high-voltage winding of the step-up transformer, fed from an industrial power, and emitter and collector are connected to the primary winding of the second step-down transformer, the secondary winding of which is connected to the electricity consumers. The radioactive alpha or beta particles are emitted from the emitter surface and fly to the manifold, and between the emitter and collector arises DC high voltage, which is an alternating voltage to the grid via a transformer converts alternating current into industrial voltage and frequency. This current is sent to the autonomous power to consumers or to the overall grid.
DESCRIPTION OF THE INVENTION
The invention relates to a device for generating electricity by the radioactive decay of atoms. It can be used to create a new type of power plants using waste from nuclear power plants that use as nuclear fuel isotopes of uranium and plutonium.
A device called a nuclear power plant [1], in which nuclear energy is released in a nuclear reactor in the form of heat by a controlled chain nuclear fission of uranium and plutonium isotopes.
Heat of nuclear fission, is used to heat steam which drives a steam turbine and associated electric generator, and thus the atomic energy is converted into electrical energy.
The disadvantage of this device - the difficulty: in addition to the energy source (nuclear reactor) required a complex system parobrazovaniya, steam turbine and generator.
A further disadvantage of this device is that most of the atomic energy is converted into heat, and smaller - in power and efficiency because the action of the device is small.
The second drawback is the additional difficulty of use and disposal of spent nuclear fuel, containing a huge amount of radioactive isotopes of nuclear fission products.
Known and atomic batteries direct action [2-4] containing the emitter in the form of a metal surface on which a thin layer of thickness 25 - 100 microns radioactive material decay as alpha or beta decay, and adjacent to the second gap-like metal surface without radioactive material called collector. In the gap between the emitter and the collector of a vacuum. Electrically charged radioactive alpha- or beta-particles emitted from the surface of the emitter, reaches the collector, whereby the emitter and collector and accumulated electric charges of opposite sign and between the emitter and the collector of a large potential difference occurs. In general, such a nuclear battery of direct action is a self-charging electrical capacitor. If the emitter and collector close the external electrical circuit, it flows through the direct current, which can be used by consumers of electricity.
The main disadvantage of all previously developed direct battery was that, although in principle, it was clear that these batteries are very promising and can produce more power, in practice, made experimental samples given current of 10 -11 A to a few microamps or a few tens of microamps at power of several milliwatts. These power sources are not of practical interest for energy.
An additional disadvantage of previously known [2-4] direct nuclear batteries was their low reliability, since the emitter made of a thin metal foil thickness of 25 - 100 microns, which is easily deformed under the influence of mechanical or electrostatic forces, and the battery fails.
The closest the technical essence and achieved result is a nuclear battery direct action proposed by the United States Patent [5] in 1950 as an abstract concept adopted in this application as a prototype. In this arrangement, the emitter is designed as a closed sphere and is centrally located in other areas that are manifold. Both spheres are metallic. The thickness of the radioactive layer on the emitter surface areas and sizes did not specify. The emitter and the collector is directly connected to the electricity consumer. The measurement voltage reached several million volts.
To remove heat generated mainly due to the collector bumps radioactive particles, it was provided for cooling air or liquid coolant.
The main drawback of the device according to US patent [5] (as in all later offers direct nuclear batteries [2-4]), is that it produces a constant current at voltages up to several million volts, while the electric current consumers calculated to alternating current at a voltage of 220-380 V and a frequency of 50 Hz. Consumers DC and are designed for voltages up to 1000 V. Since neither the US patent or in other embodiments, the atomic batteries direct action was not offered an effective electronic device to convert high voltage DC into AC electric power and frequency, before the proposed nuclear direct battery steps [2-5] could not in principle, and can not find practical use in industry and household appliances.
The purpose of the present invention - the creation on the basis of atomic prototype battery [5] powerful enough practically significant AC commercial voltage and frequency, which would, utilizing radioactive waste nuclear power plants could be an additional source of power and, in particular, could have long serve autonomous source of electricity in remote areas or in case of accidents, natural disasters or military operations, when normal power supply disabled. In addition, since its operation will be allocated a large amount of heat, it can be used for heating, for producing hot water used in the home, and even to produce additional electricity using a heat engine.
This object is achieved by the fact that a device for producing electricity from intra due to radioactive alpha or beta-decay contains two closed water-cooled or air-metal shells (emitter and collector) arranged one inside the other with a gap, inside which is supported a vacuum of 10 - 5 - 10 -6 mmHg. v., and the radioactive material is in the form of a thin layer of thickness 25-100 microns, and located on the emitter facing the gap and the other shell (collector), characterized in that the radioactive material is deposited as a metal layer on a rigid metal shell and the emitter and collector are or transverse dimensions of 0.2 to 2 m at an electrical power of 0.5-5 kW unit and 10-50 m at a power of 200-4000 kW, and in the gap between the emitter and the collector is metal control grid, electrically coupled to the secondary winding a high voltage transformer fed from the commercial power supply AC is created between the emitter and the grid alternating voltage whose amplitude is equal to the maximum potential difference, which is able to overcome a radioactive alpha or beta particle and emitter and collector electrically connected to the primary high voltage winding of the second step-down transformer, the secondary winding is connected to a common industrial AC or autonomous energy consumer.
