liu.seSearch for publications in DiVA
Change search
Link to record
Permanent link

Direct link
Alternative names
Publications (10 of 48) Show all publications
Hansson, E., Pettersson, H., Yusuf, I., Roos, P., Lindahl, P. & Eriksson, M. (2023). Correction: Particle Size-dependent Dissolution of Uranium Aerosols in Simulated Lung Fluid: A Case Study in a Nuclear Fuel Fabrication Plant (vol 123, pg 11, 2022). Health Physics, 124(1), 62-62
Open this publication in new window or tab >>Correction: Particle Size-dependent Dissolution of Uranium Aerosols in Simulated Lung Fluid: A Case Study in a Nuclear Fuel Fabrication Plant (vol 123, pg 11, 2022)
Show others...
2023 (English)In: Health Physics, ISSN 0017-9078, E-ISSN 1538-5159, Vol. 124, no 1, p. 62-62Article in journal (Other academic) Published
Place, publisher, year, edition, pages
LIPPINCOTT WILLIAMS & WILKINS, 2023
Identifiers
urn:nbn:se:liu:diva-191378 (URN)10.1097/HP.0000000000001666 (DOI)000904724400010 ()36480588 (PubMedID)
Available from: 2023-01-30 Created: 2023-01-30 Last updated: 2023-01-30
Hansson, E., Pettersson, H., Yusuf, I., Roos, P., Lindahl, P. & Eriksson, M. (2022). Particle Size-dependent Dissolution of Uranium Aerosols in Simulated Lung Fluid: A Case Study in a Nuclear Fuel Fabrication Plant. Health Physics, 123(1), 11-27
Open this publication in new window or tab >>Particle Size-dependent Dissolution of Uranium Aerosols in Simulated Lung Fluid: A Case Study in a Nuclear Fuel Fabrication Plant
Show others...
2022 (English)In: Health Physics, ISSN 0017-9078, E-ISSN 1538-5159, Vol. 123, no 1, p. 11-27Article in journal (Refereed) Published
Abstract [en]

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.

Place, publisher, year, edition, pages
Lippincott, Williams & Wilkins, 2022
Keywords
dose; internal; lungs; human; nuclear fuel cycle; uranium
National Category
Radiology, Nuclear Medicine and Medical Imaging
Identifiers
urn:nbn:se:liu:diva-185369 (URN)10.1097/HP.0000000000001564 (DOI)000797126700002 ()35522165 (PubMedID)
Note

Funding Agencies|Swedish Radiation Safety Authority [SSM2016-589-2]; Westinghouse Electric Sweden AB

Available from: 2022-05-31 Created: 2022-05-31 Last updated: 2023-01-30
Israelsson, A., Eriksson, M. & Pettersson, H. (2015). On the Distribution of Uranium in Hair: Non-Destructive Analysis Using SR-μXRF. Spectrochimica Acta Part B - Atomic Spectroscopy, 108, 28-34
Open this publication in new window or tab >>On the Distribution of Uranium in Hair: Non-Destructive Analysis Using SR-μXRF
2015 (English)In: Spectrochimica Acta Part B - Atomic Spectroscopy, ISSN 0584-8547, E-ISSN 1873-3565, Vol. 108, p. 28-34Article in journal (Refereed) Published
Abstract [en]

In the present study the distribution of uranium in single human hair shafts has been evaluated using two synchrotron radiation (SR) based micro X-ray fluorescence techniques; SR μ-XRF and confocal SR μ-XRF. The hair shafts originated from persons that have been exposed to elevated uranium concentrations. Two different groups have been studied, i) workers at a nuclear fuel fabrication factory, exposed mainly by inhalation and ii) owners of drilled bedrock wells exposed by ingestion of water. The measurements were carried out on the FLUO beamline at the synchrotron radiation facility ANKA, Karlsruhe. The experiment was optimized to detect U with a beam size of 6.8 μm × 3 μm beam focus allowing detection down to ppb levels of U in 10 s (SR μ-XRF setup) and 70 s (SR confocal μ-XRF setup) measurements. It was found that the uranium was present in a 10–15 μm peripheral layer of the hair shafts for both groups studied. Furthermore, potential external hair contamination was studied by scanning of unwashed hair shafts from the workers. Sites of very high uranium signal were identified as particles containing uranium. Such particles, were also seen in complementary analyses using variable pressure electron microscope coupled with energy dispersive X-ray analyzer (ESEM–EDX). However, the particles were not visible in washed hair shafts.

