Fukushima radionuclides in the NW Pacific, and assessment of doses for Japanese and world population from ingestion of seafood.

Science.gov (United States)

Povinec, Pavel P; Hirose, Katsumi

2015-03-12

Variations of Fukushima-derived radionuclides ((90)Sr, (134)Cs and (137)Cs) in seawater and biota offshore Fukushima and in the NW Pacific Ocean were investigated and radiation doses to the Japanese and world population from ingestion of seafood contaminated by Fukushima radionuclides were estimated and compared with those from other sources of anthropogenic and natural radionuclides. The total effective dose commitment from ingestion of radionuclides in fish, shellfish and seaweed caught in coastal waters off Fukushima was estimated to be 0.6 ± 0.4 mSv/y. The individual effective dose commitment from consumption of radioactive-contaminated fish caught in the open Pacific Ocean was estimated to be 0.07 ± 0.05 mSv/y. These doses are comparable or much lower than doses delivered from the consumption of natural (210)Po in fish and in shellfish (0.7 mSv/y). The estimated individual doses have been below the levels when any health damage of the Japanese and world population could be expected.

Long-term ingestion dose monitoring in a population group with increased 137Cs intake

International Nuclear Information System (INIS)

Bartuskova, M.; Lusnak, J.; Malatova, I.; Pfeiferova, V.; Pospisilova, H.

2008-01-01

137 Cs amounts and ingestion doses in Czech population have been monitored by whole-body counting since the Chernobyl accident. Indirect estimation of the retention through measurement of 137 Cs excreted with urine in 24 hours has also been performed since 1987. The 137 Cs content in human body can be calculated from the urine data provided that the intake of 137 Cs during the period of interest is constant. In a semi-natural environment, the 137 Cs content in mushrooms, wild berries and game decreases due to its natural decay solely. The 137 Cs content in people who mostly consume venison and have been living in an area with elevated contamination has been monitored, mostly through measurement of 137 Cs in urine. In parallel, measurements with a mobile whole-body counter have also been performed. Currently, annual doses from the ingestion of 137 Cs in the inhabitants are very low (0.001 to 0.002 mSv.year -1 ). In a group of hunters in the Jeseniky Mountains (Northern Moravia) the doses were estimated to 0.10 mSv.year -1 . (orig.)

An analysis of ingestion doses from a range of postulated Magnox reactor releases

International Nuclear Information System (INIS)

Nair, S.

1986-01-01

An analysis was carried out of ingestion doses from a range of postulated Magnox reactor releases to the atmosphere. Doses to the adult, ten year old child and one year old child were calculated, which showed the one year old child to receive the highest dose. Detailed studies were made of the significance of the ingestion dose to the one year old child in relation to other exposure routes. The ingestion dose was analysed for its contributing critical organs, foods and nuclides. Approximate calculations were also made of the dependence of the ingestion dose on the time of year when the release occurs. The ingestion pathway was found to dominate if the release occurs towards the end of the growing season but to be less significant relative to other exposure pathways at all other times. The calculations enabled a set of release-specific emergency action guidance levels of critical nuclide concentrations in the critical foods to be produced, which comply with NRPB's ingestion Emergency Reference Level guidelines. (author)

An analysis of ingestion doses from a range of postulated Magnox reactor releases

International Nuclear Information System (INIS)

Nair, S.

1985-06-01

An analysis has been carried out of ingestion doses from a range of postulated Magnox reactor releases to atmosphere. Calculations were made of the dose to the adult, ten year old child and one year old child, which showed the one year old child to receive the highest dose. Detailed studies were made of the significance of the ingestion dose to the one year old child in relation to other exposure routes. The ingestion dose was also analysed in terms of the contributing critical organs, foods and nuclides. Approximate calculations were also made of the dependence of the ingestion dose on the time of year when the release occurs. The results of the analysis were used to derive a set of release-specific Emergency Action Guidance Levels (EAGLs) of critical nuclide concentrations in the critical foods, which comply with NRPB's ingestion ERL recommendations. The EAGLs were supplemented with a corresponding set of EAGLs for grass, for use in situations where crop samples were not readily available. (author)

Fukushima radionuclides in the NW Pacific, and assessment of doses for Japanese and world population from ingestion of seafood

OpenAIRE

Povinec, Pavel P.; Hirose, Katsumi

2015-01-01

Variations of Fukushima-derived radionuclides (90Sr, 134Cs and 137Cs) in seawater and biota offshore Fukushima and in the NW Pacific Ocean were investigated and radiation doses to the Japanese and world population from ingestion of seafood contaminated by Fukushima radionuclides were estimated and compared with those from other sources of anthropogenic and natural radionuclides. The total effective dose commitment from ingestion of radionuclides in fish, shellfish and seaweed caught in coasta...

Dose estimation from residual and fallout radioactivity, 1

International Nuclear Information System (INIS)

Takeshita, Kenji

1975-01-01

External dose rates and cumulative doses for early entrants from areal surveys and simulated experiments are reviewed. The average cumulative doses to infinity at the hypocenters were 101 rad in Hiroshima and 32 rad in Nagasaki, with a variation of about 60 percent. Radioactive fallout areas nearly matched the ''black rain'' areas in Nagasaki and in Hiroshima. Radioactivity in the fallout areas was affected by radioactive decay and by the leaching and dissipation by rains. Considering these factors, the cumulative dose to infinity in the fallout area of Hiroshima was estimated to be 13 rad, excluding internal radiation doses from inhaled and ingested radionuclides. Attempts to estimate radiation dose from internally deposited radionuclides are also described. (auth.)

The relative importance of ingestion for multiple pathway dose assessments

International Nuclear Information System (INIS)

Wicker, W.; Grogan, H.; Bergstroem, U.; Hoffman, O.

1991-01-01

The general purpose of this report is to examine the relative importance of ingestion pathways, and particularly food chain transport in overall dose assessment. The importance of ingestion pathways is examined for various release scenarios and radionuclides because the findings are expected to differ with circumstances. The degree to which contaminated food products contribute to the total dose will affect the importance of accuracy and uncertainty of food chain model predictions, which is the main thrust of the Biospheric Model Validation Study (BIOMOVS). This analysis requires that all modes of radiation exposure be examined, including inhalation, external exposure, and the various ingestion pathways. (2 figs., 2 tabs.)

Dose construction for vegetable ingestion exposure in Hong Kong

International Nuclear Information System (INIS)

Lui, W.S.; Walton, A.; Yeung, M.R.

1997-01-01

The author presents the mathematical model TERRA used for the construction of ingestion doses resulting from the consumption of contaminated vegetables during a nuclear accident in Hong Kong. Using the ground surface deposited radionuclide densities as input, TERRA calculates the concentrations of 54 radionuclides on the surfaces and within the tissue of vegetables as a function of time and the radiation doses delivered to the various vital organs following their consumption by humans. The present model provides a convenient tool to determine the time histories of 54 radionuclides in vegetables and to back track or project the ingestion dose after a major accident such that more appropriate and timely countermeasures can be implemented

Estimates of radiation doses and cancer risk from food intake in Korea

International Nuclear Information System (INIS)

Moon, Eun Kyeong; Lee, Won Jin; Ha, Wi Ho; Seo, Song Won; Jin, Young Woo; Jeong, Kyu Hwan; Yoon, Hae Jung; Kim, Hyoung Soo; Hwang, Myung Sil; Choi, Hoon

2016-01-01

After the Fukushima Daiichi nuclear power plant accident, a widespread public concern for radiation exposure through the contamination of domestic or imported food has continued worldwide. Because the internal exposure from contaminated food is an important consideration for human health effect, some studies for estimating radiation doses and cancer risk from the Fukushima nuclear accident have been conducted in several countries (1). The aims of the study is to estimate internal radiation dose and lifetime risks of cancer from food ingestion in Korean population. Our findings suggest no discernible increase n radiation doses or excess fatal cancer risk from food ingestion at this stage in Korea, and provide scientific evidence of the risk communication with general public associated with low-dose radiation exposure.

Estimates of radiation doses and cancer risk from food intake in Korea

Energy Technology Data Exchange (ETDEWEB)

Moon, Eun Kyeong; Lee, Won Jin [Korea University, Seoul (Korea, Republic of); Ha, Wi Ho; Seo, Song Won; Jin, Young Woo [Korea Institute of Radiological and Medical Sciences, Seoul (Korea, Republic of); Jeong, Kyu Hwan [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of); Yoon, Hae Jung; Kim, Hyoung Soo; Hwang, Myung Sil [Ministry of Food and Drug Safety, Cheongju (Korea, Republic of); Choi, Hoon [Wonkwang University, Iksan (Korea, Republic of)

2016-04-15

After the Fukushima Daiichi nuclear power plant accident, a widespread public concern for radiation exposure through the contamination of domestic or imported food has continued worldwide. Because the internal exposure from contaminated food is an important consideration for human health effect, some studies for estimating radiation doses and cancer risk from the Fukushima nuclear accident have been conducted in several countries (1). The aims of the study is to estimate internal radiation dose and lifetime risks of cancer from food ingestion in Korean population. Our findings suggest no discernible increase n radiation doses or excess fatal cancer risk from food ingestion at this stage in Korea, and provide scientific evidence of the risk communication with general public associated with low-dose radiation exposure.

Natural radioactivity in groundwater system and estimates of committed effective dose due to water ingestion in Ilorin, Nigeria

Energy Technology Data Exchange (ETDEWEB)

Nwankwo, Levi I. [Department of Physics, University of Ilorin, Ilorin 240003 (Nigeria)

2014-07-01

Natural radioactivity measurements in drinking water have been performed in many parts of the world, mostly for assessment of the doses and risk resulting from consuming water. A study of the radionuclide concentrations in groundwater samples collected from wells distributed within Ilorin, west of central Nigeria has been carried out. Twenty Eight (28) water samples were analyzed by gamma ray spectroscopy to determine the {sup 226}Ra, {sup 228}Ra, and {sup 40}K concentrations. The specific activity values ranged from 0.02 to 7.4 Bq/l for {sup 226}Ra, 0.009 to 5.6 Bq/l for {sup 228}Ra, and 0.45 to 30.14 Bq/l for {sup 40}K. The annual ingestions of these radionuclides, using local consumption rates (average over the whole population) of 1 liter per day, were subsequently estimated to range from 0 to 0.8 mSv/y with an average of 0.36 mSv/y, 0 to 1.42 mSv/y with an average of 0.50 mSv/y, and 0 to 0.01 mSv/y with an average of 0.01 mSv/y for {sup 226}Ra, {sup 228}Ra, and {sup 40}K respectively. The results show that the mean annual effective dose values received as a result of the combined ingestion of the radionuclides from many individual wells in the study area exceed the norm of drinking water quality established by UNSCEAR/WHO. Efforts should therefore be made by policy makers to protect the populace from long-term health consequences. (authors)

Radiation dose to mouse liver cells from ingestion of tritiated food or water

International Nuclear Information System (INIS)

Komatsu, K.; Okumura, Y.; Sakamoto, K.

1990-01-01

Tritium incorporated into tissues and DNA of mice was studied after daily ingestion of tritiated food or tritiated water. The tritiated food used was a commercial preparation mixed with brine shrimp that had been reared in tritiated sea water. After ingestion of tritiated food or water for up to 22 d, the specific activity of 3H in tissues was measured as tissue-free-water 3H, tissue-bound 3H, and DNA-bound 3H. Carbon-14 glucose was added to food and drinking water to compare the 3H intake from food with that from water. The specific activity of 3H in tissues was then corrected by the specific activity of 14C in tissues to determine the 3H incorporation from the same amount of ingested food and water. DNA-bound 3H after the ingestion of tritiated food was 4.6 times higher than that of tritiated water, while tissue-bound 3H was 2.2 times higher. The radiation dose to liver from 3H incorporated through food was twofold higher than from tritiated water, which was mainly from the high incorporation of 3H into DNA. Our results demonstrated that the dose calculation based on tissue-free-water 3H alone would under-estimate the radiation exposure of the human population exposed to tritiated food

INREM II: a computer implementation of recent models for estimating the dose equivalent to organs of man from an inhaled or ingested radionuclide

International Nuclear Information System (INIS)

Killough, G.G.; Dunning, D.E. Jr.; Pleasant, J.C.

1978-01-01

This report describes a computer code, INREM II, which calculates the internal radiation dose equivalent to organs of man which results from the intake of a radionuclide by inhalation or ingestion. Deposition and removal of radioactivity from the respiratory tract is represented by the ICRP Task Group Lung Model. A four-segment catenary model of the GI tract is used to estimate movement of radioactive material that is ingested or swallowed after being cleared from the respiratory tract. Retention of radioactivity in other organs is specified by linear combinations of decaying exponential functions. The formation and decay of radioactive daughters is treated explicitly, with each radionuclide species in the chain having its own uptake and retention parameters, as supplied by the user. The dose equivalent to a target organ is computed as the sum of contributions from each source organ in which radioactivity is assumed to be situated. This calculation utilizes a matrix of S-factors (rem/μCi-day) supplied by the user for the particular choice of source and target organs. Output permits the evaluation of crossfire components of dose when penetrating radiations are present. INREM II is coded in FORTRAN IV and has been compiled and executed on an IBM-360 computer

Determination of the carbon content of domestic farm produces to estimate offsite C-14 ingestion dose

International Nuclear Information System (INIS)

Jung, Y. G.; Kim, M. J.; Lee, G. B.

2003-01-01

The carbon content of grains, leafy and root vegetables, and fruits which the Koreans usually eat were calculated to use in the estimation of offsite C-14 ingestion dose. With the data of food intake per day in the Report on 1998 national health and nutrition survey- dietary intake survey, 5 age-group integrate d intake of the 4 farm produce groups were extracted for food items and the amount. Intake percentage in each food group were taken as food weighing factor for the foods. Carbon content was calculated using protein, fat, and carbohydrate content of the foods, and multiplied by the corresponding food weighing factor to derive the content of the food groups. The calculated carbon content of grains, leafy and root vegetables, and fruits were 39.%, 4.2%, 8.0%, and 5.9% respectively. Grains and fruits were not much different from ODCM for carbon content, but vegetables were higher by 0.7%∼4.5%

Spatial distribution of tritium in surface water and assessment of ingestion dose

International Nuclear Information System (INIS)

Rupali, C.K.; Jha, S.K.; Tripathi, R.M.; Sonali, B.; Reddy, Priyanka

2014-01-01

The present study focuses on the distribution of tritium in drinking water samples from Mumbai and other suburban areas. Measurement of tritium in the drinking water was carried out using an ultra-low background LKB Quantulus Spectrometer, model 1220. The concentration of tritium in the drinking water ranged between ≤12.3-19.8TU with a geometric mean of 13.3TU. The observed values doesn't indicate any fresh input of tritium and are well within prescribed limit of 740 Bq/L (approx. 6,271.2 TU) given by USEPA for tritium ingestion through drinking water. The estimated dose due to tritium ingestion through drinking was 0.02 μSv/y which is negligible when compared to the limit of 1000 μSv/y assigned to general public. (author)

Estimation of ingestion dose due to I-131 in the initial month by using food-monitoring data after the Fukushima nuclear disaster in Japan

Energy Technology Data Exchange (ETDEWEB)

Yamaguchi, Ichiro [National Institute of Public Health, Department of Environmental Health, Wako, Saitama (Japan)

2012-11-15

The committed equivalent dose to the thyroid caused by I-131 and the effective dose caused by I-131, Cs-134 and Cs-137 due to ingestion immediately after the accidental releases following the Fukushima nuclear disaster in March 2011 were estimated retrospectively by using measured food data. A food monitoring dataset provided by the Ministry of Health, Labour and Welfare (MHLW) up to April 18, 2011 (N=1,752) was used for this study. Information on food consumption by 99 food categories was made available by using the original data of the Japanese National Food Consumption Survey, which was conducted in 2009 (N=9,942). Food concentration every 4 days and food consumption in each food category was randomly picked up (N=100,000). The levels of radioactive iodine and cesium were summed for one month and then converted to equivalent doses to the thyroid and effective doses. These doses in the first month after the Fukushima nuclear power plant accident were evaluated by using the food monitoring dataset provided by the MHLW. Assuming that food was randomly extracted from monitored food samples and food restrictions were fully implemented, the 90%tile of the equivalent doses to the thyroid and the effective doses in 1- to 6-year-old children were estimated to be around 1 mSv and 0.07 mSv, respectively. Several different methods should be considered to reduce limitations of this estimation. (author)

Dose estimates in Japan following the Chernobyl reactor accident

International Nuclear Information System (INIS)

Togawa, Orihiko; Homma, Toshimitsu; Iijima, Toshinori; Midorikawa, Yuji.

1988-02-01

Estimates have been made of the maximum individual doses and the collective doses in Japan following the Chernobyl reactor accident. Based on the measured data of ground deposition and radionuclide concentrations in air, raw milk, milk on sale and leafy vegetables, the doses from some significant radionuclides were calculated for 5 typical exposure pathways; cloudshine, groundshine, inhalation, ingestion of milk and leafy vegetables. The maximum effective dose equivalents for hypothetical individuals were calculated to be 1.8 mrem for adults, 3.7 mrem for children and 6.0 mrem for infants. The collective effective dose equivalent in Japan was estimated to be 5.8 x 10 4 man · rem; 0.50 mrem of the average dose per capita. (author)

Method for evaluation of doses from ingestion of polonium, bismuth and lead as natural radioactive material(NORM)

International Nuclear Information System (INIS)

Pena, Vanessa; Puerta, Anselmo; Morales, Javier

2013-01-01

In this work was carried out an evaluation of dose from ingestion of radioactive daughters of radon (lead, bismuth and polonium), taking into account ages from three months up to adult men, using the new model of the human alimentary tract HATM and methodology of calculating doses proposed by the ICRP publication 103, which allows the estimation of dose based on the concentration of the radionuclide present in the diet or in the water of consumption

Calculation of internal dose from ingested soil-derived uranium in humans: Application of a new method

Energy Technology Data Exchange (ETDEWEB)

Traeber, S.C.; Li, W.B.; Hoellriegl, V.; Oeh, U. [Helmholtz Zentrum Muenchen, German Research Center for Environmental Health, Research Unit Medical Radiation Physics and Diagnostics, Neuherberg (Germany); Nebelung, K. [Friedrich Schiller University of Jena, Institute of Geosciences, Jena (Germany); Michalke, B. [Helmholtz Zentrum Muenchen, German Research Center for Environmental Health, Research Unit BioGeoChemistry and Analytics, Neuherberg (Germany); Ruehm, W. [Helmholtz Zentrum Muenchen, German Research Center for Environmental Health, Institute of Radiation Protection, Neuherberg (Germany)

2015-08-15

The aim of the present study was to determine the internal dose in humans after the ingestion of soil highly contaminated with uranium. Therefore, an in vitro solubility assay was performed to estimate the bioaccessibility of uranium for two types of soil. Based on the results, the corresponding bioavailabilities were assessed by using a recently published method. Finally, these bioavailability data were used together with the biokinetic model of uranium to assess the internal doses for a hypothetical but realistic scenario characterized by a daily ingestion of 10 mg of soil over 1 year. The investigated soil samples were from two former uranium mining sites of Germany with {sup 238}U concentrations of about 460 and 550 mg/kg. For these soils, the bioavailabilities of {sup 238}U were quantified as 0.18 and 0.28 % (geometric mean) with 2.5th percentiles of 0.02 and 0.03 % and 97.5th percentiles of 1.48 and 2.34 %, respectively. The corresponding calculated annual committed effective doses for the assumed scenario were 0.4 and 0.6 μSv (GM) with 2.5th percentiles of 0.2 and 0.3 μSv and 97.5th percentiles of 1.6 and 3.0 μSv, respectively. These annual committed effective doses are similar to those from natural uranium intake by food and drinking water, which is estimated to be 0.5 μSv. Based on the present experimental data and the selected ingestion scenario, the investigated soils - although highly contaminated with uranium - are not expected to pose any major health risk to humans related to radiation. (orig.)

Correlation between the single, high dose of ingested baclofen and clinical symptoms

Directory of Open Access Journals (Sweden)

Jacek Sein Anand

2017-12-01

There is a statistically significant correlation between the dose of ingested baclofen and the presence of acute respiratory failure, and duration of mechanical ventilation. Patients who have taken a single dose of baclofen of 200 mg, or higher, should be managed in centres able to provide continuous monitoring of life functions. Those with a higher level of a single dose of baclofen ingestion (>500 mg, should be hospitalized in a Toxicology Unit or Intensive Care Unit able to provide airway support and mechanical ventilation.

Estimate of whole body doses for Lynette Tew and Becky Farnsworth from Nevada Test Site local fallout

International Nuclear Information System (INIS)

Anspaugh, L.R.; Ng, Y.C.

1985-01-01

Lynette Tew and Becky Farnsworth are decendents whose relatives are litigants in Timothy vs US. The litigants allege that the decendents were harmed by radiation doses received as a result of local fallout from the testing of nuclear weapons at the Nevada Test Site. We have calculated a best estimate of the whole body dose received by each decendent from external exposure and the ingestion of radionuclides with food. In each case the dose via ingestion is trivial compared to the external dose. For Lynette Tew the dose estimate is 0.28 rads. For Becky Farnsworth it is 0.0035 rads. 23 references, 4 tables

Internal dose estimates

International Nuclear Information System (INIS)

Wrenn, M.E.

1977-01-01

Internal doses, the procedures for making them and their significance has been reviewed. Effects of uranium, radium, lead-210, polonium-210, thorium in man are analysed based on data from tables and plots. Dosimetry of some ingested nuclides and inhalation dose due to radon-222, radon-220 and their daugther products are discussed [pt

Evaluation of ingestion dose to different age groups of public of Chutka (MP) environment due to 40K

International Nuclear Information System (INIS)

Tejpal, Menaria; Tiwari, S.N.; Mulchandani, U.; Goyal, S.; Ravi, P.M.; Tripathi, R.M.

2014-01-01

The activity levels of 40 K in the locally produced biological samples of food items as well as trend indicator samples from different locations of Chutka area of Madhya Pradesh site, were estimated by gamma spectrometry as part of preoperational survey. The observed 40 K activity in these samples is comparable with reported values from other areas of India. The annual effective dose through ingestion pathway due to 40 K is estimated for infant, child and adult categories of local population. The computed average ingestion dose due to intake of 40 K is found to be highest for infant child (0.34 mSv/y). Radionuclides enter the human body through complex mechanism including foodstuffs via the food chain. The most predominant naturally occurring radionuclides in foodstuffs is 40 K, other contributions to the radionuclides in foods include deposited fallouts from fission and activation products released during nuclear accidents and constituents of weapons tests released after detonation. The primary objective of the present study is to estimate the activity levels of 40 K in the dietary matrices and to evaluate internal dose due to annual intake of various dietary items by the population around Chutka environment, a proposed nuclear power station site near Jabalpur of Madhya Pradesh

Estimating 137Cs ingestion doses to Saamis in Kautokeino (Norway) using whole body counting vs. dietary survey results and food samples

International Nuclear Information System (INIS)

Skuterud, L.; Bergan, T.; Mehli, H.

2002-01-01

From 1965 to 1990 whole body measurements were carried out on an annual basis. Since then, 3-year cycles have been followed. In most years, the reindeer keepers have provided samples of reindeer meat for radiocaesium analysis. In 1989-1990 and 1999 dietary surveys were performed in conjunction with the whole-body monitoring. Earlier diet information is available from a separate study in 1963. Rough estimates of the radiocaesium intake by the studied population in Kautokeino have indicated that the dietary surveys have overestimated the radiocaesium intake. The aim of the present study was to evaluate the available information from Kautokeino, and to derive some conclusions regarding the reindeer meat consumption by today's reindeer keepers, and what 137 Cs ingestion doses they are exposed to. (LN)

Contribution of inhalation by food animals to man's ingestion dose

International Nuclear Information System (INIS)

Zach, R.

1985-01-01

Animals' inhalation (AI) pathway was evaluated for 57 radionuclides using infant dose predictions from the food-chain model LIMCAL. With ingestion transfer coefficients fMi to define transfer from the respiratory tract to milk, the AI pathway appeared to be insignificant compared to animals' plant ingestion, as implicitly assumed in most environmental assessment models for nuclear installations. Using ICRP Publication 30 respiratory clearance models for man to adjust ingestion transfer coefficients, animals' inhalation appeared to be important, particularly for some actinide radionuclides. The AI pathway also appeared to be significant relative to man's inhalation, especially for infants. The importance of the AI pathway varied greatly between radionuclides, and results strongly suggest that it cannot be ignored in environmental assessments. Until better data become available to implement this pathway fully, adjusted ingestion transfer coefficient values can be used for transfer from animals' respiratory tract to milk and other food products

Evaluation of radiation dose resulting from the ingestion of [3H]-and [14C]thymidine in the rat

International Nuclear Information System (INIS)

Takeda, H.; Iwakura, T.

1987-01-01

Average doses to rat tissues from the ingestion of 2-[ 14 C]thymidine were compared with those from methyl-[ 3 H]thymidine or 6-[ 3 H]thymidine. [ 14 C]thymidine gave the highest dose to spleen and small intestine. Doses to other tissues from [ 14 ]thymidine were almost the same or lower compared with those from [ 3 H]thymidine, irrespective of the 9 times higher β-ray energy of 14 C than that of 3 H. In the case of [ 14 C]thymidine, most of the dose was given by radioactivity incorporated into the organic tissue constituents (non-volatile radioactivity). In the case of [ 3 H]thymidine, the dose contributions by non-volatile radioactivity were very small and major contributions were rather from volatile radioactivity ( 3 HHO), formed by degradation of [ 3 H]thymidine. No significant difference in their total doses was found between the two [ 3 H]precursors, but the dose from non-volatile radioactivity alone was 2-3 times higher with methyl-[ 3 H]thymidine than with 6-[ 3 H]thymidine. Estimates of dose to cell nuclei in various tissues after ingestion of [ 3 H]thymidine were also made in order to predict more precisely possible radiation hazards. (author)

Method for evaluation of doses from ingestion of polonium, bismuth and lead as natural radioactive material(NORM); Metodo de evaluacion de dosis por ingestion de polonio, bismuto y plomo como materiales radiactivos naturales

Energy Technology Data Exchange (ETDEWEB)

Pena, Vanessa; Puerta, Anselmo; Morales, Javier, E-mail: vpenam@ullal.edu.co, E-mail: japuerta@unal.edu.co, E-mail: jmorales@unal.cdu.co [Universidad Nacional de Colombia, Medellin (Colombia). Grupo de Fisica Radiologica

2013-07-01

In this work was carried out an evaluation of dose from ingestion of radioactive daughters of radon (lead, bismuth and polonium), taking into account ages from three months up to adult men, using the new model of the human alimentary tract HATM and methodology of calculating doses proposed by the ICRP publication 103, which allows the estimation of dose based on the concentration of the radionuclide present in the diet or in the water of consumption.

Combined methodology for estimating dose rates and health effects from exposure to radioactive pollutants

Energy Technology Data Exchange (ETDEWEB)

Dunning, D.E. Jr.; Leggett, R.W.; Yalcintas, M.G.

1980-12-01

The work described in the report is basically a synthesis of two previously existing computer codes: INREM II, developed at the Oak Ridge National Laboratory (ORNL); and CAIRD, developed by the Environmental Protection Agency (EPA). The INREM II code uses contemporary dosimetric methods to estimate doses to specified reference organs due to inhalation or ingestion of a radionuclide. The CAIRD code employs actuarial life tables to account for competing risks in estimating numbers of health effects resulting from exposure of a cohort to some incremental risk. The combined computer code, referred to as RADRISK, estimates numbers of health effects in a hypothetical cohort of 100,000 persons due to continuous lifetime inhalation or ingestion of a radionuclide. Also briefly discussed in this report is a method of estimating numbers of health effects in a hypothetical cohort due to continuous lifetime exposure to external radiation. This method employs the CAIRD methodology together with dose conversion factors generated by the computer code DOSFACTER, developed at ORNL; these dose conversion factors are used to estimate dose rates to persons due to radionuclides in the air or on the ground surface. The combination of the life table and dosimetric guidelines for the release of radioactive pollutants to the atmosphere, as required by the Clean Air Act Amendments of 1977.

Determination of transfer factors of uranium, thorium, radium and lead from soil to agricultural product in Japan for estimating internal radiation dose through ingestion

International Nuclear Information System (INIS)

Sasaki, Tomozo; Tashiro, Yoshikazu; Fujinaga, Hideshi; Ishii, Tomoaki; Gunji, Yasuyoshi

2002-01-01

The transfer factors (TFs) of uranium (U), thorium (Th), radium (Ra) and lead (Pb) from soil to agricultural products were determined in order to estimate the internal radiation dose to the human body through ingestion. Samples of rice, potato, onion, cabbage, mandarin orange, spinach, apple and soil were collected from various districts in Japan. After appropriate pretreatment of the samples, concentrations in the sample solutions were measured by Inductively coupled plasma-mass spectrometry (ICP-MS) (for U, Th and Pb) and liquid scintillation counter (for Ra). It was recognized that TFs were 4.9 x 10 -6 (apple) and 3.6 x 10 -4 (spinach) for U, 2.8 x 10 -6 (apple) and 2.3 x 10 -4 (spinach) for Th, and 4.0 x 10 -3 (hulled rice), 7.0 x 10 -5 (onion) and 5.0 x 10 -3 (hulled rice) for Pb. The TF of Ra, however, was not determined due to detection limitations. TF values obtained in the present study range from the same order of magnitude to 1/100 compared to the data in Technical Report Series No.364 (TRS364) as reported by IAEA. It was revealed that the internal radiation dose caused by the intake of uranium series radioactive nuclides through agricultural food ingestion was 16 μSv/y, where Pb was the most contributory nuclide. (author)

Dose estimates to the public from 210Po ingestion via dietary sources at Kalpakkam (India)

International Nuclear Information System (INIS)

Kannan, V.; Iyengar, M.A.R.; Ramesh, R.

2001-01-01

Distribution of one of the natural radionuclides 210 Po activity in food of plant origin such as cereals, pulses, vegetables and food of animal origin such fish, crab, prawn, chicken, egg etc. were determined in and around Kalpakkam up to a distance of 32 km radius. The general range of 210 Po activity levels in all the dietary components (excluding milk and drinking water which are reported in mBq l -1 ) ranged widely from ≤10 to 122,641 mBq kg -1 fresh, the minimum being in vegetables and maximum being in the edible portions (muscle) of crab samples. 210 Po levels in drinking water and milk samples ranged between 0.6-2.6 and 8-12 mBq l -1 respectively. 210 Po content in cereals ranged from ≤32 to 745 mBq kg -1 and in pulses it was found to vary between ≤32 and 294 mBq kg -1 . The range of 210 Po activity in different types of vegetables was found to be ≤10-653 mBq kg -1 . Among the different varieties of vegetables, 210 Po was significantly higher in leafy vegetables (28-653 mBq kg -1 ) as compared to rooty and other types of vegetables which ranged from ≤10-180 mBq kg -1 . In food of animal origin, the observed minimum activity of 210 Po was 8 mBq l -1 in milk and the maximum observed was 122,641 mBq kg -1 in the muscles of crab. It was also observed that 210 Po activity was found to be in higher levels in the food of aquatic animal origin (1414-122,641 mBq kg -1 ) than in the food of terrestrial animal origin (other than milk) which varied from 41 to 963 mBq kg -1 . It is evident from the present study that the foods of animal origin especially crab, fish and prawn deliver significantly greater dose (93-3364 μSv yr -1 ) to the public compared to foods of plant origin whose mean dose ranged 0.08-128 μSv yr -1 . The study showed evidence to suggest that the total ingestion dose due to 210 Po received by the Kalpakkam public through dietary sources is significantly higher than the ingestion dose received due to fallout sources such as 137 Cs and 90 Sr

Adaptation of the ICRP models for the Techa River populations to estimate in utero and postnatal haemopoietic tissue doses from ingested strontium isotopes

International Nuclear Information System (INIS)

Shagina, Natalia; Tolstykh, Evgenia; Degteva, Marina; Fell, Tim; Harrison, John

2008-01-01

validated using data on 90 Sr in humans compiled at the Urals Research Center for Radiation Medicine. The models will be used to provide best estimates of doses resulting from ingestion of Sr isotopes as a result of the Techa River contamination, an essential prerequisite to analyses of health risks from protracted low-level exposure of this population. (author)

Development of internal dose calculation programing via food ingestion

International Nuclear Information System (INIS)

Kim, H. J.; Lee, W. K.; Lee, M. S.

1998-01-01

Most of dose for public via ingestion pathway is calculating for considering several pathways; which start from radioactive material released from a nuclear power plant to diffusion and migration. But in order to model these complicate pathways mathematically, some assumptions are essential and lots of input data related with pathways are demanded. Since there is uncertainty related with environment in these assumptions and input data, the accuracy of dose calculating result is not reliable. To reduce, therefore, these uncertain assumptions and inputs, this paper presents exposure dose calculating method using the activity of environmental sample detected in any pathway. Application of dose calculation is aim at peoples around KORI nuclear power plant and the value that is used to dose conversion factor recommended in ICRP Publ. 60

RSAC-6, Gamma doses, inhalation and ingestion doses, fission products inventory after fission products release

International Nuclear Information System (INIS)

Wenzel, Douglas R.; Schrader, Brad J.

2007-01-01

1 - Description of program or function: RSAC-6 is the latest version of the program RSAC (Radiological Safety Analysis Computer Program). It calculates the consequences of a release of radionuclides to the atmosphere. Using a personal computer, a user can generate a fission product inventory; decay and in-grow the inventory during transport through processes, facilities, and the environment; model the downwind dispersion of the activity; and calculate doses to downwind individuals. Internal dose from the inhalation and ingestion pathways is calculated. External dose from ground surface and plume gamma pathways is calculated. New and exciting updates to the program include the ability to evaluate a release to an enclosed room, resuspension of deposited activity and evaluation of a release up to 1 meter from the release point. Enhanced tools are included for dry deposition, building wake, occupancy factors, respirable fraction, AMAD adjustment, updated and enhanced radionuclide inventory and inclusion of the dose-conversion factors from FOR 11 and 12. 2 - Methods: RSAC6 calculates meteorological dispersion in the atmosphere using Gaussian plume diffusion for Pasquill-Gifford, Hilmeier-Gifford and Markee models. A unique capability is the ability to model Class F fumigation conditions, the meteorological condition that causes the highest ground level concentrations from an elevated release. Doses may be calculated for various pathways including inhalation, ingestion, ground surface, air immersion, water immersion pathways. Dose calculations may be made for either acute or chronic releases. Internal doses (inhalation and ingestion) are calculated using the ICRP-30 model with dose conversion factors from FOR 11. External factors are calculated using FOR 12. 3 - Unusual Features: RSAC6 calculates complete progeny in-growth and decay during all accident phases. The calculation of fission product inventories in particularly useful in the analysis of accidents where the

Website application for calculating cesium-137 ingestion doses from consumption of locally grown foods in the Marshall Islands

International Nuclear Information System (INIS)

Kehl, S.R.; Hamilton, T.F.; Simpson, A.E.; Freitas, G.D.

2013-01-01

Fallout deposition from the US nuclear weapons test program at Bikini and Enewetak Atolls (1946-1958) resulted in widespread nuclear fallout contamination of the northern Marshall Islands. About 85-90 % of the nuclear test-related dose delivered to resident populations is derived from ingestion of cesium-137 ( 137 Cs) contained in locally grown tree-crop food products. The Lawrence Livermore National Laboratory has developed a series of interactive internet applications to provide the public with an open access platform to learn more about radiological conditions in the Marshall Islands. The ingestion dose calculator application described here is one such feature whereby users can calculate hypothetical ingestion doses from 137 Cs based on interactive user input matched to environmental data on the activity concentration of 137 Cs contained in food plants such as coconut, breadfruit, Pandanus, and arrowroot. Users are asked to enter a date, an island and atoll location, a plant food type, and a daily intake amount (highlighted by the number of portions eaten per day in estimated gram equivalents). The application computes the user daily dose and the user equivalent annualized dose, and then compares the results with default settings based on dietary models developed for the Marshall Islands from independent dietary surveys. The default diets are based on a local plus imported food diet (or IA diet model) and an imported foods unavailable diet (or IUA diet model). Environmental data are decay corrected to the date entered by the user using an effective half-life of 137 Cs of 8.5 years (http://marshallislands.llnl.gov). (author)

Estimation of foetal brain dose from I-131 in the foetal thyroid

International Nuclear Information System (INIS)

O'Hare, N.J.; Murphy, D.; Malone, J.F.; Gilligan, P.

1997-01-01

The ingestion of I-131 by pregnant women can have consequences for the developing foetus, in particular brain function. As the foetal thyroid accumulates iodine from the twelfth week of gestation onwards, the determination of foetal brain dose resulting from such I-131 accumulation is essential. Normal dosimetric methods fail to treat the case of the foetus. Using an approximation method based on the MIRD approach, a foetal dose estimation scheme is developed to allow the determination of foetal brain dose from foetal thyroid irradiation. Dose values are obtained for the foetus based on the maternal intake of I-131. It was found that the choice of biokinetic model for the mother/foetus has a large impact on the determined dose estimate. (author)

Radon and radium concentrations in bottled waters: An estimate of ingestion doses

International Nuclear Information System (INIS)

Duenas, C.; Fernandez, M.C.; Carretero, J.; Liger, E.

1997-01-01

Concentration levels of Ra-226 and Rn-222 have been analysed in most of the bottled waters commercially available in Spain. Concentrations up to about 600 Bq/m 3 with a geometric mean of 12 Bq/m 3 were observed for Ra-226. For Rn-222 a geometric mean of 1200 Bq/m 3 with values ranging from 52000 to 1400 Bq/m 3 were measured. Doses resulting from the consumption of these waters were calculated. The effective dose equivalents due to the intake of Ra-226 present in these waters are expected to range from about 102 to 2 μSv·y -1 . Dose equivalents to the stomach due to Rn-222 intake through water consumption are estimated to reach values around 30 μSv·y -1 . (author)

Lead-210, bismuth-210, polonium-210. Natural activity, internal dosimetry, and dose factors for ingestion and inhalation

International Nuclear Information System (INIS)

Jacobi, W.

1979-02-01

Starting with a comprehensive review of the normal, natural activity of 210 Pb and 210 Po in the environment and in the tissues of the human body, a model of the activity and dose distributions of this nuclides in the human body is developed. Dose factors for ingestion with food and for inhalation are derived from this model, related to the intake rate unit. This 'natural exposure model' can be used for an estimation of the population exposure due to normal natural radiation as well as to man-made sourcess of these nuclides, e.g. coal-fired power plants. (orig.) [de

Dose calculation for 40K ingestion in samples of beans using spectrometry and MCNP

International Nuclear Information System (INIS)

Garcez, R.W.D.; Lopes, J.M.; Silva, A.X.; Domingues, A.M.; Lima, M.A.F.

2014-01-01

A method based on gamma spectroscopy and on the use of voxel phantoms to calculate dose due to ingestion of 40 K contained in bean samples are presented in this work. To quantify the activity of radionuclide, HPGe detector was used and the data entered in the input file of MCNP code. The highest value of equivalent dose was 7.83 μSv.y -1 in the stomach for white beans, whose activity 452.4 Bq.Kg -1 was the highest of the five analyzed. The tool proved to be appropriate when you want to calculate the dose in organs due to ingestion of food. (author)

Estimation of the committed radiation dose resulting from gamma radionuclides ingested with food

International Nuclear Information System (INIS)

Piotr Godyn; Agnieszka Dolhanczuk-Srodka; Zbigniew Ziembik; Ewa Moliszewska

2014-01-01

The objective of the study was to estimate the value of the radiation dose absorbed in consequence of consumption of popular food products for individual age groups. Potatoes, corn and sugar beet were selected for the study. Edible parts of these plants were collected in experimental fields of the KWS Lochow Polska Sp. z o.o. seeding company in Kondratowice (Poland). On the basis of the obtained study results, it can be stated that in consequence of consumption of the selected food products, people may receive increased doses from both natural and artificial radioactive isotopes. The doses calculated for several age groups do not show any health hazards in consequence of consumption of the tested food. One of the determined radionuclides was 137 Cs; however, its presence in the absorbed dose is lower than the doses from natural radioactive isotopes, in particular 40 K. (author)

Dose-Response of Sodium Bicarbonate Ingestion Highlights Individuality in Time Course of Blood Analyte Responses.

Science.gov (United States)

Jones, Rebecca Louise; Stellingwerff, Trent; Artioli, Guilherme Giannini; Saunders, Bryan; Cooper, Simon; Sale, Craig

2016-10-01

To defend against hydrogen cation accumulation and muscle fatigue during exercise, sodium bicarbonate (NaHCO 3 ) ingestion is commonplace. The individualized dose-response relationship between NaHCO 3 ingestion and blood biochemistry is unclear. The present study investigated the bicarbonate, pH, base excess and sodium responses to NaHCO 3 ingestion. Sixteen healthy males (23 ± 2 years; 78.6 ± 15.1 kg) attended three randomized order-balanced, nonblinded sessions, ingesting a single dose of either 0.1, 0.2 or 0.3 g·kg -1 BM of NaHCO 3 (Intralabs, UK). Fingertip capillary blood was obtained at baseline and every 10 min for 1 hr, then every 15 min for a further 2 hr. There was a significant main effect of both time and condition for all assessed blood analytes (p ≤ .001). Blood analyte responses were significantly lower following 0.1 g·kg -1 BM compared with 0.2 g·kg -1 BM; bicarbonate concentrations and base excess were highest following ingestion of 0.3 g·kg -1 BM (p ≤ .01). Bicarbonate concentrations and pH significantly increased from baseline following all doses; the higher the dose the greater the increase. Large interindividual variability was shown in the magnitude of the increase in bicarbonate concentrations following each dose (+2.0-5; +5.1-8.1; and +6.0-12.3 mmol·L -1 for 0.1, 0.2 and 0.3 g·kg -1 BM) and in the range of time to peak concentrations (30-150; 40-165; and 75-180 min for 0.1, 0.2 and 0.3 g·kg -1 BM). The variability in bicarbonate responses was not affected by normalization to body mass. These results challenge current practices relating to NaHCO 3 supplementation and clearly show the need for athletes to individualize their ingestion protocol and trial varying dosages before competition.

Intercomparison of iodine thyroid doses estimated for people living in urban and rural environments

International Nuclear Information System (INIS)

Voigt, G.

2000-01-01

The radioecological model ECOSYS, developed in GSF-Institut fuer Strahlenschutz has been applied to calculate thyroid doses to the population due to I-131 exposures after the Chernobyl accident. The main contribution to the thyroid doses calculated is given by the consumption of milk and vegetables. Results are presented taking into account the different activity concentrations measured in milk of private family cows and mixed collective milk of a creamery in upper Bavaria, as well as different consumption behaviour of children and adults in rural and urban areas. Thyroid doses due to different milk consumption habits and a different milk origin in adults living in urban environments are estimated to be up to 12 times, in children up to 3 times lower than those estimated for rural environments. The dose contribution by vegetables, however, in any case exceeded the one by milk because of the high intake rates for the case investigated here. These values, however, may be overestimates for vegetables and have a very high uncertainty. For adults total thyroid dose by ingestion was higher in rural areas by a factor of 1.4, for children at the age of 10 years, total thyroid dose by ingestion was 1.5 times higher in urban environments for the conditions described here. (author)

Ingestion dose from 210Po due to the consumption of packaged drinking water

International Nuclear Information System (INIS)

Nair, Madhu G.; Rao, D.D.; Sreejith, Sathyapriya R.; Sarka, P.K.

2013-01-01

Humans are chronically exposed to naturally occurring radionuclides from uranium and thorium series via inhalation and ingestion. With increased interest in radiological assessment a study was taken up for assessing natural radioactivity in drinking water. Drinking water is an important route of intake of naturally occurring 210 Po. 210 Po being a very important radionuclide from Uranium series with high specific activity causes significant internal dose. In our study 210 Po in PDW was concentrated with calcium phosphate and spontaneously deposited onto silver planchette and subsequently measured by alpha spectrometry. The concentration of 210 Po in the bottled water ranged from 0.11 mBq.l -1 to 2.9 mBq.l -1 . The highest concentration was observed in that sample that was reportedly sourced from mountain regions. Based on the concentration of 210 Po in each water sample, the annual intake rate (1.68L/d), and the Dose Coefficient (1.2 X 10 -6 Vs./Bq) recommended by the International Commission on Radiological Protection (ICRP, 1996), the annual committed effective doses to the adult population was estimated. The annual effective doses ranged between 0.10-2.16 μSv/yr. (author)

Estimation of environmental transfer of plutonium and the dose to man

International Nuclear Information System (INIS)

1981-09-01

The need to examine the behaviour of individual radionuclides in the environment is stressed. Sometimes unique pathways of exposure exist and more specialized methods of dose estimation could be considered. The toxicity of the alpha emitting plutonium isotopes is of concern and their long half-lives lead to persistence in the environment and long-term potential for exposing man. Some formulas are therefore presented for making preliminary estimates of environmental transfer and dose for the radioisotopes of the element plutonium. Exposure of man to plutonium in the environment may occur by inhalation or ingestion - the inhalation and ingestion intake rates for which specific pathways have been considered are listed. The primary pathway to man is the inhalation intake; the most important ingestion intake is the consumption of plant foods due to the greater concentration achieved and the higher consumption rates of these foods. Also discussed is plutonium in the nuclear fuel cycle, the release of plutonium from current nuclear installations, the occurrence of plutonium from weapons fallout, airborne releases of plutonium (concentration in the air, deposition rate, resuspension, transfer to plants - foliar and root uptake - transfer to milk, etc.), liquid release (concentration in water, transfer to drinking water, to fish, to plants by irrigation, to milk, to meat). The importance of the release situation and local environment conditions including land and water utilization, population factors and habits for any further investigation is pointed out

Ingestion dose from 238U, 232Th, 226Ra, 40K and 137CS in cereals, pulses and drinking water to adult population in a high background radiation area, Odisha (India)

International Nuclear Information System (INIS)

Lenka, P.; Sahoo, S. K.; Mohapatra, S.; Patra, A. C.; Dubey, J. S.; Vidyasagar, D.; Tripathi, R. M.; Puranik, V. D.

2013-01-01

A natural high background radiation area is located in Chhatrapur, Odisha in the eastern part of India. The inhabitants of this area are exposed to external radiation levels higher than the global average background values, due to the presence of uranium, thorium and its decay products in the monazite sands bearing placer deposits in its beaches. The concentrations of 232 Th, 238 U, 226 Ra, 40 K and 137 Cs were determined in cereals (rice and wheat), pulses and drinking water consumed by the population residing around this region and the corresponding annual ingestion dose was calculated. The annual ingestion doses from cereals, pulses and drinking water varied in the range of 109.4-936.8, 10.2-307.5 and 0.5-2.8 μSv y -1 , respectively. The estimated total annual average effective dose due to the ingestion of these radionuclides in cereals, pulses and drinking water was 530 μSv y -1 . The ingestion dose from cereals was the highest mainly due to a high consumption rate. The highest contribution of dose was found to be from 226 Ra for cereals and drinking water and 40 K was the major dose contributor from the intake of pulses. The contribution of man-made radionuclide 137 Cs to the total dose was found to be minimum. 226 Ra was found to be the largest contributor to ingestion dose from all sources. (authors)

A kinematic model to estimate effective dose of radioactive substances in a human body

Science.gov (United States)

Sasaki, S.; Yamada, T.

2013-05-01

The great earthquake occurred in the north-east area in Japan in March 11, 2011. Facility system to control Fukushima Daiichi nuclear power station was completely destroyed by the following giant tsunami. From the damaged reactor containment vessels, an amount of radioactive substances had leaked and diffused in the vicinity of this station. Radiological internal exposure became a serious social issue both in Japan and all over the world. The present study provides an easily understandable, kinematic-based model to estimate the effective dose of radioactive substances in a human body by simplifying the complicated mechanism of metabolism. International Commission on Radiological Protection (ICRP) has developed a sophisticated model, which is well-known as a standard method to calculate the effective dose for radiological protection. However, owing to that ICRP method is fine, it is rather difficult for non-professional people of radiology to gasp the whole images of the movement and the influences of radioactive substances in a human body. Therefore, in the present paper we propose a newly-derived and easily-understandable model to estimate the effective dose. The present method is very similar with the traditional and conventional tank model in hydrology. Ingestion flux of radioactive substances corresponds to rain intensity and the storage of radioactive substances to the water storage in a basin in runoff analysis. The key of the present method is to estimate the energy radiated in the radioactive nuclear disintegration of an atom by using classical theory of β decay and special relativity for various kinds of radioactive atoms. The parameters used in this model are only physical half-time and biological half-time, and there are no operational parameters or coefficients to adjust our theoretical runoff to ICRP. Figure shows the time-varying effective dose with ingestion duration, and we can confirm the validity of our model. The time-varying effective dose with

Estimation of absorbed dose in cell nuclei due to DNA-bound /sup 3/H

Energy Technology Data Exchange (ETDEWEB)

Saito, M; Ishida, M R; Streffer, C; Molls, M

1985-04-01

The average absorbed dose due to DNA-bound /sup 3/H in a cell nucleus was estimated by a Monte Carlo simulation for a model nucleus which was assumed to be spheroidal. The volume of the cell nucleus was the major dose-determining factor for cell nuclei which have the same DNA content and the same specific activity of DNA. This result was applied to estimating the accumulated dose in the cell nuclei of organs of young mice born from mother mice which ingested /sup 3/H-thymidine with drinking water during pregnancy. The values of dose-modifying factors for the accumulated dose due to DNA-bound /sup 3/H compared to the dose due to an assumed homogenous distribution of /sup 3/H in organ were found to be between about 2 and 6 for the various organs.

An analysis of uncertainty and of dependence on season of year of ingestion population dose arising from design basis accidents in advanced thermal reactors

International Nuclear Information System (INIS)

Nair, S.; Ponting, A.C.

1985-03-01

The results of a detailed study of ingestion collective dose from five limiting PWR design basis releases are presented, the PWR being chosen as being typical of an advanced thermal reactor for which source terms are readily available. The ingestion collective dose was calculated for a range of wind direction/weather scenarios for releases from a typical U.K. rural and a U.K. semi-urban site and scenarios identified where the ingestion pathway was of potential significance. The dependence of the ingestion collective dose for these cases on the season of year when the release occurs was investigated. An analysis was carried out of the uncertainty in the ''worst case'' ingestion calculations arising from uncertainties in foodchain input parameters. An efficient but comprehensive set of dynamic foodchain computer models was produced and the literature surveyed to produce probability distribution functions (PDF's) for all relevant independent input data items. These were used to produce output PDF's for food contamination levels and for ingestion collective dose from the five releases. Finally, the study has highlighted several areas central to ingestion collective dose assessments where the available data are inadequate. This led to the formulation of a set of future research requirements which will need to be met both to obtain a better fundamental understanding of foodchain transfer and to reduce uncertainties in ingestion collective dose assessments. (author)

Annual dose of Taiwanese from the ingestion of 210Po in oysters.

Science.gov (United States)

Lee, Hsiu-wei; Wang, Jeng-Jong

2013-03-01

Oysters around the coast of Taiwan were collected, dried, spiked with a (209)Po tracer for yield, digested with concentrated HNO(3) and H(2)O(2), and finally dissolved in 0.5 N HCl. The polonium was then spontaneously deposited onto a silver disc, and the activity of (210)Po was measured using an alpha spectrum analyzer equipped with a silicon barrier detector. Meanwhile, the internal effective dose of (210)Po coming from the intake of oysters by Taiwanese was evaluated. The results of the present study indicate that (210)Po average activity concentrations ranged from 23.4 ± 0.4 to 126 ± 94 Bq kg(-1) of fresh oysters. The oysters coming from Penghu island and Kinmen island regions contain higher concentrations of (210)Po in comparison with oysters from other regions of Taiwan. The value of (210)Po weighted average activity concentrations for all oyster samples studied is 25.9 Bq kg(-1). The annual effective dose of Taiwanese due to the ingestion of (210)Po in oysters was estimated to be 4.1 × 10(-2) mSv y(-1). Copyright © 2013. Published by Elsevier Ltd.

Polonium-210 and lead-210 in food and tobacco products: a review of parameters and an estimate of potential exposure and dose

Energy Technology Data Exchange (ETDEWEB)

Watson, A.P.

1983-07-01

Food-chain transport of Pb-210 and Po-210 from soil to edible plant parts and from animal feed to meat and milk were evaluated from a review of literature. The degree of transfer was characterized by estimating concentration factors (unweighted arithmetic means) as well as the transfer coefficients B/sub v/, B/sub r/ (unweighted geometric means, f/sub m/ and f/sub f/ (unweighted arithmetic means). Global dietary intake of Pb-210 and Po-210 was also summarized, and 50-year dose estimates to target organs calculated. The greatest estimated ingestion doses were those to populations with large dietary complements of animal protein in the form of seafood (Japan) or caribou/reindeer muscle and organ meats (Arctic Eskimos and Lapps). The magnitude of this latter source illustrates the importance of simple food chains in generating significant exposures to populations dependent upon them. The origin and magnitude of inhalation exposure and dose from tobacco products was also assessed. For the majority of internal organs evaluated, the dose resulting from smoking commercially available tobacco products is comparable to or greater than the dose estimates for ingestion of naturally occurring dietary Pb-210 and Po-210.

Polonium-210 and lead-210 in food and tobacco products: a review of parameters and an estimate of potential exposure and dose

International Nuclear Information System (INIS)

Watson, A.P.

1983-07-01

Food-chain transport of Pb-210 and Po-210 from soil to edible plant parts and from animal feed to meat and milk were evaluated from a review of literature. The degree of transfer was characterized by estimating concentration factors (unweighted arithmetic means) as well as the transfer coefficients B/sub v/, B/sub r/ (unweighted geometric means, f/sub m/ and f/sub f/ (unweighted arithmetic means). Global dietary intake of Pb-210 and Po-210 was also summarized, and 50-year dose estimates to target organs calculated. The greatest estimated ingestion doses were those to populations with large dietary complements of animal protein in the form of seafood (Japan) or caribou/reindeer muscle and organ meats (Arctic Eskimos and Lapps). The magnitude of this latter source illustrates the importance of simple food chains in generating significant exposures to populations dependent upon them. The origin and magnitude of inhalation exposure and dose from tobacco products was also assessed. For the majority of internal organs evaluated, the dose resulting from smoking commercially available tobacco products is comparable to or greater than the dose estimates for ingestion of naturally occurring dietary Pb-210 and Po-210

Spatial distribution of uranium and basic water quality parameter in the capital of Bihar and consequent ingestion dose.

