VALIDATION OF THE GEIGER-MULLER COUNTER MODEL OF BDMG-04-02 USING THE MONTE-CARLO TECHNIQUE

The model of the Geiger-Muller counter as the internal part of BDMG-04-02 detection unit in the calibration fa-cility UPGD-2 was developedin MCNP6.2. The different methods are used for the determination of the Geiger-Muller counter response. The F1 and F8 tally applicability is briefly described. BDMG-04-02 model was validated by comparative analysis of the calculated results and experimental values of the counter responses that obtained on the UPGD-2 calibration facility. Additionally, the absolute, geometric and intrinsic registration efficiency of BDMG-04-02 was determined. The paper has been emphasized the disadvantages of using the method of direct counting of the electrons on the surface of the Geiger-Muller counter (F1).

Ionizing Radiation Monitoring Technology at the Verge of Internet of Things

As nuclear technology evolves, and continues to be used in various fields since its discovery less than a century ago, radiation safety has become a major concern to humans and the environment. Radiation monitoring plays a significant role in preventive radiological nuclear detection in nuclear facilities, hospitals, or in any activities associated with radioactive materials by acting as a tool to measure the risk of being exposed to radiation while reaping its benefit. Apart from in occupational settings, radiation monitoring is required in emergency responses to radiation incidents as well as outdoor radiation zones. Several radiation sensors have been developed, ranging from as simple as a Geiger-Muller counter to bulkier radiation systems such as the High Purity Germanium detector, with different functionality for use in different settings, but the inability to provide real-time data makes radiation monitoring activities less effective. The deployment of manned vehicles equipped with these radiation sensors reduces the scope of radiation monitoring operations significantly, but the safety of radiation monitoring operators is still compromised. Recently, the Internet of Things (IoT) technology has been introduced to the world and offered solutions to these limitations. This review elucidates a systematic understanding of the fundamental usage of the Internet of Drones for radiation monitoring purposes. The extension of essential functional blocks in IoT can be expanded across radiation monitoring industries, presenting several emerging research opportunities and challenges. This article offers a comprehensive review of the evolutionary application of IoT technology in nuclear and radiation monitoring. Finally, the security of the nuclear industry is discussed.

Radiological Scouting, Monitoring and Inspection Using Drones

Human populations and natural ecosystems are bound to be exposed to ionizing radiation from the deposition of artificial radionuclides resulting from nuclear accidents, nuclear devices or radiological dispersive devices (“dirty bombs”). On the other hand, Naturally Occurring Radioactive Material industries such as phosphate production or uranium mining, contribute to the on site storage of residuals with enhanced concentrations of natural radionuclides. Therefore, in the context of the European agreements concerning nuclear energy, namely the European Atomic Energy Community Treaty, monitoring is an essential feature of the environmental radiological surveillance. In this work, we obtain 3D maps from outdoor scenarios, and complete such maps with measured radiation levels and with its radionuclide signature. In such scenarios, we face challenges such as unknown and rough terrain, limited number of sampled locations and the need for different sensors and therefore different tasks. We propose a radiological solution for scouting, monitoring and inspecting an area of interest, using a fleet of drones and a controlling ground station. First, we scout an area with a Light Detection and Ranging sensor onboard a drone to accurately 3D-map the area. Then, we monitor that area with a Geiger–Müller Counter at a low-vertical distance from the ground to produce a radiological (heat)map that is overlaid on the 3D map of the scenario. Next, we identify the hotspots of radiation, and inspect them in detail using a drone by landing on them, to reveal its radionuclide signature using a Cadmium–Zinc–Telluride detector. We present the algorithms used to implement such tasks both at the ground station and on the drones. The three mission phases were validated using actual experiments in three different outdoor scenarios. We conclude that drones can not only perform the mission efficiently, but in general they are faster and as reliable as personnel on the ground.

Comparison of the Background Radiation Level within Kanchanpur District, Nepal

We have reported the background radiation of urban and some other rural places of Kanchanpur district, Nepal. A simple portable Geiger Muller counter was used to quantify the level of overall background radiation by collecting data of different forty seven (including six urban and forty one rural places) places within the district. Our study reveals that the background radiation level of the study district is below the risk level. The maximum background count values 33.00±4.47 (Mahakali Zonal Hospital), 33.93 ± 1.16 (Mahakali School, Mahakali -01) and 31.30±3.97 CPM (Gha gaon) have been reported which is below the risk level. The observed values of radiation counts at all the sample places indicate that Kanchanpur district is radiation risk free.

Determination of the Affected Steam Generator during Primary-to-Secondary Leakage in WWER-1000 Using a Geiger-Muller Counter

The main indicator of a primary-to-secondary leakage in WWER-1000 is the increased secondary side activity. Activity can be detected by radiation devices. Accordingly, the online monitoring of the secondary side activity allows the reactor operator to successfully determine the affected steam generator and implement appropriate actions to transfer the reactor in a safe state. The detectors are supposed to be installed behind the steam generator pipelines outside of the containment. The scattered photon spectrum, formed from N-16 decay in the detection area, is analyzed. The possibility of using a detection unit with a Geiger-Muller counter to register particles with energies that exceed the device energy range, which is indicated in the technical specifications, is confirmed. The paper indicates that the detector response is determined by two different approaches. In the first case, the absorbed dose rate is calculated by the energy deposition method (KERMA factor), and in the second case, the detector count rate is calculated by taking into account the secondary ionization processes. The calculation results of the detector response taking into account the dead time are presented. The dead time effect on the absorbed dose rate registered by the counter is analyzed. The calculated response coefficients of the detector for the main reference radionuclides of the primary side, which could be potentially transported into the detector’s registration volume, is obtained. Additionally, the paper provides for the maximum limit of the detected absorbed dose rate of BDMG-04-02B. The calculations were carried out using MCNP6 neutronic code focused on the analysis of the elementary particle interaction with surrounding materials.

On Distributions of One Class of Random Sums and their Applications

We propose results of the investigation of properties of the random sums of random variables. We consider the case, where the number of summands is the first moment of an event occurrence. An integral equation is presented that determines distributions of random sums. With the help of the obtained results we analyse the distribution function of the time during which the Geiger-Muller counter will not lose any particles, the distribution function of the busy period of a redundant system with renewal, and the distribution function of the sojourn times of a single-server queueing system.