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Reduction of births in Italy after the Chernobyl accident.

After the Chernobyl accident serious concern spread throughout Italy about the possible effects of the consequent exposure to radioactivity on fetuses. A reduction of births in the first three months of 1987, and particularly in February (7.2% reduction in the birth rate), was observed throughout Italy. In April-June 1987 a 4.8% increase in the number of births was observed. The magnitude of both phenomena varied in different areas of the country. The total number of births in the first six months of 1987 was very similar to the expected (264,241 versus 263,659). Induced abortions increased in Lombardia (northern Italy) in June (+1.6%) and July of 1986 (+3.4%) and in Campania (southern Italy) in June (+12.7%) and August (+4.3%). No increase in legal abortions was detected in Lazio (central Italy). Italian data suggest a voluntary decrease in the number of planned pregnancies and the termination of some of them in the first weeks after the accident as a consequence of postdisaster stress.

Abortion, Induced↗

Evaluation of electret ion chamber for tritium measurement.

Commercial E-PERM radon-in-air monitors modified to detect tritium in air have been evaluated. Each monitor consists of a small ion chamber with access holes around the sides to allow the air to diffuse into the chamber, and an electret at the bottom to establish an electrostatic potential. Radioactive gas inside the volume generates ions, which are collected by the electret. The reduction of charge (and subsequent reduction in surface potential) on the electret is a measure of the integrated exposure. Two types of detectors, a 50 cm3 model and a 200 cm3 model, were tested for tritium-in-air concentrations from 1 to 60 MBq m-3, and gamma-absorbed dose rates from background levels to 50 microGy h-1. The HTO-in-air response of the modified E-PERM monitors was 3.3 +/- 0.3 V MBq-1 m3 h-1 for the 200 cm3 and 0.8 +/- 0.2 V MBq-1 m3 h-1 for the 50 cm3 monitor. For external gamma radiation (226Ra), the 200 cm3 chamber gave a response of 7.6 +/- 1.8 V microGy-1 and the 20 cm3 chamber 1.8 +/- 0.5 V microGy-1. The detection limit was about 3.6 and 15.2 MBq m-3 h for the 200 and 50 cm3 chambers, respectively. The accuracy and limit of detection of the electret detectors are limited by the accuracy in measuring the surface potential on the electret.

Air Pollutants, Radioactive↗

Predicted responses for a particulate detection system in a continuous stack monitor.

Predicted counting rate responses were developed for a particulate detection system that is used for continuous monitoring for the presence of radioactive particulates in the effluent air from a research reactor. The particulate detection system consists of a moving filter paper assembly, a plastic scintillation detector, and a rate meter output, and is part of a comprehensive stack monitoring system. A predicted response was derived for the case of a steady-state activity distribution across the surface of the moving filter paper that is in proximity to the detector and was determined to be 1.59 x 10(7) cpm per unit airborne concentration of 138Cs (expressed in units of Bq cm(-3)), where 138Cs was used as an indicator for a hypothetical fission product release. The corresponding response model provided by the manufacturer was found to underestimate airborne activity concentrations by about an order of magnitude. A predicted response also was derived for the case of a rapid change in airborne activity concentration, which was formulated based on the kinetics of the rate meter circuit and was used to establish alarm settings and detection limits for the particulate detection system.

Air Pollutants, Radioactive↗

The deposition and translocation of methyl iodide by crops.

Organic forms of radioactive iodine are released during routine and accidental releases from the nuclear industry. Methyl iodide is often the predominant species in these releases. This paper describes the results of a study to determine the deposition, allocation, and loss of radioiodine after crops of bean, carrot, and cabbage were exposed to CH3 125I. The deposition velocity ranged from 0.14-7.10 x 10(-4) cm s(-1), which is in line with previous studies. Translocation of radioiodine away from the leaves to other crop components was observed post exposure. The partition of radioiodine was to those crop components growing most actively at the time of exposure. This finding contradicts some previous studies and will have implications for dose assessments. Losses of radioiodine were only observed as a consequence of leaf fall. The consequences of these findings for the modeling the movement of radioiodine in crops following the deposition of methyl iodide are discussed.

Air Pollutants, Radioactive↗

Accumulation of 210Pb, 226Ra and radioactive cesium by fungi.

