131I age-dependent inhalation dose in Southern Poland from Fukushima accident

A general method for calculating doses absorbed from isotopes released in nuclear accidents is presented. As an example, this method was used to calculate doses for inhabitants of Southern Poland due to inhalation of 131I released due to the Fukushima nuclear plant accident. 131I activity measurements in the air of that region provided the basis for the study. The proposed model is based on a complex biokinetic model for iodine merging the Leggett model developed in 2010 with the human respiratory tract and gastrointestinal tract models recommended by the International Commission on Radiological Protection (ICRP). This model is described here, and it is demonstrated that resulting dose estimates are consistent with those obtained using the ICRP methodology. Using the developed model, total doses were calculated for six age groups of both genders, for gaseous and aerosol fractions alike. The committed effective dose, H50, for an adult man reached 16 nSv, which is lower than 0.001% of the background dose. The dose for the thyroid of an adult reached 0.33 μSv, which corresponds to circa 0.0007% of the dose to the population of Southern Poland after the Chernobyl nuclear plant accident.


Introduction
On 11 March 2011, a 9.0 magnitude earthquake took place off the Pacific coast of Tōhoku, Japan. Subsequent 13-mhigh tsunami waves damaged the cooling system (Tanaka 2012;Lipscy et al. 2013) at the Fukushima Daiichi Nuclear Power Plant. As a consequence, a radioactive emission occurred on the 12th of March containing mainly 131 I, 133 I, 134 Cs, 137 Cs, and other volatile species, which were transported in the atmosphere towards the north-western direction (Tanaka 2012). The accident was classified in the International Nuclear Event Scale as a level 7 accident. Previously, only the Chernobyl accident was rated at this level. During this accident, 1.8 9 10 18 Bq of 131 I were released into the environment (UNSCEAR 2000), whereas during the Fukushima accident 0.12 9 10 18 Bq of 131 I were released (USCEAR 2014).
The first traces from the Fukushima radioactive plume in Europe were detected in Reykjavik, Iceland, on the 20th of March (Bossew et al. 2012). On the morning of the 24th of March, the Laboratory of Radioactivity Analyses in Krakow, Poland, initiated an emergency mode for observations of radionuclides in the atmosphere; both aerosols and a gaseous fraction of 131 I were considered (Mietelski et al. 2014). 131 I is a beta-emitting radioisotope with a physical halflife of 8.021 days. The mean energy of electrons released during 131 I nuclear decay is 606 keV. 131 I is a nuclear fission product and as such it is commonly present in radioactive releases due to nuclear power plant failures. Furthermore, it is believed to contribute significantly to health hazards related to radioactive fallout. Being an iodine radioisotope, 131 I is easily and preferentially concentrated in the human thyroid; note that the thyroid accumulates 30% of the total intake of iodine (Johansson & K. Brudecki kamil.brudecki@ifj.edu.pl et al. 2003) which is necessary for the proper functioning of the thyroid. The International Commission on Radiological Protection (ICRP) developed a general methodology to calculate dose conversion factors and dose coefficients. This methodology was applied in the present study to estimate doses received by an average Polish citizen due to inhalation of 131 I from the Fukushima fallout. More specifically, to quantify the incorporation of aerosol and gaseous fractions of radioiodine in the human organism, the age-dependent systemic biokinetic model proposed by Leggett (2010) was combined with the ICRP human respiratory tract model (HRTM) (ICRP 1994) and the ICRP gastrointestinal tract model (GITM) (ICRP 1979).

Materials and method
A general method of dose calculation is presented in this section. First, 131 I concentration in the air was measured. Second, gaseous and aerosol 131 I fractions deposited in various lung regions were estimated. Next, a complete biokinetic model for modelling the translocation of the deposited radionuclide within a human body following inhalation was constructed. Finally, ICRP recommendations were applied to evaluate equivalent and effective doses.

