Transmutation of Nuclear Waste
Field Essence of Nuclear Physics
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A Real Cure for Chernobyl?
Ukrainian mathematician and scientist Anatoly Kinderevich has developed a practical way to render nuclear wastes less harmful. In a specially constructed chamber, hazardous radionuclides are transmuted into less harmful elements. The method could not only make Chernobyl safer, but also lead to many other new technologies. The scientists and engineers under Kinderevichís leadership have demonstrated successfully controlled accelerated decay of strontium, cesium, and Chernobyl samples.
To date, in various laboratories throughout the world, there have been at least ten successful experiments demonstrating controlled accelerated decay of radioactive isotopes. All have involved high-energy bombardment of nuclei and are prohibitively expensive. Kinderevichís approach could be the first economically feasible one.
Field Essence of Nuclear Physics (2005, 340 pp.) is rigorously mathematic and completely integrates Kozyrevís time-space flows of structurization and destructurization with models of the Coulomb barrier, thereby providing a new understanding of relativity and resolving the particle/quantum question elegantly. The Kinderevich Field Theory also explains gravity clearly and succinctly in relation to electromagnetics. The book has recently been translated into English by Randall Roffe and Vyacheslav Varetsky, a physicist at the Center of Radiation Medicine of the Ukraine Academy of Medical Sciences. Fundamentals of Field Physics (2000) and Experimental Gravitonics in the Field Physics Paradigm (2004) are currently in translation.
For more information:
de [email protected]
President, Ukraine Chiropractic Association
Nation Member World Federation of Chiropractic
In Formal Relations with United Nations World Health Organization
Member International Sports Chiropractic Federation
In Formal Relations with UNESCO
United States Patent Application 20040238366
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Vladimirovich, Kinderevich Anatoly, et al.
( December 2, 2004 )
Method and System with Apparatus for Acceleration of Activity Decrease and Radioactive Material Deactivation
Abstract -- Radioactive material can be processed by an apparatus that includes at least a cylindrical outer shell electrode, an inner electrode, and a plurality of prism-shaped ferromagnetic elements positioned between the outer and inner electrodes. The prism-shaped ferromagnetic elements are positioned around the inner circumference of the metal cylinder. The inner electrode component is located within the metal cylinder and is configured to cover the inwardly-pointing portions of the prism-shaped ferromagnetic elements. Radioactive material in a container is placed into the apparatus, and an AC voltage excitation signal is applied to the electrodes of the apparatus during treatment of the material. The frequency of the excitation signal is selected according to the frequency of structurization or the frequency of destructurization of the ferromagnetic material. The process can be monitored and controlled with the use of alpha, beta, and gamma radiation intensity measuring instruments.
Inventors: Vladimirovich, Kinderevich Anatoly; (Kiev, UA) ; Ivanovich, Kicha Leonid; (Kiev, UA)
Correspondence Name and Address:
MARK M. TAKAHASHI
GRAY CARY WARE & FREIDENRICH, LLP
4365 EXECUTIVE DRIVE, SUITE 1100
SAN DIEGO, CA 92121-2133 USA
U.S. Current Class: 205/43; 204/230.2; 204/242; 588/1
U.S. Class at Publication: 205/043; 588/001; 204/230.2; 204/242
Intern'l Class: G21F 009/00; C25B 001/00; C25C 001/22; C25C 003/34
FIELD OF THE INVENTION
 The present invention relates generally to the field of applied physics, and deals with the acceleration of processes of activity decrease and deactivation of radioactive materials of high and low activity levels. More particularly, the present invention relates to the treatment of radioactive material such as waste from nuclear power plants.
BACKGROUND OF THE INVENTION
 Worldwide development of nuclear power engineering has created a problem that is progressively turning into a global ecological issue. Namely, this problem relates to the accumulation, processing, and storing of radioactive waste materials. The United States, France, and Russia process the nuclear waste that has accumulated over time. Such processing is partial in that only five or six isotopes are returned into the new fuel cycle, while other isotopes are no longer suitable for utilization.
 There are approximately 50 actinides accumulated in every nuclear reactor at the end of each operating period, and 20 of the actinides are long-living isotopes that remain highly radiotoxic despite long periods of aging. Such nuclear waste is typically stored in special containers buried deep below the surface of the earth; nevertheless, this storage method can be the source of ecological problems and the subject of controversy and concern. Existing processing technologies for radioactive waste are very expensive, laborious, not environmentally safe, and are time consuming.
