Zeitschriftenartikel: „Dose coefficients“

1

Killough, George G., und Paul S. Rohwer. „14C DOSE COEFFICIENTS“. Health Physics 90, Nr. 3 (März 2006): 273–75. http://dx.doi.org/10.1097/00004032-200603000-00011.

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2

Schultz, F. W., und J. Zoetelief. „Dose conversion coefficients for interventional procedures“. Radiation Protection Dosimetry 117, Nr. 1-3 (01.12.2005): 225–30. http://dx.doi.org/10.1093/rpd/nci753.

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3

Veinot, K. G., N. E. Hertel, M. M. Hiller und K. F. Eckerman. „Neutron dose coefficients for local skin“. Journal of Radiological Protection 40, Nr. 2 (13.05.2020): 554–82. http://dx.doi.org/10.1088/1361-6498/ab805e.

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4

Vargo, George J. „The ICRP Database of Dose Coefficients“. Health Physics 78, Nr. 3 (März 2000): 343. http://dx.doi.org/10.1097/00004032-200003000-00015.

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5

Dubeau, J., und J. Sun. „ELECTRON EYE-LENS OPERATIONAL DOSE COEFFICIENTS“. Radiation Protection Dosimetry 188, Nr. 3 (30.01.2020): 372–77. http://dx.doi.org/10.1093/rpd/ncz295.

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Abstract In 2012, the International Commission on Radiological Protection issued a recommendation for a reduced annual eye-lens dose limit in the face of mounting evidence of the risk of cataract induction. This led to worldwide research efforts in various areas including the dose simulation in realistic eye-models, the production of dosimeters and the elaboration of protection and operation fluence to eye-lens dose coefficients. In this last case, much efforts have been expanded with regards to photon operational coefficients for Hp (3) but much less for electron radiation. In this work, Hp (3) coefficients for electrons are presented following simulations using MCNP and compared to those that are available in the literature. It is found that, at energies of 1 MeV and less, Hp (3) coefficients depend strongly on the selected electron transport options and on the dose tally volume. The effect of these differences is demonstrated for two beta emitters.

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6

Kanti, Hassan Al, Otman El Hajjaji, Tarek El Bardouni und Maged Mohammed. „Neutron conversion coefficients of ambient dose equivalent and personal dose equivalent“. Polish Journal of Medical Physics and Engineering 28, Nr. 1 (01.03.2022): 52–59. http://dx.doi.org/10.2478/pjmpe-2022-0006.

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Abstract Introduction: This work aims to calculate the ambient and personal dose equivalent conversion coefficients. Material and methods: The conversion coefficients have been calculated using MC simulation. Additionally, this paper proposes a new method that depends on an analytical approach. Results: The obtained results in good agreement between MC and an analytical approach were observed. The obtained results were compared to those published in ICRU 57 report. Conclusions: We deduced that the analytical approach is as effective and suitable as the MC simulation to calculate the operational quantity conversion coefficients.

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7

Opreanu, Razvan C., Ranji Samaraweera und John P. Kepros. „Effective Dose to Dose-Length Product Coefficients for Calculation of CT Effective Dose“. Radiology 252, Nr. 1 (Juli 2009): 315–16. http://dx.doi.org/10.1148/radiol.2521090245.

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8

Mares, V., und G. Leuthold. „Altitude-dependent dose conversion coefficients in EPCARD“. Radiation Protection Dosimetry 126, Nr. 1-4 (13.05.2007): 581–84. http://dx.doi.org/10.1093/rpd/ncm118.

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9

Khursheed, A. „Uncertainties in Dose Coefficients for Systemic Plutonium“. Radiation Protection Dosimetry 78, Nr. 2 (02.07.1998): 121–26. http://dx.doi.org/10.1093/oxfordjournals.rpd.a032342.

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10

Phipps, A. W., T. J. Silk und T. P. Fell. „The ICRP CD-ROM of Dose Coefficients“. Radiation Protection Dosimetry 79, Nr. 1 (01.10.1998): 363–65. http://dx.doi.org/10.1093/oxfordjournals.rpd.a032427.

