| 1. |
- Ainsbury, Elizabeth A., et al.
(författare)
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MULTIBIODOSE RADIATION EMERGENCY TRIAGE CATEGORIZATION SOFTWARE
- 2014
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Ingår i: Health Physics. - 0017-9078 .- 1538-5159. ; 107:1, s. 83-89
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Tidskriftsartikel (refereegranskat)abstract
- In this note, the authors describe the MULTIBIODOSE software, which has been created as part of the MULTIBIODOSE project. The software enables doses estimated by networks of laboratories, using up to five retrospective (biological and physical) assays, to be combined to give a single estimate of triage category for each individual potentially exposed to ionizing radiation in a large scale radiation accident or incident. The MULTIBIODOSE software has been created in Java. The usage of the software is based on the MULTIBIODOSE Guidance: the program creates a link to a single SQLite database for each incident, and the database is administered by the lead laboratory. The software has been tested with Java runtime environment 6 and 7 on a number of different Windows, Mac, and Linux systems, using data from a recent intercomparison exercise. The Java program MULTIBIODOSE_1.0.jar is freely available to download from http://www.multibiodose.eu/software or by contacting the software administrator: MULTIBIODOSE-software@gmx.com.
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| 2. |
- Andersson, Martin, 1983, et al.
(författare)
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IDAC-Bio, A Software for Internal Dosimetry Based on the New ICRP Biokinetic Models and Specific Absorbed Fractions
- 2022
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Ingår i: HEALTH PHYSICS. - 0017-9078 .- 1538-5159. ; 123:2, s. 165-172
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Tidskriftsartikel (refereegranskat)abstract
- Radiation dosimetry is central to virtually all radiation safety applications, optimization, and research. It relates to various individuals and population groups and to miscellaneous exposure situations-including planned, existing, and emergency situations. The International Commission on Radiological Protection (ICRP) has developed a new computational framework for internal dose estimations. Important components are more detailed and improved anatomical models and more realistic biokinetic models than before. The ICRP is currently producing new organ dose and effective dose coefficients for occupational intakes of radionuclides (OIR) and environmental intakes of radionuclides (EIR), which supersede the earlier dose coefficients in Publication 68 and the Publication 72 series, respectively. However, the ICRP only publishes dose coefficients for a single acute intake of a radionuclide and for an integration period of 50 years for intake by adults and to age 70 years for intakes by pre-adults. The new software, IDAC-Bio, performs committed absorbed dose and effective dose calculations for a selectable intake scenario, e.g., for a continuous intake or an intake during x hours per day and y days per week, and for any selected integration time. The software uses the primary data and models of the ICRP biokinetic models and numerically solves the biokinetic model and calculates the absorbed doses to organs and tissues in the ICRP reference human phantoms. The software calculates absorbed dose using the nuclear decay data in ICRP publication 107. IDAC-Bio is a further development and an important addition to the internal dosimetry program IDAC-Dose2.1. The results generated by the software were validated against published ICRP dose coefficients. The potential of the software is illustrated by dose calculations for a nuclear power plant worker who had been exposed to varying levels of Co-60 and who had undergone repeated whole-body measurements, and for a hypothetical member of the public subject to future releases of Gd-148 from neutron spallation in tungsten at the European Spallation Source.
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| 3. |
- Deperas-Kaminska, Marta, et al.