The apparatus is characterized in that the layer of radioactive material deposited on the outer surface of the inner shell, which serves as the emitter.
The apparatus is characterized in that the radioactive material is deposited on the inner surface of the outer shell, which in this embodiment is the emitter.
The apparatus is characterized in that the shell of the emitter, collector and control grid are similar in shape and are in the form of spheres, cylinders, etc.
The essence of invention is as follows
If a closed metal shell coated on its outer surface with a thin layer of radioactive metal that decays according to the scheme of alpha or beta decay, put into another closed metal shell (for example, a sphere emitter positioned at the center of another large metal sphere, collector) and in the resulting space between the shells surfaces create a vacuum of 10 -5 - 10 -6 torr. Art., then emitted from the surface of the inner lining of the emitter-charged alpha or beta particles will be free to reach the inner surface of the outer metal shell of the reservoir and on it there will be a positive charge in the case of alpha decay and the negative beta decay. The inner shell emitter respectively will acquire a negative or positive charge. These charges will increase with time as long as the potential difference between the inner and outer sheaths is not so large that the energy of the alpha or beta particle will be insufficient to overcome this potential difference.
If the electrical wire to connect the inside (the emitter) and an outer (collector) metal sheaths, it will flow through the wire constant current whose value is determined by the flow of particles from the emitter to the collector. All the device will function as a permanent rechargeable capacitor. The dimensions and shape of the collectors and emitters can be varied as traditional forms of electric capacitors provided between the emitter and the collector is maintained vacuum. For example, they may be in the form of spheres, cylinders, and, in particular, are designed as flat plates, as in the planar electric capacitor. In order to generate a high voltage direct current to alternating current to convert the voltage and frequency of industrial between the emitter and the collector is set similar to them in the form (in the form of spheres, cylinders, etc.), a metal mesh, and an alternating voltage is applied between the grid and the emitter with 50 Hz, the amplitude value of which is equal to the maximum potential difference that can be electrically charged overcome radioactive alpha or beta particles. As a result, the device begins to work as a well-known vacuum tube triode, the anode current role in which plays a stream of charged particles from the radioactive emitter to the collector. Changes in the potential difference between the emitter and the grid causes sinusoidal variation of the current which passes through the primary winding of the HV step-down transformer and the AC electric power generated 220-380 at its secondary winding to a frequency of 50 Hz, which can be used by consumers of electricity or offline through a common AC power.
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FIG. 1 shows a diagram of the proposed device, wherein the inner and outer shell and the control grid are in the form of concentric spheres. In principle this radioactive metal layer may be deposited on the inner or outer shell, respectively, and function as the collector or the emitter.
FIG. 2 shows a diagram of the device, wherein the inner and outer metal shell and the control grid are in the form of coaxial cylinders. In this case both cladding surrounding cool air flow environment. When this layer and the radioactive metal may be deposited on the inner or outer shell, as described above, and respectively function as an emitter or a collector.
The device 1 consists of an inner, outer shell 2, the control grid 3. A thin layer of radioactive metal may be deposited on the surface of the inner shell 1 and the inner surface of the outer shell 2. The inner shell and the control grid is reinforced by the insulating spacers 4 and 5. Pumping air 6 is carried out from the space through the pipe 7. by the outer shell 2 and the inner one attached wire 8 and 9. in this FIG. One connection made via an insulating seal 10, Fig. 2 - by means of one of the metal pipes 11 or 12, in which the space 13 and cooling air 14 is passed. While nozzles 12 are passed through the insulating vacuum seal 16. In the embodiment of FIG. 1, we assume that the emitter is the inner shell 1 and the control grid 3 is connected to the high-voltage winding of the step-up transformer 17 wires 9 and 18. The primary winding of the transformer 17 is connected to a common AC power, for example, with a voltage of 220 V.
In the embodiment of FIG. 2 it is assumed that the emitter is the outer shell 2 and control grid 3 is connected to the high voltage winding of the boosting transformer 17, the wires 18 and 8, the wire 18 is passed through an insulating vacuum seal 15.
In the embodiment shown in FIG. 1, shells 1 and 2 are connected to the primary winding of the HV step-down transformer 19 by wires 8 and 9 and the embodiment of Figure 2 and shell 1 and 2 are connected by wires 19 to the transformer 8 and 9. The secondary winding of this transformer is connected to the autonomous power consumer or a common commercial power AC.
