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1

Bernat, P., PP Vistoli, and S. Camaro. "Étude du comportement à long terme des déchets radioactifs. Utilisation du code de calcul Mercure IV pour la détermination du débit de dose gamma dans des échantillons de grandes tailles." Journal de Chimie Physique 93 (1996): 12–15. http://dx.doi.org/10.1051/jcp/1996930012.

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2

Cosset, J. M., and C. Haie-Meder. "Curiethérapie du cancer prostatique : haut débit ou bas débit de dose ?" Cancer/Radiothérapie 9, no. 8 (2005): 610–19. http://dx.doi.org/10.1016/j.canrad.2005.09.019.

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3

Nickers, P., P. Blanchard, J. M. Hannoun-Lévi, A. Bossi, O. Chapet, and S. Guérif. "Curiethérapie prostatique de haut débit de dose." Cancer/Radiothérapie 17, no. 2 (2013): 118–24. http://dx.doi.org/10.1016/j.canrad.2013.02.005.

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4

Fouillade, Charles, Vincent Favaudon, Marie-Catherine Vozenin, et al. "Les promesses du haut débit de dose en radiothérapie." Bulletin du Cancer 104, no. 4 (2017): 380–84. http://dx.doi.org/10.1016/j.bulcan.2017.01.012.

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5

Métayer, Y., P. Meyer, C. Brunaud, and D. Peiffert. "Contrôle de qualité en curiethérapie de débit de dose pulsé." Cancer/Radiothérapie 13, no. 4 (2009): 318–22. http://dx.doi.org/10.1016/j.canrad.2009.02.005.

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6

Peiffert, D., D. Spaeth, O. Menard, and J. Winnefeld. "La curiethérapie endobronchique de haut débit de dose: un traitement curatif." Cancer/Radiothérapie 4, no. 3 (2000): 197–201. http://dx.doi.org/10.1016/s1278-3218(00)89094-0.

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7

Charra-Brunaud, C., D. Peiffert, S. Hoffstetter, C. Marchai, V. Beckendorf, and P. Bey. "Curiethérapie postopératoire à bas débit de dose des adénocarcinomes de ï'endomètre." Bulletin du Cancer/Radiothérapie 83, no. 4 (1996): 422. http://dx.doi.org/10.1016/s0924-4212(97)86127-0.

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8

Le Bourhis, J., J. F. Moreira, V. Chassin, D. Donnarieix, and M. Lapeyre. "Curiethérapie interstitielle de débit pulsé ORL : utilisation des histogrammes dose–volume." Cancer/Radiothérapie 15, no. 6-7 (2011): 562. http://dx.doi.org/10.1016/j.canrad.2011.07.008.

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9

Bernadou, G., I. Barillot, A. Régnault-Bougnoux, G. Calais, S. Chapet, and A. Ruffier-Loubière. "Analyse comparative de la toxicité tardive de la curiethérapie de haut débit de dose et de celle de bas débit de dose du cancer de l’endomètre." Cancer/Radiothérapie 19, no. 6-7 (2015): 685–86. http://dx.doi.org/10.1016/j.canrad.2015.07.121.

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10

Charra-Brunaud, C., D. Peiffert, S. Hoffstetter, E. Luporsi, F. Guillemin, and P. Bey. "Curiethérapie vaginale postopératoire des adénocarcinomes de l'endomètre à bas débit de dose." Cancer/Radiothérapie 2, no. 1 (1998): 34–41. http://dx.doi.org/10.1016/s1278-3218(98)89059-8.

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11

Wdowczyk, D., P. Joffroy, and T. Pangrazzi. "Curiethérapie de prostate de haut débit de dose : descriptif des outils dosimétriques." Cancer/Radiothérapie 13, no. 6-7 (2009): 685–86. http://dx.doi.org/10.1016/j.canrad.2009.08.110.

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12

Reygagne Viera, E., V. Huguier, O. Boissonade, et al. "Curiethérapie de haut débit de dose multifractionnée des cicatrices chéloïdes : expérience préliminaire." Cancer/Radiothérapie 18, no. 5-6 (2014): 636. http://dx.doi.org/10.1016/j.canrad.2014.07.140.

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13

Hansen, Joyce M., Niki Fidopiastis, Trabue Bryans, Michelle Luebke, and Terri Rymer. "Radiation Sterilization: Dose Is Dose." Biomedical Instrumentation & Technology 54, s1 (2020): 45–52. http://dx.doi.org/10.2345/0899-8205-54.s3.45.

