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INVENTION
Russian Federation Patent RU2280927

METHOD FOR OPERATING TERMOELEKTROHIMICHESKIH generator (TEHG)
FOR HYDROGEN ionizing radiation

Name of the inventor: Vorogushin Victor T. (RU); Telnova Galina (RU); Solntsev Konstantin (RU)
The name of the patentee: Institute of Physical and Chemical Problems of Ceramic Materials Academy of Sciences (RU)
Address for correspondence: 119361, Moscow, ul. Ozernaya, 48, IPC RAS
Starting date of the patent: 2004.10.15

The invention relates to the preparation of hydrogen from the water during the operation of nuclear power stations using termoelektrohimicheskih generators.

The technical result of the invention is to improve a method for producing hydrogen from water by using the energy of ionizing radiation and the heat generated in the process of generating electricity. According to the invention method of operating a power plant comprising several TEHG solid ceramic electrolyte, including a solid electrolyte with proton conductivity and a solid electrolyte with conductivity of oxygen ions and bears on its surface porous electrode coatings based on palladium, a water supply system, the separation and removal of hydrogen and oxygen, but also additional TEHG electrochemical system Na-Na with a solid electrolyte based on sodium beta-alumina with a conductivity of sodium ions coated on the surface of the porous electrode coating, said TEHG placed in a compartment with water or steam and fissionable material U 235 or its oxides, followed by displacement chamber in a nuclear reactor core, and by closing the electrodes through an external load generate an electric current in these generators with simultaneous separation of water decomposition products during ionization irradiation, thus generated in the compartment heat in the process of nuclear fission and generating electrical energy fed in additional TEHG Na-Na electrochemical system. Before use in the anode chamber further TEHG placed fissile material U-235 or its oxides.

DESCRIPTION OF THE INVENTION

The invention relates to the conversion of nuclear and thermal power into electricity to produce hydrogen.

There is a method of operation of nuclear power plants, in which all of the energy released during a nuclear reaction is converted into heat energy, and then in the thermodynamic cycle turbine generator into mechanical and electrical energy. [1] The resulting electricity is supplied to the electrolyzer to produce hydrogen from water. The same occurs in the heat cycle TEHG when converting thermal energy into electrical energy [2].

It is known that in the process of generating electrical energy of the useful potential energy is converted into heat (mainly due to losses at the electrodes and electrolyte) that is usually assigned unproductively [3]. These heat losses are significant and the maximum power level equal to half the potential energy [4], ie in this case the efficiency conversion of potential energy ( e) is 0.5 (50%) of the efficiency Carnot cycle ( k).

When heating temperature T g and a temperature of 1000 K, the refrigerator 400 to the total efficiency is equal to

to · e = 0,6.0,5 = 0.3 (30%).

If the anode and cathode cavity TEHG withstand a maximum temperature of the cycle, and the heat generated in the process of generating electric power, and will be characterized by the maximum temperature and therefore can be completely disposed of in the thermodynamic cycle, increasing its efficiency [5].

In this case, the limit value efficiency defined by the formula = to · e / 1- a + (1- e).

In the preparation of hydrogen from water in the electrolyzer mode, a maximum power efficiency value electrolyzer e. will be 0.5 (50%), while the value of total efficiency power plants for hydrogen production will be equal to

= to · e · E = 0.15 (15%).

With regard to the use for this purpose in the electrolytic electricity generated by nuclear power plants, the value of the total efficiency power plants taking into account the conversion of high-grade nuclear energy will be relatively low.

It is known that the energy of the ionizing radiation produced during the nuclear reaction, per fission of U 235 of 200 MeV (the energy of fast neutrons - 5 MeV, - Beams - 10 MeV, - And neutrino particles - 18 MeV, the fission fragments - 166 MeV) [6]. Consequently, the energy of any particle of ionizing radiation thousands of times the energy of atoms in molecules (~ 5 eV) and the valence electron binding energy of atoms (~ 10 eV). [7]

It is known that during the irradiation of the ionization of water molecules decompose to hydrogen and oxygen. Part of the resulting hydrogen and oxygen atoms enter into the reverse reaction to form water and heat, and the other part is stored [7] in the form of a gas mixture of these elements. Due TEHG solid electrolyte with conductivity of hydrogen ions (proton) and oxygen ion, respectively, deposited with the electrode coatings on the basis of palladium, it becomes possible to separate and discharge of these gases from the reaction zone with the simultaneous generation of electrical current.

