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WO1990013125A1 - Fusion piezonucleaire - Google Patents

Fusion piezonucleaire Download PDF

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Publication number
WO1990013125A1
WO1990013125A1 PCT/US1989/001749 US8901749W WO9013125A1 WO 1990013125 A1 WO1990013125 A1 WO 1990013125A1 US 8901749 W US8901749 W US 8901749W WO 9013125 A1 WO9013125 A1 WO 9013125A1
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WO
WIPO (PCT)
Prior art keywords
nuclei
electrode
host material
host
electrolyte
Prior art date
Application number
PCT/US1989/001749
Other languages
English (en)
Inventor
Steven E. Jones
E. Paul Palmer
Johann Rafelski
Rodney Price
Original Assignee
Brigham Young University
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Application filed by Brigham Young University filed Critical Brigham Young University
Priority to PCT/US1989/001749 priority Critical patent/WO1990013125A1/fr
Priority to CN90102287A priority patent/CN1046996A/zh
Publication of WO1990013125A1 publication Critical patent/WO1990013125A1/fr

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Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21B—FUSION REACTORS
    • G21B3/00—Low temperature nuclear fusion reactors, e.g. alleged cold fusion reactors
    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y02E30/10—Nuclear fusion reactors

Definitions

  • Fusion of isotopic hydrogen nuclei is the principal means of producing energy in the high-temperature interiors of stars.
  • the nuclei are clothed with electrons and approach one another no closer than allowed by the molecular Coulomb barrier.
  • the rate of nuclear fusion in molecular hydrogen is then governed by the quantum- mechanical tunneling through that barrier, or equivalently, the probability of finding the two nuclei at zero separation.
  • the d-d fusion rate is exceedingly slow, about 10 ⁇ 70 per D2 molecule per second [Van Siclen, CD. & Jones, S.E. Journal of Physics G. Nucl. Phys. 12, 213-221 (1986).].
  • Muons can catalyze fusion of hydrogen isotopes. Catalysis lowers the activation energy (in this case, the coulomb barrier) without using up or destroying the catalyst. A muon brings hydrogen nuclei very close together. Quantum-mechanical tunnelling then results in fusion. Each muon promotes fusion quickly (10 ⁇ 12 seconds for deuteron-triton fusion) , and is usually released to participate in another fusion. However, muons decay naturally, and the number of fusions during a muon lifetime cannot be made large enough to offset the high cosfef* * of producing muons.
  • Ideal reactors would operate at temperatures low enough for common materials to be used for construction. They should control the rate of fusion so it could be entirely off, or else run at any useful level without danger of explosion, meltdown, or any type of disaster.
  • the equipment should be reasonably small, simple, safe, and inexpensive. And, of course, the fuel and equipment costs should be comparable to those of competing methods of generating power and/or useful radiation.
  • the present invention provides a new method of promoting nuclear fusion in a controlled fashion under moderate conditions. We have discovered a means of inducing nuclear fusion without the use of either high temperatures, pressures, or radioactive muons.
  • a distortion of the internuclear hydrogen wavefunction sufficient to achieve detectable levels of nuclear fusion can be realized under certain conditions when hydrogen isotopic nuclei are loaded into metallic crystalline lattices or other forms of condensed matter. It appears that the rate of nuclear fusion increases many-fold if the nuclei can be brought substantially closer together than their normal distance in chemical bonds. In this invention, the desired proximity is achieved through pressure or the use of catalytic sites or both.
  • the applicants have coined the term "piezonuclear fusion" or PNF from the latin root "piezo" for squeezing or pressure as a designation for nuclear fusion achieved by the method of the invention.
  • a particularly preferred embodiment involves fusion of deuterium nuclei in an electrolysis cell.
  • Other nuclei can also be used, as can other types of reactors (e.g. loading selected metals with high pressure hydrogen isotopes) .
  • Possible fusion reactions which may be carried out according to the method of the invention include: P + D ⁇ 3 He + 7 (5.4MeV) D + D ⁇ T(l.OlMeV) + p(3.02MeV)
  • the fusion can produce neutrons, gamma (and other) radiation, and thermal energy. All of these are useful products of the invention.
  • the radiation can be used for nondestructive testing and imaging as well as promoting nuclear and chemical reactions.
  • the thermal energy can be used for heating, for the production of electricity, and for power production in general.
  • the fusion rate increases as the distance between nuclei decreases, methods that compress pairs of nuclei are desirable.
  • the electrical repulsion of the nuclei can be decreased if electron density is high between the nuclei.
  • the catalytic sites should be reusable (i.e., catalyze many fusion events) . This implies preservation of the structure, removal of the ash (e.g. 3 He) and minimal blockage by materials that fuse slowly or not at all (e.g. H 2 ) •
  • the method of the invention makes use of pressure near charged interfaces, codeposition, and strueture of electroplated solids (both the phase and crystalline aspects of structure) to promote nuclear fusion.
  • Fig. 1 is a schematic representation of an apparatus in accordance with the invention and used to carry out the method of the invention
  • Fig. 2 is a schematic representation of an individual electrolysis cell
  • Figs. 3a and 3b are graphs of neutron spectra confirming the occurrence of fusion
  • Figs. 4a and 4b are schematic representations of an apparatus for carrying out an alternate embodiment of the method of the invention.