 Consequently, there exists a need for new techniques of acceleration of the processes of activity decrease and deactivation of radioactive material (hereinafter referred to as "treatment" of radioactive material).
BRIEF SUMMARY OF THE INVENTION
 The method of activity decrease and deactivation of radioactive materials uses a system that includes an apparatus for treatment of radioactive material configured to function as a large hollow capacitor having a ferromagnetic material in lieu of a dielectric material. The system includes a power source, such as a signal generator that supplies a suitable AC voltage of adjustable frequency to the apparatus. A container with radioactive material is placed into the cavity of the apparatus, an appropriate frequency is selected for the signal generator, and the AC voltage at the selected frequency is applied to the apparatus until activity of the radioactive material is decreased to the permissible level or until complete deactivation has occurred. These processes are monitored with alpha, beta, and gamma meters.
BRIEF DESCRIPTION OF THE DRAWINGS
 A more complete understanding of the present invention may be derived by referring to the detailed description and claims when considered in conjunction with the following Figures, wherein like reference numbers refer to similar elements throughout the Figures.
 FIG. 1 is a schematic block diagram of a system for treating radioactive material;
 FIG. 2 is a longitudinal sectional view of an apparatus for treating radioactive material;
 FIG. 3 is a cross sectional view of the apparatus shown in FIG. 2, as viewed from line 3-3; and
 FIG. 4 is a sectional view of a portion of the apparatus, showing the direction of the emitted flows focusing.
DETAILED DESCRIPTION OF A PREFERRED EMBODIMENT
 It should be appreciated that the particular implementations shown and described herein are illustrative of the invention and its best mode and are not intended to otherwise limit the scope of the invention in any way. Indeed, for the sake of brevity, conventional aspects of the systems (and the individual operating components of the systems) may not be described in detail herein. Also, dimensions of components of the apparatus of radioactive material treatment, which differ in each specific case of application, are not provided.
 The term "radioactive material" as used herein comprises all wastes contaminated with radioactive substances in the quantities exceeding the established standards and rules. Solid wastes are considered radioactive if specific medical exploitation dose at the distance of 1 centimeter from the given waste exceeds 0.84 milliroentgen hour per kilogram or specific activity exceeds 2.times.10.sup.-6 and 1.times.10.sup.-8 Ci/kg (7.times.10.sup.4 and 3.7.times.10.sup.2 Bq/kg), respectively, for beta- and alpha-active and transuranium elements. All radioactive isotopes, nuclear wastes can be conventionally subdivided into highly active, when specific activity amounts to 10.sup.15-10.sup.14 Bq/kg, medium active, 10.sup.13-10.sup.9 Bq/kg, low active, 10.sup.8 Bq/kg.
 FIG. 1 is a schematic block diagram of a system 100 for the treatment of radioactive material. System 100 includes at least the following components: a treatment apparatus 102 configured as a hollow capacitor of complicated shape which holds a container (capsule) 103 for holding radioactive material; an excitation signal generator 104 connected to the treatment apparatus 102 with a high frequency cable 105; one or more alpha-, beta-, and gamma-activity sensors 106 located in the container; and a grounded shielding device 107. The dashed line in FIG. 1 indicates that the activity sensor 106 may, but need not, be connected to the generator 104 for purposes of feedback control.
 The treatment apparatus 102 is generally configured as a special capacitor having an external shell electrode and an inner electrode. In lieu of a conventional dielectric material, the treatment apparatus 102 utilizes a ferromagnetic material located between the two electrodes. The treatment apparatus 102 includes a cavity formed therein; the cavity receives the container (capsule) with radioactive material. The container is positioned inside of the cavity during treatment of the material.
 The adjustable generator 104 is connected to the electrodes of the capacitor 102, and is used for supplying AC voltage of suitable frequency, at which the so-called flows of structurization or destructurization are excited in the ferromagnetic and focused inside of the apparatus. These flows cause deceleration or acceleration of radioactive decay and spontaneous radioactive decay in the container.
 Meters 106, which can be off-the-shelf commercially available instruments, are used to measure the intensity of alpha-, beta-, and gamma-radiation of the radioactive materials in the container. The readings of these detectors are used for monitoring of the technological process.