To improve the overall efficiency power plant for producing hydrogen from the water provides a method of operating TEHG using ionizing radiation.

To achieve this hermetic chamber with insulated collector placed nuclear fuel (U 235 or its oxides) and termoelektrohimicheskie oscillators with ceramic solid electrolytes (fuel cells), namely with TE conducting hydrogen ions (proton conductivity), in particular, zirconate, strontium and FC with a conductivity of oxygen ions, in particular based on zirconium and cerium oxides with additives of yttrium oxide and (or) the rare earth elements [8] - coated porous electrodes based on palladium and-water supply system and separation system and removing from the reaction zone formed during the decomposition of water gaseous reaction products in the form of hydrogen and oxygen, but also additional TEHG electrochemical system sodium-sodium with ceramic fuel cell based on sodium beta-alumina with a conductivity of sodium ions coated on the surface porous electrode (e.g., Mo) coating.

When moving the cover into the core of a nuclear reactor under the influence of ionizing radiation of the nuclear reaction decomposes to form water molecules and hydrogen atoms and oxygen ions and OH radicals type [7]. Part of the obtained product takes the reverse reaction to form water and heat, and the other part of the mixture of gaseous products accumulate. The difference in partial pressures of hydrogen and oxygen, respectively, on both sides of the solid electrolyte and proton conductivity, respectively with oxygen and the potential energy creates an electromotive force on the electrodes respectively covering the TE.

Current taps through connecting electrodes payload can be subdivided product gas mixture into components by directing the hydrogen ions and oxygen ions, respectively, through the solid electrolytes with an appropriate TEHG conductivity. Thus in one process the electrical current and generate simultaneously receive and withdrawn hydrogen and oxygen. The bay is fed water (steam) to the extent of its expansion and spending. This generated heat in the compartment is directed to additional TEHG electrochemical system sodium-sodium with TE on the basis of sodium beta-alumina coated with a porous electrode, to which the operation of the anode cavity such TEHG placed nuclear fuel. All electric energy flows directed to the electrolyzer to produce hydrogen.

INFORMATION SOURCES

  1. Bump TR The third generation of breeder reactors. Nuclear physics and plasma. M .: Science, 1974, vol. №10, s.66-77.

  2. Agrus B. Thermally regenerable element with liquid metals. Coll. PPTE and TE 1964, №11.

  3. Vorogushin VT A method for improving the efficiency thermally regenerated fuel cell. Abstracts of the VI All-Union Conference on Electrochemistry. Current sources and energy converters. 1982, vol.1, p.61.

  4. Tabor ON Plants for the direct conversion of thermal energy into electricity. M .: Higher School, 1965.

  5. Vorogushin VT Thermodynamic cycle with the heat generated by power generation. Journal of Physical Chemistry. 1982. t.LVI, s.1092-1095.

  6. Murray R. Introduction to nuclear engineering. I.L.M. 1995, p.62.

  7. Platzman RL What is ionizing radiation? Nuclear physics and plasma. M .: Nauka, 1974, p.3

  8. E. Glebova breakthrough in hydrogen future. Science and life. 2004. №2, s.16-19.

CLAIM

  1. A method of operating a system termoelektrohimicheskih generators (TEHG) with solid ceramic electrolyte, a water supply system, the separation and removal of hydrogen and oxygen, including a solid electrolyte proton conductive solid electrolyte with conductivity for oxygen ions and bears on its surface porous electrode coatings based on palladium, a and additional TEHG electrochemical system Na-Na with a solid electrolyte based on sodium beta-alumina with a conductivity of sodium ions coated on the surface of the porous electrode coating, characterized in that said TEHG placed in the compartment containing the water or steam and the fissile material U 235 or oxides, followed by displacement compartment into the core of a nuclear reactor, remotely connected TEHG electrodes with external payload generated in said TEHG electric current withdrawn, respectively, hydrogen and oxygen, is added to the compartment water as its decomposition and consumption, while a compartment heat generated in the nuclear fission power generation, and is sent to additional TEHG Na-Na electrochemical system.

  2. Operating method according to claim 1, characterized in that the anode chamber of the electrochemical system TEHG Na-Na administered before use fissile U 235 substance or its oxides.

print version
Publication date 27.11.2006gg