MCNP Simulation of Physics Parameters of Dispersion Fuels for Conversion of NIRR-1 to LEU

K. Ibikunle, U. Sadiq, Y. V. Ibrahim, S. Jonah
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引用次数: 3

Abstract

The Nigeria Research Reactor-1 (NIRR-1) is one of the Commercial Miniature Neutron Source Reactors (MNSRs) sited outside China and scheduled for conversion under the auspices of Reduced Enrichment for Research and Test Reactors (RERTR) program. Since 2006, the reduction in the fuel enrichment of MSNR facilities from greater than 90% HEU cores to less than 20% LEU cores has been embarked upon. Consequently in this work, the physics parameters of three dispersion LEU fuels, which include U3Si, U3Si2, and U9Mo enriched to 19.75% were determined by the MCNP code to investigate their suitability for the conversion of NIRR-1 to LEU. The following reactor core physics parameters were computed for the LEU fuel options: clean cold core excess reactivity (ρex), control rod (CR) worth, shut down margin (SDM), neutron flux distributions in the irradiation channels and kinetics data (i.e. effective delayed neutron fraction, βeff and prompt neutron lifetime, lf). Results are compared with experimental and calculated data of the current HEU core and indicate that it would be feasible to use any of the LEU options for the conversion of commercial MNSR in general and NIRR-1 in particular from HEU to LEU.
核素-1转低浓铀过程中分散燃料物理参数的MCNP模拟
尼日利亚1号研究堆(NIRR-1)是位于中国境外的商业微型中子源反应堆(MNSRs)之一,计划在研究和试验反应堆(RERTR)项目的支持下进行改造。自2006年以来,已经开始将MSNR设施的燃料浓缩从高浓铀堆芯的90%以上降低到低浓铀堆芯的20%以下。因此,在这项工作中,三种分散型低浓铀燃料(U3Si, U3Si2和U9Mo)的物理参数由MCNP代码确定,以研究它们对低浓铀燃料(nir -1)转化为低浓铀的适用性。净冷堆超反应性(ρex)、控制棒(CR)值、关闭裕度(SDM)、辐照通道中的中子通量分布和动力学数据(即有效延迟中子分数,βeff和提示中子寿命,lf)。结果与现有高浓铀堆芯的实验和计算数据进行了比较,表明使用任何低浓铀方案都是可行的,一般来说,特别是将低浓铀转化为低浓铀。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
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来源期刊
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