Science.gov (United States)

Kumar, Deepak; Singh, Anshuman; Jha, Rishi Kumar

2018-04-21

Investigation of presence of Uranium (U) in groundwater/drinking water is an active are of research due to its chemical and radiological toxicity as well as long-term health effects. The current study had the objective of estimating U as a naturally occurring radioactive element in groundwater samples and assessment of ingestion dose, when groundwater is the source of drinking water. The random sampling method was chosen for the collection of samples based on population density. The estimation of U was done using LED fluorimeter. Statistical tools were applied to analyze the data and its spatial distribution. The U concentrations in three blocks of urban Patna were well below the permissible limits suggested by different health agencies of the world. A correlation test was performed to analyze the association of U with other physiochemical parameters of water samples. It was found that the sulfate, chloride, calcium, hardness, alkalinity, TDS, salinity, and ORP were positively correlated, whereas fluoride, phosphate, magnesium, dissolved oxygen, and pH were negatively correlated with U concentrations. The ingestion dose due to U, occurring in groundwater, was found to vary from 0.2-27.0 μSv y -1 with a mean of 4.2 μSv y - 1 , which was well below the recommended limit of 0.1 mSv (WHO WHO Chron 38:104-108, 2012).Therefore, the water in this region is fit for drinking purposes.

Evaluation of skin and ingestion exposure pathways

Energy Technology Data Exchange (ETDEWEB)

Aaberg, Rosanne [Pacific Northwest Laboratory, Richland, WA (United States); Logsdon, Joe E [United States Environmental Protection Agency, Office of Radiation Programs, Washington, DC (United States)

1989-06-01

After a nuclear accident when there has been a release of radionuclides into the atmosphere with consequential deposition on the ground, decisions are necessary on whether protective action guides should be implemented. In order to do this, several pathways for radiation exposure must be evaluated to determine the projected dose to individuals. The objective of this study, conducted by Pacific Northwest Laboratories for the U.S. Environmental Protection Agency, is to provide background information on exposure pathways for use in the development of Protective Action Guides. The relative importance of three exposure pathways that are usually considered to be unimportant compared to other pathways expected to control relocation decisions following a nuclear power plant accident is evaluated. The three pathways are the skin dose from contact with radionuclides transferred from the ground, the skin dose from radionuclides on the ground surface, and ingestion of radionuclides transferred directly to the mouth from the hands or other contaminated surfaces. Ingestion of contaminated food is not included in this evaluation, except for situations where the food is contaminated as a result of actions by the person who consumes the food (e.g., transfer of contamination from hands to food). Estimates of skin and ingestion doses are based on a source term with a radionuclide mix predicted for an SST2-type nuclear accident in an area where the first year reference whole-body dose equivalent from whole body external exposure to gamma radiation plus the committed effective dose equivalent from inhalation of resuspended radionuclides is 1 rem. Appendixes have been included to allow the reader to examine dose factor calculations, source-term data, and quantification of contact and ingestion parameters in more detail.

Evaluation of skin and ingestion exposure pathways

International Nuclear Information System (INIS)

Aaberg, Rosanne; Logsdon, Joe E.

1989-06-01

After a nuclear accident when there has been a release of radionuclides into the atmosphere with consequential deposition on the ground, decisions are necessary on whether protective action guides should be implemented. In order to do this, several pathways for radiation exposure must be evaluated to determine the projected dose to individuals. The objective of this study, conducted by Pacific Northwest Laboratories for the U.S. Environmental Protection Agency, is to provide background information on exposure pathways for use in the development of Protective Action Guides. The relative importance of three exposure pathways that are usually considered to be unimportant compared to other pathways expected to control relocation decisions following a nuclear power plant accident is evaluated. The three pathways are the skin dose from contact with radionuclides transferred from the ground, the skin dose from radionuclides on the ground surface, and ingestion of radionuclides transferred directly to the mouth from the hands or other contaminated surfaces. Ingestion of contaminated food is not included in this evaluation, except for situations where the food is contaminated as a result of actions by the person who consumes the food (e.g., transfer of contamination from hands to food). Estimates of skin and ingestion doses are based on a source term with a radionuclide mix predicted for an SST2-type nuclear accident in an area where the first year reference whole-body dose equivalent from whole body external exposure to gamma radiation plus the committed effective dose equivalent from inhalation of resuspended radionuclides is 1 rem. Appendixes have been included to allow the reader to examine dose factor calculations, source-term data, and quantification of contact and ingestion parameters in more detail

Radioactivity in drilled and dug well drinking water of Ogun state Southwestern Nigeria and consequent dose estimates.

Science.gov (United States)

Ajayi, O S; Achuka, J

2009-07-01

Activity concentrations of (40)K, (226)Ra, (228)Ac and (235)U were measured in 11 dug and 9 drilled well water samples from 3 large cities in Ogun state, Southwestern Nigeria, consumed by the population living in the cities. The measurement was done using co-axial type high-purity germanium (HPGe) detector (Canberra Industries Inc.). The measured activity concentrations in the water samples ranged from 1.74 +/- 1.83 to 4.69 +/- 0.17 Bq l(-1); 2.89 +/- 0.62 to 7.79 +/- 7.22 Bq l(-1); 0.35 +/- 0.07 to 1.17 +/- 0.40 Bq l(-1) and 0.18 +/- 0.05 to 4.77 +/- 0.34 Bq l(-1) for (40)K, (226)Ra, (228)Ac and (235)U, respectively. Total annual effective dose rates from the ingestion of these radionuclides in the untreated wells were estimated using measured activity concentrations in the radionuclides and their ingested dose conversion factors. Estimated annual effective dose rates ranged from 0.04 to 6.82; 0.01 to 1.36 and 0.01 to 1.49 mSv y(-1) for age groups or =17 y, respectively. Committed dose for age group > or =17 y ranged from 8.8 x 10(-4) to 8.9 x 10(-2) Sv. The calculated annual effective dose values due to the ingestion of (226)Ra in the Awujale, Ake, Saboab, Alagbon, Alapora and Totoro samples exceeded International Commission on Radiological Protection limit of 1.0 mSv y(-1) for individual public exposure. These wells are recommended for treatment that would remove radium from their waters.

Radioactivity in drilled and dug well drinking water of Ogun state Southwestern Nigeria and consequent dose estimates

International Nuclear Information System (INIS)

Ajayi, O. S.; Achuka, J.

2009-01-01

Activity concentrations of 40 K, 226 Ra, 228 Ac and 235 U were measured in 11 dug and 9 drilled well water samples from 3 large cities in Ogun state, Southwestern Nigeria, consumed by the population living in the cities. The measurement was done using co-axial type high-purity germanium (HPGe) detector (Canberra Industries Inc.). The measured activity concentrations in the water samples ranged from 1.74 ± 1.83 to 4.69 ± 0.17 Bq l -1 ; 2.89 ± 0.62 to 7.79 ± 7.22 Bq l -1 ; 0.35 ± 0.07 to 1.17 ± 0.40 Bq l -1 and 0.18 ± 0.05 to 4.77 ± 0.34 Bq l -1 for 40 K, 226 Ra, 228 Ac and 235 U, respectively. Total annual effective dose rates from the ingestion of these radionuclides in the untreated wells were estimated using measured activity concentrations in the radionuclides and their ingested dose conversion factors. Estimated annual effective dose rates ranged from 0.04 to 6.82; 0.01 to 1.36 and 0.01 to 1.49 mSv y -1 for age groups -4 to 8.9 x 10 -2 Sv. The calculated annual effective dose values due to the ingestion of 226 Ra in the Awujale, Ake, Saboab, Alagbon, Alapora and Totoro samples exceeded International Commission on Radiological Protection limit of 1.0 mSv y -1 for individual public exposure. These wells are recommended for treatment that would remove radium from their waters. (authors)

The impact of food movement between production and consumption on ingestion doses

International Nuclear Information System (INIS)

Haywood, S.M.; Smith, J.; Walmsley, A.

1991-01-01

A useful endpoint of accident consequence assessment codes is the distribution of doses among the population. To produce this information for doses arising from ingestion, data are needed on the distribution of food between the point of production and the point of consumption. This paper describes the results of a preliminary investigation of the broad patterns of food distribution in the UK for six basic categories of food. The food categories considered were fresh milk, beef, mutton/lamb, grain, root crops and green vegetables. In the course of the investigation a wide range of individuals and organisations involved in food production, distribution and marketing were approached. The extent and quality of the information received varied with the foodstuff. This information was then supplemented with data derived from agricultural and population grids which indicated the patterns of supply and demand for each food category. For the purposes of the study the UK was subdivided into 9 regions, and the percentage of food produced in each source region that is consumed in each target region was then estimated for each food category. Although the data obtained were not detailed, they were sufficient to enable scoping calculations of the likely significance of food distribution patterns to be performed. The results of these calculations are discussed

Uncertainty and variability in updated estimates of potential dose and risk at a US Nuclear Test Site - Bikini Atoll

International Nuclear Information System (INIS)

Bogen, K.T.; Conrado, C.L.; Robison, W.L.

1997-01-01

Uncertainty and interindividual variability were assessed in estimated doses for a rehabilitation scenario for Bikini Island at Bikini Atoll, in which the top 40 cm of soil would be removed in the housing and village area, and the rest of the island would be treated with potassium fertilizer, prior to an assumed resettlement date of 1999. Doses were estimated for ingested 137 Cs and 90 Sr, external gamma-exposure, and inhalation+ingestion of 241 Am + 239+240 Pu. Two dietary scenarios were considered: imported foods are available (IA); imported foods are unavailable with only local foods consumed (IUA). After ∼5 y of Bikini residence under either IA or IUA assumptions, upper and lower 95% confidence limits on interindividual variability in calculated dose were estimated to lie within a ∼threefold factor of its in population-average value; upper and lower 95% confidence limits on uncertainty in calculated dose were estimated to lie within a ∼twofold factor of its expected value. For reference, the expected values of population-average dose at age 70 y were estimated to be 16 and 52 mSv under IA and IUA dietary assumptions, respectively. Assuming that 200 Bikini resettlers would be exposed to local foods (under both IA and IUA assumptions), the maximum 1-y dose received by any Bikini resident is most likely to be approximately 2 and 8 mSv under the IA and IUA assumptions, respectively. Under the most likely dietary scenario, involving access to imported foods, this analysis indicates that it is most likely that no additional cancer fatalities (above those normally expected) would arise from the increased radiation exposures considered. 33 refs., 4 figs., 4 tabs

ACRO - a computer program for calculating organ doses from acute or chronic inhalation and ingestion of radionuclides

International Nuclear Information System (INIS)

Hirayama, Akio; Kishimoto, Yoichiro; Shinohara, Kunihiko.

1978-01-01

The computer program ACRO has been developed to calculate organ doses from acute or chronic inhalation and ingestion of radionuclides. The ICRP Task Group Lung Model (TGLM) was used for inhalation model, and a simple one-compartment model for ingestion. This program is written in FORTRAN IV, and can be executed with storage requirements of about 260 K bytes. (auth.)

Ladtap XL Version 2017: A Spreadsheet For Estimating Dose Resulting From Aqueous Releases

Energy Technology Data Exchange (ETDEWEB)

Minter, K. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Jannik, T. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

2017-06-15

LADTAP XL© is an EXCEL© spreadsheet used to estimate dose to offsite individuals and populations resulting from routine and accidental releases of radioactive materials to the Savannah River. LADTAP XL© contains two worksheets: LADTAP and IRRIDOSE. The LADTAP worksheet estimates dose for environmental pathways including external exposure resulting from recreational activities on the Savannah River and internal exposure resulting from ingestion of water, fish, and invertebrates originating from the Savannah River. IRRIDOSE estimates offsite dose to individuals and populations from irrigation of foodstuffs with contaminated water from the Savannah River. In 2004, a complete description of the LADTAP XL© code and an associated user’s manual was documented in LADTAP XL©: A Spreadsheet for Estimating Dose Resulting from Aqueous Release (WSRC-TR-2004-00059) and revised input parameters, dose coefficients, and radionuclide decay constants were incorporated into LADTAP XL© Version 2013 (SRNL-STI-2011-00238). LADTAP XL© Version 2017 is a slight modification to Version 2013 with minor changes made for more user-friendly parameter inputs and organization, updates in the time conversion factors used within the dose calculations, and fixed an issue with the expected time build-up parameter referenced within the population shoreline dose calculations. This manual has been produced to update the code description, verification of the models, and provide an updated user’s manual. LADTAP XL© Version 2017 has been verified by Minter (2017) and is ready for use at the Savannah River Site (SRS).

AIRDOS-II computer code for estimating radiation dose to man from airborne radionuclides in areas surrouding nuclear facilities

International Nuclear Information System (INIS)

Moore, R.E.

1977-04-01

The AIRDOS-II computer code estimates individual and population doses resulting from the simultaneous atmospheric release of as many as 36 radionuclides from a nuclear facility. This report describes the meteorological and environmental models used is the code, their computer implementation, and the applicability of the code to assessments of radiological impact. Atmospheric dispersion and surface deposition of released radionuclides are estimated as a function of direction and distance from a nuclear power plant or fuel-cycle facility, and doses to man through inhalation, air immersion, exposure to contaminated ground, food ingestion, and water immersion are estimated in the surrounding area. Annual doses are estimated for total body, GI tract, bone, thyroid, lungs, muscle, kidneys, liver, spleen, testes, and ovaries. Either the annual population doses (man-rems/year) or the highest annual individual doses in the assessment area (rems/year), whichever are applicable, are summarized in output tables in several ways--by nuclides, modes of exposure, and organs. The location of the highest individual doses for each reference organ estimated for the area is specified in the output data

Assessment of committed effective dose due to the ingestion of 210Po and 210Pb in consumed Lebanese fish affected by a phosphate fertilizer plant

International Nuclear Information System (INIS)

Aoun, M.; El Samad, O.; Bou Khozam, R.; Lobinski, R.

2015-01-01

Ingestion of radionuclides through seafood intake is a one of the sources contributing to the internal effective dose in the human organism. In order to evaluate the internal exposure and potential risks due to 210 Po and 210 Pb associated with fish consumption, these radionuclides were measured in commonly consumed fish species from a clean area and an area subjected to the impact of a Lebanese phosphate fertilizer plant. The highest concentration of 210 Pb was 98.7 Bq/kg fresh weight while 210 Po activity concentrations varied from 3.6 Bq/kg to 140 Bq/kg. A supplementary radiation exposure was detected; the highest committed effective dose due to 210 Po and 210 Pb was found to be 1110 μSv/y and 450 μSv/y, respectively. Moreover, the average mortality and morbidity risks due to the fish consuming were estimated. - Highlights: • Enrichment in 210 Po and 210 Pb in fish affected by a phosphate fertilizer plant. • Significant human exposure associated with the ingestion of fish. • Estimation of potential risks due to 210 Po and 210 Pb via fish consumption

Lichen forage ingestion rates of free-roaming caribou estimated with fallout cesium-137

International Nuclear Information System (INIS)

Hanson, W.C.; Whicker, F.W.; Lipscomb, J.F.

1975-01-01

Lichen forage ingestion rates of free-roaming caribou herds in northern Alaska during 1963 to 1970 were estimated by applying a two-compartment, eight parameter cesium-137 kinetics model to measured fallout 137 Cs concentrations in lichen and caribou. Estimates for winter equilibrium periods (January to April) for each year ranged from 3.7 to 6.9 kg dry weight lichens per day for adult female caribou. Further refinement of these estimations were obtained by calculating probabilistic distributions of intake rates by stochastic processes based upon the mean and standard error intervals of the eight parameters during 1965 and 1968. A computer program generated 1,000 randomly sampled values within each of the eight parameter distributions. Results substantiate the contention that lichen forage ingestion rates by free-roaming caribou are significantly greater than previously held

Estimation of committed effective dose due to tritium in ground water in some places of Maharashtra

International Nuclear Information System (INIS)

Reddy, P.J.; Bhade, S.P.D.; Kolekar, R.V.; Singh, Rajvir; Pradeepkumar, K.S.

2014-01-01

In the present study Tritium concentration in well and bore well water samples were analyzed for the samples collected from the villages of Pune, Kolhapur and Ratnagiri. The activity concentration ranged from 0.55 - 3.66 Bq L -1 . The associated age-dependant dose from water ingestion in the study area was estimated. The effective committed dose recorded for different age classes is negligible compared to World Health Organization and U.S. Environmental Protection Agency dose guidelines. The Minimum Detectable Activity achieved was 1.5 Bq L -1 for a total counting time of 500 minutes. (author)

The Effective Dose Due to Radionuclides Intake Via Ingestion in Poland in 1986-1999

International Nuclear Information System (INIS)

Grabowski, D.; Kurowski, W.; Muszynski, W.; Rubel, B.; Swietochowska, J.

2001-01-01

Full text: One of the pathways of radiation exposure in humans is consumption of contaminated food. The composition of an average diet is diversified for various groups within the population and depends on age, sex, consumption habit and performed work. To asses the dose obtained by people due to ingestion of contaminated food, the activity of main products of Polish diet has been analysed for period 1986 - 1999. The samples of milk, meat, vegetables, fruit and cereals were collected all over the territory of Poland to determine the activity of caesium isotopes. In the first two-year after the Chernobyl accident the differences in contamination were observed in various regions. Later on the differences were less pronounced except in milk and meat. The calculation of an average annual intake of caesium isotopes was based on statistical data consumption and contamination of certain product important in daily diet. Annual intake of caesium was different among regions. Mean annual effective dose related to the ingestion of contaminated food of 137 Cs was assessed on 54μSv in 1986 and 28μSv in 1987 and of 134 Cs on 34μSv and 13μSv respectively. In next years the dose was diminishing and from 1993 the average annual effective dose from 137 Cs has been on level 6-7 μSv. (author)

Importance and variability in processes relevant to environmental tritium ingestion dose models

International Nuclear Information System (INIS)

Raskob, W.; Barry, P.

1997-01-01

The Aiken List was devised in 1990 to help decide which transport processes should be investigated experimentally so as to derive the greatest improvement in performance of environmental tritium assessment models. Each process was rated high, medium and low on each of two criteria. These were ''Importance'', which rated processes by how much each contributed to ingestion doses, and ''State of Modelling'', which rated the adequacy of the knowledge base on which models were built. Ratings, though unanimous, were, nevertheless, qualitative and subjective opinions. This paper describes how we have tried to quantify the ratings. To do this, we use, as measures of ''Importance'', sensitivities of predicted ingestion doses to changes in values of parameters in mathematical descriptions of individual processes. Measures of ''ModellinStatus'' were taken from a recently completed BIOMOVS study of HTO transport model performance and based either on by how much predicted transport by individual processes differed amongst participating modellers or by the variety of different ways that modellers chose to describe individual processes. The tritium transport model UFOTRI was used, and because environmental transport of HTO varies according to the weather at and after release time, sensitivities were measured in a sample of all conditions likely to arise in central Europe. (Author)

Derivation of ingestion dose conversion factors for the U-238 decay series

International Nuclear Information System (INIS)

Jenkins, P.H.; Nicoll, R.M.; Doty, R.L.

1978-01-01

Dose conversion factors (DCF's) for the U-238 decay series were derived for use in the assessment of potential doses to man, through several ingestion pathways, by radionuclide deposition from radioactive airborne effluents. The methodology used, although similar to that outlined in the U.S. Nuclear Regulatory Commission's Regulatory Guide 1.109, is complicated by consideration of the ingrowth of decay products. Eight ingestion pathways were considered: (1) fresh vegetables, (2) stored vegetables, (3) milk from cows that eat pasture grass, (4) milk from cows that eat stored feed, (5) goat milk - pasture grass, (6) goat milk - stored feed, (7) beef - pasture grass, and (8) beef - stored feed. Radionuclide deposition was assumed to occur for the entire operational lifetime of the facility. Because the expected operational lifetime may vary from facility to facility, DCF's were calculated for six lifetimes: 10, 15, 20, 25, 30, and 35 years. DCF's were calculated for each of 13 'parent' nuclides in the decay series, with each DCF considering the ingrowth of all subsequent nuclides in the series. The methodology used to derive the DCF's is detailed, and DCF's normalized to a deposition rate of the parent nuclide of 1 μCi m -2 s -1 are reported. (author)

The importance of ingestion rates for estimating food quality and energy intake.

Science.gov (United States)

Schülke, Oliver; Chalise, Mukesh K; Koenig, Andreas

2006-10-01

Testing ecological or socioecological models in primatology often requires estimates of individual energy intake. It is a well established fact that the nutrient content (and hence the energy content) of primate food items is highly variable. The second variable in determining primate energy intake, i.e., the ingestion rate, has often been ignored, and few studies have attempted to estimate the relative importance of the two predictors. In the present study individual ingestion rates were measured in two ecologically very different populations of Hanuman langurs (Semnopithecus entellus) at Jodhpur, India, and Ramnagar, Nepal. Protein and soluble sugar concentrations in 50 and 100 food items. respectively, were measured using standardized methods. Variation in ingestion rates (gram of dry matter per minute) was markedly greater among food items than among langur individuals in both populations, but did not differ systematically among food item categories defined according to plant part and age. General linear models (GLMs) with ingestion rate, protein, and soluble sugar content explained 40-80% of the variation in energy intake rates (kJ/min). The relative importance of ingestion rates was either similar (Ramnagar) or much greater (Jodhpur) than the role of sugar and/or protein content in determining the energy intake rates of different items. These results may impact socioecological studies of variation in individual energy budgets, investigations of food choice in relation to chemical composition or sensory characteristics, and research into habitat preferences that measures habitat quality in terms of abundance of important food sources. We suggest a definition of food quality that includes not only the amount of valuable food contents (energy, vitamins, and minerals) and the digestibility of different foods, but also the rate at which the food can be harvested and processed. Such an extended definition seems necessary because time may constrain primates when

ESTIMATION OF EXPOSURE DOSES FOR THE SAFE MANAGEMENT OF NORM WASTE DISPOSAL.

Science.gov (United States)

Jeong, Jongtae; Ko, Nak Yul; Cho, Dong-Keun; Baik, Min Hoon; Yoon, Ki-Hoon

2018-03-16

Naturally occurring radioactive materials (NORM) wastes with different radiological characteristics are generated in several industries. The appropriate options for NORM waste management including disposal options should be discussed and established based on the act and regulation guidelines. Several studies calculated the exposure dose and mass of NORM waste to be disposed in landfill site by considering the activity concentration level and exposure dose. In 2012, the Korean government promulgated an act on the safety control of NORM around living environments to protect human health and the environment. For the successful implementation of this act, we suggest a reference design for a landfill for the disposal of NORM waste. Based on this reference landfill, we estimate the maximum exposure doses and the relative impact of each pathway to exposure dose for three scenarios: a reference scenario, an ingestion pathway exclusion scenario, and a low leach rate scenario. Also, we estimate the possible quantity of NORM waste disposal into a landfill as a function of the activity concentration level of U series, Th series and 40K and two kinds of exposure dose levels, 1 and 0.3 mSv/y. The results of this study can be used to support the establishment of technical bases of the management strategy for the safe disposal of NORM waste.

Age-dependent doses to members of the public from intake of radionuclides: Pt. 5. Compilation of ingestion and inhalation dose coefficients

International Nuclear Information System (INIS)

1996-01-01

The present report is a compilation of age-dependent committed effective dose coefficients for ingestion and inhalation of radionuclides of the 31 elements covered in previous CRP Publications. The biokinetic models for adults given in ICRP Publication 30 are applied to calculate these dose coefficients, except that age-specific excretion rates are used and increased gastrointestinal absorption in infants is assurred. Changes in body mass, and tissue geometry in children are also taken into account. (UK)

Micro-segmental hair analysis for proving drug-facilitated crimes: Evidence that a victim ingested a sleeping aid, diphenhydramine, on a specific day.

Science.gov (United States)

Kuwayama, Kenji; Nariai, Maika; Miyaguchi, Hajime; Iwata, Yuko T; Kanamori, Tatsuyuki; Tsujikawa, Kenji; Yamamuro, Tadashi; Segawa, Hiroki; Abe, Hiroko; Iwase, Hirotaro; Inoue, Hiroyuki

2018-07-01

Sleeping aids are often abused in the commission of drug-facilitated crimes. Generally, there is little evidence that a victim ingested a spiked drink unknowingly because the unconscious victim cannot report the situation to the police immediately after the crime occurred. Although conventional segmental hair analysis can estimate the number of months since a targeted drug was ingested, this analysis cannot determine the specific day of ingestion. We recently developed a method of micro-segmental hair analysis using internal temporal markers (ITMs) to estimate the day of drug ingestion. This method was based on volunteer ingestion of ITMs to determine a timescale within individual hair strands, by segmenting a single hair strand at 0.4-mm intervals, corresponding to daily hair growth. This study assessed the ability of this method to estimate the day of ingestion of an over-the-counter sleeping aid, diphenhydramine, which can be easily abused. To model ingestion of a diphenhydramine-spiked drink unknowingly, each subject ingested a dose of diphenhydramine, followed by ingestion of two doses of the ITM, chlorpheniramine, 14days apart. Several hair strands were collected from each subject's scalp several weeks after the second ITM ingestion. Diphenhydramine and ITM were detected at specific regions within individual hair strands. The day of diphenhydramine ingestion was estimated from the distances between the regions and the days of ITM ingestion. The error between estimated and actual ingestion day ranged from -0.1 to 1.9days regardless of subjects and hair collection times. The total time required for micro-segmental analysis of 96 hair segments (hair length: 3.84cm) was approximately 2days and the cost was almost the same as in general drug analysis. This procedure may be applicable to the investigation of crimes facilitated by various drugs. Copyright © 2018 Elsevier B.V. All rights reserved.

Thyroid Dose Estimates for a Cohort of Belarusian Children Exposed to Radiation from the Chernobyl Accident

Science.gov (United States)

Drozdovitch, Vladimir; Minenko, Victor; Khrouch, Valeri; Leshcheva, Svetlana; Gavrilin, Yury; Khrutchinsky, Arkady; Kukhta, Tatiana; Kutsen, Semion; Luckyanov, Nickolas; Shinkarev, Sergey; Tretyakevich, Sergey; Trofimik, Sergey; Voillequé, Paul; Bouville, André

2013-01-01

The U.S. National Cancer Institute, in collaboration with the Belarusian Ministry of Health, is conducting a study of thyroid cancer and other thyroid diseases in a cohort of about 12,000 persons who were exposed to fallout from the Chernobyl accident in April 1986. The study subjects were 18 years old or younger at the time of exposure and resided in Belarus in the most contaminated areas of the Gomel and Mogilev Oblasts, as well as in the city of Minsk. All cohort members had at least one direct thyroid measurement made in April–June 1986. Individual data on residential history, consumption of milk, milk products and leafy vegetables as well as administration of stable iodine were collected for all cohort members by means of personal interviews conducted between 1996 and 2007. Based on the estimated 131I activities in the thyroids, which were derived from the direct thyroid measurements, and on the responses to the questionnaires, individual thyroid doses from intakes of 131I were reconstructed for all cohort members. In addition, radiation doses to the thyroid were estimated for the following minor exposure pathways: (a) intake of short-lived 132I, 133I and 132Te by inhalation and ingestion; (b) external irradiation from radionuclides deposited on the ground; and (c) ingestion intake of 134Cs and 137Cs. Intake of 131I was the major pathway for thyroid exposure; its mean contribution to the thyroid dose was 92%. The thyroid doses from 131I intakes varied from 0.5 mGy to almost 33 Gy; the mean was estimated to be 0.58 Gy, while the median was 0.23 Gy. The reconstructed doses are being used to evaluate the risk of thyroid cancer and other thyroid diseases in the cohort. PMID:23560632

An assessment of the 210Po ingestion dose due to the consumption of agricultural, marine, fresh water and forest foodstuffs in Gudalore (India)

International Nuclear Information System (INIS)

Sivakumar, R.

2014-01-01

The activity concentration of 210 Po in cereals, pulses, food materials of animal origin, vegetables and spices collected from Gudalore (India) has been estimated by radiochemical method. The activity concentration of 210 Po in cereals is found to vary from 124 to 604 mBq kg −1 . Raw rice registered the highest mean activity 504 ± 61 mBq kg −1 . In pulses 210 Po activity concentration varies from 42 to 320 mBq kg −1 and the highest activity is found in black lentil with the average value of 172 ± 38 mBq kg −1 . Leafy vegetables registered the highest 210 Po activity concentration (662–7336 mBq kg −1 ) and are followed by tuber vegetables (390–1269 mBq kg −1 ) and then by other vegetables (75–595 mBq kg −1 ). The higher concentration of 210 Po observed in leafy vegetables may be attributed to the dry deposition of 210 Po and other daughter products of 222 Rn on large leaf surfaces from the air. Among animal products fish of marine origin registered the highest 210 Po activity concentration 36,850–48,964 mBq kg −1 . The mean 210 Po activity concentration in coffee has been estimated as 7500 mBq kg −1 . The activity concentration of 210 Po in leaf and bark of tree Cinnamom zeylanicum, a popular spice, is found to vary from 3500 to 11,100 mBq kg −1 and 1600–3400 mBq kg −1 . The consumption of marine and fresh water fish contribute 60.7% (506.1 μSv y −1 ) to the total ingestion dose received. Cereals being consumed in a large scale, contribute 23.4% (194.9 μSv y −1 ) of the total ingestion dose received. The contribution from spices and leafy vegetables consumed is 5.8% (48.1 μSv y −1 ) and 6.5% (54.3 μSv y −1 ), respectively. The remaining 3.6% (30.0 μSv y −1 ) contribution to the total ingestion dose comes from other food materials and vegetables. - Highlights: • The activity concentration of 210 Po in different spices grown in the study area has been estimated. • The study

Estimative of alpha radiation dose due to natural concentration of Ra-226 in waters from Pocos de Caldas

International Nuclear Information System (INIS)

Sigaud, G.M.

1979-01-01

A dosimetric model for calculating the annual dose equivalent for an individual and the annual collective dose equivalent from 226 Ra is developed. This model is applied to the measured concentrations of 226 Ra in waters of the hydro graphic basins of the Pocos de Caldas plateau, using the pathways of drinking water and ingestion of food grown in irrigated fields. A linear model for simulating potential 226 Ra contamination of the waters of the region is also applied, and the doses from these contaminations are estimated using the dosimetric model developed. (author)

Bioaccessibility of Fukushima-Accident-Derived Cs in Soils and the Contribution of Soil Ingestion to Radiation Doses in Children.

Science.gov (United States)

Takahara, Shogo; Ikegami, Maiko; Yoneda, Minoru; Kondo, Hitoshi; Ishizaki, Azusa; Iijima, Masashi; Shimada, Yoko; Matsui, Yasuto

2017-07-01

Ingestion of contaminated soil is one potential internal exposure pathway in areas contaminated by the Fukushima Daiichi Nuclear Power Plant accident. Doses from this pathway can be overestimated if the availability of radioactive nuclides in soils for the gastrointestinal tract is not considered. The concept of bioaccessibility has been adopted to evaluate this availability based on in vitro tests. This study evaluated the bioaccessibility of radioactive cesium from soils via the physiologically-based extraction test (PBET) and the extractability of those via an extraction test with 1 mol/L of hydrochloric acid (HCl). The bioaccessibility obtained in the PBET was 5.3% ± 1%, and the extractability in the tests with HCl was 16% ± 3%. The bioaccessibility was strongly correlated with the extractability. This result indicates the possibility that the extractability in HCl can be used as a good predictor of the bioaccessibility with PBET. In addition, we assessed the doses to children from the ingestion of soil via hand-to-mouth activity based on our PBET results using a probabilistic approach considering the spatial distribution of radioactive cesium in Date City in Fukushima Prefecture and the interindividual differences in the surveyed amounts of soil ingestion in Japan. The results of this assessment indicate that even if children were to routinely ingest a large amount of soil with relatively high contamination, the radiation doses from this pathway are negligible compared with doses from external exposure owing to deposited radionuclides in Fukushima Prefecture. © 2016 Society for Risk Analysis.

Calculation of the ingestion critical dose rate for the Goiania radioactive waste repository

International Nuclear Information System (INIS)

Passos, E.M. dos; Martin Alves, A.S. De

1994-01-01

The calculation results of the critical distance for the ingestion dose rate due to a hypothetical Cs-137 release from the Abadia de Goias repository are shown. The work is based on the pathway repository-aquifer-well food chain. The calculations were based upon analytical models for the migration of radioisotopes through the aquifer and for its transfer from well water to food. (author)

Internal doses of French adult population linked to the intake of radionuclides from the decay-chains of uranium and thorium by foodstuffs ingestion

International Nuclear Information System (INIS)

Renaud, Ph.; Parache, V.; Roussel-Debet, S.

2015-01-01

This study provides the first dose assessment to the French adult population due to the intake of radionuclides from the decay chains of uranium and thorium by foodstuff ingestion (water consumption excepted). This dose varies widely with the consumption of seafood, from less than 200 μSv.y -1 for people who do not consume shellfish or crustaceans at all, to more than 2,000 μSv.y -1 for the biggest consumers (about 150 kg.y -1 according to specific dietary surveys carried out along the French seaside). For moderate consumers of seafood (around 4.6 kg.y -1 ), who probably represent a major part of the population, this internal dose would be around 330 μSv.y -1 . This variable consumption of seafood overshadows all the other causes of variability of these internal dose estimates. (authors)

Dose from Cs-137 ingestion in Italian Region in 1998-1999. A preliminary analysis of the results of a monitoring campaign

International Nuclear Information System (INIS)

Bochicchio, F.; Magnoni, M.; Agnesod, G.

2000-01-01

A measurement programme started on 1998 in order to assess the committed effective dose for all the Italian Regions due to ingestion of Cs-137. This programme was carried out within the framework of the SICRA network, which is in ad-hoc personal computer network, set up by the Ministry of Health in order to connect the regional laboratories for the control of the environmental radioactivity and the national institutes in order to allow a fast transmission and analysis of radioactivity measurement results. The programme was jointly decided and designed by the following regional and national institutes: the regional laboratories for the control of the environmental radioactivity, most of which are Regional Agencies for the Environmental Protection (ARPA); the National Agency for the Environmental Protection (ANPA); the National Institute for Prevention and Safety in Workplaces (ISPESL), the Italian National Institute of Health (ISS), the Ministry of Environment and the Ministry of Health. The following five major components of the Italian diet, which use expected to significantly contribute to the total ingestion dose, were included in the sampling protocol: milk, meat, pasta, bread, and fish. In most cases the samples were taken in big stores in order to be representative of the local consumption. The sample collection started on October 1998 and continued in 1999. The designed Minimum Detectable Activity was 0.1 Bq/kg. Most of the measured values are below the MDA so that appropriate statistical techniques are used in order to estimate the average activity concentration and dose. Regional data of food consumption are taken from the Italian National Statistic Institute, and dose conversion factor for adults is used. A minimum of 24 samples for the period October-December 1998 was asked to each Region, however, more data were sent by some Regions. Preliminary results of activity concentration measurements on 1249 samples of 1998 are the following: in 439 cases the

Methodology for assessing dose commitment to individuals and to the population from ingestion of terrestrial foods contaminated by emissions from a nuclear fuel reprocessing plant at the Savannah River Plant

International Nuclear Information System (INIS)

Ng, Y.C.; Phillips, W.A.; Ricker, Y.E.; Tandy, R.K.; Thompson, S.E.

1978-01-01

The general approach for estimating the concentrations of radionuclides in terrestrial foods and dose commitments to individuals and to the population follows procedures recommended by the U.S. Nuclear Regulatory Commission Regulatory Guide 1.109 for estimating annual doses to man from routine releases of reactor effluents (USNRC 77). These procedures evolved from the HERMES computer code (12336), which was used to assess the radiological impacts of the future development of nuclear facilities in the Upper Mississippi River Basin (11876) and in the Tennessee Valley Region. Our approach is also basically similar to the FOOD computer program for calculating radiological doses from the ingestion of terrestrial food products contaminated with radionuclides transported to fields from air and surface waters (13320). The computations for assessing terrestrial foodchain contamination and population dose are organized as a series of modules. From monthly deposition rates (or average concentrations in surface air) of radionuclides in each county we compute the following: concentrations in crops due to deposition on aerial parts; concentrations in crops due to uptake from soil via roots; total concentrations from deposition on aerial parts and root uptake; concentrations in food and feed at the time of harvest or collection; concentrations in food and feed at the time of consumption; concentrations in meat, milk, and eggs due to the ingestion of contaminated feed by livestock; intakes of radionuclides by individuals from ingestion of terrestrial foods and the resultant dosage; and intakes of radionuclides by the population and the resultant dosage. The next section describes the regional agricultural data base for the SRP site. We will then describe, in some detail, the computations for the evaluation of each module

Improving ingestion dose modelling for the ARGOS and RODOS decision support systems: A Nordic Initiative

DEFF Research Database (Denmark)

Andersson, Kasper Grann; Nielsen, Sven Poul; Thørring, Håvard

2011-01-01

A Nordic work group under the NKS-B activity PARDNOR has revised the input parameters in the ECOSYS model that is incorporated for ingestion dose modelling in the ARGOS and RODOS decision support systems. The new parameterisation takes into account recent measurement data, and targets the model f...

Natural 3H radioactivity analysis in groundwater and estimation of committed effective dose due to groundwater ingestion in Varahi and Markandeya river basins, Karnataka State, India

International Nuclear Information System (INIS)

Ravikumar, P.; Somashekar, R.K.

2011-01-01

The present study aimed at the assessment of natural tritium radioactivity in groundwater, being used for domestic and irrigation purposes in Varahi and Markandeya river basins. The study also intended to assess human health risk by estimating committed effective dose due to groundwater ingestion in the study area, taking into consideration the obtained tritium activity concentrations and annual water consumption. Tritium concentration of groundwater samples from the Varahi and Markandeya river basins were determined by liquid scintillation counting and the results laid in the range of 1.95 ± 0.25 to 11.35 ± 0.44 TU and 1.49 ± 0.75 to 9.17 ± 1.13 TU in Varahi and Markandeya river basins, respectively. Majority of the samples from Varahi (46.67%) and Markandeya (62.5%) river basins belong to modern water category aged between 5 and 10 years, while the remaining 53.33% and 37.5% of the samples from Varahi and Markandeya river basins respectively belong to sub-modern water with modern recharge, significantly influenced by precipitation and river in flowing/sea water intrusion. The effective committed dose for general public consumption considering the highest concentration value of 0.02 μSv year -1 , which is very negligible compared to EPA (0.04 mSv year -1 ), WHO (0.1 mSv year -1 ), ICRP (1.0 mSv year -1 ) and UNSCEAR (2.4 mSv year -1 ) recommended dose limits, should not mean any additional health risk for the population living nearby. (author)

Uptake and distribution of natural radioactivity in rice from soil in north and west part of peninsular malaysia for the estimation of ingestion dose to man

International Nuclear Information System (INIS)

Asaduzzaman, Kh.; Khandaker, M.U.; Amin, Y.M.; Mahat, R.

2015-01-01

Highlights: • We determine the uptake of naturally occurring radionuclides by rice from soil. • Transfer factor, effective dose and excess lifetime cancer risk have been assessed. • Evaluate the radiological impact on human body due to the radioactivity in rice. • The transfer factors for 226 Ra and 232 Th were found far beyond to IAEA default value. - Abstract: Paddy is the third most widely planted crop in Malaysia and most of the Malaysian people consume rice as their staple food. Hence, studies on the uptake of naturally occurring radionuclides by rice from soil of widely rice cultivated areas in Malaysia have been performed under normal field environments in order to evaluate various radiation hazards via rice consumption. The soil-to-rice grain transfer factors and the annual effective dose have been assessed for the natural radionuclides 226 Ra, 232 Th and 40 K. The estimated transfer factors for 226 Ra and 232 Th were found far beyond compared to the IAEA reported value for rice. Among the detected radionuclides, 40 K shows the highest transfer factor in all study locations but close to the IAEA reported range. The total effective dose obtained due to an ingestion of radionuclides via rice consumption was within the range of world average value (290 μSv y −1 ) compiled by the UNSCEAR (2000) in all study areas. On an average, the excess life time cancer risk (ELCR) values via rice consumption were found below the acceptable limit of 10 −3 for radiological risk

Estimative of the soil amount ingested by cattle in high natural radioactive region

International Nuclear Information System (INIS)

Rosa, Roosevelt; Silva, Lucia H.C.; Taddei, Maria H.T.

1997-01-01

Considering that Pocos de Caldas is a region of high natural radioactivity, where many environmental impacts have been studied, 27 samples of cattle faeces and 24 samples of local soil were collected and analyzed for Ti concentrations, during dry and rain periods. Using this element as an indicator, the percentage of soil ingestion by cattle were estimated for three management practices: confined, semi-confined and free. The results showed the management practices influence on the cattle soil ingestion percentage, and the importance of this pathway in the environmental impact assessment. (author). 7 refs., 1 tab

Agriculture-related radiation dose calculations

International Nuclear Information System (INIS)

Furr, J.M.; Mayberry, J.J.; Waite, D.A.

1987-10-01

Estimates of radiation dose to the public must be made at each stage in the identification and qualification process leading to siting a high-level nuclear waste repository. Specifically considering the ingestion pathway, this paper examines questions of reliability and adequacy of dose calculations in relation to five stages of data availability (geologic province, region, area, location, and mass balance) and three methods of calculation (population, population/food production, and food production driven). Calculations were done using the model PABLM with data for the Permian and Palo Duro Basins and the Deaf Smith County area. Extra effort expended in gathering agricultural data at succeeding environmental characterization levels does not appear justified, since dose estimates do not differ greatly; that effort would be better spent determining usage of food types that contribute most to the total dose; and that consumption rate and the air dispersion factor are critical to assessment of radiation dose via the ingestion pathway. 17 refs., 9 figs., 32 tabs

Estimation of Radionuclide Concentrations and Average Annual Committed Effective Dose due to Ingestion for the Population in the Red River Delta, Vietnam.

Science.gov (United States)

Van, Tran Thi; Bat, Luu Tam; Nhan, Dang Duc; Quang, Nguyen Hao; Cam, Bui Duy; Hung, Luu Viet

2018-02-16

Radioactivity concentrations of nuclides of the 232 Th and 238 U radioactive chains and 40 K, 90 Sr, 137 Cs, and 239+240 Pu were surveyed for raw and cooked food of the population in the Red River delta region, Vietnam, using α-, γ-spectrometry, and liquid scintillation counting techniques. The concentration of 40 K in the cooked food was the highest compared to those of other radionuclides ranging from (23 ± 5) (rice) to (347 ± 50) Bq kg -1 dw (tofu). The 210 Po concentration in the cooked food ranged from its limit of detection (LOD) of 5 mBq kg -1  dw (rice) to (4.0 ± 1.6) Bq kg -1  dw (marine bivalves). The concentrations of other nuclides of the 232 Th and 238 U chains in the food were low, ranging from LOD of 0.02 Bq kg -1  dw to (1.1 ± 0.3) Bq kg -1  dw. The activity concentrations of 90 Sr, 137 Cs, and 239+240 Pu in the food were minor compared to that of the natural radionuclides. The average annual committed effective dose to adults in the study region was estimated and it ranged from 0.24 to 0.42 mSv a -1 with an average of 0.32 mSv a -1 , out of which rice, leafy vegetable, and tofu contributed up to 16.2%, 24.4%, and 21.3%, respectively. The committed effective doses to adults due to ingestion of regular diet in the Red River delta region, Vietnam are within the range determined in other countries worldwide. This finding suggests that Vietnamese food is safe for human consumption with respect to radiation exposure.

[Evaluation of Organ Dose Estimation from Indices of CT Dose Using Dose Index Registry].

Science.gov (United States)

Iriuchijima, Akiko; Fukushima, Yasuhiro; Ogura, Akio

Direct measurement of each patient organ dose from computed tomography (CT) is not possible. Most methods to estimate patient organ dose is using Monte Carlo simulation with dedicated software. However, dedicated software is too expensive for small scale hospitals. Not every hospital can estimate organ dose with dedicated software. The purpose of this study was to evaluate the simple method of organ dose estimation using some common indices of CT dose. The Monte Carlo simulation software Radimetrics (Bayer) was used for calculating organ dose and analysis relationship between indices of CT dose and organ dose. Multidetector CT scanners were compared with those from two manufactures (LightSpeed VCT, GE Healthcare; SOMATOM Definition Flash, Siemens Healthcare). Using stored patient data from Radimetrics, the relationships between indices of CT dose and organ dose were indicated as each formula for estimating organ dose. The accuracy of estimation method of organ dose was compared with the results of Monte Carlo simulation using the Bland-Altman plots. In the results, SSDE was the feasible index for estimation organ dose in almost organs because it reflected each patient size. The differences of organ dose between estimation and simulation were within 23%. In conclusion, our estimation method of organ dose using indices of CT dose is convenient for clinical with accuracy.

Models for the evaluation of ingestion doses from the consumption of terrestrial foods following an atmospheric radioactive release

International Nuclear Information System (INIS)

Nair, S.

1984-04-01

Various methods are described which have been incorporated in the FOODWEB module of the CEGB's NECTAR environmental code and are currently being used within CEGB to assess ingestion doses from consumption of terrestrial foods following an atmospheric radioactive release. Four foodchain models which have been developed within CEGB are fully described and results of typical calculations presented. Also given are the results of a validation of the dynamic model against measured 90 Sr and 137 Cs levels in milk in the U.K. resulting from weapons fallout. Methods are also described for calculating individual and population doses from ingestion using the results of the model calculations. The population dose calculations utilise a data base describing the spatial distribution of production of a wide range of agricultural products. The development of such a data base for Great Britain is described, based on the 1972 land use and livestock census, and maps are presented for each agricultural product. (U.K.)

Radiological impact of the Chernobyl accident through ingestion in Europe. Ingestion doses determined by whole-body counting of radiocesium

International Nuclear Information System (INIS)

Inaba, Jiro

2012-01-01

Reports mainly concerning the internal exposure caused by Chernobyl Accident (CA, 1986) are discussed for reference to deal with the radiation impact on public of Fukushima Daiichi Power Plant Accident. Data of the internal exposure measured by the whole body counter are particularly noted. In adults, 1 kBq of Cs-137/body/year is equivalent to the internal exposure dose of 0.03 mSV/y. The CA released Cs-137 of total 8.5 PBq, which was then partially ingested through food to result in the internal exposure to European. For instance, in the old Soviet, the exposure was reported to amount to about 100 kBq/body (1987) of residents living in the highly contaminated area (Bryansk and others). In southern Germany like Bavaria State, the amount >1 kBq/body was recorded in 1987. In Cumbria, UK, residents had about 700 Bq of Cs-137 in June, 1986, which decreased to 450 Bq a month later. In Sami people living in Lapland area of northern Scandinavia, several tens kBq/body were found as they took the meat of reindeer of which diet was the contaminated lichen. The amount of internal Cs-137 peaked in 1987 and lowered thereafter with half lives of 1-2 years, which was thought to be partly due to various protection means conducted. The internal half life tended to elongate in people who had ingested the food harvested from such sites as difficult to get rid of the contamination like forest. Overall, the internal amount/dose of Cs-137 due to CA were at a similar level to those to the nuclear experiments in open air done in 1960s. The author, based on his experience, thinks that it can be one of relevant ways to observe the time course of the internal dose change of certain typical residents in Fukushima by measuring with the whole body counter, followed by announcement and explanation of data to the public. (T.T.)

Recovery of brodifacoum in vomitus following induction of emesis in dogs that had ingested rodenticide bait.

Science.gov (United States)

Parton, K H; Willson, E K; Collett, M G; Booth, L H

2018-01-01

To assess the benefit of inducing emesis in dogs that have ingested rodenticide bait containing brodifacoum (BDF), by determining the amount of BDF in bait recovered from the vomitus relative to the estimated amount consumed. Between 2014 and 2015 samples of vomitus from seven dogs that ingested rodenticide baits containing BDF were submitted by veterinarians in New Zealand. All seven dogs had been given apomorphine by the veterinarian and vomited within 1 hour of ingesting the bait. Some or all of the bait particles were retrieved from each sample and were analysed for concentrations of BDF using HPLC. Based on estimations of the mass of bait consumed, the concentration of BDF stated on the product label, and the estimated mass of bait in the vomitus of each dog, the amount of BDF in the vomited bait was calculated as a percentage of the amount ingested. For five dogs an estimation of the mass of bait ingested was provided by the submitting veterinarian. For these dogs the estimated percentage of BDF in the bait retrieved from the vomitus was between 10-77%. All dogs were well after discharge but only one dog returned for further testing. This dog had a normal prothrombin time 3 days after ingestion. The induction of emesis within 1 hour of ingestion can be a useful tool in reducing the exposure of dogs to a toxic dose of BDF. The BDF was not fully absorbed within 1 hour of ingestion suggesting that the early induction of emesis can remove bait containing BDF before it can be fully absorbed.

Infant doses from the transfer of radionuclides in mothers' milk

International Nuclear Information System (INIS)

Harrison, J.D.; Smith, T.J.; Phipps, A.W.

2003-01-01

Assessments of potential internal exposures of the child following radionuclide intakes by the mother require consideration of transfers during lactation as well as during pregnancy. Current ICRP work on internal dosimetry includes the estimation of radiation doses to newborn infants from radionuclides ingested in mothers' milk. Infant doses will be calculated for maternal intakes by ingestion or inhalation of the radionuclides, radioisotopes of 31 elements, for which fetal dose coefficients have been published. In this paper, modelling approaches are examined, concentrating on models developed for iodine, caesium, polonium, alkaline earth elements and the actinides. Comparisons of model predictions show maximum overall transfer to milk following maternal ingestion during lactation of about 30% of ingested activity for 131 I, 20% for 45 Ca and 137 Cs, 10% for 90 Sr, 1% for 210 Po and low values of less than 0.01% for 239 Pu and 241 Am. The corresponding infant doses from milk consumption are estimated in preliminary calculations to be about two to three times the adult dose for 45 Ca and 131 I, 70-80% of the adult dose for 90 Sr, about 40% for 137 Cs, 20% for 210 Po, and 239 Pu and 241 Am. Infant doses from radionuclides in breast milk are compared with doses to the offspring resulting from in utero exposures during pregnancy. (author)

Procedures for estimating the radiation dose in the vicinity of uranium mines and mills by direct calculation methodology

International Nuclear Information System (INIS)

Coelho, C.P.

1983-01-01

A methodology for estimating the radiation doses to the members of the general public, in the vicinity of uranium mines and mills is presented. The data collected in the surveys performed to characterize the neighborhood of the site, and used in this work to estimate the radiation dose, are required by the Regulatory Body, for the purpose of Licensing. Initially, a description is shown of the main processing steps to obtain the uranium concentrate and the critical instalation radionuclides are identified. Following, some studies required to characterize the facility neighborhood are presented, specially those related to geography, demography, metheorology, hydrology and environmental protection. Also, the basic programs for monitoring the facility neighborhood in the pre-operational and operational phases are included. It is then proposed a procedure to estimate inhalation, ingestion and external doses. As an example, the proposed procedure is applied to a hypotetical site. Finally, some aspects related to the applicability of this work are discussed. (Author) [pt

Development of an Ingestion Pathway Model for AXAIRQ

Energy Technology Data Exchange (ETDEWEB)

Simpkins, A.A.

1999-01-13

AXAIRQ is a dose mode code used for prospective accident assessment at the Savannah River Site and is primarily used to show regulatory compliance. For completeness of pathway analysis, an ingestion model, AXINGST, has been developed for use with, and incorporation in, AXAIRQ. Currently available ingestion models were referenced as a basis for AXINGST. AXINGST calculates a conservative ingestion dose following an atmospheric release of radionuclides and includes site specific variables where applicable.

Radiation dose estimates for radiopharmaceuticals

International Nuclear Information System (INIS)

Stabin, M.G.; Stubbs, J.B.; Toohey, R.E.

1996-04-01

Tables of radiation dose estimates based on the Cristy-Eckerman adult male phantom are provided for a number of radiopharmaceuticals commonly used in nuclear medicine. Radiation dose estimates are listed for all major source organs, and several other organs of interest. The dose estimates were calculated using the MIRD Technique as implemented in the MIRDOSE3 computer code, developed by the Oak Ridge Institute for Science and Education, Radiation Internal Dose Information Center. In this code, residence times for source organs are used with decay data from the MIRD Radionuclide Data and Decay Schemes to produce estimates of radiation dose to organs of standardized phantoms representing individuals of different ages. The adult male phantom of the Cristy-Eckerman phantom series is different from the MIRD 5, or Reference Man phantom in several aspects, the most important of which is the difference in the masses and absorbed fractions for the active (red) marrow. The absorbed fractions for flow energy photons striking the marrow are also different. Other minor differences exist, but are not likely to significantly affect dose estimates calculated with the two phantoms. Assumptions which support each of the dose estimates appears at the bottom of the table of estimates for a given radiopharmaceutical. In most cases, the model kinetics or organ residence times are explicitly given. The results presented here can easily be extended to include other radiopharmaceuticals or phantoms

Studies on the assessment of radio activity in vegetables and fruits grown and consumed by residents of a typical natural high background area of South India and estimation of committed effective ingestion dose for the general public

International Nuclear Information System (INIS)

Maniyan, C.G.; Selvan, Esai; Tripathi, R.M.; Puranik, V.D.

2007-01-01

Radioactivity content of vegetables and fruits commonly grown and consumed by residents of a natural High Background Area (NHBRA) has been studied. Of the studied vegetable tapioca and tomato were found to have maximum activity accumulation and Kovai, minimum. Of the fruits studied, banana was found to have maximum activity. The radio activity of the corresponding soil in which they grew, was also estimated. It was found that uptake of the plant increases with the soil concentration. The maximum uptake was by tapioca and the minimum was by coconut kernel. From the gross alpha activity, concentration of Th and U were estimated and the committed effective dose, via ingestion, for general public consuming an average amount of 30 Kg per year veg and fruits, each, was calculated to be about 0.5 mSv. (author)

Measurement of natural radionuclides in Malaysian bottled mineral water and consequent health risk estimation

Science.gov (United States)

Priharti, W.; Samat, S. B.; Yasir, M. S.