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11

Paquet, F., und J. Harrison. „ICRP Task Group 95: internal dose coefficients“. Annals of the ICRP 47, Nr. 3-4 (16.04.2018): 63–74. http://dx.doi.org/10.1177/0146645318759620.

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Internal doses are calculated using biokinetic and dosimetric models. These models describe the behaviour of the radionuclides after ingestion, inhalation, and absorption to the blood, and the absorption of the energy resulting from their nuclear transformations. The International Commission on Radiological Protection (ICRP) develops such models and applies them to provide dose coefficients and bioassay functions for the calculation of equivalent or effective dose from knowledge of intakes and/or measurements of activity in bioassay samples. Over the past few years, ICRP has devoted a considerable amount of effort to the revision and improvement of models to make them more physiologically realistic representations of uptake and retention in organs and tissues, and of excretion. Provision of new biokinetic models, dose coefficients, monitoring methods, and bioassay data is the responsibility of Committee 2 and its task groups. Three publications in a series of documents replacing the ICRP Publication 30 series and ICRP Publications 54, 68, and 78 have been issued [Occupational Intakes of Radionuclides (OIR) Parts 1–3]. OIR Part 1 describes the assessment of internal occupational exposure to radionuclides, biokinetic and dosimetric models, methods of individual and workplace monitoring, and general aspects of retrospective dose assessment. OIR Parts 2–5 provide data on individual elements and their radioisotopes. Work is also in progress on revision of dose coefficients for radionuclide intakes by members of the public.

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12

Melo, Dunstana R., Luiz Bertelli, Shawki A. Ibrahim, Lynn R. Anspaugh, André Bouville und Steven L. Simon. „Dose Coefficients for Internal Dose Assessments for Exposure to Radioactive Fallout“. Health Physics 122, Nr. 1 (Januar 2022): 125–235. http://dx.doi.org/10.1097/hp.0000000000001500.

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13

Mohd Tap, Nor Hanani, Mohamed Ariff Jaafar Sidek, Siti Farizwana Mohd Ridzwan, S. Elavarasi Selvarajah, Faizah Mohd Zaki und Hamzaini Abdul Hamid. „Computed Tomography Dose in Paediatric Care: Simple Dose Estimation Using Dose Length Product Conversion Coefficients“. Malaysian Journal of Medical Sciences 25, Nr. 4 (2018): 82–91. http://dx.doi.org/10.21315/mjms2018.25.4.8.

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14

Otto, Thomas. „Personal dose-equivalent conversion coefficients for 1252 radionuclides“. Radiation Protection Dosimetry 168, Nr. 1 (26.10.2014): 1–10. http://dx.doi.org/10.1093/rpd/ncu316.

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15

W. Stater, J. „Editorial - Reliability (and Uncertainty) of Radionuclide Dose Coefficients“. Radiation Protection Dosimetry 95, Nr. 3 (01.06.2001): 195–97. http://dx.doi.org/10.1093/oxfordjournals.rpd.a006542.

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16

Ferrari, A., M. Pelliccioni und M. Pillon. „Fluence-to-Effective Dose Conversion Coefficients for Muons“. Radiation Protection Dosimetry 74, Nr. 4 (01.12.1997): 227–33. http://dx.doi.org/10.1093/oxfordjournals.rpd.a032201.

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17

Gilby, D., P. Gribi und D. Nosske. „Quantifying the Reliability of Calculated Ingestion Dose Coefficients“. Radiation Protection Dosimetry 79, Nr. 1 (01.10.1998): 283–86. http://dx.doi.org/10.1093/oxfordjournals.rpd.a032410.

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18

Portal, G., W. G. Cross, G. Dietze, J. R. Harvey und R. B. Schwartz. „Appendix A: Conversion Coefficients for Dose Equivalent Quantities“. Reports of the International Commission on Radiation Units and Measurements os-24, Nr. 2 (April 1992): 22–30. http://dx.doi.org/10.1093/jicru_os24.2.22.