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Abstract In the radiation sterilization arena, the question often arises as to whether radiation resistance of microorganisms might be affected by the energy level of the radiation source and the rate of the dose delivered (kGy/time). The basis for the question is if the microbial lethality is affected by the radiation energy level and/or the rate the dose is delivered, then the ability to transfer dose among different radiation sources could be challenged. This study addressed that question by performing a microbial inactivation study using two radiation sources (gamma and electron beam [E-beam]), two microbial challenges (natural product bioburden and biological indicators), and four dose rates delivered by three energy levels (1.17 MeV [gamma], 1.33 MeV [gamma], and 10 MeV [high-energy E-beam]). Based on analysis of the data, no significant differences were seen in the rate of microbial lethality across the range of radiation energies evaluated. In summary, as long as proof exists that the specified dose is delivered, dose is dose.
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14

Taulelle, M., B. Chauvet, P. Vincent, et al. "Curiethérapie endobronchique à haut débit de dose : résultats et complications chez 189 patients." Bulletin du Cancer/Radiothérapie 83, no. 3 (1996): 127–34. http://dx.doi.org/10.1016/0924-4212(96)81744-0.

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15

Favaudon, V. "Radiothérapie flash à très haut débit de dose : point sur les avancées récentes." Cancer/Radiothérapie 23, no. 6-7 (2019): 674–76. http://dx.doi.org/10.1016/j.canrad.2019.07.127.

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16

Low, Daniel A. "Gamma Dose Distribution Evaluation Tool." Journal of Physics: Conference Series 250 (November 1, 2010): 012071. http://dx.doi.org/10.1088/1742-6596/250/1/012071.

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17

Leclerc, M., C. Béchade, P. Henri, et al. "Le débit de la pompe à sang n’a que peu d’impact sur la dose de dialyse en hémodialyse quotidienne à bas débit de dialysat." Néphrologie & Thérapeutique 12, no. 5 (2016): 327. http://dx.doi.org/10.1016/j.nephro.2016.07.095.

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18

Omori, Y., S. Inoue, T. Otsuka, Y. Nagamatsu, A. Sorimachi, and T. Ishikawa. "REDUCTION IN AMBIENT GAMMA DOSE RATE FROM RADIOCESIUM DUE TO SNOW COVER." Radiation Protection Dosimetry 184, no. 3-4 (2019): 510–13. http://dx.doi.org/10.1093/rpd/ncz091.

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Abstract In the present study, variations in ambient gamma dose rate associated with snow cover were examined in a radioactive-contaminated site in Fukushima Prefecture, Japan. The ambient gamma dose rates decreased with increasing snow depth. The reduction trends were different between fresh snow (0.1–0.2 g/cm3) and granular snow (0.3–0.4 g/cm3) depending on snow density. Snow cover water content (snow water equivalent) calculated from snow depth and density was a key parameter governing the reduction in the ambient gamma dose rate. The ambient gamma dose rates reduced to 0.6 and 0.5 at 4 g/cm2 and 8 g/cm2 of snow water equivalent, respectively. Based on gamma-ray flux density distributions, the ambient gamma dose rates from the primary gamma rays decreased more compared to those from scattered gamma rays due to snow cover.
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19

Kochbati, L., H. Marsiglia, P. Baldeyrou, et al. "Curiethérapie à haut débit de dose (CHDD) à visée palliative dans les cancers bronchiques." Bulletin du Cancer/Radiothérapie 83, no. 4 (1996): 424. http://dx.doi.org/10.1016/s0924-4212(97)86134-8.

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20

-Ferlet-Cavrois, Véronique. "Simulation de l'effet du débit de dose sur des transistors MOS en technologie SOI." Revue de l'Electricité et de l'Electronique -, no. 04 (1997): 83. http://dx.doi.org/10.3845/ree.1997.053.

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21

Moreau-Claeys, M. V., C. Brunaud, S. Hoffstetter, I. Buchheit, and D. Peiffert. "Curiethérapie postopératoire du fond vaginal de haut débit de dose dans le cancer endométrial." Cancer/Radiothérapie 15, no. 3 (2011): 169–75. http://dx.doi.org/10.1016/j.canrad.2010.09.002.

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22

Mazeron, R., I. Dumas, V. Martin, et al. "Curiethérapie de débit de dose pulsé dans les cancers du col utérin : pourquoi, comment ?" Cancer/Radiothérapie 18, no. 5-6 (2014): 447–51. http://dx.doi.org/10.1016/j.canrad.2014.06.010.

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23

Roussille, P., B. Roullet, O. Boissonnade, et al. "Curiethérapie de haut débit de dose, anale, multifractionnée : évaluation préliminaire de la réponse clinique." Cancer/Radiothérapie 19, no. 6-7 (2015): 681–82. http://dx.doi.org/10.1016/j.canrad.2015.07.112.