 FIGS. 2 and 3 are views of sections of an apparatus 200 for treating radioactive material. FIG. 2 is a longitudinal sectional view of apparatus 200, as viewed from line 2-2 in FIG. 3 (line 2-2 represents a line that intersects the longitudinal axis of apparatus 200), and FIG. 3 is a cross sectional view of apparatus 200, as viewed from line 3-3 in FIG. 2. FIG. 4 is a cross sectional view of a portion of the apparatus, which shows the direction of the excited flows (of structurization or destructurization) focusing.
 Apparatus 200 generally includes an outer shell electrode 202, an inner electrode 204, a plurality of ferromagnetic prisms 206, a first inner end electrode 208, a first outer end electrode 210, a second inner end electrode 212, a second outer end electrode 214, a first ferromagnetic end element 216, and a second ferromagnetic end element 218.
 Outer shell electrode 202 may be cylindrical in shape. Other shell shapes may be utilized in alternate embodiments, e.g., polyhedron, spherical, or the like, as long as the shape facilitates proper focusing of the space-time flows. Outer shell electrode 202 is formed from an electrically conductive material such as metal. Although the preferred practical embodiment employs an outer electrode formed from stainless steel, other materials such as copper, zinc, or a suitable alloy can be utilized. The inner surface of electrode 202 defines the interior of electrode 202. The size of outer shell electrode 202 may vary to accommodate the particular application.
 The ferromagnetic prisms 206 are positioned within the interior of outer shell electrode 202 and around the inner surface of outer shell electrode 202, as shown in FIG. 3. The prisms 206 are held in place in any suitable manner. For example, they can be glued to the inner electrode 204 such that electrical contact is maintained between the prisms 206 and the electrodes. In accordance with one practical embodiment, each ferromagnetic prism 206 has a triangular cross section (see FIG. 3). The triangular cross section includes an acute angle that forms an apex that points toward the interior of the apparatus. In this embodiment, each prism-shaped element 206 is identical in size, shape, and composition. The shape of the ferromagnetic prisms 206 facilitates the combination of the vectors of space-time flows generated by the prisms 206. The shape ensures that the resulting flows are directed toward the center of the cavity within the treatment apparatus.
 In the example embodiment, the cylindrical shell electrode 202 and each of the ferromagnetic prisms 206 are of the same length. As shown in FIG. 3, each of the ferromagnetic prisms 206 is positioned within the interior of the outer electrode 202 such that its apex points toward the longitudinal center of treatment apparatus 200. In other words, all of the triangles defined by the cross sections of the prisms point radially inward. The number of ferromagnetic prisms 206, and their shape, size, and composition, may vary depending upon the particular application. Practical embodiments include at least three prism elements. In the illustrated example, apparatus 200 includes twelve prism-shaped elements 206 positioned around the inner surface of outer shell electrode 202 such that adjacent prisms contact each other at their respective bases.
 The prism-shaped elements 206 should be formed from a ferromagnetic material. One suitable material is identified as material catalog number 250 VNRP according to the Ukraine National Nomenclature. 250 BHP.PI. is nickel-zinc ferromagnetic. It has the following technological characteristics: (1) specific magnetization saturation: .sigma..sub.i=50-80 A*m.sup.2/kg; (2) coefficient of shrinkage: in the limits of 1.14-1.18; (3) initial magnetic permeability: .mu..sub.H=180-400; maximal allowable operation temperature: not less than 120.degree. C. The material is generally characterized as a high frequency (10-100 MHz) ferromagnetic material. In this regard, ferromagnetic materials of low and super-high frequency are not desirable in this application.
 The inner electrode 204 is formed from an electrically conductive material, such as metal. Although the preferred practical embodiment employs an inner electrode formed from stainless steel, other materials such as copper, zinc, an alloy, or any current-conducting material can be utilized. The inner electrode 204 is located within the interior of the shell electrode 202, and is coupled to the ferromagnetic prisms 206 such that the prism-shaped elements 206 are not exposed to the interior. In this regard, the ferromagnetic material is located between the inner surface of the shell electrode 202 and the inner electrode 204. The inner electrode 204 is configured such that it does not contact the outer shell electrode 202. In the practical embodiment, the inner electrode 204 may be realized as a plurality of flat plates that are joined together at points between the prisms 206 and at the apexes of the prisms 206. Alternatively, the inner electrode 204 may be formed as a unitary component.