  • Fig. 5 is a schematic diagram of another- apparatus useful in carrying out method of the invention.
  • Fig. 6 is a schematic view of an electrolysis cell for codepositing fuel and catalytic site material
  • Fig. 7 is a schematic representation of a cell for piezonuclear reaction by compression of fuel
  • Fig. 8 is a schematic illustration of an arrangement for induc ⁇ ig shock promoted piezonuclear fusion
  • Fig. 11 is a graphic plot of the differences between radiation values measured during the method of the invention and background measurements;
  • Fig. 12 is a graph of the ratios of measured radiation levels to background radiation levels during fourteen specific tests of the method of the invention.
  • reaction (lb) occurs at a nearly equal rate as the reaction (la) , which is usually the case.
  • Metals having the capability to absorb and hold hydrogen may be used as catalyst materials in the invention. Titanium, platinum and palladium have been found to be particularly suitable catalyst materials because of their large capacities for holding hydrogen and forming hydrides. Titanium and palladium are particularly preferred.
  • Other possible catalyst materials include lanthanum, nickel, iron, copper, zirconium, tantalum, thorium alloys and lithium-aluminum hydride.
  • Electrolytic Fusion In one preferred arrangement, the method of the invention is carried out in an electrolytic cell comprising a negative electrode of hydrogen absorbing, electrically conductive material, a positive counterelectrode and an electrolyte containing fusionable nuclei.
  • a suitable arrangement is illustrated schematically in Fig. 1, which shows a pair of electrolytic cells on top of a neutron spectrometer. Fusion has been found to occur during low-voltage electrolytic infusion of deuterons in such a system as d + and metal ions from the electrolyte are deposited at (and into) the negative electrode.
  • a plurality of glass vessels 10 are placed on a support 12.
  • Fig. 2 is an enlarged schematic representation of an individual cell. Approximately 20 ml of a heavy water electrolyte solution 14 are introduced into each vessel 10, and a negative electrode 16 and a positive counterelectrode 18 are also disposed in each vessel in contact with the electrolyte solution. Electrodes 16 and 18 are appropriately connected by electrical leads 20 and 22 to a source of electrical potential, such as a battery 24.
  • a neutron detector 104 Adjacent the vessels 10 is a neutron detector 104 comprising a pyrex glass tube 108 filled with a liquid moderator/scintillator 112 which emits light when traversed by a neutron.
  • Several 6 Li-doped glass plates 120 are also disposed in tube 108.
  • Scintillation detectors in the form of photomultiplier tubes 110a and 110b- are provided to detect light from the liquid scin illator and 'the scintillating glass plates. The detector and its associated electronics are described more fully below.
  • a currently preferred electrolyte solution comprises a mixture of 800 parts by weight deuterium oxide (D 2 0) plus approximately 1 part by weight of each of the following metal salts: FeS04'7H 2 0, NiCl 2 '6H 2 0, PdCl 2 , CaC0 3 , i 2 S0 4 -H 2 0, NaS0 4 -10H 2 0, CaH 4 (P0 4 ) 2 ⁇ 2 0, Ti0S0 'H 2 S0 -8H 2 0, and a very small amount of AuCN.
  • the pH is adjusted to pH - 3 with HN0 3 .
  • Experimental evidence suggests it is advantageous for co- deposition of deuterons and metal ions to occur at the negative electrode.
  • the metal ions typically come from the electrolyte, but they may also result from the anode if a consumable anode is employed.
  • individual electrodes consisted of approximately 3 g purified "fused" titanium in pellet form, or of 0.05 g of 0.025 mm thick palladium foils, or of 5 g of mossy palladium.
  • the electrolytic method may be carried out in individual electrolytic cells, or it may be carried out in groups of plural cells. Typically four to eight cells have been used in the experimental tests reported herein in order to increase the total number of neutrons generated in the tests.
  • the electrodes may be cleaned and reused.
  • palladium pieces can be re-used after cleaning and roughening the surfaces with dilute acid or abrasives.
  • the counterelectrode or positive electrode may be any material which makes suitable electrical contact with
  • a gold or platinum foil is used for the positive electrode because of its low reactivity, high conductivity and ability to aid the formation of 0 2 gas and its removal
  • Nickel, copper and iron are less preferred because they tend to be less durable due to electrochemical reactions at the anode.
  • the method of the invention involves application of an electrical potential across the electrodes. - 15 Successful results have been obtained using DC power supplies providing from 3 to 25 volts across each cell at currents of from 10 to 500 mA. Correlations between fusion yield and voltage, current density, or surface characteristics of the metallic cathode have not yet been 20 established. mall jars, approximately 4 cm high x 4 cm diameter, holding approximately 20 ml of electrolyte solution each have been used as electrolytic cells. Such cells are very simple, and it is expected that further development
  • Example The reactor was comprised of a glass container holding a mixture of D 2 0 and H 0 with Na 2 S0 4 (0.28 M) and
  • the volume of the solution was roughly 50 ml.
  • the pH was near 3.8 at the end of the run.
  • the cathode was a lump of spongy titanium (approximately 1 g, 75% voids) and the anode was gold
  • Fig. 3a shows background neutron counts as a function of neutron energy (channel number) .
