We study a resource-constrained project scheduling problem in a hazardous environment considering some different strategies of staffing. An overhaul project of a nuclear power plant is chosen as a ...

https://www.tandfonline.com/doi/pdf/10.1080/21642583.2018.1494638

Research on a resource-constrained project scheduling problem in a hazardous environment and its staffing strategies based on PSO algorithm

The invention discloses a method and a system for calculating an annual radiation dose of liquid radioactive substances of a nuclear power plant, and belongs to the technical field of assessment of radiation environment influence of nuclear power plants. The method comprises the steps of collecting source data used for calculating an annual effective radiation dose of radionuclides of a liquid way under a normal working condition of the nuclear power plant in a to-be-assessed region; calculating annual radiation doses of radionuclides of a liquid discharge way for the public and a person according to the source data; and calculating an annual collective effective dose of liquid radionuclides for the public according to the annual effective doses of the liquid radionuclides for the public and the person, and the number of residents. Through the method and the system provided by the invention, annual personal and collective effective radiation doses of liquid radioactive pollutants for the public in sub-regions in a range of 80km around a discharge point of the liquid radioactive pollutants of a plant address of the nuclear power plant can be calculated, so that the need of assessing the influence of the annual radiation dose of the liquid discharge way for the public around in a normal running period of the coastal nuclear power plant is met.

Method and system for calculating annual radiation dose of liquid radioactive substances of nuclear power plant

Based on guides RG 1.109, RG 1.111 published by United States Nuclear Regulatory Commission (USNRC), our research concentrates in assessing radiation doses caused by radioactive substances released from the nuclear power plant (NPP) Ninh Thuan 1 under the scenario of normal operation using software package NRCDose72 provided by the USNRC. The database including the released radioactive nuclides, meteorology, terrain, population and agricultural production activities have been collected and processed to build the input data for the model calculation. The wind rose distribution obtained from the meteorological data in a five-year period from 2009-2013 showed that the radioactive nuclides released to environment spread in two main wind directions which are North East and South West. The X/Q (s/m3) and D/Q (s/m2) qualities which are, respectively, the ratio of activity concentration to release rate and that of deposition density of radioactive nuclides to release rate were calculated within an area of 80 km radius from the NPP site using XOQDOQ. Population doses were calculated using GASPAR. The XOQDOQ and GASPAR are two specific softwares in NRCDose72 package.

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Assessment of Radiation Dose Caused by Radioactive Gaseous Effluent Released from Nuclear Power Plant Ninh Thuan 1 under Scenario of Normal Working Conditions

Based on guides RG 1.109, RG 1.111 published by United States Nuclear Regulatory Commission (USNRC)~our~research~concentrates on assessing radiation doses caused by radioactive substances released from the nuclear power plant (NPP) Ninh Thuan 1 to the environment under scenario of an INES-level 5 nuclear accident caused by two incidents of the station black out (SBO) and loss of coolant accident (LOCA) using software~RASCAL4.3~provided by the Emergency Operations Center of USNRC. The plant Ninh Thuan 1 is assumed to use the VVER-1200 technology with a total power of 2400 MW\(_{e}\). The input data for the model calculations is based on building the accident scenario, the technical parameters of VVER-1200 technology and the meteorology. The meteorological data on dry and rainy seasons, which are typical for the Ninh Thuan region was also considered. The \(X/Q\) (s/m\(^{3}\)) quality and the maximum dose values were calculated within an area of 40 km radius from the NPP site, where \(X/Q\) (s/m\(^{3}\)) is the ratio of activity concentration to release rate. Based on the obtained results on dose distribution the necessary measures for nuclear emergency preparedness have been proposed according to the IAEA recommendations.

/pdf/assessment-of-radioactive-gaseous-effluent-released-from-5e3yto2y3c.pdf

Do Xuan Anh

Papers

Assessment of Radiation Dose Caused by Radioactive Gaseous Effluent Released from Nuclear Power Plant Ninh Thuan 1 under Scenario of Normal Working Conditions

Assessment of Radioactive Gaseous Effluent Released From Nuclear Power Plant Ninh Thuan 1 under Scenario of Ines-Level 5 Nuclear Accident