Fungi sampled in three areas in France were analyzed by gamma-spectrometry for their concentrations of 134Cs, 137Cs, 210Pb and 226Ra. In most of the samples radioactive cesium was detected with a maximum of 2860 Bq kg-1 (dry wt.). Activity concentrations of 210Pb were in the range < 1.76-36.5 Bq kg-1 (dry wt.). Activity concentrations of 226Ra were consistently lower, often by one order of magnitude. Models are developed to estimate the contributions of atmospheric 210Pb deposited onto the fruit bodies to the measured 210Pb concentrations and of the uptake of 222Rn soluted in soil pore water which subsequently decays into 210Pb. It is shown that both pathways are of only minor importance. Comparison with the soil-mushroom concentration ratios of stable lead, which were determined for some of the samples, confirmed that 210Pb in mushrooms mainly originates from direct uptake of 210Pb present in the soil. Despite of the high concentrations of 137Cs detected in most of the mushrooms, radiation doses to individuals due to mushroom consumption are dominated by 210Pb for the majority of the edible mushrooms sampled.

Agaricales↗

Chernobyl source term, atmospheric dispersion, and dose estimation.

The Chernobyl source term available for long-range transport was estimated by integration of radiological measurements with atmospheric dispersion modeling and by reactor core radionuclide inventory estimation in conjunction with WASH-1400 release fractions associated with specific chemical groups. These analyses indicated that essentially all of the noble gases, 60% of the radioiodines, 40% of the radiocesium, 10% of the tellurium, and about 1% or less of the more refractory elements were released. Atmospheric dispersion modeling of the radioactive cloud over the Northern Hemisphere revealed that the cloud became segmented during the first day, with the lower section heading toward Scandinavia and the upper part heading in a southeasterly direction with subsequent transport across Asia to Japan, the North Pacific, and the west coast of North America. The inhalation doses due to direct cloud exposure were estimated to exceed 10 mGy near the Chernobyl area, to range between 0.1 and 0.001 mGy within most of Europe, and to be generally less than 0.00001 mGy within the United States. The Chernobyl source term was several orders of magnitude greater than those associated with the Windscale and TMI reactor accidents. However, the 137Cs from the Chernobyl event is about 6% of that released by the U.S. and U.S.S.R. atmospheric nuclear weapon tests, while the 131I and 90Sr released by the Chernobyl accident was only about 0.1% of that released by the weapon tests.

Accidents↗

Evaluation of sampling locations for two radionuclide air-sampling systems based on the requirements of ANSI/HPS N13.1-1999.

The Pacific Northwest National Laboratory characterized the performance of sampling locations for two radionuclide air-sampling systems that continuously monitor radioactive air emissions from research and development facilities. The testing was conducted to determine whether sampling system locations would meet the criteria for uniform air velocity and contaminant concentration in the American National Standard Institute standard, Sampling and Monitoring Releases of Airborne Radioactive Substances from the Stacks and Ducts of Nuclear Facilities (ANSI/HPS N13.1-1999). The standard is a revision of the 1969 version that the facilities have been required to meet. Whereas the 1969 standard provided prescriptive criteria for the selection of sampling locations, the 1999 standard is performance-based and requires well-mixed sampling locations that must be demonstrated through performance tests that are specified in the standard. Testing at the Life Sciences Laboratory I was performed on the existing stack at the current sampling location; a scale model was built and used in place of the Radiochemical Processing Laboratory. Although both facilities' sampling sites were compliant with the 1969 standard, only the Radiochemical Processing Laboratory met the criteria of the revised standard. In the future, the use of a computational fluid dynamics computer model may be useful in determining whether a sampling location is likely to test successfully.

Aerosols↗

Indoor radon and well water radon in Virginia and Maryland.

The domestic use of radioactive water has long been a cause for concern, but only a few studies have examined prolonged exposure to radionuclide concentrations found in natural settings. This paper reports on the indoor radon concentrations from 1,500 homes in northern Virginia and southern Maryland and well water radon from 700 homes in the same area. Indoor radon concentrations are almost all between 1 and about 40 pCi/L. The winter season shows the highest values with about 40% of the homes over the US EPA action level of 4.0 pCi/L. The summer season shows the lowest values with about 25% of the homes over this level. This seasonal variation is related to home ventilation. Waterborne radon in homes with private well ranges from about 100 pCi/L to about 8,000 pCi/L. In small homes, indoor radon can be significantly increased by outgassing of the home water supply, even at water radon levels of less than 10,000 pCi/L.

Air Pollutants, Radioactive↗

The design and evaluation of an automated system for monitoring 133Xe in room air.