  • Fig. 3b shows combined counts for deuteron loaded metals produced in three runs of electrolysis of water that was enriched in D 2 0. Comparison of the figures clearly indicates the appearance of 2.5 MeV neutrons arising from nuclear d-d fusion. The excess counts shown in Fig. 3b in channels 40-130 indicate neutrons from d-d fusion were produced in the combined runs. The count rate in channels 40-130 is more than 2.5 times the background count rate. This represents seven times the standard deviation and is therefore highly significant statistically.
  • Loading catalytic materials A number of pure metals, alloys, and compounds absorb hydrogen isotopes.
  • the hydrogen may be dissolved or chemically bound in hydride form. In any case, there appear to be sites in the crystal lattice or at grain boundaries that catalyze nuclear fusion. Indirect evidence is provided by unusually high concentrations of 3 He (a d-d fusion product) in certain samples (e.g. nickel) .
  • Figs. 4a and 4b schematically illustrate an arrangement for pressure loading a fusion fuel (e.g. D 2 or DT gas) into a catalyst metal sample 32 in a sample container 30. End caps 34 are provided to close off the container.
  • the container itself may be formed of the catalytic material.
  • Fuel gas e.g. D 2
  • An outlet 38 is provided for egress of unused fuel and ash (i.e. fusion product) .
  • composition and the thermal and mechanical history of the catalyst are expected to affe t he fusion rate, as is the operating environment.
  • the thickness and material of the container walls may be adjusted as desired to allow passage of the radiation, or adjusted to extract the maximum amount of radiation or energy from the fusion occurring inside.
  • the fusion rate is controlled by the feed rate of the fuel. Higher rates may be obtainable by the use of external pressure (mechanical or hydraulic) and/or by temperature changes (heating or cooling) .
  • FIG. 5 A particular apparatus used to carry out pressure loading of fusion catalyzing material is illustrated in Fig. 5.
  • the open end of a cylindrical stainless steel sample container 50 is connected via a cap 52 provided with an O-fing seal 53, a valve 54 and a coupling 56 to a manifold line 5& which leads to a vacuum pump 60.
  • a control valve 62 ' is interposed between manifold 58 and vacuum pump 60."
  • Manifold line 58 is also connected through a valve 64 to a high pressure source of hydrogen gas 66 provided with a pressure regulator 68 and through a valve 70 to a separate high pressure source of deuterium gas 72 which also is provided with a pressure regulator 74.
  • a low pressure gauge 76 and valve 78 are provided to enable the system pressure to be monitored during evacuation by the vacuum pump 60.
  • a high pressure gauge 80 and valve 82 are provided for monitoring the system pressure during gas infusion.
  • the closed end of sample container 50 is adapted to be received in a high temperature furnace 84 with heating coils 86 which can produce controlled temperatures of up to 1000 °C. Such furnaces are commercially available.
  • a sample of metal 88 into which deuterium is to be infused is first inserted into the sample container 50, and the container is then connected to the system and evacuated with the vacuum pump 60. The sample 88 is then heated to a temperature in the range from about 500 to 1000 ⁇ C, preferably about 600 to 800 "C, and evacuation is continued to remove adsorbed and absorbed gases.
  • the pressure in the sample container is monitored, and heating and evacuation are continued until a stable low pressure condition is achieved indicating substantially complete outgassing of the sample. If desired, heating may be continued for a period of time after stable conditions have been achieved as a precautionary measure to assure complete removal of gasses from the sample.
  • the vacuum pump is then valved off, and hydrogen and/or deuterium is admitted to the sample container. Gas pressures may be as high as the sample container can withstand. Effective results can be obtained with pressures in the range from 1 to 10 atmospheres, preferably about 4 to 7 atmospheres.
  • Heating is then discontinued, and the sample is allowed to cool: Cooling may be passive, as by leaving the sample to cool to ambient temperatures, or it may be active, as by plunging the sample into liquid nitrogen or a refrigerated compartment. During heating and/or cooling, stresses and/or phase changes are generated in the sample which are believed to promote fusion of absorbed atoms in the metal sample. The sample is scanned for neutron and gamma emissions at the appropriate energies indicative of the occurrence of fusion.
  • the system was again purged by the vacuum pump, and then the H 2 supply valve was opened to admit approx. 50 psi of hydrogen gas.
  • the H 2 valve was closed and the sample tube valve opened to mix H 2 and D 2 , and the furnace was turned off, leaving the sample tube connected to the manifold.
  • the sample was allowed to cool under D % and H 2 pressure.
  • the deuterated nickel strip was placed next to a neutron spectrometer as shown in Fig. 1, and the emission of neutrons from the nickel strip was counted.
  • the initial neutron count in spectrometer channels 100 to 250 was €.27 ⁇ 1.06 counts per hour which fell off over time to 5.18 + .50 counts per hour and then to 4.68 + .86 counts per hour.
  • the background count in channels 100 to 250 was 4.96 + .43 counts per hour.
  • the neutron count in spectrometer channels 0 to 100 was 11.71 + .75 counts per hour, and the background count in these channels was 8.10 + 1.13 counts per hour. A repeat of the background for channels 0 to 100 gave 7.59 + .53 counts per hour. Only background levels of neutrons were detected in spectrometer channels 250 to 511.
  • Codeposited catalysts It may be possible to improve the structure of catalytic sites or increase the ⁇ : number per unit volume, or both, by codepositing
  • the fuel e.g. hydrogen isotopes such as D 2
  • codeposition can be accomplished by condensation methods (e.g. evaporation, sputtering, chemical vapor deposition, ion implantation, etc.), or by electroplating, or by solidification of a melt or solution.