(författare)
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RADIATION-INDUCED CHANGES IN LEVELS OF SELECTED PROTEINS IN PERIPHERAL BLOOD SERUM OF BREAST CANCER PATIENTS AS A POTENTIAL TRIAGE BIODOSIMETER FOR LARGE-SCALE RADIOLOGICAL EMERGENCIES
- 2014
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Ingår i: Health Physics. - 0017-9078 .- 1538-5159. ; 107:6, s. 555-563
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Tidskriftsartikel (refereegranskat)abstract
- The threat of a large scale radiological emergency, where thousands of people may require fast biological dosimetry for the purpose of triage, makes it necessary to search for new, high throughput biological dosimeters. The authors tested an assay based on the quantitative analysis of selected proteins in peripheral blood serum. They were particularly interested in testing proteins that are specific to irradiation of skin, as these can be used in cases of partial body exposure. Candidate proteins were identified in an earlier study with mice, where skin of the animals was exposed to different doses of radiation and global expression of serum proteins was analyzed. Eight proteins were found, the expression of which showed a consistent dose-response relationship. Human analogues of these proteins were identified, and their expression was measured in peripheral blood serum of 16 breast cancer patients undergoing external beam radiotherapy. The proteins were Apolipoprotein E; Apolipoprotein H; Complement protein 7; Prothrombinase; Pantothenate Kinase 4; Alpha-2-macroglobulin; Fetuin B and Alpha-1-Anti-Chymotrypsin. Measurements were carried out in blood samples collected prior to exposure (control), on the day after one fraction (2 Gy), on the day after five fractions (10 Gy), on the day after 10 fractions (20 Gy), and 1 mo after 23-25 fractions (total dose of 46-50 Gy). Multivariate analysis was carried out, and a multinomial logistic regression model was built. The results indicate that the combined analysis of Apolipoprotein E, Factor X, and Pantothenate Kinase 4 allows discriminating between exposure to 2 Gy and lower and between 10 Gy and higher. The discrimination is possible up to 1 mo after exposure.
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| 4. |
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| 5. |
- Galichanin, Konstantin, et al.
(författare)
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Cataract after repeated daily in vivo exposure to ultraviolet radiation
- 2014
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Ingår i: Health Physics. - 0017-9078 .- 1538-5159. ; 107:6, s. 523-529
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Tidskriftsartikel (refereegranskat)abstract
- Epidemiological data indicate a correlation between lifelong exposure to ultraviolet radiation and cortical cataract. However, there is no quantitative experimental data on the effect of daily repeated in vivo exposures of the eye to UVR. Therefore, this experiment was designed to verify whether the dose additivity for UVR exposures holds through periods of time up to 30 d. Eighty rats were conditioned to a rat restrainer 5 d prior to exposure. All animals were divided into four exposure period groups of 1, 3, 10, and 30 d of exposure to UVR. Each exposure period group of 20 animals was randomly divided into five cumulated UVR dose subgroups. Eighteen-wk-old non-anesthetized albino Sprague-Dawley rats were exposed daily to UVR-300 nm for 15 min. One week after the last exposure, animals were sacrificed. The lenses were extracted for macroscopic imaging of dark-field anatomy, and degree of cataract was quantified by measurement of the intensity of forward lens light scattering. Maximum tolerable dose (MTD2.3:16), a statistically defined standard for sensitivity for the threshold for UVR cataract, was estimated for each exposure period. Exposed lenses developed cataract with varying appearance on the anterior surface. Single low doses of UVR accumulated to cause cataract during periods up to 30 d. MTD2.3:16 for 1, 3, 10, and 30 d of repeated exposures was estimated to 4.70, 4.74, 4.80, and 6.00 kJ m, respectively. In conclusion, the lens sensitivity to UVR-B for 18-wk-old Sprague-Dawley rats decreases with the increasing number of days being exposed.
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| 6. |
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Guidelines on limits of exposure to incoherent visible and infrared radiation
- 2013
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Ingår i: Health Physics. - 0017-9078 .- 1538-5159. ; 105:1, s. 74-96
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Tidskriftsartikel (refereegranskat)abstract
- Guidelines for exposure to visible and infrared radiation were first proposed by ICNIRP in 1997. Related guidelines on limits of exposure to ultraviolet radiation (UVR) and laser radiation have been published. This document presents a revision of the guidelines for broadband incoherent radiation.
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| 7. |
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Guidelines on limits of exposure to laser radiation of wavelengths between 180 and 1000 um
- 2013
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Ingår i: Health Physics. - 0017-9078 .- 1538-5159. ; 105:3, s. 271-295
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Tidskriftsartikel (refereegranskat)abstract
- Since the publication of the ICNIRP Revision of the Guidelines on Limits of Exposure to Laser Radiation (ICNIRP 1996, 2000), further research supports amending the retinal thermal exposure limits in terms of spot size dependence, pulse duration dependence for short pulses and wavelength dependence between 1,200 nm and 1,400 nm. A detailed discussion of the rational for the changes is presented in the Appendix of these Guidelines (Rationale for updating the Guidelines).
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| 8. |
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| 9. |
- Hansson, Edvin, 1987-, et al.