2015-09-01

The radionuclides of 226Ra, 232Th and 40K were measured in ten mineral water samples, of which from the radioactivity obtained, the ingestion doses for infants, children and adults were calculated and the cancer risk for the adult was estimated. Results showed that the calculated ingestion doses for the three age categories are much lower than the average worldwide ingestion exposure of 0.29 mSv/y and the estimated cancer risk is much lower than the cancer risk of 8.40 × 10-3 (estimated from the total natural radiation dose of 2.40 mSv/y). The present study concludes that the bottled mineral water produced in Malaysia is safe for daily human consumption.

Effect of variable consumption habits in the Nordic populations on ECOSYS model predictions of ingestion dose

International Nuclear Information System (INIS)

Nielsen, Sven P.; Andersson, Kasper G.; Hansen, Hanne S.; Thoerring, Haavard; Joensen, Hans P.; Isaksson, Mats; Kostiainen, Eila; Suolanen, Vesa; Sigurgeirsson, Magnus A.; Palsson, Sigurour E.

2008-01-01

Full text: The two European standard decision support systems, ARGOS and RODOS, have in recent years become increasingly integrated in the Nordic preparedness against nuclear and radiological accidents and incidents. In the event of an emergency, decision making will rest heavily on the reliability of these tools. The ECOSYS model is the ingestion dose module in both decision support systems. This module is highly sensitive to variation in a number of input parameters, food production patterns, diets and environmental transfer data. With regard to for instance consumption habits, the ECOSYS default values, based on data from Southern Germany, have shown to be inadequate for Nordic conditions. We have thus collected recent data describing the human diets for four different age groups in each of the Nordic countries. Also the fractions of the consumed food items that have national origin and the animal feeding regimes in each of the Nordic countries have been examined. For a particular contamination scenario of atmospheric deposition of caesium-137, country specific data regarding consumption habits were used for dose calculations. Resulting 'country specific' doses were then compared among the participating countries and with the doses calculated using the default values of the parameters.The collected data for diets demonstrated that the average consumption of milk varied by a factor of 4-5 among the Nordic countries, and consumption of leafy vegetables varied by a factor of almost 4. Calculated ingestion doses based on country specific data for diets, with all other parameters being default values, varied by a factor of 1.8 among the countries. When also the import fractions were taken into account the calculated doses varied by a factor of 2. Due to the differences in the climate among the Nordic countries, and between these countries and Southern Germany, there were also very significant differences in the production regimes of some food items. In countries in

Radiation dose estimation from foods due to the accident of TEPCO Fukushima Daiichi Nuclear Power Station

International Nuclear Information System (INIS)

Yamaguchi, Ichiro

2012-01-01

Explained are the purpose of dose assessment, its methods, actual radionuclide levels in food, amounts of food intake, dose estimated hitherto, dose in the future, dose estimated by total food studies, and problems of assessing the dose from food, all of which Tokyo Electric Power Company (TEPCO) Power Station Accident has raised. Dose derived from food can be estimated by the radioactivity measured in each food material and in its combined amounts or in actually cooked food. Amounts of radioactive materials ingested in the body can be measured externally or by bioassay. Japan MHLW published levels of radioactivity in vegetables', fruits, marine products and meats from Mar. 2011, of which time course pattern has been found different each other within and between month(s). Dose due to early exposure in the Accident can be estimated by the radioactivity levels above and data concerning the amounts of food intake summarized by National Institute of Health and Nutrition in 2010 and other institutions. For instance, the thyroid tissue equivalent dose by I-131 in a 1 year old child is estimated to be 1.1-5 mSv depending on the assumed data for calculation, in the first month after the Accident when ICRP tissue equivalent dose coefficient 3.7 x 10-6 Sv/Bq is used. In the future (later than Apr. 2012), new standard limits of radiocesium levels in milk/its products and foods for infant and in other general foods are to be defined 50 and 100 Bq/kg, respectively. The distribution of committed effective doses by radiocesium (mSv/y food intake) are presented as an instance, where it is estimated by 1 million stochastic simulations using 2 covariates of Cs-134, -137 levels (as representative nuclides under regulation) in food and of daily food intake. In dose prediction, conjecturing the behavior of environmental radionuclides and the time of resume of primary industries would be necessary. (T.T.)

Transfer of 14C to prenatal and neonatal rats from their mothers exposed to 14C compounds by ingestion

International Nuclear Information System (INIS)

Takeda, H.; Fuma, S.; Miyamoto, K.; Kuroda, N.; Inaba, J.

2003-01-01

The transfer of 14 C through placenta or milk was investigated and the radiation dose to fetal and newborn rats was estimated. Female rats at gestational stages or after delivery were exposed to 14 C in the form of sodium bicarbonate, thymidine and lysine by a single ingestion. Radioactivity in maternal tissues and conceptuses (placenta, fetal membrane and fetus) and in the newborn was determined at various times after ingestion. After exposure to these 14 C compounds, there was no significant difference between the 14 C concentration in the fetus and that in the maternal tissues, suggesting that the placenta has no effect in preventing or accelerating the placental transfer of 14 C. The concentration and content of 14 C in the fetus and newborn were, however, dependent on the chemical form of 14 C and on the prenatal or neonatal stage at the time of ingestion. The result of the dose estimation showed that 14 C-lysine gave significantly higher prenatal and neonatal doses than 14 C-sodium bicarbonate or 14 C-thymidine. (author)

Dose calculation for {sup 40}K ingestion in samples of beans using spectrometry and MCNP; Calculo de dose devido a ingestao de {sup 40}K em amostras de feijao utilizando espectrometria e MCNP

Energy Technology Data Exchange (ETDEWEB)

Garcez, R.W.D.; Lopes, J.M.; Silva, A.X., E-mail: marqueslopez@yahoo.com.br [Coordenacao dos Programas de Pos-Graduacao em Engenharia (COPPE/PEN/UFRJ), Rio de Janeiro, RJ (Brazil). Centro de Tecnologia; Domingues, A.M. [Universidade Federal Fluminense (UFF), Niteroi, RJ (Brazil). Instituto de Fisica; Lima, M.A.F. [Universidade Federal Fluminense (UFF), Niteroi, RJ (Brazil). Instituto de Biologia

2014-07-01

A method based on gamma spectroscopy and on the use of voxel phantoms to calculate dose due to ingestion of {sup 40}K contained in bean samples are presented in this work. To quantify the activity of radionuclide, HPGe detector was used and the data entered in the input file of MCNP code. The highest value of equivalent dose was 7.83 μSv.y{sup -1} in the stomach for white beans, whose activity 452.4 Bq.Kg{sup -1} was the highest of the five analyzed. The tool proved to be appropriate when you want to calculate the dose in organs due to ingestion of food. (author)

POPFOOD - a computer code for calculating ingestion collective doses from continuous atmospheric releases

International Nuclear Information System (INIS)

Hotson, J.; Stacey, A.; Nair, S.

1980-07-01

The basic methodology incorporated in the POPFOOD computer code is described, which may be used to calculate equilibrium collective dose rates associated with continuous atmospheric releases and arising from consumption of a broad range of food products. The standard data libraries associated with the code are also described. These include a data library, based on the 1972 agricultural census, describing the spatial distribution of production, in England, Wales and Scotland, of the following food products: milk; beef and veal; pork bacon and ham; poultrymeat; eggs; mutton and lamb; root vegetables; green vegetables; fruit; cereals. Illustrative collective dose calculations were made for the case of 1 Ci per year emissions of 131 I, tritium and 14 C from a typical rural UK site. The calculations indicate that the ingestion pathway results in a greater collective dose than that via inhalation, with the contributions from consumption of root and green vegetables, and cereals being of comparable significance to that from liquid milk consumption, in all three cases. (author)

Dose-response effects in an outbreak of Salmonella enteritidis.

OpenAIRE

Mintz, E. D.; Cartter, M. L.; Hadler, J. L.; Wassell, J. T.; Zingeser, J. A.; Tauxe, R. V.

1994-01-01

The effects of ingested Salmonella enteritidis (SE) dose on incubation period and on the severity and duration of illness were estimated in a cohort of 169 persons who developed gastroenteritis after eating hollandaise sauce made from grade-A shell eggs. The cohort was divided into three groups based on self-reported dose of sauce ingested. As dose increased, median incubation period decreased (37 h in the low exposure group v. 21 h in the medium exposure group v. 17.5 h in the high exposure ...

Measurement of natural radionuclides in Malaysian bottled mineral water and consequent health risk estimation

Energy Technology Data Exchange (ETDEWEB)

Priharti, W.; Samat, S. B.; Yasir, M. S. [School of Applied Physics, Faculty of Science and Technology, Universiti Kebangsaan Malaysia, 43600 UKM Bangi, Selangor (Malaysia)

2015-09-25

The radionuclides of {sup 226}Ra, {sup 232}Th and {sup 40}K were measured in ten mineral water samples, of which from the radioactivity obtained, the ingestion doses for infants, children and adults were calculated and the cancer risk for the adult was estimated. Results showed that the calculated ingestion doses for the three age categories are much lower than the average worldwide ingestion exposure of 0.29 mSv/y and the estimated cancer risk is much lower than the cancer risk of 8.40 × 10{sup −3} (estimated from the total natural radiation dose of 2.40 mSv/y). The present study concludes that the bottled mineral water produced in Malaysia is safe for daily human consumption.

Comparison of the fates of ingested leucine and ingested 2-ketoisocaproate in rats

Energy Technology Data Exchange (ETDEWEB)

Imura, K.; Walser, M. (Johns Hopkins Univ. School of Medicine, Baltimore, MD (USA))

1990-05-01

We previously reported that the ratio, R, of 14C to 3H in the leucine of whole body protein, measured 6 h after ingestion of (3H)leucine and (1-14C)2-ketoisocaproate is equal to ratio of the dose of leucine to the dose of 2-ketoisocaproate (KIC) (on a leucine-free diet) required to achieve the same rate of growth. To determine whether R is dependent on the interval between injection and sampling, R was measured at intervals in purified whole body protein after oral injection of these isotopes in groups of rats; it was constant from 1 h onward for 1 wk, averaging 0.64 +/- 0.01 (means +/- SEM). Thus, the extent of incorporation into the leucine of whole body protein of ingested KIC remains close to 64% of the incorporation of ingested leucine administered as such simultaneously, from 1 h onward for at least 1 wk.

Analysis of the NAEG model of transuranic radionuclide transport and dose

International Nuclear Information System (INIS)

Kercher, J.R.; Anspaugh, L.R.

1984-01-01

We analyze the model for estimating the dose FR-om /sup 239/Pu developed for the Nevada Applied Ecology Group (NAEG) by using sensitivity analysis and uncertainty analysis. Sensitivity analysis results suggest that the air pathway is the critical pathway for the organs receiving the highest dose. Soil concentration and the factors controlling air concentration are the most important parameters. The only organ whose dose is sensitive to parameters in the ingestion pathway is the GI tract. The air pathway accounts for 100% of the dose to lung, upper respiratory tract, and thoracic lymph nodes; and 95% of its dose via ingestion. Leafy vegetable ingestion accounts for 70% of the dose FR-om the ingestion pathway regardless of organ, peeled vegetables 20%; accidental soil ingestion 5%; ingestion of beef liver 4%; beef muscle 1%. Only a handful of model parameters control the dose for any one organ. The number of important parameters is usually less than 10. Uncertainty analysis indicates that choosing a uniform distribution for the input parameters produces a lognormal distribution of the dose. The ratio of the square root of the variance to the mean is three times greater for the doses than it is for the individual parameters. As found by the sensitivity analysis, the uncertainty analysis suggests that only a few parameters control the dose for each organ. All organs have similar distributions and variance to mean ratios except for the lymph modes. 16 references, 9 figures, 13 tables

Analysis of the NAEG model of transuranic radionuclide transport and dose

International Nuclear Information System (INIS)

Kercher, J.R.; Anspaugh, L.R.

1984-11-01

We analyze the model for estimating the dose from 239 Pu developed for the Nevada Applied Ecology Group (NAEG) by using sensitivity analysis and uncertainty analysis. Sensitivity analysis results suggest that the air pathway is the critical pathway for the organs receiving the highest dose. Soil concentration and the factors controlling air concentration are the most important parameters. The only organ whose dose is sensitive to parameters in the ingestion pathway is the GI tract. The air pathway accounts for 100% of the dose to lung, upper respiratory tract, and thoracic lymph nodes; and 95% of its dose via ingestion. Leafy vegetable ingestion accounts for 70% of the dose from the ingestion pathway regardless of organ, peeled vegetables 20%; accidental soil ingestion 5%; ingestion of beef liver 4%; beef muscle 1%. Only a handful of model parameters control the dose for any one organ. The number of important parameters is usually less than 10. Uncertainty analysis indicates that choosing a uniform distribution for the input parameters produces a lognormal distribution of the dose. The ratio of the square root of the variance to the mean is three times greater for the doses than it is for the individual parameters. As found by the sensitivity analysis, the uncertainty analysis suggests that only a few parameters control the dose for each organ. All organs have similar distributions and variance to mean ratios except for the lymph modes. 16 references, 9 figures, 13 tables

Weldon Spring historical dose estimate

International Nuclear Information System (INIS)

Meshkov, N.; Benioff, P.; Wang, J.; Yuan, Y.

1986-07-01

This study was conducted to determine the estimated radiation doses that individuals in five nearby population groups and the general population in the surrounding area may have received as a consequence of activities at a uranium processing plant in Weldon Spring, Missouri. The study is retrospective and encompasses plant operations (1957-1966), cleanup (1967-1969), and maintenance (1969-1982). The dose estimates for members of the nearby population groups are as follows. Of the three periods considered, the largest doses to the general population in the surrounding area would have occurred during the plant operations period (1957-1966). Dose estimates for the cleanup (1967-1969) and maintenance (1969-1982) periods are negligible in comparison. Based on the monitoring data, if there was a person residing continually in a dwelling 1.2 km (0.75 mi) north of the plant, this person is estimated to have received an average of about 96 mrem/yr (ranging from 50 to 160 mrem/yr) above background during plant operations, whereas the dose to a nearby resident during later years is estimated to have been about 0.4 mrem/yr during cleanup and about 0.2 mrem/yr during the maintenance period. These values may be compared with the background dose in Missouri of 120 mrem/yr

Weldon Spring historical dose estimate

Energy Technology Data Exchange (ETDEWEB)

Meshkov, N.; Benioff, P.; Wang, J.; Yuan, Y.

1986-07-01

This study was conducted to determine the estimated radiation doses that individuals in five nearby population groups and the general population in the surrounding area may have received as a consequence of activities at a uranium processing plant in Weldon Spring, Missouri. The study is retrospective and encompasses plant operations (1957-1966), cleanup (1967-1969), and maintenance (1969-1982). The dose estimates for members of the nearby population groups are as follows. Of the three periods considered, the largest doses to the general population in the surrounding area would have occurred during the plant operations period (1957-1966). Dose estimates for the cleanup (1967-1969) and maintenance (1969-1982) periods are negligible in comparison. Based on the monitoring data, if there was a person residing continually in a dwelling 1.2 km (0.75 mi) north of the plant, this person is estimated to have received an average of about 96 mrem/yr (ranging from 50 to 160 mrem/yr) above background during plant operations, whereas the dose to a nearby resident during later years is estimated to have been about 0.4 mrem/yr during cleanup and about 0.2 mrem/yr during the maintenance period. These values may be compared with the background dose in Missouri of 120 mrem/yr.

Estimation of 210Po activity in mussel sample and its contribution in radiation dose to the public around Kanyakumari Coast, India

International Nuclear Information System (INIS)

Macklin Rani, L.; Govindaraju, M.; Jeevanram, R.K.; Muthukumaran, V.R.

2013-01-01

Polonium-210 ( 210 Po), a naturally occurring á-emitting radionuclide exists in the environment as a result of Uranium- 238 ( 238 U) decay chain. It is therefore ubiquitously distributed in the rocks, soils, making up Earths crust, in the atmosphere and in natural waters. 210 Po enters in marine organisms via adsorption, absorption and ingestion and is transferred through seafood consumption. The concentration of 210 Po in the edible portions of marine organisms may be many folds higher than that in the seawater because of biological re-concentration processes. In the present study, sampling sites were chosen to determine the difference of 210 Po concentration in bivalve mussel, an appropriate bio-indicator for radioactive contamination. The concentration of radionuclide Polonium-210 ( 210 Po) in brown mussel (Perna perna), obtained from different locations of Kanyakumari coastal area were estimated, which ranged between 76.0 ± 5.1 Bq/kg and 310.20 ± 18.4 Bq/kg. The highest activity was observed at Kalluvilai. The daily and annual intake of 210 Po from ingestion via mussel was estimated in these areas. To evaluate the internal exposure, annual committed effective dose to the adult population of this coastal area was determined and compared with the Indian and worldwide values to assess the risk status of the study area. It was observed that the average annual committed effective dose of 210 Po through ingestion is higher than the recommended dose of ICRP, 1990 (1 mSv/year) for general public due to the contribution of seafood, mussel species (3.09 mSv/year) in daily diet. (author)

Diagnose of the ingestion of Asclepias mellodora St. Hil. by sheep through microhistological analysis of their digestive contents

Directory of Open Access Journals (Sweden)

María Silvia Cid

2011-02-01

Full Text Available Asclepias mellodora St. Hil. is a native acute toxic species frequent in the grasslands of the Buenos Aires province, Argentina, whose toxicity had not been assessed until now. This study evaluates the minimal lethal dose of this species for sheep, and the possibility of microscopically recognizing its fragments in gastrointestinal contents as a complementary diagnostic tool in necropsies. Three Frisona sheep (average LW=55±4.5 kg were dosed via an esophageal tube with each one of the following doses of asclepias: 8.0, 5.0, 2.0 and 0.8 g DM.kg LW-1. Sheep poisoned with the three higher doses died between 10 and 85 h after intoxication, but those receiving the lower dose did not. During necropsies we: 1 determined the dry weight of the contents of rumen+reticulum, omasum+abomasum, and large intestine, 2 estimated the percentages of asclepias fragments by microanalysis correcting for digestion effects on fragment recognition, and 3 calculated the total mass of asclepias in the digestive tract of each animal. For the three higher doses, the mass of asclepias identified in the total ingesta was 12.3±3.4% of the amount supplied, possibly because of the strong diarrhea its ingestion produced. The percentages of asclepias in rumen+reticulum did not differ from the average quantified for the entire tract. The results of this study indicate that the minimal lethal doses of asclepias for sheep is between 2.0 and 0.8g DM·kg LW-1, and that the microhistological analysis of the rumen+reticulum, the easiest region to sample, can be used to confirm the ingestion of this toxic species, although the estimated percentage will be not a good estimator of the ingested percentage.

A development of computer code for evaluating internal radiation dose through ingestion and inhalation pathways

International Nuclear Information System (INIS)

Lee, Jeong Ho; Lee, Chang Woo; Choi, Yong Ho; Chun, Ki Jung; Kim, Kook Chan; Kim, Sang Bok; Kim, Jin Kyu

1991-07-01

The computer codes were developed to evaluate internal radiation dose when radioactive isotopes released from nuclear facilities are taken through ingestion and inhalation pathways. Food chain models and relevant data base representing the agricultural and social environment of Korea are set up. An equilibrium model-KFOOD, which can deal with routine releases from a nuclear facility and a dynamic model-ECOREA, which is suitable for the description of acute radioactivity release following nuclear accident. (Author)

Model to estimate the local radiation doses to man from the atmospheric release of radionuclides (LWBR development program)

International Nuclear Information System (INIS)

Rider, J.L.; Beal, S.K.

1977-04-01

A model was developed to estimate the radiation dose commitments received by people in the vicinity of a facility that releases radionuclides into the atmosphere. This model considers dose commitments resulting from immersion in the plume, ingestion of contaminated food, inhalation of gaseous and suspended radioactivity, and exposure to ground deposits. The dose commitments from each of these pathways is explicitly considered for each radionuclide released into the atmosphere and for each daughter of each released nuclide. Using the release rate of only the parent radionuclide, the air and ground concentrations of each daughter are calculated for each position of interest. This is considered to be a significant improvement over other models in which the concentrations of daughter radionuclides must be approximated by separate releases

Dose from drinking water Finland

International Nuclear Information System (INIS)

Maekelaeinen, Ilona; Salonen, Laina; Huikuri, Pia; Arvela, Hannu

1999-01-01

The dose from drinking water originates almost totally from naturally occurring radionuclides in the uranium-238 series, the most important nuclide being radon-222. Second comes lead-210, and third polonium-210. The mean age-group-weighted dose received by ingestion of drinking water is 0.14 mSv per year. More than half of the total cumulative dose of 750 manSv is received by the users of private wells, forming 13% of the population. The most exposed group comprises the users of wells drilled in bedrock, who receive 320 manSv while comprising only 4% of the population. The calculated number of annual cancer incidences due to drinking water is very sensitive to the dose-conversion factors of ingested radon used, as well as to the estimated lung cancer incidences caused by radon released from water into indoor air. (au)

137Cs and 40K concentrations on imported powder milk and its contribution to the annual effective dose by ingestion for children

International Nuclear Information System (INIS)

Vargas, D.; Borrell Munnoz, J. L.; D'Alessandro, K.; Gelen Rudnikas, A.; Diaz Rizo, O.; Martinez Herrera, E.; Gonzales Mesa, A.; Marrero Arias, L.; Hilda Zambrano, M.

2013-01-01

Low Background Gamma Spectrometry was used to determine activity concentrations of 137 Cs and 40 K on different powder milk samples imported in Cuba for local consumption. Radionuclide concentration has been evaluated using a high-purity germanium (HPGe) detector (2.04 keV of FWHM and 30% of relative efficiency coupled to a low background system. A relative procedure, using the Certified Reference Materials (CRM) IAEA-152 and 154, was implemented. Samples were dried at 105 o C, macerated and sieved at 125 μm using standardized procedures . Results show that radionuclide activities is strongly dependent on milk type (full and skimmed milk) and on its origin, showing in all samples an activity concentration for 137 Cs is from 1.30 to 2.69 Bq kg -1 only in the 54.7 % of them. Annual effective dose committed by powder milk ingestion for children has been estimated as 9.3x10 -3 mSv y -1 , beneath the permissible dose regulated by the Cuban authorities based on doses reported worldwide for population affected only by global fallout. (Author)

Analysis of the Nevada-Applied-Ecology-Group model of transuranic radionuclide transport and dose

International Nuclear Information System (INIS)

Kercher, J.R.; Anspaugh, L.R.

1991-01-01

The authors analyze the model for estimating the dose from 239 Pu developed for the Nevada Applied Ecology Group (NAEG) by using sensitivity analysis and uncertainty analysis. Sensitivity analysis results suggest that the inhalation pathway is the critical pathway for the organs receiving the highest dose. Soil concentration and the factors controlling air concentration are the most important parameters. The only organ whose dose is sensitive to parameters in the ingestion pathway is the GI tract. The inhalation pathway accounts for 100% of the dose to lung, upper respiratory tract and thoracic lymph nodes; and 95% of the dose to liver, bone, kidney and total body. The GI tract receives 99% of its dose via ingestion. Leafy vegetable ingestion accounts for 70% of the dose from the ingestion pathway regardless of organ, peeled vegetables 20%; accidental soil ingestion 5% ingestion of beef liver 4%; beef muscle 1%. Uncertainty analysis indicates that choosing a uniform distribution for the input parameters produces a lognormal distribution of the dose. The ratio of the square root of the variance to the mean is three times greater for the doses than it is for the individual parameters. As found by the sensitivity analysis, the uncertainty analysis suggests that only a few parameters control the dose for each organ. All organs have similar distributions and variance to mean ratios except for the lymph nodes. (author)

A crisis management decision support system to reduce ingestion dose

International Nuclear Information System (INIS)

Schenker-Wicki, A.; Gibbert, R.

1993-01-01

Environmental accidents such as extensive radioactive or chemical contamination can have more serious consequences for a population than any other kind of accidents known before. Owing to the serious consequences and the high number of people who may be affected, the selection of the best countermeasures to ameliorate the imminent impact is very difficult and the political responsibility is enormous. To help overcome such problems the National Emergency Operations Center in Zurich (Switzerland) has developed a decision support system to evaluate acceptable countermeasures for reducing ingestion dose after an accidental release of radioactive material. The system involves all the necessary modules and techniques for efficient decision making, based on the most recent developments in decision theory as well as the necessary structuring of the decision-making process. The decision-making concept comprehends decision making on two different levels, a technical and a political one. (author)

Natural radioactivity in various water samples and radiation dose estimations in Bolu province, Turkey.

Science.gov (United States)

Gorur, F Korkmaz; Camgoz, H

2014-10-01

The level of natural radioactivity for Bolu province of north-western Turkey was assessed in this study. There is no information about radioactivity measurement reported in water samples in the Bolu province so far. For this reason, gross α and β activities of 55 different water samples collected from tap, spring, mineral, river and lake waters in Bolu were determined. The mean activity concentrations were 68.11 mBq L(-1), 169.44 mBq L(-1) for gross α and β in tap water. For all samples the gross β activity is always higher than the gross α activity. All value of the gross α were lower than the limit value of 500 mBq L(-1) while two spring and one mineral water samples were found to have gross β activity concentrations of greater than 1000 mBq L(-1). The associated age-dependent dose from all water ingestion in Bolu was estimated. The total dose for adults had an average value exceeds the WHO recommended limit value. The risk levels from the direct ingestion of the natural radionuclides in tap and mineral water in Bolu were determinated. The mean (210)Po and (228)Ra risk the value of tap and mineral waters slightly exceeds what some consider on acceptable risk of 10(-4) or less. Copyright © 2014 Elsevier Ltd. All rights reserved.

Estimates of radiation doses due to ingested radiocesium and strontium 90 to the Romanian population. The second and the third year after the Chernobyl accident

International Nuclear Information System (INIS)

Botezatu, E.; Iacob, O.

1992-01-01

The paper reports the data provided by all the Romanian radiation hygiene laboratories from the Institutes of Hygiene and Public Health and the Regional Prophylactic Medicine Centers. The 134 Cs, 137 Cs and 90 Sr concentrations in some 20,000 various samples (water and foodstuff) were determined after the Chernobyl accident, as part of a long-term sanitary surveillance programme. The measurements were performed by using gamma spectroscopy and radiochemical analysis. As expected, measurements of 90 Sr and radiocesium concentrations in the samples collected from all over Romania showed a grater contamination with radiocesium. The levels of the contamination have greatly decreased during the period of 30 April 1987 - 30 April 1989. Charting the levels of food radioactivity, it was possible to divide Romania into three zones. These zones overlap pretty well those of the 137 Cs deposition (UNSCEAR 1988). Doses from ingestion of contaminated foods were calculated as products of average concentration in foods, consumption amounts and age specific dose per unit intake factors. The effective dose equivalent received by individuals (children and adults) during the second and third year following the accident were determined. (author) 1 fig., 7 tabs., 13 refs

Assessment of prospective foodchain doses from radioactive discharges from BNFL Sellafield

International Nuclear Information System (INIS)

Ould-Dada, Z.; Tucker, S.; Webbe-Wood, D.; Mondon, K.; Hunt, J.

2002-01-01

This paper presents the method used by the UK Food Standards Agency (FSA) to assess the potential impact of proposed radioactive discharges from the Sellafield nuclear site on food and determine their acceptability. It explains aspects of a cautious method that has been adopted to reflect the UK government policy and uncertainties related to people's habits with regard to food production and consumption. Two types of ingestion doses are considered in this method: 'possible' and 'probable' doses. The method is specifically applied to Sellafield discharge limits and calculated possible and probable ingestion doses are presented and discussed. Estimated critical group ingestion doses are below the dose limit and constraint set for members of the public. The method may be subject to future amendments to take account of changes in government policy and the outcome of a recent Consultative Exercise on Dose Assessments carried out by FSA. Uncertainties inherent in dose assessments are discussed and quantified wherever possible

A study on the application of countermeasure for the reduction of the ingestion dose after nuclear accidents

International Nuclear Information System (INIS)

Hwang, Won Tae; Suh, Kyung Suk; Kim, Eun Han; Choi, Young Gil; Han, Moon Hee; Cho, Gyu Seong

1998-01-01

The effectiveness of dose reduction resulting from the application of countermeasures for ingestion pathways after nuclear accidents was investigated together with the derivation of optimized intervention levels for Korean foodstuffs. The radioactivity in foodstuffs was predicted from a dynamic food chain model DYNACON for the date which the deposition occurs. The effectiveness of countermeasures strongly depended on radionuclides, foodstuffs and date of deposition

New Jersey's experience with implementing Protective Action Guides during the 1988 Salem ingestion pathway exercise

International Nuclear Information System (INIS)

White, Duncan

1989-01-01

On November 30 and December 1, 1988, the New Jersey Department of Environmental Protection (DEP) and three other State agencies (Health, Agriculture and State Police) participated in the ingestion pathway portion of the 1988 Salem Nuclear Generating Station Emergency Exercise. The purpose of this phase of the exercise was to demonstrate the ingestion pathway components of the State's Radiological Emergency Response Plan (RERP) to the Federal Emergency Management Agency (FEMA). The intent of this paper is to provide a summary of difficulties and some lessons learned in implementing the DEP's ingestion pathway Protective Action Guides (PAGs) during the exercise as well as during the preparation of a total population dose estimate (TPDE)

New Jersey's experience with implementing Protective Action Guides during the 1988 Salem ingestion pathway exercise

Energy Technology Data Exchange (ETDEWEB)

White, Duncan [New Jersey Department of Environmental Protection, Trenton, NJ (United States)

1989-09-01

On November 30 and December 1, 1988, the New Jersey Department of Environmental Protection (DEP) and three other State agencies (Health, Agriculture and State Police) participated in the ingestion pathway portion of the 1988 Salem Nuclear Generating Station Emergency Exercise. The purpose of this phase of the exercise was to demonstrate the ingestion pathway components of the State's Radiological Emergency Response Plan (RERP) to the Federal Emergency Management Agency (FEMA). The intent of this paper is to provide a summary of difficulties and some lessons learned in implementing the DEP's ingestion pathway Protective Action Guides (PAGs) during the exercise as well as during the preparation of a total population dose estimate (TPDE)

Transfer of {sup 14}C to prenatal and neonatal rats from their mothers exposed to {sup 14}C compounds by ingestion

Energy Technology Data Exchange (ETDEWEB)

Takeda, H.; Fuma, S.; Miyamoto, K.; Kuroda, N.; Inaba, J

2003-07-01

The transfer of {sup 14}C through placenta or milk was investigated and the radiation dose to fetal and newborn rats was estimated. Female rats at gestational stages or after delivery were exposed to {sup 14}C in the form of sodium bicarbonate, thymidine and lysine by a single ingestion. Radioactivity in maternal tissues and conceptuses (placenta, fetal membrane and fetus) and in the newborn was determined at various times after ingestion. After exposure to these {sup 14}C compounds, there was no significant difference between the {sup 14}C concentration in the fetus and that in the maternal tissues, suggesting that the placenta has no effect in preventing or accelerating the placental transfer of {sup 14}C. The concentration and content of {sup 14}C in the fetus and newborn were, however, dependent on the chemical form of {sup 14}C and on the prenatal or neonatal stage at the time of ingestion. The result of the dose estimation showed that {sup 14}C-lysine gave significantly higher prenatal and neonatal doses than {sup 14}C-sodium bicarbonate or {sup 14}C-thymidine. (author)

The MIRD method of estimating absorbed dose

International Nuclear Information System (INIS)

Weber, D.A.

1991-01-01

The estimate of absorbed radiation dose from internal emitters provides the information required to assess the radiation risk associated with the administration of radiopharmaceuticals for medical applications. The MIRD (Medical Internal Radiation Dose) system of dose calculation provides a systematic approach to combining the biologic distribution data and clearance data of radiopharmaceuticals and the physical properties of radionuclides to obtain dose estimates. This tutorial presents a review of the MIRD schema, the derivation of the equations used to calculate absorbed dose, and shows how the MIRD schema can be applied to estimate dose from radiopharmaceuticals used in nuclear medicine

Gastrointestinal bleeding following NSAID ingestion in children

African Journals Online (AJOL)

Both presented with a history of fever and passage of bloody stools. There was a positive history of NSAID ingestion in both patients that was prescribed in the referring hospitals. ..... Bostwick HE, Halata MS, Feerick J, Newman LJ, Medow MS. Gastrointestinal bleeding in children following ingestion of low-dose. Ibuprofen.

Increase of methanol in exhaled breath quantified by SIFT-MS following aspartame ingestion.

Science.gov (United States)

Španěl, Patrik; Dryahina, Kseniya; Vicherková, Petra; Smith, David

2015-11-19

Aspartame, methyl-L-α-aspartyl-L-phenylalaninate, is used worldwide as a sweetener in foods and drinks and is considered to be safe at an acceptable daily intake (ADI) of 40 mg per kg of body weight. This compound is completely hydrolyzed in the gastrointestinal tract to aspartic acid, phenylalanine and methanol, each being toxic at high levels. The objective of the present study was to quantify the volatile methanol component in the exhaled breath of ten healthy volunteers following the ingestion of a single ADI dose of aspartame. Direct on-line measurements of methanol concentration were made in the mouth and nose breath exhalations using selected ion flow tube mass spectrometry, SIFT-MS, several times before aspartame ingestion in order to establish individual pre-dose (baseline) levels and then during two hours post-ingestion to track their initial increase and subsequent decrease. The results show that breath methanol concentrations increased in all volunteers by 1082   ±   205 parts-per-billion by volume (ppbv) from their pre-ingestion values, which ranged from 193 to 436 ppbv to peak values ranging from 981-1622 ppbv, from which they slowly decreased. These observations agree quantitatively with a predicted increase of 1030 ppbv estimated using a one-compartment model of uniform dilution of the methanol generated from a known amount of aspartame throughout the total body water (including blood). In summary, an ADI dose of aspartame leads to a 3-6 fold increase of blood methanol concentration above the individual baseline values.

Analysis of parameters for the off-site dose calculation due to HTO, OBT, and radioactive carbon ingestion

International Nuclear Information System (INIS)

Lee, G. B.; Jeung, Y. K.; Bang, S. Y.; Um, H. M.

2004-01-01

For assessment of tritium and radiocarbon ingestion dose to off site individuals, water, hydrogen, and carbon content of main farm produce of Korea were investigated to replace the existing data in K-DOSE60, the Offsite Dose Calculation Manual(ODCM) of Korea Hydro and Nuclear Power Co. Ltd. (KHNP). Main items and weighting factors of farm produce were determined with the nationwide food intake data in 2001, 2002. Main farm produce were sampled around Kori, Wolsong, Ulchin, Yonggwang nuclear power sites. Content of each produce was multiplied by weighting factor and summed up to make the weighted mean group value. For grains, water, hydrogen, and carbon content was not much different from the existing data currently used in K-DOSE60, but root vegetables had 3.5 times more hydrogen, and leafy vegetables and fruits had 0.7 - 1.3 times more or less water, hydrogen, and carbon contents than K-DOSE60

Estimation of doses to individuals from radionuclides disposed of in Solid Waste Storage Area 6

International Nuclear Information System (INIS)

Fields, D.E.; Boegly, W.J. Jr.; Huff, D.D.

1986-01-01

A simple methodology has been applied to estimate maximum possible doses to individuals from exposure to radionuclides released from Solid Waste Storage Area No. 6. This is the only operating shallow-land disposal site for radioactive waste at the Oak Ridge National Laboratory. The methodology is based upon simple, conservative assumptions. A data base of radionuclides disposed of in trenches and auger holes was prepared, and several radionuclide transport and ingestion scenarios were considered. The results of these simulations demonstrate the potential for adverse health effects associated with this waste disposal area, and support the need for further calculations using more complete and realistic assumptions

Internal dose estimation by bio-assay techniques

International Nuclear Information System (INIS)

Sawant, Pramilla D.

2016-01-01

Radiation exposure, both external and internal, can occur to radiation workers during the operation of various nuclear fuel cycle facilities and radiation facilities. The assessment of radiation doses to workers, routinely or potentially exposed to radiation, through intake of radionuclide is an integral part of the radiation protection programme. Internal dose is the radiation exposure that results from the intake of radioactive materials into the body by inhalation, ingestion, absorption through the skin or via wounds. Assessment of radiation doses arising from the intake of radioactive material by the workers is termed as internal exposure assessment. Unlike external exposure, internal exposure cannot be measured directly. Its evaluation is based on the calculation of the intake of radionuclide either from direct measurements (e.g, external monitoring of whole body or of specific organs and tissues) or indirect measurements (e.g. radioactivity in urine, faeces, breath or samples from the working environment) (ICRP Pub. 78, 1997 and NRPB-W60, 2004). Another method of internal dose assessment is based on the measurement of airborne radionuclides in the working areas of the facility and the worker's occupancy in those areas

Reduction in the volume of water for ingesting orally disintegrating tablets of solifenacin (Vesicare® OD), and the clinical disintegration time of Vesicare® OD after unit-dose packaging.

Science.gov (United States)

Uchida, Shinya; Yoshita, Tomohiro; Namiki, Noriyuki

2013-03-25

This study aimed to determine the amount of water required for ingesting an orally disintegrating tablet (ODT) of solifenacin (Vesicare(®), VES) and VES conventional tablets (VES-CT). We measured the disintegration time of VES-ODT in the oral cavity (clinical disintegration time) before and after unit-dose packaging. Thirty healthy volunteers participated in this randomized crossover trial. The participants were asked to drink water during the intake placebos of VES and after the disintegration of placebos of VES-ODT in their oral cavity. The amounts of water required for ingesting placebos of VES-CT and of VES-ODT were 42.8±27.0 mL and 20.0±23.7 mL, respectively, which indicated that the amount of water required for ingesting ODTs was significantly lesser than that for ingesting CTs. Furthermore, 5 (16.7%) participants did not require water for ingesting the ODTs. Clinical disintegration time of VES-ODT was 21.4s in 10 healthy volunteers. This clinical disintegration time did not change significantly after unit-dose packaging or subsequent storage for 56 days. This study showed that the amount of water required for ingesting VES-ODT is lower than that for ingesting VES-CT. Crown Copyright © 2013. Published by Elsevier B.V. All rights reserved.

An attempt and significance of using scandium (Sc) indication for quantitative estimation of soil ingested by pastured cattle

International Nuclear Information System (INIS)

Koyama, Takeo; Sudo, Madoka; Miyamoto, Susumu; Kikuchi, Takeaki; Takahashi, Masayoshi; Kuma, Tadashi.

1985-01-01

Pastured beef cattle constantly ingest soil together with grass. Dried grass and silage used in winter also contain some soil. Sc occurs in soil in much greater amounts than in grass and is not absorbed by digestive canals, and the Sc content can be determined accuretely by the activation analysis method. In view of this, a technique is devised which uses Sc as an indication in estimating the amount of soil ingested by cattle, and this new method is found to be better than the conventional one with Ti indication. Accordingly, dung is collected from the same cattle at the end of the pastured and housed periods. The dung samples are dried, ground, activated and analysed. On the basis of results of this analysis, the amount of soil ingested at the end of the pastured and housed periods is estimated at 106 +- 120 and 129 +- 171 g/day, respectively, which broadly agree with values previously reported. An evaluation of the amounts of Se and Zn taken by cattle from soil is also carried out. (Nogami, K.)

Retrospective evaluation of xylitol ingestion in dogs: 192 cases (2007-2012).

Science.gov (United States)

DuHadway, Meghan R; Sharp, Claire R; Meyers, Katherine E; Koenigshof, Amy M

2015-01-01

To summarize the signalment, clinical signs, prevalence of decreased blood glucose concentration (BG), prevalence of increased liver values, treatment, and outcome in dogs known to have ingested xylitol. Retrospective study from December 2007 to February 2012 SETTING: Three university teaching hospitals. One hundred ninety-two client-owned dogs with known or suspected xylitol ingestion. None. The median ingested xylitol dose was 0.32 g/kg (range 0.03-3.64 g/kg). Clinical signs were present in 39 (20%) dogs on presentation to the veterinary teaching hospitals. The most common clinical sign was vomiting (n = 25), followed by lethargy (12). The median duration of clinical signs prior to presentation was 93 minutes (range 0-5,040 minutes). Dogs that developed clinical signs ingested a significantly higher dose of xylitol than those that were asymptomatic. Thirty dogs became hypoglycemic (BG ≤ 3.3 mmol/L [60 mg/dL]) at some time point during their hospitalization. When evaluating all dogs, there was a significant difference between the initial and lowest BGs. Thirty dogs had increased alanine aminotransferase activity or total serum bilirubin concentration. Dogs with increases in alanine aminotransferase activity or total serum bilirubin concentration had a significantly lower nadir BG. All dogs survived to discharge and 158 were known to be alive at 28 days. The rest were lost to follow up. The prognosis for dogs evaluated by a veterinarian that ingest lower doses of xylitol and do not develop liver failure is excellent. Dogs ingesting xylitol should be hospitalized and monitored for variations in BG, because BG drops in most dogs following presentation. Additional studies are needed in dogs ingesting higher doses of xylitol before correlations between dose and the development of clinical signs or liver failure can be established. Treatment and prognosis for these dogs warrants further investigation. © Veterinary Emergency and Critical Care Society 2015.

210Po, 210Pb, 40K and 137Cs in edible wild berries and mushrooms and ingestion doses to man from high consumption rates of these wild foods

International Nuclear Information System (INIS)

Gwynn, Justin P.; Nalbandyan, Anna; Rudolfsen, Geir

2013-01-01

This paper discusses activity concentrations of 210 Po, 210 Pb, 40 K and 137 Cs in edible wild berries and mushrooms collected from Øvre Dividalen national park, Northern Norway and derives committed effective ingestion doses to man based on high consumption rates of these wild foods. Edible wild berries and mushrooms accumulated similar levels of 210 Pb, but mushrooms accumulated higher levels of 210 Po and 40 K than berries. There appears to be a clear difference in the ability of Leccinum spp. of fungi to accumulate 210 Po and/or translocate 210 Po to mushrooms compared to Russula spp. of fungi. Activity concentrations of 137 Cs in edible wild berries and mushrooms from Øvre Dividalen national park reflected the lower levels of fallout of this radionuclide in Northern Norway compared to more central areas following the Chernobyl accident. For mushrooms, ingestion doses are dominated by 210 Po, while for berries, 40 K is typically the main contributor to dose. Based on high consumption rates, ingestion doses arising from the combination of 210 Po, 210 Pb and 40 K were up to 0.05 mSv/a for berries and 0.50 mSv/a for mushrooms. Consumption of such wild foods may result in a significant contribution to total annual doses when consumed in large quantities, particularly when selecting mushrooms species that accumulate high activity concentrations of 210 Po. - Highlights: ► 210 Po/ 210 Pb activity ratios were typically less than one for berries. ► 210 Po/ 210 Pb activity ratios were all greater than one for mushrooms. ► Dose rates from mushrooms were dominated by 210 Po and by 40 K for berries. ► Wild foods can give a significant contribution to total annual ingestion dose.

Dynamic model of the global iodine cycle for the estimation of dose to the world population from releases of iodine-129 to the environment

International Nuclear Information System (INIS)

Kocher, D.C.

1979-11-01

A dynamic linear compartment model of the global iodine cycle has been developed for the purpose of estimating long-term doses and dose commitments to the world population from releases of 129 I to the environment. The environmental compartments assumed in the model comprise the atmosphere, hydrosphere, lithosphere, and terrestrial biosphere. The global transport of iodine is described by means of time-invariant fractional transfer rates between the environmental compartments. The fractional transfer rates for 129 I are determined primarily from available data on compartment inventories and fluxes for naturally occurring stable iodine and from data on the global hydrologic cycle. The dose to the world population is estimated from the calculated compartment inventories of 129 I, the known compartment inventories of stable iodine, a pathway analysis of the intake of iodine by a reference individual, dose conversion factors for inhalation and ingestion, and an estimate of the world population. For an assumed constant population of 12.21 billion beyond the year 2075, the estimated population dose commitment is 2 x 10 5 man-rem/Ci. The sensitivity of the calculated doses to variations in some of the parameters in the model for the global iodine cycle is investigated. A computer code written to calculate global compartment inventories and dose rates and population doses is described and documented

Polonium-210 and Lead-210 in food and tobacco products: transfer parameters and normal exposure and dose

International Nuclear Information System (INIS)

Watson, A.P.

1985-01-01

Food-chain transport of Pb-210 and Po-210 from soil to edible plant parts and from animal feed to meat and milk was evaluated from a review of literature. The degree of transfer was characterized by estimating concentration factors as well as the transfer coefficients B/sub v/, B/sub r/, f/sub m/, and f/sub f/. Global dietary intake of Pb-210 and Po-210 was also summarized, and 50-y dose estimates to target organs were calculated. The greatest estimated ingestion doses were those to populations with large dietary complements of animal protein in the form of seafood (Japan) or caribou/reindeer muscle and organ meats (Arctic Eskimos and Lapps). The origin and magnitude of inhalation exposure and dose from tobacco products were also assessed. For the majority of internal organs evaluated, the dose resulting from smoking commercially available tobacco products is comparable with or greater than the dose estimates for ingestion of naturally occurring dietary Pb-210 and Po-210. 79 refs

The biological impacts of ingested radioactive materials on the pale grass blue butterfly

Science.gov (United States)

Nohara, Chiyo; Hiyama, Atsuki; Taira, Wataru; Tanahara, Akira; Otaki, Joji M.

2014-05-01

A massive amount of radioactive materials has been released into the environment by the Fukushima Dai-ichi Nuclear Power Plant accident, but its biological impacts have rarely been examined. Here, we have quantitatively evaluated the relationship between the dose of ingested radioactive cesium and mortality and abnormality rates using the pale grass blue butterfly, Zizeeria maha. When larvae from Okinawa, which is likely the least polluted locality in Japan, were fed leaves collected from polluted localities, mortality and abnormality rates increased sharply at low doses in response to the ingested cesium dose. This dose-response relationship was best fitted by power function models, which indicated that the half lethal and abnormal doses were 1.9 and 0.76 Bq per larva, corresponding to 54,000 and 22,000 Bq per kilogram body weight, respectively. Both the retention of radioactive cesium in a pupa relative to the ingested dose throughout the larval stage and the accumulation of radioactive cesium in a pupa relative to the activity concentration in a diet were highest at the lowest level of cesium ingested. We conclude that the risk of ingesting a polluted diet is realistic, at least for this butterfly, and likely for certain other organisms living in the polluted area.

The biological impacts of ingested radioactive materials on the pale grass blue butterfly.

Science.gov (United States)

Nohara, Chiyo; Hiyama, Atsuki; Taira, Wataru; Tanahara, Akira; Otaki, Joji M

2014-05-15

A massive amount of radioactive materials has been released into the environment by the Fukushima Dai-ichi Nuclear Power Plant accident, but its biological impacts have rarely been examined. Here, we have quantitatively evaluated the relationship between the dose of ingested radioactive cesium and mortality and abnormality rates using the pale grass blue butterfly, Zizeeria maha. When larvae from Okinawa, which is likely the least polluted locality in Japan, were fed leaves collected from polluted localities, mortality and abnormality rates increased sharply at low doses in response to the ingested cesium dose. This dose-response relationship was best fitted by power function models, which indicated that the half lethal and abnormal doses were 1.9 and 0.76 Bq per larva, corresponding to 54,000 and 22,000 Bq per kilogram body weight, respectively. Both the retention of radioactive cesium in a pupa relative to the ingested dose throughout the larval stage and the accumulation of radioactive cesium in a pupa relative to the activity concentration in a diet were highest at the lowest level of cesium ingested. We conclude that the risk of ingesting a polluted diet is realistic, at least for this butterfly, and likely for certain other organisms living in the polluted area.

Estimated radiation dose from timepieces containing tritium

International Nuclear Information System (INIS)

McDowell-Boyer, L.M.

1980-01-01

Luminescent timepieces containing radioactive tritium, either in elemental form or incorporated into paint, are available to the general public. The purpose of this study was to estimate potential radiation dose commitments received by the public annually as a result of exposure to tritium which may escape from the timepieces during their distribution, use, repair, and disposal. Much uncertainty is associated with final dose estimates due to limitations of empirical data from which exposure parameters were derived. Maximum individual dose estimates were generally less than 3 μSv/yr, but ranged up to 2 mSv under worst-case conditions postulated. Estimated annual collective (population) doses were less than 5 person/Sv per million timepieces distributed

Biological dose estimation for accidental supra-high dose gamma-ray exposure

International Nuclear Information System (INIS)

Chen, Y.; Yan, X.K.; Du, J.; Wang, Z.D.; Zhang, X.Q.; Zeng, F.G.; Zhou, P.K.

2011-01-01

To correctly estimate the biological dose of victims accidentally exposed to a very high dose of 60 Co gamma-ray, a new dose-effect curve of chromosomal dicentrics/multicentrics and rings in the supra-high dose range was established. Peripheral blood from two healthy men was irradiated in vitro with doses of 60 Co gamma-rays ranging from 6 to 22 Gy at a dose rate of 2.0 Gy/min. Lymphocytes were concentrated, cultured and harvested at 52 h, 68 h and 72 h. The numbers of dic + r were counted. The dose-effect curves were established and validated using comparisons with doses from the Tokai-mura accident and were then applied to two victims of supra-high dose exposure accident. The results indicated that there were no significant differences in chromosome aberration frequency among the different culture times from 52 h to 72 h. The 6-22 Gy dose-effect curve was fitted to a linear quadratic model Y = -2.269 + 0.776D - 7.868 x l0 -3 D 2 . Using this mathematic model, the dose estimates were similar to data from Tokai-mura which were estimated by PCC ring. Whole body average doses of 9.7 Gy and 18.1 Gy for two victims in the Jining accident were satisfactorily given. We established and successfully applied a new dose-effect curve of chromosomal dicentrics plus ring (dic + r) after 6-22 Gy γ-irradiation from a supra-high dose 60 Co gamma-ray accident.

A user's guide to the POPFOOD computer code for evaluating ingestion collective doses

International Nuclear Information System (INIS)

Nair, S.; Palamountain, J.

1980-09-01

A complete description is given of the wide range of user options available for running the POPFOOD computer code, which was developed for the calculation of annual ingestion collective doses from routine atmospheric discharges of radioactivity in the UK. The various options have been depicted pictorially to allow the prospective user to obtain a rapid appreciation of their scope. Facilities for modifying temporarily the library and input data are also described. In addition, input and output data for a sample test case, covering broad range of the various available options, are provided to facilitate programme testing. POPFOOD is written in Fortran IV (level H). The programme is compiled under release 20.6, OPT=2 on the IBM 370/165 computer. (author)

IODES, Calculating the Estimation of Dose to the World Population from Releases of Iodine-129 to the Environment

International Nuclear Information System (INIS)

2002-01-01

1 - Description of program or function: IODES is a dynamic linear compartment model of the global iodine cycle which estimates long-term doses and dose commitments to the world population from releases of 129 I to the environment. The global environment is divided into different compartments comprising the atmosphere, hydrosphere, lithosphere, and terrestrial biosphere. The global transport of iodine is described by means of time-invariant fractional transfer rates between the environmental compartments. The fractional transfer rates for 129 I are determined primarily from available data on compartment inventories and fluxes for naturally occurring stable iodine and from data on the global hydrologic cycle. The dose to the world population is estimated from the calculated compartment inventories of 129 I, the known compartment inventories of stable iodine, a pathway analysis of the intake of iodine by a reference individual, dose conversion factors for inhalation and ingestion, and an estimate of the world population. For an assumed constant population of 12.21 billion beyond the year 2075, the estimated population dose commitment is 2 x 105 man-rem/Ci. 2 - Methods: IODES calculates 129 I inventories in the different environmental compartments and individual and population doses as a function of time after a release to the environment by solving a set of simultaneous first-order linear differential equations using numerical methods. 3 - Restrictions on the complexity of the problem: - The subroutine LSODE for solving the differential equations is provided online at the ORNL computer center and, thus, is not included in the IODES code package. If the LSODE routine is not available to the user, then an appropriate differential equation routine must be supplied by the user, and the initialization of parameters and the call statement for LSODE in the main program must be changed accordingly

A kinematic model to estimate the effective dose of radioactive isotopes in the human body for radiological protection

Science.gov (United States)

Sasaki, S.; Yamada, T.

2013-12-01

The great earthquake attacked the north-east area in Japan in March 11, 2011. The system of electrical facilities to control Fukushima Daiichi nuclear power station was completely destroyed by the following tsunamis. From the damaged reactor containment vessels, an amount of radioactive substances had leaked and been diffused in the vicinity of this station. Radiological internal exposure becomes a serious social issue both in Japan and all over the world. The present study provides an easily understandable, kinematic-based model to estimate the effective dose of radioactive substances in a human body by simplified the complicated mechanism of metabolism. International Commission on Radiological Protection (ICRP) has developed an exact model, which is well-known as a standard method to calculate the effective dose for radiological protection. However, owing to that the above method accord too much with the actual mechanism of metabolism in human bodies, it becomes rather difficult for non-professional people of radiology to gasp the whole images of the movement and the influences of radioactive substances in a human body. Therefore, in the present paper we propose a newly-derived and easily-understandable model to estimate the effective dose. The present method is very similar with the traditional and conventional hydrological tank model. Ingestion flux of radioactive substances corresponds to rain intensity and the storage of radioactive substances to the water storage in a basin in runoff analysis. The key of this method is to estimate the energy radiated from the radioactive nuclear disintegration of an atom by using classical theory of E. Fermi of beta decay and special relativity for various kinds of radioactive atoms. The parameters used in this study are only physical half-time and biological half-time, and there are no intentional and operational parameters of coefficients to adjust our theoretical runoff to observation of ICRP. Figure.1 compares time

Metabolism of ingested uranium and radium

Energy Technology Data Exchange (ETDEWEB)

Wrenn, M.D.; Durbin, P.W.; Howard, B.; Lipsztein, J.; Rundo, J.; Still, E.T.; Willis, D.L.

