首页> 外国专利> 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

机译: 233 U同位素工作在铀-燃料循环中的核反应器的方法

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
机译:技术领域:本发明涉及一种随着同位素 233 的发展而在铀-fuel燃料循环中运行核反应堆的方法,旨在用于反应堆堆芯的初始装载用氧化物铀-燃料。使用的燃料为( 235 U α 238 U β 232 Th 1-α-β)O 2 高浓燃料 235 U( 235 U 0.9 238 U 0.1 ),并使用重水作为调节剂和冷却剂(D 2 O)。同时,中子通量的强度及其能量分布是在反应堆运动的频谱中形成的,其中快中子的分数高于热中子,并控制反应堆在功率下的运行通过使其处于临界状态,在重水反应堆中与轻水(H 2 O)进行连续稀释,从而在同位素 233 U和中子吸收剂之间保持平衡效果:延长运动时间的可能性,确保起动机同位素 235 U深度燃烧和有效生产同位素< Sup> 233 U.; 2 cl,6 dwg

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