Atmospheric radionuclides transported to Fukuoka, Japan remote from the Fukushima Dai-ichi nuclear power complex following the nuclear accident

Momoshima, Noriyuki; Sugihara, Shinji; Ichikawa, R.; Yokoyama, H.

doi:10.1016/j.jenvrad.2011.09.001

Cited by 64 publications

(41 citation statements)

References 5 publications

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“…The two cases also have very close SR values (the SR of GP4 is 28 and that of GP3 is 27). Since there were no simulations with intermediate gaseous fractions, the results can only indicate that the optimal gaseous fractions of 131 I lie somewhere between 30 or 60 % for the model setup in this study, which is also consistent with the result from the study by Momoshima et al (2012).…”

Section: The Influence Of Emission Rates and Characteristicssupporting

confidence: 88%

Modeling and sensitivity analysis of transport and deposition of radionuclides from the Fukushima Dai-ichi accident

Huang

et al. 2014

Atmos. Chem. Phys.

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Abstract. The atmospheric transport and ground deposition of radioactive isotopes 131 I and 137 Cs during and after the Fukushima Dai-ichi Nuclear Power Plant (FDNPP) accident (March 2011) are investigated using the Weather Research and Forecasting-Chemistry (WRF-Chem) model. The aim is to assess the skill of WRF in simulating these processes and the sensitivity of the model's performance to various parameterizations of unresolved physics. The WRF-Chem model is first upgraded by implementing a radioactive decay term into the advection-diffusion solver and adding three parameterizations for dry deposition and two parameterizations for wet deposition. Different microphysics and horizontal turbulent diffusion schemes are then tested for their ability to reproduce observed meteorological conditions. Subsequently, the influence of emission characteristics (including the emission rate, the gas partitioning of 131 I and the size distribution of 137 Cs) on the simulated transport and deposition is examined. The results show that the model can predict the wind fields and rainfall realistically and that the ground deposition of the radionuclides can also be captured reasonably well. The modeled precipitation is largely influenced by the microphysics schemes, while the influence of the horizontal diffusion schemes on the wind fields is subtle. However, the ground deposition of radionuclides is sensitive to both horizontal diffusion schemes and microphysical schemes. Wet deposition dominated over dry deposition at most of the observation stations, but not at all locations in the simulated domain. To assess the sensitivity of the total daily deposition to all of the model physics and inputs, the averaged absolute value of the difference (AAD) is proposed. Based on AAD, the total deposition is mainly influenced by the emission rate for both 131 I and 137 Cs; while it is not sensitive to the dry deposition parameterizations since the dry deposition is just a minor fraction of the total deposition. Moreover, for 131 I, the deposition is moderately sensitive (AAD between 10 and 40 % between different runs) to the microphysics schemes, the horizontal diffusion schemes, gas-partitioning and wet deposition parameterizations. For 137 Cs, the deposition is very sensitive (AAD exceeding 40 % between different runs) to the microphysics schemes and wet deposition parameterizations, but moderately sensitive to the horizontal diffusion schemes and the size distribution.

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Section: The Influence Of Emission Rates and Characteristicssupporting

confidence: 88%

Modeling and sensitivity analysis of transport and deposition of radionuclides from the Fukushima Dai-ichi accident

Huang

et al. 2014

Atmos. Chem. Phys.

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“…Exposures in long-term individual doses were modeled through cloud shine and ground shine pathways, while the calculations for the long-term doses were modeled through ground shine pathway (via the food chain). The potential exposure situation for a nuclear reactor facility was not a typical accident affected by the fuel in the core which releases radioactive material to the environment [13]. Thus, the effects to the public and the types of consequences may be different.…”

Section: Fission Product Dispersion and Radiation Dose In The Environmentioning

confidence: 99%

A Backward Method to Estimate the Dai-ichi Reactor Core Damage Using Radiation Exposure in the Environment

