Comparison of deterministic and stochastic methods for external gamma dose rate calculation in the decommissioning of nuclear power plants

2019 ◽  
Vol 134 ◽  
pp. 67-76 ◽  
Author(s):  
Dávid Bednár ◽  
Martin Lištjak ◽  
Andrej Slimák ◽  
Vladimír Nečas
Keyword(s):  
Dose Rate ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Gamma Dose ◽  
Gamma Dose Rate ◽  
Stochastic Methods ◽  
Rate Calculation

Field Methods for Studying the Radiation Situation in the Area of the Belarusian NPP in the Pre-Operational Period

ANRI ◽  
2020 ◽  
pp. 31-44
Author(s):  
Aleksey Ekidin ◽  
Aleksey Vasil'ev ◽  
Maksim Vasyanovich ◽  
Evgeniy Nazarov ◽  
Mariya Pyshkina ◽  
...  
Keyword(s):  
Dose Rate ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Field Studies ◽  
Radiation Monitoring ◽  
Normal Operation ◽  
Construction Site ◽  
External Radiation ◽  
Field Methods

The article presents the results of field studies in the area of the Belarusian NPP in the pre-operational period. The «background» contents of gamma-emitting radionuclides in individual components of the environment are determined. The main array of dose rate measurements in the area of the NPP construction site is in the range 0.048 ÷ 0.089 μSv/h. External radiation in the surveyed area is formed at 96% due to 40K, 226Ra and 232Th. The information obtained can be used to correctly interpret the data of future radiation monitoring during normal operation of nuclear power plants.

scholarly journals A preliminary study of geological variation of in-situ gamma dose rate in the vicinity of coal-fired power plants

2021 ◽  
Vol 23 (4) ◽  
pp. 1810-1817
Author(s):  
Vu Ngoc Ba ◽  
Bui Ngoc Thien ◽  
Truong Thi Xuan Truong ◽  
Nguyen Quang Dao ◽  
Le Xuan Thuyen ◽  
...  
Keyword(s):  
Dose Rate ◽  
Power Plants ◽  
Fossil Fuels ◽  
Gamma Dose ◽  
Gamma Dose Rate ◽  
Coal Consumption ◽  
Dose Rates ◽  
Average Value ◽  
Effective Doses ◽  
The Difference

Introduction: The utilization of fossil fuels in coal-fired power plants (CFPPs) for electricity generation could lead to the release of additional natural and artificial radioisotopes into the surrounding environment and consequently, increase the gamma dose rate at these areas. Methods: In this study, the geological variation of gamma dose rate in the vicinity of Duyen Hai CFPP complex and Vinh tan CFPP complex were evaluated. Results: The obtained gamma dose rates were in the range from 0.07 to 0.22 μSv h-1 with the average value of 0.13 μSv h-1 for Duyen Hai area and in the range from 0.14 to 0.34 μSv h-1 with the average value of 0.21 μSv h-1. The results indicated that the gamma dose rate in Vinh tan area is higher than the corresponding value of Duyen Hai area. Both natural aspects, such as the geological differences as well as geomorphology and weathering process, and anthropogenic aspects, such as the difference in operational scale, coal consumption and ash discharge between Duyen Hai and Vinh Tan CFPP complex, might significantly contribute to the variation of gamma dose rate in the investigated locations. Conclusion: Overall, the calculated outdoor annual effective doses of two studied areas showed that the radiological impacts of both Duyen Hai and Vinh Tan CFPP complex to the environment and public health are negligible.

scholarly journals Uncertainty analysis of containment dose rate for core damage assessment in nuclear power plants

2018 ◽  
Vol 50 (5) ◽  
pp. 673-682
Author(s):  
Guohua Wu ◽  
Jiejuan Tong ◽  
Yan Gao ◽  
Liguo Zhang ◽  
Yunfei Zhao
Keyword(s):  
Uncertainty Analysis ◽  
Dose Rate ◽  
Damage Assessment ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Core Damage

scholarly journals Study of a High Temperature–Resistant Shielding Material for the Shielding Doors of Nuclear Power Plants

2021 ◽  
Vol 9 ◽  
Author(s):  
LI Xiao-ling ◽  
Wu Rong-jun ◽  
Xu Xiao-hui ◽  
Zhang Duo-fei ◽  
YU Ming
Keyword(s):  
High Temperature ◽  
Dose Rate ◽  
Nuclear Power ◽  
Optimization Design ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Neutron Shielding ◽  
Comprehensive Properties ◽  
Loss Of Coolant Accident ◽  
Shielding Material

An optimization design and application of high temperature–resistant shielding material was carried out according to the nuclear power plant source characteristics and special protection requirements such as loss-of-coolant accident (LOCA). The composition of lead–boron polyethylene shielding composite was optimized based on the genetic algorithm and Monte Carlo methods and then realized by blending modification and graft copolymerization to improve its high temperature–resistant, shielding, and mechanical properties. Then comprehensive properties such as mechanical, neutron shielding, damp heat aging, irradiation resistance, and high temperature resistance were tested. These experiments proved that the high temperature–resistant lead–boron polyethylene shielding composite has excellent performance; especially, as it is able to keep a complete structure in a high-temperature environment of up to 190°C for 48 h. Finally, the shielding composite was applied to the shielding door design of a reactor pit chamber. When the shield thickness is 60 mm, the level of the neutron dose rate was reduced by 10 times, and that of the γ dose rate was reduced by 5 times, which meets all the requirements of radiation protection safety for nuclear power plants.

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