The radioactive gas 133Xe is widely used for ventilation imaging. This paper describes a system for continuous monitoring of the air concentration of 133Xe. The instrument consisted of a sodium iodide scintillation detector, a scaler/ratemeter and a data logger. The crystal was mounted inside a lead shield and enclosed in a perspex cylinder. A fan at one end of the cylinder drew room air into a shielded active volume via an inlet aperture designed to generate turbulent flow with no stagnant areas. The instrument was rendered relatively insensitive to external radiation by positioning the energy window over the 31 keV peak in the 133Xe spectrum. The detector sensitivity was approximately 2 s-1 per MBq m-3, with a typical background count rate of 0.12 s-1. The system was therefore capable of detecting a concentration of 0.06 MBq m-3 in a one-minute sampling interval. Results collected at five centres demonstrated that the eight-hour time-averaged concentrations were much less than the derived air concentration (DAC) for occupationally exposed persons (mean values 0.4 to 1.5% of the DAC), but that transient concentrations were extremely variable (mean values 7 to 24% of the DAC).

Air Pollutants, Occupational↗

[Radiation exposure and risk of radon in the room air of Swiss houses].

The radioactive noble gas radon, a member of the natural decay chains of uranium and thorium, enters the indoor environment in regionally highly diverging amounts. Subsoil of dwellings, building materials and drinking water are the main sources. In Switzerland and in many other countries, exposure of the lung tissue to the short lived radon decay products is the most important component of the radiation dose of the general public. Annual doses in areas with crystalline rock of high uranium content may reach the limits set up for occupational exposure. However, a clear link between cumulative exposure to radon daughters and elevation of the lung cancer incidence exists only for underground miners. The majority of human epidemiological studies point to a linear dose effect relationship. The indoor radon levels are determined by geology, building materials and techniques, climate and behaviour of the occupants. Experiences from Scandinavia and the Northern parts of America clearly indicate the possibility of cost-efficient remedial measures to reduce indoor radon levels.

Air Pollution, Radioactive↗

Radionuclide transport from soil to air, native vegetation, kangaroo rats and grazing cattle on the Nevada test site.

Between 1970 and 1986 the Nevada Applied Ecology Group (NAEG), U.S. Department of Energy, conducted environmental radionuclide studies at weapons-testing sites on or adjacent to the Nevada Test Site. In this paper, NAEG studies conducted at two nuclear (fission) sites (NS201, NS219) and two nonnuclear (nonfission) sites (Area 13 [Project 57] and Clean Slate 2) are reviewed, synthesized and compared regarding (1) soil particle-size distribution and physical-chemical characteristics of 239 + 240Pu-bearing radioactive particles, (2) 239 + 240Pu resuspension rates and (3) transuranic and fission-product radionuclide transfers from soil to native vegetation, kangaroo rats and grazing cattle. The data indicate that transuranic radionuclides were transferred more readily on the average from soil to air, the external surfaces of native vegetation and to tissues of kangaroo rats at Area 13 than at NS201 or NS219. The 239 + 240Pu resuspension factor for undisturbed soil at Area 13 was three to four orders-of-magnitude larger than at NS201 and NS219, the geometric mean (GM) vegetation-over-soil 239 + 240Pu concentration ratio was from ten to 100 times larger than at NS201, and the GM GI-over-soil, carcass-over-soil and pelt-over-soil 239 + 240Pu ratios for kangaroo rats were about ten times larger than at NS201. These results are consistent with the finding that Area 13, compared with NS201 or NS219, has a higher percentage of radioactivity associated with smaller soil particles and a larger percentage of resuspendable and respirable soil. However, the resuspension factor increased by a factor of 27 at NS201 when the surface soil was disturbed, and by a factor of 12 at NS219 following a wildfire. The average (GM) concentration of 239 + 240Pu for the GI (and contents) of Area 13 kangaroo rats and for the rumen contents of beef cattle that grazed Area 13 were very similar (400 vs. 440 Bq kg-1 dry wt, respectively) although the variability between individuals was very large. The GM carcass-over-GI 239 + 240Pu concentration ratio for kangaroo rats at Area 13, Clean Slate 2, and NS201 were similar in value (approximately 2 X 10(-2)), as were the GM GI-over-vegetation concentration ratios (approximately 2 X 10(0)) (no statistical differences).(ABSTRACT TRUNCATED AT 400 WORDS)

Air Pollutants, Radioactive↗

Poor design of local exhaust hood leads to radioactive release in the work area.