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24

Marchal, C., C. Corbice, and C. Marchal. "Installation d’un projecteur de curiethérapie de haut débit de dose dans un bunker d’accélérateur." Cancer/Radiothérapie 19, no. 6-7 (2015): 695–96. http://dx.doi.org/10.1016/j.canrad.2015.07.146.

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25

Benabid, D., D. Brune, F. Lesaunier, JC Vernhes, B. Mauger, and JF Tranchant. "P61 La curiethérapie endocavitaire vaginale à bas débit de dose (BDD), et la curiethérapie à haut débit de dose (HDD), dans le cancer de l'endomètre: expérience du centre Francois-Baclesse de Caen." Cancer/Radiothérapie 2, no. 5 (1998): 633. http://dx.doi.org/10.1016/s1278-3218(98)80134-0.

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26

Omori, Yasutaka, Takuma Ishikawa, Atsuyuki Sorimachi, and Tetsuo Ishikawa. "DISTRIBUTIONS OF INDOOR GAMMA DOSE RATES IN RELATION TO GAMMA-RAY EMISSIONS FROM BUILDING MATERIALS: CASE STUDY OF HIGH-RISE CONCRETE BUILDING IN FUKUSHIMA." Radiation Protection Dosimetry 184, no. 1 (2018): 116–26. http://dx.doi.org/10.1093/rpd/ncy192.

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Abstract The spatial distribution of ambient gamma dose rates in a high-rise steel-reinforced concrete building in Fukushima, Japan, was examined relative to the gamma-ray emissions from building materials and radionuclides derived from the 2011 nuclear accident. The results revealed the minor role of accident-derived radionuclides in ambient gamma dose rates ~7 y after the accident. The ambient gamma dose rates were higher in the upper floors because of gamma-ray emissions from natural radionuclides in the floor slabs. The fractional contribution of natural radionuclides to the ambient gamma dose rates indicated compositional differences in concrete between the upper- and lower-floor slabs.
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27

Sarradin, M., I. Troussier, C. Évrard, et al. "Escalade de dose focale sur l’indice tumoral par curiethérapie de haut débit de dose associée et radiothérapie tridimensionnelle conformationnelle." Cancer/Radiothérapie 19, no. 6-7 (2015): 671–72. http://dx.doi.org/10.1016/j.canrad.2015.07.087.

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28

Saini, H. K., and M. I. S. Gill. "Induction of Mutation in Rough Lemon (Citrus jambhiri Lush.) Using Gamma Rays." Journal of Horticultural Sciences 4, no. 1 (2009): 41–44. http://dx.doi.org/10.24154/jhs.v4i1.554.

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The present investigation was carried out to study variability induced by gamma rays with respect to vegetative characters and LD50 dose in Rough lemon. Rough lemon seeds were gamma irradiated at doses of 0, 4, 6 and 8 kr along with control. Seed germination decreased with increasing dose of gamma radiation. Seedling height and leaf size also decreased with increasing dose of gamma radiation, whereas, apical branching, number of branches/seedling, number of variegated / albino seedlings and number of leaves increased with increasing dose of gamma radiation. Maximum variability for seedling height, number of leaves, leaf size, colour, internode length, and per cent apical branching was observed at two months from sowing in seeds treated with 8 kr dose of gamma radiation. Variability for all characters was, however, found to be minimum in the control.
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29

Omori, Yasutaka, Atsuyuki Sorimachi, Manlaijav Gun-Aajav, et al. "ELEVATION OF GAMMA DOSE RATE BY CONSTRUCTION OF THE ASIAN HIGHWAY 3 (AH3) BETWEEN ULAANBAATAR AND SAINSHAND, MONGOLIA." Radiation Protection Dosimetry 184, no. 1 (2018): 127–34. http://dx.doi.org/10.1093/rpd/ncy173.

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Abstract The present study aimed at examining changes of gamma radiation level associated with road construction in Mongolia. A car-borne survey of gamma dose rate was made for a paved, ~450-km long part of the Asian Highway 3 between Ulaanbaatar and Sainshand. The gamma dose rates ranged from 48 to 173 nGy/h. Elevation of the gamma dose rates was observed only on a 86-km long segment of the survey route which was newly constructed from 2011 to 2013. The gamma dose rates over the newer paved segment were twice as high as those over the bare dirt surface alongside it. Outdoor measurements of gamma-ray pulse height distributions also indicated an abundance of natural radionuclides, especially 232Th-series elements in road materials. These findings suggest that the gamma dose rates were elevated by introduction of road materials containing large amounts of natural radionuclides.
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30

Waheeb, Ahmed H., Zeinab Eltaher, Mohamed N. Yassin, and Magdy M. Khalil. "Comparison between different Dosimetric Tools based on Intensity-modulated Radiotherapy (IMRT): A Phantom Study." NeuroQuantology 19, no. 11 (2021): 141–50. http://dx.doi.org/10.14704/nq.2021.19.11.nq21184.

