利用 24Na 测量对临界事故后暴露人员进行分流时的中子剂量估算:东海村临界事故案例研究。

IF 0.8 4区 环境科学与生态学 Q4 ENVIRONMENTAL SCIENCES Radiation protection dosimetry Pub Date : 2024-12-31 DOI:10.1093/rpd/ncae222
Munehiko Kowatari, Osamu Kurihara
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引用次数: 0

摘要

我们通过全身测量法进行24Na测量,研究了临界事故人员分诊的中子剂量估计。作为案例研究,我们检查了1999年9月日本核燃料转换公司的临界事故(国际上称为“Tokaimura事故”)。我们研究了由于初级脉冲照射在工人C体内产生的中子诱导放射性核素。通过蒙特卡罗模拟,共鉴定出87种放射性核素,工作人员C的活度在1.3 × 10-19 Bq至6.9 × 106 Bq之间。计算结果显示,活性最高的放射性核素为28Al (t1/2 = 2.2 min) 6.9 × 106 Bq。38Cl的比活性达到24Na的3倍。这些放射性核素将严重影响事故后立即进行的全身测量中的24Na测量。在事故现场通过全身测量来确定24Na的特异活性,能谱法是更可取的。
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Neutron dose estimation by 24Na measurements in the triage of exposed individuals after criticality accidents: a case study of the Tokaimura criticality accident.

We investigated the neutron dose estimation for the triage of personnel involved in criticality accidents by conducting 24Na measurements via the whole-body measurement method. For a case study, we examined the September 1999 Japan Nuclear Fuel Conversion Co. criticality accident (internationally known as "the Tokaimura accident"). We investigated the neutron-induced radionuclides produced in worker C's body due to the irradiation of the primary pulse. A total of 87 radionuclides were identified, with activities ranging from 1.3 × 10-19 Bq to 6.9 × 106 Bq for worker C by Monte Carlo simulations. The radionuclide with the highest activity was revealed by calculation results: 28Al (t1/2 = 2.2 min) 6.9 × 106 Bq. The specific activity of 38Cl reached a level that was three times that of 24Na. These radionuclides would severely affect the 24Na measurement in the whole-body measurements performed in the immediate post-accident period. Spectrometry would be preferable for determining 24Na specific activities by whole-body measurements at accident sites.

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来源期刊
Radiation protection dosimetry
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.
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