1983-01-01

Metabolic models for U and Ra are described to estimate the risks to human health from ingesting these elements in drinking water. Chemical toxicity, which is relevant to U in its natural, depleted or slightly enriched state, is addressed, as are the radiotoxicity and the radiobiological effects of the important alpha-emitting isotopes of Ra, including /sup 224/Ra, /sup 226/Ra, and /sup 228/Ra. This paper estimates the kinetics of skeletal U deposition, so that risk coefficients for bone cancer induction can be applied. Skeletal cancer is regarded as the major potential radiobiological effect of ingested alpha-emitting radioisotopes of Ra and the presumed radiobiological effect of U, if any. Best estimates of normal U metabolism are used, because even in extreme cases the amounts of U or Ra ingested in potable water are not great enough to chemically or radiobiologically modify their metabolic behavior.

Metabolism of ingested uranium and radium

International Nuclear Information System (INIS)

Wrenn, M.D.; Durbin, P.W.; Howard, B.; Lipsztein, J.; Rundo, J.; Still, E.T.; Willis, D.L.

1983-01-01

Metabolic models for U and Ra are described to estimate the risks to human health from ingesting these elements in drinking water. Chemical toxicity, which is relevant to U in its natural, depleted or slightly enriched state, is addressed, as are the radiotoxicity and the radiobiological effects of the important alpha-emitting isotopes of Ra, including 224 Ra, 226 Ra, and 228 Ra. This paper estimates the kinetics of skeletal U deposition, so that risk coefficients for bone cancer induction can be applied. Skeletal cancer is regarded as the major potential radiobiological effect of ingested alpha-emitting radioisotopes of Ra and the presumed radiobiological effect of U, if any. Best estimates of normal U metabolism are used, because even in extreme cases the amounts of U or Ra ingested in potable water are not great enough to chemically or radiobiologically modify their metabolic behavior

A review of soil and dust ingestion studies for children.

Science.gov (United States)

Moya, Jacqueline; Phillips, Linda

2014-11-01

Soil and dust ingestion by children may be important pathways of exposure to environmental contaminants. Contaminated soil and dust may end up on children's hands and objects, because they play close to the ground. These contaminants can be ingested by children, because they have a tendency to place objects, including their fingers, in their mouths. Assessing exposure through this pathway requires information about the amount of soil and dust ingested by children. Estimates of soil and dust ingestion and information on the prevalence of the behavior have been published in the literature, but research in this area is generally limited. Three methodologies have been used to quantify soil and dust ingestion rates. In this paper, these are referred to as the tracer element method, the biokinetic model comparison method, and the activity pattern method. This paper discusses the information available on the prevalence of soil and dust ingestion behavior, summarizes the three methodologies for quantifying soil and dust ingestion, and discusses their limitations. Soil ingestion data derived from studies that use these methodologies are also summarized. Although they are based on different estimation approaches, the central tendency estimates of soil and dust ingestion derived from the three methodologies are generally comparable.

Estimates concentrations in bottled 222Rn of the dose due to mineral waters in Iran

International Nuclear Information System (INIS)

Assadi, M. R.; Esmaealnejad, M.; Rahmatinejad, Z.

2006-01-01

Radon is a radionuclide that has the main role in exposure. Radon in water causes exposure in whole body but the largest dose being received by the stomach, as EPA (Environmental Protection Agency) estimates that radon in drinking water causes about 168 cancer deaths per year: 89 p ercent f rom lung cancer caused by breathing released to the indoor air from water and 11 p ercent f rom stomach cancer caused by consuming water containing radon. Now days the consumption of bottled mineral waters has become very popular. As is known, some kinds of mineral waters contain naturally occurring radionuclides in higher concentration than the usual drinking (tap) water. Surveys and reports on radon in most surface waters is low compared with radon level in groundwater and mineral water. In our work, the concentration of Rn(222) was determined in some bottled mineral waters available in Iran , and in next step the dose contribution ; due to ingestion ; for 1 l d -1 bottled mineral water consumption.

Measurements of natural and artificial radionuclides in food samples and water for human consumption in Austria for the calculation of the ingestion dose

International Nuclear Information System (INIS)

Claudia Landstetter; Michael Zapletal; Merita Sinojmeri; Christian Katzlberger

2013-01-01

A new report on food habits of the Austrian population in the year 2006/2007 was released in 2008. Mixed diets and foodstuffs are measured within a monitoring program according to the Austrian radiation protection law, food law, and the Commission Recommendation 2000/473/Euratom on the application of Article 36 of the Euratom Treaty concerning the monitoring of the levels of radioactivity in the environment for the purpose of assessing the exposure of the population as a whole. In addition, drinking and mineral water samples are measured for natural and artificial radionuclides. The ingestion dose for the Austrian population is recalculated based on the results of these measurements, literature data, and the data of the new report on food habits. In general, the major part of the ingestion dose is caused by natural radionuclides, especially 40 K. (author)

Ingestion dose pathway parameters of H-3 and C-14 in Korea

Energy Technology Data Exchange (ETDEWEB)

Yang-Geun Chung; Gab-Bock Lee; Sun-Young Bang [Korea Electric Power Research Institute (Korea, Republic of); Seung-Ong Lee [Korea Hydro and Nuclear Power Cooperation (Korea, Republic of)

2006-07-01

Full text of publication follows: H-3 and C-14 are the main nuclides for public ingestion dose around nuclear power plants in Korea. Key parameters of H-3 and C-14 ingestion dose pathways are the fractions of moisture, hydrogen, and carbon in agricultural vegetation. In this study, representative values of the moisture, hydrogen, and carbon contents for categorized food groups were established. The food stuffs are classified into four groups such as grain, leafy vegetable, root vegetable, and fruit. Methods Weighting factors for individual food items were considered to calculate representative values of each food group using the 2001-2002 national dietary survey, published by the Ministry of Health and Welfare (MOHW). The weighting factor for individual food stuff was determined by the ratio of each food item to the total intake of each food group. Representative values of the moisture, hydrogen, and carbon contents for the four food groups were calculated using the annual weighting factor and the fractions of moisture, hydrogen, and carbon of individual food stuff based on the sixth revision of Food Composition Table published by the Rural Living Science Research Institute (RLSI). Results The weighting factor of rice in grain group was 95% on a yearly basis. Those of Chinese cabbage in leafy vegetable group and radish in root vegetable group were 58% and 52%, respectively. The fruit consumption varied with seasons. Annual weighting factors of apple, persimmon, water melon, and pear in fruit were 21%, 18%, 17%, and 15%, respectively. The respective fractions of moisture in grain, leafy vegetable, root vegetable, and fruit were 10.8%, 93.0%, 88.3%, and 88.0%: those of hydrogen were 5.6%, 0.4%, 0.7%, and 0.74%: those of carbon were 39.68%, 2.84%, 4.98%, and 5.23%. The hydrogen fraction of root vegetable was 75% larger than that of leafy vegetable. The values of moisture, hydrogen, and carbon contents in agricultural vegetation calculated from the Food Composition

Ingestion dose pathway parameters of H-3 and C-14 in Korea

International Nuclear Information System (INIS)

Yang-Geun Chung; Gab-Bock Lee; Sun-Young Bang; Seung-Ong Lee

2006-01-01

Full text of publication follows: H-3 and C-14 are the main nuclides for public ingestion dose around nuclear power plants in Korea. Key parameters of H-3 and C-14 ingestion dose pathways are the fractions of moisture, hydrogen, and carbon in agricultural vegetation. In this study, representative values of the moisture, hydrogen, and carbon contents for categorized food groups were established. The food stuffs are classified into four groups such as grain, leafy vegetable, root vegetable, and fruit. Methods Weighting factors for individual food items were considered to calculate representative values of each food group using the 2001-2002 national dietary survey, published by the Ministry of Health and Welfare (MOHW). The weighting factor for individual food stuff was determined by the ratio of each food item to the total intake of each food group. Representative values of the moisture, hydrogen, and carbon contents for the four food groups were calculated using the annual weighting factor and the fractions of moisture, hydrogen, and carbon of individual food stuff based on the sixth revision of Food Composition Table published by the Rural Living Science Research Institute (RLSI). Results The weighting factor of rice in grain group was 95% on a yearly basis. Those of Chinese cabbage in leafy vegetable group and radish in root vegetable group were 58% and 52%, respectively. The fruit consumption varied with seasons. Annual weighting factors of apple, persimmon, water melon, and pear in fruit were 21%, 18%, 17%, and 15%, respectively. The respective fractions of moisture in grain, leafy vegetable, root vegetable, and fruit were 10.8%, 93.0%, 88.3%, and 88.0%: those of hydrogen were 5.6%, 0.4%, 0.7%, and 0.74%: those of carbon were 39.68%, 2.84%, 4.98%, and 5.23%. The hydrogen fraction of root vegetable was 75% larger than that of leafy vegetable. The values of moisture, hydrogen, and carbon contents in agricultural vegetation calculated from the Food Composition

Estimation of dose from chromosome aberration rate

International Nuclear Information System (INIS)

Li Deping

1990-01-01

The methods and skills of evaluating dose from correctly scored shromsome aberration rate are presented, and supplemented with corresponding BASIC computer code. The possibility and preventive measures of excessive probability of missing score of the aberrations in some of the current routine score methods are discussed. The use of dose-effect relationship with exposure time correction factor G in evaluating doses and their confidence intervals, dose estimation in mixed n-γ exposure, and identification of high by nonuniform acute exposure to low LET radiation and its dose estimation are discussed in more detail. The difference of estimated dose due to whether the interaction between subleisoms produced by n and γ have been taken into account is examined. In fitting the standard dose-aberration rate curve, proper weighing of experiment points and comparison with commonly accepted values are emphasised, and the coefficient of variation σ y √y of the aberration rate y as a function of dose and exposure time is given. In appendix I and II, the dose-aberration rate formula is derived from dual action theory, and the time variation of subleisom is illustrated and in appendix III, the estimation of dose from scores of two different types of aberrations (of other related score) is illustrated. Two computer codes are given in appendix IV, one is a simple code, the other a complete code, including the fitting of standard curve. the skills of using compressed data storage, and the production of simulated 'data ' for testing the curve fitting procedure are also given

Relationship between kidney burden and radiation dose from chronic ingestion of U: Implications for radiation standards for the public

International Nuclear Information System (INIS)

Kocher, D.C.

1989-01-01

Metabolic models for U in adults recommended by Wrenn et al. (1985) and the International Commission on Radiological Protection (ICRP 1979a) were used to study the relationship between kidney burden and radiation dose from chronic ingestion of soluble 238U or natural U and whether current radiation standards for the public provide adequate protection against chemical toxicity from U in the kidney. We assumed that the threshold concentration for chemical toxicity is 1 microgram of U g-1 of kidney and that a safety factor of 10 should be applied in limiting kidney burdens for maximally exposed individuals in the general public. We found that a limit on annual effective dose equivalent of 1 mSv (0.1 rem) for chronic exposures of the public from all sources, as recommended by the ICRP (1985) and the National Council on Radiation Protection and Measurements (NCRP 1987), corresponds to concentrations of U in the kidney from chronic ingestion that exceed the assumed threshold for chemical toxicity of 1 microgram g-1 only for 238U using the metabolic model of the ICRP (1979a). However, using either metabolic model (ICRP 1979a; Wrenn et al. 1985), the predicted concentrations of U in the kidney exceeded the limit of 0.1 microgram g-1, based on the assumed safety factor for protection of the public, for both 238U and natural U. From these results, we concluded that chemical toxicity should be considered in developing health protection standards for the public for ingestion of soluble 238U or natural U. Environmental radiation standards for certain practices established by the U.S. Environmental Protection Agency and Nuclear Regulatory Commission (EPA 1987a, 1987b, 1987c, 1987d; NRC 1988a) are consistent with a limit on annual effective dose equivalent of 0.25 mSv (25 mrem) per practice. If the metabolic model of Wrenn et al. 27 references

Fetus dose estimate of a pregnant worker

International Nuclear Information System (INIS)

Castro, P.; Espana, M.L.; Sevillano, D.; Minguez, C.; Ferrer, C.; Lopez Franco, P.

2006-01-01

A female employee working in diagnostic radiology should take additional controls to protect the unborn child from ionizing radiations. The fetus is particularly sensitive to the effects of x-rays and, so, the determination of the equivalent dose to the unborn child is of interest for risk estimates from occupational exposures of the pregnant workers. The ian of this study is to develop a method for fetus dose estimate of a pregnant worker who participates in interventional radiology procedures. Factors for converting dosemeter readings to equivalent dose to the fetus have been measured using thermoluminescence dosimetry. Equivalent dose to the uterus is used to simulate the equivalent dose to the fetus during the first two months of pregnancy. Measurements at different depths are made to consider the variations in the position of the uterus between pregnant women. The normalized doses obtained are dependent on the beam quality. Accurate estimation of fetus doses due to occupational exposures can be made using the data provided in the current study. (Author)

Estimation of population dose from all sources in Japan

International Nuclear Information System (INIS)

Kusama, Tomoko; Nakagawa, Takeo; Kai, Michiaki; Yoshizawa, Yasuo

1988-01-01

The purposes of estimation of population doses are to understand the per-caput doses of the public member from each artificial radiation source and to determine the proportion contributed of the doses from each individual source to the total irradiated population. We divided the population doses into two categories: individual-related and source-related population doses. The individual-related population dose is estimated based on the maximum assumption for use in allocation of the dose limits for members of the public. The source-related population dose is estimated both to justify the sources and practices and to optimize radiation protection. The source-related population dose, therefore, should be estimated as realistically as possible. We investigated all sources that caused exposure to the population in Japan from the above points of view

Evaluation of the amount of 210Po ingested by the Spanish population and its relation to their diet habit

International Nuclear Information System (INIS)

Díaz-Francés, I.; García-Tenorio, R.; Mantero, J.; Manjón, G.

2013-01-01

In this work, the contribution of 210 Po to the committed effective dose via ingestion received by the Spanish population have been evaluated, by determining the 210 Po activity concentrations in an ample set of samples which can be considered representatives of the diet consumed in Spain. The obtained results show a quit high variability, preventing the possibility to fix a representative value for the 210 Po contribution to the ingestion doses received by the Spanish population, but in general these values, due exclusively to 210 Po, are higher than the average value assigned by UNSCEAR to the annual committed effective dose received by the worldwide population due to the ingestion of natural and anthropogenic radionuclides. Knowing the diet habits of the Spanish population and the 210 Po bioaccumulative behavior in the marine trophic chain, which implies enhanced concentration of 210 Po in the sea food in comparison with the obtained ones in other components of the diet, the variable and generally higher ingestion doses due to 210 Po received by the Spanish population can be associated to the variable and rich consumption of marine products. The Spanish population has the seafood as an essential component of his diet. Although the 210 Po levels in the edible parts of a great variety of marine organisms can be found in the literature in general the great majority of these determinations corresponds to raw edible products. But little is known about the effects of cooking on the 210 Po content of seafood which are normally cooked for human consumption. Then it is important to check if cooking can alter the 210 Po content in the seafood in order to refine the dose estimates to human consumers. Trying to cover this gap, and at the same time trying to confirm the key role of the seafood in the 210 Po ingestion doses received by the Spanish population, we have also analyzed the 210 Po content in the edible parts of several seafood products bought in commercial markets

Some radioactivity concentrations and ingestion dose projections arising from consumption of food containing Chernobyl contamination

International Nuclear Information System (INIS)

Paz, L.R. de la; Palattao, M.V.; Estacio, J.F.L.; Anden, A.

1987-04-01

Doses arising from the ingestion of radioactive contamination coming from Chernobyl accident are calculated using various radioactivity limits adopted by different organizations after the accident. These are compared with that allowed in the Philippines. Projected concentrations of Cs-137 and Cs-134 in various food items in the affected countries, one month and one year after the accident are calculated using a model proposed by Boone, Ng and Palms. Except for food produced in one or two hot spots, the projected concentrations after one year are expected to return to within the range of pre-Chernobyl values. (Auth.) 12 refs.; 13 tabs.; 6 figs

Doses due to tritium releases by NET - data base and relevant parameters on biological tritium behaviour

International Nuclear Information System (INIS)

Diabate, S.; Strack, S.

1990-12-01

This study gives an overview on the current knowledge about the behaviour of tritium in plants and in food chains in order to evaluate the ingestion pathway modelling of existing computer codes for dose estimations. The tritium uptake and retention by plants standing at the beginning of the food chains is described. The different chemical forms of tritium, which may be released into the atmosphere (HT, HTO and tritiated organics), and incorporation of tritium into organic material of plants are considered. Uptake and metabolism of tritiated compounds in animals and man are reviewed with particular respect to organically bound tritium and its significance for dose estimations. Some basic remarks on tritium toxicity are also included. Furthermore, a choice of computer codes for dose estimations due to chronic or accidental tritium releases has been compared with respect to the ingestion pathway. (orig.) [de

Oxycodone Ingestion Patterns in Acute Fracture Pain With Digital Pills.

Science.gov (United States)

Chai, Peter R; Carreiro, Stephanie; Innes, Brendan J; Chapman, Brittany; Schreiber, Kristin L; Edwards, Robert R; Carrico, Adam W; Boyer, Edward W

2017-12-01

Opioid analgesics are commonly prescribed on an as-needed (PRN) basis for acute painful conditions. Uncertainty of how patients actually take PRN opioids, coupled with a desire to completely cover pain, leads to variable and overly generous opioid prescribing practices, resulting in a surplus of opioids. This opioid surplus becomes a source for diversion and nonmedical opioid use. Understanding patterns of actual opioid ingestion after acute painful conditions can help clinicians counsel patients on safe opioid use, and allow timely recognition and intervention when escalating opioid self-dosing occurs, to prevent tolerance and addiction. We used a novel oxycodone digital pill system (ingestible biosensor within a standard gelatin capsule combined with 5-mg oxycodone) that when ingested, is activated by the chloride ion gradient in the stomach thereby emitting a radiofrequency signal captured by a wearable reader. The reader relays ingestion data to a cloud-based server that displays ingestion events to the study team. We deployed the oxycodone digital pill among opioid-naive individuals discharged from the emergency department with acute fracture pain. Participants were trained on digital pill operation and discharged with twenty-one 5-mg oxycodone digital pills. They were instructed to take digital pills PRN for pain on discharge. We conducted a brief interview 7 days after study enrollment, at which point participants returned the digital pill system. We identified oxycodone ingestion events in real time by data from the digital pill system and performed pill counts at the return visit to validate digital pill reporting of medication ingestion. In this study, 26 individuals were approached; 16 enrolled with 15 completing the study. Participants ingested a median of 6 (3-9.5) oxycodone digital pills over the course of 7 days, with 82% of the oxycodone dose ingested in the first 3 days. In individuals who required operative repair, 86% (N = 6) continued to ingest

PardNor - PARameters for ingestion dose models for NORdic areas. Status report for the NKS-B activity 2008

International Nuclear Information System (INIS)

Nielsen, S.P.; Andersson, K.G.

2009-03-01

The ECOSYS foodchain model is built into the European standard decision support systems ARGOS and RODOS, which are integrated in the preparedness for radiological events in the Nordic countries. However, a review has revealed that a number of parameters in ECOSYS do not reflect the current state-of-the-art knowledge, and do not adequately represent Nordic conditions. Improved and country/region specific data is required for ECOSYS to give trustworthy results. It is the aim of the PardNor activity to collect new data, and thus enable reliable use of ECOSYS for scenarios involving contamination of Nordic food production areas. In the reported work period of the PardNor activity, analyses have been performed for each Nordic country to determine the sensitivity of the ingestion dose end-point in ECOSYS to variation in 9 selected, potentially important parameters (human dietary components and animal fodder components). This parametric sensitivity was found to vary considerably between the different Nordic countries, reflecting considerable differences in diet and domestic production, and highlighting the importance of last year's work to identify appropriate location-specific parameters. A simple empirical Danish soil temperature based methodology for calculation of more reliable location-specific values of leaf area index (LAI) was tested for Swedish conditions and applied to estimate the seasonal LAI variation in other countries. The leaf area index reaches its maximum value much earlier in the southern parts of the Nordic region than in the northern. This means that the conditions for deposition and interception to vegetation would over a certain time span be very different in different Nordic areas. Also the influence on ECOSYS dose estimates of resuspension enrichment factors, leaching rates, fixation rates and desorption rates was investigated in the reported activity period, identifying new data sets where needed.(au)

PardNor - PARameters for ingestion dose models for NORdic areas. Status report for the NKS-B activity 2008

Energy Technology Data Exchange (ETDEWEB)

Nielsen, S.P.; Andersson, K.G. (Technical Univ. of Denmark, Risoe National Lab. for Sustainable Energy, Roskilde (Denmark))

2009-03-15

The ECOSYS foodchain model is built into the European standard decision support systems ARGOS and RODOS, which are integrated in the preparedness for radiological events in the Nordic countries. However, a review has revealed that a number of parameters in ECOSYS do not reflect the current state-of-the-art knowledge, and do not adequately represent Nordic conditions. Improved and country/region specific data is required for ECOSYS to give trustworthy results. It is the aim of the PardNor activity to collect new data, and thus enable reliable use of ECOSYS for scenarios involving contamination of Nordic food production areas. In the reported work period of the PardNor activity, analyses have been performed for each Nordic country to determine the sensitivity of the ingestion dose end-point in ECOSYS to variation in 9 selected, potentially important parameters (human dietary components and animal fodder components). This parametric sensitivity was found to vary considerably between the different Nordic countries, reflecting considerable differences in diet and domestic production, and highlighting the importance of last year's work to identify appropriate location-specific parameters. A simple empirical Danish soil temperature based methodology for calculation of more reliable location-specific values of leaf area index (LAI) was tested for Swedish conditions and applied to estimate the seasonal LAI variation in other countries. The leaf area index reaches its maximum value much earlier in the southern parts of the Nordic region than in the northern. This means that the conditions for deposition and interception to vegetation would over a certain time span be very different in different Nordic areas. Also the influence on ECOSYS dose estimates of resuspension enrichment factors, leaching rates, fixation rates and desorption rates was investigated in the reported activity period, identifying new data sets where needed.(au)

Animal data on GI-tract uptake of plutonium - implications for environmental dose assessments

International Nuclear Information System (INIS)

Kocher, D.C.; Ryan, M.T.

1983-01-01

A selection of published data on GI-tract uptake of ingested plutonium in animals is reviewed for the purpose of estimating an uptake fraction which would be appropriate for environmental dose assessments in adult humans. Recent data in the adult rat and guinea pig suggest that a GI-tract uptake fraction of 10 -3 would be a reasonable and prudent choice for ingestion of environmental plutonium by adults. This value is a factor of ten larger than the value currently recommended by the International Commission on Radiological Protection for assessing doses from occupational exposures. (author)

The effect of chronic progressive-dose sodium bicarbonate ingestion on CrossFit-like performance: A double-blind, randomized cross-over trial.

Science.gov (United States)

Durkalec-Michalski, Krzysztof; Zawieja, Emilia E; Podgórski, Tomasz; Łoniewski, Igor; Zawieja, Bogna E; Warzybok, Marta; Jeszka, Jan

2018-01-01

Sodium bicarbonate (SB) has been proposed as an ergogenic aid, as it improves high-intensity and resistance exercise performance. However, no studies have yet investigated SB application in CrossFit. This study examined the effects of chronic, progressive-dose SB ingestion on CrossFit-like performance and aerobic capacity. In a randomized, double-blind, cross-over trial, 21 CrossFit-trained participants were randomly allocated to 2 groups and underwent 2 trials separated by a 14-day washout period. Participants ingested either up to 150 mg∙kg-1 of SB in a progressive-dose regimen or placebo for 10 days. Before and after each trial, Fight Gone Bad (FGB) and incremental cycling (ICT) tests were performed. In order to examine biochemical responses, blood samples were obtained prior to and 3 min after completing each exercise test. No gastrointestinal (GI) side effects were reported during the entire protocol. The overall FGB performance improved under SB by ~6.1% (pCrossFit-like performance, as well as delayed ventilatory threshold occurrence.

Dose-response effects in an outbreak of Salmonella enteritidis.

Science.gov (United States)

Mintz, E D; Cartter, M L; Hadler, J L; Wassell, J T; Zingeser, J A; Tauxe, R V

1994-02-01

The effects of ingested Salmonella enteritidis (SE) dose on incubation period and on the severity and duration of illness were estimated in a cohort of 169 persons who developed gastroenteritis after eating hollandaise sauce made from grade-A shell eggs. The cohort was divided into three groups based on self-reported dose of sauce ingested. As dose increased, median incubation period decreased (37 h in the low exposure group v. 21 h in the medium exposure group v. 17.5 h in the high exposure group, P = 0.006) and greater proportions reported body aches (71 v. 85 v. 94%, P = 0.0009) and vomiting (21 v. 56 v. 57%, P = 0.002). Among 118 case-persons who completed a follow-up questionnaire, increased dose was associated with increases in median weight loss in kilograms (3.2 v. 4.5 v. 5.0, P = 0.0001), maximum daily number of stools (12.5 v. 15.0 v. 20.0, P = 0.02), subjective rating of illness severity (P = 0.0007), and the number of days of confinement to bed (3.0 v. 6.5 v. 6.5, P = 0.04). In this outbreak, ingested dose was an important determinant of the incubation period, symptoms and severity of acute salmonellosis.

Occupational dose estimates for a monitored retrievable storage facility

International Nuclear Information System (INIS)

Harty, R.; Stoetzel, G.A.

1986-06-01

Occupational doses were estimated for radiation workers at the monitored retrievable storage (MRS) facility. This study provides an estimate of the occupational dose based on the current MRS facility design, examines the extent that various design parameters and assumptions affect the dose estimates, and identifies the areas and activities where exposures can be reduced most effectively. Occupational doses were estimated for both the primary storage concept and the alternate storage concept. The dose estimates indicate the annual dose to all radiation workers will be below the 5 rem/yr federal dose equivalent limit. However, the estimated dose to most of the receiving and storage crew (the workers responsible for the receipt, storage, and surveillance of the spent fuel and its subsequent retrieval), to the crane maintenance technicians, and to the cold and remote maintenance technicians is above the design objective of 1 rem/yr. The highest annual dose is received by the riggers (4.7 rem) in the receiving and storage crew. An indication of the extent to which various design parameters and assumptions affect the dose estimates was obtained by changing various design-based assumptions such as work procedures, background dose rates in radiation zones, and the amount of fuel received and stored annually. The study indicated that a combination of remote operations, increased shielding, and additional personnel (for specific jobs) or changes in operating procedures will be necessary to reduce worker doses below 1.0 rem/yr. Operations that could be made at least partially remote include the removal and replacement of the tiedowns, impact limiters, and personnel barriers from the shipping casks and the removal or installation of the inner closure bolts. Reductions of the background dose rates in the receiving/shipping and the transfer/discharge areas may be accomplished with additional shielding

Estimated Daily Average Per Capita Water Ingestion by Child and Adult Age Categories Based on USDA's 1994-96 and 1998 Continuing Survey of Food Intakes by Individuals (Journal Article)

Science.gov (United States)

Current water ingestion estimates are important for the assessment of risk to human populations of exposure to water-borne pollutants. This paper reports mean and percentile estimates of the distributions of daily average per capita water ingestion for 12 age range groups. The a...

Methodology for calculation of doses to man and implementation in Pandora

Energy Technology Data Exchange (ETDEWEB)

Avila, Rodolfo [Facilia AB, Bromma (Sweden); Bergstroem, Ulla [Swepro Project Management AB, Solna (Sweden)

2006-07-15

This report describes methods and data for calculation of doses to man to be used in safety assessments of repositories for nuclear fuel. The methods are based on the latest recommendations from the ICRP; the EU and the national radiation protection authorities. Equations are given for calculation of doses from ingestion of contaminated water and food, inhalation of contaminated air and external exposure from radionuclides in the ground. With the exception of the exposure from food ingestion, the equations are the same used in previous safety assessments. A general equation is suggested for estimation of the exposure from food ingestion, in which the annual demand of carbon is used instead of the annual ingestion of different food-stuffs, which was earlier applied. The report contains tables with recommended values for physiological characteristics such as water intake, food intake and inhalation rates, based on information summarised in an Appendix. Furthermore, tables are given with recommended age dependent dose conversion factors for ingestion and inhalation for a number of nuclides of interest for safety assessments. The most recently published dose conversion factors for external exposure from contaminated ground are also given. An overview of the implementation of the methodology in Pandora, which is the tool that SKB and Posiva currently use for biosphere modelling, is also provided. The work presented in the report is a result from a joint project commissioned by SKB and Posiva.

Methodology for calculation of doses to man and implementation in Pandora

International Nuclear Information System (INIS)

Avila, Rodolfo; Bergstroem, Ulla

2006-07-01

This report describes methods and data for calculation of doses to man to be used in safety assessments of repositories for nuclear fuel. The methods are based on the latest recommendations from the ICRP; the EU and the national radiation protection authorities. Equations are given for calculation of doses from ingestion of contaminated water and food, inhalation of contaminated air and external exposure from radionuclides in the ground. With the exception of the exposure from food ingestion, the equations are the same used in previous safety assessments. A general equation is suggested for estimation of the exposure from food ingestion, in which the annual demand of carbon is used instead of the annual ingestion of different food-stuffs, which was earlier applied. The report contains tables with recommended values for physiological characteristics such as water intake, food intake and inhalation rates, based on information summarised in an Appendix. Furthermore, tables are given with recommended age dependent dose conversion factors for ingestion and inhalation for a number of nuclides of interest for safety assessments. The most recently published dose conversion factors for external exposure from contaminated ground are also given. An overview of the implementation of the methodology in Pandora, which is the tool that SKB and Posiva currently use for biosphere modelling, is also provided. The work presented in the report is a result from a joint project commissioned by SKB and Posiva

The Northern Marshall Islands Radiological Survey: data and dose assessments.

Science.gov (United States)

Robison, W L; Noshkin, V E; Conrado, C L; Eagle, R J; Brunk, J L; Jokela, T A; Mount, M E; Phillips, W A; Stoker, A C; Stuart, M L; Wong, K M

1997-07-01

Fallout from atmospheric nuclear tests, especially from those conducted at the Pacific Proving Grounds between 1946 and 1958, contaminated areas of the Northern Marshall Islands. A radiological survey at some Northern Marshall Islands was conducted from September through November 1978 to evaluate the extent of residual radioactive contamination. The atolls included in the Northern Marshall Islands Radiological Survey (NMIRS) were Likiep, Ailuk, Utirik, Wotho, Ujelang, Taka, Rongelap, Rongerik, Bikar, Ailinginae, and Mejit and Jemo Islands. The original test sites, Bikini and Enewetak Atolls, were also visited on the survey. An aerial survey was conducted to determine the external gamma exposure rate. Terrestrial (soil, food crops, animals, and native vegetation), cistern and well water samples, and marine (sediment, seawater, fish and clams) samples were collected to evaluate radionuclide concentrations in the atoll environment. Samples were processed and analyzed for 137Cs, 90Sr, 239+240Pu and 241Am. The dose from the ingestion pathway was calculated using the radionuclide concentration data and a diet model for local food, marine, and water consumption. The ingestion pathway contributes 70% to 90% of the estimated dose. Approximately 95% of the dose is from 137Cs. 90Sr is the second most significant radionuclide via ingestion. External gamma exposure from 137Cs accounts for about 10% to 30% of the dose. 239+240Pu and 241Am are the major contributors to dose via the inhalation pathway; however, inhalation accounts for only about 1% of the total estimated dose, based on surface soil levels and resuspension studies. All doses are computed for concentrations decay corrected to 1996. The maximum annual effective dose from manmade radionuclides at these atolls ranges from .02 mSv y(-1) to 2.1 mSv y(-1). The background dose in the Marshall Islands is estimated to be 2.4 mSv y(-1). The combined dose from both background and bomb related radionuclides ranges from slightly

Transmission dose estimation algorithm for in vivo dosimetry

International Nuclear Information System (INIS)

Yun, Hyong Geun; Shin, Kyo Chul; Huh, Soon Nyung; Woo, Hong Gyun; Ha, Sung Whan; Lee, Hyoung Koo

2002-01-01

Measurement of transmission dose is useful for in vivo dosimetry of QA purpose. The objective of this study is to develope an algorithm for estimation of tumor dose using measured transmission dose for open radiation field. Transmission dose was measured with various field size (FS), phantom thickness (Tp), and phantom chamber distance (PCD) with an acrylic phantom for 6 MV and 10 MV X-ray. Source to chamber distance (SCD) was set to 150 cm. Measurement was conducted with a 0.6 cc Farmer type ion chamber. Using measured data and regression analysis, an algorithm was developed for estimation of expected reading of transmission dose. Accuracy of the algorithm was tested with flat solid phantom with various settings. The algorithm consisted of quadratic function of log(A/P) (where A/P is area-perimeter ratio) and tertiary function of PCD. The algorithm could estimate dose with very high accuracy for open square field, with errors within ±0.5%. For elongated radiation field, the errors were limited to ±1.0%. The developed algorithm can accurately estimate the transmission dose in open radiation fields with various treatment settings

Transmission dose estimation algorithm for in vivo dosimetry

Energy Technology Data Exchange (ETDEWEB)

Yun, Hyong Geun; Shin, Kyo Chul [Dankook Univ., Seoul (Korea, Republic of); Huh, Soon Nyung; Woo, Hong Gyun; Ha, Sung Whan [Seoul National Univ., Seoul (Korea, Republic of); Lee, Hyoung Koo [Catholic Univ., Seoul (Korea, Republic of)

2002-07-01

Measurement of transmission dose is useful for in vivo dosimetry of QA purpose. The objective of this study is to develope an algorithm for estimation of tumor dose using measured transmission dose for open radiation field. Transmission dose was measured with various field size (FS), phantom thickness (Tp), and phantom chamber distance (PCD) with an acrylic phantom for 6 MV and 10 MV X-ray. Source to chamber distance (SCD) was set to 150 cm. Measurement was conducted with a 0.6 cc Farmer type ion chamber. Using measured data and regression analysis, an algorithm was developed for estimation of expected reading of transmission dose. Accuracy of the algorithm was tested with flat solid phantom with various settings. The algorithm consisted of quadratic function of log(A/P) (where A/P is area-perimeter ratio) and tertiary function of PCD. The algorithm could estimate dose with very high accuracy for open square field, with errors within {+-}0.5%. For elongated radiation field, the errors were limited to {+-}1.0%. The developed algorithm can accurately estimate the transmission dose in open radiation fields with various treatment settings.

Considerations on absorbed dose estimates based on different β-dose point kernels in internal dosimetry

International Nuclear Information System (INIS)

Uchida, Isao; Yamada, Yasuhiko; Yamashita, Takashi; Okigaki, Shigeyasu; Oyamada, Hiyoshimaru; Ito, Akira.

1995-01-01

In radiotherapy with radiopharmaceuticals, more accurate estimates of the three-dimensional (3-D) distribution of absorbed dose is important in specifying the activity to be administered to patients to deliver a prescribed absorbed dose to target volumes without exceeding the toxicity limit of normal tissues in the body. A calculation algorithm for the purpose has already been developed by the authors. An accurate 3-D distribution of absorbed dose based on the algorithm is given by convolution of the 3-D dose matrix for a unit cubic voxel containing unit cumulated activity, which is obtained by transforming a dose point kernel into a 3-D cubic dose matrix, with the 3-D cumulated activity distribution given by the same voxel size. However, beta-dose point kernels affecting accurate estimates of the 3-D absorbed dose distribution have been different among the investigators. The purpose of this study is to elucidate how different beta-dose point kernels in water influence on the estimates of the absorbed dose distribution due to the dose point kernel convolution method by the authors. Computer simulations were performed using the MIRD thyroid and lung phantoms under assumption of uniform activity distribution of 32 P. Using beta-dose point kernels derived from Monte Carlo simulations (EGS-4 or ACCEPT computer code), the differences among their point kernels gave little differences for the mean and maximum absorbed dose estimates for the MIRD phantoms used. In the estimates of mean and maximum absorbed doses calculated using different cubic voxel sizes (4x4x4 mm and 8x8x8 mm) for the MIRD thyroid phantom, the maximum absorbed doses for the 4x4x4 mm-voxel were estimated approximately 7% greater than the cases of the 8x8x8 mm-voxel. They were found in every beta-dose point kernel used in this study. On the other hand, the percentage difference of the mean absorbed doses in the both voxel sizes for each beta-dose point kernel was less than approximately 0.6%. (author)

Collective effective dose equivalent, population doses and risk estimates from occupational exposures in Japan

International Nuclear Information System (INIS)

Maruyama, Takashi; Nishizawa, Kanae; Kumamoto, Yoshikazu; Iwai, Kazuo; Mase, Naomichi.

1993-01-01

Collective dose equivalent and population dose from occupational exposures in Japan, 1988 were estimated on the basis of a nationwide survey. The survey was conducted on annual collective dose equivalents by sex, age group and type of radiation work for about 0.21 million workers except for the workers in nuclear power stations. The data on the workers in nuclear power stations were obtained from the official report of the Japan Nuclear Safety Commission. The total number of workers including nuclear power stations was estimated to be about 0.26 million. Radiation works were subdivided as follows: medical works including dental; non-atomic energy industry; research and education; atomic energy industry and nuclear power station. For the determination of effective dose equivalent and population dose, organ or tissue doses were measured with a phantom experiment. The resultant doses were compared with the doses previously calculated using a chord length technique and with data from ICRP publications. The annual collective effective dose equivalent were estimated to be about 21.94 person·Sv for medical workers, 7.73 person·Sv for industrial workers, 0.75 person·Sv for research and educational workers, 2.48 person·Sv for atomic energy industry and 84.4 person ·Sv for workers in nuclear power station. The population doses were calculated to be about 1.07 Sv for genetically significant dose, 0.89 Sv for leukemia significant dose and 0.42 Sv for malignant significant dose. The population risks were estimated using these population doses. (author)

Adult head CT scans: the uncertainties of effective dose estimates

International Nuclear Information System (INIS)

Gregory, Kent J.; Bibbo, Giovanni; Pattison, John E.

2008-01-01

Full Text: CT scanning is a high dose imaging modality. Effective dose estimates from CT scans can provide important information to patients and medical professionals. For example, medical practitioners can use the dose to estimate the risk to the patient, and judge whether this risk is outweighed by the benefits of the CT examination, while radiographers can gauge the effect of different scanning protocols on the patient effective dose, and take this into consideration when establishing routine scan settings. Dose estimates also form an important part of epidemiological studies examining the health effects of medical radiation exposures on the wider population. Medical physicists have been devoting significant effort towards estimating patient radiation doses from diagnostic CT scans for some years. The question arises: How accurate are these effective dose estimates? The need for a greater understanding and improvement of the uncertainties in CT dose estimates is now gaining recognition as an important issue (BEIR VII 2006). This study is an attempt to analyse and quantify the uncertainty components relating to effective dose estimates from adult head CT examinations that are calculated with four commonly used methods. The dose estimation methods analysed are the Nagel method, the ImpaCT method, the Wellhoefer method and the Dose-Length Product (DLP) method. The analysis of the uncertainties was performed in accordance with the International Standards Organisation's Guide to the Expression of Uncertainty in Measurement as discussed in Gregory et al (Australas. Phys. Eng. Sci. Med., 28: 131-139, 2005). The uncertainty components vary, depending on the method used to derive the effective dose estimate. Uncertainty components in this study include the statistical and other errors from Monte Carlo simulations, uncertainties in the CT settings and positions of patients in the CT gantry, calibration errors from pencil ionization chambers, the variations in the organ

Distribution of 226Ra and 228Ra in drinking water and dose assessment

International Nuclear Information System (INIS)

Ajay Kumar; Sugandhi, S.; Usha, N.; Rupali, K.; Gurg, R.P.

2002-01-01

The radioactivity concentrations of 226 Ra and 228 Ra have been analysed in 123 drinking water samples received from different regions of India. The maximum concentrations of 226 Ra and 228 Ra in drinking water are 8 mBq/l and 11.5 mBq/l respectively. The higher doses due to intake of 228 Ra through drinking water suggests that 228 Ra should also be measured in the assessment of ingestion dose to the population. The estimated committed effective doses range from 0.082 to 2.45 μSv/year and from 1.53 to 8.81 μSv/year for the ingestion of 226 Ra and 228 Ra respectively. (author)

Fast skin dose estimation system for interventional radiology.

Science.gov (United States)

Takata, Takeshi; Kotoku, Jun'ichi; Maejima, Hideyuki; Kumagai, Shinobu; Arai, Norikazu; Kobayashi, Takenori; Shiraishi, Kenshiro; Yamamoto, Masayoshi; Kondo, Hiroshi; Furui, Shigeru

2018-03-01

To minimise the radiation dermatitis related to interventional radiology (IR), rapid and accurate dose estimation has been sought for all procedures. We propose a technique for estimating the patient skin dose rapidly and accurately using Monte Carlo (MC) simulation with a graphical processing unit (GPU, GTX 1080; Nvidia Corp.). The skin dose distribution is simulated based on an individual patient's computed tomography (CT) dataset for fluoroscopic conditions after the CT dataset has been segmented into air, water and bone based on pixel values. The skin is assumed to be one layer at the outer surface of the body. Fluoroscopic conditions are obtained from a log file of a fluoroscopic examination. Estimating the absorbed skin dose distribution requires calibration of the dose simulated by our system. For this purpose, a linear function was used to approximate the relation between the simulated dose and the measured dose using radiophotoluminescence (RPL) glass dosimeters in a water-equivalent phantom. Differences of maximum skin dose between our system and the Particle and Heavy Ion Transport code System (PHITS) were as high as 6.1%. The relative statistical error (2 σ) for the simulated dose obtained using our system was ≤3.5%. Using a GPU, the simulation on the chest CT dataset aiming at the heart was within 3.49 s on average: the GPU is 122 times faster than a CPU (Core i7-7700K; Intel Corp.). Our system (using the GPU, the log file, and the CT dataset) estimated the skin dose more rapidly and more accurately than conventional methods.

CY 1995 radiation dose reconciliation report and resulting CY 1996 dose estimate for the 324 nuclear facility

International Nuclear Information System (INIS)

Landsman, S.D.; Thornhill, R.E.; Peterson, C.A.

1996-04-01

In this report, the dose estimate for CY 1995 is reconciled by month wih actual doses received. Results of the reconciliation were used to revise estimates of worker dose for CY 1996. Resulting dose estimate for the facility is also included. Support for two major programs (B-Cell Cleanout and Surveillance and Maintenance) accounts for most of the exposure received by workers in the faility. Most of the expousre received by workers comes from work in the Radiochemical Engineering Complex airlock. In spite of schedule and work scope changes during CY 1995, dose estimates were close to actual exposures received. A number of ALARA measures were taken throughout the year; exposure reduction due to those was 20.6 Man-Rem, a 28% reduction from the CY 1995 estimate. Baseline estimates for various tasks in the facility were used to compile the CY 1996 dose estimate of 45.4 Man-Rem; facility goal for CY 1996 is to reduce worker dose by 20%, to 36.3 Man-Rem

Radionuclides in food and the radiation exposure due to ingestion; Radionuklide in Lebensmitteln und die Strahlenexposition durch Ingestion

Energy Technology Data Exchange (ETDEWEB)

Michel, Rolf

2015-06-01

As a consequence of the reactor accidents in Fukushima Daiichi high amounts of radioactive iodine and cesium isotopes were released into the terrestrial and marine Japanese environment. The largest release occurred on March 15, 2011 as a consequence of the containment failure of unit 2. Due to the meteorological conditions large area fallout occurred in the district of Fukushima. Other prefectures in the north of Japan were also contaminated. As a consequence of the high surface contamination the dose limits for drinking water, milk and milky products and food were increased to 200 Bq/kg.It turned out that the contamination of rice was marginal, the contamination of predatory fish higher than that of non-predatory fish. A systematic investigation of food samples could allow a better estimation of ingestion induced exposure.

Dose-dependent increases in flow-mediated dilation following acute cocoa ingestion in healthy older adults

Science.gov (United States)

Feehan, Robert P.; Kunselman, Allen R.; Preston, Amy G.; Miller, Debra L.; Lott, Mary E. J.

2011-01-01

An inverse relation exists between intake of flavonoid-rich foods, such as cocoa, and cardiovascular-related mortality. Favorable effects of flavonoids on the endothelium may underlie these associations. We performed a randomized, double-blind, placebo-controlled study to test the hypothesis that acute cocoa ingestion dose dependently increases endothelium-dependent vasodilation, as measured by an increase in brachial artery flow-mediated dilation (FMD), in healthy older adults. Measurements were obtained before (preingestion) and after (1- and 2-h postingestion) ingestion of 0 (placebo), 2, 5, 13, and 26 g of cocoa in 23 adults (63 ± 2 yr old, mean ± SE). Changes in brachial artery FMD 1- and 2-h postingestion compared with preingestion were used to determine the effects of cocoa. FMD was unchanged 1 (Δ−0.3 ± 0.2%)- and 2-h (Δ0.1 ± 0.1%) after placebo (0 g cocoa). In contrast, FMD increased both 1-h postingestion (2 g cocoa Δ0.0 ± 0.2%, 5 g cocoa Δ0.8 ± 0.3%, 13 g cocoa Δ1.0 ± 0.3%, and 26 g cocoa Δ1.6 ± 0.3%: P FMD 1- and 2-h postingestion (r = 0.44–0.48; both P FMD in healthy older humans. These responses may help to explain associations between flavonoid intake and cardiovascular-related mortality in humans. PMID:21903881

Methodology for calculation of doses to man and implementation in Pandora

International Nuclear Information System (INIS)

Avila, R.; Bergstroem, U.

2006-07-01

This report describes methods and data for calculation of doses to man to be used in safety assessments of repositories for nuclear fuel. The methods are based on the latest recommendations from the ICRP, the EU and the national radiation protection authorities. Equations are given for calculation of doses from ingestion of contaminated water and food, inhalation of contaminated air and external exposure from radionuclides in the ground. With the exception of the exposure from food ingestion, the equations are the same used in previous safety assessments. A general equation is suggested for estimation of the exposure from food ingestion, in which the annual demand of carbon is used instead of the annual ingestion of different foodstuffs, which was earlier applied. The report contains tables with recommended values for physiological characteristics such as water intake, food intake and inhalation rates, based on information summarised in an Appendix. Furthermore, tables are given with recommended age dependent dose conversion factors for ingestion and inhalation for a number of nuclides of interest for safety assessments. The most recently published dose conversion factors for external exposure from contaminated ground are also given. An overview of the implementation of the methodology in Pandora, which is the tool that Posiva and SKB currently use for biosphere modelling, is also provided. The work presented in the report is a result from a joint project commissioned by Svensk Kaernbraenslehantering AB (SKB) and Posiva. The report will be printed also as a SKB report R-06-68. (orig.)

beta. and. gamma. -comparative dose estimates on Enewetak Atoll

Energy Technology Data Exchange (ETDEWEB)

Crase, K.W.; Gudiksen, P.H.; Robison, W.L. (California Univ., Livermore (USA). Lawrence Livermore National Lab.)

1982-05-01

Enewetak Atoll in the Pacific is used for atmospheric testing of U.S. nuclear weapons. Beta dose and ..gamma..-ray exposure measurements were made on two islands of the Enewetak Atoll during July-August 1976 to determine the ..beta.. and low energy ..gamma..-contribution to the total external radiation doses to the returning Marshallese. Measurements were made at numerous locations with thermoluminescent dosimeters (TLD), pressurized ionization chambers, portable NaI detectors, and thin-window pancake GM probes. Results of the TLD measurements with and without a ..beta..-attenuator indicate that approx. 29% of the total dose rate at 1 m in air is due to ..beta..- or low energy ..gamma..-contribution. The contribution at any particular site, however, is reduced by vegetation. Integral 30-yr external shallow dose estimates for future inhabitants were made and compared with external dose estimates of a previous large scale radiological survey. Integral 30-yr shallow external dose estimates are 25-50% higher than whole body estimates. Due to the low penetrating ability of the ..beta..'s or low energy ..gamma..'s, however, several remedial actions can be taken to reduce the shallow dose contribution to the total external dose.

Methodology for estimating radiation dose rates to freshwater biota exposed to radionuclides in the environment

International Nuclear Information System (INIS)

Blaylock, B.G.; Frank, M.L.; O'Neal, B.R.

1993-08-01

The purpose of this report is to present a methodology for evaluating the potential for aquatic biota to incur effects from exposure to chronic low-level radiation in the environment. Aquatic organisms inhabiting an environment contaminated with radioactivity receive external radiation from radionuclides in water, sediment, and from other biota such as vegetation. Aquatic organisms receive internal radiation from radionuclides ingested via food and water and, in some cases, from radionuclides absorbed through the skin and respiratory organs. Dose rate equations, which have been developed previously, are presented for estimating the radiation dose rate to representative aquatic organisms from alpha, beta, and gamma irradiation from external and internal sources. Tables containing parameter values for calculating radiation doses from selected alpha, beta, and gamma emitters are presented in the appendix to facilitate dose rate calculations. The risk of detrimental effects to aquatic biota from radiation exposure is evaluated by comparing the calculated radiation dose rate to biota to the U.S. Department of Energy's (DOE's) recommended dose rate limit of 0.4 mGy h -1 (1 rad d -1 ). A dose rate no greater than 0.4 mGy h -1 to the most sensitive organisms should ensure the protection of populations of aquatic organisms. DOE's recommended dose rate is based on a number of published reviews on the effects of radiation on aquatic organisms that are summarized in the National Council on Radiation Protection and Measurements Report No. 109 (NCRP 1991). DOE recommends that if the results of radiological models or dosimetric measurements indicate that a radiation dose rate of 0. 1 mGy h -1 will be exceeded, then a more detailed evaluation of the potential ecological consequences of radiation exposure to endemic populations should be conducted

Maximum likelihood estimation for cytogenetic dose-response curves

International Nuclear Information System (INIS)

Frome, E.L.; DuFrain, R.J.

1986-01-01

In vitro dose-response curves are used to describe the relation between chromosome aberrations and radiation dose for human lymphocytes. The lymphocytes are exposed to low-LET radiation, and the resulting dicentric chromosome aberrations follow the Poisson distribution. The expected yield depends on both the magnitude and the temporal distribution of the dose. A general dose-response model that describes this relation has been presented by Kellerer and Rossi (1972, Current Topics on Radiation Research Quarterly 8, 85-158; 1978, Radiation Research 75, 471-488) using the theory of dual radiation action. Two special cases of practical interest are split-dose and continuous exposure experiments, and the resulting dose-time-response models are intrinsically nonlinear in the parameters. A general-purpose maximum likelihood estimation procedure is described, and estimation for the nonlinear models is illustrated with numerical examples from both experimental designs. Poisson regression analysis is used for estimation, hypothesis testing, and regression diagnostics. Results are discussed in the context of exposure assessment procedures for both acute and chronic human radiation exposure

Determination of water, hydrogen, and carbon content of Korean main farm produces for the calculation of H-3 and C-14 ingestion dose

International Nuclear Information System (INIS)

Chung, Yang Geun; Lee, Gab Bock; Kim, Mi Ja; Eum, Hee Moon

2003-01-01

Water, hydrogen, and carbon content of grains, leafy vegetable, root vegetable, and fruits in Korea were determined to be used in the calculation of HTO, OBT, C-14 offsite ingestion dose. The individual items and the weighting factors of the 4 groups were based on the results of nationwide dietary intake survey in Korea. Items produced in an island or imported were excluded for the reason that they would not be affected directly by the nuclear power plants in the nation. On the same assumption, cooked and instant foods also were excluded. Items within 95% of the cumulative percentage of intake in each category were selected as the main farm produces, and then each intake percentage was taken as the weighting factor. Water, Hydrogen, and carbon content were determined using the data in Food Composition TABLE of Korea. H and C content were calculated from protein, fat, and carbohydrate content in the TABLE, and multiplied by each weighting factor to make the group-representative value. Grains, lefty and root vegetable, and fruits of Korea had 11.0%, 93.6%, 87.9%, 86.2% of water, 5.6%, 0.4%. 0.7%, 0.9% of hydrogen, and 39.6%, 2.5%, 5.2%, 6.0% of carbon, respectively. This is different from those in the ODCM from AECL data. Over ODCM, water content of grains and vegetable were 0.92-0.98 times ODCM, and fruits 1.03 times ODCM, which would result in the change of HTO ingestion dose as much. Hydrogen content of grains and vegetables are 1.02-2.33 times ODCM, but fruits 0.9 times ODCM. Carbon content of grains, leafy vegetables, and fruits are 0.7-0.98 times ODCM, but root vegetables 1.49 times ODCM. This would result in the change of ingestion dose as much

Bayesian estimation of dose rate effectiveness

International Nuclear Information System (INIS)

Arnish, J.J.; Groer, P.G.

2000-01-01

A Bayesian statistical method was used to quantify the effectiveness of high dose rate 137 Cs gamma radiation at inducing fatal mammary tumours and increasing the overall mortality rate in BALB/c female mice. The Bayesian approach considers both the temporal and dose dependence of radiation carcinogenesis and total mortality. This paper provides the first direct estimation of dose rate effectiveness using Bayesian statistics. This statistical approach provides a quantitative description of the uncertainty of the factor characterising the dose rate in terms of a probability density function. The results show that a fixed dose from 137 Cs gamma radiation delivered at a high dose rate is more effective at inducing fatal mammary tumours and increasing the overall mortality rate in BALB/c female mice than the same dose delivered at a low dose rate. (author)

The Northern Marshall Islands radiological survey: Data and dose assessments

International Nuclear Information System (INIS)

Robison, W.L.; Noshkin, V.E.; Conrado, C.L.

