Estimation of 241Am and 239Pu activity embedded in the tissue using portable planar HPGe detector.

IF 0.8 4区环境科学与生态学 Q4 ENVIRONMENTAL SCIENCES

Radiation protection dosimetry Pub Date : 2024-06-03 DOI:10.1093/rpd/ncae105

Manohari Murugan, Sugumar Ponraj, Mathiyarasu Ramasamy, Ponraju Durairaj, Venkatraman Balasubramanian

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引用次数: 0

Abstract

This paper describes a procedure for the estimation of 241Am and 239Pu activity present in the human tissue by measuring the depth of contaminant using a portable Planar High Purity Germanium detector (HPGe). The ratios of photopeak counts of X-rays or gammas obtained with the detector coupled to collimator are calculated for the estimation of depth of the contaminant and the optimum one is determined. Since Minimum Detectable Activities (MDA) for the detector coupled to a collimator are higher than that of bare detector, activity must be estimated using bare detector, after locating the contaminant. Two methods are described for the estimation of plutonium coexisting with 241Am: (i) Abundance and isotopic correction for 239Pu (ii) and 239Pu:241Am ratio. The procedure to estimate 239Pu when plutonium isotopes alone are present is also established. An optimum monitoring period to detect the minimum value of intake for both radionuclides corresponding to chelation therapy and excision is also derived.

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使用便携式平面 HPGe 探测器估算嵌入组织中的 241Am 和 239Pu 放射性活度。

本文介绍了一种利用便携式平面高纯锗探测器（HPGe）测量污染物深度，从而估算人体组织中 241Am 和 239Pu 放射性活度的方法。通过计算探测器与准直器耦合获得的 X 射线或伽马射线的光峰计数比率，来估算污染物的深度，并确定最佳比率。由于与准直器耦合的探测器的最小可探测放射性活度（MDA）高于裸探测器，因此在确定污染物位置后，必须使用裸探测器估算放射性活度。本报告介绍了估算与 241Am 共存的钚的两种方法：(i) 239Pu 的丰度和同位素校正 (ii) 以及 239Pu:241Am 比率。此外，还制定了在只有钚同位素存在时估算 239Pu 的程序。此外，还得出了一个最佳监测期，以检测与螯合疗法和切除术相对应的两种放射性核素的最小摄入值。

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

Radiation protection dosimetry 环境科学-公共卫生、环境卫生与职业卫生

CiteScore

1.40

自引率

10.00%

发文量

223

审稿时长

6-12 weeks

期刊介绍： Radiation Protection Dosimetry covers all aspects of personal and environmental dosimetry and monitoring, for both ionising and non-ionising radiations. This includes biological aspects, physical concepts, biophysical dosimetry, external and internal personal dosimetry and monitoring, environmental and workplace monitoring, accident dosimetry, and dosimetry related to the protection of patients. Particular emphasis is placed on papers covering the fundamentals of dosimetry; units, radiation quantities and conversion factors. Papers covering archaeological dating are included only if the fundamental measurement method or technique, such as thermoluminescence, has direct application to personal dosimetry measurements. Papers covering the dosimetric aspects of radon or other naturally occurring radioactive materials and low level radiation are included. Animal experiments and ecological sample measurements are not included unless there is a significant relevant content reason.