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19

Prinz, Heino. „Hill coefficients, dose–response curves and allosteric mechanisms“. Journal of Chemical Biology 3, Nr. 1 (25.09.2009): 37–44. http://dx.doi.org/10.1007/s12154-009-0029-3.

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20

Portal, G., W. G. Cross, G. Dietze, J. R. Harvey und R. B. Schwartz. „Appendix A: Conversion Coefficients for Dose Equivalent Quantities“. Journal of the International Commission on Radiation Units and Measurements os24, Nr. 2 (15.04.1992): 22–30. http://dx.doi.org/10.1093/jicru/os24.2.22.

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21

Boyer, Arthur L. „Relationship between Attenuation Coefficients and Dose-Spread Kernels“. Radiation Research 113, Nr. 2 (Februar 1988): 235. http://dx.doi.org/10.2307/3577199.

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22

Bolch, W. E., N. Petoussi-Henss, F. Paquet und J. Harrison. „ICRP dose coefficients: computational development and current status“. Annals of the ICRP 45, Nr. 1_suppl (05.04.2016): 156–77. http://dx.doi.org/10.1177/0146645316636010.

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23

Kicken, P. J. H., M. Zankl und G. J. Kemerink. „Patient Dosimetry in Arteriography of the Lower Limbs. Part II: Dose Conversion Coefficients, Organ Doses and Effective Dose“. Radiation Protection Dosimetry 81, Nr. 1 (01.01.1999): 37–45. http://dx.doi.org/10.1093/oxfordjournals.rpd.a032568.

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24

TSUDA, Shuichi, und Yasuhiro YAMAGUCHI. „Review of Dose Conversion Coefficients for High-energy Radiations.“ Japanese Journal of Health Physics 36, Nr. 1 (2001): 51–60. http://dx.doi.org/10.5453/jhps.36.51.

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25

Melintescu, A., D. Galeriu und H. Takeda. „Reassessment of tritium dose coefficients for the general public“. Radiation Protection Dosimetry 127, Nr. 1-4 (07.06.2007): 153–57. http://dx.doi.org/10.1093/rpd/ncm267.

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26

Toohey, R. E., L. Bertelli, S. L. Sugarman, A. L. Wiley und D. M. Christensen. „DOSE COEFFICIENTS FOR INTAKES OF RADIONUCLIDES VIA CONTAMINATED WOUNDS“. Health Physics 100, Nr. 5 (Mai 2011): 508–14. http://dx.doi.org/10.1097/hp.0b013e3181fb2e01.

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27

Timoshenko, G. N., und M. I. Belvedersky. „Fluence-to-effective dose conversion coefficients for male astronauts“. Journal of Radiological Protection 39, Nr. 2 (April 2019): 511–21. http://dx.doi.org/10.1088/1361-6498/ab0583.

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28

Mares, V., S. Roesler und H. Schraube. „Averaged particle dose conversion coefficients in air crew dosimetry“. Radiation Protection Dosimetry 110, Nr. 1-4 (01.08.2004): 371–76. http://dx.doi.org/10.1093/rpd/nch137.

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29

Liu, Zhenzhou, und Jinxiang Chen. „New calculations of neutron kerma coefficients and dose equivalent“. Journal of Radiological Protection 28, Nr. 2 (22.05.2008): 185–93. http://dx.doi.org/10.1088/0952-4746/28/2/002.

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30

Schwahn, Scott O. „ON ABSORBED DOSE COEFFICIENTS CALCULATED BY VEINOT AND HERTEL“. Health Physics 92, Nr. 6 (Juni 2007): 668. http://dx.doi.org/10.1097/01.hp.0000261598.58155.0f.

