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METHOD AND REACTOR FOR THE GENERATION OF ENERGY IN THE PROCESS OF A CONTROLLED NUCLEAR FISSION (международный патент)
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| 06.12.2009, 21:44 |
| The present invention relates to the field of nuclear physics and, more particularly, to the physics of energy generation in the fission-type reactors. A problem to be solved in accordance with the present invention resides in the improvement of ecology, power efficiency and safety. A technical result of the proposed method lies in an increase in the efficiency and the use of neutrons; the formation of stationary compositions of a fuel mixture; a deep depletion of a fertile material. The above technical results are achieved by the fact that in a known method for the generation of energy in the process of a controlled nuclear fission by means of neutrons, comprising moderating and recoverying thermal neutrons to a fissile core, circulating a fuel composition containing a fertile material with isotopes of so formed fissile materials through a fast neutron region, a thermal neutron region of the fissile core, and through a cooling region, the improvements reside in that it further comprises selection and a directed recovery of thermal neutrons into a thermal neutron region of the fissile core, circulation of a fuel composition is performed over two loops one of which passing through the thermal neutron region and a cooling region and the other passing through the fast neutron region and the cooling region, and a material of fuel compositions of both loops is interchanged. The problem is also solved thanks to the fact that in a known reactor for generating energy in the process of a controlled nuclear fission comprising a moderator, a fuel composition in a closed loop passing through the cooling region and the fissile core with the thermal and fast neutron regions, the improvements reside in that the fuel composition is disposed within at least two loops one of which intersecting the thermal neutron region and the other intersecting the fast neutron region of the fissile core, and said loops are interconnected by a device for interchanging a material of both loops, said moderator is made in the form of a hollow shaper of a directed thermal neutron flux, said fissile core is located in a hollow, and said shaper comprises ducts for shaping a directed neutron flux oriented only in the direction of a fuel composition loop intersecting the thermal neutron region of the fissile core. (не забудьте нажать "скачать с сервера")
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