These findings can further increase the understanding of uranium excretion in hair and its potential use as a biomonitor.

Place, publisher, year, edition, pages
Elsevier, 2015
Keywords
μ-XRF; Hair; Confocal; Uranium; Internal dosimetry
National Category
Radiology, Nuclear Medicine and Medical Imaging
Identifiers
urn:nbn:se:liu:diva-108891 (URN)10.1016/j.sab.2015.04.001 (DOI)000355360400005 ()
Available from: 2014-07-11 Created: 2014-07-11 Last updated: 2017-12-05Bibliographically approved
Pham, M. K., Benmansour, M., Carvalho, F. P., Chamizo, E., Degering, D., Engeler, C., . . . Zhou, W. (2014). Certified Reference Material IAEA-446 for radionuclides in Baltic Sea seaweed. Applied Radiation and Isotopes, 87, 468-474
Open this publication in new window or tab >>Certified Reference Material IAEA-446 for radionuclides in Baltic Sea seaweed
Show others...
2014 (English)In: Applied Radiation and Isotopes, ISSN 0969-8043, E-ISSN 1872-9800, Vol. 87, p. 468-474Article in journal (Refereed) Published
Abstract [en]

A Certified Reference Material (CRM) for radionuclides in seaweed (Fucus vesiculosus) from the Baltic Sea (IAEA-446) is described and the results of the certification process are presented. The K-40, Cs-132, U-234 and Pu239+240 radionuclides were certified for this material, and information values for 12 other radionuclides (Sr-90, Tc-99, Pb-210 (Po-210), Ra-226, Ra-228, Th-228, Th-230, Th-232, U-235, U-238, Pu-239 and Pu-240) are presented. The CRM can be used for Quality Assurance/Quality Control of analysis of radionuclides in seaweed and other biota samples, as well as for development and validation of analytical methods, and for training purposes.

Place, publisher, year, edition, pages
Elsevier, 2014
Keywords
Certified Reference Material; Sea weed (Fucus vesiculosus); Radionuclides; Quality Assurance/Quality Control
National Category
Earth and Related Environmental Sciences
Identifiers
urn:nbn:se:liu:diva-112024 (URN)10.1016/j.apradiso.2013.11.013 (DOI)000335274000102 ()24291528 (PubMedID)
Available from: 2014-11-13 Created: 2014-11-13 Last updated: 2017-12-05Bibliographically approved
Israelsson, A. & Pettersson, H. (2014). 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. Health Physics, 107(2), 143-149
Open this publication in new window or tab >>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 (English)In: Health Physics, ISSN 0017-9078, E-ISSN 1538-5159, Vol. 107, no 2, p. 143-149Article in journal (Refereed) Published
Abstract [en]

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.

Place, publisher, year, edition, pages
Wolters Kluwer, 2014
National Category
Radiology, Nuclear Medicine and Medical Imaging
Identifiers
urn:nbn:se:liu:diva-108889 (URN)10.1097/HP.0000000000000075 (DOI)000338678800005 ()24978285 (PubMedID)
Available from: 2014-07-11 Created: 2014-07-11 Last updated: 2017-12-05Bibliographically approved
Israelsson, A. & Pettersson, H. (2014). Using Hair as a Bioindicator for Inhalation of Uranium: A Study on Nuclear Fuel Fabrication Workers.
Open this publication in new window or tab >>Using Hair as a Bioindicator for Inhalation of Uranium: A Study on Nuclear Fuel Fabrication Workers
2014 (English)Manuscript (preprint) (Other academic)
Abstract [en]

Scalp hair is evaluated and compared with urine as a potential biomonitor following inhalation intake of uranium. The samples were collected among eight workers at a nuclear fuel fabrication factory and the sample concentrations of 234U and 238U were analyzed by α-spectrometry after radiochemical preparation using a TBP-based liquidliquid separation method. Personal air samplers (PAS) filters were also analyzed for determination of inhaled uranium activity.