I measurements
Iodine from the air was collected at the Institute of Nuclear Physics in Krakow, Poland, by a combined aerosol sampler MASS-500/gas sampler, operated at a flow rate of 250 m 3 h -1 (Mietelski et al. 2014;Masson et al. 2011). The sorbent type for the aerosol fraction was a Petryanov filter FPP-15-1.5 (poly(vinyl chloride)) which has good aerosol-collecting properties: The aerosol collection efficiency of the Petryanov filter for aerosols with diameters 0.3 lm and for a linear velocity of the air passing through the filter of about 0.36 m s -1 reached 96.7% (Lipiński et al. 2013). For collection of the gas fraction, a sorbent of granular activated carbon impregnated with KI (IBJ-6, mesh size 2 mm, produced by Gryskand, Hajnówka, Poland) was used. The average efficiency of gaseous iodine adsorption reached (67 ± 11)% (Table 1). The use of activated carbon impregnated with KI allowed collection of both organic and inorganic iodine (Wilhelm 1982;Wangchang et al. 1993).
Between the 21st of March and 12th of April, the sorbents were changed every day. The filters and the granulated carbon from the gas cassettes were analysed by means of a lowbackground gamma spectrometer with HPGe detectors. Prior to measurements, the filters were compressed into pellets of 5 cm diameter and about 4 mm height. The carbon from each cassette was transferred into 0.5-L plastic Marinelli beakers and measured. Isotopes such as 131 I, 132 I, 129m Te, 132 Te, 134 Cs, 136 Cs, and 137 Cs were detected in the filters. The maximum activity for aerosols was equal to (5.73 ± 0.35), (0.461 ± 0.041) and (0.436 ± 0.038) mBq m -3 for 131 I, 134 Cs, and 137 Cs, respectively, as observed on 29 March 2011. The detailed results are presented in Table 1 (Masson et al. 2011(Masson et al. , 2013Mietelski et al. 2014).

Deposition in the human respiratory tract
In the present study, the HRTM published in ICRP (1994) was used. In this approach, the human respiratory tract is divided into four anatomical regions, namely the extrathoracic region ET (consists of two parts: ET1 comprising interior nose and ET2 comprising posterior nasal passages, larynx, pharynx, and mouth), the bronchial region BB, the bronchiolar region bb, and the alveolarinterstitial region AI. The deposition of 131 I aerosol fractions was calculated for five activity median aerodynamic diameters (AMADs) of the attached aerosols that were observed in Southern Poland after the Fukushima accident, i.e. 0.35, 0.36, 0.38, 0.47, and 0.53 lm (Masson et al. 2013). The deposition was calculated by a logarithmic interpolation of the deposition fraction values published by the ICRP in the HRTM using a six-term exponential function. Exemplary depositions for an adult male and a 0.35 lm aerosol AMAD are presented in Table 2.
In the gas fraction, iodine in elemental and organic form is absorbed in the respiratory tract in various proportions. However, when it is not possible to distinguish them (as was the case in the present study), the ICRP recommends adoption of the deposition rate for elemental iodine; accordingly, 100% deposition in the respiratory tract for elemental iodine was assumed in the present study with the respective distribution of 10% ET1, 40% ET2, and 50% BB (ICRP 1995). This simplification resulted in an overestimation of the calculated doses. In general, the fractional deposition in the respiratory tract regions was estimated for six age groups, both genders and four exercise levels, notably sitting, sleeping, light exercise, and heavy exercise. The typical time-budget distribution of different activities for 3-month infants was assumed as 71-29% for sleeping and light exercises, respectively, while the typical time budget for an adult male was assumed to be 33, 25, 41, and 1% for sleeping, sitting, light exercise, and heavy exercise, respectively. The average breathing rate for an adult man is 22.2 m 3 day -1 , while the breathing rates for the other age groups are 2.86 m 3 day -1 for 3-month-old infants, 5.16 m 3 day -1 for 1-year-olds, 8.72 m 3 day -1 for 5-yearolds, 15.3 m 3 day -1 for 10-year-olds, 20.1 m 3 day -1 for 15-year-old males, 18 m 3 day -1 for 15-year-old females, and 17.8 m 3 day -1 for adult females. These breathing rates and other detailed ventilation parameters used in the model were taken from ICRP (2002) and are presented in Table 3.