1997-01-01

Fallout from atmospheric nuclear tests, especially from those conducted at the Pacific Proving Grounds between 1946 and 1958, contaminated areas of the Northern Marshall Islands. A radiological survey at some Northern Marshall Islands was conducted from September through November 1978 to evaluate the extent of residual radioactive contamination. The atolls included in the Northern Marshall Islands Radiological Survey (NMIRS) were Likiep, Ailuk, Utirik, Wotho, Ujelang, Taka, Rongelap, Rongerik, Bikar, Ailinginae, and Mejit and Jemo Islands. The original test sites, Bikini and Enewetak Atolls, were also visited on the survey. An aerial survey was conducted to determine the external gamma exposure rate. Terrestrial (soil, food crops, animals, and native vegetation), cistern and well water samples, and marine (sediment, seawater, fish and clams) samples were collected to evaluate radionuclide concentrations in the atoll environment. Samples were processed and analyzed for 137 Cs, 90 Sr, 239+240 Pu and 241 Am. The dose from the ingestion pathway was calculated using the radionuclide concentration data and a diet model for local food, marine, and water consumption. The ingestion pathway contributes 70% to 90% of the estimated dose. Approximately 95% of the dose is from 137 Cs accounts for about 10% to 30% of the dose. 239+240 Pu and 241 Am are the major contributors to dose via the inhalation pathway; however, inhalation accounts for only about 1% of the total estimated dose, based on surface soil levels and resuspension studies. All doses are computed for concentrations decay corrected to 1996. The maximum annual effective dose from manmade radionuclides at these atolls ranges from .02 mSv y -1 . The background dose in the Marshall Islands is estimated to be 2.4 mSv y -1 to 4.5 mSv y -1 . The 50-y integral dose ranges from 0.5 to 65 mSv. 35 refs., 2 figs., 9 tabs

Nonparametric estimation of benchmark doses in environmental risk assessment

Science.gov (United States)

Piegorsch, Walter W.; Xiong, Hui; Bhattacharya, Rabi N.; Lin, Lizhen

2013-01-01

Summary An important statistical objective in environmental risk analysis is estimation of minimum exposure levels, called benchmark doses (BMDs), that induce a pre-specified benchmark response in a dose-response experiment. In such settings, representations of the risk are traditionally based on a parametric dose-response model. It is a well-known concern, however, that if the chosen parametric form is misspecified, inaccurate and possibly unsafe low-dose inferences can result. We apply a nonparametric approach for calculating benchmark doses, based on an isotonic regression method for dose-response estimation with quantal-response data (Bhattacharya and Kong, 2007). We determine the large-sample properties of the estimator, develop bootstrap-based confidence limits on the BMDs, and explore the confidence limits’ small-sample properties via a short simulation study. An example from cancer risk assessment illustrates the calculations. PMID:23914133

Ingestion of 210Po by public residing in and around Kalpakkam through dietary source

International Nuclear Information System (INIS)

Arunachalam, Kantha Deivi; Baskaran, Kamesh Viswanathan; Annamalai, Sathesh Kumar; Sivasubramanian, K.S.; Venkatraman, B.

2014-01-01

The distribution of naturally occurring radionuclide Polonium-210 ( 210 Po) activity in dietary source of Kalpakkam, Nuclear Power Plant, Tamil Nadu and its nearby region was studied. The 210 Po was analyzed in the food materials consumed by the male and female individuals (he/she) living in the study area of Kalpakkam (nuclear power plant) was done by 24-hr Duplicate Diet Study (DDS) and Market Basket Study (MBS). The MBS was done by collecting the food materials such as, cereals, fruits, nuts, leafy vegetables, other vegetables, fish, meat and milk collected from the study area. The DDS was done by collecting the food materials including the beverages consumed in 24 h from different age groups of male and female individuals living in surroundings of Kalpakkam. The intake and ingestion dose of the radionuclide 210 Po was estimated. The mean concentration of 210 Po in DDS (n= 33) was found to be 36 mBq.kg -1 of fresh weight. The MBS was collected based on food consumption representing more than 85-95% of annual supply, and were divided into 8 food groups. The mean concentration of 210 Po in 8 food groups namely leafy vegetables was 288 mBq.kg -1 (n=4), vegetables 33 mBq.kg -1 (n=12), fish 7294 mBq.kg -1 (n=5) and cereal 34 (n=1) mBq.kg -1 of fresh weight respectively. The remaining food categories such as nuts (n=1), fruits (n= 4), meat food (n= 2) and milk (n= 2) are below detection limit of 30 mBq.kg -1 fresh weight. The annual intake and ingestion dose due to 210 Po was estimated by DDS and MBS in adults, adolescents and children. Thereby, discussing the risk level of 210 Po ingestion to the local inhabitants in Kalpakkam region. (author)

SU-F-P-19: Fetal Dose Estimate for a High-Dose Fluoroscopy Guided Intervention Using Modern Data Tools

Energy Technology Data Exchange (ETDEWEB)

Moirano, J [University of Washington, Seattle, WA (United States)

2016-06-15

Purpose: An accurate dose estimate is necessary for effective patient management after a fetal exposure. In the case of a high-dose exposure, it is critical to use all resources available in order to make the most accurate assessment of the fetal dose. This work will demonstrate a methodology for accurate fetal dose estimation using tools that have recently become available in many clinics, and show examples of best practices for collecting data and performing the fetal dose calculation. Methods: A fetal dose estimate calculation was performed using modern data collection tools to determine parameters for the calculation. The reference point air kerma as displayed by the fluoroscopic system was checked for accuracy. A cumulative dose incidence map and DICOM header mining were used to determine the displayed reference point air kerma. Corrections for attenuation caused by the patient table and pad were measured and applied in order to determine the peak skin dose. The position and depth of the fetus was determined by ultrasound imaging and consultation with a radiologist. The data collected was used to determine a normalized uterus dose from Monte Carlo simulation data. Fetal dose values from this process were compared to other accepted calculation methods. Results: An accurate high-dose fetal dose estimate was made. Comparison to accepted legacy methods were were within 35% of estimated values. Conclusion: Modern data collection and reporting methods ease the process for estimation of fetal dose from interventional fluoroscopy exposures. Many aspects of the calculation can now be quantified rather than estimated, which should allow for a more accurate estimation of fetal dose.

Fallout 3H ingestion in Akita, Japan

International Nuclear Information System (INIS)

Hisamatsu, S.; Takizawa, Y.; Abe, T.; Katsumata, T.

1987-01-01

To study fallout 3 H ingestion in Japan, 16 separate food group samples were collected from Akita during 1985. The 3 H concentration in free water and that in a tissue-bound form were determined separately. The average 3 H concentration in the tissue-bound form was 2.2 Bq L-1, 1.7 times higher than in the free water of the food. The ingestions of 3 H in the tissue-bound form and as free water in the diet were 0.60 Bq d-1 and 1.0 Bq d-1, respectively. Cereals represented the food group that contributed the most to the ingestion of tissue-bound 3 H. Total 3 H ingestion was estimated to be 4.1 Bq d-1. The contribution of the tissue-bound form to the total ingestion was 15%, considerably lower than reported for Italian diets. The ratio of 3 H ingestion in the tissue-bound form to the free water form in the diet was similar to the ratio reported for New York City

Evaluation of soil-plant transfer factors of iodine. Estimation of annual ingestion for iodine from the diet

International Nuclear Information System (INIS)

Saas, Arsene.

1980-11-01

The author presents the iodine middle contents of the soils and vegetables. A synthesis on the iodine evolution in the soils and vegetables allows to conclude that the vegetable absorption of this isotope is correlated with the isotopiquely exchangeable iodine of the soil. The soil-plant transfer-factors are calculated for the vegetables, cereals, fruits from the stable iodine quantitative analysis. The annual iodine ingestion has been estimated from the dietary of the European Communites areas. This one is a little different of the quantity estimated by CRESTA-LACOURLY-R 2979, yet the contribution by consummation unity is different [fr

A Web-Based System for Bayesian Benchmark Dose Estimation.

Science.gov (United States)

Shao, Kan; Shapiro, Andrew J

2018-01-11

Benchmark dose (BMD) modeling is an important step in human health risk assessment and is used as the default approach to identify the point of departure for risk assessment. A probabilistic framework for dose-response assessment has been proposed and advocated by various institutions and organizations; therefore, a reliable tool is needed to provide distributional estimates for BMD and other important quantities in dose-response assessment. We developed an online system for Bayesian BMD (BBMD) estimation and compared results from this software with U.S. Environmental Protection Agency's (EPA's) Benchmark Dose Software (BMDS). The system is built on a Bayesian framework featuring the application of Markov chain Monte Carlo (MCMC) sampling for model parameter estimation and BMD calculation, which makes the BBMD system fundamentally different from the currently prevailing BMD software packages. In addition to estimating the traditional BMDs for dichotomous and continuous data, the developed system is also capable of computing model-averaged BMD estimates. A total of 518 dichotomous and 108 continuous data sets extracted from the U.S. EPA's Integrated Risk Information System (IRIS) database (and similar databases) were used as testing data to compare the estimates from the BBMD and BMDS programs. The results suggest that the BBMD system may outperform the BMDS program in a number of aspects, including fewer failed BMD and BMDL calculations and estimates. The BBMD system is a useful alternative tool for estimating BMD with additional functionalities for BMD analysis based on most recent research. Most importantly, the BBMD has the potential to incorporate prior information to make dose-response modeling more reliable and can provide distributional estimates for important quantities in dose-response assessment, which greatly facilitates the current trend for probabilistic risk assessment. https://doi.org/10.1289/EHP1289.

Dose Estimation from Daily and Weekly Dosimetry Data

International Nuclear Information System (INIS)

Ostrouchov, G.

2001-01-01

Statistical analyses of data from epidemiologic studies of workers exposed to radiation have been based on recorded annual radiation doses (yearly dose of record). It is usually assumed that the dose values are known exactly, although it is generally recognized that the data contain uncertainty due to measurement error and bias. In our previous work with weekly data, a probability distribution was used to describe an individual's dose during a specific period of time and statistical methods were developed for estimating it from weekly film dosimetry data. This study showed that the yearly dose of record systematically underestimates doses for Oak Ridge National Laboratory (ORNL) workers. This could result in biased estimates of dose-response coefficients and their standard errors. The results of this evaluation raise serious questions about the suitability of the yearly dose of record for direct use in low-dose studies of nuclear industry workers. Here, we extend our previous work to use full information in Pocket meter data and develop the Data Synthesis for Individual Dose Estimation (DSIDE) methodology. Although the DSIDE methodology in this study is developed in the context of daily and weekly data to produce a cumulative yearly dose estimate, in principle it is completely general and can be extended to other time period and measurement combinations. The new methodology takes into account the ''measurement error'' that is produced by the film and pocket-meter dosimetry systems, the biases introduced by policies that lead to recording left-censored doses as zeros, and other measurement and recording practices. The DSIDE method is applied to a sample of dose histories obtained from hard copy dosimetry records at ORNL for the years 1945 to 1955. First, the rigorous addition of daily pocket-meter information shows that the negative bias is generally more severe than was reported in our work based on weekly film data only, however, the amount of bias also varies

Dose Estimation from Daily and Weekly Dosimetry Data

Energy Technology Data Exchange (ETDEWEB)

Ostrouchov, G.

2001-11-16

Statistical analyses of data from epidemiologic studies of workers exposed to radiation have been based on recorded annual radiation doses (yearly dose of record). It is usually assumed that the dose values are known exactly, although it is generally recognized that the data contain uncertainty due to measurement error and bias. In our previous work with weekly data, a probability distribution was used to describe an individual's dose during a specific period of time and statistical methods were developed for estimating it from weekly film dosimetry data. This study showed that the yearly dose of record systematically underestimates doses for Oak Ridge National Laboratory (ORNL) workers. This could result in biased estimates of dose-response coefficients and their standard errors. The results of this evaluation raise serious questions about the suitability of the yearly dose of record for direct use in low-dose studies of nuclear industry workers. Here, we extend our previous work to use full information in Pocket meter data and develop the Data Synthesis for Individual Dose Estimation (DSIDE) methodology. Although the DSIDE methodology in this study is developed in the context of daily and weekly data to produce a cumulative yearly dose estimate, in principle it is completely general and can be extended to other time period and measurement combinations. The new methodology takes into account the ''measurement error'' that is produced by the film and pocket-meter dosimetry systems, the biases introduced by policies that lead to recording left-censored doses as zeros, and other measurement and recording practices. The DSIDE method is applied to a sample of dose histories obtained from hard copy dosimetry records at ORNL for the years 1945 to 1955. First, the rigorous addition of daily pocket-meter information shows that the negative bias is generally more severe than was reported in our work based on weekly film data only, however, the

Determination of the equivalent doses due to the ingestion of radionuclides from the uranium and thorium series presents in drinking waters of the region of Santa Luzia, Paraiba state, Brazil

International Nuclear Information System (INIS)

Pastura, Valeria F. da S.; Campos, Thomas F. da C.; Petta, Reinaldo A.

2011-01-01

This paper determined the original dose equivalents from radionuclides of uranium and thorium series in a drinking water of well which is supplied to the population of Santa Luzia, Paraiba state, Brazil. The collected waters are near to the mineralized phlegmatic bodies in rose quartz and amazonite feldspar. Radiometric measurements performed on the feldspar vein point out counting ratios surrounding 30000 cps and the analysis of collected samples of minerals presented tenors for the 226 Ra and 219 Pb varying from 0.50 to 2.30 Bq/sw. For determination of concentration of radionuclides U Total , 226 Ra, 228 Ra and 219 Pb, found in the not desalinated, two methods were used, spectrophotometry with arsenazo and radiochemistry, both realized in the CNEN-LAPOC laboratories. For the calculation of dose equivalent it was taken into consideration the following parameters: the dose coefficients for incorporation by ingestion for public individuals with ages over 17 years (Norma CNEN-NN-3.01, Regulatory Position 3.01/011) and daily ingestion of 4 liters of water, which is over the recommended by the WHO of 2L/day - 1993. The obtained values were compared with the reference value for compromised dose equivalent established by WHO for evaluate the risk potential to the health of population, by ingestion. The radionuclide concentrations in the wells varies from 0.054 to 0.21 Bq/L, resulting dose equivalents of 3.94 x 10 -3 mSv/year and 0.17 mSv/year in the studied population

Estimates of bias and uncertainty in recorded external dose

International Nuclear Information System (INIS)

Fix, J.J.; Gilbert, E.S.; Baumgartner, W.V.

1994-10-01

A study is underway to develop an approach to quantify bias and uncertainty in recorded dose estimates for workers at the Hanford Site based on personnel dosimeter results. This paper focuses on selected experimental studies conducted to better define response characteristics of Hanford dosimeters. The study is more extensive than the experimental studies presented in this paper and includes detailed consideration and evaluation of other sources of bias and uncertainty. Hanford worker dose estimates are used in epidemiologic studies of nuclear workers. A major objective of these studies is to provide a direct assessment of the carcinogenic risk of exposure to ionizing radiation at low doses and dose rates. Considerations of bias and uncertainty in the recorded dose estimates are important in the conduct of this work. The method developed for use with Hanford workers can be considered an elaboration of the approach used to quantify bias and uncertainty in estimated doses for personnel exposed to radiation as a result of atmospheric testing of nuclear weapons between 1945 and 1962. This approach was first developed by a National Research Council (NRC) committee examining uncertainty in recorded film badge doses during atmospheric tests (NRC 1989). It involved quantifying both bias and uncertainty from three sources (i.e., laboratory, radiological, and environmental) and then combining them to obtain an overall assessment. Sources of uncertainty have been evaluated for each of three specific Hanford dosimetry systems (i.e., the Hanford two-element film dosimeter, 1944-1956; the Hanford multi-element film dosimeter, 1957-1971; and the Hanford multi-element TLD, 1972-1993) used to estimate personnel dose throughout the history of Hanford operations. Laboratory, radiological, and environmental sources of bias and uncertainty have been estimated based on historical documentation and, for angular response, on selected laboratory measurements

beta- and gamma-Comparative dose estimates on Eniwetok Atoll

Energy Technology Data Exchange (ETDEWEB)

Crase, K.W.; Gudiksen, P.H.; Robison, W.L.

1982-05-01

Eniwetok Atoll is one of the Pacific atolls used for atmospheric testing of U.S. nuclear weapons. Beta dose and gamma-ray exposure measurements were made on two islands of the Eniwetok Atoll during July-August 1976 to determine the beta and low energy gamma-contribution to the total external radiation doses to the returning Marshallese. Measurements were made at numerous locations with thermoluminescent dosimeters (TLD), pressurized ionization chambers, portable NaI detectors, and thin-window pancake GM probes. Results of the TLD measurements with and without a beta-attenuator indicate that approx. 29% of the total dose rate at 1 m in air is due to beta- or low energy gamma-contribution. The contribution at any particular site, however, is somewhat dependent on ground cover, since a minimal amount of vegetation will reduce it significantly from that over bare soil, but thick stands of vegetation have little effect on any further reductions. Integral 30-yr external shallow dose estimates for future inhabitants were made and compared with external dose estimates of a previous large scale radiological survey (En73). Integral 30-yr shallow external dose estimates are 25-50% higher than whole body estimates. Due to the low penetrating ability of the beta's or low energy gamma's, however, several remedial actions can be taken to reduce the shallow dose contribution to the total external dose.

Automated dose estimation for lost or damaged dosimeters

International Nuclear Information System (INIS)

Thompson, W.L.; Deininger, R.J.

1988-01-01

This paper reports that some dosimetry vendors will compute doses for their customers' lost/damaged dosimeters based upon an average of recent dosimeter readings. However, the vendors usually require authorization from the customer for each such occurrence. Therefore, the tedious task of keeping track of the overdue status of each missing dosimeter and constantly notifying the vendor is still present. Also, depending on the monthly variability of a given person's doses, it may be more valid to use the employee's average dose, his/her highest dose over a recent period, an average dose of other employees with similar job duties for that period, or the maximum permissible dose. Thus, the task of estimating doses for lost/damaged dosimeters cannot be delegated to dosimetry vendor. Instead, the radiation safety department must sue the data supplied by the vendor as input for performing estimates. The process is performed automatically at the Medical Center Hospital of Vermont using a personal computer and a relational database

Convolution-based estimation of organ dose in tube current modulated CT

Science.gov (United States)

Tian, Xiaoyu; Segars, W. Paul; Dixon, Robert L.; Samei, Ehsan

2016-05-01

Estimating organ dose for clinical patients requires accurate modeling of the patient anatomy and the dose field of the CT exam. The modeling of patient anatomy can be achieved using a library of representative computational phantoms (Samei et al 2014 Pediatr. Radiol. 44 460-7). The modeling of the dose field can be challenging for CT exams performed with a tube current modulation (TCM) technique. The purpose of this work was to effectively model the dose field for TCM exams using a convolution-based method. A framework was further proposed for prospective and retrospective organ dose estimation in clinical practice. The study included 60 adult patients (age range: 18-70 years, weight range: 60-180 kg). Patient-specific computational phantoms were generated based on patient CT image datasets. A previously validated Monte Carlo simulation program was used to model a clinical CT scanner (SOMATOM Definition Flash, Siemens Healthcare, Forchheim, Germany). A practical strategy was developed to achieve real-time organ dose estimation for a given clinical patient. CTDIvol-normalized organ dose coefficients ({{h}\\text{Organ}} ) under constant tube current were estimated and modeled as a function of patient size. Each clinical patient in the library was optimally matched to another computational phantom to obtain a representation of organ location/distribution. The patient organ distribution was convolved with a dose distribution profile to generate {{≤ft(\\text{CTD}{{\\text{I}}\\text{vol}}\\right)}\\text{organ, \\text{convolution}}} values that quantified the regional dose field for each organ. The organ dose was estimated by multiplying {{≤ft(\\text{CTD}{{\\text{I}}\\text{vol}}\\right)}\\text{organ, \\text{convolution}}} with the organ dose coefficients ({{h}\\text{Organ}} ). To validate the accuracy of this dose estimation technique, the organ dose of the original clinical patient was estimated using Monte Carlo program with TCM profiles explicitly modeled. The

Estimation of 18FDG doses's cost

International Nuclear Information System (INIS)

Hamza, Fatma; Amouri, W.; Jardak, I.; Kallel, F.; Charfeddine, S.; Guermazi, F.

2013-01-01

The cyclotron facility, essentially for medical use, is far from being a simple establishment of a dedicated device to accelerate particles producing a beta plus emitter radioelement. The cyclotron site encompasses more over all necessary equipments for the production and the quality control of considered radiotracer that 18 FDG is just one example. This facility is subject to strict standards in terms of radiopharmaceutical production, radiation level, pressure level and airflow resulting in the production of a drug submitted to the MA (Marketing Authorization). These multiple factors directly influence the final cost of the dose that remains to be reachable by the patient. The aim of this work is to estimate the cost of a dose of 18 FDG to ensure financial viability of the project while accessible to the patient. The cost of the facility will entail the following: buildings and utilities, equipment and operational cost. This calculation is possible only if we define in advance the type of cyclotron, which is bound to the market needs in particular the number of PET facilities, the number of scans per day and the radioactive decay of radioelement. Our study represents a simulation that considers some hypothesis. We assumed that the cyclotron is installed in Sousse and that the PET facilities number (positon emission tomography) is 6 in which 4 are located 2 hours away. For a PET scan, the average dose per patient is about 350 MBq (5 MBq/kg) and the exam duration is about 45 minutes. Each center performs 10 tests per day. In terms of fees, we considered device and building's cost, facility amortization, consumables (target, marking accessories), maintenance, remuneration expense and the annual electricity consumption. All our calculations have been reported to the number of working days per year. The estimates were made outside the customs duties and technical assistance that may last up to 2 years. Requirements and needs were estimated at 5.4 curies per day. For

The estimation of occupational effective dose in diagnostic radiology with two dosimeters

International Nuclear Information System (INIS)

Niklason, L.T.; Marx, M.V.; Chan, Heang-Ping

1994-01-01

Annual effective dose limits have been proposed by national and international radiation protection committees. Radiation protection agencies must decide upon a method of converting the radiation dose measured from dosimeters to an estimate of effective dose. A proposed method for the estimation of effective dose from the radiation dose to two dosimeters is presented. Correction factors are applied to an over-apron collar dose and an under-apron dose to estimate the effective dose. Correction factors are suggested for two cases, both with and without a thyroid shield. Effective dose may be estimated by the under-apron dose plus 6% of the over-collar dose if a thyroid shield is not worn or plus 2% of the over-collar dose if a thyroid shield is worn. This method provides a reasonable estimate of effective dose that is independent of lead apron thickness and accounts for the use of a thyroid shield. 17 refs., 3 tabs

Estimates of external dose-rate conversion factors and internal dose conversion factors for selected radionuclides released from fusion facilities

Energy Technology Data Exchange (ETDEWEB)

Homma, Toshimitsu; Togawa, Orihiko [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

1996-11-01

This report provides a tabulation of both external dose-rate conversion factors and internal dose conversion factors using radioactive decay data in the updated Evaluated Nuclear Structure Data File (ENSDF) for selected 26 radionuclides and all their daughter radionuclides of potential importance in safety assessments of fusion facilities. The external dose-rate conversion factors for 21 target organs are tabulated for three exposure modes that are immersion in contaminated air, irradiation at a height of 1 m above a contaminated ground surface and immersion contaminated water. For internal exposure, committed dose equivalents, based on the methodology of ICRP Publication 30, in the same target organs per intake of unit activity are given for the inhalation and ingestion exposure pathways. The data presented here is intended to be generally used for safety assessments of fusion reactors. Comparisons of external effective dose-rate conversion factors and committed effective dose equivalents are made with the previous data from the independent data bases to provide quality assurance on our calculated results. There is generally good agreement among data from the independent data bases. The differences in the values of both effective dose-rate and dose conversion factors appeared are primarily due to differences in calculational methodology, the use of different radioactive decay data, and compilation errors. (author)

Cancer risks from ingestion of radiostrontium

Energy Technology Data Exchange (ETDEWEB)

Raabe, O. G.

2004-07-01

Studies have been conducted of the lifetime effects in 403 beagles of the skeletal uptake in seven logarithmically increasing dosage groups of ingested Sr-90. The Sr-90 was fed during skeletal developmental from mid-gestation to adulthood at age 540 days resulting in lifetime protracted beta radiation exposure of the skeleton and some adjacent tissues. Statistical analysis of all types of cancer deaths in the 403 exposed beagles and in 162 unexposed controls indicated that deaths caused by five types of cancer were significantly elevated by high level exposure to Sr-90; these were (1) myeloid leukemia, (2) bone sarcoma, (3) squamous cell carcinoma of periodontal origin, (4) nasal carcinoma, and (5) oral carcinoma. Dose response analysis of these radiation-induced cancer deaths showed non-linear relationships with marked thresholds. A mean lifetime skeletal absorbed dose of 22.5 +/-5.7 Gy SD (22.5 +/-5.7 Sv SD) was associated with the lowest dosage group in which any radiation induced cancer deaths were observed. Three-dimensional models of the observed dose-rate/time/response relationships were fir with maximum likelihood regression methods to describe the risks of death associated with the different types of radiation-induced cancer. The models show that a life-time virtual threshold for cancer risk occurs because the time required to induce cancer is longer at lower radiation dose rates and may exceed the natural life span. Scaling these results to predict human cancer risks from ingestion of Sr-90 shows negligible risks for people whose lifetime cumulative skeletal dose is less than 10 Sv. (Author)

Determination of 210Po in leafy vegetables and annual effective dose assessment to the inhabitants of Mumbai city, India

International Nuclear Information System (INIS)

Dubey, J.S.; Sahoo, S.K.; Mohapatra, S.; Patra, A.C.; Lenka, P.; Ravi, P.M.; Tripathi, R.M.; Nair, A.

2014-01-01

Present study deals with the measurement of activity concentration of 210 Po in leafy vegetable of Mumbai city and corresponding ingestion dose assessment to the population. 210 Po activity levels ranged from 44.5-183.3 with an average value of 81.8 mBq/kg. Minimum activity of 210 Po was found in shepu and maximum in methi. The concentration reported here is slightly more than the UNSCEAR value. The estimated total effective dose was found to vary from 0.3 - 1.4 with an average value of 0.6 μSv/y, which is about 1% of global average total ingestion dose due to 210 Po. (author)

Radiation dose in cardiac SPECT/CT: An estimation of SSDE and effective dose

International Nuclear Information System (INIS)

Abdollahi, Hamid; Shiri, Isaac; Salimi, Yazdan; Sarebani, Maghsoud; Mehdinia, Reza; Deevband, Mohammad Reza; Mahdavi, Seied Rabi; Sohrabi, Ahmad; Bitarafan-Rajabi, Ahmad

2016-01-01

Aims: The dose levels for Computed Tomography (CT) localization and attenuation correction of Single Photon Emission Computed Tomography (SPECT) are limited and reported as Volume Computed Tomography Dose Index (CTDIvol) and Dose-Length Product (DLP). This work presents CT dose estimation from Cardiac SPECT/CT based on new American Association of Physicists in Medicine (AAPM) Size Specific Dose Estimation (SSDE) parameter, effective dose, organ doses and also emission dose from nuclear issue. Material and methods: Myocardial perfusion SPECT/CT for 509 patients was included in the study. SSDE, effective dose and organ dose were calculated using AAPM guideline and Impact-Dose software. Data were analyzed using R and SPSS statistical software. Spearman-Pearson correlation test and linear regression models were used for finding correlations and relationships among parameters. Results: The mean CTDIvol was 1.34 mGy ± 0.19 and the mean SSDE was 1.7 mGy ± 0.16. The mean ± SD of effective dose from emission, CT and total dose were 11.5 ± 1.4, 0.49 ± 0.11 and 12.67 ± 1.73 (mSv) respectively. The mean ± SD of effective dose from emission, CT and total dose were 11.5 ± 1.4, 0.49 ± 0.11 and 12.67 ± 1.73 (mSv) respectively. The spearman test showed that correlation between body size and organ doses is significant except thyroid and red bone marrow. CTDIvol was strongly dependent on patient size, but SSDE was not. Emission dose was strongly dependent on patient weight, but its dependency was lower to effective diameter. Conclusion: The dose parameters including CTDIvol, DLP, SSDE, effective dose values reported here are very low and below the reference level. This data suggest that appropriate CT acquisition parameters in SPECT/CT localization and attenuation correction are very beneficial for patients and lowering cancer risks.

Radiation dose in cardiac SPECT/CT: An estimation of SSDE and effective dose

Energy Technology Data Exchange (ETDEWEB)

Abdollahi, Hamid, E-mail: Hamid_rbp@yahoo.com [Department of Medical Physics, School of Medicine, Iran University of Medical Sciences, Tehran (Iran, Islamic Republic of); Shiri, Isaac [Department of Medical Physics, School of Medicine, Iran University of Medical Sciences, Tehran (Iran, Islamic Republic of); Salimi, Yazdan [Biomedical Engineering and Medical Physics Department, Faculty of Medicine, Shahid Beheshti University of Medical Sciences, Tehran (Iran, Islamic Republic of); Sarebani, Maghsoud; Mehdinia, Reza [Department of Medical Physics, School of Medicine, Iran University of Medical Sciences, Tehran (Iran, Islamic Republic of); Deevband, Mohammad Reza [Biomedical Engineering and Medical Physics Department, Faculty of Medicine, Shahid Beheshti University of Medical Sciences, Tehran (Iran, Islamic Republic of); Mahdavi, Seied Rabi [Department of Medical Physics, School of Medicine, Iran University of Medical Sciences, Tehran (Iran, Islamic Republic of); Radiation Biology Research Center, Iran University of Medical Sciences, Tehran (Iran, Islamic Republic of); Sohrabi, Ahmad [Department of Biostatistics, School of Public Health, Iran University of Medical Sciences, Tehran (Iran, Islamic Republic of); Bitarafan-Rajabi, Ahmad, E-mail: bitarafan@hotmail.com [Department of Medical Physics, School of Medicine, Iran University of Medical Sciences, Tehran (Iran, Islamic Republic of); Department of Nuclear Medicine, Rajaei Cardiovascular, Medical and Research Center, Iran University of Medical Sciences, Tehran (Iran, Islamic Republic of)

2016-12-15

Aims: The dose levels for Computed Tomography (CT) localization and attenuation correction of Single Photon Emission Computed Tomography (SPECT) are limited and reported as Volume Computed Tomography Dose Index (CTDIvol) and Dose-Length Product (DLP). This work presents CT dose estimation from Cardiac SPECT/CT based on new American Association of Physicists in Medicine (AAPM) Size Specific Dose Estimation (SSDE) parameter, effective dose, organ doses and also emission dose from nuclear issue. Material and methods: Myocardial perfusion SPECT/CT for 509 patients was included in the study. SSDE, effective dose and organ dose were calculated using AAPM guideline and Impact-Dose software. Data were analyzed using R and SPSS statistical software. Spearman-Pearson correlation test and linear regression models were used for finding correlations and relationships among parameters. Results: The mean CTDIvol was 1.34 mGy ± 0.19 and the mean SSDE was 1.7 mGy ± 0.16. The mean ± SD of effective dose from emission, CT and total dose were 11.5 ± 1.4, 0.49 ± 0.11 and 12.67 ± 1.73 (mSv) respectively. The mean ± SD of effective dose from emission, CT and total dose were 11.5 ± 1.4, 0.49 ± 0.11 and 12.67 ± 1.73 (mSv) respectively. The spearman test showed that correlation between body size and organ doses is significant except thyroid and red bone marrow. CTDIvol was strongly dependent on patient size, but SSDE was not. Emission dose was strongly dependent on patient weight, but its dependency was lower to effective diameter. Conclusion: The dose parameters including CTDIvol, DLP, SSDE, effective dose values reported here are very low and below the reference level. This data suggest that appropriate CT acquisition parameters in SPECT/CT localization and attenuation correction are very beneficial for patients and lowering cancer risks.

Monte Carlo estimation of the absorbed dose in computed tomography

Energy Technology Data Exchange (ETDEWEB)

Kim, Jin Woo; Youn, Han Bean; Kim, Ho Kyung [Pusan National University, Busan (Korea, Republic of)

2016-05-15

The purpose of this study is to devise an algorithm calculating absorbed dose distributions of patients based on Monte Carlo (MC) methods, and which includes the dose estimations due to primary and secondary (scattered) x-ray photons. Assessment of patient dose in computed tomography (CT) at the population level has become a subject of public attention and concern, and ultimate CT quality assurance and dose optimization have the goal of reducing radiation-induced cancer risks in the examined population. However, the conventional CT dose index (CTDI) concept is not a surrogate of risk but it has rather been designed to measure an average central dose. In addition, the CTDI or the dose-length product has showed troubles for helical CT with a wider beam collimation. Simple algorithms to estimate a patient specific CT dose based on the MCNP output data have been introduced. For numerical chest and head phantoms, the spatial dose distributions were calculated. The results were reasonable. The estimated dose distribution map can be readily converted into the effective dose. The important list for further studies includes the validation of the models with the experimental measurements and the acceleration of algorithms.

Estimation of internal exposure for exposed personnel from a CANDU nuclear fuel factory

International Nuclear Information System (INIS)

Horhoianu, Valeria; Valeca Monica; Hirica, Ovidiu; Todoran, Anca

2004-01-01

The knowledge of the radioactive material behaviour inside the human body is an essential issue for interpretation of the radioactivity measurements in human body or excretions in terms of internal contamination or committed equivalent dose. The paper presents evaluation of internal contamination of professionally exposed workers from a CANDU nuclear fuel factory with the ACRO computer code which estimates burden and tissue or organ dose resulting from inhalation or ingestion of radioactive materials. The workplaces where continuous aerosol sampling are carried out have been taken into account for the analysis. For potentially inhaled activity assessment, the average aerosol concentrations were estimated. The dose equivalent and collective dose equivalent are also estimated. (authors)

Estimation of internal exposure for exposed personnel from a Candu nuclear fuel factory

International Nuclear Information System (INIS)

Horhoianu, V.; Hirica, O.; Valeca, M.; Todoran, A.

2003-01-01

The knowledge of the radioactive material behavior inside the human body is an essential issue for interpretation of the radioactivity measurements in human body or excretions in terms of internal contamination or committed equivalent dose. The paper present evaluation of internal contamination of professionally exposed workers from a Candu nuclear fuel factory with the ACRO computer code which estimate burden and tissue or organ dose resulting from inhalation or ingestion of radioactive materials. The workplaces where continuos aerosols sampling are carried out, has been taken into account for the analysis. For potentially inhaled activity assessment, the average aerosol concentrations were estimated. The dose equivalent and collective dose equivalent are also estimated. (authors)

Estimation of Internal Exposure for Exposed Personnel from a CANDU Nuclear Fuel Factory

International Nuclear Information System (INIS)

Horhoianu, V.; Valeca, M.; Margeanu, S.

2001-01-01

Full text: The knowledge of the radioactive material behaviour inside the human body is an essential issue for interpretation of the radioactivity measurements in human body or excretions in terms of internal contamination or committed equivalent dose. The paper presents evaluation of internal contamination of professionally exposed workers from a CANDU nuclear fuel factory with the ACRO computer code which estimate burden and tissue or organ dose resulting from inhalation or ingestion of radioactive materials. The workplaces where continuos aerosols sampling are carried out, has been taken into account for the analysis. For potentially inhaled activity assessment, the average aerosol concentrations were estimated. The dose equivalent and collective dose equivalent are also estimated. (author)

Uncertainty analysis for an updated dose assessment for a US nuclear test site: Bikini Atoll

International Nuclear Information System (INIS)

Bogen, K.T.; Conrado, C.L.; Robison, W.L.

1995-11-01

A detailed analysis of uncertainty and interindividual variability in estimated doses was conducted for a rehabilitation scenario for Bikini Island at Bikini Atoll, in which the top 40 cm of soil would be removed in the housing and village area, and the rest of the island is treated with potassium fertilizer, prior to an assumed resettlement date of 1999. Predicted doses were considered for the following fallout-related exposure pathways: ingested Cesium-137 and Strontium-90, external gamma exposure, and inhalation and ingestion of Americium-241 + Plutonium-239+240. Two dietary scenarios were considered: (1) imported foods are available (IA), and (2) imported foods are unavailable (only local foods are consumed) (IUA). Corresponding calculations of uncertainty in estimated population-average dose showed that after ∼5 y of residence on Bikini, the upper and lower 95% confidence limits with respect to uncertainty in this dose are estimated to be approximately 2-fold higher and lower than its population-average value, respectively (under both IA and IUA assumptions). Corresponding calculations of interindividual variability in the expected value of dose with respect to uncertainty showed that after ∼5 y of residence on Bikini, the upper and lower 95% confidence limits with respect to interindividual variability in this dose are estimated to be approximately 2-fold higher and lower than its expected value, respectively (under both IA and IUA assumptions). For reference, the expected values of population-average dose at age 70 were estimated to be 1.6 and 5.2 cSv under the IA and IUA dietary assumptions, respectively. Assuming that 200 Bikini resettlers would be exposed to local foods (under both IA and IUA assumptions), the maximum 1-y dose received by any Bikini resident is most likely to be approximately 2 and 8 mSv under the IA and IUA assumptions, respectively

Age- and gender-specific estimates of cumulative CT dose over 5 years using real radiation dose tracking data in children

International Nuclear Information System (INIS)

Lee, Eunsol; Goo, Hyun Woo; Lee, Jae-Yeong

2015-01-01

It is necessary to develop a mechanism to estimate and analyze cumulative radiation risks from multiple CT exams in various clinical scenarios in children. To identify major contributors to high cumulative CT dose estimates using actual dose-length product values collected for 5 years in children. Between August 2006 and July 2011 we reviewed 26,937 CT exams in 13,803 children. Among them, we included 931 children (median age 3.5 years, age range 0 days-15 years; M:F = 533:398) who had 5,339 CT exams. Each child underwent at least three CT scans and had accessible radiation dose reports. Dose-length product values were automatically extracted from DICOM files and we used recently updated conversion factors for age, gender, anatomical region and tube voltage to estimate CT radiation dose. We tracked the calculated CT dose estimates to obtain a 5-year cumulative value for each child. The study population was divided into three groups according to the cumulative CT dose estimates: high, ≥30 mSv; moderate, 10-30 mSv; and low, <10 mSv. We reviewed clinical data and CT protocols to identify major contributors to high and moderate cumulative CT dose estimates. Median cumulative CT dose estimate was 5.4 mSv (range 0.5-71.1 mSv), and median number of CT scans was 4 (range 3-36). High cumulative CT dose estimates were most common in children with malignant tumors (57.9%, 11/19). High frequency of CT scans was attributed to high cumulative CT dose estimates in children with ventriculoperitoneal shunt (35 in 1 child) and malignant tumors (range 18-49). Moreover, high-dose CT protocols, such as multiphase abdomen CT (median 4.7 mSv) contributed to high cumulative CT dose estimates even in children with a low number of CT scans. Disease group, number of CT scans, and high-dose CT protocols are major contributors to higher cumulative CT dose estimates in children. (orig.)

Size-specific dose estimate (SSDE) provides a simple method to calculate organ dose for pediatric CT examinations

Energy Technology Data Exchange (ETDEWEB)

Moore, Bria M.; Brady, Samuel L., E-mail: samuel.brady@stjude.org; Kaufman, Robert A. [Department of Radiological Sciences, St Jude Children' s Research Hospital, Memphis, Tennessee 38105 (United States); Mirro, Amy E. [Department of Biomedical Engineering, Washington University, St Louis, Missouri 63130 (United States)

2014-07-15

Purpose: To investigate the correlation of size-specific dose estimate (SSDE) with absorbed organ dose, and to develop a simple methodology for estimating patient organ dose in a pediatric population (5–55 kg). Methods: Four physical anthropomorphic phantoms representing a range of pediatric body habitus were scanned with metal oxide semiconductor field effect transistor (MOSFET) dosimeters placed at 23 organ locations to determine absolute organ dose. Phantom absolute organ dose was divided by phantom SSDE to determine correlation between organ dose and SSDE. Organ dose correlation factors (CF{sub SSDE}{sup organ}) were then multiplied by patient-specific SSDE to estimate patient organ dose. The CF{sub SSDE}{sup organ} were used to retrospectively estimate individual organ doses from 352 chest and 241 abdominopelvic pediatric CT examinations, where mean patient weight was 22 kg ± 15 (range 5–55 kg), and mean patient age was 6 yrs ± 5 (range 4 months to 23 yrs). Patient organ dose estimates were compared to published pediatric Monte Carlo study results. Results: Phantom effective diameters were matched with patient population effective diameters to within 4 cm; thus, showing appropriate scalability of the phantoms across the entire pediatric population in this study. IndividualCF{sub SSDE}{sup organ} were determined for a total of 23 organs in the chest and abdominopelvic region across nine weight subcategories. For organs fully covered by the scan volume, correlation in the chest (average 1.1; range 0.7–1.4) and abdominopelvic region (average 0.9; range 0.7–1.3) was near unity. For organ/tissue that extended beyond the scan volume (i.e., skin, bone marrow, and bone surface), correlation was determined to be poor (average 0.3; range: 0.1–0.4) for both the chest and abdominopelvic regions, respectively. A means to estimate patient organ dose was demonstrated. Calculated patient organ dose, using patient SSDE and CF{sub SSDE}{sup organ}, was compared to

LADTAP-2, Organ Doses to Man and Other Biota from Aquatic Environment

International Nuclear Information System (INIS)

Strenge, D.L.; Peloquin, R.A.; Whelan, G.

1989-01-01

1 - Description of problem or function: LADTAP2 performs environmental dose analyses for releases of liquid effluents from light-water nuclear power plants into surface waters during routine operation. The analyses estimate radiation doses to individuals, population groups, and biota from ingestion (aquatic foods, water, and terrestrial irrigated foods) and external exposure (shoreline, swimming, and boating) pathways. The calculated doses provide information for National Environmental Policy Act (NEPA) evaluations and for determining compliance with Appendix I of 10 CFR 50 (the 'ALARA' philosophy). The program consists of a hydrologic model chosen to represent mixing in the effluent impoundment system and the receiving surface waters and the exposure pathway models which estimate exposure of selected groups at various water usage locations in the environment. Two types of population doses are calculated. An ALARA analysis is performed based on exposure of people within 50 miles of the site, and a NEPA analysis is performed based on exposure of the entire U.S. population to effluents from the site. A population-dose analysis prepared in the form of a cost-benefit table presents the total-body and thyroid doses from each radionuclide released and the population doses (total-body and thyroid) per curie of each radionuclide released. 2 - Method of solution: The impoundment system is represented by one of four hydrologic models: direct release to the receiving water, linear flow with no mixing (the plug-flow model), linear flow through the impoundment with partial recirculation through the reactor (the partially mixed model), or complete mixing in the impoundment with partial recirculation through the reactor (the completely mixed model). The last three account for radiological decay during transit through the impoundment system. Optional models are available to estimate dilution in nontidal rivers and near-shore lake environments. The consequence calculation part of

New risk estimates at low doses

International Nuclear Information System (INIS)

Fry, R.J.M.

1992-01-01

The age of molecular radiation epidemiology may be at hand. The techniques are available to establish with the degree of precision required to determine whether agent-specific mutations can be identified consistently. A concerted effort to examine radiation-induced changes in as many relevant genes as possible appears to be justified. Cancers in those exposed to low doses of ionizing radiation should be chosen for the investigation. Parallel studies of radiation-induced cancers in experimental animals would not only complement the human studies, but perhaps reveal approaches to extrapolation of risk estimates across species. A caveat should be added to this optimistic view of what molecular studies might contribute to the knotty problem of risk estimates at low doses. The suggestions are made by one with no expertise in the field of molecular biology

Mutation frequencies in male mice and the estimation of genetic hazards of radiation in men: (specific-locus mutations/dose-rate effect/doubling dose/risk estimation)

International Nuclear Information System (INIS)

Russell, W.L.; Kelly, E.M.

1982-01-01

Estimation of the genetic hazards of ionizing radiation in men is based largely on the frequency of transmitted specific-locus mutations induced in mouse spermatogonial stem cells at low radiation dose rates. The publication of new data on this subject has permitted a fresh review of all the information available. The data continue to show no discrepancy from the interpretation that, although mutation frequency decreases markedly as dose rate is decreased from 90 to 0.8 R/min (1 R = 2.6 X 10 -4 coulombs/kg) there seems to be no further change below 0.8 R/min over the range from that dose rate to 0.0007 R/min. Simple mathematical models are used to compute: (a) a maximum likelihood estimate of the induced mutation frequency at the low dose rates, and (b) a maximum likelihood estimate of the ratio of this to the mutation frequency at high dose rates in the range of 72 to 90 R/min. In the application of these results to the estimation of genetic hazards of radiation in man, the former value can be used to calculate a doubling dose - i.e., the dose of radiation that induces a mutation frequency equal to the spontaneous frequency. The doubling dose based on the low-dose-rate data compiled here is 110 R. The ratio of the mutation frequency at low dose rate to that at high dose rate is useful when it becomes necessary to extrapolate from experimental determinations, or from human data, at high dose rates to the expected risk at low dose rates. The ratio derived from the present analysis is 0.33

Estimation of internal exposure with use of urinalysis

International Nuclear Information System (INIS)

Nakagawa, Naoko; Kimura, Kayano

2013-01-01

Easily explained is a simple method to estimate the internal exposure to radio-cesium using the result of urinalysis. Urinary Cs (Cs-134, -137) concentration can be conveniently measured with Ge-detector of which sensitivity is as high as to detect even <1 Bq/L. At the steady state in the body, the ingested Cs amount is equivalent to the excreted amount; daily ingested Cs = daily excreted Cs (Bq/day): and 80% of body Cs is known to be excreted in urine; daily ingested Cs = daily urinary Cs/0.8= U x X/0.8 where U is daily urine volume (L) and X is Cs concentration (Bq/L) in the daily urine measurable with the detector. Thus the yearly internal exposure dose can be estimated by calculation using the body Cs (Bq/day) and the effective dose coefficient A (Sv/Bq) defined by ICRP (Pub. 72, 1998); A x U x X/0.8 x 365/1000 (mSv), where actually, the dose is committed effective dose for oral ingestion. A is dependent on the age. Alternatively, the level of body Cs at the equilibrium (Bq/kg, body weight M kg) can be estimated by B x U x X/0.8/M, where B, variable with age, is a dynamic parameter determined with half-lives and pharmacokinetic model of Cs (ICRP Pub. 56, 1990 and Pub. 67, 1992). Actually, the Cs urinalysis of 132 children was conducted in Iwate Prefecture in Dec. 2011-Mar. 2012. Their daily urinary Cs excretion was found to be in the range of not-detected (13 cases), <1 (20), <2 (48), <3 (33), <4 (15), to <5 (3) Bq/day; and when the not-detected 13 cases above were excluded below, daily Cs ingestion was from <1.25 to <6.25 Bq/day; internal exposure from <5.5 to <28 mc-Sv; body Cs level from <1.9 to <9.5 Bq/kg; and body Cs from <66 to <330 Bq. These were enough below the limit 1 mSv or 20 Bq/kg defined as a safety standard limit. Systematic survey of the internal exposure done in Fukushima Prefecture was that with the whole body counter, less sensitive than urinalysis (e.g., not detected at 7 Bq/kg). The advantage of the urinalysis is that anyone can easily

Severe neurotoxicity following ingestion of tetraethyl lead.

Science.gov (United States)

Wills, Brandon K; Christensen, Jason; Mazzoncini, Joe; Miller, Michael

2010-03-01

Organic lead compounds are potent neurotoxins which can result in death even from small exposures. Traditionally, these compounds are found in fuel stabilizers, anti-knock agents, and leaded gasoline. Cases of acute organic lead intoxication have not been reported for several decades. We report a case of a 13-year-old Iraqi male who unintentionally ingested a fuel stabilizer containing 80-90% tetraethyl lead, managed at our combat support hospital. The patient developed severe neurologic symptoms including agitation, hallucinations, weakness, and tremor. These symptoms were refractory to escalating doses of benzodiazepines and ultimately required endotracheal intubation and a propofol infusion. Adjunctive therapies included chelation, baclofen, and nutrition provided through a gastrostomy tube. The patient slowly recovered and was discharged in a wheelchair 20 days after ingestion, still requiring tube feeding. Follow-up at 62 days post-ingestion revealed near-resolution of symptoms with residual slurred speech and slight limp. This case highlights the profound neurotoxic manifestations of acute organic lead compounds.

Dose estimation in embryo or fetus in external fields

International Nuclear Information System (INIS)

Gregori, Beatriz N.

2001-01-01

The embryo or the fetus can be irradiated as result of radiological procedures of diagnosis of therapy in where the beam effects directly on the same one or in tissues or peripherical organs. Some authors have suggested that in the first stages of the pregnancy the dose in ovaries can be the good estimated of the dose in embryo or fetus. In advanced conditions of the development, probably also in the early stage, is more appropriated to specify the dose in the embryo or fetus equal of the uterus. The dose in the uterus is a good estimated so much for external irradiation as for radionuclides incorporation

Impacts of Stable Element Intake on C and I Dose Estimates - Implications for Proposed Yucca Mountain Repository

Energy Technology Data Exchange (ETDEWEB)

D.W. Moeller; M.T. Ryan; Lin-Shen C. Sun; R.N. Cherry Jr.

2004-12-21

The purpose of this study was to evaluate the influence of the intake of stable isotopes of carbon and iodine on the committed doses due to the ingestion of {sup 14}C and {sup 129}I. This was accomplished through the application of two different computational approaches. The first was based on the assumption that ground (drinking) water was the only source of intake of both {sup 14}C and {sup 129}I and stable carbon and stable iodine. For purposes of the second approach, the intake of {sup 14}C and {sup 129}I was still assumed to be only that in the ground (drinking) water, but the intake of stable carbon and stable iodine was assumed to be that in the drinking water plus other components of the diet. The doses were estimated using either a conversion formula or the applicable dose coefficients in Federal Guidance Reports No. 11 and No. 13. Serving as input for the analyses was the estimated maximum concentration of {sup 14}C or {sup 129}I that would be present in the ground water due to potential releases from the proposed Yucca Mountain high-level radioactive waste repository during the first 10,000 years after closure. The estimated concentrations of stable carbon and iodine were based on analyses of ground water samples collected in the Amargosa Valley, NV. Based on the accompanying analyses, three conclusions were reached. First, no dose estimate, using a conversion formula in which the ratios of the stable to radioactive isotopes of an element serve as input, should ever be made without including the stable element intake contributions from all components of the diet. Second, the study suggests that the dose coefficients for {sup 129}I in Federal Guidance Reports No. 11 and No. 12 which, in turn, are based on publications of the ICRP, may not be appropriate for application in developed nations of the world, especially those in which relatively large amounts of seafood are consumed and the use of iodized salt is common. The estimated average daily intake of

Determination of 210Po concentration in commercially available infant formulae and assessment of daily ingestion dose

Directory of Open Access Journals (Sweden)

Ravi K. Prabhath

2015-07-01

Full Text Available A study has been conducted to estimate the concentration of natural radioactive polonium in commercially available packaged infant food formulae available in Mumbai, India and the corresponding daily dose normalized based on its shelf life. Eleven most popular international brands of infant formulae were sourced from market and three aliquots from each sample were analysed for concordant results. Autodeposition method onto a silver planchet from hot dilute acid solution followed by alpha spectrometry was performed for estimation of polonium. Radiochemical recovery was ascertained by the addition of 209Po tracer. Radiochemical recovery of 209Po tracer was ranged from 14.7 to 98.1 %. The 210Po concentration in the samples was in the range of 0.08–0.23 Bq kg−1 on measured date and the corresponding daily dose, calculated on normalized date which is at mid-point of the shelf life of the sample, was ranged from 0.04 to 0.89 μSv d−1 as per the recommended daily consumption. The annual committed effective dose estimated based on the average of daily dose was found to be 150 μSv.

Maximum likelihood estimation for cytogenetic dose-response curves

International Nuclear Information System (INIS)

Frome, E.L; DuFrain, R.J.

1983-10-01

In vitro dose-response curves are used to describe the relation between the yield of dicentric chromosome aberrations and radiation dose for human lymphocytes. The dicentric yields follow the Poisson distribution, and the expected yield depends on both the magnitude and the temporal distribution of the dose for low LET radiation. A general dose-response model that describes this relation has been obtained by Kellerer and Rossi using the theory of dual radiation action. The yield of elementary lesions is kappa[γd + g(t, tau)d 2 ], where t is the time and d is dose. The coefficient of the d 2 term is determined by the recovery function and the temporal mode of irradiation. Two special cases of practical interest are split-dose and continuous exposure experiments, and the resulting models are intrinsically nonlinear in the parameters. A general purpose maximum likelihood estimation procedure is described and illustrated with numerical examples from both experimental designs. Poisson regression analysis is used for estimation, hypothesis testing, and regression diagnostics. Results are discussed in the context of exposure assessment procedures for both acute and chronic human radiation exposure

Maximum likelihood estimation for cytogenetic dose-response curves

Energy Technology Data Exchange (ETDEWEB)

Frome, E.L; DuFrain, R.J.

1983-10-01

In vitro dose-response curves are used to describe the relation between the yield of dicentric chromosome aberrations and radiation dose for human lymphocytes. The dicentric yields follow the Poisson distribution, and the expected yield depends on both the magnitude and the temporal distribution of the dose for low LET radiation. A general dose-response model that describes this relation has been obtained by Kellerer and Rossi using the theory of dual radiation action. The yield of elementary lesions is kappa(..gamma..d + g(t, tau)d/sup 2/), where t is the time and d is dose. The coefficient of the d/sup 2/ term is determined by the recovery function and the temporal mode of irradiation. Two special cases of practical interest are split-dose and continuous exposure experiments, and the resulting models are intrinsically nonlinear in the parameters. A general purpose maximum likelihood estimation procedure is described and illustrated with numerical examples from both experimental designs. Poisson regression analysis is used for estimation, hypothesis testing, and regression diagnostics. Results are discussed in the context of exposure assessment procedures for both acute and chronic human radiation exposure.

Dose-response relationships and risk estimates for the induction of cancer due to low doses of low-LET radiation

International Nuclear Information System (INIS)

Elaguppillai, V.

1981-01-01

Risk estimates for radiation-induced cancer at low doses can be obtained only by extrapolation from the known effects at high doses and high dose rates, using a suitable dose-response model. The applicability of three different models, linear, sublinear and supralinear, are discussed in this paper. Several experimental studies tend to favour a sublinear dose-response model (linear-quadratic model) for low-LET radiation. However, human epidemiological studies do not exclude any of the dose-response relationships. The risk estimates based on linear and linear quadratic dose-response models are compared and it is concluded that, for low-LET radiation, the linear dose-response model would probably over-estimate the actual risk of cancer by a factor of two or more. (author)

Caffeine Ingestion Increases Estimated Glycolytic Metabolism during Taekwondo Combat Simulation but Does Not Improve Performance or Parasympathetic Reactivation.