 The inner electrode 204 is held in place in any suitable manner, for example, by gluing or welding it to the prism shaped elements 206. As shown in FIGS. 2 and 3, the inner electrode 204 defines a cavity 220 within the interior of the treatment apparatus 200. The cavity 220 is shaped to accommodate the container 222 in which the radioactive material is placed. The container 222 is formed as a cylindrical vessel in which radioactive material is sealed. In a practical embodiment, the container 222 is preferably formed of lead because lead screens alpha, beta, and gamma radiation while allowing the space-time flows to pass. Although not shown, the container 222 rests on dielectric or insulating plates or mounts to ensure that the container 222 is electrically isolated from the inner electrode 204 during processing of the radioactive material.
 The first inner end electrode 208 is formed from an electrically conductive material. The first inner end electrode 208 is connected to one end of the inner electrode 204 to establish electrical continuity. In the example embodiment, the first inner end electrode 208 is a conical shell electrode that contacts the inner electrode 204 at the inwardly facing points. In this regard, the first inner end electrode 208 is physically attached to the inner electrode at these points. In practice, these two electrodes can be connected together (by welding, soldering, etc.).
 The exact dimensions and configuration of first inner end electrode 208 may vary from one system to another. Generally, the dimensions of the first inner end electrode 208 are proportional to the dimensions of the Egyptian pyramids.
 First ferromagnetic end element 216 is mounted in the first inner end electrode 208 as shown in FIG. 2. The end element 216 may be welded, bonded, or otherwise secured to the first inner end electrode 208. The end element 216 is preferably formed from the same ferromagnetic material used for the prism-shaped elements 206. In this example, the end element 216 is cone-shaped, which allows it to mate with conical shell electrode 208. Generally, the dimensions of the first ferromagnetic end element 216 are proportional to the dimensions of the Egyptian pyramids. The height of the first ferromagnetic end element 216 may be greater than the height of the first inner end electrode 208, as depicted in FIG. 2 and FIG. 5. This feature facilitates the focusing properties of the apparatus.
 The first outer end electrode 210 is mounted to the outer surface of the first ferromagnetic end element 216 such that electrode 210 does not contact the first inner end electrode 208. The first outer end electrode 210 may be glued or otherwise secured to the outer surface of the end element 216. The first outer end electrode 210 is formed from an electrically conductive material. As schematically shown in FIG. 2, the first outer end electrode 210 is electrically connected to the outer shell electrode 202 and to the second outer end electrode 214. This electrical connection may be established using wire, cabling, or any suitable electrical conductor.
 The exact dimensions and configuration of first outer end electrode 210 may vary from one system to another. In accordance with one practical embodiment, the first outer end electrode is a circular plate. The diameter of the first outer end electrode 210 may be less than the base diameter of the first ferromagnetic end element 216, as depicted in FIG. 2.
 The second inner end electrode 212 is also formed from an electrically conductive material. The second inner end electrode 212 is connected to the end of the inner electrode 204 (opposite the first inner end electrode) to establish electrical continuity. Thus, the first inner end electrode 208, the second inner end electrode 212, and the inner electrode 204 cooperate to form one electrode component. In the example embodiment, the second inner end electrode 212 is a truncated conical shell electrode that contacts the inner electrode 204 at its inwardly facing points. In this regard, the second inner end electrode 212 can be physically attached to the inner electrode 204 at these points, in the same manner as described above for the first inner end electrode 208. In this example, the truncated tip forms an opening in the second inner end electrode 212. As shown in FIG. 2, this opening is positioned within the interior of the outer shell electrode 202. The exact dimensions and configuration of second inner end electrode 212 may vary from one system to another.
 Second ferromagnetic end element 218 is mounted in the second inner end electrode 212 as shown in FIG. 2. The end element 218 can be glued or otherwise secured to the second inner end electrode 212. The ferromagnetic end element 218 should be formed from the same ferromagnetic material used for the prism-shaped elements 206. In this example, the end element 218 is shaped like a truncated cone, which allows it to mate with second inner end electrode 212. The height of the second ferromagnetic end element 218 may be greater than the height of the second inner end electrode 212, as depicted in FIG. 2.
 As shown in FIG. 2, the second ferromagnetic end element 218 has a conduit or passageway formed therein along its central axis. In the example embodiment, this conduit is a cylindrical hole having a diameter that is large enough to allow for passage of the container 222.