2016

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The Fukushima accident resulted in the melting of the reactor core due to loss of supply of coolant when the reactor stopped from operating conditions. The earthquake and tsunami caused loss of electricity due to the flooding that occurred in the reactor. The absence of the coolant supply after reactor shutdown resulted in heat accumulation, causing the temperature of the fuel to rise beyond its melting point. In the early stages of the accident, operator could not determine the severity of the accident and the percentage of the reactor core damaged. The available data was based on the radiation exposure in the environment that was reported by the authorities. The aim of this paper is to determine the severity of the conditions in the reactor core based on the radiation doses measured in the environment. The method is performed by backward counting based on the measuring radiation exposure and radionuclides releases source term. The calculation was performed by using the PC-COSYMA code. The results showed that the core damage fraction at Dai-ichi Unit 1 was 70%, and the resulting individual effective dose in the exclusion area is 401 mSv, while the core damage fraction at Unit 2 was 30%, and the resulting individual effective dose was 99.1 mSv, while for Unit 3, the core damage fraction was 25% for an individual effective dose of 92.2 mSv. The differences between the results of the calculation for estimation of core damage proposed in this paper with the previously reported results is probably caused by the applied model for assessment, differences in postulations and assumptions, and the incompleteness of the input data. This difference could be reduced by performing calculations and simulations for more varied assumptions and postulations.

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“…3 Comparison with calculated committed equivalent doses of Bronchial (BB) and a unity region of Alveolar-Interstitial (AI) and Bronchiolar (bb), associated with beta particles of Cs-134 and Cs-137, by PHITS and general standard method Cs-134:ˇ-particle (Sv/particles) Cs-137:ˇ-particle (Sv/particles) Type-F Type-M Type-S Type-F Type-M Type-S PHITS BB 1.62220E-11 2.18575E-08 4.03264E-08 1.71321E-11 1.06724E-06 7.89293E-06 AI+bb 7.15408E-12 6.32775E-08 2.40142E-07 8.40650E-12 8.73540E-08 6.46041E-07 General BB 4.21726E-10 4.60743E-07 6.01231E-07 5.86399E-10 6.60018E-07 9.03500E-07 standard method AI+bb 1.94080E-11 7.51489E-08 2.45339E-07 2.66325E-11 1.02437E-07 6.11277E-07 doses attributed to the gamma rays of Cs-134 and Cs-137 on the PHITS calculation results are entirely consistent with those of the general standard method at both the respiratory tracts of BB and AI+bb.…”

Section: Committed Equivalent Doses In Comparison Withmentioning

confidence: 99%

“…A few years after this accident, we had slightly understood some findings regarding all the radioactivity for released radioactive cesium isotopes of Cs-134 and Cs-137 into the environment and the exact migrations for the radioactive plumes including those radioactive materials upon atmospheric conditions [1][2][3][4][5]. Four years elapsed and it has now become clear that the radioactive materials have chemical and physical properties concerning chemical forms, particle sizes, shape, phases (gas or aerosol), water solubility, and residence time [6][7][8][9][10].…”

Section: Introductionmentioning

confidence: 99%

Monte Carlo Evaluation of Internal Dose and Distribution Imaging Due to Insoluble Radioactive Cs-Bearing Particles of Water Deposited Inside Lungs via Pulmonary Inhalation Using PHITS Code Combined with Voxel Phantom Data

Sakama

Takeda

Matsumoto

et al. 2016

Radiological Issues for Fukushima’s Revitalized Future

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The role of this study in terms of health physics and radiation protection has been implemented to evaluate the internal dose (relative to the committed equivalent dose) and the dose distribution imaging due to gamma rays (photons) and beta particles emitted from the radioactive Cs-bearing particles in atmospheric aerosol dusts deposited in the lungs via pulmonary inhalation. The PHITS code combined with voxel phantom data (DICOM formats) of human lungs was used. We have dealt with the insoluble radioactive Cs-bearing particles of water (about 2.6 m diameter) migrated onto any of six regions, ET1, ET2, BB, AI-bb, LNET, and LNTH, in a respiratory system until dropping into blood vessels. Source parameters were those of an adult male breathing a typical air volume outdoors; in the simulated atmosphere (such as systematically setting up a field) those particles would be released on

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Atmospheric radionuclides transported to Fukuoka, Japan remote from the Fukushima Dai-ichi nuclear power complex following the nuclear accident

Cited by 64 publications

References 5 publications

Modeling and sensitivity analysis of transport and deposition of radionuclides from the Fukushima Dai-ichi accident

Modeling and sensitivity analysis of transport and deposition of radionuclides from the Fukushima Dai-ichi accident

A Backward Method to Estimate the Dai-ichi Reactor Core Damage Using Radiation Exposure in the Environment

Monte Carlo Evaluation of Internal Dose and Distribution Imaging Due to Insoluble Radioactive Cs-Bearing Particles of Water Deposited Inside Lungs via Pulmonary Inhalation Using PHITS Code Combined with Voxel Phantom Data

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