(författare)
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Particle Size-dependent Dissolution of Uranium Aerosols in Simulated Lung Fluid : A Case Study in a Nuclear Fuel Fabrication Plant
- 2022
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Ingår i: Health Physics. - : Lippincott, Williams & Wilkins. - 0017-9078 .- 1538-5159. ; 123:1, s. 11-27
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Tidskriftsartikel (refereegranskat)abstract
- Inhalation exposure to uranium aerosols can be a concern in nuclear fuel fabrication. The ICRP provides default absorption parameters for various uranium compounds but also recommends determination of material-specific absorption parameters to improve dose calculations for individuals exposed to airborne radioactivity. Aerosol particle size influences internal dosimetry calculations in two potentially significant ways: the efficiency of particle deposition in the various regions of the respiratory tract is dependent on aerodynamic particle size, and the dissolution rate of deposited materials can vary according to particle size, shape, and porosity because smaller particles tend to have higher surface-to-volume ratios than larger particles. However, the ICRP model assumes that deposited particles of a given material dissolve at the same rate regardless of size and that uptake to blood of dissolved material normally occurs instantaneously in all parts of the lung (except the anterior portion of the nasal region, where zero absorption is assumed). In the present work, the effect of particle size on dissolution in simulated lung fluid was studied for uranium aerosols collected at the plant, and its influence on internal dosimetry calculations was evaluated. Size fractionated uranium aerosols were sampled at a nuclear fuel fabrication plant using portable cascade impactors. Absorption parameters, describing dissolution of material according to the ICRP Human Respiratory Tract Model, were determined in vitro for different size fractions using simulated lung fluid. Samples were collected at 16 time-points over a 100-d period. Uranium content of samples was determined using inductively coupled plasma mass spectrometry and alpha spectrometry. In addition, supplementary experiments to study the effect of pH drift and uranium adsorption on filter holders were conducted as they could potentially influence the derived absorption parameters. The undissolved fraction over time was observed to vary with impaction stage cut-point at the four main workshops at the plant. A larger fraction of the particle activity tended to dissolve for small cut-points, but exceptions were noted. Absorption parameters (rapid fraction, rapid rate, and slow rate), derived from the undissolved fraction over time, were generally in fair agreement with the ICRP default recommendations for uranium compounds. Differences in absorption parameters were noted across the four main workshops at the plant (i.e., where the aerosol characteristics are expected to vary). The pelletizing workshop was associated with the most insoluble material and the conversion workshop with the most soluble material. The correlation between derived lung absorption parameters and aerodynamic particle size (impactor stage cut-point) was weak. For example, the mean absorption parameters derived from impaction stages with low (taken to be <5 mu m) and large (>= 5 mu m) cut-points did not differ significantly. Drift of pH and adsorption on filter holders appeared to be of secondary importance, but it was found that particle leakage can occur. Undissolved fractions and to some degree derived lung absorption parameters were observed to vary depending on the aerodynamic size fraction studied, suggesting that size fractionation (e.g., using cascade impactors) is appropriate prior to conducting in vitro dissolution rate experiments. The 0.01-0.02 mu m and 1-2 mu m size ranges are of particular interest as they correspond to alveolar deposition maxima in the Human Respiratory Tract Model (HRTM). In the present work, however, the dependency on aerodynamic size appeared to be of minor importance, but it cannot be ruled out that particle bounce obscured the results for late impaction stages. In addition, it was noted that the time over which simulated lung fluid samples are collected (100 d in our case) influences the curve-fitting procedure used to determine the lung absorption parameters, in particular the slow rate that increased if fewer samples were considered.
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| 10. |
- Hansson, Edvin, et al.
