Design of the Important Area Airborne Radioactivity Monitoring System and Calculation of the Alarm Threshold of HTR-PM

2018 ◽  
Author(s):  
Wenqian Li ◽  
Chuan Li ◽  
Jianzhu Cao ◽  
Feng Xie
Keyword(s):  
High Temperature ◽  
Monitoring System ◽  
Power Plants ◽  
Radiation Monitoring ◽  
Operational Experience ◽  
Primary Coolant ◽  
Pressurized Water ◽  
Radioactivity Monitoring ◽  
Radiation Monitoring System ◽  
Airborne Radioactivity

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.

Design of the Area Radiation Monitoring System in Nuclear Island of HTR-PM

2017 ◽  
Author(s):  
Feng Xie ◽  
Jiaji Kong ◽  
Hongqi Liu ◽  
Jianzhu Cao
Keyword(s):  
High Temperature ◽  
Power Plant ◽  
Dose Rate ◽  
Monitoring System ◽  
Radiation Monitoring ◽  
Radiation Dose Rate ◽  
Pressurized Water ◽  
Proper Actions ◽  
Radiation Monitoring System ◽  
High Temperature Gas

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.

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

2016 ◽  
Author(s):  
Feng Xie ◽  
Wenqian Li ◽  
Zhihui Li ◽  
Jianzhu Cao ◽  
Hong Li ◽  
...  
Keyword(s):  
Monitoring System ◽  
Nuclear Power ◽  
Thermal Power ◽  
Radiation Monitoring ◽  
Power Station ◽  
Liquid Form ◽  
Pressurized Water ◽  
Primary Loop ◽  
Carbon 14 ◽  
Radiation Monitoring System

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.

Environmental Radiation Monitoring System Development for Atmospheric Plumes from Light Water Reactor Nuclear Power Plants

1982 ◽  
Vol 56 (3) ◽  
pp. 580-590 ◽  
Author(s):  
Tachimori Ohba ◽  
Satsuharu Takimoto ◽  
Yoshio Kitada ◽  
Tomio Tsunoda ◽  
Akira Kobayashi ◽  
...  
Keyword(s):  
Monitoring System ◽  
Nuclear Power ◽  
Power Plants ◽  
System Development ◽  
Radiation Monitoring ◽  
Light Water Reactor ◽  
Environmental Radiation ◽  
Light Water ◽  
Water Reactor ◽  
Radiation Monitoring System

scholarly journals Performance of the High Pressure Xe detector for the Radiation Monitoring System of the Nuclear Power Plants

2011 ◽  
Vol 1 (0) ◽  
pp. 324-327
Author(s):  
Byeong Hyeon PARK ◽  
Doh Yun JANG ◽  
Cheol Ho LEE ◽  
Byoung Hwi KANG ◽  
Han Soo KIM ◽  
...  
Keyword(s):  
High Pressure ◽  
Monitoring System ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Radiation Monitoring ◽  
Radiation Monitoring System

A Remote Radiation Monitoring System Using an Autonomous Unmanned Helicopter for Nuclear Emergencies

2008 ◽  
Vol 45 (sup5) ◽  
pp. 414-416 ◽  
Author(s):  
Shin-ichi Okuyama ◽  
Tatsuo Torii ◽  
Akihiko Suzuki ◽  
Masanori Shibuya ◽  
Nobuyuki Miyazaki
Keyword(s):  
Monitoring System ◽  
Radiation Monitoring ◽  
Unmanned Helicopter ◽  
Radiation Monitoring System ◽  
Remote Radiation

High-Temperature Oxidation Modeling of New Perspective Accident Tolerant Fuel Claddings

2019 ◽  
Author(s):  
Alexander Vasiliev
Keyword(s):  
High Temperature ◽  
High Temperature Oxidation ◽  
Power Plants ◽  
Renewable Energy Sources ◽  
Nuclear Industry ◽  
Safety Level ◽  
Pressurized Water ◽  
Temperature Oxidation ◽  
Design Basis ◽  
New Perspective

Abstract Currently, the comprehension among the specialists and functionaries is getting stronger that the nuclear industry can encounter serious difficulties in development in the case of insufficiently decisive measures to enhance the safety level of nuclear objects. The keen competition with renewable energy sources like wind, solar or geothermal energy takes place presently and is expected to continue in future decades. One of main measures of nuclear safety enhancement could be the drastic renovation of materials used in nuclear industry. The analytical models of high-temperature oxidation of new perspective materials including chromium-nickel-based alloys, zirconium-based cladding with protective chromium coating, FeCrAl alloys and composite claddings on the basis of SiC/SiC in the course of design-basis and beyond-design-basis accidents at nuclear power plants (NPPs) are developed and implemented to severe accident computer running code. The comparison with available experimental data is conducted. The preliminary calculations of nuclear pressurized water reactor loss-of-coolant accidents with new types of claddings demonstrate encouraging results for hydrogen generation rate and integral hydrogen production. It looks optimistic for considerable upgrade of safety level for future generation NPPs using new fuel and cladding materials.

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