Calculation of age-dependent effective doses for external exposure using the MCNP code

Kerntechnik ◽  
2013 ◽  
Vol 78 (3) ◽  
pp. 209-213 ◽  
Author(s):  
Tran Van Hung
Keyword(s):  
External Exposure ◽  
Mcnp Code ◽  
Age Dependent ◽  
Effective Doses

scholarly journals Effective doses for external exposure from the photon radiation field of soil contamination

2019 ◽  
Vol 2 (1) ◽  
pp. 84-90
Author(s):  
Tran Van Hung
Keyword(s):  
Soil Contamination ◽  
Effective Dose ◽  
Radiation Field ◽  
Photon Radiation ◽  
External Exposure ◽  
Mcnp Code ◽  
Photon Sources ◽  
Effective Doses ◽  
Dose Coefficients

Organ and effective doses of adult for external exposure to photons uniformly distributed in soil were calculated using a MIRD-5 type phantom and MCNP code. The calculations were performed for mono-energic photon sources with source energies from 0.01 MeV to 5 MeV. The effective dose coefficients in this calculation using MCNP code were compared to the calculated results in report of Keith F. Eckerman và Jeffrey C. Ryman.

EVALUATION OF DOSE IN SLEEP BY MATTRESS CONTAINING MONAZITE

2019 ◽  
Vol 187 (3) ◽  
pp. 286-299
Author(s):  
Bong-Gi Kim ◽  
Kyu-Hwan Jeong ◽  
Hyeong-Ki Shin
Keyword(s):  
Age Groups ◽  
Decay Chain ◽  
Dose Assessment ◽  
Internal Exposure ◽  
External Exposure ◽  
Radon Progeny ◽  
Conversion Factors ◽  
Assessment Program ◽  
Radioactive Concentration ◽  
Effective Doses

Abstract Some companies in Korea have sold beds which contain a processed product containing monazite powder. Consumers may receive external exposure by radiation emitted by progeny radionuclides in uranium and thorium, and internal exposure through the breathing of radon progeny radionuclides produced in the decay chain. Thus, in this study, age specific dose conversion factors (mSv y−1 Bq−1) by external exposure and dose conversion factors by internal exposure (mSv y−1 per Bq m−3) were derived. Besides, a dose assessment program were developed to calculate dose by taking into account real conditions. And the age specific dose was evaluated using the radioactive concentration measured by the NSSC. As a results, external exposure was assessed to get effective doses in the range of 0.00086 to 0.0015 mSv y−1 by external exposure and a committed effective doses in the range of 1.3 to 12.26 mSv y−1 by internal exposure for all age groups.

scholarly journals Dosimetry of external population exposure: a comparison of the Chernobyl and Fukushima accidents

2020 ◽  
Vol 13 (1) ◽  
pp. 27-37 ◽  
Author(s):  
V. Yu. Golikov
Keyword(s):  
Gamma Radiation ◽  
Radioactive Fallout ◽  
Population Exposure ◽  
External Exposure ◽  
Dose Rates ◽  
Accident Data ◽  
Accurate Comparison ◽  
Effective Doses ◽  
The Moment ◽  
External Population

The paper is devoted to comparing the models and the doses of the population external exposure from radioactive fallout after the accident at the Chernobyl and Fukushima-1 NPPs estimated with their help. In the case of the Fukushima-1 accident, the model proposed by the UNSCEAR was used. Both the values of the doses of gamma radiation in the environment and the values of the effective doses of external exposure of comparable population groups normalized to the same surface activity of radionuclides were close for both accidents. The reasons for this are both the similarity of the isotopic compositions of the radioactive fallout and the fact that the “Japanese” model of external exposure was based on the “Chernobyl” model up to using the same numerical values for some parameters, due to the lack of specific Japanese post-accident data for the moment of the first dose estimates for the inhabitants of Japan. For a more accurate comparison of the external exposure of residents after two accidents it is necessary to verify the values of the parameters of the Japanese model using the results of measurements of gamma radiation dose rates in the environment and individual external doses of the residents after the accident at the Fukushima-1 NPP.

scholarly journals Age-dependent annual effective dose estimations of 226Ra, 232Th, 40K and 222Rn from drinking water in Baling, Malaysia

2017 ◽  
Vol 18 (1) ◽  
pp. 32-39 ◽  
Author(s):  
Nisar Ahmad ◽  
Jalil ur Rehman ◽  
Muhammad Rafique ◽  
Tabassum Nasir
Keyword(s):  
Drinking Water ◽  
Natural Radioactivity ◽  
Annual Effective Dose ◽  
World Health ◽  
Hpge Detectors ◽  
The World ◽  
Age Dependent ◽  
Effective Doses ◽  
Health Organization ◽  
Drinking Water Samples

