Design of the Process and Effluent Radiation Monitoring System of HTR-PM

Author(s):  
Feng Xie ◽  
Wenqian Li ◽  
Zhihui Li ◽  
Jianzhu Cao ◽  
Hong Li ◽  
...  

The process and effluent radiation monitoring system can provide information about kinds of the radionuclide and activity concentrations, which is indispensable, important, and peculiar for a nuclear power station compared to a regular thermal power station. On the basis of knowledge about pressurized water reactors (PWRs) and high temperature gas-cooled reactors (HTGRs), the process and effluent radiation monitoring system of HTR-PM has been designed. It mainly contains several monitoring channels for concerned process systems, certain important areas, and gaseous and liquid effluents. For the coolant is helium and spherical fuel elements containing tristructural isotropic (TRISO) coated particles are adopted in HTR-PM, the source terms are different from those of PWRs. Not only fission or activation products in the gaseous or liquid form are monitored, but also the radioactive dust in the primary loop is sampled for analysis. The tritium (H-3) and carbon-14 (C-14) are taken a key consideration, which will be sampled in the primary loop, in certain important areas, in the secondary loop, and in the gaseous effluent in the stack. Design features of the process and effluent radiation monitoring system of HTR-PM are introduced and discussed compared to those of PWRs.

2021 ◽  
Vol 23 (3) ◽  
pp. 91
Author(s):  
Jupiter Sitorus Pane ◽  
Pande Made Udiyani ◽  
Muhammad Budi Setiawan ◽  
Surip Widodo ◽  
I Putu Susila

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.


2019 ◽  
Vol 186 (2-3) ◽  
pp. 337-341
Author(s):  
Jakub Lüley ◽  
Štefan Čerba ◽  
Branislav Vrban ◽  
Filip Osuský ◽  
Ondrej Sľuka

Abstract Even with the very low probability of events leading to leakage of radioactive particles outside the nuclear facility (<10−4 per reactor per year), R&D of systems that could mitigate the impact of these events cannot be neglected. For such a purpose, the RMS-00x radiation monitoring system could be used, which is a modular system covering the functionality of dose rate measurement, air sampling and radiation map creation without requiring the human personnel to be present at the measurement site. Before this system is used in real conditions, its components must be thoroughly calibrated, based on certified measurement equipment and state-of-art simulation tools. This article deals with the description of the RMS-00x sensor modules and demonstrates their functionality in combination with unmanned aerial vehicle. In addition, demonstration of the use of the developed technology was carried out as part of the regular emergency planning and preparedness of Nuclear Power Plant Jaslovské Bohunice (EBO) nuclear power plant on 26 October 2017.


Author(s):  
Feng Gao ◽  
Jianguo Zhang ◽  
Yifang Yang ◽  
Zhentao Wang ◽  
Haijun Wang

It was well known that the radiation monitoring is an essential part of dealing with a nuclear accident safely. When a Nuclear-powered Vessel (NPV) was in the event of a nuclear accident at sea, the rescue vessels with different functions would rush to the scene of the accident to implement a rescue. In order to ensure the radiation safety of the emergency personnel aboard the rescue vessels, some kinds of radiation measuring devices should be installed and the ambient radiation levels should be measured. However, the occurrence of the nuclear accident at sea is few and unforeseeable, so the rescue vessels usually perform other ordinary works and are dispersed in different departments. Since that, the service efficiency of the fixed radiation measuring devices installed in the rescue vessels is low. What’s more, it is difficult keep all of them at a good condition. In order to resolve these contradictions, a new type of radiation monitoring system, which has been called as Area Radiation Monitoring System for the Nuclear Accident at Sea (ARMS), is proposed in this paper. With the application of Building Block Design, the ARMS becomes easy to be assembled and disassembled, so the centralized maintenance comes true. The ARMS has a more wide range of uses, not only for the nuclear accident emergency radiation monitoring at sea, but also for ordinary or emergency radiation monitoring for monitoring nuclear power plant and the Nuclear-powered Vessel harbor. The component and function of the monitoring system as well as its Data Transmission Networks are introduced in this paper.