(författare)
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Uranium Aerosol Activity Size Distributions at a Nuclear Fuel Fabrication Plant
- 2020
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Ingår i: Health Physics. - : LIPPINCOTT WILLIAMS & WILKINS. - 0017-9078 .- 1538-5159. ; 119:3, s. 327-341
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Tidskriftsartikel (refereegranskat)abstract
- Inhalation of uranium aerosols is a concern in nuclear fuel fabrication. Determination of committed effective doses and lung equivalent doses following inhalation intake requires knowledge about aerosol characteristics; e.g., the activity median aerodynamic diameter (AMAD). Cascade impactor sampling of uranium aerosols in the breathing zone of nuclear operators was carried out at a nuclear fuel fabrication plant producing uranium dioxide via ammonium uranyl carbonate. Complementary static sampling was carried out at key process steps. Uranium on impaction substrates was measured using gross alpha counting and alpha spectrometry. Activity size distributions were evaluated for both unimodal and bimodal distributions. When a unimodal distribution was assumed, the average AMAD in the operator breathing zone at the workshops was 12.9-19.3 mu m, which is larger than found in previous studies. Certain sampling occasions showed variable isotope ratios (U-234/U-238) at different impactor stages, indicating more than one population of particles; i.e., a multimodal activity size distribution. When a bimodal distribution (coarse and fine fraction) was assumed, 75-88% of the activity was associated with an AMAD of 15.2-18.9 mu m (coarse fraction). Quantification of the AMAD of the fine fraction was associated with large uncertainties. Values of 1.7-7.1 mu m were obtained. Static sampling at key process steps in the workshops showed AMADs of 4.9-17.2 mu m, generally lower than obtained by breathing zone sampling, when a unimodal distribution was assumed. When a bimodal distribution was assumed, a smaller fraction of the activity was associated with the coarse fraction compared to breathing zone sampling. This might be due to impactor positioning during sampling and sedimentation of large particles. The average committed effective dose coefficient for breathing zone sampling and a bimodal distribution was 1.6-2.6 mu Sv Bq(-1)for(234)U when Type M/S absorption parameters were assumed (5.0 mu Sv Bq(-1)for an AMAD of 5 mu m). The corresponding lung equivalent dose coefficient was 3.6-10.7 mu Sv Bq(-1)(29.9 mu Sv Bq(-1)for an AMAD of 5 mu m). The predicted urinary excretion level 100 d after inhalation intake was found to be 13-34% of that corresponding to an AMAD of 5 mu m. Uranium aerosols generated at a nuclear fuel fabrication plant using ammonium uranyl carbonate route of conversion were associated with larger AMADs compared to previous work, especially when sampling of aerosols was carried out in the operator breathing zone. A bimodal activity size distribution can be used in calculations of committed effective doses and lung equivalent doses, but parameters associated with the fine fraction must be interpreted with care due to large uncertainties.
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| 11. |
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| 12. |
- Israelsson, Axel, et al.
(författare)
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Measurements of 234U and 238U in Hair, Urine, and Drinking Water Among Drilled Bedrock Well Water Users for the Evaluation of Hair as a Biomonitor of Uranium Intake
- 2014
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Ingår i: Health Physics. - : Wolters Kluwer. - 0017-9078 .- 1538-5159. ; 107:2, s. 143-149
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Tidskriftsartikel (refereegranskat)abstract
- Hair is evaluated and compared with urine as a biomonitor for human intake of uranium. Concentrations of U and U and the activity ratio between them are measured in the hair, urine, and drinking water of 24 drilled bedrock well water users in Östergötland, Sweden. The samples are measured with α-spectrometry after radiochemical preparation using liquid-liquid separation with tributylphosphate. The results show that there is a stronger correlation between the uranium concentrations in the drinking water of each subject and the hair of the subject (r = 0.50) than with the urine (r = 0.21). There is also a stronger correlation between the activity ratios of water and hair (r = 0.91) than between water and urine (r = 0.56). These results imply that hair may serve as a robust indicator of chronic uranium intake. One obvious advantage over sampling urine is that hair samples reflect a much longer excretion period: weeks compared to days. The absorbed fraction of uranium, the f value, is calculated as the ratio between the excreted amount of uranium in urine and hair per day and the daily drinking water intake of uranium. The f values stretch from 0.002 to 0.10 with a median of 0.023.
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| 13. |
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| 14. |
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| 15. |
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| 16. |
- Persson, Bertil R.