 The second outer end electrode 214 is mounted to the outer surface of the second ferromagnetic end element 218 such that electrode 214 does not contact the second inner end electrode 212. The second outer end electrode 214 is formed from an electrically conductive material. As schematically shown in FIG. 2, the second outer end electrode 214 is electrically connected to the outer shell electrode 202 and to the first outer end electrode 210. This electrical connection may be established using wire, cabling, or any suitable electrical conductor. Thus, the first outer end electrode 210, the second outer end electrode 214, and the outer shell electrode 202 cooperate to form one outer electrode component.
 As shown in FIG. 2, the second outer end electrode 214 has a hole formed therein. This hole is sized to accommodate canister 222. The hole is positioned for alignment with the conduit formed in the second ferromagnetic end element 218. Thus, the opening formed by the truncated tip of the second inner end electrode 212, the conduit in the second end element 218, and the hole in the second outer end electrode 214 form a passageway for the radioactive material, which may be enclosed within the container 222.
 The exact dimensions and configuration of the second outer end electrode 214 may vary from one system to another. In accordance with one practical embodiment, the second outer end electrode 214 is a ring-shaped plate. The outer diameter of the second outer end electrode 214 may be less than the base diameter of the second ferromagnetic end element 218, as depicted in FIG. 2.
 The generator of the excitation signal 104 is shown in FIG. 1; it is connected to the second outer end electrode 214, to the second inner end electrode 212, as shown in FIG. 2.
Theory of Operation
 The basis of the proposed method is constituted by the phenomenon of excitation of flows of structurization, .DELTA..tau..sub.l, and destructurization, .DELTA..tau..sub.2, in substance. Its physical substantiation is based upon the frequencies of proton nuclear magnetic resonance (NMR) in the phases of dispersion (J. W. Emsley, J. Feeney, and L. H. Sutcliffe, HIGH RESOLUTION NUCLEAR MAGNETIC SPECTROSCOPY, in two volumes, New York (1966)). Dispersion phase at NMR is a state of transition from the frequency of structurization to the frequency of destructurization or vice versa. In the chart showing energy absorption in NMR, crossing of the abscissa will be present without failure. This phenomenon characterizes dispersion.
 It is established that when exposed to electromagnetic oscillations of specific frequency f.sub.i, the substance, absorbing the energy of these oscillations, emits the flows of structurization, .DELTA..tau..sub.1. At this, chemical shift takes place; and the substance somewhat decreases its sizes (isomerism). At the frequency of oscillations f.sub.2, the substance emits the flows of destructurization, .DELTA..tau..sub.2. At this, chemical shift takes place; and the substance somewhat increases its sizes (isomerism).
 The frequency of structurization f.sub.1, is defined as such a frequency of electromagnetic oscillations that ferromagnetic material, when exposed to it, as a result of nuclear magnetic resonance, emits the flows of space-time .DELTA..tau..sub.1 that cause the phenomenon of structurization and dilation of any physical process. The frequency of destructurization f.sub.2 is defined as such a frequency of electromagnetic oscillations that ferromagnetic material, when exposed to it, as a result of nuclear magnetic resonance, emits the flows of space-time .DELTA..tau..sub.2 that cause the phenomenon of destructurization and acceleration of any physical process (A. B. , . , . , ., 2000r. (A. V. Kinderevich, L. I. Kicha, FIELD THEORY. ELEMENTS OF NUMBERS THEORY, Kyiv 2000)--pp. 405-408). The reaction of the space-time flows effect is measured by N. A. Kozyrev detector, which is considered in the works: H. A.// . AH. APM. CCCP, 1997r. (Kozyrev N. A., ASTRONOMICAL OBSERVATIONS BY THE WAY OF PHYSICAL PROPERTIES OF TIME, Academy of Sciences of Armenian SSR (1977)); H. A., B. B.// , 1980r. (Kozyrev N. A., Nasonov V. V., PROBLEMS OF UNIVERSE STUDIES (1980)); M. M., . A., M. .//CCCP, 1990r., c.314 (Lavrentyev M. M., Yeganova I. A., Lutset M. K., Doklady Akademyy Nauk USSR, (1990), p. 314).