  • the invention embraces methods for codepositing to form catalytic sites in films or bulk material of the proper shape and size for a fusion reactor.
  • Fig. 6 schematically illustrates an electrolysis cell arrangement for codepositing fuel (e.g. deuterium) and catalytic material. Atoms and ions are shown greatly magnified.
  • a pressure relief tube 26 is included to allow escape of gases produced during the electrolysis. Emissions of radiation and/or thermal energy may be produced during the deposition process.
  • Fig. 7 schematically illustrates an apparatus embodiment comprising a container 90 with catalytic particles 92 suspended inside, input means 94 for adding the fusion isotopes to the particles, and an ash output 96.
  • Piezonuclear fusion is promoted by compression of fuel (e.g. deuterium) at the surfaces and in the interior of colliding moving particles. Thermal energy and radiation would be transmitted through the walls if the device is intended as a radiation source. As a power source, the walls would transmit only thermal energy.
  • fuel e.g. deuterium
  • Particle size, composition, temperature, and background gas are important parameters for the control of fusion rate in this reactor.
  • the particles may be produced by conventional methods (e.g. precipitation, condensation or grinding) , or by other methods such as exploding wires.
  • Shocks in condensed matter Shock waves created by impact, explosives, or electrical discharges create very high transient pressures. Such shocks can be expected to : increase the rate of nuclear fusion, especially for fuel in catalytic sit ⁇ s.
  • Fig. 8 schematically illustrates an embodiment comprising a shaped condensed catalyst loaded with fuel, a mechanism for creating repeated shock waves in the catalyst, and a structure for transmitting or capturing the desired emission (radiation and/or thermal energy) .
  • the catalyst body 300 is shaped to concentrate the shock wave produced by the impact of a "hammer” 301 on an interposed anvil 302 which drives the catalyst body against a massive stationary anvil 303.
  • the "hammer 1 ' may consist of material driven mechanically, explosively, or by electric discharge.
  • Detection Apparatus The occurrence of cold nuclear fusion is confirmed by the detection of neutron emissions of the appropriate energy.
  • the electrolytic , cells are placed on or alongside the neutron spectrometer 104 of Fig.- 1.
  • Fig. 1 schematically illustrates a particularly preferred neutron spectrometer adapted to register the 2.5 MeV neutrons produced from d-d fusion.
  • Trimethylbenzene base liquid organic scintillator/moderator 112 (BC-505 from Bicron) is contained in the pyrex cylinder 108 having a diameter of about 12.5 cm, and in which three lithium-6-doped glass scintillator plates 120 are embedded. It is preferred to use a liquid scintillator based on trimethylbenzene because the trimethylbenzene has good neutron moderating ability and it also has an index of refraction near that of the 6 Li-glass.
  • Another preferred liquid scintillator comprises decahydronaphthalene containing 4 grams per liter 2,5-diphenyloxazole and 0.5 g/1 l,4-bis-[2-(5- phenyloxazolyl) ]-benzene.
  • Suitable glass plates containing approximately 57% Si0 2 , 18% A1 0 3 , 17% Li 0 (95% 6 Li) , 4% Mgo and 4% Ce 2 0 3 are commercially available from Levy West, Ltd. , Harlow, London. Neutrons deposit energy in the liquid scintillator via collisions and the resulting light output yields energy information.
  • the counting efficiency for the neutron detection system is of the order of 10%; that is to say, approximately one of every ten neutrons passing through the system will generate a detectable signal. Due to the fact that the detector is placed on only one side of the test cells, geometric considerations further reduce the effective counting efficiency by an additional factor of approximately 10%. Thus for every count detected in the illustrated experimental system in excess of background levels, approximately one hundred neutrons are generated in the experiment.
  • An overall wide-energy-spectrum calibration of the spectrometer may be obtained using neutrons from 252 Ca fission. Calibration with monoenergetic 2.9 and 5.2 MeV neutrons can be done with neutrons generated via deuteron-deuteron interactions at 90° and 0°, respectively, with respect to the deuteron beam from a Van de Graaff accelerator.
  • the observed energy spectra show a broad structure which implies that 2.45 MeV neutrons should appear in the multi-channel analyzer spectrum in channels 45 to 150.
  • Stability of the detector system can be checked between data runs by measuring the counting rate for fission neutrons from a broad-spectrum californium-252 source. We have performed other extensive tests proving that our neutron counter 'does not respond preferentially in this pulse height range .to other sources of radiation, such as thermal neutrons.
  • FIG. 9a and 9b A schematic representation of the electronic circuitry used in the neutron detector is illustrated in Figs. 9a and 9b.
  • the electronic system which processes the signals taken from the neutron detector 104 is governed by the logic requirement that only liquid event pulses whi h fall within a preselected gate time prior to a pulse identified as a neutron capture event are actually counted and measured.
  • the conditioning electronics is sensitive to the total energy of the neutron resulting in two characteristic pulses of light occurring within a predetermined coincidence time.
  • the coincidence requirement is designed to reduce background counts resulting from gamma rays to which the liquid scintillator 112 is also sensitive.
