用模拟核燃料样品进行无损检测的脉冲中子成像

Daisuke Ito , Tadafumi Sano , Jun-ichi Hori , Yoshiyuki Takahashi , Hiroyuki Hasemi , Takashi Kamiyama , Ken Nakajima
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引用次数: 1

摘要

用含少量锕系元素的反式铀(TRU)燃料建立快堆系统,需要一种高衰变热、高放射性核燃料的综合评价方法。此外,从核安全的角度出发,需要一种快速、准确的钚定量方法。为了满足这些需求,必须开发一种核浓度、热性质和物理信息的定量评价技术。本文主要研究脉冲中子的无损成像技术。在北海道大学中子源(HUNS)上进行了实验,并应用气电子倍增器(GEM)获得了飞行时间(TOF)的二维信息。为了模拟核燃料球团,制备了热中子截面与浓缩铀燃料相当的样品,并获得了模拟样品的透射图像。此外,在样品中插入一小块模拟实际燃料中Pu点的铟,并讨论了该小点的可探测性。
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Pulsed Neutron Imaging for Non-destructive Testing using Simulated Nuclear Fuel Samples

An integrated assessment method for a nuclear fuel with high decay heat and high radioactivity is required to establish fast reactor system with Trans-Uranium (TRU) fuel containing minor actinides. In addition, a Pu quantitation method with rapidity and accuracy is also necessary in a viewpoint of nuclear security. For these demands, a quantitative evaluation technique for nuclei concentration, thermal property and physical information of such fuel has to be developed. The present study focuses on the non-destructive imaging using pulsed neutrons. Experiments are carried out at Hokkaido University Neutron Source (HUNS) and a gas electron multiplier (GEM) is applied to obtain 2-D information of time-of-flight (TOF). To simulate a nuclear fuel pellet, a sample with equivalent thermal neutron cross-section to the enriched uranium fuel is prepared and the transmitted images of the simulated sample are acquired. Furthermore, a small piece of In, which simulates the Pu spot in the actual fuel, is inserted into the sample and the detectability of the small spot is discussed.

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