Biokinetic models
To describe the behaviour of the inhaled 131 I in the human body and iodine accumulation in organs and tissues, the systemic biokinetic compartment model by Leggett (2010), the HRTM, and GITM were combined together into a onecompartment model. Such a solution has already been successfully applied for calculation of doses due to inhalation of indoor short-lived radon (both 222 Rn and 220 Rn) progenies for members of the public (Lie et al. 2008;Brudecki et al. 2014). The model is based on three subsystems for extrathyroidal inorganic iodine, thyroidal iodine, and extrathyroidal organic iodine. The model flow chart is presented in Fig. 1.
The biokinetic behaviour of the inhaled iodine in the respiratory tract and other organs can be described by a system of first-order linear differential equations. The iodine activity in tissue and organs at any time after intake can be calculated numerically by solving these equations. The time-integrated iodine activityÃ in the thyroid and in other organs was calculated hereby integrating the activity in the organ up to the age of 70 years for children and over the 50-year commitment period following the intake for adults. The system of first-order differential equations was solved using the commercially available software SAAM II (Epsilon Group, VA, USA) (Barrett et al. 1998).  (Leggett 2010;ICRP 1979ICRP , 1994 Equivalent dose and effective dose The general methodology for dose calculation developed by the ICRP was also applied in the present study. Equivalent thyroid doses were calculated based on the time-integrated activityÃ and radiation-weighted S W factors. In general, the equivalent dose H(r T , T D ) in any target organ r T at age T integrated over the dose integration period T D is given by Eq.
(1) (Bolch et al. 2009) where A(r S , t) is the time-dependent activity in the source region r S at time t; S W (r T / r S , t) is the radiation-weighted S factor, which depends on the radiation-weighting factor w R and energy E R of radiation R. S is calculated as given in Eq. (2) For a given age group, S W (r T / r S , t) is constant over the time interval T D age andÃ may be calculated as (Eq. 3) Consistently, the equivalent dose in a specific age group is (Eq. 4) In the present investigation, the effective doses for adults and 15-year-olds are estimated based on the adequate female and male equivalent doses and ICRP 103 (2007) recommendations. For the other age groups, i.e. infants, 1-, 5-, and 10-yearolds, the effective doses are calculated without taking into consideration gender differences, according to ICRP (1991). In practice, the S W value was calculated using the SEECAL program (Oak Ridge National Laboratory, Oak Ridge, TN, USA). The time-dependent activity, A(r S , t), was obtained by modelling for separate anatomical regions (Fig. 1) and the w T values used for calculations were taken from ICRP 60 (1991). Tissue-weighting factors, w T , were taken from ICRP 60 (1991) instead of ICRP 103 (2007), to allow validation of the model and comparison of the results with ICRP dose coefficients (ICRP 1995). Other 4 to other 3 0.62 Other 4 to blood 1 0.14 Blood 2 to kidneys 2 3.6 Kidneys 2 to blood 2 21 Kidneys 2 to blood 1 0.14 Blood 2 to liver 2 21 Liver 2 to blood 2 21 Liver 2 to blood 1 0.14 Stomach contents to SI contents 20.57 SI contents to blood 1 594

Validation of the method
To validate the methods applied, the estimated doses were compared with those obtained using ICRP dose coefficients (ICRP 1995) for the gaseous fraction of 131 I. Results are presented in Table 5. The biggest differences are observed for infants (36%) and 1-year-old children (16%). In the other age groups, differences are around 10%. Such discrepancies occurred owing to the fact that Leggett's model is more accurate than the current ICRP model proposed by Riggs (1952).