The results show that there is a large day-to-day variation (7-70 Bq d-1) of the inhaled 234U activity over a 6 week period. A large variation is also seen for the 234U activity concentration among 12 urine samples collected over a 12 week period; (2-50 mBq kg-1). Four hair samples from the same subject and period showed less variation (100-240 mBq g-1) as they reflect the average excretion over a longer period than the periodic urine samples.

The total inhalation intake and excretion in urine and hair was obtained for two study subjects over a 6 week period. The uranium inhalation to urine and hair factors finh,u and finh,h were 0.0014 and 0.0002 respectively, given by calculations based on the measured PAS, urine and hair data. It has been demonstrated that scalp hair could be a valuable complement to urine as biomonitor of uranium intake.

Keywords
Hair, uranium, alpha spectroscopy
National Category
Radiology, Nuclear Medicine and Medical Imaging
Identifiers
urn:nbn:se:liu:diva-108890 (URN)
Available from: 2014-07-11 Created: 2014-07-11 Last updated: 2014-07-11Bibliographically approved
Sandborg, M., Nilsson Althén, J., Pettersson, H. & Rossitti, S. (2012). Patient Organ Radiation Doses During Treatment for Aneurysmal Subarachnoid Hemorrhage. Clinical neuroradiology, 22(4), 315-325
Open this publication in new window or tab >>Patient Organ Radiation Doses During Treatment for Aneurysmal Subarachnoid Hemorrhage
2012 (English)In: Clinical neuroradiology, ISSN 1869-1447, Vol. 22, no 4, p. 315-325Article in journal (Refereed) Published
Abstract [en]

PURPOSE: The aim of this retrospective study was to estimate risk organ doses and to estimate radiation risks during the imaging work-up and treatment for aneurysmal subarachnoid hemorrhage (SAH). METHODS: The imaging procedures comprised computed tomography and digital subtraction angiography studies for diagnosis or endovascular interventional procedures in 50 consecutive patients. Equivalent organ doses (H(T)) to skin, brain, eye lens, salivary glands, thyroid and oral mucosa were measured using thermoluminescence dosimeters in an anthropomorphic head phantom. Picture archiving and communication system (PACS) and radiological information system (RIS) records were analyzed and the frequency of each imaging procedure was recorded as well as the registered individual kerma-length product (P(KL)) and the kerma-area product (P(KA)). The doses were computed by multiplying the recorded P(KL) and P(KA) values by the conversion coefficients H(T)/P(KL) and H(T)/P(KA) from the head phantom. RESULTS: The mean fluoroscopy time, P(KL) and P(KA) were 38 min, 7269 mGy cm and 286 Gy cm(2), respectively. The estimated mean equivalent doses were as follows: skin 2.51 Sv, brain 0.92 Sv, eye lens 0.43 Sv and salivary glands 0.23 Sv. Maximum organ doses were 2.3-3.5 times higher than the mean. Interventional procedures contributed 66 % to skin dose, 55 % to brain dose and 25 % to eye lens dose. Of the patients with an estimated skin dose exceeding 6 Sv, only 1 developed temporary epilation. CONCLUSION: The risk for radiation-induced cancer for SAH patients is low (2-3 cases per 1,000 patients, of which 90 % are expected to be benign types) compared with the risk of tissue reactions on the head such as skin erythema and epilation (1 temporary epilation per 50 patients).