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31

Veinot, K. G., K. F. Eckerman, M. B. Bellamy, M. M. Hiller, S. A. Dewji, C. E. Easterly, N. E. Hertel und R. Manger. „Effective dose rate coefficients for exposure to contaminated soil“. Radiation and Environmental Biophysics 56, Nr. 3 (10.05.2017): 255–67. http://dx.doi.org/10.1007/s00411-017-0692-7.

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32

Otto, T. „Conversion coefficients from kerma to ambient dose and personal dose for X-ray spectra“. Journal of Instrumentation 14, Nr. 11 (07.11.2019): P11011. http://dx.doi.org/10.1088/1748-0221/14/11/p11011.

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33

SATO, Osamu, Nobuaki YOSHIZAWA, Shunji TAKAGI, Satoshi IWAI, Takashi UEHARA, Yukio SAKAMOTO, Yasuhiro YAMAGUCHI und Shun-ichi TANAKA. „Calculations of Effective Dose and Ambient Dose Equivalent Conversion Coefficients for High Energy Photons“. Journal of Nuclear Science and Technology 36, Nr. 11 (November 1999): 977–87. http://dx.doi.org/10.1080/18811248.1999.9726290.

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34

Domienik-Andrzejewska, Joanna, Marcin Brodecki und Marek Zmyślony. „CORRELATION OF EYE LENS DOSES AND PERSONAL DOSE EQUIVALENT MEASURED ON THE ARM OF INTERVENTIONAL CARDIOLOGISTS FOR A RETROSPECTIVE ASSESSMENT OF DOSES TO OPERATORS’ EYE LENS“. Radiation Protection Dosimetry 189, Nr. 3 (01.04.2020): 271–78. http://dx.doi.org/10.1093/rpd/ncaa039.

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Abstract Coefficients converting the readings of the whole body dosemeter worn on the left arm to eye lens doses were determined by analysing the correlations between Hp(10) and Hp(3) values. Doses were measured on a phantom for specific C-arm projections typically used during CA/PCI procedures. In order to estimate the cumulative eye lens doses, conversion coefficients were then applied to the dose records of interventional cardiologists collected in the database of dosimetry service between the years 1995 and 2009. The Hp(10) to Hp(3) conversion coefficients are 0.29 (CV = 34%) and 0.17 (CV = 42%) for left and right eye lens, respectively. However, they can vary from one laboratory to another depending on working technique. From among 61 interventional cardiologists, none exceeded the threshold dose of 0.5 Gy for eye lens opacities. However, 44% of interventional cardiologists were likely to exceed the annual limit of 20 mSv for the most exposed eye at least once in the analysed time period.

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35

Krins, A., J. Fidorra, U. Pleiß, P. Sahre und T. Schönmuth. „Biokinetic model for the calculation of dose coefficients for oral and intravenous administration of ¹⁴C labeled drugs“. Kerntechnik 68, Nr. 5-6 (01.10.2003): 205–13. http://dx.doi.org/10.1515/kern-2003-0083.

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Abstract A first order biokinetic model is presented for the calculation of dose coefficients from human activity excretion data after intravenous and oral administration of 14C labeled drugs. It is intended for the dose estimation in human studies in drug research, where the number of measurements is low and their uncertainty rather high. The model depends on only 6 parameters that are to be adjusted with the help of the measurement data. A comparison of measured and calculated activities in excreta of four human studies on 14C labeled drugs revealed considerable agreement, although some limitations have to be accepted. In contrast to the biokinetic model for 14C in organic compounds recommended by the International Commission on Radiological Protection (ICRP) the present model does not assume a fixed biological half-life of 40 days, but follows the experimental data. In consequence, the resulting dose coefficients differ from the ICRP value. For experimental data tested and assuming uniform activity distribution, the committed effective doses amount between one twenty-fifth to one fiftieth of the values calculated from the ICRP model. The uncertainty of the derived dose coefficients is estimated to be about ± 50%.