Abstract Natural radioactivity and radon concentration were studied in drinking water samples from Baling area, Kedah, Malaysia, using HPGe and RAD-7 detectors, respectively. Average concentrations obtained for 226Ra, 232Th, 40K and 222Rn were 44.2 ± 3.9, 38.1 ± 5.0, 140.9 ± 10.6 mBq l−1 and 5.7 ± 0.68 Bq l−1, respectively. Cumulative annual effective doses due to ingestion of 226Ra, 232Th, 40K and 222Rn for infants, children and adults were estimated to be 13.77, 2.857 and 2.581 μSv y−1, respectively. Average annual effective doses due to inhalation of radon released in the air during consumption and ingestion of drinking water were separately estimated to be 15.2 and 1.2 μSv y−1, respectively. A positive correlation (R2 = 0.87) was observed between 222Rn and 226Ra determined by RAD-7 and HPGe detectors, respectively. In this study, the estimated annual effective doses due to ingestion of 226Ra, 232Th, 40K and 222Rn for infants, children and adults were found to be below the World Health Organization (WHO) recommended limits of 0.1 mSv y−1.

Age-dependent dose conversion coefficients for external exposure to radioactive cesium in soil

2015 ◽  
Vol 53 (1) ◽  
pp. 69-81 ◽  
Author(s):  
Daiki Satoh ◽  
Takuya Furuta ◽  
Fumiaki Takahashi ◽  
Akira Endo ◽  
Choonsik Lee ◽  
...  
Keyword(s):  
Radioactive Cesium ◽  
External Exposure ◽  
Age Dependent ◽  
Conversion Coefficients

Evaluation of External Exposure During Building and Operation of Concrete Bridges Constructions That Reuse the Conditionally Released Steels

2011 ◽  
Author(s):  
Michal Panik ◽  
Vladimir Necas
Keyword(s):  
Effective Dose ◽  
Computer Code ◽  
Concrete Bridges ◽  
Internal Exposure ◽  
Critical Groups ◽  
External Exposure ◽  
Calculation Results ◽  
Effective Doses ◽  
The Subject ◽  
The Individual

This paper presents ongoing results of the project presented at ICEM’10 [1] related to the topics of reusing the conditionally released materials from decommissioning. The subject of the reuse of conditionally released materials in this case is modeling of bridge constructions which reuse the conditionally released steel in the form of reinforcement bars for the concrete bridges. A general approach for the project was presented at ICEM’10. The activities of the project continue in evaluating the individual effective doses from the external exposure based on reused conditionally released steels separately for public and for professionals (the internal exposure will be evaluated in next stages of the project). Evaluated scenarios are related to critical groups of professionals constructing the bridges (worker’s scenarios). The computer code VISIPLAN 3D ALARA 4.0 planning tool was used for the calculation of the individual effective dose for professionals. Various limits of the annual individual effective dose are used for the evaluation of calculation results. The aim of the ongoing modeling is to develop a set of data of maximal radioactivity concentration for individual radionuclides in the conditionally released steel used in the bridges model constructions in order not to exceed the limits for the individual effective dose.

scholarly journals Verification of model of external population exposure in Japan after the accident at the “Fukushima-1” NPP

2020 ◽  
Vol 13 (2) ◽  
pp. 31-40
Author(s):  
V. Yu. Golikov
Keyword(s):  
Japanese Population ◽  
Adult Population ◽  
Radioactive Fallout ◽  
Exposure Model ◽  
Geometric Standard Deviation ◽  
External Exposure ◽  
Stochastic Version ◽  
Model Average ◽  
Effective Doses ◽  
Time Periods

The paper is devoted to the verification of the model of external exposure of the Japanese population from radioactive fallout after the accident at the “Fukushima-1” NPP published by UNSCEAR in 2014. The paper presents specific quantitative examples of the verification of the external exposure model of the Japanese population after the accident at the “Fukushima-1” nuclear power plant. As an independent set of experimental data for validation of the model estimates we used the results of measurements of individual doses of external radiation in various population groups in Japan in different time periods after fallout. In the case of the deterministic version of the model, it was shown that for the adult population working mainly outdoors (construction workers and agricultural workers), the differences between the average values of effective doses predicted by the model and those obtained on the basis of measurements were less than 20%. For office workers, this difference was larger, from 34 to 70%, depending on whether their office buildings are wooden or multi-story concrete. For children under 16 years of age and a longer period of time for measuring individual doses after radioactive fallout (2011 – 2015), the differences between the model average effective doses and those estimated on the basis of measurements ranged from –24% to +32% in different time periods. In the case of the stochastic version of the model, it was shown that for the three considered groups of the adult population the distributions of individual doses obey the logarithmically normal law and the differences in the values of the calculated and experimental geometric means ranged from –7% to +20%. The geometric standard deviation values obtained in the simulation were always slightly higher than the similar values estimated based on the measurement results.

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