Vol. 25 No. 2 (2015)
Papers

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

Le Dinh Cuong
Institute for Nuclear Science and Technology (INST), 179 Hoang Quoc Viet, Hanoi
Do Xuan Anh
Institute for Nuclear Science and Technology (INST), 179 Hoang Quoc Viet, Hanoi
Duong Duc Thang
Institute for Nuclear Science and Technology (INST), 179 Hoang Quoc Viet, Hanoi
Nguyen Hao Quang
Vietnam Atomic Energy Institute (VINATOM), 59 Ly Thuong Kiet, Hanoi

Published 11-09-2015

Keywords

  • Loss of Coolant Cccident (LOCA),
  • Station Black Out (SBO),
  • source term,
  • radioactive release,
  • maximum dose value,
  • nuclear power plant (NPP) Ninh Thuan 1,
  • International Nuclear Event Scale (INES),
  • RASCAL4.3
  • ...More
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How to Cite

Khai, N. T., Cuong, L. D., Anh, D. X., Thang, D. D., Giap, T. V., Ha, N. T. T., Bac, V. T., & Quang, N. H. (2015). Assessment of Radioactive Gaseous Effluent Released From Nuclear Power Plant Ninh Thuan 1 under Scenario of Ines-Level 5 Nuclear Accident. Communications in Physics, 25(2), 165. https://doi.org/10.15625/0868-3166/25/2/6133

Abstract

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.

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