(författare)
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90Sr in northern Sweden : Relationships and annual variations from 1961 to 1969 in lichen, reindeer and man
- 1971
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Ingår i: Health Physics. - : Ovid Technologies (Wolters Kluwer Health). - 0017-9078. ; 20:4, s. 393-402
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Tidskriftsartikel (refereegranskat)abstract
- The transport of fallout-90Sr has been investigated in the food-chain: Lichen-reindeer-man during 1961-1969. The maximum levels which occurred in lichen during 1963-1965 were about 13 nCi/kg dry wt. The90Sr-level in the lichen-carpet decreased to about 5 nCi/kg dry wt. in 1967-1969. The effective half-time of 90Sr in the lichen-carpet was estimated to be 2.5 ± 0.8 a. The vertical distribution of90Sr in the lichen-carpet was studied during 1966— 1969 and indicates an increased deposition of90Sr-fallout during 1968-1969. The90Sr/Ca-ratio has also been studied in reindeer-bone and muscle tissues. This ratio increased up to 1965 to about 700 pCi/g in reindeer-meat and to 1000pCi/g in bone, and then there was a decrease to about 400 pCi/g in both meat and bone in 1969. The seasonal variation of the 90Sr/Ca-ratio in reindeer-meat and bone since 1965 was evaluated from the 90Sr/Ca-ratio in lichen by using a three-compartment model for the Sr-retention in reindeer. The90Sr/Ca-ratio in the skeleton of adult Swedish Lapps was calculated from the 90Sr/Ca-ratio estimated for diet. The absorbed dose delivered by90Sr +90Y during the period 1950-1970 has been estimated to be 30 mrad to the endosteum (cells lining bone-surfaces) and 20 mrad to the active bone-marrow. Corresponding absorbed dose values for the whole period 1950-2000 were estimated to be 80 ± 15 mrad to the whole endosteum and 50 ± 10 mrad to the bone-marrow.
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| 17. |
- Romm, H., et al.
(författare)
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VALIDATION OF SEMI-AUTOMATIC SCORING OF DICENTRIC CHROMOSOMES AFTER SIMULATION OF THREE DIFFERENT IRRADIATION SCENARIOS
- 2014
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Ingår i: Health Physics. - 0017-9078 .- 1538-5159. ; 106:6, s. 764-771
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Tidskriftsartikel (refereegranskat)abstract
- Large scale radiological emergencies require high throughput techniques of biological dosimetry for population triage in order to identify individuals indicated for medical treatment. The dicentric assay is the gold standard technique for the performance of biological dosimetry, but it is very time consuming and needs well trained scorers. To increase the throughput of blood samples, semi-automation of dicentric scoring was investigated in the framework of the MULTIBIODOSE EU FP7 project, and dose effect curves were established in six biodosimetry laboratories. To validate these dose effect curves, blood samples from 33 healthy donors (>10 donors/scenario) were irradiated in vitro with Co-60 gamma rays simulating three different exposure scenarios: acute whole body, partial body, and protracted exposure, with three different doses for each scenario. All the blood samples were irradiated at Ghent University, Belgium, and then shipped blind coded to the participating laboratories. The blood samples were set up by each lab using their own standard protocols, and metaphase slides were prepared to validate the calibration curves established by semi-automatic dicentric scoring. In order to achieve this, 300 metaphases per sample were captured, and the doses were estimated using the newly formed dose effect curves. After acute uniform exposure, all laboratories were able to distinguish between 0 Gy, 0.5 Gy, 2.0, and 4.0 Gy (p < 0.001), and, in most cases, the dose estimates were within a range of +/- 0.5 Gy of the given dose. After protracted exposure, all laboratories were able to distinguish between 1.0 Gy, 2.0 Gy, and 4.0 Gy (p < 0.001), and here also a large number of the dose estimates were within +/- 0.5 Gy of the irradiation dose. After simulated partial body exposure, all laboratories were able to distinguish between 2.0 Gy, 4.0 Gy, and 6.0 Gy (p < 0.001). Overdispersion of the dicentric distribution enabled the detection of the partial body samples; however, this result was clearly dose-dependent. For partial body exposures, only a few dose estimates were in the range of +/- 0.5 Gy of the given dose, but an improvement could be achieved with higher cell numbers. The new method of semi-automation of the dicentric assay was introduced successfully in a network of six laboratories. It is therefore concluded that this method can be used as a high-throughput screening tool in a large-scale radiation accident.
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| 18. |
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| 19. |
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| 20. |
- Tondel, Martin, et al.
