EURADOS intercomparison on measurements and Monte Carlo modelling for the assessment of americium in a USTUR leg phantom

López, M. A.; Broggio, David; Capello, Kevin; Cardenas-Mendez, E.; El-Faramawy, Nabil; Franck, Didier; James, Anthony; Kramer, Gary H.; Lacerenza, G.; Lynch, Timothy P.; Navarro, Juan F.; Navarro, T.; Pérez, B.; Rühm, W.; Tolmachev, Sergei Y.; Weitzenegger, E.

doi:10.1093/rpd/ncq304

Cited by 13 publications

(10 citation statements)

References 3 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…Alternatively, numerical calibration techniques may be applied. Mathematical software combines voxel phantoms and Monte Carlo statistical simulations to model photon transport from the phantom and the detection of photons by a simulated detector (Franck et al., 2003; Hunt et al., 2003; Gómez-Ros et al., 2007; Lopez et al., 2011a). The International Atomic Energy Agency (IAEA, 1996) and the International Commission on Radiation Units and Measurements (ICRU, 2002) have given guidance on the direct measurement of body content of radionuclides.…”

Section: Methods Of Individual and Workplace Monitoringmentioning

confidence: 99%

Section: Body Activity Measurements (In-vivo Measurements)mentioning

confidence: 99%

See 1 more Smart Citation

ICRP Publication 130: Occupational Intakes of Radionuclides: Part 1

Paquet¹,

et al. 2015

View full text Add to dashboard Cite

This report is the first in a series of reports replacing Publications 30 and 68 to provide revised dose coefficients for occupational intakes of radionuclides by inhalation and ingestion. The revised dose coefficients have been calculated using the Human Alimentary Tract Model (Publication 100) and a revision of the Human Respiratory Tract Model (Publication 66) that takes account of more recent data. In addition, information is provided on absorption into blood following inhalation and ingestion of different chemical forms of elements and their radioisotopes. In selected cases, it is judged that the data are sufficient to make material-specific recommendations. Revisions have been made to many of the models that describe the systemic biokinetics of radionuclides absorbed into blood, making them more physiologically realistic representations of uptake and retention in organs and tissues, and excretion. The reports in this series provide data for the interpretation of bioassay measurements as well as dose coefficients, replacing Publications 54 and 78. In assessing bioassay data such as measurements of whole-body or organ content, or urinary excretion, assumptions have to be made about the exposure scenario, including the pattern and mode of radionuclide intake, physical and chemical characteristics of the material involved, and the elapsed time between the exposure(s) and measurement. This report provides some guidance on monitoring programmes and data interpretation.

show abstract

Section: Methods Of Individual and Workplace Monitoringmentioning

confidence: 99%

Section: Body Activity Measurements (In-vivo Measurements)mentioning

confidence: 99%

ICRP Publication 130: Occupational Intakes of Radionuclides: Part 1

Paquet¹,

et al. 2015

View full text Add to dashboard Cite

show abstract

“…Doses from intakes of radionuclides are estimated from monitoring data of activity in total/partial body and in excreta samples (urine and faeces) using biokinetic and dosimetric models and from assumptions about the pattern of intake and the properties of the radioactive material inside the body. Past intercomparison exercises (88,89) have shown a wide range in doses that can be obtained from the same data set from different assessors demonstrating the need for guidance on harmonising internal dose evaluations. Any actions required in this context must take into account the stateof-the-art tools currently available and forthcoming publications such as ICRP/OIR Reports (90) , revised IDEAS Guidelines for the Estimation of Committed Doses from Incorporation Monitoring Data (59) , ISO Standards in internal dosimetry (91) and the output of the TechRec project Technical Recommendations for Monitoring Individuals Occupationally Exposed to Internal Radiation currently being prepared for the EC by a consortium of EURADOS voting member institutions.…”

Section: Harmonisationmentioning

confidence: 99%

Eurados Strategic Research Agenda: Vision for Dosimetry of Ionising Radiation

Rühm¹,

Fantuzzi²,

Harrison³

et al. 2015

Radiat Prot Dosimetry

Self Cite

View full text Add to dashboard Cite

Since autumn 2012, the European Radiation Dosimetry Group (EURADOS) has been developing its Strategic Research Agenda (SRA), which is intended to contribute to the identification of future research needs in radiation dosimetry in Europe. The present article summarises-based on input from EURADOS Working Groups (WGs) and Voting Members-five visions in dosimetry and defines key issues in dosimetry research that are considered important for the next decades. The five visions include scientific developments required towards (a) updated fundamental dose concepts and quantities, (b) improved radiation risk estimates deduced from epidemiological cohorts, (c) efficient dose assessment for radiological emergencies, (d) integrated personalised dosimetry in medical applications and (e) improved radiation protection of workers and the public. The SRA of EURADOS will be used as a guideline for future activities of the EURADOS WGs. A detailed version of the SRA can be downloaded as a EURADOS report from the EURADOS website (www.eurados.org).

show abstract

“…For this purpose, acquiring experimental data following the method employed here would be very difficult and tedious. Calculating the detector response with Monte Carlo methods was found to be reliable for welldefined experimental situations (Lamart et al, 2009;Lopez et al, 2011;Broggio et al, 2012). However, in the present case a very detailed model of the MUs would be necessary because of the significance of scattered radiation.…”

Section: Discussionmentioning

confidence: 86%

An experimental study of detection limits and corresponding doses of IRSNin vivomonitoring vehicles in the case of post-accident scenarios

et al. 2014

Self Cite

View full text Add to dashboard Cite

-The measurement performances of in vivo monitoring vehicles were studied considering an increase in the radiological background in areas where the population is not evacuated after a nuclear accident. The study focused on 137 Cs and 131 I Detection Limits (DLs) and corresponding doses, for adults and one-year-old children. These DLs for ground contamination were obtained experimentally using a grid of point sources. Then, the DLs and doses were calculated using the experimental data and a safety factor for two accident scenarios. For these scenarios the 137 Cs DL corresponds to a committed effective dose of 0.02 mSv. The 131 I DL corresponds to committed equivalent thyroid doses of 3 mSv (adult) and 30 mSv (one-year-old child). To guarantee a 45 mSv thyroid equivalent dose assessment for the child the surface activity of 131 I + 132 I + 133 I should be below 1.6 MBq/m 2 . This study shows that the vehicles can operate in a contaminated area where the population is not evacuated. However, in such a case, the contamination level outside and inside the vehicle should be kept stable to guarantee efficient body counting.

show abstract

EURADOS intercomparison on measurements and Monte Carlo modelling for the assessment of americium in a USTUR leg phantom

Cited by 13 publications

References 3 publications

ICRP Publication 130: Occupational Intakes of Radionuclides: Part 1

ICRP Publication 130: Occupational Intakes of Radionuclides: Part 1

Eurados Strategic Research Agenda: Vision for Dosimetry of Ionising Radiation

An experimental study of detection limits and corresponding doses of IRSNin vivomonitoring vehicles in the case of post-accident scenarios

Contact Info

Product

Resources

About