| 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. |
- Bernhardsson, Christian, et al.
(författare)
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Comparative Measurements of the External Radiation Exposure in a 137Cs Contaminated Village in Belarus Based on Optically Stimulated Luminescence in NaCl and Thermoluminescence in LiF.
- 2012
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Ingår i: Health Physics. - 1538-5159. ; 103:6, s. 740-749
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Tidskriftsartikel (refereegranskat)abstract
- ABSTRACT: Laboratory studies have shown that ordinary household salt (NaCl) exhibits several promising properties for retrospective dosimetry; e.g., a linear dose response and a low detection limit, down to a few mGy or even less. In an attempt to test NaCl as a dosimeter outside the laboratory, the first results from the use of NaCl as a dosimeter under normal environmental conditions are reported here. For this purpose, special dosimeter kits with NaCl and lithium fluoride (LiF) chips were designed. The dosimeter kits were positioned at different locations in a Chernobyl Cs-contaminated village in Belarus during the summers of 2008, 2009, and 2010. The results from the two luminescent detectors were also compared with those of measurements carried out with a handheld 75 cm NaI(Tl) detector and with a 8 dm high pressure ionization chamber. The radiation level in the village was inhomogeneous, and depending on the type of house and countermeasures carried out, the ambient dose rate inside and around the houses varied between 0.05 μSv h and 0.50 μSv h. Based on the different measurements, the annual external effective dose to a hypothetical adult population in the village was estimated as 1-1.5 mSv y. Detector readings from the two luminescent materials correlated relatively strongly to that of the ambient survey NaI(Tl) detector. After three repeated surveys using similar dosimeter kits for prospective dosimetry, the potential use of ordinary household salt as a complement to other techniques for retrospective dose estimations is more evident, and shortcomings of the technique have been identified.
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| 4. |
- Christiansson, Maria, et al.
(författare)
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Optimizing A Readout Protocol For Low Dose Retrospective Osl-Dosimetry Using Household Salt
- 2012
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Ingår i: Health Physics. - 1538-5159. ; 102:6, s. 631-636
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Tidskriftsartikel (refereegranskat)abstract
- The authors' aim has been to find a single aliquot regenerative dose (SAR) protocol that accurately recovers an unknown absorbed dose in the region between 1-250 mGy in household salt. The main investigation has been conducted on a specific mine salt (>98.5% NaCl) intended for household use, using optical stimulation by blue LED (lambda = 462 nm). The most accurate dose recovery for this brand of salt is found to be achieved when using Peak Signal Summing (PSS) of the OSL-decay and a preheat temperature of 200 degrees C after the test dose. A SAR protocol for the household salt with preset values of regenerative doses (R1-R5) and a test dose (TED) of 17 mGy is also suggested here. Under laboratory conditions, the suggested protocol recovers unknown absorbed doses in this particular brand within 5% (2 SD) in the dose range between 1-250 mGy. This is a very promising result for low dose applications of household salt as a retrospective dosimeter after a nuclear or radiological event. Health Phys. 102(6):631-636;2012
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| 5. |
- 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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| 6. |
- 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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| 7. |
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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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| 8. |
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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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| 9. |
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| 10. |
- 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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