  • pulse-shape discrimination is able to distinguish a glass-produced light event, having a relatively long delay time of about 70 nsec, from a liquid-produced event having a relatively short decay time of about 5 nsec.
  • Each of the photomultiplier tubes 110a and 110b produces an anode and a dynode signal.
  • the A-anode signal from photomultiplier tube 110a is fed to an integrating amplifier 200a whereas the B-anode signal from photomultiplier tube 110b is fed to an integrating amplifier 200b.
  • Integrating amplifiers 200a and 200b may, for example, be stretcher amplifiers AN105 supplied by EG&G. These amplifiers have been coupled to grounding switches to enhance integration time characteristics as will be explained hereinbelow.
  • the outputs of integrating amplifiers 200a and 200b are fed to a summer 202 and the summed output is supplied to an amplifier 204 which may, for example, be an ORTEC linear amplifier model 572.
  • the output of amplifier 204 is fed to a delay amplifier 206, as, for example, a series of ORTEC 427A units.
  • the delay amplifier 206 supplies a 20 microsecond delay and subsequently feeds the signal to an analog to digital (A/D) converter 210.
  • the output of the A/D converter is fed to a pulse height analyzer 212.
  • the A/D converter 210 performs the digital conversion of the incoming analog signal from the delay amplifier 206 only upon receipt of a gating or coincidence signal fed to a coincidence input terminal 214.
  • the output of summer 202 is also fed to a gate 220, as, for example, a linear gate LG101 supplied by EG&G.
  • the output of gate 220 is fed to a shaper/amplifier 222 such as an ORTEC time filter amplifier model 454.
  • the output of the shaper/amplifier 222 is in turn fed to a discriminator 224 coupled with a delay 225 of a 10 nsec period to supply a narrow output logic pulse signal to a pulse stretcher 226.
  • the discriminator 224 may be, for example, EG&G model T101 and the pulse stretcher 226 may be EG&G model GG100.
  • the output of the pulse stretcher 226 is fed to a linear gate 230 via a 10 db attenuator, not shown.
  • Linear gate 230 may, for example, be a logic gate and slow coincidence module supplied by ORTEC as model- 409. «
  • the output of linear gate 230 is in turn fed as a coincidence signal to the coincidence input terminal 214 of
  • the A and B dynode outputs of photomultiplier tubes 110a and 110b respectively are fed to a summer 240 which provides a summed output to amplifier 242 which may be, for example, an ORTEC timing filter amplifier model 454.
  • the output of the amplifier 242 is split by a three-way coupler 244 and fed to a differential discriminator 246 coupled to a 118 nsec delay 248.
  • the differential discriminator 246 may, for exampie, be EG&G model TD101/N.
  • the output of the differential discriminator 246 is fed to a gate and delay circuit 250 such as, for example, ORTEC model 416A.
  • the output of gate and delay 250 supplies a signal along line Gl as, the gating input signal to gate 220 of Fig. 9a.
  • the second output of three-way coupler 244 is fed to another differential discriminator 252, such as, for example, EG&G model TD101/N.
  • the output of this differential discriminator 252 is fed to a gate and delay circuit 254, such as ORTEC model 416.
  • the output of gate and delay circuit 254 is fed by a signal line G2 to an anti-coincidence input terminal of gate 230.
  • the summed output of summer 240 is also fed to an amplifier 260 which may be, for example, EG&G model AN101.
  • the output of amplifier 260 is in turn fed to a gate generator 262 which is coupled to a 400 nsec delay 264.
  • the gate generator 262 may, for example, be an EG&G model T101 discriminator.
  • the output of the gate generator 262 is fed to a grounding switch 268a and to an identical grounding switch 268b.
  • Grounding switch 268a supplies an output along signal line SW A to a conditioning input of integrating amplifier 200a.
  • the output of grounding switch 268b supplies a signal along signal line SW B as a conditioning signal to integrating amplifier 200b.
  • Normally conductive matched diodes within the grounding switch provide a low impedance path to ground permitting a relative fast RC integrating time constant.
  • the ground switch is also shown in Figure 2 of the article entitled "A New Technique for Capture and Fission Cross-Sectioned Measurements" appearing in Nuclear Instruments and Methods. Volume 72, pages 23-28, 1969, by J. B. Czirr, incorporated herein by reference.
  • Figs. 9a and 9b the block diagram of Figs. 9a and 9b is seen to contain a first branch (Fig. 9a) which may be termed the “total light” branch and a second branch (Fig. 9b) which may be termed the “early light” branch.
  • Fig. 9a the incoming light signal is fully integrated in integrating amplifiers 200a and 200b.
  • the outputs of integrating amplifier 200a and 200b are summed in the summer 202 and subsequently amplified in amplifier 204 which also provides pulse shaping.
  • the shaped output of amplifier 204 is delayed by a delayed amplifier 206 which provides a 20 microsecond delay prior to feeding the analog signal to the A/D converter 210.
  • the digital conversion takes place, and the digitized output signal is fed to the pulse height analyzer 212 thereby providing a measure of the total light energy supplied to the photomultiplier tube.
  • This total light output is proportional to the integrated output from the light pulses produced by the incident heutron in the liquid scintillator-moderator 112. Since the light pulse produced by thermal neutrons in the glass scintillator plates 120 is constant, it need not be stored in the pulse height analyzer. Thus, the glass 5 event is not gated into the A/D converter 210 so it never gets digitized. Thus, a measure of the integrated light output produced in the liquid scintillator during the thermalizing of the incident neutron provides complete information as to the incident neutron energy.
