Comparisons between a new point kernel-based scheme and the infinite plane source assumption method for radiation calculation of deposited airborne radionuclides from nuclear power plants

Zhang, Xiaole; Efthimiou, George C.; Wang, Yan; Huang, Meng

doi:10.1016/j.jenvrad.2018.01.002

Cited by 12 publications

(4 citation statements)

References 40 publications

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“…The atmospheric transport model is usually coupled with a gamma radiation model to evaluate radiation exposure [233][234][235][236] . Monte Carlo codes are important tools for simulating interactions between neurons, protons, photons, and electrons with other particles and media.…”

Section: Radiation From Cloud and Ground Depositionmentioning

confidence: 99%

“…In the Japanese System for Prediction of Environmental Emergency Dose Information (SPEEDI) [ 247 , 248 ] and the Worldwide Version of SPEEDI [249] , integration based on the point kernel method is applied for radioactive plume gamma dose computation. The point kernel method has been combined with the Lagrangian puff model to evaluate the ground radiation due to deposition, and the differences between the proposed method and the traditional "infinite plane " source assumption have been investigated under various meteorological conditions [234] . The Lagrangian CALPUFF model has been utilized to investigate external and internal radiation from hypothesized severe accidents at the Daya Bay Nuclear Power Plant (DBNPP) [250] .…”

Section: Radiation From Cloud and Ground Depositionmentioning

confidence: 99%

See 1 more Smart Citation

Atmospheric dispersion of chemical, biological, and radiological hazardous pollutants: Informing risk assessment for public safety

Zhang

Wang

2022

Journal of Safety Science and Resilience

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Section: Radiation From Cloud and Ground Depositionmentioning

confidence: 99%

Section: Radiation From Cloud and Ground Depositionmentioning

confidence: 99%

Atmospheric dispersion of chemical, biological, and radiological hazardous pollutants: Informing risk assessment for public safety

Zhang

Wang

2022

Journal of Safety Science and Resilience

Self Cite

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“…To achieve this goal, the authors devised a G(E) function to calculate the radiation level within the vehicle from spectra obtained by an unshielded or partially shielded detector outside the vehicle. To validate this approach, the authors established a controlled test area featuring known radioactive contaminations [58]. Specifically, the authors opted to employ multiple point-type sealed sources to create a dispersed radioactive contaminated test area, facilitating the evaluation of the proposed methodology [59].…”

Section: Introduction Of the Radiation Protection Features Of The Fir...mentioning

confidence: 99%

Applicability of an Ionising Radiation Measuring System for Real-Time Effective-Dose-Optimised Route Finding Solution during Nuclear Accidents

Zsitnyányi,

Petrányi,

Jónás

et al. 2024

Fire

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The reduction in the effective dose of evacuated injured persons through contaminated areas of nuclear accidents is an essential emergency services requirement. In this context, there appeared a need to develop a dose-optimised route finding method for firefighting rescue vehicles, which includes the development of a real-time decision support measurement and evaluation system. This determines and visualises the radiation exposure of possible routes in a tested area. The system inside and outside of the vehicle measures the ambient dose equivalent rate, the gamma spectra, and also the airborne radioactive aerosol and iodine levels. The method uses gamma radiation measuring NaI(Tl) scintillation detectors mounted on the outside of the vehicle, to determine the dose rate inside the vehicle using the previously recorded attenuation conversation function, while continuously collecting the air through a filter and using an alpha, beta, and gamma radiation measuring NaI(Tl)+ PVT + ZnS(Ag) scintillator to determine the activity concentration in the air, using these measured values to determine the effective dose for all routes and all kinds of vehicles. The energy-dependent shielding effect of the vehicle, the filtering efficiency of the collective protection equipment, and the vehicle’s speed and travel time were taken into account. The results were validated by using gamma point sources with different activity and energy levels. The measurement results under real conditions and available real accident data used in our simulations for three different vehicles and pedestrians proved the applicability of the system. During a nuclear accident based on our model calculations, the inhalation of radioactive aerosols causes a dose almost an order of magnitude higher than the external gamma radiation caused by the fallout contamination. The selection of the appropriate vehicle and its route is determined by the spectrum that can be measured at the accident site but especially by the radioactive aerosol concentration in the air that can be measured in the area. In the case of radiation measuring detectors, the shielding effect of the carrier vehicle must be taken into account, especially in the case of heavy shielding vehicles. The method provides an excellent opportunity to reduce the damage to the health of accident victims and first responders during rescue operations.

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“…As a kind of neutral particle, the neutron has a strong penetrating power. It appears widely in nuclear/fusion plants [1][2][3][4]. A transparent window (viewing window) is required for visual inspection in nuclear/fusion plants.…”

Section: Introductionmentioning

confidence: 99%

Thermal Analysis of a New Neutron Shielding Vacuum Multiple Glass

et al. 2020

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The neutron shielding glass is widely used in nuclear/fusion plants. To improve its temperature resistance and heat insulation, a Gadolinium (Gd)-containing laminate vacuum multiple glass is proposed by using the vacuum insulation method. A 3D finite element model validated by theoretical calculation was developed to analyse the heat transfer path and numerical simulation of the multiple glass was carried out to obtain the temperature distribution and the maximum temperatures of the organic glass in relation to dynamic working temperatures, the sealing agent width, view size, and vacuum thermal conductivity. The results show that the vacuum layer between common glasses can make the work temperature of neutron shielding glass increase. The multiple glass has good heat-shielding performance and it is expected to work in a high-temperature environment. In addition, the vacuum layer between the common glasses and the sealing agent width decay with respect to the view size and vacuum thermal conductivity show an increase in the working temperature of the neutron shielding glass. It was concluded that the order of affecting the temperatures of the organic glass follows the pattern of: view size > vacuum thermal conductivity > sealing agent width.

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Comparisons between a new point kernel-based scheme and the infinite plane source assumption method for radiation calculation of deposited airborne radionuclides from nuclear power plants

Cited by 12 publications

References 40 publications

Atmospheric dispersion of chemical, biological, and radiological hazardous pollutants: Informing risk assessment for public safety

Atmospheric dispersion of chemical, biological, and radiological hazardous pollutants: Informing risk assessment for public safety

Applicability of an Ionising Radiation Measuring System for Real-Time Effective-Dose-Optimised Route Finding Solution during Nuclear Accidents

Thermal Analysis of a New Neutron Shielding Vacuum Multiple Glass

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