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Theme 6. Environmental monitoring and assessment 主题6。环境监察及评估
Pub Date : 2023-02-01 DOI: 10.4103/0972-0464.368745
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引用次数: 0
Theme 3. Radiation safety and protection in medical and industrial sectors 主题3。医疗和工业部门的辐射安全和防护
Pub Date : 2023-02-01 DOI: 10.4103/0972-0464.368742
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引用次数: 0
Theme 7. Existing Exposures 主题7。现有的风险
Pub Date : 2023-02-01 DOI: 10.4103/0972-0464.368746
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引用次数: 0
Theme 1. Foundation Topics on Radiation Protection Philosophy and Risk Estimates 主题1。关于辐射防护理念和风险评估的基础主题
Pub Date : 2023-02-01 DOI: 10.4103/0972-0464.368740
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引用次数: 0
Theme 5. Nuclear instrumentation and system development 主题5。核仪器和系统开发
Pub Date : 2023-02-01 DOI: 10.4103/0972-0464.368744
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引用次数: 0
Theme 8. Emergency preparedness and response 8个主题。应急准备和反应
Pub Date : 2023-02-01 DOI: 10.4103/0972-0464.368747
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引用次数: 0
Theme 9. Regulatory framework: System of protection, standards and regulation 主题9。监管框架:保护、标准和监管体系
Pub Date : 2023-02-01 DOI: 10.4103/0972-0464.368748
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引用次数: 0
Uncertainty in estimated intake for routine lung monitoring of Pu/Am Pu/Am常规肺部监测估计摄入量的不确定性
Pub Date : 2023-01-01 DOI: 10.4103/rpe.rpe_25_23
M. Nadar, Sushanta Halder, L. Mishra, Deepak Akar, Indrasen Singh, Pramilla Sawant
In routine monitoring of radiation workers to detect internal contamination due to Pu/Am, it is assumed that intake has occurred at the midpoint of the monitoring interval. Radiation worker is normally monitored at the end of the annual monitoring interval, within a span of ±1 month under a routine in vivo monitoring program. An uncertainty is introduced in intake estimation as the time of intake can vary over the entire monitoring interval. In this work, uncertainties introduced in the intake estimation of Type M and S compounds of Pu/Am are evaluated due to unknown time of intake for annual and biennial monitoring frequency.
在对辐射工作人员进行常规监测以检测由于Pu/Am引起的内部污染时,假定摄入发生在监测间隔的中点。放射工作人员通常在年度监测间隔结束时进行监测,在常规体内监测计划下进行±1个月的监测。由于摄入时间在整个监测间隔内可能变化,因此在摄入估计中引入了不确定性。在这项工作中,由于每年和两年监测频率的摄入时间未知,对Pu/Am的M型和S型化合物的摄入估计中引入的不确定性进行了评估。
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引用次数: 0
A review on current status of radioactivity monitoring in Indian nonnuclear industries 印度非核工业放射性监测现状综述
Pub Date : 2023-01-01 DOI: 10.4103/rpe.rpe_31_22
S. Sahu, M. Tiwari, R. Bhangare, V. Pulhani, AVinod Kumar
The distribution of naturally occurring radioactive materials (NORM) generated/discharged in nonnuclear industries such as coal combustion residuals from different coal-based power plants, fertilizer, construction, tobacco, and other industries into the environment, has not been reviewed in the Indian context. In the present review, systematic survey and analysis of the reported occurrence of U238, Th232, and K40 in these nonnuclear industrial sectors is discussed. Most of the data compiled and described in this review are sourced from major popularly referred, peer-reviewed scientific journal publications since the year 2005. Apart from radioactivity levels in products from nonnuclear industrial sectors different radiological indices such as absorbed dose, dose rate, etc., are also compared and discussed. Overall, this review presents a comprehensive analysis of NORMs in nonnuclear industrial sectors of India.
非核工业中产生/排放的天然放射性物质(NORM)的分布,如不同燃煤发电厂、化肥、建筑、烟草和其他行业的燃煤残留物,尚未在印度进行审查。在本综述中,对U238、Th232和K40在这些非核工业部门的报道进行了系统的调查和分析。本综述中汇编和描述的大多数数据来源于自2005年以来普遍引用的、经过同行评审的主要科学期刊出版物。除了非核工业部门产品的放射性水平外,还比较和讨论了不同的放射性指标,如吸收剂量、剂量率等。总体而言,本综述对印度非核工业部门的NORM进行了全面分析。
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引用次数: 0
Gamma spectrometry of coolant lines of KAMINI reactor KAMINI反应堆冷却剂管线的伽马能谱
Pub Date : 2023-01-01 DOI: 10.4103/rpe.rpe_30_23
TK Srinivasan, P. Annadurai, Akila Raghuraman, R. Sarangapani
Gamma spectrometry of the KAMINI reactor coolant lines at the selected spots/locations was carried out during 20kWt power and shutdown using portable spectrometers such as RIIDEye-X, RayMon (Cadmium Zinc Telluride), and hyper pure germanium.133Xe (81 keV),85m Kr (150 keV), and 135Xe (250 keV) isotopes could be identified. The spectra results did not indicate the presence of internal contamination due to any corrosion activation products such as 56Mn, 59Fe, 60Co, and fission products. The gamma radiation level observed during reactor power on the selected locations is only due to the fission product noble gases (FPNGs) and their short-lived radionuclides 88Rb and 138Cs generated and not any pipeline internal contamination.137Cs and trace quantities of 60Co were identified in the mixed bed regenerated liquid. The presence of 137Cs could be attributed due to the tramp fuel fissions.
在20kWt功率和停堆期间,使用便携式光谱仪,如RIIDEye-X、RayMon(碲化镉锌)和超纯锗,对选定地点/位置的KAMINI反应堆冷却剂管线进行了伽马能谱分析。可以鉴定出133Se(81keV)、85m Kr(150keV)和135Xe(250keV)同位素。光谱结果没有表明由于任何腐蚀活化产物如56Mn、59Fe、60Co和裂变产物而存在内部污染。在选定位置的反应堆通电期间观察到的伽马辐射水平仅是由于裂变产物惰性气体(FPNG)及其产生的短寿命放射性核素88Rb和138Cs,而不是任何管道内部污染。在混床再生液体中发现了137Cs和痕量60Co。137Cs的存在可归因于不稳定燃料裂变。
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引用次数: 0
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Radiation Protection and Environment
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