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36

Spielmann, Vladimir, Wei Bo Li, Maria Zankl, Juan Camilo Ocampo Ramos und Nina Petoussi-Henss. „Uncertainty analysis in internal dose calculations for cerium considering the uncertainties of biokinetic parameters and S values“. Radiation and Environmental Biophysics 59, Nr. 4 (20.09.2020): 663–82. http://dx.doi.org/10.1007/s00411-020-00872-9.

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Abstract Radioactive cerium and other lanthanides can be transported through the aquatic system into foodstuffs and then be incorporated by humans. Information on the uncertainty of reported dose coefficients for exposed members of the public is then needed for risk analysis. In this study, uncertainties of dose coefficients due to the ingestion of the radionuclides 141Ce and 144Ce were estimated. According to the schema of internal dose calculation, a general statistical method based on the propagation of uncertainty was developed. The method takes into account the uncertainties contributed by the biokinetic models and by the so-called S values. These S-values were derived by using Monte Carlo radiation transport simulations with five adult non-reference voxel computational phantoms that have been developed at Helmholtz Zentrum München, Germany. Random and Latin hypercube sampling techniques were applied to sample parameters of biokinetic models and S values. The uncertainty factors, expressed as the square root of the 97.5th and 2.5th percentile ratios, for organ equivalent dose coefficients of 141Ce were found to be in the range of 1.2–5.1 and for 144Ce in the range of 1.2–7.4. The uncertainty factor of the detriment-weighted dose coefficient for 141Ce is 2.5 and for 144Ce 3.9. It is concluded that a general statistical method for calculating the uncertainty of dose coefficients was developed and applied to the lanthanide cerium. The dose uncertainties obtained provide improved dose coefficients for radiation risk analysis of humans. Furthermore, these uncertainties can be used to identify those parameters most important in internal dose calculations by applying sensitivity analyses.

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37

Isaksson, Mats, Martin Tondel, Robert Wålinder und Christopher Rääf. „Absorbed dose rate coefficients for ¹³⁴Cs and ¹³⁷Cs with steady-state distribution in the human body: S-coefficients revisited“. Journal of Radiological Protection 41, Nr. 4 (24.11.2021): 1213–27. http://dx.doi.org/10.1088/1361-6498/ac2ec4.

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Abstract In the event of an accidental release of radioactive elements from a nuclear power plant, it has been shown that the radionuclides contributing the most to long-term exposure are 134Cs and 137Cs. In the case of nuclear power plant fallout, with subsequent intake of radionuclides through the food chain, the internal absorbed dose to target tissues from protracted intake of radionuclides needs to be estimated. Internal contamination from food consumption is not caused by a single intake event; hence, the committed equivalent dose, calculated by a dose coefficient or dose per content function, cannot be easily used to calculate the cumulative absorbed dose to relevant target tissues in the body. In this study, we calculated updated absorbed dose rate coefficients for 134Cs and 137Cs based on data from the International Commission on Radiological Protection (ICRP) on specific absorbed fractions. The absorbed dose rate coefficients are provided for male and female adult reference phantoms, respectively, assuming a steady-state distribution of Cs that we calculated from the ICRP biokinetic model for Cs. With these coefficients, the absorbed dose to the listed target tissues, separately and to the total body, are related to the number of nuclear transitions (time-integrated activity) in each listed source region. Our new absorbed dose rate coefficients are given for the complete set of target tissues and have not been presented before. They are also provided for aggregated categories of organs to facilitate epidemiological studies.

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38

van Dillen, Teun, Arjan van Dijk, Astrid Kloosterman, Federica Russo und Chantal Mommaert. „Accounting for ingrowth of radioactive progeny in dose assessments: generic weighting factors for dose coefficients“. Journal of Radiological Protection 40, Nr. 1 (11.12.2019): 83–118. http://dx.doi.org/10.1088/1361-6498/ab3e9b.

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39

Kim, Sora, Byung-Il Min, Kihyun Park, Byung-Mo Yang und Kyung-Suk Suh. „The System of Radiation Dose Assessment and Dose Conversion Coefficients in the ICRP and FGR“. Journal of Radiation Protection and Research 41, Nr. 4 (31.12.2016): 424–35. http://dx.doi.org/10.14407/jrpr.2016.41.4.424.