To protect the environment from potential X-ray or gamma-ray installation of FIG. 1 and 2 have a protective coating 20.
Operation is as follows. After assembly of the device through the pipe 7 the air from the space 6 between the shells 1 and 2 is evacuated with a vacuum pump to a vacuum of 10 -5 - 10 -6 Torr. Art. If radioactive metal layer deposited on the outer surface of the inner casing 1 (FIG. 1) and it is the emitter, the radioactive decay occur when charged alpha or beta particles move to the inner surface of the outer shell 2, which in this case is the collector that reaches they give her the electric charge.
When the alpha-decay particles have a positive charge, and because the outer shell collector is positively charged. The inner shell-emitter 1 acquires a negative charge. Between the shells 1 and 2, the potential difference will arise which will increase the accumulation of charges on the shells. Charge accumulation will occur as long as the energy alpha particles will be insufficient to overcome the potential difference between the shells 1 and 2. The entire device is like an electrical capacitor.
Since the energy of alpha particles emitted from decaying nuclei, usually measured several million electron-volts, and the potential difference between the shells 1 and 2 can reach several million volts.
If a transformer between the emitter 17 and control grid to create a high alternating voltage with an amplitude equal to the maximum possible voltage between the emitter and the collector in this type of radioactivity between the alternating current arises, which connection wires 8 and 9 in FIG. 1 and 2 will flow through the primary winding of the high-voltage step-down transformer 19, which converts this current into an alternating current of industrial frequency and voltage, which may be sent to the consumer or to Autonomous general electric network.
Reaching collector, alpha particles lose their electric charge and are converted to atoms of helium, which through the nozzle 7 continuously or periodically pumped out by a vacuum pump.
If the energy source used material decays to form the beta-particles, the device operation is the same as in the alpha decay, with the only difference that the emitter is positively charged, and the collector - negatively. However, this embodiment does not require continuously or periodically pumped helium gas in the space between the emitter and collector: helium in this case is formed.
If both the proposed use three identical devices, it can be obtained by a three-phase alternating current, which is commonly used in industry.
Under real conditions, there may be instances when a radioactive material are simultaneously formed alpha and beta particles. In this case, the device will work on the scheme of radioactive decay, which provides a maximum flow of charges on the outer and inner shell. This embodiment is important for operation of radioactive waste from nuclear reactors, containing various radioactive isotopes.
Calculations to prove device performance.
Initially, we describe a general method of calculation, and then apply it to specific cases.
The number of radioactive nuclei of the material disintegrating per unit time is described by equation [6] 
Where
T - the half-life; A - atomic weight; m - mass, n 0 - Avogadro's number. Since only half of the resulting alpha and beta particles may fly from the surface of the emitter, the ratio must be respected 
Where
I - current, due to the particle flow between the emitter and collector; Z - atomic number equal to the number of elementary charges an e, is numerically equal to the charge of an electron. For alpha particles, Z = 2, beta particles Z = 1.
The mass of radioactive material needed for a current equal to 
Where
en 0 = F = 9,648 · July 10 K / kmol, the Faraday constant.
For application of this mass of material with a thin layer thickness 
at a density 
on the shell surface area required 
If the shell formed as a sphere, its radius can be found by the equation 
Let the energy of the emitted alpha or beta particles is E. Then the potential difference between the inner and outer shells can reach a value of 
Power of the electric current generated by the device will
P = IV. (7)
The concrete calculations proving the efficiency of the device (for alpha versions and beta decay).
1/. Let plutonium isotope Pu 238 will be used as the material type alpha radioactivity decay, which has the following characteristics: T = 87,6 s = 2.76 * 10 9, A = 238, E = 5,5 MeV [7] . = 19.8 × 10 3 kg / m 3 [8]. As a result of calculation by the equations (1) - (7) that when m = 1000 kg = 100 mm, I = 0,1 A, V = 2,25 MV, P = 0,22 MW, R = 6,3 m.
Thus, if applied to the surface of the emitter layer of plutonium 100 microns thick, with a diameter of the spherical shell 12 meters will be received current source power of 0.22 MW, which can be considered a good feature to offer a very simple device. In this further device will generate approximately the same amount of heat that can be used for heating, for producing hot water for domestic use or for more power by using various heat engines. One such plant can provide electricity and heat to a small village. One square meter of emitter of such a facility will produce 0,430 kW of electricity and heat.
Twenty of these devices make it possible to get a power comparable to the power of the first nuclear power plant built in the USSR in 1954., Where power was 5.4 MW.
After the dissolution of plutonium Pu 238 is converted into uranium 234 U, which is sufficiently stable and can be used as raw materials in nuclear reactors to produce uranium isotope U 235 that is used as fuel in nuclear power plants.
2 /. Consider now the second embodiment of the device shown in Figure 2, in which the emitter is a cylindrical outer shell 2.