(författare)
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Incidence of neoplasms in ages 0-19 y in parts of Sweden with high 137Cs fallout after the Chernobyl accident
- 1996
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Ingår i: Health Physics. - 0017-9078 .- 1538-5159. ; 71:6, s. 947-950
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Tidskriftsartikel (refereegranskat)abstract
- The incidence of neoplasms in childhood and adolescence in northern and central Sweden before and after the radioactive fallout from the Chernobyl accident was investigated in an ecologic study, 1978 to 1992. The study included all parishes in the six most contaminated counties classified after aerial mapping of ground radiation from 137Cs and investigated 746 cases of neoplasms in ages 0-19 y, diagnosed in the six counties. Incidence and relative risks of neoplasms were compared in areas with high, intermediate, and low contamination after versus before the Chernobyl accident in 1986. A continuous increase of brain tumor incidence in the ages 0-19 y during the period 1978-92 without clear relationship to the Chernobyl fallout was discovered. No clear relationship between the incidence of brain tumor and the exposure to varying levels of radiation from 137Cs was apparent. A somewhat decreased relative risk of acute lymphatic leukemia appeared in areas with increased exposure. Other neoplasms showed no changes in incidence over time or with regard to exposure. Until now, there is no indication that the Chernobyl accident has affected the incidence of childhood and adolescence neoplasms in Sweden, but it is still too early for any final conclusion about the effect of this event.
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| 21. |
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| 22. |
- Yusuf, Ibtisam, et al.
(författare)
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Particle Size Dependent Dissolution of Uranium Aerosols in Simulated Gastrointestinal Fluids
- 2023
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Ingår i: Health Physics. - : LIPPINCOTT WILLIAMS & WILKINS. - 0017-9078 .- 1538-5159. ; 124:4, s. 285-300
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Tidskriftsartikel (refereegranskat)abstract
- Uranium aerosol exposure can be a health risk factor for workers in the nuclear fuel industry. Good knowledge about aerosol dissolution and absorption characteristics in the gastrointestinal tract is imperative for solid dose assessments and risk management. In this study, an in vitro dissolution model of the GI tract was used to experimentally study solubility of size-fractionated aerosols. The aerosols were collected from four major workshops in a nuclear fuel fabrication plant where uranium compounds such as uranium hexafluoride (UF6), uranium dioxide (UO2), ammonium uranyl carbonate, AUC [UO2CO3 center dot 2(NH4)(2)CO3] and triuranium octoxide (U3O8) are present. The alimentary tract transfer factor, f(A), was estimated for the aerosols sampled in the study. The transfer factor was derived from the dissolution in the small intestine in combination with data on absorption of soluble uranium. Results from the conversion workshop indicated a f(A) in line with what is recommended (0.004) by the ICRP for inhalation exposure to Type M materials. Obtained transfer factors, f(A), for the powder preparation and pelletizing workshops where UO2 and U3O8 are handled are lower for inhalation and much lower for ingestion than those recommended by the ICRP for Type M/S materials f(A) = 0.00029 and 0.00016 vs. 0.0006 and 0.002, respectively. The results for ingestion and inhalation f(A) indicate that ICRPs conservative recommendation of f(A) for inhalation exposure is applicable to both ingestion and inhalation of insoluble material in this study. The dissolution- and subsequent absorption-dependence on particle size showed correlation only for one of the workshops (pelletizing). The absence of correlation at the other workshops may be an effect of multiple chemical compounds with different size distribution and/or the reported presence of agglomerated particles at higher cut points having more impact on the dissolution than particle size. The impact on dose coefficients [committed effective dose (CED) per Bq] of using experimental f(A) vs. using default f(A) recommended by the ICRP for the uranium compounds of interest for inhalation exposure was not significant for any of the workshops. However, a significant impact on CED for ingestion exposure was observed for all workshops when comparing with CED estimated for insoluble material using ICRP default f(A). This indicates that the use of experimentally derived site-specific f(A) can improve dose assessments. It is essential to acquire site-specific estimates of the dissolution and absorption of uranium aerosols as this provides more realistic and accurate dose- and risk-estimates of worker exposure. In this study, the results indicate that ICRPs recommendations for ingestion of insoluble material might overestimate absorption and that the lower f(A) found for inhalation could be more realistic for both inhalation and ingestion of insoluble material.
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| 23. |
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