Directory of Open Access Journals (Sweden)

João Paulo Lopes-Silva

Full Text Available The aim of this study was to evaluate the effect of caffeine ingestion on performance and estimated energy system contribution during simulated taekwondo combat and on post-exercise parasympathetic reactivation.Ten taekwondo athletes completed two experimental sessions separated by at least 48 hours. Athletes consumed a capsule containing either caffeine (5 mg∙kg-1 or placebo (cellulose one hour before the combat simulation (3 rounds of 2 min separated by 1 min passive recovery, in a double-blind, randomized, repeated-measures crossover design. All simulated combat was filmed to quantify the time spent fighting in each round. Lactate concentration and rating of perceived exertion were measured before and after each round, while heart rate (HR and the estimated contribution of the oxidative (WAER, ATP-PCr (WPCR, and glycolytic (W[La-] systems were calculated during the combat simulation. Furthermore, parasympathetic reactivation after the combat simulation was evaluated through 1 taking absolute difference between the final HR observed at the end of third round and the HR recorded 60-s after (HRR60s, 2 taking the time constant of HR decay obtained by fitting the 6-min post-exercise HRR into a first-order exponential decay curve (HRRτ, or by 3 analyzing the first 30-s via logarithmic regression analysis (T30.Caffeine ingestion increased estimated glycolytic energy contribution in relation to placebo (12.5 ± 1.7 kJ and 8.9 ± 1.2 kJ, P = 0.04. However, caffeine did not improve performance as measured by attack number (CAF: 26. 7 ± 1.9; PLA: 27.3 ± 2.1, P = 0.48 or attack time (CAF: 33.8 ± 1.9 s; PLA: 36.6 ± 4.5 s, P = 0.58. Similarly, RPE (CAF: 11.7 ± 0.4 a.u.; PLA: 11.5 ± 0.3 a.u., P = 0.62, HR (CAF: 170 ± 3.5 bpm; PLA: 174.2 bpm, P = 0.12, oxidative (CAF: 109.3 ± 4.5 kJ; PLA: 107.9 kJ, P = 0.61 and ATP-PCr energy contributions (CAF: 45.3 ± 3.4 kJ; PLA: 46.8 ± 3.6 kJ, P = 0.72 during the combat simulation were unaffected. Furthermore

Caffeine Ingestion Increases Estimated Glycolytic Metabolism during Taekwondo Combat Simulation but Does Not Improve Performance or Parasympathetic Reactivation.

Science.gov (United States)

Lopes-Silva, João Paulo; Silva Santos, Jonatas Ferreira da; Branco, Braulio Henrique Magnani; Abad, César Cavinato Cal; Oliveira, Luana Farias de; Loturco, Irineu; Franchini, Emerson

2015-01-01

The aim of this study was to evaluate the effect of caffeine ingestion on performance and estimated energy system contribution during simulated taekwondo combat and on post-exercise parasympathetic reactivation. Ten taekwondo athletes completed two experimental sessions separated by at least 48 hours. Athletes consumed a capsule containing either caffeine (5 mg∙kg-1) or placebo (cellulose) one hour before the combat simulation (3 rounds of 2 min separated by 1 min passive recovery), in a double-blind, randomized, repeated-measures crossover design. All simulated combat was filmed to quantify the time spent fighting in each round. Lactate concentration and rating of perceived exertion were measured before and after each round, while heart rate (HR) and the estimated contribution of the oxidative (WAER), ATP-PCr (WPCR), and glycolytic (W[La-]) systems were calculated during the combat simulation. Furthermore, parasympathetic reactivation after the combat simulation was evaluated through 1) taking absolute difference between the final HR observed at the end of third round and the HR recorded 60-s after (HRR60s), 2) taking the time constant of HR decay obtained by fitting the 6-min post-exercise HRR into a first-order exponential decay curve (HRRτ), or by 3) analyzing the first 30-s via logarithmic regression analysis (T30). Caffeine ingestion increased estimated glycolytic energy contribution in relation to placebo (12.5 ± 1.7 kJ and 8.9 ± 1.2 kJ, P = 0.04). However, caffeine did not improve performance as measured by attack number (CAF: 26. 7 ± 1.9; PLA: 27.3 ± 2.1, P = 0.48) or attack time (CAF: 33.8 ± 1.9 s; PLA: 36.6 ± 4.5 s, P = 0.58). Similarly, RPE (CAF: 11.7 ± 0.4 a.u.; PLA: 11.5 ± 0.3 a.u., P = 0.62), HR (CAF: 170 ± 3.5 bpm; PLA: 174.2 bpm, P = 0.12), oxidative (CAF: 109.3 ± 4.5 kJ; PLA: 107.9 kJ, P = 0.61) and ATP-PCr energy contributions (CAF: 45.3 ± 3.4 kJ; PLA: 46.8 ± 3.6 kJ, P = 0.72) during the combat simulation were unaffected

Estimated dietary intake of radionuclides and health risks for the citizens of Fukushima City, Tokyo, and Osaka after the 2011 nuclear accident.

Directory of Open Access Journals (Sweden)

Michio Murakami

Full Text Available The radionuclides released from the Fukushima Daiichi nuclear power plant in 2011 pose a health risk. In this study, we estimated the 1st-year average doses resulting from the intake of iodine 131 (131I and cesium 134 and 137 (134Cs and 137Cs in drinking water and food ingested by citizens of Fukushima City (∼50 km from the nuclear power plant; outside the evacuation zone, Tokyo (∼230 km, and Osaka (∼580 km after the accident. For citizens in Fukushima City, we considered two scenarios: Case 1, citizens consumed vegetables bought from markets; Case 2, citizens consumed vegetables grown locally (conservative scenario. The estimated effective doses of 134Cs and 137Cs agreed well with those estimated through market basket and food-duplicate surveys. The average thyroid equivalent doses due to ingestion of 131I for adults were 840 µSv (Case 1 and 2700 µSv (Case 2 in Fukushima City, 370 µSv in Tokyo, and 16 µSv in Osaka. The average effective doses due to 134Cs and 137Cs were 19, 120, 6.1, and 1.9 µSv, respectively. The doses estimated in this study were much lower than values reported by the World Health Organization and the United Nations Scientific Committee on the Effects of Atomic Radiation, whose assessments lacked validation and full consideration of regional trade in foods, highlighting the importance of including regional trade. The 95th percentile effective doses were 2-3 times the average values. Lifetime attributable risks (LARs of thyroid cancers due to ingestion were 1.7-37×10-6 (Case 1 and5.6-79×10-6 (Case 2 in Fukushima City, 0.73-13×10-6 in Tokyo, and 0.04-0.49×10- 6 in Osaka. The contributions of LARs of thyroid cancers due to ingestion were 5.4%-11% of all exposure (Case 1 and 11%-25% (Case 2 in Fukushima City [corrected].

An estimation of exposure from gaseous and volatile radioactive effluents released from EWA reactor between 1971 and 1975

International Nuclear Information System (INIS)

Filipiak, B.; Nowicki, K.

1979-01-01

The paper gives an estimation of radiation doses for individuals due to gaseous radioactive effluents released from EWA reactor between 1971 and 1975. The doses were estimated for three organs, three groups of people: adults, teenagers and children and for three of the most important exposure paths: the external radiation from a passing cloud, inhalation and from milk ingestion. The results of calculations indicate that the radiation doses received by individuals living in the vicinity of EWA reactor were much below the limit doses or those due to the background radiation. (author)

Estimating baseline risks from biouptake and food ingestion at a contaminated site

International Nuclear Information System (INIS)

MacDonell, M.; Woytowich, K.; Blunt, D.; Picel, M.

1993-01-01

Biouptake of contaminants and subsequent human exposure via food ingestion represents a public concern at many contaminated sites. Site-specific measurements from plant and animal studies are usually quite limited, so this exposure pathway is often modeled to assess the potential for adverse health effects. A modeling tool was applied to evaluate baseline risks at a contaminated site in Missouri, and the results were used to confirm that ingestion of fish and game animals from the site area do not pose a human health threat. Results were also used to support the development of cleanup criteria for site soil

Dosing of cytotoxic chemotherapy: impact of renal function estimates on dose.

Science.gov (United States)

Dooley, M J; Poole, S G; Rischin, D

2013-11-01

Oncology clinicians are now routinely provided with an estimated glomerular filtration rate on pathology reports whenever serum creatinine is requested. The utility of using this for the dose determination of renally excreted drugs compared with other existing methods is needed to inform practice. Renal function was determined by [Tc(99m)]DTPA clearance in adult patients presenting for chemotherapy. Renal function was calculated using the 4-variable Modification of Diet in Renal Disease (4v-MDRD), Chronic Kidney Disease Epidemiology Collaboration (CKD-EPI), Cockcroft and Gault (CG), Wright and Martin formulae. Doses for renal excreted cytotoxic drugs, including carboplatin, were calculated. The concordance of the renal function estimates according to the CKD classification with measured Tc(99m)DPTA clearance in 455 adults (median age 64.0 years: range 17-87 years) for the 4v-MDRD, CKD-EPI, CG, Martin and Wright formulae was 47.7%, 56.3%, 46.2%, 56.5% and 60.2%, respectively. Concordance for chemotherapy dose for these formulae was 89.0%, 89.5%, 85.1%, 89.9% and 89.9%, respectively. Concordance for carboplatin dose specifically was 66.4%, 71.4%, 64.0%, 73.8% and 73.2%. All bedside formulae provide similar levels of concordance in dosage selection for the renal excreted chemotherapy drugs when compared with the use of a direct measure of renal function.

Going beyond the most exposed people in a dose assessment

Energy Technology Data Exchange (ETDEWEB)

Hjerpe, Thomas; Broed, Robert [Facilia AB, Gustavslundsvaegen 151C, SE-167 51 Bromma (Sweden); Ikonen, Ari T.K. [Environmental Research and Assessment, EnviroCase, Ltd., Hallituskatu 1 D 4, FI-28 100 Pori (Finland)

2014-07-01

The dose assessment in a long-term radiation safety assessment often focus on assessing dose of a representative person to be used for determining compliance with a radiation dose constraint. This representative person is often assumed to receive a dose that is representative of the most exposed people, i.e., the more highly exposed individuals in the population. This is not always sufficient, the Finnish regulations for disposal of nuclear waste has radiation dose constraint to the most exposed people as well as for larger groups of exposed people. This work presents the methodology to assessing dose of a representative person for a larger group of exposed people as applied by Posiva in the TURVA-2012 safety case for the spent nuclear fuel disposal at Olkiluoto. In addition, annual doses from the set of biosphere calculation cases analysed in TURVA-2012 are presented and discussed. Special focus is given on explaining the differences in exposure levels and exposure routes between the estimated annual doses to representative persons for most exposed people and a larger exposed group. The results show that the annual doses to a larger group of people ranges from one to three orders of magnitude below the annual doses to the most exposed people. Furthermore, the exposure route related to food ingestion is less significant for the larger group of people compared to the most exposed people and that the exposure route related to water ingestion shows the opposite behaviour. (authors)

Dose estimation of the THOR BNCT treatment room

International Nuclear Information System (INIS)

Hsu, F.Y.; Liu, H.M.; Yu, C.C.; Huang, Y.H.; Tsai, H.N.

2006-01-01

BNCT beam of Tsing Hua Open-pool Reactor (THOR) was designed and constructed since 1998. A treatment room for the newly modified THOR BNCT beam was constructed for the next clinical-stage trials in 2004. Dose distribution in a patient (or a phantom) is important as irradiated with the BNCT beam. The dose distributions for different type of radiations such as neutron and photons in the treatment room are strongly becoming the index or reference of success for a BNCT facility. An ART head phantom was placed in front of the THOR BNCT beam port and was irradiated. In each section of the head phantom, numbers of small holes are inside and separated uniformly. Dual detector: TLD-600 and TLD-700 chips were placed inside these holes within the phantom to distinct doses of neutron and photon. Besides, Dual-TLD chips were latticed placed in the horizontal plane of beam central axis, in the treatment room to estimate the spatial dose distribution of neutron and photon. Gold foils were assisted in TLD dose calibrations. Neutron and photon dose distributions in phantom and spatial dose distributions in the THOR BNCT treatment room were both estimated in this work. Testing and improvement in THOR BNCT beam were continuative during these years. Results of this work could be the reference and be helpful for the further clinical trials in nearly future. (author)

Biological dose estimation in a radiation accident involving low-dose ...

African Journals Online (AJOL)

Blood specimens were collected from 8 people 18 days after they had been accidentally exposed to a 947,2 GBq iridium192 source during industrial application. The equivalent whole-body dose received at day 0 was estimated using a model based on quantitative and qualitative chromosome aberration analysis in ...

PardNor - PARameters for ingestion dose models for NORdic areas

Energy Technology Data Exchange (ETDEWEB)

Nielsen, Sven P.; Andersson, K.G. (Technical Univ. of Denmark, Risoe National Lab. for Sustainable Energy, Roskilde (Denmark))

2008-07-15

patterns could easily lead to a difference in long term ingestion doses by a factor of at least two between the Nordic countries. It was also demonstrated that early phase doses received before countermeasures can be effectively implemented may deviate by at least an order of magnitude. Finally, typical animal feeding regimes have been examined and described for the different Nordic countries. Here it has been found that both the fodder items and the seasonal variation in their application vary considerably. (au)

PardNor - PARameters for ingestion dose models for NORdic areas

International Nuclear Information System (INIS)

Nielsen, Sven P.; Andersson, K.G.

2008-07-01

patterns could easily lead to a difference in long term ingestion doses by a factor of at least two between the Nordic countries. It was also demonstrated that early phase doses received before countermeasures can be effectively implemented may deviate by at least an order of magnitude. Finally, typical animal feeding regimes have been examined and described for the different Nordic countries. Here it has been found that both the fodder items and the seasonal variation in their application vary considerably. (au)

Estimate of ovarian dose and entrance skin dose in uterine artery embolization procedures

International Nuclear Information System (INIS)

Silva, Marcia C.; Nasser, Felipe; Affonso, Breno B.; Araujo Junior, Raimundo T.; Zlotnik, Eduardo; Messina, Marcos L.; Baracat, Edmund C.

2010-01-01

The goal of this study was to estimate the ovarian dose and entrance skin dose (ESD) of patients who underwent uterine artery embolization (UAE) procedure. To achieve this, 49 UAE procedures were accompanied where the parameters of image acquisition were recorded for the calculation of the DEP from the output of the X-ray tube. The estimation of the ovarian dose was carried out by the insertion of a vaginal probe containing 3 TLD's. The obtained values were compared with the results of other authors and a higher value of ovarian dose (28,97 cGy) and ESD (403,57 cGy) was found in this work. Analysis of the results allowed to observe that this result was obtained mainly as a result of the high number of arteriography series and the frames/second rates employed. Following on from these observations, the protocol of EMUT was altered reducing the frames/seg rate from 2 to 1. Efforts with a view to reducing the number of arteriography series also became part of the next proceedings. (author)

Estimation of population doses from diagnostic medical examinations in Japan, 1974. II. Estimation of genetically significant dose

Energy Technology Data Exchange (ETDEWEB)

Hashizume, T; Maruyama, T; Kumamoto, Y [National Inst. of Radiological Sciences, Chiba (Japan)

1976-03-01

The genetically significant dose from radiographic and fluoroscopic examination in Japan has been estimated based on a 1974 nation wide survey of randomly sampled hospitals and clinics. The gonad dose during x-ray diagnosis was determined with an ionization chamber placed at the positions of ovary and testis in a Rando phantom. The instrumented phantom was irradiated with medical diagnostic x-rays on the basis of the exposure data on the patients selected in the nation wide survey. In the calculation of the genetically significant dose, the child expectancy of the patients that undergo each particular type of examination was assumed to be same as that of the general population. The resultant genetically significant dose was 11.1 and 5.43 mrad per person per year for radiography and fluoroscopy, respectively. These values were compared with those of 1960 and 1969. Though the number of examinations per year shows a yearly increase, the genetically significant dose is gradually on the decrease. This may be due to technical improvements in medical radiological practices.

Annual intake of 137Cs and 90Sr from ingestion of main foodstuffs in Taiwan

International Nuclear Information System (INIS)

Wang, Chih-Jung; Lai, Shu-Ying; Huang, Ching-Chung; Lin, Yu-ming

1996-01-01

The radioactivities of eight main foodstuffs were investigated during 1985-1994 to evaluate the annual intake from the ingestion of 137 Cs and 90 Sr for the residents of Taiwan. The evaluation of annual intake was based on the results of radiochemical analysis of 90 Sr and gamma-ray spectrometry of 137 Cs as well as annual consumption rates of those foodstuffs in Taiwan. The annual intake 90 Sr and 137 Cs per capita is 13 and 60 Bq, respectively. Among the eight foodstuffs, fruit contributed the most to the annual intake of 90 Sr, vegetable second, rice the third and egg the least. For 137 Cs, rice contributed the most, then fruit, meat the third and flour the least. Based on the new conversion factors from ICRP 60, the annual committed effective doses of Taiwanese due to the ingestion of radionuclides 90 Sr and 137 Cs were estimated to be 3.7 x 10 -7 and 7.8 x 10 -7 Sv, respectively. (author)

Estimating Derived Response Levels at the Savannah River Site for Use with Emergency Response Models

International Nuclear Information System (INIS)

Simpkins, A.A.

2002-01-01

Emergency response computer models at the Savannah River Site (SRS) are coupled with real-time meteorological data to estimate dose to individuals downwind of accidental radioactive releases. Currently, these models estimate doses for inhalation and shine pathways, but do not consider dose due to ingestion of contaminated food products. The Food and Drug Administration (FDA) has developed derived intervention levels (DIL) which refer to the radionuclide-specific concentration in food present throughout the relevant period of time, with no intervention, that could lead to an individual receiving a radiation dose equal to the protective action guide. In the event of an emergency, concentrations in various food types are compared with these levels to make interdictions decisions. Prior to monitoring results being available, concentrations in the environmental media (i.e. soil), called derived response levels (DRLs), can be estimated from the DILs and directly compared with computer output to provide preliminary guidance as to whether intervention is necessary. Site-specific derived response levels (DRLs) are developed for ingestion pathways pertinent to SRS: milk, meat, fish, grain, produce, and beverage. This provides decision-makers with an additional tool for use immediately following an accident prior to the acquisition of food monitoring data

Dose estimation for space radiation protection

International Nuclear Information System (INIS)

Xu Feng; Xu Zhenhua; Huang Zengxin; Jia Xianghong

2007-01-01

For evaluating the effect of space radiation on human health, the dose was estimated using the models of space radiation environment, models of distribution of the spacecraft's or space suit's mass thickness and models of human body. The article describes these models and calculation methods. (authors)

We can do better than effective dose for estimating or comparing low-dose radiation risks

International Nuclear Information System (INIS)

Brenner, D.J.

2012-01-01

The effective dose concept was designed to compare the generic risks of exposure to different radiation fields. More commonly these days, it is used to estimate or compare radiation-induced cancer risks. For various reasons, effective dose represents flawed science: for instance, the tissue-specific weighting factors used to calculate effective dose are a subjective mix of different endpoints; and the marked and differing age and gender dependencies for different health detriment endpoints are not taken into account. This paper suggests that effective dose could be replaced with a new quantity, ‘effective risk’, which, like effective dose, is a weighted sum of equivalent doses to different tissues. Unlike effective dose, where the tissue-dependent weighting factors are a set of generic, subjective committee-defined numbers, the weighting factors for effective risk are simply evaluated tissue-specific lifetime cancer risks per unit equivalent dose. Effective risk, which has the potential to be age and gender specific if desired, would perform the same comparative role as effective dose, be just as easy to estimate, be less prone to misuse, be more directly understandable, and would be based on solid science. An added major advantage is that it gives the users some feel for the actual numerical values of the radiation risks they are trying to control.

Patient-specific dose estimation for pediatric chest CT

Energy Technology Data Exchange (ETDEWEB)

Li Xiang; Samei, Ehsan; Segars, W. Paul; Sturgeon, Gregory M.; Colsher, James G.; Frush, Donald P. [Medical Physics Graduate Program, Duke University, Durham, North Carolina 27705 and Department of Radiology, Duke Advanced Imaging Laboratories, Duke University Medical Center, Durham, North Carolina 27705 (United States); Medical Physics Graduate Program, Duke University, Durham, North Carolina 27705 (United States); Department of Radiology, Duke Advanced Imaging Laboratories, Duke University Medical Center, Durham, North Carolina 27705 (United States); Department of Physics, Duke University, Durham, North Carolina 27710 (United States); and Department of Biomedical Engineering, Duke University, Durham, North Carolina 27708 (United States); Medical Physics Graduate Program, Duke University, Durham, North Carolina 27705 and Department of Radiology, Duke Advanced Imaging Laboratories, Duke University Medical Center, Durham, North Carolina 27705 (United States); Department of Radiology, Duke Advanced Imaging Laboratories, Duke University Medical Center, Durham, North Carolina 27705 (United States); Medical Physics Graduate Program, Duke University, Durham, North Carolina 27705 and Global Applied Science Laboratory, GE Healthcare, Waukesha, Wisconsin 53188 (United States); Medical Physics Graduate Program, Duke University, Durham, North Carolina 27705 and Department of Radiology, Division of Pediatric Radiology, Duke University Medical Center, Durham North Carolina 27710 (United States)

2008-12-15

Current methods for organ and effective dose estimations in pediatric CT are largely patient generic. Physical phantoms and computer models have only been developed for standard/limited patient sizes at discrete ages (e.g., 0, 1, 5, 10, 15 years old) and do not reflect the variability of patient anatomy and body habitus within the same size/age group. In this investigation, full-body computer models of seven pediatric patients in the same size/protocol group (weight: 11.9-18.2 kg) were created based on the patients' actual multi-detector array CT (MDCT) data. Organs and structures in the scan coverage were individually segmented. Other organs and structures were created by morphing existing adult models (developed from visible human data) to match the framework defined by the segmented organs, referencing the organ volume and anthropometry data in ICRP Publication 89. Organ and effective dose of these patients from a chest MDCT scan protocol (64 slice LightSpeed VCT scanner, 120 kVp, 70 or 75 mA, 0.4 s gantry rotation period, pitch of 1.375, 20 mm beam collimation, and small body scan field-of-view) was calculated using a Monte Carlo program previously developed and validated to simulate radiation transport in the same CT system. The seven patients had normalized effective dose of 3.7-5.3 mSv/100 mAs (coefficient of variation: 10.8%). Normalized lung dose and heart dose were 10.4-12.6 mGy/100 mAs and 11.2-13.3 mGy/100 mAs, respectively. Organ dose variations across the patients were generally small for large organs in the scan coverage (<7%), but large for small organs in the scan coverage (9%-18%) and for partially or indirectly exposed organs (11%-77%). Normalized effective dose correlated weakly with body weight (correlation coefficient: r=-0.80). Normalized lung dose and heart dose correlated strongly with mid-chest equivalent diameter (lung: r=-0.99, heart: r=-0.93); these strong correlation relationships can be used to estimate patient-specific organ

Estimating effective doses to children from CT examinations

International Nuclear Information System (INIS)

Heron, J.C.L.

2000-01-01

Full text: Assessing doses to patients in diagnostic radiology is an integral part of implementing optimisation of radiation protection. Sources of normalised data are available for estimating doses to adults undergoing CT examinations, but for children this is not the case. This paper describes a simple method for estimating effective doses arising from paediatric CT examinations. First the effective dose to an adult is calculated, having anatomically matched the scanned regions of the child and the adult and also matched the irradiation conditions. A conversion factor is then applied to the adult effective dose, based on the region of the body being scanned - head, upper or lower trunk. This conversion factor is the child-to-adult ratio of the ratios of effective dose per entrance air kerma (in the absence of the patient) at the FAD. The values of these conversion factors were calculated by deriving effective dose per entrance air kerma at the FAD for new-born, 1, 5, 10, 15 and adult phantoms using four projections (AP, PA, left and right laterals) over a range of beam qualities and FADs.The program PCXMC was used for this purpose. Results to date suggest that the conversion factors to give effective doses for children undergoing CT examinations of the upper trunk are approximately 1.3, 1.2, 1.15, 1.1 and 1.05 for ages 0, 1, 5, 10 and 15 years respectively; CT of the lower trunk - 1.4, 1.3, 1.2, 1.2, 1.1; and CT of the head - 2.3, 2.0, 1.5, 1.3, 1.1. The dependence of these factors on beam quality (HVL from 4 to 10 mm Al) is less than 10%, with harder beams resulting in slightly smaller conversion factors. Dependence on FAD is also less than 10%. Major sources of uncertainties in the conversion factors include matching anatomical regions across the phantoms, and the presence of beam divergence in the z-direction when deriving the factors. The method described provides a simple means of estimating effective doses arising from paediatric CT examinations with

Estimation of dose and exposure at sentinel node study

International Nuclear Information System (INIS)

Skopljak, A.; Kucukalic-Selimovic, E.; Beslic, N.; Begic, A.; Begovic-Hadzimuratovic, S.; Drazeta, Z.; Beganovic, A.

2005-01-01

The purpose of this study was to estimate the dose end exposure in staff involved in sentinel node procedure for breast cancer patients. The Institute of Nuclear Medicine in Sarajevo uses a protocol for lymphoscintigraphy of the sentinel node whereby 13 MBq of 9 9mT c nanocoll are used. In this study, we measured radiation doses and exposure of a nuclear medicine physician and a technologist, as well as a surgeon performing sentinel node lymphoscintigraphy and biopsy. Dose and exposure were calculated using the equation in which we have gamma constant for 9 9mT c. Calculations were made for different times of exposure and distance. In Table 1. we estimated the dose and exposure during sentinel node study. Radiation levels were very low and the most exposed hospital staff performing sentinel node study were nuclear medicine physicians. The doses on the hands of surgeons were negligible 8 hours after exposure.(author)

Radionuclides in food and the radiation exposure due to ingestion

International Nuclear Information System (INIS)

Michel, Rolf

2015-01-01

As a consequence of the reactor accidents in Fukushima Daiichi high amounts of radioactive iodine and cesium isotopes were released into the terrestrial and marine Japanese environment. The largest release occurred on March 15, 2011 as a consequence of the containment failure of unit 2. Due to the meteorological conditions large area fallout occurred in the district of Fukushima. Other prefectures in the north of Japan were also contaminated. As a consequence of the high surface contamination the dose limits for drinking water, milk and milky products and food were increased to 200 Bq/kg.It turned out that the contamination of rice was marginal, the contamination of predatory fish higher than that of non-predatory fish. A systematic investigation of food samples could allow a better estimation of ingestion induced exposure.

Estimated effects on radiation doses from alternatives in a spent fuel transportation system

International Nuclear Information System (INIS)

Schneider, K.J.; Ross, W.A.; Smith, R.I.

1988-07-01

This paper contains the results of a study of estimated radiation doses to the public and workers from the transport of spent fuel from commercial nuclear power reactors to a geologic repository. A postulated reference rail/legal-weight truck transportation system is defined that would use current transportation technology, and provide a breakdown of activities and time/distance/dose-rate estimates for each activity within the system. Collective doses are estimated for each of the major activities at the reactor site, in transit, and at the repository receiving facility. Annual individual doses to the maximally exposed individuals or groups of individuals are also estimated. The dose-reduction potentials and costs are estimated for a total of 17 conceptual alternatives and subalternatives to the postulated reference system. Most of the alternatives evaluated are estimated to provide both cost and dose reductions. The major conclusion is that the potential exists for significant future reductions in radiation doses to the public and workers and for reductions in costs compared to those based on a continuation of past practices in the US

Estimated effects on radiation doses from alternatives in a spent fuel transportation system

International Nuclear Information System (INIS)

Schneider, K.J.; Ross, W.A.; Smith, R.I.

1988-01-01

This paper contains the results of a study of estimated radiation doses to the public and workers from the transport of spent fuel from commercial nuclear power reactors to a geologic repository. A postulated reference rail/legal-weight truck transportation system is defined that would use current transportation technology, and provide a breakdown of activities and time/distance/dose-rate estimates for each activity within the system. Collective doses are estimated for each of the major activities at the reactor site, in transit, and at the repository receiving facility. Annual individual doses to the maximally exposed individuals or groups of individuals also estimated. The dose-reduction potentials and costs are estimated for a total of 17 conceptual alternatives and subalternatives to the postulated reference system. Most of the alternatives evaluated are estimated to provide both cost and dose reductions. The major conclusion is that the potential exists for significant future reductions in radiation doses to the public and workers and for reductions in costs compared to those based on a continuation of past practices in the U.S

Simplification of an MCNP model designed for dose rate estimation

Science.gov (United States)

Laptev, Alexander; Perry, Robert

2017-09-01

A study was made to investigate the methods of building a simplified MCNP model for radiological dose estimation. The research was done using an example of a complicated glovebox with extra shielding. The paper presents several different calculations for neutron and photon dose evaluations where glovebox elements were consecutively excluded from the MCNP model. The analysis indicated that to obtain a fast and reasonable estimation of dose, the model should be realistic in details that are close to the tally. Other details may be omitted.

Biological dose estimation and comet analysis of the victims in a high dose 60Co radiation accident

International Nuclear Information System (INIS)

Chen Ying; Liu Xiulin; Luo Yisheng; Li You; Yao Bo

2007-01-01

Objective: To explore the methods of chromosome preparation in human peripheral blood and bone marrow after very high dose exposure and fit the dose-response curve of dicentrics and tings in the range of high doses over 6 Gy for estimating biological dose and detecting DNA damage in the victims of '10.21' accident. Methods: The samples of peripheral blood and bone marrow in 2 victims were collected to prepare chromosome mataphases and dicentrics (multicentrics) + rings were counted. The dose-response curve and equation of human blood irradiated between 6-22 Gy in vitro were established and applied to assess biological dose of 2 victims. In addition, their DNA damages were tested by alkaline single cell gel electrophoresis. Results: The dicentric + ring numbers of 4.47 per cell in victims B's peripheral blood lymphocytes and 9.15 per cell in victim A's bone marrow who had no mitosis in peripheral blood cell. The whole body average doses of victims B and A estimated by 6-22 Gy equation arrived at 9.4 Gy and 19.5 Gy, respectively. The serious DNA damages were expressed by small head and large tail comet figures. Conclusions: The biological doses of 2 victims estimated by 6-22 Gy dose-response curve have reached the levels of extreme grave bone marrow and intestinal ARS, respectively. (authors)

Estimation of dose in irradiated chicken bone by ESR method

International Nuclear Information System (INIS)

Tanabe, Hiroko; Hougetu, Daisuke

1998-01-01

The author studied the conditions needed to routinely estimate the radiation dose in chicken bone by repeated re-irradiation and measuring ESR signals. Chicken meat containing bone was γ-irradiated at doses of up to 3kGy, accepted as the commercially used dose. The results show that points in sample preparation and ESR measurement are as follows: Both ends of bone are cut off and central part of compact bone is used for experiment. To obtain accurate ESR spectrum, marrow should be scraped out completely. Sample bone fragments of 1-2mm particle size and ca.100mg are recommended to obtain stable and maximum signal. In practice, by re-irradiating up to 5kGy and extrapolating data of the signal intensity to zero using linear regression analysis, radiation dose is estimated. For example, in one experiment, estimated doses of chicken bones initially irradiated at 3.0kGy, 1.0kGy, 0.50kGy and 0.25kGy were 3.4kGy, 1.3kGy, 0.81kGy and 0.57kGy. (author)

Patient absorbed radiation doses estimation related to irradiation anatomy

International Nuclear Information System (INIS)

Soares, Flavio Augusto Penna; Soares, Amanda Anastacio; Kahl, Gabrielly Gomes

2014-01-01

Developed a direct equation to estimate the absorbed dose to the patient in x-ray examinations, using electric, geometric parameters and filtering combined with data from irradiated anatomy. To determine the absorbed dose for each examination, the entrance skin dose (ESD) is adjusted to the thickness of the patient's specific anatomy. ESD is calculated from the estimated KERMA greatness in the air. Beer-Lambert equations derived from power data mass absorption coefficients obtained from the NIST / USA, were developed for each tissue: bone, muscle, fat and skin. Skin thickness was set at 2 mm and the bone was estimated in the central ray of the site, in the anteroposterior view. Because they are similar in density and attenuation coefficients, muscle and fat are treated as a single tissue. For evaluation of the full equations, we chose three different anatomies: chest, hand and thigh. Although complex in its shape, the equations simplify direct determination of absorbed dose from the characteristics of the equipment and patient. The input data is inserted at a single time and total absorbed dose (mGy) is calculated instantly. The average error, when compared with available data, is less than 5% in any combination of device data and exams. In calculating the dose for an exam and patient, the operator can choose the variables that will deposit less radiation to the patient through the prior analysis of each combination of variables, using the ALARA principle in routine diagnostic radiology sector

Chest X ray effective doses estimation in computed radiography

International Nuclear Information System (INIS)

Abdalla, Esra Abdalrhman Dfaalla

2013-06-01

Conventional chest radiography is technically difficult because of wide in tissue attenuations in the chest and limitations of screen-film systems. Computed radiography (CR) offers a different approach utilizing a photostimulable phosphor. photostimulable phosphors overcome some image quality limitations of chest imaging. The objective of this study was to estimate the effective dose in computed radiography at three hospitals in Khartoum. This study has been conducted in radiography departments in three centres Advanced Diagnostic Center, Nilain Diagnostic Center, Modern Diagnostic Center. The entrance surface dose (ESD) measurement was conducted for quality control of x-ray machines and survey of operators experimental techniques. The ESDs were measured by UNFORS dosimeter and mathematical equations to estimate patient doses during chest X rays. A total of 120 patients were examined in three centres, among them 62 were males and 58 were females. The overall mean and range of patient dosed was 0.073±0.037 (0.014-0.16) mGy per procedure while the effective dose was 3.4±01.7 (0.6-7.0) mSv per procedure. This study compared radiation doses to patients radiographic examinations of chest using computed radiology. The radiation dose was measured in three centres in Khartoum- Sudan. The results of the measured effective dose showed that the dose in chest radiography was lower in computed radiography compared to previous studies.(Author)

Estimation of effective dose equivalente from external irradiations

International Nuclear Information System (INIS)

Wakabayashi, T.

1985-07-01

A methodology for computing effective dose equivalent, derived from the computer code ALGAM: Monte Carlo Estimation of Internal Dose from Gamma-ray Sources in a Phantom Man, developed at Oak Ridge National Laboratory, is presented. The modified code was run for 12 different photon energy levels, from 0,010 Mev to 4.0 Mev, which provides computing the absorved dose, for these energy levels, in each one of the 97 organs of the original code. The code also was run for the principal energy levels used in the calibration of the dosimetric films. The results of the absorved doses per photon obtained for these levels of energy have been transformed in effective dose equivalents. (M.A.C.) [pt

Spent shot availability and ingestion on areas managed for mourning doves

Science.gov (United States)

Schulz, J.H.; Millspaugh, J.J.; Washburn, B.E.; Wester, G.R.; Lanigan, J. T.; Franson, J.C.

2002-01-01

Mourning dove (Zenaida macroura) hunting is becoming increasingly popular, especially in managed shooting fields. Given the possible increase in the availability of lead (Pb) shot on these areas, our objective was to estimate availability and ingestion of spent shot at the Eagle Bluffs Conservation Area (EBCA, hunted with nontoxic shot) and the James A. Reed Memorial Wildlife Area (JARWA, hunted with Pb shot) in Missouri. During 1998, we collected soil samples one or 2 weeks prior to the hunting season (prehunt) and after 4 days of dove hunting (posthunt). We also collected information on number of doves harvested, number of shots fired, shotgun gauge, and shotshell size used. Dove carcasses were collected on both areas during 1998-99. At EBCA, 60 hunters deposited an estimated 64,775 pellets/ha of nontoxic shot on or around the managed field. At JARWA, approximately 1,086,275 pellets/ha of Pb shot were deposited by 728 hunters. Our posthunt estimates of spent-shot availability from soil sampling were 0 pellets/ha for EBCA and 6,342 pellets/ha for JARWA. Our findings suggest that existing soil sampling protocols may not provide accurate estimates of spent-shot availability in managed dove shooting fields. During 1998-99, 15 of 310 (4.8%) mourning doves collected from EBCA had ingested nontoxic shot. Of those doves, 6 (40.0%) contained a?Y7 shot pellets. In comparison, only 2 of 574 (0.3%) doves collected from JARWA had ingested Pb shot. Because a greater proportion of doves ingested multiple steel pellets compared to Pb pellets, we suggest that doves feeding in fields hunted with Pb shot may succumb to acute Pb toxicosis and thus become unavailable to harvest, resulting in an underestimate of ingestion rates. Although further research is needed to test this hypothesis, our findings may partially explain why previous studies have shown few doves with ingested Pb shot despite their feeding on areas with high Pb shot availability.

Estimation of the Radon-induced Dose for Russia's Population: Methods and Results

International Nuclear Information System (INIS)

Marenny, A.M.; Savkin, M.N.; Shinkarev, S.M.

2000-01-01

A model is proposed for inferring the radon-induced annual average collective and personal doses, as well as the dose distribution of the population, all over Russia from selective radon monitoring in some regions of Russia. The model assumptions and the selective radon monitoring results that underlie the numerical estimates obtained for different population groups are presented. The current estimate of the collective radon-induced dose received by the population of Russia (148,100,000 as of 1996) is about 130,000 man Sv, of which 55,000 man Sv is for the rural population (27% of the total population) and 75,000 man Sv for the urban population (73% of the total). The average radon-induced personal dose in Russia is estimated to be about 0.87 mSv. About 1,000,000 people receive annual doses above 10 mSv, including some 200,000 people who receive doses above 20 mSv annually. The ways of making the current estimates more accurate are outlined. (author)

Measuring water ingestion from spray exposures.

Science.gov (United States)

Sinclair, Martha; Roddick, Felicity; Nguyen, Thang; O'Toole, Joanne; Leder, Karin

2016-08-01

Characterisation of exposure levels is an essential requirement of health risk assessment; however for water exposures other than drinking, few quantitative exposure data exist. Thus, regulatory agencies must use estimates to formulate policy on treatment requirements for non-potable recycled water. We adapted the use of the swimming pool chemical cyanuric acid as a tracer of recreational water ingestion to permit detection of small water volumes inadvertently ingested from spray exposures. By using solutions of 700-1000 mg/L cyanuric acid in an experimental spray exposure scenario, we were able to quantify inadvertent water ingestion in almost 70% of participants undertaking a 10 min car wash activity using a high pressure spray device. Skin absorption was demonstrated to be negligible under the experimental conditions, and the measured ingestion volumes ranged from 0.06 to 3.79 mL. This method could be applied to a range of non-potable water use activities to generate exposure data for risk assessment processes. The availability of such empirical measurements will provide greater assurance to regulatory agencies and industry that potential health risks from exposure to non-potable water supplies are well understood and adequately managed to protect public health. Copyright © 2016 Elsevier Ltd. All rights reserved.

Simplification of an MCNP model designed for dose rate estimation

Directory of Open Access Journals (Sweden)

Laptev Alexander

2017-01-01

Full Text Available A study was made to investigate the methods of building a simplified MCNP model for radiological dose estimation. The research was done using an example of a complicated glovebox with extra shielding. The paper presents several different calculations for neutron and photon dose evaluations where glovebox elements were consecutively excluded from the MCNP model. The analysis indicated that to obtain a fast and reasonable estimation of dose, the model should be realistic in details that are close to the tally. Other details may be omitted.

Estimation of inhalation doses from airborne releases using gross monitors

International Nuclear Information System (INIS)

Goldstein, N.P.

1978-01-01

Monitoring programs at most nuclear facilities involve continuous gross measurements supplemented by periodic isotopic analyses of release samples. The isotopic measurements are required to accurately assess the potential dose from the various effluent streams, but in between these measurements, one depends on the gross monitors to provide approximate indications of the dose. The effluent streams release a variety of nuclides, each with its own dose factor. This means that the relationship between the counting rate in a gross monitor and the potential dose of the effluent being monitored will depend on the isotopic composition of this release. If this composition changes, then the dose indicated by the gross monitor (calibrated for the original group of isotopes) may be significantly in error. The problem of indicating inhalation doses from gross monitoring of airborne releases is considered. In order for this type of monitor to accurately indicate dose, regardless of the isotopic makeup of a release, the analysis shows that its response to each isotope should be proportional to the dose factor of that isotope. These ideas are applied to the monitoring of air particulates using gross beta and gross gamma monitors. The study shows that the former more closely satisfies this condition and as a result, satisfactorily indicates the actual dose from reactor effluents, as determined from detailed isotopic data published in the literature. On the other hand, the gross gamma monitor, with its poorer fit to the condition, provided less than satisfactory accuracy in its dose estimates. In addition, a variety of other mathematical response functions were considered but their dose estimation capabilities were not much better than the straight beta response. The study shows that reasonably accurate dose estimates can be made using properly selected gross monitors, but that significant errors can result with improper ones. (author)

The points for attention in retrospective personal dose estimate

International Nuclear Information System (INIS)

Wang Wuan

1994-01-01

The points which the attention should be paid to in the retrospective personal dose estimate are discussed. They are representative of the dose data, truthfulness of the operation history, accuracy of the man-hour statistics, and rationality of the parameters selection

Proof of concept and dose estimation with binary responses under model uncertainty.

Science.gov (United States)

Klingenberg, B

2009-01-30

This article suggests a unified framework for testing Proof of Concept (PoC) and estimating a target dose for the benefit of a more comprehensive, robust and powerful analysis in phase II or similar clinical trials. From a pre-specified set of candidate models, we choose the ones that best describe the observed dose-response. To decide which models, if any, significantly pick up a dose effect, we construct the permutation distribution of the minimum P-value over the candidate set. This allows us to find critical values and multiplicity adjusted P-values that control the familywise error rate of declaring any spurious effect in the candidate set as significant. Model averaging is then used to estimate a target dose. Popular single or multiple contrast tests for PoC, such as the Cochran-Armitage, Dunnett or Williams tests, are only optimal for specific dose-response shapes and do not provide target dose estimates with confidence limits. A thorough evaluation and comparison of our approach to these tests reveal that its power is as good or better in detecting a dose-response under various shapes with many more additional benefits: It incorporates model uncertainty in PoC decisions and target dose estimation, yields confidence intervals for target dose estimates and extends to more complicated data structures. We illustrate our method with the analysis of a Phase II clinical trial. Copyright (c) 2008 John Wiley & Sons, Ltd.

Expedited Radiation Biodosimetry by Automated Dicentric Chromosome Identification (ADCI) and Dose Estimation.

Science.gov (United States)

Shirley, Ben; Li, Yanxin; Knoll, Joan H M; Rogan, Peter K

2017-09-04

Biological radiation dose can be estimated from dicentric chromosome frequencies in metaphase cells. Performing these cytogenetic dicentric chromosome assays is traditionally a manual, labor-intensive process not well suited to handle the volume of samples which may require examination in the wake of a mass casualty event. Automated Dicentric Chromosome Identifier and Dose Estimator (ADCI) software automates this process by examining sets of metaphase images using machine learning-based image processing techniques. The software selects appropriate images for analysis by removing unsuitable images, classifies each object as either a centromere-containing chromosome or non-chromosome, further distinguishes chromosomes as monocentric chromosomes (MCs) or dicentric chromosomes (DCs), determines DC frequency within a sample, and estimates biological radiation dose by comparing sample DC frequency with calibration curves computed using calibration samples. This protocol describes the usage of ADCI software. Typically, both calibration (known dose) and test (unknown dose) sets of metaphase images are imported to perform accurate dose estimation. Optimal images for analysis can be found automatically using preset image filters or can also be filtered through manual inspection. The software processes images within each sample and DC frequencies are computed at different levels of stringency for calling DCs, using a machine learning approach. Linear-quadratic calibration curves are generated based on DC frequencies in calibration samples exposed to known physical doses. Doses of test samples exposed to uncertain radiation levels are estimated from their DC frequencies using these calibration curves. Reports can be generated upon request and provide summary of results of one or more samples, of one or more calibration curves, or of dose estimation.

Assessment of uncertainties of external dose estimation after the Chernobyl accident

International Nuclear Information System (INIS)

Kruk, Julianna

2008-01-01

Full text: In the remote period of time after the Chernobyl accident the estimation of an external exposure with using of direct dose rate measurements or individual monitoring of inhabitants is rationally only for settlements where the preliminary estimation makes the range equal or greater 1.0 mSv per year. For inhabitancies of settlements where the preliminary estimation makes the range less 1.0 mSv per year the external dose is correctly to estimate by calculation. For the last cases the uncertainty should be assessed. The most accessible initial parameter for calculation of a dose of an external exposure is the average ground deposition of Cs-137 for the settlements. The character of density distribution of Cs-137 deposition in an area of one settlement is well enough studied. The best agreement of distribution of this parameter is reached with log-normal distribution practically for all settlements of the investigated territories with factor of a variation 0.3-0.6 and the standard geometrical deviation lying within the limits of 1.4-1.7. The dose factors which correspond to the structure of an available housing of settlement (type of apartment houses: wooden, stone, multi-storey) and age structure of the population are bring the main contribution into uncertainty of the external dose estimation. The situations with a different level of known information have been considered for the estimation of influence of those parameters on the general uncertainty. Thus the estimation of the uncertainty of the external dose was done for two variant: optimistic and pessimistic. In the optimistic case the estimation of external doses will be spent for specific settlement with known structure of housing and according to a known share of the living population in houses of the certain type. In that case, variability value dose factor will be limited to the chosen type of a residential building (for example - the one-storied wooden house), and a share of the living population

Estimation of doses to patients from ''complex'' conventional X-ray examinations

International Nuclear Information System (INIS)

Calzado, A.; Vano, E.; Moran, P.; Ruiz, S.; Gonzalez, L.; Castellote, C.

1991-01-01

A numerical method has been developed to estimate organ doses and effective dose-equivalent for patients undergoing three 'complex' examinations (barium meal, barium enema and intravenous urography). The separation of radiological procedures into a set of standard numerical views is based on the use of Monte Carlo conversion factors and measurements within a Remab phantom. Radiation doses measured in a phantom for such examinations were compared with predictions of the ''numerical'' method. Dosimetric measurements with thermoluminescent dosemeters attached to the patient's skin along with measurements of the dose-area product during the examination have enabled the derivation of organ doses and to estimate effective dose-equivalent. Mean frequency weighted values of dose-area product, energy imparted to the patient, doses to a set of organs and effective dose-equivalent in the area of Madrid are reported. Comparisons of results with those from similar surveys in other countries were made. (author)

Estimation of doses to patients with chronic radiation sickness from external occupational exposure

International Nuclear Information System (INIS)

Jia Delin; Dai Guangfu

1991-01-01

The doses to patients with chronic radiation sickness who had engaged in diagnostic radiology have been estimated according to the radiation work load, type and capacity of X-ray equipment, protection conditions, data of nationwide survey on doses to X-ray workers in China, or the data of dose monitoring in working places. Based on the activities of radium sources, time taken up in performing radium therapy, distance to radium sources and radiation work load, the doses to patients who had engaged in radium therapy have been estimated. The results of estimated average doses for 29 cases of chronic radiation sickness are given. Their average red marrow dose, trunk dose and effective dose equivalent are 1.3 Gy, 1.2 Gy and 1.6 Sv, respectively

Hygienic estimation of population doses due to stratospheric fallout

International Nuclear Information System (INIS)

Marej, A.N.; Knizhnikov, V.A.

1980-01-01

The hygienic estimation of external and internal irradiation of the USSR population due to stratospheric global fallouts of fission products after nuclear explosions and weapon tests, is carried out. Numerical values which characterize the dose-effect dependence in the case of radiation of marrow, bone tissue and whole body are presented. Values of mean individual and population doses of irradiation due to global fallouts within 1963-1975, types of injury and the number of mortal cases due to malignant neoplasms are presented. A conclusion is made that the contribution of radiation due to stratospheric fallouts in the mortality due to malignant neoplasms is insignificant. Annual radiation doses, conditioned by global fallouts within the period of 1963-1975 constitute but several percent from the dose of radiation of the natural radiation background. Results of estimation of genetic consequences of irradiation due to atmospheric fallouts are presented

Metabolic and exercise endurance effects of coffee and caffeine ingestion.

Science.gov (United States)

Graham, T E; Hibbert, E; Sathasivam, P

1998-09-01

Caffeine (Caf) ingestion increases plasma epinephrine (Epi) and exercise endurance; these results are frequently transferred to coffee (Cof) consumption. We examined the impact of ingestion of the same dose of Caf in Cof or in water. Nine healthy, fit, young adults performed five trials after ingesting (double blind) either a capsule (Caf or placebo) with water or Cof (decaffeinated Cof, decaffeinated with Caf added, or regular Cof). In all three Caf trials, the Caf dose was 4.45 mg/kg body wt and the volume of liquid was 7.15 ml/kg. After 1 h of rest, the subject ran at 85% of maximal O2 consumption until voluntary exhaustion (approximately 32 min in the placebo and decaffeinated Cof tests). In the three Caf trials, the plasma Caf and paraxanthine concentrations were very similar. After 1 h of rest, the plasma Epi was increased (P capsules than with Cof. During the exercise there were no differences in Epi among the three Caf trials, and the Epi values were all greater (P capsule trial; there were no differences among the other four tests. One cannot extrapolate the effects of Caf to Cof; there must be a component(s) of Cof that moderates the actions of Caf.

Suicide attempt using pure methanol with hospitalization of the patient soon after ingestion: case report.

Science.gov (United States)

Bucaretchi, Fábio; De Capitani, Eduardo Mello; Madureira, Paulo Roberto de; Cesconetto, Danielle Menezes; Lanaro, Rafael; Vieira, Ronan José

2009-05-01

Most patients with methanol poisoning typically show up one to several days after ingestion, presenting severe acidosis, visual disorders, or both. Reports of hospitalization less than 6 h after exposure are unusual. We describe a case of attempted suicide using methanol admitted 3 h after ingestion. A 52-year-old male was hospitalized 3 h after intentional ingestion of 150 ml of 99.9% methanol with no co-ingestion of ethanol. He was alert and cooperative, presenting nausea and vertigo, and reporting six episodes of vomiting. Physical examination showed no remarkable features. A blood sample for methanol and ethanol determination was obtained 4 h after ingestion. The result (available 10 h after ingestion) showed 70 mg/dl of methanol, without detectable ethanol. He was treated with a loading dose of 10% ethanol solution (7 ml/kg, intravenously), followed by a maintenance dose of 0.9-1.0 ml/kg/h intravenously (10 to 51 h); hemodialysis (19 to 27 h, together with 2.1 ml/kg/h of 10% ethanol intravenously); and folinic acid intravenously (50 mg every 6 h, from 4 to 51 h). He developed mild/moderate metabolic acidosis without acidemia and was discharged on day four after ophthalmological evaluation and cerebral computed tomography scan, without abnormalities. Follow-up revealed no sequelae. This could be classified as a potentially severe case of methanol poisoning, according to the amount and concentration of methanol ingested, and blood methanol concentration at 4 h. The good outcome was attributable to early hospitalization and early antidotal therapy with hemodialysis, starting at 10 and 19 h, respectively.

Single point estimation of phenytoin dosing: a reappraisal.

Science.gov (United States)

Koup, J R; Gibaldi, M; Godolphin, W

1981-11-01

A previously proposed method for estimation of phenytoin dosing requirement using a single serum sample obtained 24 hours after intravenous loading dose (18 mg/Kg) has been re-evaluated. Using more realistic values for the volume of distribution of phenytoin (0.4 to 1.2 L/Kg), simulations indicate that the proposed method will fail to consistently predict dosage requirements. Additional simulations indicate that two samples obtained during the 24 hour interval following the iv loading dose could be used to more reliably predict phenytoin dose requirement. Because of the nonlinear relationship which exists between phenytoin dose administration rate (RO) and the mean steady state serum concentration (CSS), small errors in prediction of the required RO result in much larger errors in CSS.

Effect of Carbohydrate and Caffeine Ingestion on Badminton Performance.

Science.gov (United States)

Clarke, Neil D; Duncan, Michael J

2016-01-01

To investigate the effect of ingesting carbohydrate and caffeine solutions on measures that are central to success in badminton. Twelve male badminton players performed a badminton serve-accuracy test, coincidence-anticipation timing (CAT), and a choice reaction-time sprint test 60 min before exercise. Participants then consumed 7 mL/kg body mass of either water (PLA), 6.4% carbohydrate solution (CHO), a solution containing a caffeine dose of 4 mg/kg, or 6.4% carbohydrate and 4 mg/kg caffeine (C+C). All solutions were flavored with orange-flavored concentrate. During the 33-min fatigue protocol, participants were provided with an additional 3 mL/kg body mass of solution, which was ingested before the end of the protocol. As soon as the 33-min fatigue protocol was completed, all measures were recorded again. Short-serve accuracy was improved after the ingestion of CHO and C+C compared with PLA (P = .001, η(p)(2) = .50). Long-serve accuracy was improved after the ingestion of C+C compared with PLA (P badminton match can maintain serve accuracy, anticipation timing, and sprinting actions around the court.