 In the monograph A. B. , . , . , ., 2000r. (A. V. Kinderevich, L. I. Kicha, FIELD THEORY. ELEMENTS OF NUMBERS THEORY, Kyiv (2000)), it is shown that any substance affects the flows .DELTA..tau..sub.2 emitted by some mass very insignificantly; and it is essentially transparent for them. However, insignificant fraction of these flows deflects at specified angle when passing from a less dense substance to a denser one. This could result in appearance of some resemblance of static lenses of .DELTA..tau..sub.2 focusing, which have real and imaginary focuses, and, consequently, in local thickening of the space-time flows and their rarefication, which is related to the Hubble number, H, changes in this local region, acquiring the magnitude H.sub.1. The normal intensity of the physical processes is determined by the Hubble constant: 1 H = 2.8 .times. 10 - 18 1 c .
 If the flows density increase takes place, then in this local region H.sub.1>H, if the flows rarefication takes place, then H.sub.1<H. Relation 2 H 1 H
 is an attribute of the local region: at 3 H 1 H > 1
 destructurization takes place, at 4 H 1 H < 1
 structurization takes place. It is substantiated theoretically that the larger the flow .DELTA..tau..sub.2, the smaller will be structurization at the given point of the Earth surface.
 This is explained by the fact that the values .DELTA..tau..sub.2 and 5 H 1 H
 are linked by the relation 6 t 2 = 0.5 H 1 H M 4 R E 2 ,
 where M=const, R.sub.E is the radius of Earth. From here, it is seen that when the value 7 H 1 H > 1
 increases at given point of "Earth-Universe" destructurization will increase and vice versa at 8 H 1 H < 1.
 It is shown that the change of the magnitude of the activity, A, of radioactive materials at the initial specific activity A.sub.0=(10.sup.8.div.10.sup.15) Bq/kg equals to: 9 A = A 0 - H H 1 t , ( 1 )
 where .lambda. is the decay constant, t is time.
 It could be easily noted that at the specific magnitudes of the value 10 H 1 H ,
 the given exponential function decreases faster as compared to the known function for the activity assessment: A=A.sub.0e.sup.-.lambda.t.
 As an example, the following calculations are for the radioactive isotope Cs-137, where the radioactivity of the freshly unloaded fuel, A.sub.0, is equal to 10.sup.15 Bq/kg.
 The half-life for Cs-137 (T.sub.1/2) is 30.2 years=9.5.times.10.sup.8 seconds. Respectively, 11 = 0.693 T 1 / 2 = 7.3 .times. 10 - 10 .
 Let 12 H H 1 = 10 6 ,
 that is, H.sub.1<<H, then according to expression (1), A=10.sup.12.times.e.sup.-7.3.times.10.sup..sup.-10.sup..times.10.sup..sup- .6.sup.t. For time t=10 days=8.6.times.10.sup.5 seconds, 13 A = 10 12 e 629 .
 That is, a significant decrease of the radioisotope activity magnitude will take place.
 If we accept that e.sup.25=6.times.10.sup.10, then we obtain 14 A 10 12 6 .times. 10 10 1.6 .times. 10 - 3 Bq / k g .
 Such decrease of the activity will occur during 9.4 hours since 15 t = 25 7.3 .times. 10 - 4 = 3.4 .times. 10 4
 seconds. Consequently, the decrease of the Hubble number H.sub.1 in some local region will cause the decrease of activity and, respectively, deactivation of radioactive material.
 Consequently, to decrease the activity of radioactive material, it should be placed into the local region where structurization takes place at given flow density .DELTA..tau..sub.1, excited in ferromagnetic material at the frequency of electromagnetic oscillations f.sub.1.
 It is substantiated theoretically that in order to accelerate deactivation of radioactive material with unexcited nuclei with A.sub.0=10.sup.2 Bq/kg and lower, the intensity of the fission reaction should be increased. It means that the radioactive material should be placed in the local region with 16 H 1 H > 1.
 It is shown that at neutron multiplication under the conditions of 17 H 1 H
 and flow .DELTA..tau..sub.2 growth, when the specific density of neutrons flux reaches 10.sup.20 cm/s, under fulfillment of the criterion 18 p .times. Nv k ( H 1 H ) 2 4 , 8 .times. 10 13 Ci ,
 where .rho. is probability, N is the number of atoms, v is the average number of neutrons at decay of one atom v=2.5, K is the stage of decay, .DELTA..tau..sub..rho.2 is the flow from nuclear structurization, spontaneous chain reaction could occur. This should be taken into consideration when determining the amount of radioactive material to be subjected to deactivation lest the critical mass be formed.
 It is shown that the activity change in this case equals to 19 A = A 0 ' H 1 H t .
