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首页> 外文期刊>Annals of nuclear energy >Monte Carlo simulation of core physics parameters of the Nigeria Research Reactor-1 (NIRR-1)
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Monte Carlo simulation of core physics parameters of the Nigeria Research Reactor-1 (NIRR-1)

机译：尼日利亚研究堆1（NIRR-1）核心物理参数的蒙特卡罗模拟

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摘要

The Monte Carlo N-Particle (MCNP) code, version 4C (MCNP4C) and a set of neutron cross-section data were used to develop an accurate three-dimensional computational model of the Nigeria Research Reactor-1 (NIRR-1). The geometry of the reactor core was modeled as closely as possible including the details of all the fuel elements, reactivity regulators, the control rod, all irradiation channels, and Be reflectors. The following reactor core physics parameters were calculated for the present highly enriched uranium (HEU) core: clean cold core excess reactivity (ρ_(ex)), control rod (CR) and shim worth, shut down margin (SDM), neutron flux distributions in the irradiation channels, reactivity feedback coefficients and the kinetics parameters. The HEU input model was validated by experimental data from the final safety analyses report (SAR). The model predicted various key neutronics parameters fairly accurately and the calculated thermal neutron fluxes in the irradiation channels agree with the values obtained by foil activation method. Results indicate that the established Monte Carlo model is an accurate representation of the NIRR-1 HEU core and will be used to perform feasibility for conversion to low enriched uranium (LEU).
机译：使用蒙特卡罗N粒子（MCNP）代码，版本4C（MCNP4C）和一组中子横截面数据来开发尼日利亚研究堆1（NIRR-1）的精确三维计算模型。反应堆堆芯的几何形状尽可能接近建模，包括所有燃料元件，反应性调节器，控制棒，所有辐照通道和Be反射镜的细节。对于当前的高浓缩铀（HEU）堆芯，计算了以下反应堆堆芯物理参数：干净的冷堆芯过量反应性（ρ_（ex）），控制棒（CR）和匀场值，关闭余量（SDM），中子通量分布在辐照通道中，反应性反馈系数和动力学参数。 HEU输入模型已通过最终安全分析报告（SAR）中的实验数据进行了验证。该模型相当准确地预测了各种关键的中子学参数，并且在辐射通道中计算出的热中子通量与箔活化方法获得的值一致。结果表明，已建立的蒙特卡洛模型是NIRR-1 HEU核的准确代表，将用于进行向低浓铀（LEU）转化的可行性。

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