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40

Zankl, M., U. Fill, C. Hoeschen, W. Panzer und D. Regulla. „Average glandular dose conversion coefficients for segmented breast voxel models“. Radiation Protection Dosimetry 114, Nr. 1-3 (17.05.2005): 410–14. http://dx.doi.org/10.1093/rpd/nch513.

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41

Alghamdi, A. A., A. Ma, M. Tzortzis und N. M. Spyrou. „Neutron-fluence-to-dose conversion coefficients in an anthropomorphic phantom“. Radiation Protection Dosimetry 115, Nr. 1-4 (20.12.2005): 606–11. http://dx.doi.org/10.1093/rpd/nci268.

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42

Veinot, K. G., und N. E. Hertel. „Personal dose equivalent conversion coefficients for photons to 1 GeV“. Radiation Protection Dosimetry 145, Nr. 1 (08.12.2010): 28–35. http://dx.doi.org/10.1093/rpd/ncq380.

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43

Karavasilis, E., A. Dimitriadis, H. Gonis, P. Pappas, E. Georgiou und E. Yakoumakis. „DOSE COEFFICIENTS FOR LIVER CHEMOEMBOLISATION PROCEDURES USING MONTE CARLO CODE“. Radiation Protection Dosimetry 172, Nr. 4 (08.12.2015): 409–15. http://dx.doi.org/10.1093/rpd/ncv492.

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44

Romanyukha, Anna, Les Folio, Stephanie Lamart, Steven L. Simon und Choonsik Lee. „BODY SIZE-SPECIFIC EFFECTIVE DOSE CONVERSION COEFFICIENTS FOR CT SCANS“. Radiation Protection Dosimetry 172, Nr. 4 (10.01.2016): 428–37. http://dx.doi.org/10.1093/rpd/ncv511.

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45

Moussa, Hanna M., und Mark A. Melanson. „Translation of Dose Coefficients From ICRP 53 to ICRP 80“. Health Physics 104, Nr. 2 (Februar 2013): 224–26. http://dx.doi.org/10.1097/hp.0b013e3182758035.

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46

Leggett, Richard, Patricia Scofield und Keith Eckerman. „Basis and Implications of the CAP88 Age-Specific Dose Coefficients“. Health Physics 105 (August 2013): S149—S157. http://dx.doi.org/10.1097/hp.0b013e3182904db1.

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47

Suzuki, K., H. Sekimoto und N. Ishigure. „Dependence of Dose Coefficients for Inhaled 239Pu on Absorption Parameters“. Radiation Protection Dosimetry 93, Nr. 3 (01.02.2001): 267–69. http://dx.doi.org/10.1093/oxfordjournals.rpd.a006438.

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48

Suzuki, K., H. Sekimoto und N. Ishigure. „Sensitivity Analysis of Dose Coefficients for 239Pu to Transfer Rates“. Radiation Protection Dosimetry 88, Nr. 3 (01.04.2000): 197–208. http://dx.doi.org/10.1093/oxfordjournals.rpd.a033037.

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49

Chen, J., D. Meyerhof und S. Vlahovich. „Neutron fluence-to-dose conversion coefficients for embryo and fetus“. Radiation Protection Dosimetry 110, Nr. 1-4 (01.08.2004): 693–98. http://dx.doi.org/10.1093/rpd/nch176.

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50

Yu, K. N., T. T. K. Cheung, A. K. M. M. Haque, D. Nikezic, B. M. F. Lau und D. Vucic. „Radon progeny dose conversion coefficients for Chinese males and females“. Journal of Environmental Radioactivity 56, Nr. 3 (Januar 2001): 327–40. http://dx.doi.org/10.1016/s0265-931x(00)00204-6.

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Zeitschriftenartikel zum Thema „Dose coefficients“

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