 Here 20 A 0 ' = A 0 H 1 H
 is increase of the activity in the intensification apparatus due to the spontaneous fission of nuclei. Let 21 H 1 H = 10 7 ,
 then A=A'.sub.0e.sup.-.lambda..times.10.sup..sup.7.sup..times.t. As an example, the following calculations are for the unexcited nuclei activity decrease for Cs-137 isotope.
 22 A 0 ' = A 0 H 1 H = 10 6 Bq / kg ; A=A'.sub.0e.sup.-7.2.times.10.sup..sup.-10.sup..times.10.sup..sup.7.sup.t- =10.sup.9e.sup.-7.2.times.10.sup..sup.-3.sup.t.
 For the time t=10 days=24.times.3600.times.10=86.times.10.sup.5 seconds, 23 A = 10 9 7.3 .times. 10 - 3 .times. 8.6 .times. 10 5 = 10 9 6290 .
 Meanwhile, even at e.sup.20, the activity will already be A=0.9 Bq/kg.
 Consequently, in this case, in order to decrease activity, accelerate deactivation of radioactive material, it should be placed into the local region where destructurization takes place at given flow density .DELTA..tau..sub.2 excited in ferromagnetic material at the frequency of electromagnetic oscillations of f.sub.2.
 The lenses of the space-time flows focusing are known shaped as pyramid, cone, prism described in the monograph A. B. , . , . , ., 2000r. (A. V. Kinderevich, L. I. Kicha, FIELD THEORY. ELEMENTS OF NUMBERS THEORY, Kyiv (2000)). We could not find the most close as to their technical essence apparatuses.
 The proposed apparatus for radioactive material treatment 102 (see FIGS. 1, 2, 3, and 4) serves for changing of intensity of physical processes in the local region 220. The elements of the apparatus shaped as prisms 206 as well as cones 216 and 218 formed of ferromagnetic are surrounded by the electrodes 202, 204, 208, 210, 212, and 214. These elements create and focus the flows of space-time, which facilitate acceleration or deceleration of physical processes in the local region. The energy of the external electromagnetic field is absorbed in the elements of the apparatus 102; in this process, spins of ferromagnetic are oriented so that it emits powerful flows of structurization, .DELTA..tau..sub.1, or destructurization, .DELTA..tau..sub.2. Diagram of the flows .DELTA..tau..sub.1 summation is presented in FIG. 4. The specified flows in the local region of the apparatus 102 change the magnitude of the Hubble number and in this way facilitate intensification of the process of radioactive decay of the radioactive material enclosed in the container 222.
Processing Time Sequence at Embodiment of the Method Together with the Apparatus for its Realization
 The container 222 with highly active radioactive waste is loaded into the inner cavity of the apparatus 102 through the cylindrical hole in the second end element 218; and then the adjustable generator of electromagnetic oscillations 104 is turned on. The frequency is set to the frequency of structurization, f.sub.1, at which decrease of intensity of alpha, beta, and gamma radiation begins as monitored by the instruments 106 located directly in the container 222. When the threshold magnitude of the activity is reached, the generator 104 is turned off, and the container 222 with radioactive waste is removed from the inner cavity of the apparatus 102.
 In the case of treatment of nuclear power plants fuel elements, which have passed the stage of activity decrease, they are removed from the container 222 and fragmented or ground into smaller pieces. This provides for the possibility of selecting of the amount of radioactive material, which excludes occurrence of chain reaction when treated at the frequency f.sub.2.
 After the specified procedure, the container 222 with low active wastes enclosed in it is loaded into the inner cavity of the apparatus 102 for the second time. The adjustable generator of electromagnetic oscillations 104 is turned on; the frequency of destructurization, f.sub.2, is selected, at which activity of the radioactive material somewhat increases, but then irreversible decrease of intensity of alpha, beta, and gamma radiation begins, which is monitored by the instruments 106 located directly in the container 222. When the activity value reaches the magnitude of the environment background, the generator 104 is turned off, and the container 222 with deactivated radioactive wastes is removed from the inner cavity of the apparatus 102 for usage in other ecologically safe technological processes.
 The present invention has been described above with reference to a preferred embodiment. However, those skilled in the art having read this disclosure will recognize that changes and modifications may be made to the preferred embodiment without departing from the scope of the present invention. These and other changes or modifications are intended to be included within the scope of the present invention, as expressed in the following claims.