At a U.S. Department of Energy (DOE) waste handling facility, transuranic waste contained in standard 208-L (55-gallon) drums was being prepared to meet the DOE's Waste Isolation Pilot Project Waste Acceptance Criteria. During a particular waste handling operation, it was necessary for the workers to open several 208-L drums with TRU waste and prepare the waste to meet the WIPP Waste Acceptance Criteria. This operation was performed while the waste drums where positioned adjacent to a drum ventilator, which was designed to capture emissions generated from the drums during waste handling activities. During this activity, the continuous air monitor alarmed and reached an instantaneous air concentration of 0.1 Bq m(-3), or a factor of 300 times higher than the derived air concentration for inhalation class W 239Pu. The DOE conducted an investigation to determine why the drum ventilator did not control the transuranic emissions and to evaluate possible improvements to the drum ventilator and exposure controls. By adding upper and lower flanges to the drum ventilator, the capture velocity was increased by 88% without increasing the fan's speed. Adding flanges is a simple and inexpensive modification that enhances the performance of the drum ventilator. In addition to a poor design, the drum ventilator's capture velocity was compromised by competing air velocities that were generated by waste handling activities.

Air Pollution, Radioactive↗

Internal exposure of the staff involved in the cleanup after the accident at the Chernobyl nuclear power plant in 1986.

This article presents the results of our work from 1987 to 1994 on the reconstruction of internal exposure of the witnesses to the Chernobyl accident with respect to inhalation of airborne particles of nuclear fuel. Our results eliminate the hypothesis that inhalation intake of radioactive aerosols was a considerable pathway of exposure for staff at the Chernobyl nuclear power plant. It would conceivably lead to a nonuniform dose distribution in the body. Under that condition, actual equivalent doses in some organs, e.g., in lungs and in the wall of the lower large intestine are much higher than the actual effective dose. Therefore it is impossible to correctly assess the health risk for certain cohorts of the Chernobyl accident witnesses if the inhalation pathway is neglected. In that case not only the actual effective dose, but the actual equivalent doses too play a role in radiological measurement, when evaluating the hazard for less-exposed accident witnesses. That conclusion is of great importance to radiation protection policy, the planning of epidemiological studies and the carrying out of medical remedial actions for the different cohorts of accident witnesses. The findings should be taken into consideration in planning protective measures and in assessing health effects following the Chernobyl accident.

Air Pollutants, Radioactive↗

Investigation of aerial dispersion of radioactive dust from an open-pit uranium mine by passive vinyl collectors.

Detailed investigations of the aerial dispersion of radioactive dust from the biggest open-pit U mining and milling operation in Australia were carried out. Spatial distributions of the long-lived radionuclides of 238U series and their origin, i.e., mining and milling operations vs. natural background radiation, have been studied. Horizontal flux, dry deposition, and ground resuspension of the radionuclides were investigated along a 50-km transect in the direction of the prevailing monsoonal winds in the region. The study was performed by means of unconventional "sticky vinyl" passive dust collectors, occasionally supported by high-volume air filter samplers. The data from the flux measurements show an inverse square to inverse cubic dependence, and the dry deposition exhibits an inverse square dependence, of radionuclide load vs. distance. The pit has been the predominant contributor of long-lived U series radionuclides to the environment within the radius of several kilometers from the operations. An aerial dispersion computer code (LUCIFER), based on a Gaussian plume model, was developed for the project. Experimental data were used as the code input data. Good agreement between the measured data and the normalized computed results was obtained.

Air Pollutants, Radioactive↗

Isotopic signature of atmospheric xenon released from light water reactors.

A global monitoring system for atmospheric xenon radioactivity is being established as part of the International Monitoring System to verify compliance with the Comprehensive Nuclear-Test-Ban Treaty (CTBT). The isotopic activity ratios of (135)Xe, (133m)Xe, (133)Xe and (131m)Xe are of interest for distinguishing nuclear explosion sources from civilian releases. Simulations of light water reactor (LWR) fuel burn-up through three operational reactor power cycles are conducted to explore the possible xenon isotopic signature of nuclear reactor releases under different operational conditions. It is studied how ratio changes are related to various parameters including the neutron flux, uranium enrichment and fuel burn-up. Further, the impact of diffusion and mixing on the isotopic activity ratio variability are explored. The simulations are validated with reported reactor emissions. In addition, activity ratios are calculated for xenon isotopes released from nuclear explosions and these are compared to the reactor ratios in order to determine whether the discrimination of explosion releases from reactor effluents is possible based on isotopic activity ratios.