The ecosystem models used for dose assessments in SR-Can

Energy Technology Data Exchange (ETDEWEB)

Avila, Rodolfo [Facilia AB, Bromma (Sweden)

2006-11-15

The estimation of doses to humans in the main scenarios considered in SR-Can is carried out by multiplying the radionuclide releases to the biosphere by Landscape Dose Factors (LDF), which provide estimates of doses incurred by unit releases of activity of a specific radionuclide to the landscape. The landscape models considered in deriving the LDFs consist of a set of interconnected ecosystem models of different types, including aquatic and terrestrial ecosystems. Aquatic ecosystems comprise the sea, lakes and rivers. The terrestrial ecosystems include agricultural lands, forests and mires. In this report dose conversion factor for each individual ecosystem are reported. Two release cases are considered in the report: a constant unit release rate during 10,000 years and a pulse release, i.e. a unit release during one year. For deriving the LDF values, at each considered time period an ecosystem model is assigned to each landscape object, according to the projected succession of ecosystems in the objects. The applied ecosystem models have been described elsewhere, but some modifications have been made which are described in this report. The main modifications applied to the models are to consider releases through bottom sediments and to consider upstream fluxes for the estimation of the fluxes of radionuclides between the different landscape objects. To facilitate calculations of the radionuclide concentrations in the ingested food, aggregated transfer factors are derived for each ecosystem type. These relate the radionuclide concentrations in the edible carbon production in different ecosystem types to the radionuclide concentrations in the main environmental substrates of the ecosystems, i.e. the water in aquatic ecosystems and the soil in the terrestrial ecosystems. The report provides a description of the methods applied for the derivation of aggregated transfer factors for each ecosystem type and for irrigation. These factors are applicable for situations of

The ecosystem models used for dose assessments in SR-Can

International Nuclear Information System (INIS)

Avila, Rodolfo

2006-11-01

The estimation of doses to humans in the main scenarios considered in SR-Can is carried out by multiplying the radionuclide releases to the biosphere by Landscape Dose Factors (LDF), which provide estimates of doses incurred by unit releases of activity of a specific radionuclide to the landscape. The landscape models considered in deriving the LDFs consist of a set of interconnected ecosystem models of different types, including aquatic and terrestrial ecosystems. Aquatic ecosystems comprise the sea, lakes and rivers. The terrestrial ecosystems include agricultural lands, forests and mires. In this report dose conversion factor for each individual ecosystem are reported. Two release cases are considered in the report: a constant unit release rate during 10,000 years and a pulse release, i.e. a unit release during one year. For deriving the LDF values, at each considered time period an ecosystem model is assigned to each landscape object, according to the projected succession of ecosystems in the objects. The applied ecosystem models have been described elsewhere, but some modifications have been made which are described in this report. The main modifications applied to the models are to consider releases through bottom sediments and to consider upstream fluxes for the estimation of the fluxes of radionuclides between the different landscape objects. To facilitate calculations of the radionuclide concentrations in the ingested food, aggregated transfer factors are derived for each ecosystem type. These relate the radionuclide concentrations in the edible carbon production in different ecosystem types to the radionuclide concentrations in the main environmental substrates of the ecosystems, i.e. the water in aquatic ecosystems and the soil in the terrestrial ecosystems. The report provides a description of the methods applied for the derivation of aggregated transfer factors for each ecosystem type and for irrigation. These factors are applicable for situations of

Feasibility of an ingestible sensor-based system for monitoring adherence to tuberculosis therapy.

Directory of Open Access Journals (Sweden)

Robert Belknap

Full Text Available Poor adherence to tuberculosis (TB treatment hinders the individual's recovery and threatens public health. Currently, directly observed therapy (DOT is the standard of care; however, high sustaining costs limit its availability, creating a need for more practical adherence confirmation methods. Techniques such as video monitoring and devices to time-register the opening of pill bottles are unable to confirm actual medication ingestions. A novel approach developed by Proteus Digital Health, Inc. consists of an ingestible sensor and an on-body wearable sensor; together, they electronically confirm unique ingestions and record the date/time of the ingestion. A feasibility study using an early prototype was conducted in active TB patients to determine the system's accuracy and safety in confirming co-ingestion of TB medications with sensors. Thirty patients completed 10 DOT visits and 1,080 co-ingestion events; the system showed 95.0% (95% CI 93.5-96.2% positive detection accuracy, defined as the number of detected sensors divided by the number of transmission capable sensors administered. The specificity was 99.7% [95% CI 99.2-99.9%] based on three false signals recorded by receivers. The system's identification accuracy, defined as the number of correctly identified ingestible sensors divided by the number of sensors detected, was 100%. Of 11 adverse events, four were deemed related or possibly related to the device; three mild skin rashes and one complaint of nausea. The system's positive detection accuracy was not affected by the subjects' Body Mass Index (p = 0.7309. Study results suggest the system is capable of correctly identifying ingestible sensors with high accuracy, poses a low risk to users, and may have high patient acceptance. The system has the potential to confirm medication specific treatment compliance on a dose-by-dose basis. When coupled with mobile technology, the system could allow wirelessly observed therapy (WOT for

Home gardening near a mining site in an arsenic-endemic region of Arizona: assessing arsenic exposure dose and risk via ingestion of home garden vegetables, soils, and water.

Science.gov (United States)

Ramirez-Andreotta, Monica D; Brusseau, Mark L; Beamer, Paloma; Maier, Raina M

2013-06-01

The human-health risk posed by gardening near a legacy mine and smelter in an arsenic-endemic region of Arizona was characterized in this study. Residential soils were used in a greenhouse study to grow common vegetables, and local residents, after training, collected soil, water, and vegetables samples from their home gardens. Concentrations of arsenic measured in water, soil, and vegetable samples were used in conjunction with reported US intake rates to calculate the daily dose, Incremental Excess Lifetime Cancer Risk (IELCR), and Hazard Quotient for arsenic. Relative arsenic intake dose decreased in order: water>garden soils>homegrown vegetables, and on average, each accounted for 77, 16, and 7% of a residential gardener's daily arsenic intake dose. The IELCR ranges for vegetables, garden soils, and water were 10(-8) to 10(-4), 10(-6) to 10(-4), and 10(-5) to 10(-2), respectively. All vegetables (greenhouse and home garden) were grouped by scientific family, and the risk posed decreased as: Asteraceae≫Fabaceae>Amaranthaceae>Liliaceae>Brassicaceae>Solanaceae≫Cucurbitaceae. Correlations observed between concentrations of arsenic in vegetables and soils were used to estimate a maximum allowable level of arsenic in soil to limit the excess cancer risk to 10(-6). The estimated values are 1.56 mg kg(-1), 5.39 mg kg(-1), 11.6 mg kg(-1) and 12.4 mg kg(-1) for the Asteraceae, Brassicaceae, Fabaceae, and Amaranthaceae families, respectively. It is recommended that home gardeners: sample their private wells annually, test their soils prior to gardening, and, if necessary, modify their gardening behavior to reduce incidental soil ingestion. This study highlights the importance of site-specific risk assessment, and the need for species-specific planting guidelines for communities. Copyright © 2013 Elsevier B.V. All rights reserved.

Detection of β-lactoglobulin in human breast-milk 7 days after cow milk ingestion.

Science.gov (United States)

Matangkasombut, Ponpan; Padungpak, Savitree; Thaloengsok, Sasikanya; Kamchaisatian, Wasu; Sasisakulporn, Cherapat; Jotikasthira, Wanlapa; Benjaponpitak, Suwat; Manuyakorn, Wiparat

2017-08-01

β-lactoglobulin (BLG), a major allergen in cow milk (CM) can be detected in human breast-milk (BM) and is associated with exacerbation of symptoms in breastfed infants with cow milk protein allergy (CMPA). Currently, it is not known how long lactating mothers who consume dairy products need to withhold breastfeeding. To elucidate the kinetics of BLG in BM after maternal ingestion of a single dose of CM. Nineteen lactating mothers, four of whom had infants with CMPA, were instructed to avoid CM for 7 days before ingesting a single dose of CM and to continue to withhold CM thereafter throughout the study period. BLG was measured by ELISA in BM from 15 mothers of healthy infants before and at 3, 6 and 24 h, and 3 and 7 days after CM ingestion. Four pairs of mothers and CMPA infants were enrolled for BM challenge after the mothers had ingested CM. After CM ingestion, the level of BLG in BM increased significantly from 0.58 ng/ml (0.58 g/L) (IQR 0.38-0.88) to a peak level of 1.23 ng/ml (IQR 1.03-2.29), p < 0.001. The BLG level on day 3 (1.15 ng/ml, IQR 0.89-1.45) and day 7 (1.08 ng/ml (IQR 0.86-1.25) after CM ingestion was significantly higher than baseline (p = 0.01 and p = 0.001, respectively). BLG was detected in all BM samples from the four mothers of CMPA infants after CM ingestion, and the level was not different from that in the mothers of the 15 healthy infants. Three of the four CMPA infants developed symptoms such as maculopapular rash and hypersecretion in the airways after BM challenge. BLG can be detected in BM up to 7 days after CM ingestion. Lactating mothers should suspend breastfeeding to CMPA infants more than 7 days after CM ingestion.

On the uncertainties in effective dose estimates of adult CT head scans

International Nuclear Information System (INIS)

Gregory, Kent J.; Bibbo, Giovanni; Pattison, John E.

2008-01-01

Estimates of the effective dose to adult patients from computed tomography (CT) head scanning can be calculated using a number of different methods. These estimates can be used for a variety of purposes, such as improving scanning protocols, comparing different CT imaging centers, and weighing the benefits of the scan against the risk of radiation-induced cancer. The question arises: What is the uncertainty in these effective dose estimates? This study calculates the uncertainty of effective dose estimates produced by three computer programs (CT-EXPO, CTDosimetry, and ImpactDose) and one method that makes use of dose-length product (DLP) values. Uncertainties were calculated in accordance with an internationally recognized uncertainty analysis guide. For each of the four methods, the smallest and largest overall uncertainties (stated at the 95% confidence interval) were: 20%-31% (CT-EXPO), 15%-28% (CTDosimetry), 20%-36% (ImpactDose), and 22%-32% (DLP), respectively. The overall uncertainties for each method vary due to differences in the uncertainties of factors used in each method. The smallest uncertainties apply when the CT dose index for the scanner has been measured using a calibrated pencil ionization chamber

Literature study of the radiobiological parameters of Caesium-137 required for evaluating internal irradiation doses as a function of age

International Nuclear Information System (INIS)

Garnier, A.

1968-01-01

This document reassembles information published in scientific literature on radiobiological parameters of Cs-137, necessary for the estimate of the internal irradiation dose of man according to his age (during growth). The data are completed by a commented review of the mathematical models, proposed in order to value the irradiation doses from ingested cesium and the biological parameters. (author) [fr

Estimating the Absorbed Dose to Critical Organs During Dual X-ray Absorptiometry

Energy Technology Data Exchange (ETDEWEB)

Mokhtari-Dizaji, M.; Sharafi, A. A.; Larijani, B.; Mokhlesian, N.; Hasanzadeh, H. [Tarbiat Modares University, Tehran (Iran, Islamic Republic of)

2008-04-15

Objective : The purpose of this study is to estimate a patient's organ dose (effective dose) during performance of dual X-ray absorptiometry by using the correlations derived from the surface dose and the depth doses in an anthropomorphic phantom. Materials and Methods : An anthropomorphic phantom was designed and TLDs (Thermoluminescent Dosimeters) were placed at the surface and these were also inserted at different depths of the thyroid and uterus of the anthropomorphic phantom. The absorbed doses were measured on the phantom for the spine and femur scan modes. The correlation coefficients and regression functions between the absorbed surface dose and the depth dose were determined. The derived correlation was then applied for 40 women patients to estimate the depth doses to the thyroid and uterus. Result : There was a correlation between the surface dose and depth dose of the thyroid and uterus in both scan modes. For the women's dosimetry, the average surface doses of the thyroid and uterus were 1.88 {mu}Gy and 1.81 Gy, respectively. Also, the scan center dose in the women was 5.70 Gy. There was correlation between the thyroid and uterus surface doses, and the scan center dose. Conclusion : We concluded that the effective dose to the patient's critical organs during dual X-ray absorptiometry can be estimated by the correlation derived from phantom dosimetry.

Estimating the Absorbed Dose to Critical Organs During Dual X-ray Absorptiometry

International Nuclear Information System (INIS)

Mokhtari-Dizaji, M.; Sharafi, A. A.; Larijani, B.; Mokhlesian, N.; Hasanzadeh, H.

2008-01-01

Objective : The purpose of this study is to estimate a patient's organ dose (effective dose) during performance of dual X-ray absorptiometry by using the correlations derived from the surface dose and the depth doses in an anthropomorphic phantom. Materials and Methods : An anthropomorphic phantom was designed and TLDs (Thermoluminescent Dosimeters) were placed at the surface and these were also inserted at different depths of the thyroid and uterus of the anthropomorphic phantom. The absorbed doses were measured on the phantom for the spine and femur scan modes. The correlation coefficients and regression functions between the absorbed surface dose and the depth dose were determined. The derived correlation was then applied for 40 women patients to estimate the depth doses to the thyroid and uterus. Result : There was a correlation between the surface dose and depth dose of the thyroid and uterus in both scan modes. For the women's dosimetry, the average surface doses of the thyroid and uterus were 1.88 μGy and 1.81 Gy, respectively. Also, the scan center dose in the women was 5.70 Gy. There was correlation between the thyroid and uterus surface doses, and the scan center dose. Conclusion : We concluded that the effective dose to the patient's critical organs during dual X-ray absorptiometry can be estimated by the correlation derived from phantom dosimetry

Some aspects of dose evaluation, 3

International Nuclear Information System (INIS)

Yoshida, Yoshikazu

1979-01-01

This paper describes methods of calculating the radioiodine releases and resultant doses in the ''Guide for calculation of doses to man from routine releases of effluents from light-water-cooled nuclear power plants for evaluating compliance with dose objectives around a site of LWRs'' by the Japan Nuclear Safety Commission. Examples of dose calculation in the design stage of plants and releases of radioiodine from operating plants are also given. The thyroid dose objective from radioiodine in reactor effluents was determined to be 15 mrem per year by the AEC of Japan in 1975. In the guide, models and parameters are given as most realistic on the basis of current knowledge and experience; in cases involving unknown factors these are on conservative side. Calculations of annual average releases of gaseous and liquid effluents are made using the models and parameters established through operational experiences of the LWR plants. Annual thyroid doses are calculated from inhalation and ingestion of leafy vegetable and cow's milk for gaseous effluents and ingestion of marine food for liquid effluents. In calculation of the thyroid dose, fw = 0.2 is used instead of = 0.3 in ICRP publ. 2 for ingestion of foods excluding seaweed and the specific activity method for ingestion of foods including seaweed. It is because Japanese take foods with much stable iodine. Calculated annual releases of 131 I in gaseous effluents of typical BWR (1100 MWe) and PWR (800 MWe) are about 2 Ci and 0.7 Ci per year per plant and the annual thyroid doses are about 4 mrem and 9 mrem per year, respectively. Actually, however, releases of 131 I in gaseous effluents from the operating LWR plants are about less than one tenth of the above figures. (author)

Agricultural measures to reduce radiation doses to man caused by severe nuclear accidents

International Nuclear Information System (INIS)

Dorp, F. van; Eleveld, R.; Frissel, M.J.

1981-01-01

Agricultural land and products may become contaminated after a severe nuclear accident. If radiation doses to man caused by the ingestion of contaminated agricultural products from such areas will be unacceptably high, measures to reduce this radiation dose will have to be taken. Radiation doses to man can be estimated by using models which describe quantitatively the transfer of radionuclides through the biosphere. The following processes and pathways are described in this study: accidental releases into atmospheric environments and subsequent nearby deposition; contamination of crops by direct deposition and the subsequent short term pathway (e.g. grass-cow-milk-man); contamination of soil and the subsequent long term pathway (e.g. soil-crop-man, soil-grass-cattle-milk/meat-man). Depending on the degree of contamination and on the estimated radiation doses to man, various measures are advised. (Auth.)

Aging of microplastics promotes their ingestion by marine zooplankton.

Science.gov (United States)

Vroom, Renske J E; Koelmans, Albert A; Besseling, Ellen; Halsband, Claudia

2017-12-01

Microplastics (microplastics to test their impacts, while aging processes such as weathering and biofouling alter the characteristics of plastic particles in the marine environment. We investigated zooplankton ingestion of polystyrene beads (15 and 30 μm) and fragments (≤30 μm), and tested the hypothesis that microplastics previously exposed to marine conditions (aged) are ingested at higher rates than pristine microplastics. Polystyrene beads were aged by soaking in natural local seawater for three weeks. Three zooplankton taxa ingested microplastics, excluding the copepod Pseudocalanus spp., but the proportions of individuals ingesting plastic and the number of particles ingested were taxon and life stage specific and dependent on plastic size. All stages of Calanus finmarchicus ingested polystyrene fragments. Aged microbeads were preferred over pristine ones by females of Acartia longiremis as well as juvenile copepodites CV and adults of Calanus finmarchicus. The preference for aged microplastics may be attributed to the formation of a biofilm. Such a coating, made up of natural microbes, may contain similar prey as the copepods feed on in the water column and secrete chemical exudates that aid chemodetection and thus increase the attractiveness of the particles as food items. Much of the ingested plastic was, however, egested within a short time period (2-4 h) and the survival of adult Calanus females was not affected in an 11-day exposure. Negative effects of microplastics ingestion were thus limited. Our findings emphasize, however, that aging plays an important role in the transformation of microplastics at sea and ingestion by grazers, and should thus be considered in future microplastics ingestion studies and estimates of microplastics transfer into the marine food web. Copyright © 2017 Elsevier Ltd. All rights reserved.

Skin dose estimation due to a contamination by a radionuclide β emitter: are doses equivalent good estimator of protection quantities?

International Nuclear Information System (INIS)

Bourgois, L.

2011-01-01

When handling radioactive β emitters, measurements in terms of personal dose equivalents H p (0.07) are used to estimate the equivalent dose limit to skin or extremities given by regulations. First of all, analytical expressions for individual dose equivalents H p (0.07) and equivalent doses to the extremities H skin are given for a point source and for contamination with a radionuclide β emitter. Second of all, operational quantities and protection quantities are compared. It is shown that in this case the operational quantities significantly overstate the protection quantities. For a skin contamination the ratio between operational quantities and protection quantities is 2 for a maximum β energy of 3 MeV and 90 for a maximum β energy of 150 keV. (author)

Organ dose estimates for the Japanese atomic-bomb survivors

International Nuclear Information System (INIS)

Kerr, G.D.

1978-10-01

Recent studies concerning radiation risks to man by the Committee on Biological Effects of Ionizing Radiation of the National Academy of Sciences-National Research Council and the United Nations Scientific Committee on the Effects of Atomic Radiation have emphasized the need for estimates of dose to organs of the Japanese atomic-bomb survivors. Shielding of internal organs by the body has been investigated for fission-weapon gamma rays and neutrons, and ratios of mean absorbed dose in a number of organs to survivors' T65D assignments of tissue kerma in air are provided for adults. Ratios of mean absorbed dose to tissue kerma in air are provided also for the thyroid and active bone marrow of juveniles. These organ dose estimates for juveniles are of interest in studies of radiation risks due to an elevated incidence of leukemia and thyroid cancer in survivors exposed as children compared to survivors exposed as adults

Radiation dose estimates for carbon-11-labelled PET tracers

International Nuclear Information System (INIS)

Aart, Jasper van der; Hallett, William A.; Rabiner, Eugenii A.; Passchier, Jan; Comley, Robert A.

2012-01-01

Introduction: Carbon-11-labelled positron emission tomography (PET) tracers commonly used in biomedical research expose subjects to ionising radiation. Dosimetry is the measurement of radiation dose, but also commonly refers to the estimation of health risk associated with ionising radiation. This review describes radiation dosimetry of carbon-11-labelled molecules in the context of current PET research and the most widely used regulatory guidelines. Methods: A MEDLINE literature search returned 42 articles; 32 of these were based on human PET data dealing with radiation dosimetry of carbon-11 molecules. Radiation burden expressed as effective dose and maximum absorbed organ dose was compared between tracers. Results: All but one of the carbon-11-labelled PET tracers have an effective dose under 9 μSv/MBq, with a mean of 5.9 μSv/MBq. Data show that serial PET scans in a single subject are feasible for the majority of radiotracers. Conclusion: Although differing in approach, the two most widely used regulatory frameworks (those in the USA and the EU) do not differ substantially with regard to the maximum allowable injected activity per PET study. The predictive validity of animal dosimetry models is critically discussed in relation to human dosimetry. Finally, empirical PET data are related to human dose estimates based on homogenous distribution, generic models and maximum cumulated activities. Despite the contribution of these models to general risk estimation, human dosimetry studies are recommended where continued use of a new PET tracer is foreseen.

Studies in China on ingestion and organ content of trace elements of importance in radiological protection. Country report

International Nuclear Information System (INIS)

Wang Jixian; Zhu Hongda; Chen Rusong

2000-01-01

In order to estimate internal dose and derive annual limits of intake for radionuclides in the field of Radiation Protection, it is necessary to study the parameters of ingestion of radionuclides from diet, deposition in tissues and following metabolism of the radionuclides. But these kinds of parameters may be influenced by intake of nutrients and inorganic constituents of diets, for example, a relatively higher uptake rate and longer retention time of radioiodine in thyroid of person who's diet poor of stable iodine. So there is a need to have accurate knowledge of corresponding stable elements intake and their concentration in organs, especially for some trace elements of importance in radiological protection such as Caesium, Iodine, Strontium, Thorium and Uranium. A IAEA RCA CRP on 'Ingestion and organ content of trace elements of importance in Radiological protection' was formulated in 1995 and initiated after the first RCM CRP on the project, held in Manila, Philippine 1-4 July 1996. This is the progress report for studies in China on ingestion and organ content of trace elements of importance in radiological protection after the first RCM

Natural radioactivity in groundwater and estimates of committed effective dose due to water ingestion in the state of Chihuahua (Mexico)

International Nuclear Information System (INIS)

Villalba, L.; Montero-Cabrera, M. E.; Manjon-Collado, G.; Colmenero-Sujo, L.; Renteria-Villalobos, M.; Cano-Jimenez, A.; Rodriguez-Pineda, A.; Davila-Rangel, I.; Quirino-Torres, L.; Herrera-Peraza, E. F.

2006-01-01

The activity concentration of 222 Rn, 226 Ra and total uranium in groundwater samples collected from wells distributed throughout the state of Chihuahua has been measured. The values obtained of total uranium activity concentration in groundwater throughout the state run from -1 . Generally, radium activity concentration was -1 , with some exceptions; in spring water of San Diego de Alcala, in contrast, the value reached ∼5.3 Bq l -1 . Radon activity concentration obtained throughout the state was from 1.0 to 39.8 Bq l -1 . A linear correlation between uranium and radon dissolved in groundwater of individual wells was observed near Chihuahua City. Committed effective dose estimates for reference individuals were performed, with results as high as 134 μSv for infants in Aldama city. In Aldama and Chihuahua cities the average and many individual wells showed activity concentration values of uranium exceeding the Mexican norm of drinking water quality. (authors)

Effects of lifetime ingestion of 90Sr in beagle dogs

International Nuclear Information System (INIS)

Book, S.A.; Spangler, W.L.; Swartz, L.A.

1982-01-01

To investigate the effects of lifetime 90 Sr ingestion, fifteen beagle dogs were fed the equivalent of 1.3, 4.0, and 12.0 μCi 90 Sr. Exposures prior to weaning were made by maternal administration of one of the same 90 Sr levels, begining at 21 days of gestation. Median survival was 12.5 years for the 1.3 μCi/day group, 6.5 years for the 4 μCi/day group, and 5.2 years of the 12 μCi/day group, compared to unirradiated control values of 14.5 to 15 years. The normal life span of more than half of the 1.3 μCi/day group is remarkable, considering they ingested 5900 to 7500 μCi 90 Sr during their lifetimes. One of seven 1.3 μCi/day dogs died of mycloproliferative syndrome (MPS), while one of four 4 μCi/day and one of four 12 μCi/day dogs died from MPS. In addition, another 12 μCi/day dog died of osteosarcoma and two others in the same group showed skeletal changes related to 90 Sr exposure. Other deaths were as could be expected in normal canine populations. Lifetime skeletal doses, determined by periodic whole-body counting, were 1990-3750, 1880-9230, and 6360-14,680 rad for the 1.3, 4, and 12 μCi/day groups, respectively. Comparison of these values with those from the large 90 Sr toxicity study at Davis in which 90 Sr feeding ended at 18 months of age indicates similar average skeletal doses from the two types of feeding regimens. The similarity of the skeletal doses may relate to the inability of 90 Sr to be incorporated to any great extent into a mature skeleton that no longer has the high calcium turnover associated with early life. As a result, deaths from lifetime 90 Sr ingestion appeared no earlier than when 90 Sr ingestion ended in early adulthood

Estimates of effective dose in adult CT examinations

International Nuclear Information System (INIS)

Mohamed, Mustafa Awad Elhaj.

2015-12-01

The goal of study was to estimate effective dose (E) in adult CT examinations for Toshiba X64 slice using CT. Exp version 2.5 software in Sudan. Using of CT in medical diagnosis delivers radiation doses to patients that are higher than those from other radiological procedures. lack of optimized protocols could be an additional source of increased dose in developing countries. In order to achieve these objectives, data of CT-scanner has been collected from three hospitals ( ANH, ZSH and MMH). Data collected included equipment information and scan parameters for individual patients, who were used to asses. 300 adult patients underwent head, chest, abdomen-pelvis and peivis CT examinations. The CT1_w , CTD1_vol, DLP, patient effective dos and organ doses were estimated, using CT exposure parameters and CT Exp version 2.5 software. A large variation of mean effective dose and organ doses among hospitals was observed for similar CT examinations. These variations largely originated from different CT scanning protocols used in different hospitals and scan length. The mean effective dose in this study in the Brain, PNS, Chest, pulmonary, Abdomen-pelvis, Pelvis, KUB and CTU were 3.2 mSv, 2.6 mSv, 18.9 mSv 17.6 mSv 27.1 mSv, 11.2 mSv, 9.6 mSv and 23.7 mSv respectively, and organ equivalent, doses presented in this study in this study for the eye lens (for head), lungs and thymus ( for chest) , liver, kidney and small intest ( for abdomen t-pelvis), bladder, uterus and gonads ( for pelvis), were 62.9 mSv, 39.5 mSv, 34.1 mSv, 53.9 mSv, 52.6 mSv, 58.1 mSv, 37 mSv, and 34.6 mSv, respectively. These values were mostly comparable to and slightly higher than the values of effective doses reported from similar studies the United Kingdom, Tanzania, Australia, Canada and Sudan. It was concluded that patient effective dose and organ doses could be substantially minimized through careful selection of scanning parameters based on clinical indications of study, patient size, and body

Caustic Ingestions

Directory of Open Access Journals (Sweden)

M Rafeey

2014-04-01

Full Text Available Prevention has a main role in reducing the occurrence of corrosive ingestion especially in children, yet this goal is far from being reached in developing countries, where such injuries are largely unreported and their true prevalence simply cannot be extrapolated from random articles or personal experience. Because of the accidental nature of the ingestions, the case fatality rate for pediatric patients is significantly less than that of adolescents and adults.  Currently, esophagoscopy is recommended for all patients with a history of caustic substance ingestion because clinical criteria have not proved to be reliable predictors of esophageal injury. The presence or absence of three serious signs and symptoms-vomiting, drooling, and stridor—as well as the presence and location of oropharyngeal burns could be  compared with the findings on subsequent esophagoscopy. Medical or endoscopic prevention of stricture is debatable, yet esophageal stents, absorbable or not, show promising data. The purpose of this lecture is to outline the current epidemiology, mechanism of injury, clinical manifestations, management and long-term complications of caustic ingestions in pediatric patients.   Key Words: Caustic, Children, Ingestions.

Determinations of 90Sr, 137Cs, 226Ra, 228Ra, 210Pb, 210Po contents in chinese diet and estimations of internal doses due to these radionuclides

International Nuclear Information System (INIS)

Zhu Hongda; Wang Shouliang; Meng Wei; Wang Daoping; Zheng Xiujun; Liu Qingfen; Liu Peng

1993-01-01

As a part of Chinese Total Diet Survey taken place in 1990, the authors report the determined results on 90 Sr, 137 Cs, 226 Ra, 228 Ra, 210 Pb and 210 Pb and 210 Po contents in various foods of Chinese total diet. Based on obtained dietary composition and the determined contents, the Annual Intakes (AI) and Committed Dose Equivalents (CDE) for the public by ingestion were estimated. It is shown that the total CDE for 6 radionuclides is about 0.24 mSv/a. The food categories and nuclides whose relative contributions to the total are dominant were vegetables, aquatic products and cereal, and 210 Pb, 210 Po, 228 Ra, respectively. The results have updated the data from 1982 survey and have complemented important information for water consumption. The regional difference of dietary compositions and resultant internal doses are discussed as well

Time improvement of photoelectric effect calculation for absorbed dose estimation

International Nuclear Information System (INIS)

Massa, J M; Wainschenker, R S; Doorn, J H; Caselli, E E

2007-01-01

Ionizing radiation therapy is a very useful tool in cancer treatment. It is very important to determine absorbed dose in human tissue to accomplish an effective treatment. A mathematical model based on affected areas is the most suitable tool to estimate the absorbed dose. Lately, Monte Carlo based techniques have become the most reliable, but they are time expensive. Absorbed dose calculating programs using different strategies have to choose between estimation quality and calculating time. This paper describes an optimized method for the photoelectron polar angle calculation in photoelectric effect, which is significant to estimate deposited energy in human tissue. In the case studies, time cost reduction nearly reached 86%, meaning that the time needed to do the calculation is approximately 1/7 th of the non optimized approach. This has been done keeping precision invariant

Ingestion of phosphorus-32 at Massachusetts Institute of Technology, Cambridge, Massachusetts, identified on August 19, 1995

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-12-01

On Monday, October 16, 1995, the Massachussetts Institue of Technology (MIT, the licensee) notified the US Nuclear Regulatory Commission (NRC) of an incident involving ingestion of phosphorus-32 by a researcher at the MIT Center for Cancer Research. The licensee informed the NRC that a researcher had reported the incident on August 19. The licensee initially estimated the intake as 500 microcuries (19 MBq) and the dose as 4000 millirem (40 mSv) to the individual. On October 12, the licensee informed the researcher that its final intake estimate was 579 microcuries (21 MBq), just under the 600 microcuries (22 MBq) which would represent an overexposure. On October 17, the NRC established an Incident Investigation Team to investigate the case. NRC also contracted with Lawrence Livermore National Laboratory and Oak Ridge Institute for Science and Education to do independent dose assessments of the urine sample data and the whole-body data. The Team concluded that the licensee`s final intake and dose estimates were in accordance with accepted scientific references and NRC guidance. However, recognizing the uncertainties involved in the use of models to simulate human characteristics, the Team determined the intake would be better characterized as likely falling within a range of 500 to 750 microcuries (19--28 NMq). An NRC medical consultant concluded that no symptoms or acute effects should be observed from an intake of this level.

Ingestion of phosphorus-32 at Massachusetts Institute of Technology, Cambridge, Massachusetts, identified on August 19, 1995

International Nuclear Information System (INIS)

1995-12-01

On Monday, October 16, 1995, the Massachussetts Institue of Technology (MIT, the licensee) notified the US Nuclear Regulatory Commission (NRC) of an incident involving ingestion of phosphorus-32 by a researcher at the MIT Center for Cancer Research. The licensee informed the NRC that a researcher had reported the incident on August 19. The licensee initially estimated the intake as 500 microcuries (19 MBq) and the dose as 4000 millirem (40 mSv) to the individual. On October 12, the licensee informed the researcher that its final intake estimate was 579 microcuries (21 MBq), just under the 600 microcuries (22 MBq) which would represent an overexposure. On October 17, the NRC established an Incident Investigation Team to investigate the case. NRC also contracted with Lawrence Livermore National Laboratory and Oak Ridge Institute for Science and Education to do independent dose assessments of the urine sample data and the whole-body data. The Team concluded that the licensee's final intake and dose estimates were in accordance with accepted scientific references and NRC guidance. However, recognizing the uncertainties involved in the use of models to simulate human characteristics, the Team determined the intake would be better characterized as likely falling within a range of 500 to 750 microcuries (19--28 NMq). An NRC medical consultant concluded that no symptoms or acute effects should be observed from an intake of this level

Methods of estimating population exposures from Plowshare applications

Energy Technology Data Exchange (ETDEWEB)

Kaye, S V; Rohwer, P S [Health Physics Division, Oak Ridge National Laboratory, Oak Ridge, TN (United States)

1969-07-01

When estimating doses to populations it is necessary to divide the total population into groups that have parameters of similar type and magnitude in order to identify critical population groups. Age groups constitute the most basic and generally useful way of dividing the total population for estimating dose. Models for estimating dose, particularly the internal dose from inhalation and ingestion of radioactivity, should be written as a function of age. The importance of considering age-dependency is emphasized by the fact that some of the internal dose parameters change by much as a factor of ten for some radionuclides when comparing a one year old with an adult. A computer code called INREM has been written which can consider all internal dose parameters as a function of age. The major imitation in using this computer code for all radionuclides is the paucity of age-dependent input data for many radionuclides. Tritium, iodine, cesium, and strontium have been studied in detail with INREM and the results and interpretations are discussed. Another code, EXREM, computes the external dose rates and cumulative doses from both beta particles and gamma photons from submersion in a radioactive cloud, submersion in contaminated water and exposure above a contaminated land surface. This code can consider up to 25 Plowshare detonations and a variety of combinations for calculating doses and dose rates in relation to a detonation schedule. The importance of using both INREM and EXREM to estimate the total dose to a population group is stressed. (author)

Methods of estimating population exposures from Plowshare applications

International Nuclear Information System (INIS)

Kaye, S.V.; Rohwer, P.S.

1969-01-01

When estimating doses to populations it is necessary to divide the total population into groups that have parameters of similar type and magnitude in order to identify critical population groups. Age groups constitute the most basic and generally useful way of dividing the total population for estimating dose. Models for estimating dose, particularly the internal dose from inhalation and ingestion of radioactivity, should be written as a function of age. The importance of considering age-dependency is emphasized by the fact that some of the internal dose parameters change by much as a factor of ten for some radionuclides when comparing a one year old with an adult. A computer code called INREM has been written which can consider all internal dose parameters as a function of age. The major imitation in using this computer code for all radionuclides is the paucity of age-dependent input data for many radionuclides. Tritium, iodine, cesium, and strontium have been studied in detail with INREM and the results and interpretations are discussed. Another code, EXREM, computes the external dose rates and cumulative doses from both beta particles and gamma photons from submersion in a radioactive cloud, submersion in contaminated water and exposure above a contaminated land surface. This code can consider up to 25 Plowshare detonations and a variety of combinations for calculating doses and dose rates in relation to a detonation schedule. The importance of using both INREM and EXREM to estimate the total dose to a population group is stressed. (author)

Effect of Acetaminophen Ingestion on Thermoregulation of Normothermic, Non-Febrile Humans.

Directory of Open Access Journals (Sweden)

Josh eFoster

2016-03-01

Full Text Available In non-febrile mouse models, high dose acetaminophen administration causes profound hypothermia. However, this potentially hazardous side-effect has not been confirmed in non-febrile humans. Thus, we sought to ascertain whether an acute therapeutic dose (20 mg·kg lean body mass of acetaminophen would reduce non-febrile human core temperature in a sub-neutral environment. Ten apparently healthy (normal core temperature, no musculoskeletal injury, no evidence of acute illness Caucasian males participated in a preliminary study (Study one to determine plasma acetaminophen concentration following oral ingestion of 20 mg·kg lean body mass acetaminophen. Plasma samples (every 20 minutes up to 2-hours post ingestion were analysed via enzyme linked immunosorbent assay. Thirteen (eight recruited from Study one apparently healthy Caucasian males participated in Study two, and were passively exposed to 20°C, 40% r.h. for 120 minutes on two occasions in a randomised, repeated measures, crossover design. In a double blind manner, participants ingested acetaminophen (20 mg·kg lean body mass or a placebo (dextrose immediately prior to entering the environmental chamber. Rectal temperature, skin temperature, heart rate, and thermal sensation were monitored continuously and recorded every ten minutes. In Study one, the peak concentration of acetaminophen (14 ± 4 µg/ml in plasma arose between 80 and 100 minutes following oral ingestion. In Study two, acetaminophen ingestion reduced the core temperature of all participants, whereas there was no significant change in core temperature over time in the placebo trial. Mean core temperature was significantly lower in the acetaminophen trial compared with that of a placebo (p 0.05. The results indicate oral acetaminophen reduces core temperature of humans exposed to an environment beneath the thermal neutral zone. These results suggest that acetaminophen may inhibit the thermogenic mechanisms required to regulate

Uncertainty analysis in estimating Japanese ingestion of global fallout Cs-137 using health risk evaluation model

International Nuclear Information System (INIS)

Shimada, Yoko; Morisawa, Shinsuke

1998-01-01

Most of model estimation of the environmental contamination includes some uncertainty associated with the parameter uncertainty in the model. In this study, the uncertainty was analyzed in a model for evaluating the ingestion of radionuclide caused by the long-term global low-level radioactive contamination by using various uncertainty analysis methods: the percentile estimate, the robustness analysis and the fuzzy estimate. The model is mainly composed of five sub-models, which include their own uncertainty; we also analyzed the uncertainty. The major findings obtained in this study include that the possibility of the discrepancy between predicted value by the model simulation and the observed data is less than 10%; the uncertainty of the predicted value is higher before 1950 and after 1980; the uncertainty of the predicted value can be reduced by decreasing the uncertainty of some environmental parameters in the model; the reliability of the model can definitively depend on the following environmental factors: direct foliar absorption coefficient, transfer factor of radionuclide from stratosphere down to troposphere, residual rate by food processing and cooking, transfer factor of radionuclide in ocean and sedimentation in ocean. (author)

Derivation of dose conversion factors for tritium

Energy Technology Data Exchange (ETDEWEB)

Killough, G. G.

1982-03-01

For a given intake mode (ingestion, inhalation, absorption through the skin), a dose conversion factor (DCF) is the committed dose equivalent to a specified organ of an individual per unit intake of a radionuclide. One also may consider the effective dose commitment per unit intake, which is a weighted average of organ-specific DCFs, with weights proportional to risks associated with stochastic radiation-induced fatal health effects, as defined by Publication 26 of the International Commission on Radiological Protection (ICRP). This report derives and tabulates organ-specific dose conversion factors and the effective dose commitment per unit intake of tritium. These factors are based on a steady-state model of hydrogen in the tissues of ICRP's Reference Man (ICRP Publication 23) and equilibrium of specific activities between body water and other tissues. The results differ by 27 to 33% from the estimate on which ICRP Publication 30 recommendations are based. The report also examines a dynamic model of tritium retention in body water, mineral bone, and two compartments representing organically-bound hydrogen. This model is compared with data from human subjects who were observed for extended periods. The manner of combining the dose conversion factors with measured or model-predicted levels of contamination in man's exposure media (air, drinking water, soil moisture) to estimate dose rate to an individual is briefly discussed.

Derivation of dose conversion factors for tritium

International Nuclear Information System (INIS)

Killough, G.G.

1982-03-01

For a given intake mode (ingestion, inhalation, absorption through the skin), a dose conversion factor (DCF) is the committed dose equivalent to a specified organ of an individual per unit intake of a radionuclide. One also may consider the effective dose commitment per unit intake, which is a weighted average of organ-specific DCFs, with weights proportional to risks associated with stochastic radiation-induced fatal health effects, as defined by Publication 26 of the International Commission on Radiological Protection (ICRP). This report derives and tabulates organ-specific dose conversion factors and the effective dose commitment per unit intake of tritium. These factors are based on a steady-state model of hydrogen in the tissues of ICRP's Reference Man (ICRP Publication 23) and equilibrium of specific activities between body water and other tissues. The results differ by 27 to 33% from the estimate on which ICRP Publication 30 recommendations are based. The report also examines a dynamic model of tritium retention in body water, mineral bone, and two compartments representing organically-bound hydrogen. This model is compared with data from human subjects who were observed for extended periods. The manner of combining the dose conversion factors with measured or model-predicted levels of contamination in man's exposure media (air, drinking water, soil moisture) to estimate dose rate to an individual is briefly discussed

TU-H-207A-08: Estimating Radiation Dose From Low-Dose Lung Cancer Screening CT Exams Using Tube Current Modulation

International Nuclear Information System (INIS)

Hardy, A; Bostani, M; McMillan, K; Zankl, M; Cagnon, C; McNitt-Gray, M

2016-01-01

Purpose: The purpose of this work is to estimate effective and lung doses from a low-dose lung cancer screening CT protocol using Tube Current Modulation (TCM) across patient models of different sizes. Methods: Monte Carlo simulation methods were used to estimate effective and lung doses from a low-dose lung cancer screening protocol for a 64-slice CT (Sensation 64, Siemens Healthcare) that used TCM. Scanning parameters were from the AAPM protocols. Ten GSF voxelized patient models were used and had all radiosensitive organs identified to facilitate estimating both organ and effective doses. Predicted TCM schemes for each patient model were generated using a validated method wherein tissue attenuation characteristics and scanner limitations were used to determine the TCM output as a function of table position and source angle. The water equivalent diameter (WED) was determined by estimating the attenuation at the center of the scan volume for each patient model. Monte Carlo simulations were performed using the unique TCM scheme for each patient model. Lung doses were tallied and effective doses were estimated using ICRP 103 tissue weighting factors. Effective and lung dose values were normalized by scanspecific 32 cm CTDIvol values based upon the average tube current across the entire simulated scan. Absolute and normalized doses were reported as a function of WED for each patient. Results: For all ten patients modeled, the effective dose using TCM protocols was below 1.5 mSv. Smaller sized patient models experienced lower absolute doses compared to larger sized patients. Normalized effective and lung doses showed some dependence on patient size (R2 = 0.77 and 0.78, respectively). Conclusion: Effective doses for a low-dose lung screening protocol using TCM were below 1.5 mSv for all patient models used in this study. Institutional research agreement, Siemens Healthcare; Past recipient, research grant support, Siemens Healthcare; Consultant, Toshiba America Medical

TU-H-207A-08: Estimating Radiation Dose From Low-Dose Lung Cancer Screening CT Exams Using Tube Current Modulation

Energy Technology Data Exchange (ETDEWEB)

Hardy, A; Bostani, M [University of California, Los Angeles, Los Angeles, CA (United States); McMillan, K [Mayo Clinic, Rochester, MN (United States); Zankl, M [Helmholtz Zentrum Munchen, Neuherberg (Germany); Cagnon, C [UCLA Medical Center, Los Angeles, CA (United States); McNitt-Gray, M [UCLA School of Medicine, Los Angeles, CA (United States)

2016-06-15

Purpose: The purpose of this work is to estimate effective and lung doses from a low-dose lung cancer screening CT protocol using Tube Current Modulation (TCM) across patient models of different sizes. Methods: Monte Carlo simulation methods were used to estimate effective and lung doses from a low-dose lung cancer screening protocol for a 64-slice CT (Sensation 64, Siemens Healthcare) that used TCM. Scanning parameters were from the AAPM protocols. Ten GSF voxelized patient models were used and had all radiosensitive organs identified to facilitate estimating both organ and effective doses. Predicted TCM schemes for each patient model were generated using a validated method wherein tissue attenuation characteristics and scanner limitations were used to determine the TCM output as a function of table position and source angle. The water equivalent diameter (WED) was determined by estimating the attenuation at the center of the scan volume for each patient model. Monte Carlo simulations were performed using the unique TCM scheme for each patient model. Lung doses were tallied and effective doses were estimated using ICRP 103 tissue weighting factors. Effective and lung dose values were normalized by scanspecific 32 cm CTDIvol values based upon the average tube current across the entire simulated scan. Absolute and normalized doses were reported as a function of WED for each patient. Results: For all ten patients modeled, the effective dose using TCM protocols was below 1.5 mSv. Smaller sized patient models experienced lower absolute doses compared to larger sized patients. Normalized effective and lung doses showed some dependence on patient size (R2 = 0.77 and 0.78, respectively). Conclusion: Effective doses for a low-dose lung screening protocol using TCM were below 1.5 mSv for all patient models used in this study. Institutional research agreement, Siemens Healthcare; Past recipient, research grant support, Siemens Healthcare; Consultant, Toshiba America Medical

Radiation dose to technologists per nuclear medicine examination and estimation of annual dose.

Science.gov (United States)

Bayram, Tuncay; Yilmaz, A Hakan; Demir, Mustafa; Sonmez, Bircan

2011-03-01

Conventional diagnostic nuclear medicine applications have been continuously increasing in most nuclear medicine departments in Turkey, but to our knowledge no one has studied the doses to technologists who perform nuclear medicine procedures. Most nuclear medicine laboratories do not have separate control rooms for technologists, who are quite close to the patient during data acquisition. Technologists must therefore stay behind lead shields while performing their task if they are to reduce the radiation dose received. The aim of this study was to determine external radiation doses to technologists during nuclear medicine procedures with and without a lead shield. Another aim was to investigate the occupational annual external radiation doses to Turkish technologists. This study used a Geiger-Müller detector to measure dose rates to technologists at various distances from patients (0.25, 0.50, 1, and 2 m and behind a lead shield) and determined the average time spent by technologists at these distances. Deep-dose equivalents to technologists were obtained. The following conventional nuclear medicine procedures were considered: thyroid scintigraphy performed using (99m)Tc pertechnetate, whole-body bone scanning performed using (99m)Tc-methylene diphosphonate, myocardial perfusion scanning performed using (99m)Tc-methoxyisobutyl isonitrile, and (201)Tl (thallous chloride) and renal scanning performed using (99m)Tc-dimercaptosuccinic acid. The measured deep-dose equivalent to technologists per procedure was within the range of 0.13 ± 0.05 to 0.43 ± 0.17 μSv using a lead shield and 0.21 ± 0.07 to 1.01 ± 0.46 μSv without a lead shield. Also, the annual individual dose to a technologist performing only a particular scintigraphic procedure throughout a year was estimated. For a total of 95 clinical cases (71 patients), effective external radiation doses to technologists were found to be within the permissible levels. This study showed that a 2-mm lead shield

Suicide attempt using pure methanol with hospitalization of the patient soon after ingestion: case report

Directory of Open Access Journals (Sweden)

Fábio Bucaretchi

Full Text Available CONTEXT: Most patients with methanol poisoning typically show up one to several days after ingestion, presenting severe acidosis, visual disorders, or both. Reports of hospitalization less than 6 h after exposure are unusual. We describe a case of attempted suicide using methanol admitted 3 h after ingestion. CASE REPORT: A 52-year-old male was hospitalized 3 h after intentional ingestion of 150 ml of 99.9% methanol with no co-ingestion of ethanol. He was alert and cooperative, presenting nausea and vertigo, and reporting six episodes of vomiting. Physical examination showed no remarkable features. A blood sample for methanol and ethanol determination was obtained 4 h after ingestion. The result (available 10 h after ingestion showed 70 mg/dl of methanol, without detectable ethanol. He was treated with a loading dose of 10% ethanol solution (7 ml/kg, intravenously, followed by a maintenance dose of 0.9-1.0 ml/kg/h intravenously (10 to 51 h; hemodialysis (19 to 27 h, together with 2.1 ml/kg/h of 10% ethanol intravenously; and folinic acid intravenously (50 mg every 6 h, from 4 to 51 h. He developed mild/moderate metabolic acidosis without acidemia and was discharged on day four after ophthalmological evaluation and cerebral computed tomography scan, without abnormalities. Follow-up revealed no sequelae. CONCLUSION: This could be classified as a potentially severe case of methanol poisoning, according to the amount and concentration of methanol ingested, and blood methanol concentration at 4 h. The good outcome was attributable to early hospitalization and early antidotal therapy with hemodialysis, starting at 10 and 19 h, respectively.

Estimation of population doses from diagnostic medical examinations in Japan, 1974. IV. Dose estimation of fetus exposed in utero to diagnostic x rays

Energy Technology Data Exchange (ETDEWEB)

Hashizume, T; Maruyama, T; Kumamoto, Y [National Inst. of Radiological Sciences, Chiba (Japan)

1976-07-01

In fetus exposed in utero to diagnostic x rays for the medical examinations of the mother, the absorbed dose has been estimated on the basis of a 1974 nation wide radiological survey. The results of the survey showed that the number of radiographs per year connected with pregnant women was 0.32 million for chest examination excluding mass surveys. 0.29 million for obstetrical examinations including pelvimetry, and 0.21 million for abdominal and pelvic examinations with a total of 0.82 million. The dose absorbed in the fetus was measured with an ionization chamber placed at the hypothetical center of the fetus in an ''average woman'' Rando phantom in which a maternal body was simulated by adding MixDp materials. ''The collective dose'' to the fetus in the pregnant women receiving a given type of examination was calculated from the number of radiographs per year connected with the pregnant women and the fetal doses. The percapita mean marrow dose (CMD), the leukemia significant dose (LSD) and the genetically significant dose (GSD) for the fetus were determined from the collective dose, taking into account the birth expectancy, the child expectancy, life expectancy and significant factor for the fetus. The collective dose to the fetus was estimated to be 9.3 x 10/sup 4/ man rad per year. The resultant values of CMD, LSD and GSD were 0.81 mrad per year, 0.79 mrad per person per year and 1.44 mrad per person per year, respectively.

Estimation of the total absorbed dose by quartz in retrospective conditions

International Nuclear Information System (INIS)

Correcher, V.; Delgado, A.

2003-01-01

The estimation of the total absorbed dose is of great interest in areas affected by a radiological accident when no conventional dosimetric systems are available. This paper reports about the usual methodology employed in dose reconstruction from the thermoluminescence (TL) properties of natural quartz, extracted from selected ceramic materials (12 bricks) picked up in the Chernobyl area. It has been possible to evaluate doses under 50mGy after more than 11 years later since the radiological accident happened. The main advance of this fact is the reduction of the commonly accepted limit dose estimation more than 20 times employing luminescence methods. (Author) 11 refs

A new approach to the estimation of radiopharmaceutical radiation dose distributions

International Nuclear Information System (INIS)

Hetherington, E.L.R.; Wood, N.R.

1975-03-01

For a photon energy of 150 keV, the Monte Carlo technique of photon history simulation was used to obtain estimates of the dose distribution in a human phantom for three activity distributions relevant to diagnostic nuclear medicine. In this preliminary work, the number of photon histories considered was insufficient to produce complete dose contours and the dose distributions are presented in the form of colour-coded diagrams. The distribution obtained illustrate an important deficiency in the MIRD Schema for dose estimation. Although the Schema uses the same mathematical technique for calculating photon doses, the results are obtained as average values for the whole body and for complete organs. It is shown that the actual dose distributions, particularly those for the whole body may, differ significantly from the average value calculated using the MIRD Schema and published absorbed fractions. (author)

Fetus dose estimation in thyroid cancer post-surgical radioiodine therapy

International Nuclear Information System (INIS)

Mianji, Fereidoun A.; Karimi Diba, Jila; Babakhani, Asad

2015-01-01

Unrecognised pregnancy during radioisotope therapy of thyroid cancer results in hardly definable embryo/fetus exposures, particularly when the thyroid gland is already removed. Sources of such difficulty include uncertainty in data like pregnancy commencing time, amount and distribution of metastasized thyroid cells in body, effect of the thyroidectomy on the fetus dose coefficient etc. Despite all these uncertainties, estimation of the order of the fetus dose in most cases is enough for medical and legal decision-making purposes. A model for adapting the dose coefficients recommended by the well-known methods to the problem of fetus dose assessment in athyrotic patients is proposed. The model defines a correction factor for the problem and ensures that the fetus dose in athyrotic pregnant patients is less than the normal patients. A case of pregnant patient undergone post-surgical therapy by I-131 is then studied for quantitative comparison of the methods. The results draw a range for the fetus dose in athyrotic patients using the derived factor. This reduces the concerns on under- or over-estimation of the embryo/fetus dose and is helpful for personal and/or legal decision-making on abortion. (authors)

SU-E-T-86: A Systematic Method for GammaKnife SRS Fetal Dose Estimation

Energy Technology Data Exchange (ETDEWEB)

Geneser, S; Paulsson, A; Sneed, P; Braunstein, S; Ma, L [UCSF Comprehensive Cancer Center, San Francisco, CA (United States)

2015-06-15

Purpose: Estimating fetal dose is critical to the decision-making process when radiation treatment is indicated during pregnancy. Fetal doses less than 5cGy confer no measurable non-cancer developmental risks but can produce a threefold increase in developing childhood cancer. In this study, we estimate fetal dose for a patient receiving Gamma Knife stereotactic radiosurgery (GKSRS) treatment and develop a method to estimate dose directly from plan details. Methods: A patient underwent GKSRS on a Perfexion unit for eight brain metastases (two infratentorial and one brainstem). Dose measurements were performed using a CC13, head phantom, and solid water. Superficial doses to the thyroid, sternum, and pelvis were measured using MOSFETs during treatment. Because the fetal dose was too low to accurately measure, we obtained measurements proximally to the isocenter, fitted to an exponential function, and extrapolated dose to the fundus of the uterus, uterine midpoint, and pubic synthesis for both the preliminary and delivered plans. Results: The R-squared fit for the delivered doses was 0.995. The estimated fetal doses for the 72 minute preliminary and 138 minute delivered plans range from 0.0014 to 0.028cGy and 0.07 to 0.38cGy, respectively. MOSFET readings during treatment were just above background for the thyroid and negligible for all inferior positions. The method for estimating fetal dose from plan shot information was within 0.2cGy of the measured values at 14cm cranial to the fetal location. Conclusion: Estimated fetal doses for both the preliminary and delivered plan were well below the 5cGy recommended limit. Due to Pefexion shielding, internal dose is primarily governed by attenuation and drops off exponentially. This is the first work that reports fetal dose for a GK Perfexion unit. Although multiple lesions were treated and the duration of treatment was long, the estimated fetal dose remained very low.

SU-E-T-86: A Systematic Method for GammaKnife SRS Fetal Dose Estimation

International Nuclear Information System (INIS)

Geneser, S; Paulsson, A; Sneed, P; Braunstein, S; Ma, L

2015-01-01

Purpose: Estimating fetal dose is critical to the decision-making process when radiation treatment is indicated during pregnancy. Fetal doses less than 5cGy confer no measurable non-cancer developmental risks but can produce a threefold increase in developing childhood cancer. In this study, we estimate fetal dose for a patient receiving Gamma Knife stereotactic radiosurgery (GKSRS) treatment and develop a method to estimate dose directly from plan details. Methods: A patient underwent GKSRS on a Perfexion unit for eight brain metastases (two infratentorial and one brainstem). Dose measurements were performed using a CC13, head phantom, and solid water. Superficial doses to the thyroid, sternum, and pelvis were measured using MOSFETs during treatment. Because the fetal dose was too low to accurately measure, we obtained measurements proximally to the isocenter, fitted to an exponential function, and extrapolated dose to the fundus of the uterus, uterine midpoint, and pubic synthesis for both the preliminary and delivered plans. Results: The R-squared fit for the delivered doses was 0.995. The estimated fetal doses for the 72 minute preliminary and 138 minute delivered plans range from 0.0014 to 0.028cGy and 0.07 to 0.38cGy, respectively. MOSFET readings during treatment were just above background for the thyroid and negligible for all inferior positions. The method for estimating fetal dose from plan shot information was within 0.2cGy of the measured values at 14cm cranial to the fetal location. Conclusion: Estimated fetal doses for both the preliminary and delivered plan were well below the 5cGy recommended limit. Due to Pefexion shielding, internal dose is primarily governed by attenuation and drops off exponentially. This is the first work that reports fetal dose for a GK Perfexion unit. Although multiple lesions were treated and the duration of treatment was long, the estimated fetal dose remained very low

Aspects of pre-dose and other luminescence phenomena in quartz absorbed dose estimation

International Nuclear Information System (INIS)

Adamiec, G.

