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METHOD OF OPERATION OF THE NUCLEAR REACTOR IN THE URANIUM-THORIUM FUEL CYCLE WITH THE WORK OF ISOTOPE 233U
METHOD OF OPERATION OF THE NUCLEAR REACTOR IN THE URANIUM-THORIUM FUEL CYCLE WITH THE WORK OF ISOTOPE 233U
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机译: 233 Sup> U同位素工作在铀-燃料循环中的核反应器的方法
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摘要
FIELD: physics.;SUBSTANCE: invention relates to a method for operating a nuclear reactor in an uranium-thorium fuel cycle with the development of an isotope 233U and is intended for the initial loading of the reactor core with oxide uranium-thorium fuel. The fuel used is (235Uα238Uβ232Th1-α-β)O2 high-enriched fuel 235U (235U0.9238U0.1) and the choice of water/fuel volumes in the range of 1.5-1.7 using heavy water as a moderator and coolant (D2O). At the same time, the intensity of the neutron flux and its energy distribution is formed at the beginning of the reactor campaign in the spectrum, in which the fraction of fast neutrons prevails over the thermal ones, and controlling the operation of the reactor at power by keeping it in a critical state, providing a balance between the isotope 233U and neutron absorbers by continuous dilution during the heavy water reactor campaign with light water (H2O) until the moment when light water will take half of the composition.;EFFECT: possibility of extending the campaign time, the possibility of ensuring a deep burnup of the starter isotope 235U and effective production of the isotope 233U.;2 cl, 6 dwg
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