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This study examined the gamma passing rate (GPR) consistency during applying different kinds of gamma analyses and dosimeters to IMRT. Methods: Import treatment protocols for QA phantom irradiation have been recalculated. A gamma analysis was used for comparing the measured and calculated dose distribution of IMRT for different gamma criteria (2%/2mm, 3%/3mm, 4%/4mm, 3%/5mm, 3%/5mm). These criteria are evaluated when 5%, 10%, or 15% of the dose distribution is suppressed. Measured and calculated dose distribution was evaluated with gamma analysis to dose difference (DD) with DTA criteria (distance to agreement). IMRT QA plans to 25 patients from various sites were formed with the Varian Eclipse treatment planning system. Results: Results indicate different diverse hardware and software combinations show varied levels of agreement with expected analysis for the same pass-rate criterion. For a dosimetry audit of the IMRT technique, an EPID detector is superior to conventional methods comparable to Gafchromic EPT3 film and 2D array due to cost, time-consuming, and set up error to get result analysis. The gamma passing rate (GPR) average is increased by increasing the low-dose threshold for different dosimetric tools. For EPID, regardless of the gamma criterion employed, the %GP does not appear to be dependent on the low-dose threshold values (5%-15%) because it indicates that fulfilment the low-dose threshold to global normalization has little effect on patient-specific QA outcomes. Conclusions: It is concluded that GPRs differ depending on gamma, dosimetric tools, and the suppressing dose ratio. To get the best results of quality assurance, each institution should thus carefully develop its procedure for gamma analysis by defining the gamma index analysis and gamma criterion using its dosimetric tools.
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31

Kulhar, Manjeet, Kashyap Dhoot, and Arun Pandya. "Gamma Dose Rate Measurement Using RadFET." IEEE Transactions on Nuclear Science 66, no. 10 (2019): 2220–28. http://dx.doi.org/10.1109/tns.2019.2942955.

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32

Aitken, M. J., and J. Xie. "Moisture correction for annual gamma dose." Ancient TL 8, no. 2 (1990): 6–9. https://doi.org/10.26034/la.atl.1990.157.

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33

Shamshad, A., M. Rashid, and A. Husain. "High gamma dose dosimetry by polycarbonates." Radiation Physics and Chemistry 50, no. 3 (1997): 307–11. http://dx.doi.org/10.1016/s0969-806x(97)00038-8.

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34

Wahjuningrum, Dian Agustin, Setyabudi Setyabudi, Darmawan Darwis, and Andi Syahrimayani. "Determination of gamma radiation sterilization dose on bioceramic BCP-Sr-Ag as bone graft according to ISO 11137 standards." Conservative Dentistry Journal 13, no. 1 (2023): 19–23. http://dx.doi.org/10.20473/cdj.v13i1.2023.19-23.

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Background: BCP-Sr-Ag as a bone graft needs to be sterilized. One way of sterilization is to use gamma radiation. Sterilization by gamma radiation requires the correct sterilization dose. Based on ISO 11137 the determination of the sterilization dose through 3 steps: determination bioburden, determination of verification dose, and determination of sterilization dose. Purpose:Determination of gamma radiation sterilization dose on BCP-Sr-Ag bioceramic as bone graft based on ISO 11137 through determination bioburden, determination verification dose, and determination of sterilization dose. Method: A total 30 samples of 3 different batch BCP-Sr-Ag were determined for bioburden using TSA media. A total 100 samples of BCP-Sr-Ag were irradiated with a verification dose using cobalt-60 gamma source. The 100 samples then tested for sterilization using TSA media to determine the sterilization dose. Results: The average bioburden values of batches 1,2, and 3 were 56,8;61,8; and 60,5 CFU. The average value of the whole batch is 59,7 CFU. Based on ISO 11137, the verification dose is 7,4 kGy and the sterilization dose is 20,5 kGy. Conclusion: The average bioburden value of the entire batch was 59,7 CFU. The bioburden value used for verification dose determination is 64,22 CFU so the the gamma radiation sterilization dose is 20,5 kGy.
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35

Alves, Carlos, and Jorge Sanjurjo-Sánchez. "An Overview of Radiological Hazards Related to Geological External Gamma Radiation in Outdoor Environments." Proceedings 2, no. 10 (2018): 562. http://dx.doi.org/10.3390/iecg_2018-05337.