2000-01-01

The understanding of all luminescence processes occurring in quartz is of paramount importance in the further development of robust absorbed dose estimation techniques (for the purpose of dating and retrospective dosimetry). The findings presented in this thesis, aid future improvements of absorbed dose estimation techniques using quartz by presenting investigations in the following areas: 1) interpretation of measurement results, 2) numerical modelling of luminescence in quartz, 3) phenomena needing inclusion in future physical models of luminescence. In the first part, the variability of properties of single quartz grains is examined. Through empirical and theoretical considerations, investigations are made of various problems of measurements of luminescence using multi-grain aliquots, and specifically areas where the heterogeneity of the sample at the inter-grain level may be misinterpreted at the multi-grain-aliquot level. The results obtained suggest that the heterogeneity of samples is often overlooked, and that such differences can have a profound influence on the interpretation of measurement results. Discussed are the shape of TL glow curves, OSL decay curves, dose response curves (including consequences for using certain signals as proxies for others), normalisation procedures and D E estimation techniques. Further, a numerical model of luminescence is proposed, which includes multiple R-centres and is used to describe the pre-dose sensitisation in quartz. The numerical model exhibits a broad-scale behaviour observed experimentally in a sample of annealed quartz. The shapes of TAC for lower (20 Gy) and higher doses (1 kGy) and the evolution with temperature of the isothermal sensitisation curves are qualitatively matched for the empirical and numerical systems. In the third area, a preliminary investigation of the properties of the '110 deg. C peak' in the 550 nm emission band, in annealed quartz is presented. These properties are in sharp contrast with

Optimizing CT radiation dose based on patient size and image quality: the size-specific dose estimate method

Energy Technology Data Exchange (ETDEWEB)

Larson, David B. [Stanford University School of Medicine, Department of Radiology, Stanford, CA (United States)

2014-10-15

The principle of ALARA (dose as low as reasonably achievable) calls for dose optimization rather than dose reduction, per se. Optimization of CT radiation dose is accomplished by producing images of acceptable diagnostic image quality using the lowest dose method available. Because it is image quality that constrains the dose, CT dose optimization is primarily a problem of image quality rather than radiation dose. Therefore, the primary focus in CT radiation dose optimization should be on image quality. However, no reliable direct measure of image quality has been developed for routine clinical practice. Until such measures become available, size-specific dose estimates (SSDE) can be used as a reasonable image-quality estimate. The SSDE method of radiation dose optimization for CT abdomen and pelvis consists of plotting SSDE for a sample of examinations as a function of patient size, establishing an SSDE threshold curve based on radiologists' assessment of image quality, and modifying protocols to consistently produce doses that are slightly above the threshold SSDE curve. Challenges in operationalizing CT radiation dose optimization include data gathering and monitoring, managing the complexities of the numerous protocols, scanners and operators, and understanding the relationship of the automated tube current modulation (ATCM) parameters to image quality. Because CT manufacturers currently maintain their ATCM algorithms as secret for proprietary reasons, prospective modeling of SSDE for patient populations is not possible without reverse engineering the ATCM algorithm and, hence, optimization by this method requires a trial-and-error approach. (orig.)

An investigation of the ingestion exposure pathways in Hong Kong

International Nuclear Information System (INIS)

Yeung, Mankit Ray; Lui, Wai Sing

1995-01-01

An investigation of the food supply and the dietetic pattern of Hong Kong was conducted and some of the important factors affecting the ingestion exposure pathways following a severe nuclear accident were examined. It was found that the nuclide concentrations in the vegetables are very sensitive to time and substantial saving in effective dose resulted from ingesting contaminated vegetables can be achieved by appropriate imposition of restriction on the consumption of local produce. The consumption of locally grown vegetables in large quantity and the proximity of the Hong Kong vegetable farms to the Guangdong Nuclear Power Station suggests that the vegetable-human pathway is important and warrants special attention

Effect of caffeine ingestion on anaerobic capacity quantified by different methods

Science.gov (United States)

Arcoverde, Lucyana; Silveira, Rodrigo; Tomazini, Fabiano; Sansonio, André; Bertuzzi, Romulo; Andrade-Souza, Victor Amorim

2017-01-01

We investigated whether caffeine ingestion before submaximal exercise bouts would affect supramaximal oxygen demand and maximal accumulated oxygen deficit (MAOD), and if caffeine-induced improvement on the anaerobic capacity (AC) could be detected by different methods. Nine men took part in several submaximal and supramaximal exercise bouts one hour after ingesting caffeine (5 mg·kg-1) or placebo. The AC was estimated by MAOD, alternative MAOD, critical power, and gross efficiency methods. Caffeine had no effect on exercise endurance during the supramaximal bout (caffeine: 131.3 ± 21.9 and placebo: 130.8 ± 20.8 s, P = 0.80). Caffeine ingestion before submaximal trials did not affect supramaximal oxygen demand and MAOD compared to placebo (7.88 ± 1.56 L and 65.80 ± 16.06 kJ vs. 7.89 ± 1.30 L and 62.85 ± 13.67 kJ, P = 0.99). Additionally, MAOD was similar between caffeine and placebo when supramaximal oxygen demand was estimated without caffeine effects during submaximal bouts (67.02 ± 16.36 and 62.85 ± 13.67 kJ, P = 0.41) or when estimated by alternative MAOD (56.61 ± 8.49 and 56.87 ± 9.76 kJ, P = 0.91). The AC estimated by gross efficiency was also similar between caffeine and placebo (21.80 ± 3.09 and 20.94 ± 2.67 kJ, P = 0.15), but was lower in caffeine when estimated by critical power method (16.2 ± 2.6 vs. 19.3 ± 3.5 kJ, P = 0.03). In conclusion, caffeine ingestion before submaximal bouts did not affect supramaximal oxygen demand and consequently MAOD. Otherwise, caffeine seems to have no clear positive effect on AC. PMID:28617848

Limiting values of radionuclide intake and air concentration and dose conversion factors for inhalation, submersion, and ingestion: Federal guidance report No. 11

International Nuclear Information System (INIS)

Eckerman, K.F.; Wolbarst, A.B.; Richardson, A.C.B.

1988-09-01

Radiation protection programs for workers are based, in the United States, on a hierarchy of limitations stemming from Federal guidance approved by the President. This guidance, which consists of principles, policies, and numerical primary guides, is used by Federal agencies as the basis for developing and implementing their own regulatory standards. The primary guides are usually expressed in terms of limiting doses to workers. The protection of workers against taking radioactive materials into the body, however, is accomplished largely through the use of regulations based on derived guides expressed in terms of quantities or concentrations of radionuclides. The values of these derived guides are chosen so as to assure that workers in work environments that conform to them are unlikely to receive radiation doses that exceed the primary guides. The purpose of the present report is to set forth derived guides that are consistent with current Federal radiation protection guidance. They are intended to serve as the basis for regulations setting upper bounds on the inhalation and ingestion of, and submersion in, radioactive materials in the workplace. The report also includes tables of exposure-to-dose conversion factors, for general use in assessing average individual committed doses in any population that is adequately characterized by Reference Man. 38 refs

Limiting values of radionuclide intake and air concentration and dose conversion factors for inhalation, submersion, and ingestion: Federal guidance report No. 11

Energy Technology Data Exchange (ETDEWEB)

Eckerman, K.F.; Wolbarst, A.B.; Richardson, A.C.B.

1988-09-01

Radiation protection programs for workers are based, in the United States, on a hierarchy of limitations stemming from Federal guidance approved by the President. This guidance, which consists of principles, policies, and numerical primary guides, is used by Federal agencies as the basis for developing and implementing their own regulatory standards. The primary guides are usually expressed in terms of limiting doses to workers. The protection of workers against taking radioactive materials into the body, however, is accomplished largely through the use of regulations based on derived guides expressed in terms of quantities or concentrations of radionuclides. The values of these derived guides are chosen so as to assure that workers in work environments that conform to them are unlikely to receive radiation doses that exceed the primary guides. The purpose of the present report is to set forth derived guides that are consistent with current Federal radiation protection guidance. They are intended to serve as the basis for regulations setting upper bounds on the inhalation and ingestion of, and submersion in, radioactive materials in the workplace. The report also includes tables of exposure-to-dose conversion factors, for general use in assessing average individual committed doses in any population that is adequately characterized by Reference Man. 38 refs.

Possible potassium chlorate nephrotoxicity associated with chronic matchstick ingestion.

Science.gov (United States)

Thurlow, John S; Little, Dustin J; Baker, Thomas P; Yuan, Christina M

2013-06-01

We present a case of a 48-year-old active duty male soldier with a history of chronic exposure to potassium chlorate, later diagnosed with chronic interstitial nephritis. He reported regular matchstick consumption to prevent chigger (Trombicula autumnalis) bites, amounting to ∼5.8 g of potassium chlorate over 3 years. Potassium chlorate can cause anuric renal failure within days of a toxic dose. Its slow excretion and mechanism of action suggest that renal toxicity may result from lower-dose chronic exposure. This case represents possible sequelae of chronic potassium chlorate ingestion.

Possible potassium chlorate nephrotoxicity associated with chronic matchstick ingestion*

Science.gov (United States)

Thurlow, John S.; Little, Dustin J.; Baker, Thomas P.; Yuan, Christina M.

2013-01-01

We present a case of a 48-year-old active duty male soldier with a history of chronic exposure to potassium chlorate, later diagnosed with chronic interstitial nephritis. He reported regular matchstick consumption to prevent chigger (Trombicula autumnalis) bites, amounting to ∼5.8 g of potassium chlorate over 3 years. Potassium chlorate can cause anuric renal failure within days of a toxic dose. Its slow excretion and mechanism of action suggest that renal toxicity may result from lower-dose chronic exposure. This case represents possible sequelae of chronic potassium chlorate ingestion. PMID:26064493

Development of the methodology for estimation of dose from a source

International Nuclear Information System (INIS)

Golebaone, E.M.

2012-04-01

The geometry of a source plays an important role when determining which method to apply in order to accurately estimate dose from a source. If wrong source geometry is used the dose received may be underestimated or overestimated therefore this may lead to wrong decision in dealing with the exposure situation. In this project moisture density gauge was used to represent a point source in order to demonstrate the key parameters to be used when estimating dose from point source. The parameters to be considered are activity of the source, the ambient dose rate, gamma constant for the radionuclide, as well as the transport index on the package of the source. The distance from the source, and the time spent in the radiation field must be known in order to calculate the dose. (author)

Estimation of Absorbed Dose in Occlusal Radiography

International Nuclear Information System (INIS)

Yoo, Young Ah; Choi, Karp Shick; Lee, Sang Han

1990-01-01

The purpose of this study was to estimate absorbed dose of each important anatomic site of phantom (RT-210 Head and Neck Section R, Humanoid Systems Co., U.S.A.) head in occlusal radiography. X-radiation dosimetry at 12 anatomic sites in maxillary anterior topography, maxillary posterior topography, mandibular anterior cross-section, mandibular posterior cross-section, mandibular anterior topographic, mandibular posterior topographic occlusal projection was performed with calcium sulfate thermoluminescent dosimeters under 70 Kvp and 15 mA, 1/4 second (8 inch cone ) and 1 second (16 inch cone) exposure time. The results obtained were as follows: Skin surface produced highest absorbed dose ranged between 3264 mrad and 4073 mrad but there was little difference between projections. In maxillary anterior topographic occlusal radiography, eyeballs, maxillary sinuses, and pituitary gland sites produced higher absorbed doses than those of other sites. In maxillary posterior topographic occlusal radiography, exposed eyeball site and exposed maxillary sinus site produced high absorbed doses. In mandibular anterior cross-sectional occlusal radiography, all sites were produced relatively low absorbed dose except eyeball sites. In Mandibular posterior cross-sectional occlusal radiography, exposed eyeball site and exposed maxillary sinus site were produced relatively higher absorbed doses than other sites. In mandibular anterior topographic occlusal radiography, maxillary sinuses, submandibular glands, and thyroid gland sites produced high absorbed doses than other sites. In mandibular posterior topographic occlusal radiography, submandibular gland site of the exposed side produced high absorbed dose than other sites and eyeball site of the opposite side produced relatively high absorbed dose.

Calculation of radiation dose to infants from radioactive breast milk and suspensions necessary to constrain dose

International Nuclear Information System (INIS)

Cormack, J.; Shearer, J.

2000-01-01

Full text: For nuclear medicine patients who are breast feeding an infant, special radiation safety precautions may need to be taken. An estimate of the potential radiation dose to the child from ingested milk must be made, and breast-feeding may need to be suspended until levels of radioactivity in the breast-milk have fallen to acceptable levels. The risk of radiation to the child must be weighed against the benefits of breast-feeding and the possible trauma to both mother and child arising from interruption or cessation of the milk supply. In the United States, the Nuclear Regulatory Commission (NRC) has already published regulations which will necessitate an estimate of the infant's dose from breast milk to be made, in principle, for every breast-feeding patient. There is obviously, therefore, a need to provide a rapid and reliable means of estimating such doses. A spreadsheet template which automatically calculates the cumulative dose to breast feeding infants based on any multi-exponential clearance of activity from the breast milk, and any pattern of feeding, has been developed by the authors. The time (post administration) for which breast-feeding should be interrupted in order to constrain the radiation dose to a selected limit is also calculated along with the concentration of activity in breast milk at which feeding can resume. The effect of changing dose limits, feeding patterns and using individually derived breast milk clearance rates may be readily modelled using this spreadsheet template. Data has been included for many of the most commonly used radiopharmaceuticals and new data can readily be incorporated as it becomes available. Copyright (2000) The Australian and New Zealand Society of Nuclear Medicine Inc

An estimate of the doubling dose of ionizing radiation for humans

International Nuclear Information System (INIS)

Neel, J.V.

1990-01-01

All accumulated data on the children of Hiroshima and Nagasaki survivors have been analyzed employing the revised procedures for estimating gonadal radiation exposures that became effective in 1986. The basic statistical procedure employed has been to obtain a linear regression of indicator on the combined gonadal exposures of the parents. There is no statistically significant regression of indicator on dose for any of the indicators; however, it is accepted that some mutations were produced in the survivors of the bombings. The implications of the data for the genetic doubling dose of radiation for humans have been explored. The appropriate dose rate factor to be applied in extrapolating to the effect of chronic radiation is 2. This leads to a doubling dose estimate for the chronic irradiation of humans of between 3.4 and 4.5 Sv. The error is large but indeterminate, but the estimate is based on conservative assumptions. (3 tabs.)

Dose estimation by biological methods

International Nuclear Information System (INIS)

Guerrero C, C.; David C, L.; Serment G, J.; Brena V, M.

1997-01-01

The human being is exposed to strong artificial radiation sources, mainly of two forms: the first is referred to the occupationally exposed personnel (POE) and the second, to the persons that require radiological treatment. A third form less common is by accidents. In all these conditions it is very important to estimate the absorbed dose. The classical biological dosimetry is based in the dicentric analysis. The present work is part of researches to the process to validate the In situ Fluorescent hybridation (FISH) technique which allows to analyse the aberrations on the chromosomes. (Author)

RADTRAD: A simplified model for RADionuclide Transport and Removal And Dose estimation

International Nuclear Information System (INIS)

Humphreys, S.L.; Miller, L.A.; Monroe, D.K.; Heames, T.J.

1998-04-01

This report documents the RADTRAD computer code developed for the U.S. Nuclear Regulatory Commission (NRC) Office of Nuclear Reactor Regulation (NRR) to estimate transport and removal of radionuclides and dose at selected receptors. The document includes a users' guide to the code, a description of the technical basis for the code, the quality assurance and code acceptance testing documentation, and a programmers' guide. The RADTRAD code can be used to estimate the containment release using either the NRC TID-14844 or NUREG-1465 source terms and assumptions, or a user-specified table. In addition, the code can account for a reduction in the quantity of radioactive material due to containment sprays, natural deposition, filters, and other natural and engineered safety features. The RADTRAD code uses a combination of tables and/or numerical models of source term reduction phenomena to determine the time-dependent dose at user-specified locations for a given accident scenario. The code system also provides the inventory, decay chain, and dose conversion factor tables needed for the dose calculation. The RADTRAD code can be used to assess occupational radiation exposures, typically in the control room; to estimate site boundary doses; and to estimate dose attenuation due to modification of a facility or accident sequence

Estimation of Dose Received in Decommissioning of Phosphate Acid Factory-Petro Kimia Gresik

International Nuclear Information System (INIS)

Lubis, Erwansyah; Heru Umbara; Agus Gindo S

2007-01-01

The estimation of dose received in decommissioning of Phosphate Acid Factory-Petro Kimia Gresik (PAF-PKG) was carried out. The external dose estimated base on the radiation rate in each working area of zona-1, 2, 3 and 4. The internal dose estimated base on the radionuclides activity and diameter of particulate exist in each working area. The calculation of the internal dose was carried out by LUDEP 2.0 computer code. The results indicated that in the normal activity of decommissioning, the effective dose will received by the worker per year were 0.27 mSv in zona-1, 1.23 mSv in zona-2, 1.37 mSv in zona-3 and 11.85 mSv in zona-4. The internal dose received when a worse accident happens in decommissioning activity is 21.06 mSv for lung organ or 4.2 % of the dose limit for that organ. Based on the discussion above, indicated that in the decommissioning of PAF-PKG the dose received by the workers is far lower than the dose limit. (author)

Method of estimating patient skin dose from dose displayed on medical X-ray equipment with flat panel detector

International Nuclear Information System (INIS)

Fukuda, Atsushi; Koshida, Kichiro; Togashi, Atsuhiko; Matsubara, Kousuke

2004-01-01

The International Electrotechnical Commission (IEC) has stipulated that medical X-ray equipment for interventional procedures must display radiation doses such as air kerma in free air at the interventional reference point and dose area product to establish radiation safety for patients (IEC 60601-2-43). However, it is necessary to estimate entrance skin dose for the patient from air kerma for an accurate risk assessment of radiation skin injury. To estimate entrance skin dose from displayed air kerma in free air at the interventional reference point, it is necessary to consider effective energy, the ratio of the mass-energy absorption coefficient for skin and air, and the backscatter factor. In addition, since automatic exposure control is installed in medical X-ray equipment with flat panel detectors, it is necessary to know the characteristics of control to estimate exposure dose. In order to calculate entrance skin dose under various conditions, we investigated clinical parameters such as tube voltage, tube current, pulse width, additional filter, and focal spot size, as functions of patient body size. We also measured the effective energy of X-ray exposure for the patient as a function of clinical parameter settings. We found that the conversion factor from air kerma in free air to entrance skin dose is about 1.4 for protection. (author)

Estimate of dose in interventional radiology: a study of cases

International Nuclear Information System (INIS)

Pinto, N.; Braz, D.; Lopes, R.; Vallim, M.; Padilha, L.; Azevedo, F.; Barroso, R.

2006-01-01

Values of absorbed dose taken by patients and professionals involved in interventional radiology can be significant mainly for the reason of these proceedings taking long time of fluoroscopy There are many methods to estimate and reduce doses of radiation in the interventional radiology, particularly because the fluoroscopy is responsible for the high dose contribution in the patient and in the professional. The aim of this work is the thermoluminescent dosimetry to estimate the dose values of the extremities of the professionals involved in the interventional radiology and the product dose-area was investigated using a Diamentor. This evaluation is particularly useful for proceedings that interest multiple parts of the organism. In this study were used thermoluminescent dosimeters (LiF:Mg, Ti - Harshaw) to estimate the dose values of the extremities of the professionals and to calibrate them. They were irradiated with X rays at 50 mGy, in Kerma in air and read in the reader Harshaw-5500. The product dose-area (D.A.P.) were obtained through the Diamentor (M2-P.T.W.) calibrated in Cgy.cm 2 fixed in the exit of the X-rays tube. The patients of these study were divided in three groups: individuals submitted to proceedings of embolization, individuals submitted to cerebral and renal arteriography and individuals submitted to proceedings of Transjungular Inthahepatic Porta Systemic Stent Shunt (TIPS). The texts were always carried out by the same group: radiologist doctor), an auxiliary doctor and a nursing auxiliary. The section of interventional radiology has an Angiostar Plus Siemens equipment type arc C, in which there is trifocal Megalix X-ray tube and a intensifier of image from Sirecon 40-4 HDR/33 HDR. In this work the dose estimated values were 137.25 mSv/year for the doctors, 40.27 mSv/year for the nursing and 51.95 mSv/year for the auxiliary doctor and they are below the rule, but in this study it was not taken in consideration the emergency texts as they were

Cytogenetic biological dosimetry. Dose estimative in accidental exposure

International Nuclear Information System (INIS)

Santos, O.R. dos; Campos, I.M.A. de.

1988-01-01

The methodology of cytogenetic biological dosimetry is studied. The application in estimation of dose in five cases of accidental exposure is reported. An hematological study and culture of lymphocytes is presented. (M.A.C.) [pt

Estimation of the fetal dose by dose measurement during an irradiation of a parotid tumor; Estimation de la dose foetale par mesure de dose lors d'une irradiation d'une tumeur de la parotide

Energy Technology Data Exchange (ETDEWEB)

Marchesi, V.; Graff-Cailleaud, P.; Peiffert, D. [Centre Alexis-Vautrin, 54 - Vandoeuvre-les-Nancy (France); Noel, A. [Institut National Polytechnique de Lorraine, CRAN CNRS UMR-7039, 54 - Vandoeuvre-les-Nancy (France)

2006-11-15

The irradiation of a five months pregnant patient has been made for a right parotid attack. In conformation with the legislative texts relative to radiation protection ( publication 84 of the ICRP) an estimation of the dose received for the fetus has been led by dose measurement on phantom. With the dose limit ( 100 mGy) recommended in the publication 84 of the ICRP neither modification of the treatment nor abortion was necessary. (N.C.)

Foreign-body ingestion: characteristics and outcomes in a lower socioeconomic population with predominantly intentional ingestion.

Science.gov (United States)

Palta, Renee; Sahota, Amandeep; Bemarki, Ali; Salama, Paul; Simpson, Nicole; Laine, Loren

2009-03-01

Previous reports of foreign-body ingestions focused primarily on accidental ingestions. To describe the characteristics and management of foreign-body ingestions, with predominantly intentional ingestion, in a lower socioeconomic status population. A retrospective case series. An urban county hospital. Patients >/=17 years old, with foreign-body ingestions between 2000 and 2006. Characteristics of ingestion cases, endoscopic extraction, need for surgery, and complications. Among 262 cases, 92% were intentional, 85% involved psychiatric patients, and 84% occurred in patients with prior ingestions. The time from ingestion to presentation was >48 hours in 168 cases (64%). The overall success rate for endoscopic extraction was 90% (165/183 cases). Surgery was performed in 30 cases (11%) and was more common for objects beyond the pylorus versus objects above the pylorus (16/43 [37%] vs 10/151 [7%], respectively) and in cases with a greater delay from ingestion to presentation (25/168 [15%] if >48 hours vs 4/77 [5%] if 48 hours vs 14/165 [8%] if ingestions in an urban county hospital occurred primarily in psychiatric patients who had repeated episodes of intentional ingestions. Endoscopic extraction was unsuccessful in 10% of cases. Long delays from ingestion to presentation and intervention may account for relatively high rates of surgery and perforation. Strategies to prevent ingestions and delays in endoscopic management are needed in this population.

Heartburn and regurgitation in pregnancy: the effect of fat ingestion.

Science.gov (United States)

Dall'Alba, Valesca; Fornari, Fernando; Krahe, Cláudio; Callegari-Jacques, Sidia Maria; Silva de Barros, Sérgio Gabriel

2010-06-01

Reflux symptoms are common in pregnancy, but their association with fat ingestion is unclear. To investigate an association of dietary fats with heartburn and regurgitation in pregnancy. This is a prospective study in which 89 pregnant women (gestational age 34 +/- 4 weeks) attending a low-risk prenatal outpatient clinic were asked to provide information on the frequency they experienced heartburn and regurgitation. Fat ingestion was estimated by means of a 24-h diet record. Symptomatic patients were compared with those with no reflux symptoms (n = 20). Heartburn once a week or more often occurred in 56 of the 89 patients (63%). The ingested amount of polyunsaturated fatty acids was higher in patients with heartburn (11.2 +/- 6.4 vs. 7.7 +/- 3.5 mg; P = 0.022) than in controls after adjusting for age, gain weight during pregnancy, ingestion of caffeine and vitamin C, and total energetic intake. The ingestion of monounsaturated fatty acids was higher in patients with heartburn, but with a borderline statistical significance (16.1 +/- 11 vs. 11.8 +/- 6.5 mg; P = 0.061). No association was observed between the consumption of fats and regurgitation. This study suggests that heartburn in the third trimester of pregnancy is associated with the ingestion of polyunsaturated fatty acids.

Estimation of frequency, population doses and stochastic risks in brachytherapy in Japan, 1983

International Nuclear Information System (INIS)

Maruyama, Takashi; Kumamoto, Yoshikazu; Noda, Yutaka; Nishizawa, Kanae; Furuya, Yoshiro; Iwai, Kazuo.

1988-01-01

Based on the replies to a questionnaire distributed throughout Japan in 1983, genetically significant dose (GSD), per Caput mean bone marrow dose (CMD), leukemogenically significant dose (LSD), malignantly significant dose (MSD), and per Caput effective dose equivalent (EDE) from using small sealed radiation sources for radiotherapy were estimated. Annual frequencies of brachytherapy were estimated to be 2.6 x 10 3 for men and 36.3 x 10 3 for women, with a total of 38.9 x 10 3 . The annual frequencies of using afterloading technique were 0.3 x 10 3 for men and 18.8 x 10 3 for women, with a total of 19.1 x 10 3 . The annual population doses per person were 7.9 nGy for GSD, 118 μGy for CMD, 19.3 μGy for LSD, 172 μGy for MSD, and 428 μGy for EDE. The annual collective effective dose equivalent was estimated to be 5.13 x 10 4 man Sv. (Namekawa, K.)

Estimated collective effective dose to the population from nuclear medicine examinations in Slovenia

International Nuclear Information System (INIS)

Skrk, Damijan; Zontar, Dejan

2013-01-01

A national survey of patient exposure from nuclear medicine diagnostic procedures was performed by Slovenian Radiation Protection Administration in order to estimate their contribution to the collective effective dose to the population of Slovenia. A set of 36 examinations with the highest contributions to the collective effective dose was identified. Data about frequencies and average administered activities of radioisotopes used for those examinations were collected from all nuclear medicine departments in Slovenia. A collective effective dose to the population and an effective dose per capita were estimated from the collected data using dose conversion factors. The total collective effective dose to the population from nuclear medicine diagnostic procedures in 2011 was estimated to 102 manSv, giving an effective dose per capita of 0.05 mSv. The comparison of results of this study with studies performed in other countries indicates that the nuclear medicine providers in Slovenia are well aware of the importance of patient protection measures and of optimisation of procedures

Necessary accuracy of dose estimation during cohort epidemiologic study after irradiation

International Nuclear Information System (INIS)

Orlov, M.Yu.; Stepanenko, V.F.; Khoshi, M.; Takada, Dzh.

2003-01-01

Effect of breadth of dose ranges on values of radiation risk was estimated. Ratios of observed numbers of mortalities because of leukemia in the cohort in 1950 - 1974 under deferent radiation dose to expected number of mortalities in this cohort only under background radiation were used as degree of risk. Data of cooperative Japan-American Program LSS (Life Span Study) were applied in the researches. It is established that required for the risk assessment with uncertainty 20 - 30 % the accuracy of dose estimation comprises 30 - 35 % in the range 1 - 5 rad and 5 - 10 % in the range 5 - 30 rad [ru

System for estimation of mean active bone marrow dose

International Nuclear Information System (INIS)

Ellis, R.E.; Healy, M.J.R.; Shleien, B.; Tucker, T.

1975-09-01

The exposure measurements, model and computer program for estimation of mean active bone marrow doses formerly employed in the 1962 British Survey of x-ray doses and proposed for application to x-ray exposure information obtained in the U.S. Public Health Service's X-Ray Exposure Studies (1966 and 1973) are described and evaluated. The method described is feasible for use to determine the mean active bone marrow doses to adults for examinations having a skin to source distance of 80 cm or less. For a greater SSD, as for example in chest x rays, a small correction in the calculation dose can be made

ESTIMATION OF THE CONVERSION COEFFICIENTS FROM DOSE-AREA PRODUCT TO EFFECTIVE DOSE FOR BARIUM MEAL EXAMINATIONS FOR ADULT PATIENTS

Directory of Open Access Journals (Sweden)

A. V. Vodovatov

2018-01-01

Full Text Available Fluoroscopic examinations of the upper gastro-intestinal tract and, especially, barium meal examinations, are commonly performed in a majority of hospitals. These examinations are associated both with substantial individual patient doses and contribution to the collective dose from medical exposure. Effective dose estimation for this type of examinations is complicated due to: 1 the necessity to simulate the moving X-ray irradiation field; 2 differences in study structure for the individual patients; 3 subjectivity of the operators; and 4 differences in the X-ray equipment. The aim of the current study was to estimate conversion coefficients from dose-area product to effective dose for barium meal examinations for the over couch and under couch exposure conditions. The study was based on data collected in the X-ray unit of the surgical department of the St-Petersburg Mariinsky hospital. A model of patient exposure during barium meal examination was developed based on the collected data on fluoroscopy protocols and adult patient irradiation geometry. Conversion coefficients were calculated using PCXMC 2.0 software. Complete examinations were converted into a set of typical fluoroscopy phases and X-ray images, specified by the examined anatomical region and the projection of patient exposure. Conversion coefficients from dose-area product to effective dose were calculated for each phase of the examination and for the complete examination. The resulting values of the conversion coefficients are comparable with published data. Variations in the absolute values of the conversion coefficients can be explained by differences in clinical protocols, models for the estimation of the effective dose and parameters of barium meal examinations. The proposed approach for estimation of effective dose considers such important features of fluoroscopic examinations as: 1 non-uniform structure of examination, 2 significant movement of the X-ray tube within a single

Studies of osmotic diarrhea induced in normal subjects by ingestion of polyethylene glycol and lactulose.

Science.gov (United States)

Hammer, H F; Santa Ana, C A; Schiller, L R; Fordtran, J S

1989-10-01

The purpose of these studies was to gain insight into the pathophysiology of pure osmotic diarrhea and the osmotic diarrhea caused by carbohydrate malabsorption. Diarrhea was induced in normal volunteers by ingestion of polyethylene glycol (PEG), which is nonabsorbable, not metabolized by colonic bacteria, and carries no electrical charge. In PEG-induced diarrhea, (a) stool weight was directly correlated with the total mass of PEG ingested; (b) PEG contributed 40-60% of the osmolality of the fecal fluid, the remainder being contributed by other solutes either of dietary, endogenous, or bacterial origin; and (c) fecal sodium, potassium, and chloride were avidly conserved by the intestine, in spite of stool water losses exceeding 1,200 g/d. Diarrhea was also induced in normal subjects by ingestion of lactulose, a disaccharide that is not absorbed by the small intestine but is metabolized by colonic bacteria. In lactulose-induced diarrhea, (a) a maximum of approximate 80 g/d of lactulose was metabolized by colonic bacteria to noncarbohydrate moieties such as organic acids; (b) the organic acids were partially absorbed in the colon; (c) unabsorbed organic acids obligated the accumulation of inorganic cations (Na greater than Ca greater than K greater than Mg) in the diarrheal fluid; (d) diarrhea associated with low doses of lactulose was mainly due to unabsorbed organic acids and associated cations, whereas with larger doses of lactulose unmetabolized carbohydrates also played a major role; and (e) the net effect of bacterial metabolism of lactulose and partial absorption of organic acids on stool water output was done dependent. With low or moderate doses of lactulose, stool water losses were reduced by as much as 600 g/d (compared with equimolar osmotic loads of PEG); with large dose, the increment in osmotically active solutes within the lumen exceeded the increment of the ingested osmotic load, and the severity of diarrhea was augmented.

Estimating adolescent sleep need using dose-response modeling.

Science.gov (United States)

Short, Michelle A; Weber, Nathan; Reynolds, Chelsea; Coussens, Scott; Carskadon, Mary A

2018-04-01

This study will (1) estimate the nightly sleep need of human adolescents, (2) determine the time course and severity of sleep-related deficits when sleep is reduced below this optimal quantity, and (3) determine whether sleep restriction perturbs the circadian system as well as the sleep homeostat. Thirty-four adolescents aged 15 to 17 years spent 10 days and nine nights in the sleep laboratory. Between two baseline nights and two recovery nights with 10 hours' time in bed (TIB) per night, participants experienced either severe sleep restriction (5-hour TIB), moderate sleep restriction (7.5-hour TIB), or no sleep restriction (10-hour TIB) for five nights. A 10-minute psychomotor vigilance task (PVT; lapse = response after 500 ms) and the Karolinska Sleepiness Scale were administered every 3 hours during wake. Salivary dim-light melatonin onset was calculated at baseline and after four nights of each sleep dose to estimate circadian phase. Dose-dependent deficits to sleep duration, circadian phase timing, lapses of attention, and subjective sleepiness occurred. Less TIB resulted in less sleep, more lapses of attention, greater subjective sleepiness, and larger circadian phase delays. Sleep need estimated from 10-hour TIB sleep opportunities was approximately 9 hours, while modeling PVT lapse data suggested that 9.35 hours of sleep is needed to maintain optimal sustained attention performance. Sleep restriction perturbs homeostatic and circadian systems, leading to dose-dependent deficits to sustained attention and sleepiness. Adolescents require more sleep for optimal functioning than typically obtained.

Maxine: A spreadsheet for estimating dose from chronic atmospheric radioactive releases

Energy Technology Data Exchange (ETDEWEB)

Jannik, Tim [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Bell, Evaleigh [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Dixon, Kenneth [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

2017-07-24

MAXINE is an EXCEL© spreadsheet, which is used to estimate dose to individuals for routine and accidental atmospheric releases of radioactive materials. MAXINE does not contain an atmospheric dispersion model, but rather doses are estimated using air and ground concentrations as input. Minimal input is required to run the program and site specific parameters are used when possible. Complete code description, verification of models, and user’s manual have been included.

Population dose estimation from a hypothetical release of 2.4 x 106 curies of noble gases and 1 x 104 curies of 131I at the Three Mile Island Nuclear Station, Unit 2

International Nuclear Information System (INIS)

Berger, C.D.; Lane, B.H.; Cotter, S.J.; Miller, C.W.; Glandon, S.R.

1981-09-01

Beginning on March 28, 1979, a sequence of events occurred at the Three Mile Island Nuclear Station Unit 2 (TMINS-2) nuclear power reactor which resulted in the accidental release of approximately 2.4 x 10 6 Ci of noble gases and 13 to 15 Ci 131 I. A comprehensive study of this incident has been reported by the President's Commission on the Accident at Three Mile Island. As part of this study, the Technical Assessment Task Group for the Commission addressed a series of alternative event scenarios, including the potential for a higher release of 131 I. As a continuation of this task, this report presents the estimated collective dose to the population within 50 miles of TMINS-2 from a hypothetical release of 2.4 x 10 6 Ci of noble gases and 1 x 10 4 Ci 131 I by the methodology of atmospheric dispersion modeling and population dose estimation through the inhalation, ingestion and immersion exposure pathways

Evaluation of a Commercially Available Euthanasia Solution as a Voluntarily Ingested Euthanasia Agent in Laboratory Mice.

Science.gov (United States)

Dudley, Emily S; Boivin, Gregory P

2018-01-01

All currently accepted methods of euthanasia for laboratory mice involve some degree of stress, fear, anxiety, or pain. We evaluated the voluntary oral administration of a euthanasia drug in 99 male and 81 female mice of various strains. We first explored the palatability of sugar-cookie dough with various flavorings added. We placed the cookie dough in the cage with an adult mouse and recorded the amount ingested after 1 h. Mice readily ingested all flavors of sugar-cookie dough. We then added a euthanasia solution containing pentobarbital and phenytoin to all flavors of cookie dough and placed a small bolus in the cage of each mouse or mouse pair. We observed the mice for 1 h for clinical signs of pentobarbital intoxication and then weighed uneaten dough to determine the dose of pentobarbital ingested. Palatability declined sharply when euthanasia solution was present. Mice ingested higher doses of pentobarbital in cookie dough during the dark phase and after fasting. Ingestion caused ataxia in some mice but was not sufficient to cause loss of righting reflex, unconsciousness, or death in any mouse. We successfully identified sugar cookie dough as a drug vehicle that was readily and rapidly eaten by mice without the need for previous exposure. Additional research is needed to identify euthanasia compounds for mice that do not affect the palatability of cookie dough.

Radioactivity of flour, wheat, bread improvers and dose estimates in Sudan

International Nuclear Information System (INIS)

Hamdan, Adam Mahana

2015-10-01

The steady rise in the use of isotopes and nuclear technology in various purposes in human life, both agro-industrial military, medical, may increase the chances of radioactive contamination that increases the exposure of ionizing radiation which raise awareness in increasing the need to know how to assess that exposure. Control of imported foodstuffs to ensure that not contaminated with radioactive materials is very important at this stage. The present study aims to investigating radioactivity in foodstuff consumed in Sudan to measure radionuclide in wheat flour, bread improvers specific objectives to measure radioactive contaminants and to estimate radiation dose from this consumption. The health impact of radionuclide ingestion from foodstuffs was evaluated by the committed effective doses determined in 30 samples of foodstuff. collected in the Port Sudan on the red sea, the radioactivity tracer of K-40, U-238 and Th-232 were measured by gamma ray spectrometry employing an using Nal (Ti) calibration process carried out for gamma spectrometry using MW652 as a reference source which recommended by International Atomic Energy Agency (IAEA) including source Cs-137 and Co-60 with two energy levels. The K-40 activity concentration in the flour samples, rang (303.07-40.48) (Bq/kg), 238U (4.81-1.95) (Bq/kg), Th-232 (7.60-1.61) Bq/kg) wheat samples range k-40 (250.62-27.22) (Bq/kg), U-238 (4.92-190) (Bq/kg), Th-232 (5.74-1.61) (Bq/kg) and bread improvers samples k-40 (68.60-13.61 (Bq/kg) U-238 (5.73-194) (Bq/kg). The total average effective dose for age (>17 years) was found in to flour be 2.35±7.12 mSv/y, 1.15±0.95 mSv/y, 1.65±2.02 mSv/y, the maximum dose values obtained were 6.01 mSv/y, 1.95 mSv/y, 1.57 mSv/y. The total average effective dose for age (>17 years) was found in to wheat 1.58±6.85 mSv/y 1.16±1.33 mSv/y, 0.48±1.14 mSv/y, the maximum dose values obtained were 4.14 mSv/y, 1.66 mSv/y, 0.99 mSv/y. The total average effective dose for age (>17 years) was

Fetal doses from plutonium-239 and polonium-210

International Nuclear Information System (INIS)

Harrison, J.D.; Morgan, A.; Stather, J.W.

1992-01-01

The transfer of 239 Pu and 210 Po from the maternal circulation to the developing embryo and fetus was studied in rodents. The highest concentrations of both isotopes were measured in the yolk sac. In utero doses to haemopoietic tissue have been calculated taking account of transfer to the blastocyst/egg cylinder, yolk sac, liver and bone marrow. From animal data, the concentration ratios relative to maternal liver for these tissues were taken to be 0.1, 2, 0.01 and o.02, respectively for 239 Pu; and 1, 2, 0.1 and 0.1, respectively, for 210 Po. These concentration ratios were applied to periods of human gestation of 0-2.5 weeks, 2.5-6 weeks, 6-12 weeks and 12-38 weeks, and used to calculate fetal tissue doses for chronic maternal intake by ingestion of 1 kBq 239 Pu or 2 kBq 210 Po in the year of pregnancy (1 ALI for a member of the public). On this basis, the total in utero dose to haemopoietic tissue was about 1 μSv from 239 Pu and 60 μSv from 210 Po compared with red bone marrow doses to the mother in the year of 19 μSv from 239 Pu and 160 μSv from 210 Po. The yolk sac and bone marrow dominated in utero doses from both nuclides. For 239 Pu, because of its long half life, an important consideration was activity present in the offspring at birth and committed dose equivalents to red bone marrow in the child and mother. The total dose to haemopoietic tissue in the offspring to age 70 years, including in utero doses, was calculated as 13 μSv compared with a maternal dose to red bone marrow of 1400 μSv. For both isotopes the risk of leukaemia in the year of pregnancy was estimated to be of the same order for mother and fetus. For 239 Pu, the overall risk to 70 years of age was two orders of magnitude higher for the mother than her offspring. For 239 Pu, an acute intake of 1 kBq by ingestion during the period of yolk sac haemopoiesis would result in the highest in utero dose, estimated at about 20 μSv. However, activity at birth would be lower and the overall

Determination of the equivalent doses due to the ingestion of radionuclides from the uranium and thorium series presents in drinking waters of the region of Santa Luzia, Paraiba state, Brazil; Determinacao das doses equivalentes devido a ingestao de radionuclideos das series do uranio e torio presentes em aguas de consumo do municipio de Santa Luzia, estado da Paraiba

Energy Technology Data Exchange (ETDEWEB)

Pastura, Valeria F. da S., E-mail: vpastura@cnen.gov.b [Comissao Nacional de Energia Nuclear (DRSN/CNEN), Rio de Janeiro, RJ (Brazil). Diretoria de Radioprotecao e Seguranca Nuclear. Coordenacao de Materias Primas e Minerais; Campos, Thomas F. da C.; Petta, Reinaldo A., E-mail: thomascampos@geologia.ufrn.b, E-mail: petta@geologia.ufrn.b [Universidade Federal do Rio Grande do Norte (LARANA/UFRN), Natal, RN (Brazil). Lab. de Radioatividade Natural

2011-10-26

This paper determined the original dose equivalents from radionuclides of uranium and thorium series in a drinking water of well which is supplied to the population of Santa Luzia, Paraiba state, Brazil. The collected waters are near to the mineralized phlegmatic bodies in rose quartz and amazonite feldspar. Radiometric measurements performed on the feldspar vein point out counting ratios surrounding 30000 cps and the analysis of collected samples of minerals presented tenors for the {sup 226}Ra and {sup 219}Pb varying from 0.50 to 2.30 Bq/sw. For determination of concentration of radionuclides U{sub Total}, {sup 226}Ra, {sup 228}Ra and {sup 219}Pb, found in the not desalinated, two methods were used, spectrophotometry with arsenazo and radiochemistry, both realized in the CNEN-LAPOC laboratories. For the calculation of dose equivalent it was taken into consideration the following parameters: the dose coefficients for incorporation by ingestion for public individuals with ages over 17 years (Norma CNEN-NN-3.01, Regulatory Position 3.01/011) and daily ingestion of 4 liters of water, which is over the recommended by the WHO of 2L/day - 1993. The obtained values were compared with the reference value for compromised dose equivalent established by WHO for evaluate the risk potential to the health of population, by ingestion. The radionuclide concentrations in the wells varies from 0.054 to 0.21 Bq/L, resulting dose equivalents of 3.94 x 10{sup -3} mSv/year and 0.17 mSv/year in the studied population

Estimation of organ and effective dose due to Compton backscatter security scans

International Nuclear Information System (INIS)

Hoppe, Michael E.; Schmidt, Taly Gilat

2012-01-01

Purpose: To estimate organ and effective radiation doses due to backscatter security scanners using Monte Carlo simulations and a voxelized phantom set. Methods: Voxelized phantoms of male and female adults and children were used with the GEANT4 toolkit to simulate a backscatter security scan. The backscatter system was modeled based on specifications available in the literature. The simulations modeled a 50 kVp spectrum with 1.0 mm-aluminum-equivalent filtration and a previously measured exposure of approximately 4.6 μR at 30 cm from the source. Photons and secondary interactions were tracked from the source until they reached zero kinetic energy or exited from the simulation’s boundaries. The energy deposited in the phantoms’ respective organs was tallied and used to calculate total organ dose and total effective dose for frontal, rear, and full scans with subjects located 30 and 75 cm from the source. Results: For a full screen, all phantoms’ total effective doses were below the established 0.25 μSv standard, with an estimated maximum total effective dose of 0.07 μSv for full screen of a male child. The estimated maximum organ dose due to a full screen was 1.03 μGy, deposited in the adipose tissue of the male child phantom when located 30 cm from the source. All organ dose estimates had a coefficient of variation of less than 3% for a frontal scan and less than 11% for a rear scan. Conclusions: Backscatter security scanners deposit dose in organs beyond the skin. The effective dose is below recommended standards set by the Health Physics Society (HPS) and the American National Standards Institute (ANSI) assuming the system provides a maximum exposure of approximately 4.6 μR at 30 cm.

Phantom measurements and computed estimates of breast dose with radiotherapy for Hodgkin's lymphoma: dose reduction with the use of the involved field

International Nuclear Information System (INIS)

Wirth, A.; Kron, T.; Sorell, G.; Cramb, J.; Wittwer, H.; Sullivan, K.

2008-01-01

Full text: The risk of breast cancer following radiotherapy for Hodgkin's lymphoma appears to be dose related. In this study we compared breast dose in an anthropomorphic phantom for conventional 'mantle'; upper mediastinal/bilateral neck (minimantle) and unilateral neck fields, and evaluated the accuracy of computer planned dose estimates for out-of-field doses. For each field, computer-planned breast dose (CPD) estimates were compared with thermolu-minescence dosimetry measurements in five locations within 'breast tissue'. CPD were also compared with ion chamber measurements in a slab phantom. Measured dose and CPD were within 20% of each other up to approximately 10 cm from the field edge. Beyond 10 cm, the CPD underestimated dose by a factor of 2 or more. The minimantle reduced the breast dose by a factor of approximately 10 compared with the mantle treatment. Treating the neck field lowered the breast dose by a further 50% or more. Modern involved-field radiotherapy for lymphoma substantially reduces breast dose compared with mantle fields. Computer dosimetery underestimated dose at larger distances from the field. This needs to be considered if computer dosimetery is used to estimate breast dose and, by extrapolation, breast cancer risk.

Dose-response curve estimation: a semiparametric mixture approach.

Science.gov (United States)

Yuan, Ying; Yin, Guosheng

2011-12-01

In the estimation of a dose-response curve, parametric models are straightforward and efficient but subject to model misspecifications; nonparametric methods are robust but less efficient. As a compromise, we propose a semiparametric approach that combines the advantages of parametric and nonparametric curve estimates. In a mixture form, our estimator takes a weighted average of the parametric and nonparametric curve estimates, in which a higher weight is assigned to the estimate with a better model fit. When the parametric model assumption holds, the semiparametric curve estimate converges to the parametric estimate and thus achieves high efficiency; when the parametric model is misspecified, the semiparametric estimate converges to the nonparametric estimate and remains consistent. We also consider an adaptive weighting scheme to allow the weight to vary according to the local fit of the models. We conduct extensive simulation studies to investigate the performance of the proposed methods and illustrate them with two real examples. © 2011, The International Biometric Society.

A study on pre-heat conditions in equivalent-dose estimation of holocene loess using single-aliquot regenerative-dose (SAR) protocol

International Nuclear Information System (INIS)

Jia Yaofeng; Huang Chunchang; Pang Jiangli; Lu Xinwei; Zhang Xu

2007-01-01

Through various arrangements of pre-heat and cut-heat temperatures in the equivalent-dose estimation of Holocene loess using a Double-SAR dating protocol, the paper estimated the equivalent-doses from several loess samples by application of IRSL and Post-IR OSL signals, respectively. The measured results present that the equivalent-dose depends on the heat temperature, especially depends on the cut-heat temperature, showing the equivalent-dose increases with the cut-heat temperature; a plateau of equivalent-dose appears at the 200-300 degree C preheat temperatures and the 200-240 degree C cut-heat temperatures, furthermore, the equivalent-doses estimated by IRSL and Post-IR OSL signals respectively are close to each other, which resulted from the similar sensitivity change directions of optical stimulated signals and their smaller change ranges in the measurement cycles using the various temperatures of pre-heat and cut-heat. This suggests that the 200-300 degree C pre-heat temperatures and the 200-240 degree C cut-heat temperatures are fit for dating young Holocene loess samples. (authors)

Dose assessment for decontamination in Goiania

International Nuclear Information System (INIS)

Amaral, E.C.S.

2000-01-01

Shortly after the accident at Goiania, the need arose to set derived intervention levels for the various exposure pathways to guide and optimise clean up measures. For the members of the critical group an intervention level of 5 mSv for the total effective dose in the first year after the accident was chosen, which then was subdivided into values of 1 mSv due to the contribution of external irradiation indoors, 3 mSv from external irradiation while being outdoors, and 1 mSv due to incorporation of resuspended particles and ingestion of locally produced food. The clean up indoors could be directed such that a pre-described ambient dose rate was no longer exceeded. These exposure levels and effective doses to the critical groups predicted in 1988 are compared to actual measurements made in 1988 to 1993 in a local house near one primary contamination foci, and best estimate. It can be shown that the actual doses received by members of the public living in the affected areas were significantly lower. The various reasons for this overprediction will be discussed. (author)

A PC program for estimating organ dose and effective dose values in computed tomography

International Nuclear Information System (INIS)

Kalender, W.A.; Schmidt, B.; Schmidt, M.; Zankl, M.

1999-01-01

Dose values in CT are specified by the manufacturers for all CT systems and operating conditions in phantoms. It is not trivial, however, to derive dose values in patients from this information. Therefore, we have developed a PC-based program which calculates organ dose and effective dose values for arbitrary scan parameters and anatomical ranges. Values for primary radiation are derived from measurements or manufacturer specifications; values for scattered radiation are derived from Monte Carlo calculations tabulated for standard anthropomorphic phantoms. Based on these values, organ doses can be computed by the program for arbitrary scan protocols in conventional and in spiral CT. Effective dose values are also provided, both with ICRP 26 and ICRP 60 tissue-weighting coefficients. Results for several standard CT protocols are presented in tabular form in this paper. In addition, potential for dose reduction is demonstrated, for example, in spiral CT and in quantitative CT. Providing realistic patient dose estimates for arbitrary CT protocols is relevant both for the physician and the patient, and it is particularly useful for educational and training purposes. The program, called WinDose, is now in use at the Erlangen University hospitals (Germany) as an information tool for radiologists and patients. Further extensions are planned. (orig.)

Estimation of dose in dental radiology exams in critical regions

International Nuclear Information System (INIS)

Bonzoumet, S.P.J.; Braz, D.; Padilha, Lucas

2005-01-01

The objective of this paper is to estimate the values of doses, which are absorbed dose to the lens and thyroid in a dental X-ray. Thermoluminescence dosimeters were used, once they provide a reading of quality and effectiveness. This study was based on dental exams conducted in patients in order to estimate the dose that disperses to the lens of the eye and for the thyroid during an intraoral exam. Data collection took place in two institutions, one governmental, which had the device SELETRONIC 70X and other particular. This study showed that there is a considerable variation between the appliances. Using the appliance DABI 1070, there was a greater absorption of radiation in the right eye (values greater than 5 mGy) and a lower dose in the thyroid, and the Seletronic 70X presented an incidence of higher dose deposited in the skin and in other points there was a balance in the values. In the appliance SELETRONIC 70X, there was again a greater absorption of radiation in the right eye and a lower setting in the thyroid. The excessive dose, besides does not favor at all for the quality of radiograph, represents a risk for the patient who absorbs unnecessary and harmful radiation to the body

Uncertainties in estimating heart doses from 2D-tangential breast cancer radiotherapy

DEFF Research Database (Denmark)

Laugaard Lorenzen, Ebbe; Brink, Carsten; Taylor, Carolyn W.

2016-01-01

BACKGROUND AND PURPOSE: We evaluated the accuracy of three methods of estimating radiation dose to the heart from two-dimensional tangential radiotherapy for breast cancer, as used in Denmark during 1982-2002. MATERIAL AND METHODS: Three tangential radiotherapy regimens were reconstructed using CT......-based planning scans for 40 patients with left-sided and 10 with right-sided breast cancer. Setup errors and organ motion were simulated using estimated uncertainties. For left-sided patients, mean heart dose was related to maximum heart distance in the medial field. RESULTS: For left-sided breast cancer, mean...... to the uncertainty of estimates based on individual CT-scans. For right-sided breast cancer patients, mean heart dose based on individual CT-scans was always

Uncertainties in effective dose estimates of adult CT head scans: The effect of head size

International Nuclear Information System (INIS)

Gregory, Kent J.; Bibbo, Giovanni; Pattison, John E.

2009-01-01

Purpose: This study is an extension of a previous study where the uncertainties in effective dose estimates from adult CT head scans were calculated using four CT effective dose estimation methods, three of which were computer programs (CT-EXPO, CTDOSIMETRY, and IMPACTDOSE) and one that involved the dose length product (DLP). However, that study did not include the uncertainty contribution due to variations in head sizes. Methods: The uncertainties due to head size variations were estimated by first using the computer program data to calculate doses to small and large heads. These doses were then compared with doses calculated for the phantom heads used by the computer programs. An uncertainty was then assigned based on the difference between the small and large head doses and the doses of the phantom heads. Results: The uncertainties due to head size variations alone were found to be between 4% and 26% depending on the method used and the patient gender. When these uncertainties were included with the results of the previous study, the overall uncertainties in effective dose estimates (stated at the 95% confidence interval) were 20%-31% (CT-EXPO), 15%-30% (CTDOSIMETRY), 20%-36% (IMPACTDOSE), and 31%-40% (DLP). Conclusions: For the computer programs, the lower overall uncertainties were still achieved when measured values of CT dose index were used rather than tabulated values. For DLP dose estimates, head size variations made the largest (for males) and second largest (for females) contributions to effective dose uncertainty. An improvement in the uncertainty of the DLP method dose estimates will be achieved if head size variation can be taken into account.