基于创新数学公式和Python代码的U3O8样品富集率估算与验证

R. El-Tayebany, H. Elbegawy, S. El-Mongy
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引用次数: 0

摘要

根据浓缩程度的不同,浓缩铀可用于多种用途,例如为电力和研究反应堆制造新燃料。此外,根据1968年的《不扩散核武器条约》(NPT),应对国家,特别是全面保障监督协定的无核武器国家进行检查和核查,以证明其“和平利用”承诺。因此,核查浓缩过程和百分比被认为是调查目的的基本要素。本文的主要目的是利用创新的公式估计和验证U3O8样品的富集百分比。浓缩计算使用不同低浓缩铀(LEU)比例的经认证的安全保障核材料进行,实验使用HpGe探测器,计算使用Python 3.10代码。与经认证的浓缩百分比(从耗尽的0.32% - 4.5%)相比,结果证明了精确和可接受的值,差异范围为1⁓3.8%。这项工作中使用的新公式适用于国家、区域和国际保障视察目标。
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Estimation and Validation of Enrichment Percentage of U3O8 Samples using Innovative Mathematical Formula and Python Code
Depending on the enrichment levels, enriched uranium can be used for many purposes, such as the fabrication of fresh fuels for power and research reactors. Furthermore, under the 1968 Treaty on the Non-Proliferation (NPT), the states, specifically non-nuclear-weapon states of comprehensive safeguards agreements, should be inspected and verified to prove "peaceful use" commitments. Consequently, verifying the enrichment process and the percentage is considered an essential element for investigation purposes. The primary motivation of this paper is to estimate and validate U3O8 samples enrichment percentage using innovative formula. The enrichment calculations were conducted using certified safeguarded nuclear materials with varying low enriched uranium (LEU) ratios, both experimentally with a HpGe detector and computationally with Python 3.10 code. The results prove precise and acceptable values compared to the certified declared enrichment percentage (from depleted 0.32% - 4.5%) with differences in the range of 1⁓ 3.8%. The new formula used in this work applies to national, regional, and international safeguards inspection targets.
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