  • the gating signal supplied to the coincidence input terminal 214 of the A/D converter 210 is generated from a second branch of the summer 202.
  • This second branch is shown by the lower branch in Fig. 9a and comprises the gate 220, shaper/ amplifier 222, discriminator 224, pulse
  • Fig. 9b shows the "early light” branch which is also utilized to differentiate between light generated in the
  • the output of the summer 240 is fed to the amplifier 242 which is operated with a fast integration time of 50 nsec.
  • the term "early light” is used to characterize this branch (Fig. 9b) since the integration time of amplifier 242 is much shorter than that of amplifier 200a and 200b.
  • the output of amplifier 242 is then fed via the three-way coupler 244 to the differential discriminator 246.
  • This differential discriminator 246 selects a region in the pulse height of the incoming signal corresponding to glass events which have an intensity corresponding to neutron capture in the Li-6. Gamma ray background events will also fall within the selected pulse height window.
  • the "total light” from these gammas will be considerably less than that from neutron capture in the glass because of the relatively longer decay time of the neutrons in the glass.
  • indications of such gamma events will pass through differential discriminator 246 and gate and delay circuit 250 so as to trigger the linear gate 220 (Fig. 9a) , they will be eliminated by means of the discriminator 224 which selects only a certain upper energy spectrum from the "total light" spectrum input thereto.
  • the data processing logic of Figs. 9a and 9b also eliminates successive signals resulting from successive neutron captures in the glass. Such events are eliminated by means of the differential discriminator 252 (set at about the same window as differential discriminator 246) and gate and delay circuit 254 supplying an anti-coincidence signal along line G2 to the anti-coincidence input of gate 230.
  • the differential discriminator 252 set at about the same window as differential discriminator 246
  • gate and delay circuit 254 supplying an anti-coincidence signal along line G2 to the anti-coincidence input of gate 230.
  • the first neutron capture event in the glass scintillator 120 passes through differential discriminator 252 and produces the anti-coincidence signal via gate and delay circuit 254.
  • this same first signal passes through the differential discriminator 246 enables gate 220 and passes the first signal through the discriminator 224 and pulse stretcher 226.
  • the anti- coincidence signal G2 is fed into the linear gate 230 together with the coincidence signal from the pulse stretcher 226 thereby preventing any coincidence signal from being generated and fed to the A/D converter 210.
  • the anti ⁇ coincidence signal is generated at the linear gate 230 thereby blocking the delayed first signal from the delay 206 from being digitized by the A/D converter 210.
  • An alternate anti-coincidence circuit for eliminating successive neutron capture events in the glass may be implemented by passing the output of the discriminator 224 to a gate and delay circuit 280 (Fig. 9a) similar to the gate and delay circuit 254.
  • the output of the gate and delay circuit 280 is in turn fed as the signal along line G2 to the anti-coincidence terminal of linear gate 230.
  • Fig_ 10 displays the neutron energy spectrum obtained under conditions described above, juxtaposed with the background spectrum.
  • foreground (solid) and background (dotted) counts are shown as functions of pulse height in the neutron spectrometer, and -ten counts have been added to each three-channel bin for clarity of presentation.
  • the background counts are scaled by a factor 0.46 to match the foreground counts over the entire energy range (channels 0 to 511) illustrated in the figure.
  • a feature in channels 45-150 still rises above background by nearly four standard deviations. This implies that our assumption is too conservative and that this structure represents a real physical effect.
  • Fig. 11 is a difference spectrum obtained by subtracting scaled background from the foreground. Statistical errors are shown. The illustrated plot of the difference between the foreground and background levels was obtained by rescaling the background by a factor of 0.44 to match the foreground level in regions just above and just below the feature in channels 45 to 150. It shows a robust signal centered at channel 100 of over five standard-deviation statistical significance. A Gaussian fit to this peak yields a centroid at channel 101 and a sigma of 28 channels. This is precisely where 2.5 MeV fusion neutrons should appear in the' spectrum. The fact that a significant signal appears above background with the correct energy for d-d fusion neutrons ("2.5 MeV) provides strong evidence that room temperature nuclear fusion is indeed occurring in the electrolytic catalysis cells.
  • Fig. 12 depicts the ratio of foreground rate to background rate in the 2.5 MeV-energy region of the pulse-height spectrum for fourteen individual test runs which enter into the combined data discussed above.
  • Fig. 12 displays, for each run, the ratio of foreground count rate in the 2.5 MeV-energy region with background rates obtained for each run. Background rates were improved upon during the experiments, so we plot the data in terms of foreground-to-background ratios rather than absolute rates.
  • Run 6 is particularly noteworthy, having a statistical significance of approximately 5 standard deviations above background.
  • Fused titanium pellets were used as negative electrodes with a total mass of about 3 g.
  • the neutron production rate increased after about one hour of electrolysis. After about eight hours, the rate dropped dramatically as shown in the subsequent run 7.
  • surfaces of the Ti electrodes showed a dark gray coating.
  • An analysis using electron microscopy with a microprobe showed that the surface coating was mostly iron, deposited with deuterons at the cathode.