Air Pollutants, Radioactive↗

Time dependence of the 137Cs resuspension factor on the Romanian territory after the Chernobyl accident.

On the basis of the radioactivity levels in aerosol and atmospherical deposition samples due to the Chernobyl accident, the resuspension factor of 137Cs as a four-parameter function has been inferred. The standard procedure to derive the dependence of resuspension on time assumes that the initial deposit is instantaneous. A simple method assuming a constant deposition rate over a fixed period has been proposed. Also, based on existing experimental data, an attempt was made to consider a realistic time dependence of the deposition rate to cope with the particular case of the Chernobyl accident. The differences between the two models are outlined. The Chernobyl direct deposit has been assumed to be the deposit measured between 30 April and 30 June 1986. The calculated values of the resuspension factor are consistent with the IAEA's recommended model and depend on the rainfall that occurred in June 1986 and the site-specific disturbance conditions during the first 100 d following 1 July 1986 and only on artificial disturbance by humans and vehicles after that.

Accidents↗

Effective dose scaling factors for use with cascade impactor sampling data in tenorm inhalation exposures.

When assessing the effective dose to workers following radio-aerosol inhalation exposures, significant reductions in dose uncertainty can be achieved through direct measurement of the particle-size distribution. The University of Washington Mark III cascade impactor is one such air sampling device that permits the user to determine aerosol mass and radioactivity concentrations as a function of particle size within eight different size intervals (each corresponding to a different impactor stage or end filter). Traditionally, dose assessments made using the LUDEP code or other internal dosimetry software utilize this air sampling information by assigning the radioactivity measured at each stage as concentrated at a single representative size central to the size interval. In this study, we explore more realistic assumptions that the measured radioactivity distributes uniformly, linearly increases, or linearly decreases across the particle size interval for each impactor stage. The concept of an effective dose scaling factor, SF(E), is thus introduced whereby (1) the former approach can be used (which requires less computational effort using the LUDEP code), and (2) the resulting values of effective dose per stage can then be rescaled to values appropriate to a linear radioactivity distribution per stage. For a majority of (238)U-series radionuclides, particle size ranges, and absorption classes, differences in these two approaches are less than 10%, and thus no corrections in effective dose per particle stage are needed. Significant corrections, however, were noted in select cases. For uniform or linearly decreasing radioactivity distributions, end-filter particles (0.03 to 0.35 microm) of type F, M, or S radionuclides were assigned values of SF(E) ranging from 1.15 to 1.44, while 3(rd) stage particles (4.5 to 12 microm) of type M and S radionuclides were assigned values of SF(E) ranging from 1.11 to 1.53. When the cascade impactor measurements indicate a linear increase of activity across a given impactor-stage size range, values of SF(E) range from a high of 1.11 (6(th) stage particles of type F radionuclides) to lows of 0.85 to 0.91 (4(th) stage and end-filter particles of type M and S radionuclides). In these cases, the inhalation dose coefficient varies non-linearly across the particle size range, and the assumption of a mono-size distribution per impactor stage either underestimates (SF(E) > 1) or overestimates (SF(E) < 1) that stage's contribution to the worker effective dose.

Aerosols↗

Use of historical uranium air sampling data to estimate worker exposure potential to airborne radioactive particulate in a uranium processing facility.

Historical industrial hygiene monitoring records from a uranium processing plant were collected and analyzed to characterize exposure potential to airborne radioactive particulate. More than 2,100 samples were collected during the period of 1954-1968. The data was organized by job title, plant number, and year of measurement. Laboratory analysis of air samples indicated a wide range of potential exposures to the alpha-emitting particulate. Logarithmic transformation of the data was necessary to approximate Gaussian distributions. Geometric Mean (GM) values were used as the measure of central tendency within years. GM values ranged from 23-49 disintegrations per minute per cubic meter of air sampled (dpm/m3) with the years 1963 and 1964 being significantly higher than other years (ANOVA: p < 0.05). When comparing exposure potential across plants, GM ranged from 20-68 dpm/m3, with plants 5 and 8 being significantly higher than the others (ANOVA: p < 0.05). Exposure potential for specific job titles across the plants varied widely. GM for clerks was the lowest (11 dpm/m3) while furnace operators were the highest (235 dpm/m3). Other job titles with potentially high exposures were chemical operators, forklift operators, machine operators, and furnace operators. This analysis indicates the magnitude and distributions of worker exposure to alpha-emitting airborne particulate. Additional analysis and epidemiologic studies are planned for this facility.

Aerosols↗