Determination of Pu-239 for nuclear material safeguards verification purposes

Proceedings of the Sixteenth National Radio Science Conference. NRSC'99 (IEEE Cat. No.99EX249) Pub Date : 1999-02-23 DOI:10.1109/NRSC.1999.760953

S. El-Mongy, W.A.M. El-Gamal

引用次数: 1

Abstract

This work aims at measurement of Pu-239 for nuclear materials safeguards verification purposes. The work was carried out at Los-Alamos National Lab, (USA). Due to the strategic nature of the element, few samples were available to be assayed. The gamma spectrometric non-destructive assay technique was used for determining amount of Pu in the samples. A correction factor for self-attenuation due to the Pu matrix was made. The results show that the declared (certified) and measured (verified) values of Pu-239 agree with an average precision of about 0.40%.

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用于核材料保障核查目的的钚-239的测定

这项工作旨在为核材料保障核查目的测量钚-239。这项工作在洛斯阿拉莫斯国家实验室(美国)进行。由于该元素的战略性质，很少有样品可供分析。采用伽马能谱法无损测定样品中Pu的含量。提出了一种自衰减校正因子。结果表明，Pu-239的申报(认证)值与测量(验证)值的平均精度一致，约为0.40%。

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

Proceedings of the Sixteenth National Radio Science Conference. NRSC'99 (IEEE Cat. No.99EX249)

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