  • Isotopic hydrogen is known to accumulate at imperfections in metal lattices [Bowman, Metal Hydrides (ed. G. Bambakides) 109- 144 (New York, Plenum, 1981).] and local high concentration of hydrogen ions might be conducive to piezonuclear fusion.
  • Electrolysis is one way to produce conditions which are far from equilibrium.
  • Other procedures which may be used to generate fusion promoting non-equilibrium conditions or stress include subjecting the infused sample to variations in pressure, temperature, phase, mechanical shocks, etc. Such non- equilibrium conditions are believed to promote stress induced hopping of ions which favors the occurrence of fusion.
  • the rate of "emission of radiation is generally proportional to the level of the operating parameters.
  • voltage and current density probably have the strongest influence on the rate, at least up to some saturating voltage.
  • the radiation can be turned on or off or run at some intermediate level with transition times depending on the rate of fusion at loaded catalytic sites or the rate of refilling sites with existing fuel. This control of the level during continuous operation confers an important advantage.
  • the present invention provides a new method of promoting cold nuclear fusion through infusion of deuterons into materials such as metals. While the need for off-equilibrium conditions is clearly implied by our data, techniques other than electrochemical may also be successful. Metals, which had been outgassed by heating to high temperatures (600 to 800 °C) under vacuum, have been infused with deuterium by subjecting the hot metal to deuterium at elevated pressure (>4 atmospheres) , and then the metals were subsequently cooled under D 2 gas pressure to induce fusion. The results were comparable to those obtained using electrolytic infusion into metals. Fusion may also be promoted by heating deuterium infused samples. If desired, sample preparation (e.g. outgassing of samples) may be effected under an inert atmosphere rather than under vacuum. We have begun to explore the use of ion implantation, and of elevated pressures and temperatures.
  • Nondestructive testing The radiation from the invention can be used to image the interiors of opaque objects, and thus to detect flaws or structures of interest. Examples are the searching of airline baggage for plastic or other explosives; the examination of aircraft wings and other structures for flaws in the internal honeycomb; detection of imperfections in welds of all kinds; and measurement of flow rate and impurities in oil pipelines, 5.- Promotion of chemical and nuclear reactions: Hot atom chemistry resulting from ionizing radiation produces
  • Radiation crosslinks certain types of polymers and improves their mechanical properties. Certain chemical elements are transmuted to other (more valuable) elements upon absorption of a neutron.
  • An example is 196 Hg to gold.
  • the invention may also be used to generate helium
  • Elemental analysis The envisioned radiation sources can be used to stimulate x-ray fluorescence that is of value in elemental analysis. With some elements, the neutrons cause neutron activation with subsequent
  • Thermal energy and charged particles are produced by nuclear fusion reactions. In sufficient amounts, such thermal energy can be used for 5 space heating, running heat engines, producing electrical power (e.g with steam turbines) or even direct conversion of t e flux of charged particles directly into electrical power.
  • enriched content of fusionable nuclei refers to fusionable nuclei contents in excess of naturally occurring levels. Statements that a phenomenon occurs “at” the electrode are intended to include occurrences both at the surface of the electrode and within the electrode.

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  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Electrolytic Production Of Non-Metals, Compounds, Apparatuses Therefor (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

Est décrit un procédé pour activer la fusion nucléaire par injection de noyaux fusibles dans un matériau, tels que du palladium ou du titane.
PCT/US1989/001749 1989-04-26 1989-04-26 Fusion piezonucleaire WO1990013125A1 (fr)

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WO1992002020A1 (fr) * 1989-04-28 1992-02-06 University Of Hawaii Systeme de production de chaleur excedentaire favorisee par procede electrochimique
EP0645777A1 (fr) * 1993-09-27 1995-03-29 CHIKUMA, Toichi Appareillage pour la fusion nucléaire froide
WO1995020816A1 (fr) * 1994-01-27 1995-08-03 Universita' Degli Studi Di Siena Production d'energie et generateur associe exploitant la fusion stimulee non harmonique
RU2193241C2 (ru) * 1993-06-11 2002-11-20 Блэк Лайт Пауэр Инк. Способ и устройство преобразования материи в энергию и энергии в материю
WO2007019390A3 (fr) * 2005-08-03 2007-03-29 Ccmi Corp Amelioration des catalyseurs heterogenes a phase solide actifs en surface
