Journal articles: 'Radiation survey meter'

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Kadhim, Ali Kareem. "Calibration of ionization chamber survey meter." Iraqi Journal of Physics (IJP) 14, no. 29 (February 3, 2019): 198–208. http://dx.doi.org/10.30723/ijp.v14i29.236.

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Radiation measuring devices need to process calibration whichlose their sensitivity and the extent of the response and the amount ofstability under a changing conditions from time to time and thisperiod depends on the nature and use of field in which used devices.A comparison study was done to a (451P) (ionization chambersurvey meter) and this showed the variation of calibration factor infive different years. This study also displayed the concept ofradiation instrument calibration and necessity of every yearcalibration of them.In this project we used the five years calibration data for ionizationchamber survey meter model Inspector (451P) to get that the valuesof Calibration Factor (CF) and Response (1/CF). The value deviation(Δ%) of CFs for four years of calibration in comparison of CF for theyear 2007 are very high and the device under research is not good touse in field and reliable because the ionization chamber is verysensitive to humidity and must calibrate a year or less, or duringevery two years and must maintain carefully to reduce the discardedeffects to the measurements.

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IIDA, Haruzou, Takashi KAMATA, Katsunori WATAI, Hiro AMANO, and Yoshiyuki SHIRAKAWA. "Application of a Dynamic Prediction Survey Meter to 60Co Contamination Monitoring." RADIOISOTOPES 57, no. 11 (2008): 669–77. http://dx.doi.org/10.3769/radioisotopes.57.669.

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Zubair, H. T., R. Rifiat, Adebiyi Oresegun, F. Hamidi, J. Othman, M. D. Khairina, A. Basaif, S. A. Ibrahim, H. A. Abdul-Rashid, and D. A. Bradley. "Fiber optic coupled survey meter for NORM and low-level radioactivity monitoring." Radiation Physics and Chemistry 188 (November 2021): 109682. http://dx.doi.org/10.1016/j.radphyschem.2021.109682.

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Avdic, Senada, Beco Pehlivanovic, Mersad Music, and Alma Osmanovic. "Correlation analysis of gamma dose rate from natural radiation in the test field." Nuclear Technology and Radiation Protection 31, no. 3 (2016): 260–67. http://dx.doi.org/10.2298/ntrp1603260a.

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This paper deals with correlation analysis of gamma dose rate measured in the test field with the five distinctive soil samples from a few minefields in Federation of Bosnia and Herzegovina. The measurements of ambient dose equivalent rate, due to radionuclides present in each of the soil samples, were performed by the RADIAGEMTM 2000 portable survey meter, placed on the ground and 1m above the ground. The gamma spectrometric analysis of the same soil samples was carried out by GAMMA-RAD5 spectrometer. This study showed that there is a high correlation between the absorbed dose rate evaluated from soil radioactivity and the corresponding results obtained by the survey meter placed on the ground. Correlation analysis indicated that the survey meter, due to its narrow energy range, is not suitable for the examination of cosmic radiation contribution.

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Haq, M. Mohib-ul, Ghulam Mohammad Mir, Nazir Ahmad Khan, Mohammad Ashraf Teli, M. Maqbool Lone, Fir Afroz, Shoukat H. Khan, Tanveer A. Rather, and Aijaz Ahmad Khan. "Study of Radiation Safety Concerns in Departments of Diagnostic Radiology of various Hospitals of Kashmir valley." JMS SKIMS 13, no. 2 (December 17, 2010): 51–55. http://dx.doi.org/10.33883/jms.v13i2.48.

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BACKGROUND: A primary consideration in any radiographic procedure is to reduce the dose to the patient and the operator while still achieving the diagnostic goals. OBJECTIVE: To study the radiation exposure and protective measures in different units of various hospitals in Kashmir valley in compliance to recommendations from regulatory authorities. METHODS: Twenty-eight stationary X-ray units of various major hospitals of the Kashmir Valley were surveyed by the radiation safety group of SKIMS. Panoramic survey meter, Thyac-V survey meter-470A, Prima-7 digital survey meters were used for radiation exposure estimations. The radiation level measurements were carried out at different critical locations like control console, door and the corridor adjacent to the Diagnostic equipment and were compared with the standards of AERB and IAEA. RESULTS: Of the 28 stationary X-Ray units identified 21 were functional and surveyed. Seventy seven Radiation workers (Technicians) operating these units perform about 1335 diagnostic procedures daily on these units. Out of 21 X-ray units surveyed, 9 (42.86%) had dose rate at the control panel within the permissible limits and 12(57.14%) had exposure levels higher than permissible limits. The dose levels at the door and corridor were exceeding the permissible limits in all the units. Most of the radiation workers had no concept of radiation protective measures and did not use any personal radiation monitoring device like TLD (Thermo-luminescent dosimeter). CONCLUSIONS: To avoid radiation exposure, the radiation safety measures ought to be strictly followed which is possible by making the concerned authorities answerable and accountable. Also the radiation workers need to be made aware of hazards of radiation exposure, importance of using personnel monitoring devices and providing knowledge about the safety measures. (JMS 2010;13(2):51-55)

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M.A.A, Mashud, Hossain S.M.S, Hossain M.S, Razzaque M.A, and Islam M.S. "A First Response Microcontroller Based Digital Radiation Survey Meter Using Scintillation Detector." International Journal on Cybernetics & Informatics 3, no. 5 (October 31, 2014): 11–19. http://dx.doi.org/10.5121/ijci.2014.3502.

