首页> 外文会议>14th International Conference on Nuclear Engineering 2006(ICONE14) vol.3 >NEUTRON TRANSPORT CHARACTERISTICS OF A NUCLEAR REACTOR BASED DYNAMIC NEUTRON IMAGING SYSTEM
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NEUTRON TRANSPORT CHARACTERISTICS OF A NUCLEAR REACTOR BASED DYNAMIC NEUTRON IMAGING SYSTEM

机译:基于核反应器的动态中子成像系统的中子传输特性

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An advanced dynamic neutron imaging system has been constructed in the McMaster Nuclear Reactor (MNR) for nondestructive testing and multi-phase flow studies in energy and environmental applications. A high quality neutron beam is required with a thermal neutron flux greater than 5.0x10~6 n/cm~2-s and a collimation ratio of 120 at image plane to promote high-speed neutron imaging up to 2000 frames per second. Neutron source strength and neutron transport have been experimentally and numerically investigated. Neutron source strength at the beam tube entrance was evaluated experimentally by measuring the thermal and fast neutron fluxes, and simple analytical neutron transport calculations were performed based upon these measured neutron fluxes to predict facility components in accordance with high-speed dynamic neutron imaging and operation safety requirements. Monte-Carlo simulations (using MCNP-4B code) with multiple neutron energy groups have also been used to validate neutron beam parameters and to ensure shielding capabilities of facility shutter and cave walls. Neutron flux distributions at the image plane and the neutron beam characteristics were experimentally measured by irradiating a two-dimensional array of Copper foils and using a real-time neutron radiography system. The neutron image characteristics - such as neutron flux, image size, beam quality - measured experimentally and predicted numerically for beam tube, beam shutter and radiography cave are compared and discussed in detail in this paper. The experimental results show that thermal neutron flux at image plane is nearly uniform over an imaging area of 20.0-cm diameter and its magnitude ranges from 8.0x10~6 - 1.0x10~7 n/cm~2-sec while the neutron-to-gamma ratio is 6.0x10~5 n/cm~2-uSv.
机译:McMaster核反应堆(MNR)中已构建了先进的动态中子成像系统,用于能源和环境应用中的无损检测和多相流研究。需要高质量的中子束,其热中子通量应大于5.0x10〜6 n / cm〜2-s,并且在像面上的准直比为120,以促进高速中子成像,每秒高达2000帧。对中子源强度和中子输运进行了实验和数值研究。通过测量热中子通量和快速中子通量,对束管入口处的中子源强度进行了实验评估,并根据这些测得的中子通量进行了简单的分析中子输运计算,以根据高速动态中子成像和操作安全性来预测设施组成要求。具有多个中子能级的Monte-Carlo模拟(使用MCNP-4B代码)也已用于验证中子束参数并确保设施百叶窗和洞穴壁的屏蔽能力。通过照射二维的铜箔阵列并使用实时中子射线照相系统,通过实验测量了像平面上的中子通量分布和中子束特性。本文比较并讨论了通过实验测得的中子图像特征,例如中子通量,图像大小,束质量,并对束管,束快门和射线照相洞穴进行了数值预测。实验结果表明,在成像平面上,在直径为20.0-cm的成像区域内,中子通量几乎是均匀的,其大小范围为8.0x10〜6-1.0x10〜7 n / cm〜2秒,而中子到伽玛比为6.0x10〜5 n / cm〜2-uSv。

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