Place, publisher, year, edition, pages
Springer, 2012
National Category
Medical and Health Sciences
Identifiers
urn:nbn:se:liu:diva-78917 (URN)10.1007/s00062-012-0147-0 (DOI)000311500500004 ()22576966 (PubMedID)
Available from: 2012-06-25 Created: 2012-06-25 Last updated: 2014-02-27
Gårdestig, M. & Pettersson, H. B. (2012). RadiaCopter - UAS Gamma spectrometry for detection and identification of radioactive sources. In: IRPA13 the 13th International Congress of the International Radiation Protection Association: . Paper presented at 13th International Congress of the International Radiation Protection Association (IRPA13), 13-18 May 2012, Glasgow, Scotland, UK (pp. P09-22).
Open this publication in new window or tab >>RadiaCopter - UAS Gamma spectrometry for detection and identification of radioactive sources
2012 (English)In: IRPA13 the 13th International Congress of the International Radiation Protection Association, 2012, p. P09-22Conference paper, Poster (with or without abstract) (Other academic)
National Category
Medical and Health Sciences
Identifiers
urn:nbn:se:liu:diva-106261 (URN)
Conference
13th International Congress of the International Radiation Protection Association (IRPA13), 13-18 May 2012, Glasgow, Scotland, UK
Available from: 2014-05-03 Created: 2014-05-01 Last updated: 2014-05-12Bibliographically approved
Pham, M. K., Betti, M., Povinec, P. P., Benmansour, M., Buenger, V., Drefvelin, J., . . . Zheng, J. (2011). A certified reference material for radionuclides in the water sample from Irish Sea (IAEA-443). JOURNAL OF RADIOANALYTICAL AND NUCLEAR CHEMISTRY, 288(2), 603-611
Open this publication in new window or tab >>A certified reference material for radionuclides in the water sample from Irish Sea (IAEA-443)
Show others...
2011 (English)In: JOURNAL OF RADIOANALYTICAL AND NUCLEAR CHEMISTRY, ISSN 0236-5731, Vol. 288, no 2, p. 603-611Article in journal (Refereed) Published
Abstract [en]

A new certified reference material (CRM) for radionuclides in sea water from the Irish sea (IAEA-443) is described and the results of the certification process are presented. Ten radionuclides (H-3, K-40, Sr-90, Cs-137, U-234, U-235, U-238, Pu-238, Pu239+240 and Am-241) have been certified, and information values on massic activities with 95% confidence intervals are given for four radionuclides (Th-230, Th-232, Pu-239 and Pu-240). Results for less frequently reported radionuclides (Tc-99, Th-228, Np-237 and Pu-241) are also reported. The CRM can be used for quality assurance/quality control of the analysis of radionuclides in water samples, for the development and validation of analytical methods and for training purposes. The material is available in 5 L units from IAEA (http://nucleus.iaea.org/rpst/index.htm).

Place, publisher, year, edition, pages
Springer Science Business Media, 2011
Keywords
Certified reference material, Sea water, Irish sea, Radionuclides, Massic activity
National Category
Medical and Health Sciences
Identifiers
urn:nbn:se:liu:diva-67012 (URN)10.1007/s10967-010-0976-8 (DOI)000288219300042 ()
Available from: 2011-03-25 Created: 2011-03-25 Last updated: 2011-04-21
Karlsson, M. P., Halse, T., Carlsson, M., Gårdestig, M., Stark, K. & Pettersson, H. B. (2011). External radiation doses to biota: Monte Carlo dose model calculations. In: XVI Conference of the NSFS, Reykjavik Iceland, 22-25 August 2011: Current Challenges in Radiation Protection Conference Proceedings. Paper presented at XVI Conference of the NSFS, Reykjavik Iceland, 22-25 August 2011.
Open this publication in new window or tab >>External radiation doses to biota: Monte Carlo dose model calculations
Show others...
2011 (English)In: XVI Conference of the NSFS, Reykjavik Iceland, 22-25 August 2011: Current Challenges in Radiation Protection Conference Proceedings, 2011Conference paper, Published paper (Other academic)
Abstract [en]

Realistic and reliable dose models are required to estimate the radiological risks to non-human biota, in regions contaminated by radioactivity. To facilitate detailed dose calculations, a graphical user interface has been developed to the Monte Carlo N-Particle Transport code (MCNP): the TADPOLE editor (Terrestrial and Aquatic Dose assessment Program for Organisms in their Local Environment). The editor is intended for site and biota specific analyses of absorbed dose from external γ- and β- radiation.

An experiment was performed in controlled, laboratory conditions as a first validation of the calculation models assigned by the editor. Measurements with TL-dosimeters yielded lower doses than was calculated by MCNP5 through the editor.

Keywords
Radioecology; Monte Carlo; MCNP; Non-human biota; Software tool
National Category
Medical and Health Sciences
Identifiers
urn:nbn:se:liu:diva-76071 (URN)
Conference
XVI Conference of the NSFS, Reykjavik Iceland, 22-25 August 2011
Available from: 2012-03-26 Created: 2012-03-26 Last updated: 2017-02-27
Organisations
Identifiers
ORCID iD: ORCID iD iconorcid.org/0000-0001-6430-7990

Search in DiVA

Show all publications