The method of obtaining thermal energy at nuclear fission of heavy elements of slow neutrons

 

(57) Abstract:

Usage: the invention relates to the field of nuclear energy and can be used as a method of obtaining thermal energy at nuclear fission of heavy elements with slow neutrons. Summary of the invention in nuclear reactors as nuclear fuel use fissile isotopes predominantly of highly enriched uranium-235 or plutonium-239, the mass content m1which in each portion of the original sahajayoga fuel, chosen in relation to the contents of m2it impurities within 1(m1+m2)/m1E1/e,65. Fission for each portion of the first loaded into the reactor fuel is carried out in stages in n cycles, with one portion of the fuel is chosen within 2n5. In each of the cycles of reaction and reduce the content of m3to be removed from the fuel fission fragments in relation to the number of m4fuel in the reactor to a value of 0.8 m3/m40,99. Then remove from the reactor fuel or part of m5within 1,2(m5+m4)/m4(m6+m5/m5(m7+m8/m8(m1+m2)/m1E1/e,65.

The reaction is words which one portion of the fuel is chosen within 2n5. In each of the cycles of reaction and reduce the content of m3to be removed from the fuel fission fragments in relation to the number of m4fuel in the reactor to a value of 0.8 m3/m40,99. Then remove from the reactor fuel or part of m5within 1,2(m5+m4)/m4(m6+m5)/m5(m7+m8)/m8(m1+ m2) / m11,05, specific energyproject e1fuel support in relation to the maximum allowable values of its energonapryazhennosti e2within 0,35 e1/ e20,65, fission for each portion of the first loaded into the reactor fuel is carried out in stages in n cycles, with one portion of the fuel is chosen in the range of 2 n to 5, in each of the cycles of reaction and reduce the content of m3to be removed from the fuel fission fragments in relation to the number of m4fuel in the reactor to a value of 0.8 m3/ m40.99, and then removed from the reactor fuel or part of m5within 1,2 (m5+ m4) / m42 and is directed at the radiochemical processing and isotopic enrichment, primarily in the cascade of centrifugal machines, cleaning it before the content is tanoe fuel in the reactor and, if necessary, desegregate reactor original fuel and so forth are fission, supporting the maximum number of m7in the reactor fissile material within 1 (m7+ m8) / m81,05, where m8the total number in the reactor fuel.

 

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