Assessment of Radiation Dose Caused by Radioactive Gaseous Effluent Released from Nuclear Power Plant Ninh Thuan 1 under Scenario of Normal Working Conditions
- 1 Institute for Nuclear Science and Technology (INST), Hanoi, Vietnam
- 2 Institute for Nuclear Science and Technology (INST), Hanoi, Vietnam
- 3 Institute for Nuclear Science and Technology (INST), Hanoi, Vietnam
- 4 Institute for Nuclear Science and Technology (INST), Hanoi, Vietnam
- 5 Institute for Nuclear Science and Technology (INST), Hanoi, Vietnam
- 6 Institute for Nuclear Science and Technology (INST), Hanoi, Vietnam
- 7 Institute for Nuclear Science and Technology (INST), Hanoi, Vietnam
- 8 Institute for Nuclear Science and Technology (INST), Hanoi, Vietnam
- 9 Vietnam Atomic Energy Institute (VINATOM), Hanoi, Vietnam
Abstract
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/m 3 ) and D/Q (s/m 2 ) 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.
- UNSCEAR 2000 Report Vol. 1, Exposures from Man-Made Sources of Radiation.
- UNSCEAR 2008 Report Vol. 2, Radiation Exposures in Accidents.
- Sagendorf, J.F., Goll, J.T. and Sandusky, W.F. (1982) XOQDOQ: Computer Program for the Meteorological Evaluation of Routine Releases at Nuclear Power Stations. NUREG/CR-2919, US Nuclear Regulatory Commission, Washington DC.
- Strenge, D.L., Bander, T.J. and Soldat, J.K. (1987) GASPAR II—Technical Reference and User Guide. NUREG/CR-4653, US Nuclear Regulatory Commission, Washington DC.
- (1977) Regulatory Guide 1.109—Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I. US Nuclear Regulatory Commission.
- (1977) Regulatory Guide 1.111—Methods for Estimation Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactor. US Nuclear Regulatory Commission.
- Pasquill, F. (1974) Atmospheric Diffusion. Halsted Press, New York.
- Quinn, W.H. and Burt, W.V. (1967) Computation of Incoming Radiation over the Equatorial Pacific. Journal of Applied Meteorology.
- Subpart, D. Radiation Dose Limits for Individual Members of the Public. Part 20-Standards for Protection against Radiation, NRC Regulations (10 CFR).
- (2014) The Vietnam Ministry of Science and Technology (MOST) on Preparing and Planning the Emergency Preparedness for Radiation and Nuclear Accidents. Circular No. 25/2014/TT-BKHCN.
- Manual for Reactor Produced Radioisotopes, IAEA-TECDOC-1340, Vienna.
- UNSCEAR 2013 Report, Volume II, Scientific Annex B: Effects of Radiation Exposure of Children.
- Age-Dependent Doses to Members of the Public from Intake of Radionuclides: Part 1, Pergamon Press, 1989.