Results and discussion
In the present study, doses to South Poland residents due to inhalation of 131 I were calculated, based on the 131 I measured in air in South Poland after the nuclear power plant accident in Fukushima. The resulting effective doses and equivalent doses for the thyroid obtained for six age groups, namely 3-month infants, 1-, 5-, 10-, 15-year-old, and adults, as well as both genders for adults and 15-yearold teenagers, are shown in Tables 6 and 7. With regard to the aerosol fraction, as expected the highest equivalent dose was achieved for the thyroid. The estimated doses for this organ were equal to 1.0 9 10 -7 , 1.9 9 10 -7 , 1.5 9 10 -7 , 1.0 9 10 -7 , 7.7 9 10 -8 , 6.9 9 10 -8 , 5.7 9 10 -8 , and 4.6 9 10 -8 Sv for infants, 1-, 5-, 10-year-old children, 15-year-old males, 15-year-old females, male and female adults, respectively. The equivalent doses received by other body parts usually did not exceed hundreds of pSv. The largest effective dose (9.6 nSv) was calculated for a 1-year-old child, while for older ages, lower values were calculated (Fig. 2).
It should be noted that the doses calculated due to the gaseous fraction are overestimated. As already mentioned above, elemental and organic iodine in the gas fraction are absorbed in the respiratory tract in various proportions: 100% of elemental iodine is absorbed while only 70% of organic iodine is absorbed. For an adult male, the difference between the effective dose due to inhalation of elemental iodine and organic iodine is 25% (ICRP 1995). Because we were not able to distinguish between elemental and organic iodine in the gas fraction, it was assumed that all was elemental iodine and a 100% absorption was used, consistent with the recommendations of the ICRP. This led to a conservative dose assessment. Considering that organic iodine constitutes up to 86% of the total gaseous fraction (Noguchi and Murata 1988), doses estimated in the Eff dose (present method) 1.9 9 10 -8 2.8 9 10 -8 2.6 9 10 -8 2.3 9 10 -8 1.9 9 10 -8 1.7 9 10 -8 1.4 9 10 -8 1.1 9 10 -8 Eff dose (ICRP 71, dose coefficients) 1.4 9 10 -8 2.4 9 10 -8 2.3 9 10 -8 2.1 9 10 -8 1.8 9 10 -8 1.6 9 10 -8 1.3 9 10 -8 1.0 9 10 -8 Difference 36% 16% 13% 10% 6% 6% 8% 10% In general, the effective doses from iodine in the gaseous fraction are higher than those from iodine attached to aerosols: The gas-to-aerosol effective dose ratios are equal to 3.6, 2.9, 3.5, 4.4, 5.0, 4.8, and 4.7 for infant, 1-, 5-, 10-year-old children, 15-year-old boys and girls, adult men and women, respectively. Such differences in dose between the gaseous and aerosol fractions are caused by differences in deposition in the respiratory system. Accumulation of volatile (gaseous) iodine is between 70% and 100%, while the maximum deposition of particulate iodine (iodine attached to aerosols) observed in Southern Poland is on the 43% level for 0.53lm-diameter particles for a 1-year-old child.
The sum of the thyroid doses induced by the iodine attached to aerosols or present in the gaseous fraction (and assuming 100% absorption) is equal to 0.48, 0.74, 0.66, 0.55, 0.46, 0.41, 0.33, and 0.26 lSv for infants, 1-, 5-, 10-year-old children, 15-year-old boys and girls, adult men and women, respectively. Compared with inhalation doses of 131 I by Polish residents after the Chernobyl nuclear accident, when equivalent doses for the thyroid reached 178, 120, and 45 mSv for 5-year-old children, 10-year-old children, and adults, respectively (Pietrzak-Flis et al. 2003), the values due to the Fukushima accident are practically negligible. Similarly, the effective doses estimated here for Southern Poland are significantly lower than those estimated for the inhabitants of Fukushima and Japan: Depending on the residence place, thyroid doses for Japanese people were estimated as (0.1 7 4.3), (0.1 7 5.9), and (0.2 7 7.5) mSv for adults, 10-year-old children, and 1-year-old children, respectively (UNSCEAR 2014). The doses found in the present study are consistent with those estimated by WHO (2012), who estimated for areas outside Japan effective doses of less than 0.01 mSv.
In the present paper, dose evaluation was performed for adults and 15-year-old teenagers for male and female separately, although ICRP recommends (ICRP 103) to calculate doses for adults as the average of the two genders (see Eq. 7). Differences found between these two approaches are presented in Table 8; the biggest discrepancy reached 13%.

Conclusions
In the present study, doses due to 131 I originating from the Fukushima Daiichi Nuclear Power Plant accident inhaled by residents of Southern Poland were estimated. The doses were calculated for both 131 I in aerosol and 131 I in gaseous fractions. The dose values due to volatile iodine in the gaseous fraction were found to be higher than those estimated for particulate iodine (i.e. iodine attached to aerosols); the difference can be attributed to differences in the deposition of the discussed fractions in the human respiratory tract. The effective committed dose, H 50 , for a male adult reached 16 nSv, which is less than 0.001% of the local background dose. The thyroid dose for an adult reached 0.33 lSv, which is less than 0.0007% of the dose that had been estimated for residents of Southern Poland, due to the Chernobyl accident. The doses to the inhabitants of Southern Poland did by no means represent any health hazard. Moreover, 131 I air concentrations were comparable in most European countries (especially Central and Eastern parts of Europe). Therefore, the presented dose calculations are representative not only for Poles but also for most Europeans.