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Rocks and soils are an important source of external gamma radiation due to their content in U, Th, and K. The dose rate derived from the emission of gamma-rays of radioisotopes can be directly measured or assessed from their content. In the present study, values of outdoor gamma radiation absorbed dose rate are analyzed to explore the implications of levels related to those values in terms of the exposure time necessary for attaining a certain yearly effective dose. We propose simple relations with the absorbed dose rate and with the gamma index of materials.
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36

KARATEPE ÇELİK, Şule, and Sultan ŞAHİN BAL. "Environmental Gamma Dose Measurement in Arin Lake (Bitlis)." Karadeniz Fen Bilimleri Dergisi 13, no. 4 (2023): 1729–37. http://dx.doi.org/10.31466/kfbd.1332646.

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Arin Lake is a stopover for many migratory bird species, mostly flamingos and songbirds.The assignment of gamma dose rate is very important for the air quality of an environment and human health. For this purpose, the environmental gamma radiation dose rate in air was measured for 27 different point in Arin Lake area in Bitlis province. Measurements were conducted using a portable gamma survey meter supplied with a NaI(Tl) scintillation detector. Gamma dose values were measured in the range 0.035 - 0.165 μSv/h for ground level with mean 0.117 μSv/h. Similarly gamma dose values for 1 m above the ground were measured in the range 0.027 - 0.150 μSv/h with mean 0.104 μSv/h.
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37

Top, Gülcan, Yüksel Örgün, Gürsel Karahan, Mark Horvath, and Györgyi Kampfl. "EFFECTS OF LOCAL BUILDING MATERIALS ON INDOOR GAMMA DOSES AND RELATED RADIOLOGICAL HEALTH RISKS, AYVACIK, ÇANAKKALE/TURKEY." Radiation Protection Dosimetry 190, no. 1 (2020): 108–17. http://dx.doi.org/10.1093/rpd/ncaa086.

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Abstract In situ indoor gamma dose rate measurements were held in 79 dwellings by NaI(Tl) scintillation probe connected portable dose rate meter. For the building materials and impurities (nodules), spectrometric gamma analysis was applied by a high-resolution HpGe detector. For Ahmetçe and Nusratlı villages in Ayvacik/Çanakkale (Turkey), the measured in situ indoor gamma dose rates and related indoor annual effective dose equivalents (AEDEin) were 3 and 3.3 times, and indoor excess lifetime cancer risks (ELCRin) were 4.25 and 4.68 times higher than those of the world averages, respectively. The used local rocks were mostly ignimbrite and dacitic–rhyolitic tuffaceous (Arıklı tuff), and wall plasters were made of local soil. The highest in situ indoor gamma dose rates of the region belonged to Nusratlı village due to the intense impurities (nodules) and hydrothermal alterations in Arıklı tuff. Spectrometric gamma results revealed that 40K has an important effect on the indoor gamma doses.
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38

Gromov, Alexander A., Alexander P. Zhanzhora, and Vladimir F. Shikalov. "Certification of a specialized source of gamma radiation spatially combined with modeling reference field of neutron radiation." Izmeritel`naya Tekhnika, no. 3 (2021): 53–57. http://dx.doi.org/10.32446/0368-1025it.2021-3-53-57.

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The results of metrological studies of the field of the experimental channel of the research nuclear reactor OR (experimental base of the NRC “Kurchatov Institute”) with a capacity of 0.1–300 kW are presented. The empirical dependence of the contribution of the absorbed dose of gamma radiation during the raising and lowering reactor power in the total absorbed dose during the irradiation in the reactor and absorbed dose rate from a power reactor OR in the steady state. Based on these results, the absorbed dose and absorbed dose rate of gamma radiation can be pre-calculated. According to metrological studies results, the experimental channel of the reactor OR was certified in terms of the absorbed dose rate of gamma radiation as a specialized source of gamma radiation spatially combined with the modeling reference field of neutrons. The specialized source is designed for calibration of special-purpose measuring instruments and testing for radiation resistance of products operating in conditions of mixed gamma-neutron radiation of nuclear reactors.
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39

Trihi, M., JL Duroux, MJ Hyvernaud, and M. Bernard. "Dosimétrie à haut débit de dose : mise au point d'un « chronodosimètre » à base de PMMA." Journal de Chimie Physique 93 (1996): 231–34. http://dx.doi.org/10.1051/jcp/1996930231.

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40

Ma, Lijun, Lynn Verhey, Cynthia Chuang, et al. "Effect of composite sector collimation on average dose fall-off for Gamma Knife Perfexion." Journal of Neurosurgery 109, Supplement (2008): 15–20. http://dx.doi.org/10.3171/jns/2008/109/12/s4.

