TAILIEUCHUNG - Research for forecasting the effect of various meteorological-dynamic conditions on the possible spreading of Cs-137 radioactive substances in case a level 7 incident occurs from Fengcheng nuclear power plant (China)

This study is conducted based on the hypothesis of an accident from Fengcheng NPP with an incident level of 7, equivalent to the Fukushima accident. A modeling system has been established with different failure scenarios based on the Delft3D model. The research results will provide more insights into the extent and scope of the incident and the impact of meteorological conditions and dynamics on the propagation and distribution of radiation when an incident occurs. | Vietnam Journal of Marine Science and Technology 2023 23 1 39 55 Vietnam Academy of Science and Technology Vietnam Journal of Marine Science and Technology journal homepage jmst Research for forecasting the effect of various meteorological-dynamic conditions on the possible spreading of Cs-137 radioactive substances in case a level 7 incident occurs from Fengcheng nuclear power plant China Nguyen Minh Hai1 Vu Duy Vinh1 Nguyen Trong Ngo2 Tran Quang Thien2 1 Institute of Marine Resources and Environment VAST Vietnam 2 Dalat Nuclear Research Institute Lam Dong Vietnam Received 31 December 2021 Accepted 30 June 2022 ABSTRACT Because its location is quite close to the Vietnamese border the future operation of the Fengcheng Fengcheng Nuclear Power Plant NPP can raise many concerns about the impact on the marine environment in case a serious incident occurs. Based on the Delft3D modeling toolkit calculation scenarios to simulate the spreading of Cs-137 radioactive emission when a level 7 incident occurs at Fengcheng NPP have been set up according to different dynamic meteorological conditions presented at the time of incidents during the Northeast monsoon transitional monsoon or Southwest monsoon to assess predict the possibility of radioactive emission and to spread and their affecting the waters of Vietnam. The simulation results show that when a level 7 incident occurs from Fengcheng NPP the area of influence might be the entire East Sea after 3 6 months. The Gulf of Tonkin area would be contaminated with high radiation levels 300 350 Bq m3 after about one month. The radiation would then gradually decrease to less than 150 Bq m3 after one year and below 30 Bq m3 after two years. The impacts of various dynamical and meteorological conditions on the ability to spread and disperse radioactive substances when an incident occurs are only evident in the early stages up to 3 months after the incident . After this time the contaminated area would cover .

• Sinh học
• Nuclear power plant
• Cs 137 radioactive emission
• Northeast monsoon
• Transitional monsoon
• Marine science
• Nuclear engineering and technology
• Seismic fragility evaluation
• The base isolated nuclear power plant piping system
• The failure criterion based on stress strain
• Nuclear power plant piping system
• Seismic fragility analysis
• BNL NRC benchmark model
• Improved PCA method
• Sensor fault detection and isolation in a nuclear power plant
• Sensor fault detection and isolation
• Sensitivity analysis of thermal hydraulic parameters
• The corrosion intensity in nuclear power plant steam generators
• Nuclear power plant steam generators
• The failure of steam generators
• The heat exchangers
• Architectural model driven dependability analysis
• Computer based safety system in nuclear power plant
• Safety system in nuclear power plant
• Embedded Real Time Safety Systems
• Nuclear science and engineering
• Thin plate type embedded ultrasonic transducer
• Magnetostriction for the thickness monitoring
• The secondary piping system of a nuclear power plant
• Secondary Piping System
• Shear Horizontal Wave
• Power plant engineering
• Diesel power plant
• Gas turbine power plant
• Hydro electric power plants
• Electrical system
• Development of earthquake instrumentation for shutdown
• Restart criteria of the nuclear power plant
• Multivariable decision making process
• The nuclear power plant
• Multi unit Level 3 probabilistic safety assessment
• Six unit nuclear power plant site
• Probabilistic safety assessments
• The Fukushima Daiichi nuclear power plant
• Mitigation of high energy arcing faults
• Nuclear power plant medium voltage switchgear
• Nuclear power plants
• High energy arcing fault
• Communications in Physics
• Radioactive gaseous effluent released
• Ninh Thuan 1 nuclear power plant under scenario
• Ines level 7 nuclear accident
• Station black out
• Loss of coolant accident
• International Nuclear Event Scale
• Radioactive effluents released from Korean nuclear power plants
• The resulting radiation doses to members of the public
• Korean nuclear power plants
• Nuclear power plant Ninh Thuan
• Ines level 5 nuclear accident
• The IAEA recommendations
• The Emergency Operations Center of USNRC
• Development of an information reference system
• Reconstruction models of nuclear power plants
• Work site reconstruction models
• Six nuclear power plant workers
• Circulating water systems
• Hydroelectric power plant
• Diesel engine
• Turbines power plants
• Environmental degradation
• Fragility assessment for electric cabinet in nuclear power plant
• Response surface methodology
• The fragility function
• The variability of risk assessment
• Evaluation of availability of nuclear power plant dynamic systems
• Extended dynamic reliability graph with general gates
• Extended dynamic reliability graph
• Reliability graph with general gates
• Comprehensive evaluation method for user interface design
• Nuclear power plant based on mental workload
• Comprehensive evaluation method
• Fuzzy comprehensive evaluation
• Development of field programmable gate arrayebased encryption module
• Mitigate man in the middle attack
• Nuclear power plant data communication network
• Field programmable gate array
• Multi unit Level 2 probabilistic safety assessment
• Level 2 Probabilistic Safety Assessment
• Site Containment Failure Probability
• Multi unit Level 1 probabilistic safety assessment
• Multi unit Core Damage Frequency
• Multi unit Probabilistic
• Safety Assessment Multi unit
• Probabilistic Risk Assessment
• Multi unit Risk
• Site Core Damage Frequency
• Identification of nonregular indication according
• Change of grain size surface geometry
• Nuclear power plant (NPP) reactor vessel
• Upper head alloy 690 penetration
• Characteristics and internal exposure evaluation
• Radioactive aerosols during pipe cutting
• Decommissioning of nuclear power plant
• Pipe cutting internal exposure
• Nuclear energy
• Nuclear power plant outage
• Computer vision
• Automatically detecting abnormal human
• Field operation and preparation
• Data driven simulation
• Environmental impact assessment
• Environmental law
• Environmental agency
• Environmental regulations
• Nuclear regulatory body