We assume that as a radioactive material, and plutonium Pu 238 used as a layer 100 microns thick. The diameter of the cylindrical emitter D = 0,4 m and its height is 1.5 m.
Given that each square meter of the emitter makes it possible to receive up to 0,430 kW of electricity and heat as well, we get the following characteristics of the device: the emitter surface area of 1.9 m 2, the total electric power of 0.82 kW and the same heat. 3 - 4 of the device, placed under the ground, can be for many years to supply electricity and heat to the house, located in a remote area (eg farm, a weather station, a military post, and the like).
3 /. Consider now the exemplary operation of Figure 1 apparatus, in which a radioactive material is used as cesium Cs 137 isotope, which decays by beta decay scheme.
Main characteristics of this isotope following: T = 30 = 9.4 * 10 8; E = 0,51 MeV; = 1.53 × 10 3 kg / m 3 [7.8]. If we take this isotope mass m = 1000 kg, and apply it to the inner surface of the sphere as a layer 100 microns thick, we obtain I = 0,25 A; V = 0,51 MW; P = 0,12 MW; sphere radius R = 23 m.
The results obtained for the isotope 137 Cs, according to their energy performance comparable with those obtained for the isotope Pu-239 and may be of practical interest.
After the collapse of 137 Cs isotope enters Ba isotope 137, which is stable.
The device for generating electricity from the energy of radioactive decay has advantages over conventional nuclear power plants operating by the energy splitting of atomic nuclei (isotopes of uranium, plutonium, thorium). For operation of the device there is no need to build a nuclear reactor near the plant. No complex system of converting thermal energy into electrical energy that is used in modern nuclear power plants.
The proposed device may not have an atomic explosion. power plant design is very simple, and it can be constructed without the large capital investment in the short term.
The big advantage of the device is that it can work, using as an energy source radioactive isotopes produced in reactors of nuclear power plants and on ships military and icebreaking fleet. Thus, to a large extent the problem of the use and disposal of nuclear waste can be solved, which is flooded in the sea or buried in the ground, which will inevitably lead to environmental contamination by radioactive waste.
The big advantage of the device is that it can be operated without additional load of radioactive material for decades.
The economic effect of the use of the device will be significant but quantitatively it is currently difficult to assess.
INFORMATION SOURCES
1. NV Saveliev Course of general physics, M .: Science, 1971, p. 469 - 472.
2. Team. ed. Fratkin GM Radioisotope sources of electrical energy. M .: Atomizdat, 1978, p. 87, 222-223.
3. William Corliss, Harvey D. Energy sources to radioactive isotopes. M .: Mir, 1967, p. 345-348.
4. Linder EG nuclear electric generator. US patent N 2661431, 1953.
5. EG Linder The method and means for producing electrical energy from nuclear reactions. US patent N 2517120, 1950.
6. BM Yavorsky, AA Detlaf Handbook of physics. Publishing house of the physical and mathematical literature. M., 1963, p. 744.
7. Physical quantities. Handbook ed. IS Grigoriev, Meilikhov E.3., Atomizdat, 1991, p. 1015, 1040.
8. Physical and chemical properties of elements. Handbook ed. GV Samsonov Publishing house "Naukova Dumka". Kiev, 1965, p. 112.
CLAIM
1. A device for producing electricity from intra due to radioactive alpha- or beta-decay, comprising two closed air or water-cooled metal shell (emitter and collector) arranged one inside the other with a gap inside which a vacuum is maintained of 10 -5 - 10 - 6 mmHg, wherein the radioactive material is in the form of a thin layer of a thickness of 25 - 100 microns, and located on the emitter facing the gap and the other shell (collector), characterized in that the radioactive material is applied in the form of a metal layer on a rigid metal shell and emitter and collector or have transverse dimensions of 0.2 - 2 m with the electric power unit of 0.5 - 5 kW and 10 - 50 m at a power of 200 - 4000 kW, and in the gap between the emitter and the collector is a metal grid management electrically connected to the secondary winding of high voltage transformer fed by an AC commercial power, creating between the emitter and the grid alternating voltage whose amplitude is equal to the maximum potential difference, which is able to overcome a radioactive alpha- or beta-particle emitter and a collector electrically connected to the primary winding of the HV the second transformer secondary winding is connected to a common industrial AC or autonomous energy consumer.
2. Device according to claim 1, characterized in that the layer of radioactive material deposited on the outer surface of the inner shell, which serves as the emitter.
3. Device according to claim 1, characterized in that the radioactive material is deposited on the inner surface of the outer shell, which in this embodiment is the emitter.
4. Device according to claims 1 - 3, characterized in that the shell of the emitter, collector and control grid are similar in shape and are in the form of spheres, cylinders, etc.
print version
Publication date 25.03.2007gg
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