Identifikasi kebutuhan sarana-prasarana pemantauan radiasi nirawak dalam pengawasan radiasi reaktor riset di Indonesia

The facility’s licensee conducts environmental radiation monitoring in nuclear facilities to monitor radiation exposure in the facility’s vicinity. This activity is carried out also to monitor radiation release as a result of nuclear reactor operation. Aside from that, monitoring also works as a device to monitor radioactive release in a nuclear emergency. Therefore, the radiation monitoring system is crucial in nuclear utilization facilities to determine the number of radiation exposure to the surrounding environment. However, the existing stationary monitoring system has a risk of being unable to work if the system is down in case of natural disaster occurs. One way to mitigate this risk is to deploy an unmanned radiation monitoring system to monitor radiation exposure without putting personnel at risk. To define a suitable unmanned radiation monitoring system, identification of facilities and infrastructure required to design an unmanned radiation monitoring system for a research reactor in Indonesia is carried out. Facilities and infrastructure needed for unmanned radiation monitoring systems are unmanned aerial vehicles, radiation detector, control and communication module, navigation system, and software for the control system. These required facilities and infrastructure are then specified to determine the necessary specification for monitoring research reactor in Indonesia. The facilities’ required specifications are unmanned aerial vehicles with rotary-wing type, CdZnTe Detector, and GPS/GLONASS based navigation system. For infrastructure specification, control and communication module and software for the control system is not specified in how the system could meet the expected required performance rather than in detail. However, the system must provide and process measurement data in real-time to be presented in a radiation heatmap. Keywords: Identification, Radiation Monitoring, Unmanned

Hygienic assessment of personnel working conditions in underground uranium mining

The aim of the study is to assess the main radiation-hazardous factors that determine the effective dose of personnel during underground uranium mining at the Priargunsky Industrial Mining and Chemical Association, and to summarize the data of the radiation control of the enterprise for 2016-2020. The main factors that create personnel dose loads are: the volume activity of short-lived daughter products of radon decay in the air, the dose rate of external gamma radiation, and the volume activity of long-lived alpha-emitting radionuclides of the uranium-radium series in industrial dust. Information on the structure and values of individual effective doses of workers is presented. Recommendations for improving the radiation monitoring system are given.

PRELIMINARY DEVELOPMENT OF RADIONUCLIDES RELEASE OF INDIVIDUAL DOSE CODE PROGRAM FOR RADIATION MONITORING PURPOSES

Environmental radiation monitoring is one of the important efforts in protecting society and the environment from radiation hazards, both natural and artificial. The presence of three nuclear research reactors and plans to build a nuclear power plant reactor prompted Indonesia to prepare a radiation monitoring system for safety and security (SPRKK). The goal of the study is to provide an appropriate method for developing radiation monitoring system to support the development of nuclear power plant in the near future. For this preliminary study, the author developed a code program using Gaussian distribution model approach for predicting radionuclide release and individual dose acceptancy by human being within 16 wind directions sectors and up to 50 km distance. The model includes estimation of source term from the nuclear installation, release of radionuclides source into air following Gaussian diffusion model, some of the release deposit to the land and entering human being through inhalation, direct external exposure, and resuspension, and predicted its accepted individual dose. This model has been widely used in various code program such as SimPact and PC-Cosyma. For this study, the model will be validated using SimPact code program. The model has been successfully developed with less than 5% deviation. Further study will be done by evaluating the model with real measuring data from research reactor installation and prepare for interfacing with real time radiation data acquisition and monitoring as part of radiation monitoring system during normal and accident condition.

IMPLEMENTATION OF RADIATION MONITORING SYSTEM

Multiple atomic accidents urge for the development of radiation monitoring systems which has the capability to measure and display radiation level in the contaminated zones. This paper presents the design and implementation of such systems using Geiger Müller (GM) counter nuclear kit which can be used in any radiation contaminated area. GM counter transmits readings of radiation at fixed intervals to the Arduino microcontroller in real-time. This proposed system utilizes liquid crystal display (LCD) as an interface for displaying the information. This system is easy to use and modular. The experimental data and the obtained results shows that this proposed radiation monitoring system is feasible and efficient.

The Current State of Monitoring of Radiation Situation in the State Corporation “Rosatom”

The industry-specific radiation monitoring system of the State Corporation «Rosatom» (OSMRO) performs the functions of the subsystem for monitoring the radiation situation of the State Corporation «Rosatom» as part of the Unified State Automated System for Monitoring the Radiation Situation on the territory of the Russian Federation. Currently, 29 organizations of the State Corporation «Rosatom» are involved in the OSMRO, which monitor the radiation situation in the sanitary protection zone and the observation zone (local level). At the corporate level, monitoring is carried out by the Departmental Information and Analytical Center of the State Corporation «Rosatom». The article considers the goals, objectives, and current state of the organization and monitoring of the radiation situation. It is shown that the operation of an extensive radiation monitoring system in the State Corporation «Rosatom» contributes not only to the radiation safety of the population and the environment, but also contributes to the confirmation of the safe operation of enterprises and organizations of the nuclear industry.

Features of background radiation of different St. Petersburg districts

Radiation safety takes an essential part in the megalopolises' ecological system. Nowadays the influence of radiation factor on the biosphere is considered one of the determining factors and it causes the necessity to monitor the environmental and radiation safety of the population. The aim of the study is a comparative assessment of the ambient equivalent dose rate (ADER) of gamma radiation according to automated radiation monitoring system (АSКRО) data and its own measurements in the South-Western district of St. Petersburg. The article presents an analysis of the radiation background of St. Petersburg over the past five years based on the data of the АSКRО, as well as the results of own measurements of the ADER in the South-Western district of St. Petersburg using the dosimeter-radiometer "Ecologist profi". When analyzing the radiation levels of various districts of St. Petersburg, it was found that the regions with a relatively higher level of ADER included the Central and South-Western regions. The results of our own meas-urements are comparable with the data from АSКRО; there are no significant differences be-tween the data samples. The results of the study show that the АSКRО data can be used for a general description of the radiation situation in certain areas of St. Petersburg, but they can not serve as a substitute for operational radiation control (monitoring). It is necessary to constantly control and monitor the radiation situation in the region in order to obtain information for timely detection of changes in the radiation situation and to prevent possible negative consequences of radiation exposure for the population and the natural environment.