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INVENTION
Patent of the Russian Federation RU2035070
ENERGY NUCLEAR INSTALLATION
The name of the inventor: Vasilyev AA; Danilov M.M .; Katarzhnov Yu.D .; Kiselev G.V .; Kushin VV; Nedopekin VG; Plotnikov SV; Rogov VI; Chuvilo IV; Grebenkin K.F.
The name of the patent owner: Closed Joint-Stock Company - Center of Accelerating Technologies "Cascade"
Address for correspondence:
Date of commencement of the patent: 1993.04.27
Use: nuclear power. SUMMARY OF THE INVENTION: The apparatus comprises at least one accelerator and one subcritical and neutron multiplying cell, arranged in the form of a cylindrical blanket located in a protective box, located around a neutron producing target interacting with an accelerator ion beam. The blanket is divided into multiplying neutrons of the section by at least one ring neutron valve. Absorption of the neutron flux by the valve from the propagating section to the neighboring one towards the target is 10-1000 times.
DESCRIPTION OF THE INVENTION
The invention relates to nuclear power engineering and can be used in solving the problem of nuclear firing of weapons-grade plutonium and uranium-235 with the production of useful energy.
An energy nuclear facility (EYU) containing a REMK-1000 channel nuclear reactor is known. The active zone of this reactor can be represented as consisting of 117 identical subcritical polycells connected along a neutron flux. Polyamides collectively form the active zone of the channel reactor in a critical state [1]
The disadvantage of the well-known nuclear power plant is its low nuclear safety associated with the emergence of a positive feedback on the neutron flux between polycells.
The closest technical solution is the ETH containing at least one accelerator and one subcritical and neutron multiplying cell, which is a cylindrical blanket placed in a protective box around a neutron-producing target interacting with an ion beam from an accelerator with an energy of the order of 1 GeV, a steam generating unit And an electric generator [2]
The disadvantage of this solution is the high energy density of the cell that replicates neutrons, which leads to a decrease in the reliability and nuclear safety of the EYA.
The technical result of the proposal is to enhance the nuclear safety of the nuclear power station by reducing the energy density of a single cell multiplying a neutron by partitioning its core with neutron valves and using accelerators with a reduced ion energy while maintaining the total power of the EYU.
The essence of the invention consists in that in the EYU containing at least one accelerator and one subcritical and neutron multiplying cell made in the form of a cylindrical blanket located in the protective box, located around a neutron-producing target interacting with the ion beam from the accelerator, and the blanket is divided into Multiplying the neutrons of the section with at least one ring neutron valve, which ensures the absorption of the neutron flux from the propagating section to the neighboring one towards the target by a factor of 10-1000.
The essence of the invention consists in the fact that the neutron valve is made in the form of continuous layers of the absorber of thermal neutrons and the retarder of fast neutrons located in the direction from the target.
The essence of the invention consists in the fact that the number of neutron gates in one cell does not exceed five.
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In Fig. The functional scheme of the EYE is presented for the case when the proposed EYU contains six power blocks, each of which is provided with an accelerator, and the active zone of each cell is partitioned by a single neutron valve. The neutron-multiplying cell 1 is made in the form of a subcritical blanket 2 with a neutron-producing target 3 located in its center, partitioned by a neutron valve 4 and enclosed in a corresponding protective box 5. Each target 3 is associated with an appropriate deuteron accelerator 6. Each cell 1 is connected to the input 7 and output 8 collectors. The outlet manifold 8 through the heat exchanger-steam generator 9 and the main circulation pump 10 is connected to the inlet manifold 7. The heat exchanger-steam generator 9 is connected to the turbine unit 11 and the electric power generator 12. Each of the neutron valves 4 is made in the form of a solid ring cylinder and consists of a thermal neutron absorber, for example a boron 2-5 cm thick and a fast neutron moderator, for example a carbon 30-50 cm thick, with a layer of thermal absorber first in relation to the target 3 Neutrons. |
EYA WORKS AS FOLLOWS:
Each of the accelerators 6 produces an ion beam, for example deuterons, with energy in the range (20-200) MeV, by which the target target 3 (lithium or beryllium) is irradiated, generating a flux of primary neutrons that multiply in the first (central) section of each of the six subcritical Blankets 2 and through the neutron valve 4 enter the second (peripheral) and subcritical propagation section of the blanket 2. The multiplying sections of the blanket 2 are manufactured by the reactor technology and have a neutron spectrum that is rigid enough so that the neutrons with minimal absorption pass through the valve 4 in the direction away from the target 3. In the opposite direction, to the center of the blanket 2, the neutron transmission is attenuated 10-1000 times, since the structure of the valve 4 is operating: successive deceleration and neutron capture. Each section of blanket 2 operates in subcritical mode with an effective multiplication factor K eff = 0.90-0.97, the maximum value of which is determined by the conditions of nuclear safety. Thus, the neutrons generated from the target 3 are multiplied in the first multiplying neutron section of the blanket 2 with the multiplication factor K y = 1 / (1-K ef ), and the fission neutron generation rate n 1 in the first section of the blanket 2:
N 1 = 1 · K y · K pr , n / s, where I is the beam current of accelerated deuterons;
K n is the coefficient of transformation of deuterons into neutrons.
The multiplying section is created with a large neutron leakage through the side surface and the valve 4 so that the neutron transfer coefficient from the previous to the next section of K n is not less than 0.1 such part of the neutrons enter the excitation (multiplication) of the subsequent section of the blanket, where it multiplies with the corresponding K The effect of this section. Consequently, the rate of neutron generation n 2 in the second section of blanket 2 will be
N 2 = n 1 · K y · K n = I · K y2 · K n · K pr , n / s
Thus, each of the blankets 2 partitioned by neutron valves 4 operates as a neutron multiplier from target 3 with a significantly higher neutron multiplication factor than for a conventional one-section blanket, with each section of blanket 2 having a given value of K eff determined by the requirements of the nuclear safety of the facility.
The coolant, the cooling blanket 2, flows through the pipes of the output manifold 8 to the heat exchanger-steam generator 9 where it partially evaporates and drives the turbine unit 11 that starts the electric power generator 12. The condensate after the condensers of the turbines 11 through the main circulating pump 10 is again fed through the inlet pipes Collector 7 into each of the cells 1.
CLAIM
1. ENERGY NUCLEAR PLANT, containing at least one subcritical and neutron multiplying cell, arranged in the form of a cylindrical blanket located in a protective box around a neutron producing target interacting with an ion beam of an accelerator, characterized in that the blanket is divided into neutron multiplying sections at At least one ring neutron valve, which ensures that the neutron flux is absorbed from the propagation section to the neighboring one 10,000 times toward the target.
2. The plant according to claim 1, characterized in that the neutron valve is in the form of continuous layers of the absorber of thermal neutrons and a moderator of fast neutrons located in the direction from the target.
3. The plant according to claim 1 and / or 2, characterized in that the number of neutron valves in one cell does not exceed five.
print version
Date of publication 25.03.2007gg
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