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Object The new capability of composite sector collimation in Gamma Knife Perfexion produces complex, nonspherical, and nonelliptical dose distributions. In this study, the authors investigated the effect of composite sector collimation on average dose fall-off compared with the previous Gamma Knife model. Methods A general formalism was derived to describe the peripheral dose distribution of all Gamma Knife models in the form of (V/V0) = (D/D0)γ, where V is the volume of the peripheral isodose line with the value of D, V0 is the reference prescription isodose volume, D0 is the prescription dose, and γ is the fitting parameter that determines how fast the dose falls off near the target. Based on this formula, the authors compared 40 cases involving patients treated with Gamma Knife Perfexion with 40 similar cases involving patients treated with Gamma Knife model 4C. The cases were grouped based on the use of the sector collimators in the treatment planning process. For each group as well as all cases combined, the mean γ values were compared by means of the Student t-test for varying ranges of the peripheral dose distribution—from 100% of the prescription dose to 75, 50, and 25% of the prescription dose. Results The fit of general formula to the data was excellent for both Gamma Knife Perfexion and Gamma Knife 4C with R2> 0.99 for all the cases. The overall γ values (mean ± 2 standard deviations) were as follows: γ = −1.74 ± 0.47 (Model 4C) versus −1.77 ± 0.40 (Perfexion) within 100–75% of the prescription dose; γ = −1.57 ± 0.26 (Model 4C) versus −1.58 ± 0.25 (Perfexion) within 100–50% of the prescription dose; γ = −1.47 ± 0.18 (Model 4C) versus −1.50 ± 0.16 (Perfexion) within 100–25% of the prescription dose. No statistical significance between the mean differences for Gamma Knife Perfexion and Model 4C was found within these ranges. The probability values were 0.65, 0.84, and 0.22, respectively. Conclusions The use of composite sector collimators in Gamma Knife Perfexion demonstrated no statistically significant effects on the volume-averaged dose fall-off near a target periphery for typical treatment cases.
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41

Saleh, Muneer Aziz, Ahmad Termizi Ramli, Khaidzir Bin Hamzah, et al. "In situ measurement of terrestrial gamma dose rates in eastern region of Peninsular Malaysia and its relation to geological formation and soil types." Radiochimica Acta 107, no. 6 (2019): 503–16. http://dx.doi.org/10.1515/ract-2018-2950.

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Abstract This present study aims to obtain baseline data of environmental terrestrial radiation and to assess the corresponding health risk in the ambient environment in eastern region of Peninsular Malaysia. The measurements were taken 1 m above the soil surface using NaI [Ti] detector with a total of 2144 measured points which covered all geological formations and soil types. The measured gamma dose rates ranged from 26 nGy h−1 to 750 nGy h−1 with a mean value of 172±90 nGy h−1. The mean gamma dose rate is three times higher than world averages of 57 nGy h−1. The data of gamma dose rates show the reading of the gamma dose rates not fit to the normal distribution. The variations of gamma dose rates based on geological formation and soil types were investigated using the unbalanced one way ANOVA. The results indicated strong significant differences due to the different geological formations and soil types. The T-test of gamma dose rates for each pair of soil types or geological formations and their hypothesis test at 95 % confidential level were compared to shows the significant difference between each pairs. The results indicate that the gamma dose rates for all pairs of soil types were significant differed except the miscellaneous soil while the gamma dose rates of the pairs of geological formation were also significant differed except the intermediate and intrusive geological formations. Acid intrusive and intermediate intrusive geological formations has the highest mean values of 223 nGy h−1 and 278 nGy h−1, respectively. These values are approximately four and five times the world average. Soil type (Steep land) has the highest gamma dose rate with the mean value of 215 nGy h−1. The radiological health information which are the total annual effective dose equivalent, the collective effective dose, lifetime effective dose and the lifetime cancer risk for each person are 0.844 mSv, 3.53×103 man Sv y−1, 59.10 mSv and 3.25×10−3, respectively. The results in eastern region of Peninsular Malaysia were comparable to different areas in Malaysia, which indicate the value reported in UNSCEAR, 2000 should be adjusted to the current status in Malaysia.
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42

Biagtan, E., E. Goldberg, R. Stephens, E. Valeroso, and J. Harmon. "Gamma dose and dose rate effects on scintillator light output." Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms 108, no. 1-2 (1996): 125–28. http://dx.doi.org/10.1016/0168-583x(95)00874-8.

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43

Al-Azmi, Darwish. "Indoor Gamma Dose Rates In Kuwait Using Handheld Gamma-ray Spectrometer." Health Physics 111, no. 1 (2016): 11–16. http://dx.doi.org/10.1097/hp.0000000000000510.