EA012529B1 (ru) * 2003-04-15 2009-10-30 Блэклайт Пауэр, Инк. Плазменный реактор и способ получения низкоэнергетических частиц водорода
CN103219051A (zh) * 2012-08-23 2013-07-24 孙福民 可控连续氘核聚变产能方法及可控连续氘核聚变产能系统
JP2016138807A (ja) * 2015-01-27 2016-08-04 三菱重工業株式会社 核種変換反応膜の再生方法及び核種変換システム
WO2016206443A1 (fr) * 2015-06-24 2016-12-29 林溪石 Tube de réaction à fusion froide
JP2017167161A (ja) * 2017-05-31 2017-09-21 三菱重工業株式会社 放射性セシウム処理システム及び放射性セシウム処理方法
WO2018236444A1 (fr) * 2016-09-23 2018-12-27 Jerome Drexler Appareil et procédé de génération d'électricité par fusion contrôlée catalysée par muons
US10322826B2 (en) 2016-08-26 2019-06-18 Jerome Drexler Interplanetary spacecraft using fusion-powered thrust
US10377511B2 (en) 2016-10-17 2019-08-13 Jerome Drexler Interplanetary spacecraft using fusion-powered constant-acceleration thrust
US10384813B2 (en) 2016-11-16 2019-08-20 Jerome Drexler Spacecraft landing and site-to-site transport for a planet, moon or other space body
US10793295B2 (en) 2017-12-05 2020-10-06 Jerome Drexler Asteroid redirection facilitated by cosmic ray and muon-catalyzed fusion
US10815014B2 (en) 2018-08-24 2020-10-27 Jerome Drexler Spacecraft collision-avoidance propulsion system and method
US10815015B2 (en) 2017-12-05 2020-10-27 Jerome Drexler Asteroid redirection and soft landing facilitated by cosmic ray and muon-catalyzed fusion
US10940931B2 (en) 2018-11-13 2021-03-09 Jerome Drexler Micro-fusion-powered unmanned craft
US10960993B2 (en) 2018-10-30 2021-03-30 Jerome Drexler Spacecraft-module habitats and bases
WO2023248107A1 (fr) * 2022-06-21 2023-12-28 Aganyan Fusion Procédé de fusion thermonucléaire contrôlée

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CN108801878A (zh) * 2018-07-10 2018-11-13 华侨大学 一种确定堆积散粒状物料空隙率的方法

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Techn. Bulletin, Engelhard Industries Ltd, Volume 7, (1-2), 1966, Baker Platinum Division, (Sutton, Surrey, GB), H. BRODOWSKY et al.: "Solubility and Diffusion of Hydrogen and Deuterium in Palladium and Palladium Alloys", pages 41-50 *

Cited By (24)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
WO1992002020A1 (fr) * 1989-04-28 1992-02-06 University Of Hawaii Systeme de production de chaleur excedentaire favorisee par procede electrochimique
RU2193241C2 (ru) * 1993-06-11 2002-11-20 Блэк Лайт Пауэр Инк. Способ и устройство преобразования материи в энергию и энергии в материю
EP0645777A1 (fr) * 1993-09-27 1995-03-29 CHIKUMA, Toichi Appareillage pour la fusion nucléaire froide
AU691242B2 (en) * 1994-01-27 1998-05-14 Universita' Degli Studi Di Siena Energy generation and generator by means of anharmonic stimulated fusion
CN1127735C (zh) * 1994-01-27 2003-11-12 锡耶纳技术研究大学 利用非调谐受激聚变的能量发生和发生器
WO1995020816A1 (fr) * 1994-01-27 1995-08-03 Universita' Degli Studi Di Siena Production d'energie et generateur associe exploitant la fusion stimulee non harmonique
EA012529B1 (ru) * 2003-04-15 2009-10-30 Блэклайт Пауэр, Инк. Плазменный реактор и способ получения низкоэнергетических частиц водорода
WO2007019390A3 (fr) * 2005-08-03 2007-03-29 Ccmi Corp Amelioration des catalyseurs heterogenes a phase solide actifs en surface
US9339808B2 (en) 2005-08-03 2016-05-17 Ccmi Corporation Enhancement of surface-active solid-phase heterogeneous catalysts
CN103219051B (zh) * 2012-08-23 2018-01-09 孙福民 可控连续氘核聚变产能系统
CN103219051A (zh) * 2012-08-23 2013-07-24 孙福民 可控连续氘核聚变产能方法及可控连续氘核聚变产能系统
JP2016138807A (ja) * 2015-01-27 2016-08-04 三菱重工業株式会社 核種変換反応膜の再生方法及び核種変換システム
WO2016206443A1 (fr) * 2015-06-24 2016-12-29 林溪石 Tube de réaction à fusion froide
US10322826B2 (en) 2016-08-26 2019-06-18 Jerome Drexler Interplanetary spacecraft using fusion-powered thrust
WO2018236444A1 (fr) * 2016-09-23 2018-12-27 Jerome Drexler Appareil et procédé de génération d'électricité par fusion contrôlée catalysée par muons
US10377511B2 (en) 2016-10-17 2019-08-13 Jerome Drexler Interplanetary spacecraft using fusion-powered constant-acceleration thrust
US10384813B2 (en) 2016-11-16 2019-08-20 Jerome Drexler Spacecraft landing and site-to-site transport for a planet, moon or other space body
JP2017167161A (ja) * 2017-05-31 2017-09-21 三菱重工業株式会社 放射性セシウム処理システム及び放射性セシウム処理方法
US10793295B2 (en) 2017-12-05 2020-10-06 Jerome Drexler Asteroid redirection facilitated by cosmic ray and muon-catalyzed fusion
US10815015B2 (en) 2017-12-05 2020-10-27 Jerome Drexler Asteroid redirection and soft landing facilitated by cosmic ray and muon-catalyzed fusion
US10815014B2 (en) 2018-08-24 2020-10-27 Jerome Drexler Spacecraft collision-avoidance propulsion system and method
US10960993B2 (en) 2018-10-30 2021-03-30 Jerome Drexler Spacecraft-module habitats and bases
US10940931B2 (en) 2018-11-13 2021-03-09 Jerome Drexler Micro-fusion-powered unmanned craft
WO2023248107A1 (fr) * 2022-06-21 2023-12-28 Aganyan Fusion Procédé de fusion thermonucléaire contrôlée

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