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Theoretical and Experimental Research in Neutron Spectra and Nuclear Waste Transmutation on Fast Subcritical Assembly with MOX Fuel

机译:用MOX燃料快速亚临界组件的中子谱和核废料嬗变的理论与实验研究

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The paper deals with theoretical and experimental investigation of transmutation rates for a number of long-lived fission products and minor actinides, as well as with neutron spectra formed in a subcritical assembly driven with the following monodirectional beams: 660-MeV protons and 14-MeV neutrons. In this work, the main objective is the comparison of neutron spectra in the MOX assembly for different external driving sources: a 660-MeV proton accelerator and a 14-MeV neutron generator. The SAD project (JINR, Russia) has being discussed.. In the context of this project, a subcritical assembly consisting of a cylindrical lead target surrounded by a cylindrical MOX fuel layer will be constructed. Present conceptual design of the subcritical assembly is based on the core with a nominal unit capacity of 15 kW (thermal). This corresponds to a multiplication coefficient, k_(eff) = 0.945, and an accelerator beam power of 0.5 kW. The results of theoretical investigations on the possibility of incinerating long-lived fission products and minor actinides in fast neutron spectrum and formation of neutron spectra with different hardness in subcritical systems based on the MOX subcritical assembly are discussed. Calculated neutron spectra emitted from a lead target irradiated by a 660-MeV protons are also presented.
机译:本文对多种长寿裂变产物和次要散浮液的嬗变速率的理论和实验研究,以及在具有以下单向梁驱动的亚临界组件中形成的中子谱:660meV质子和14-mev中子。在这项工作中,主要目的是用于不同外部驱动源的MOX组件中中子谱的比较:660meV质子加速器和14-MeV中子发生器。已经讨论了悲伤的项目(Jinr,俄罗斯)。在该项目的上下文中,将构建由圆柱形MOX燃料层包围的圆柱形引线目标组成的亚临界组件。当前亚临界组件的概念设计基于具有15kW(热)的标称单位容量的核心。这对应于乘法系数,K_(EFF)= 0.945,以及0.5kW的加速度光束功率。讨论了基于MOX亚临界组件的亚临界系统中快速中子谱中焚烧长寿裂变产物和小型散浮液的理论研究的结果。还介绍了从660meV质子照射的铅靶发出的计算中子谱。

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