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Sanzelle, S., H. Erramli, J. Faïn, and D. Miallier. "The assessment of gamma dose-rate by gamma-ray field spectrometer." International Journal of Radiation Applications and Instrumentation. Part D. Nuclear Tracks and Radiation Measurements 14, no. 1-2 (1988): 209–13. http://dx.doi.org/10.1016/1359-0189(88)90066-0.

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Kaur, Manpreet, Ajay Kumar, Rohit Mehra, and Rosaline Mishra. "Seasonal variation of indoor and outdoor gamma dose rates of Reasi district of Jammu and Kashmir." Nuclear Technology and Radiation Protection 33, no. 1 (2018): 106–11. http://dx.doi.org/10.2298/ntrp1801106k.

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In the present study, the indoor gamma dose rate has been studied seasonally and the outdoor gamma dose rate was also measured in and around the 24 dwellings of 10 villages of Reasi district of Jammu and Kashmir, India, at about one meter above the ground surfaces by using Dosimeter-Radiometer MKS-03 (SARAD). The study was carried out to assess the annual equivalent dose rate for the inhabitants of the dwellings. The survey was designed in such a way so as to obtain a uniform and representative distribution of measurements locations. The indoor to outdoor dose ratio was calculated as 1.8, which indicated that the indoor gamma dose rate as compared to outdoor gamma dose rate has elevated levels of radon exposure due to confined space and poor ventilation. The average indoor gamma dose rate for three seasons such as winter, summer, and rainy were 0.18 ? 0.02, 0.12 ? 0.03, and 0.15 ? 0.03 ?Svh-1, respectively. It was observed that the indoor gamma dose rate during the winter season is higher than those for rainy and summer seasons. The indoor and outdoor annual equivalent dose rate was also measured from the health hazard point of view and it varied from 771 ? 210 to 1402 ? 280 ?Svy-1 and 105 ? 53 to 315 ? 105 ?Svy-1. These results revealed that the outdoor equivalent dose rate levels in all of the locations were below the 1000 ?Svy-1 maximum permissible limit for the public set by International Commission on Radiological Protection, except the few locations of indoor equivalent dose rate.
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Obajdin, Nevena, Djeni Smilovic-Radojcic, David Rajlic, Manda Svabic-Kolacio, and Slaven Jurkovic. "Impact of stringent tolerance criteria on verification of absorbed dose distributions and evaluation through inhomogeneous media." Nuclear Technology and Radiation Protection 37, no. 2 (2022): 138–44. http://dx.doi.org/10.2298/ntrp2202138o.

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Advances of radiation delivery devices have increased the complexity of the radiation oncology treatments. Herewith, outcome of the treatment, as well as patient safety, strongly depend on the consistency of absorbed dose delivery. Both can be ensured by comprehensive system of verification of calculated absorbed dose distributions. Standard method is evaluation of calculated absorbed dose distribution according to gamma method, using a 2-D detector and a homogeneous phantom, to obtain measured dose distribution. Purpose of this research was to investigate the influence of tolerance criteria on gamma passing rate. Additionally, the agreement in heterogeneous phantom was analysed. Absorbed dose calculations were performed using systems Monaco and XiO. Detector with 1020 ionization chambers in homogeneous phantom and semi-anthropomorphic phantom was used for measurements. Absorbed dose distributions of around 3500 patients were analysed using gamma method. In homogeneous phantom, average gamma passing rates were within tolerance for 3 %/2 mm. For measurements in heterogeneous media, the highest average gamma passing rate was obtained for small volumes of medium treatment complexity (??=93.84%), while large volumes of treatment with low complexity yielded the lowest gamma passing rates (??= 83.22%).
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Rakotovao, L. O., Sidik Permana, R. H. Oetami, and Rasito. "Simulation of Neutron and Gamma Dose Rate of The TRIGA 2000 Reactor Using Monte Carlo Method." Journal of Physics: Conference Series 2328, no. 1 (2022): 012007. http://dx.doi.org/10.1088/1742-6596/2328/1/012007.

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Abstract The neutron and gamma radiation doses were calculated from the operation of the 1 MW TRIGA 2000 Reactor in a simulation using the Monte Carlo method with MCNPX and PHITS program. Simulation is done by modelling the geometry of the reactor component materials and running it on a computer. The radiation source in the form of a fission reaction in the reactor core has been simulated using MCNPX to produce a dose of neutron and gamma radiation in the TRIGA 2000 core. Attenuation of neutron and gamma radiation by the reactor building is simulated using the PHITS code so that the neutron and gamma dose rates are obtained on the source, y, and z from reactor core. Interpolation of dose rate curves on large material thicknesses was carried out with the TVL neutron and gamma values of the simulation results for each reactor material. The simulation results shows that the gamma neutron dose rate outside the TRIGA 2000 reactor building is still below the dose limit value for radiation workers.
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Ghiasi, Hosein, and Asghar Mesbahi. "Gantry orientation effect on the neutron and capture gamma ray dose equivalent at the maze entrance door in radiation therapy." Nuclear Technology and Radiation Protection 27, no. 1 (2012): 70–74. http://dx.doi.org/10.2298/ntrp1201070g.