Author(s):  
Wenqian Li ◽  
Chuan Li ◽  
Jianzhu Cao ◽  
Feng Xie

Unlike the conventional pressurized water reactor (PWR), helium is adopted as the coolant in the high-temperature gas-cooled reactor pebble-bed module (HTR-PM). Due to the leakage of the primary coolant, in certain process rooms and some important areas, the airborne radioactivity should be monitored for the purpose of personnel radiation protection and emergency control. The system executing above function in HTR-PM is called important area airborne radioactivity monitoring system. This system consists of five separate monitoring channels, in which online and/or sampling monitoring devices will be included. For radiation monitoring system of a reactor, the calculation and setting of alarm thresholds for online devices is an important issue. The set of alarm thresholds requires not only accurate calculation but also feedback from actual operational experience. The design of the high-temperature reactor is different from the PWR, so the set of the alarm thresholds need special considerations. Based on the calculation of source terms and production-removal model, the theoretical radioactive levels of the sampled gases of all the online monitors were calculated and the alarm thresholds adopted in the current design are presented in this paper. The set of the alarm thresholds takes the influences of the background and other factors into account. This paper provides a method for calculating and determining the alarm thresholds of the radiation monitoring system, which can provide references for other nuclear power plants.


Author(s):  
Feng Xie ◽  
Jiaji Kong ◽  
Hongqi Liu ◽  
Jianzhu Cao

The area radiation monitoring system can supply information of the abnormal radiation levels in a nuclear power plant quickly, give an alarm on site explicitly, and display the dose rate value and alarm information remotely. Thus, it can help the radiation protection officer to take proper actions timely to protect personnel from excess irradiation. According to the experience and technology from the pressurized water reactors (PWRs), the area radiation monitoring system in nuclear island of high temperature gas-cooled reactor pebbled-bed module (HTR-PM) which is a modular high temperature gas-cooled reactor demonstration power plant in China has been designed. It is used to monitor the external radiation exposure dose rate at the passageway in the control areas, operational areas, equipment rooms, etc. The design scheme of the area radiation monitoring system in nuclear island of HTR-PM is presented, which can be divided into two parts, the stationary area γ radiation monitoring subsystem and portable radiation dose rate monitoring subsystem. The operational principle of the system, the layout of the area radiation monitors, the main characteristics of the instruments, and the communication logical framework of the system are introduced in this paper.


1982 ◽  
Vol 56 (3) ◽  
pp. 580-590 ◽  
Author(s):  
Tachimori Ohba ◽  
Satsuharu Takimoto ◽  
Yoshio Kitada ◽  
Tomio Tsunoda ◽  
Akira Kobayashi ◽  
...  

2020 ◽  
Vol 225 ◽  
pp. 08008 ◽  
Author(s):  
Jakub Lüley ◽  
Branislav Vrban ◽  
Štefan Čerba ◽  
Filip Osuský ◽  
Vladimír Nečas

The absence of online radiation monitoring systems has been observed in the case of Fukushima nuclear accident. As the tsunami destroyed 23 of the 24 status monitoring points, almost no relevant radiation dose measurements data were available. A rapid deployment of a mobile radiological unit that can quickly determine the activity and direction of the radioactive cloud spread on the ground or in the air can prevent unnecessary deaths and related financial losses. Although the design of the current generation of NPPs incorporates features that minimize the risk of large radioactive releases outside the reactor, it is still important to focus on the development of systems that can mitigate the consequences of such events. In situations when the level of radiation does not permit the personal to perform the required measurements, online unmanned radiation monitoring systems may come to the play. For such a purpose the RMS-00x radiation monitoring system could be used, which is a modular system covering the functionality of dose rate measurement, air sampling and radiation map creation without requiring the human personnel to be present at the measurement site. The main purpose of the RMS-00x radiation monitoring system is the rapid deployment of unmanned monitoring devices to reduce the radiation burden on workers and on public. The system can be applied in the vicinity of a nuclear power plant (NPP) or at any location, where source of ionizing radiation could be present. Before this system is used in real conditions, its components must be thoroughly calibrated, based on certified measurement equipment and state-of-art simulation tools. This paper deals with the description of the RMS-00X sensor modules and demonstrates their functionality in combination with UAV. In addition, demonstration of the use of the developed technology was carried out as part of the regular emergency planning and preparedness of EBO NPP on 26th October 2017.


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