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In the present study, the effect of gantry orientation on the photoneutron and capture gamma dose calculations for maze entrance door was evaluated. A typical radiation therapy room made of ordinary concrete was simulated using MCNPX Monte Carlo code. Gantry rotation was simulated at eight different angles around the isocenter. Both neutron and capture gamma dose vary considerably with gantry angle. The ratios of the maximum to the minimum values for neutron and capture gamma dose equivalents were 1.9 and 1.4, respectively. On the other hand, comparison of the Monte Carlo calculated mean value over all orientations with Monte Carlo calculated neutron and gamma dose showed that the Wu-McGinley method differed by 5% and 2%, respectively. However, for more conservative shielding calculations, factors of 1.6 and 1.3 should be applied to the calculated neutron and capture gamma doses at downward irradiation. Finally, it can be concluded that the gantry angle influences neutron and capture gamma dose at the maze entrance door and it should be taken into account in shielding considerations.
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49

Maraghechi, Borna, Jack Davis, Shyam Badu, Andre Fleck, Johnson Darko, and Ernest Osei. "Retrospective analysis of portal dosimetry pre-treatment quality assurance of prostate volumetric-modulated arc therapy (VMAT) plans." Journal of Radiotherapy in Practice 17, no. 1 (2017): 44–52. http://dx.doi.org/10.1017/s1460396917000486.

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AbstractBackgroundElectronic portal imaging device (EPID) offers high-resolution digital image that can be compared with a predicted portal dose image. A very common method to quantitatively compare a measured and calculated dose distribution that is routinely used for quality assurance (QA) of volumetric-modulated arc therapy (VMAT) and intensity-modulated radiation therapy treatment plans is the evaluation of the gamma index. The purpose of this work was to evaluate the gamma passing rate (%GP), maximum gamma (γmax), average gamma (γave), maximum dose difference (DDmax) and the average dose difference (DDave) for various regions of interest using Varian’s implementation of three absolute dose gamma calculation techniques of improved, local, and combined improved and local.Methods and materialsWe analyzed 232 portal dose images from 100 prostate cancer patients’ VMAT plans obtained using the Varian EPID on TrueBeam Linacs.ResultsOur data show that the %GP, γmax and γave depend on the gamma calculation method and the acceptance criteria. Higher %GP values were obtained compared with both our current institutional action level and the American Association of Physicists in Medicine Task Group 119 recommendations.ConclusionsThe results of this study can be used to establish stricter action levels for pre-treatment QA of prostate VMAT plans. A stricter 3%/3 mm improved gamma criterion with a passing rate of 97% or the 2%/2 mm improved gamma criterion with a passing rate of 95% can be achieved without additional measurements or configurations.
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Leontaris, F., A. Boziari, A. Clouvas, M. Kolovou, and J. Guilhot. "PROCEDURES TO MEASURE MEAN AMBIENT DOSE EQUIVALENT RATES USING ELECTRET ION CHAMBERS." Radiation Protection Dosimetry 190, no. 1 (2020): 6–21. http://dx.doi.org/10.1093/rpd/ncaa061.

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Abstract The capabilities of electret ion chambers (EICs) to measure mean ambient dose equivalent rates were investigated by performing both laboratory and field studies of their properties. First, EICs were ‘calibrated’ to measure ambient gamma dose equivalent in the Ionizing Calibration Laboratory of the Greek Atomic Energy Commission. The EICs were irradiated with different gamma photon energies and from different angles. Calibration factors were deduced (electret’s voltage drop due to irradiation in terms of ambient dose equivalent). In the field studies, EICs were installed at eight locations belonging to the Greek Early Warning System Network (which is based on Reuter-Stokes ionization chambers) for three periods, averaging 5 months each. In the same locations, in situ gamma spectrometry measurements were performed with portable germanium detectors. Gamma ambient dose equivalent rates were deduced by the in situ gamma spectrometry measurements and by soil sample analysis. The mean daily electret potential drop (in Volts) was compared with the mean daily ambient dose equivalent, measured with a portable HPGe detector and Reuter-Stokes high-pressure ionization chambers. From these measurements, ‘field’ calibration factors (electret’s voltage drop due to gamma radiation in terms of ambient dose equivalent) were deduced and found in very good agreement with the values deduced in Laboratory. The influence of cosmic radiation and the intrinsic voltage loss when performing long-term environmental gamma measurements with EICs, was estimated.
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