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Celeste, D., A. Curioni, A. Fazzi, M. Silari, and V. Varoli. "B-RAD: a radiation survey meter for operation in intense magnetic fields." Journal of Instrumentation 14, no. 05 (May 28, 2019): T05007. http://dx.doi.org/10.1088/1748-0221/14/05/t05007.

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Zhou, Bo, Taosheng Li, Yuhai Xu, Cunkui Gong, Qiang Yan, and Lei Li. "Study on method of dose estimation for the Dual-moderated neutron survey meter." Radiation Measurements 59 (December 2013): 81–83. http://dx.doi.org/10.1016/j.radmeas.2013.04.018.

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Balakrishnan, Dhanya, A. G. Umadevi, Jose P. Abraham, P. J. JoJo, M. Harikumar, and Sujata Radhakrishnan. "Assessment Of Natural Radioactivity Level And Radiation Hazard Parameters In The Terrestrial Environment Of Eloor Island, Kerala." International Journal of Fundamental Physical Sciences 5, no. 2 (June 30, 2015): 38–42. http://dx.doi.org/10.14331/ijfps.2015.330084.

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The present study is aimed at measuring the concentration of primordial radionuclides in the soil samples of Eloor Island, an industrial area in Ernakulum District and evaluating the radiation exposure to the local population. The ambient radiation exposure rate was measured using portable scintillometer survey meter and the activity concentration of 232Th, 238U and 40K in the soil samples were analyzed using (5×4)” NaI(Tl) gamma spectrometer. The exposure rate measured using survey meter varied from 63 nGyh-1 to 374 nGyh-1. The activity concentration of 232Th, 238U and 40K in soil samples ranged from 44.8 Bq kg-1 to 792.8 Bqkg-1 for 232Th, 8 Bqkg-1 to 445.5 Bqkg-1 for 238U and 129 Bqkg-1 to 1160.5 Bqkg-1 for 40K. Hence the absorbed gamma dose and radiation hazard indices due to natural environmental radiation was done. The study showed no significant impact due to the NORM Industries in the Eloor Industrial region.

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Takekawa, Shoichi, Yoshihiko Ueda, Yoshihiko Ueda, Yoshihiro Hiramatsu, Hirotsugu Munechika, and Fumio Shishido. "Imaging of Beta-Rays from Tissue Blocks with Thorotrast Deposition by Autoradiography using Fuji Computed Radiography." Jurnal Radiologi Indonesia 1, no. 2 (September 1, 2015): 58–64. http://dx.doi.org/10.33748/jradidn.v1i2.7.

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Background: Autoradiography of tissue with radioactive substance such as Thorotrast by Fuji Computed Radiography (FCR) has been available. We obtained autoradiographs from Thorotrast-deposited tissue by FCR. However, the nature of radiation from tissue with Thorotrast was not certain, because alpha particles are shielded by the plastic front of the FCR cassette. Therefore, we undertook investigation to clearly explain the nature of radiation from Thorotrast in case of autoradiography.Materials and Methods: Tissue blocks of liver and spleen with Thorotrast deposition were imaged by autoradiography using FCR, and radioactivity of tissue blocks was measured by a GM survey meter. Measurement was carried out by both with and without an aluminum plate between the tissue and the surface of GM survey meter to shield beta-rays.Results: Autoradiographs of the liver and spleen with Thorotrast were successful. It took only one day to obtain autoradiograph of the spleen, and 14 days for the liver. The radioactivity count decreased dramatically when an aluminum plate was inserted between the specimen and GM survey meter, but some radiation remained. The tissue blocks were contained in a plastic bag and the front of the Cassette of Imaging Plate is covered by a thin plastic board, so alpha-rays from Thorium dioxide in Thorotrast had been shielded from the beginning.Conclusion: We concluded that the radiation from the tissue blocks with Thorotrast in a plastic bag was mostly from beta-rays and less than 5% of radiation was from gamma-rays from the daughter nuclei of Thorium dioxide.

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Avdic, Senada, Izet Gazdic, Mersad Music, and Beco Pehlivanovic. "Assessment of a relative contribution of terrestrial background radiation in the test field by using RADIAGEMTM 2000 portable survey meter." Nuclear Technology and Radiation Protection 31, no. 2 (2016): 121–27. http://dx.doi.org/10.2298/ntrp1602121a.

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This study is focused on the radiological investigation of terrestrial gamma radiation in the test field with soil samples from different minefields in the Federation of Bosnia and Herzegovina. Measurements of ambient dose equivalent rate, commonly referred to as ?air dose rate?, in the test field located in the Tuzla Canton, were performed by RADIAGEMTM 2000 portable survey meter, based on energy-compensated Geiger-Muller counter. Its performances were tested in the laboratory conditions with gamma point sources. Since all the samples in the test field were exposed to the same cosmic radiation, there was a possibility to assess a relative contribution of terrestrial gamma radiation due to soil samples of different composition. One set of measurements in the test field was performed with RADIAGEMTM 2000, at a height of about one meter above the ground and basic statistical parameters indicated that there was no significant difference of terrestrial gamma radiation from different soil samples. The other set of measurements was carried out with the same device placed on the ground in the test field. Processing of experimental data on terrestrial gamma radiation has shown that it was possible to make a difference between relative contributions of terrestrial gamma radiation from individual soil samples. The results of investigation could be useful for multiple purposes of public interest.

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Yoshida, T., N. Tsujimura, and T. Yamano. "Development of a hand-held fast neutron survey meter." Radiation Protection Dosimetry 146, no. 1-3 (April 12, 2011): 72–75. http://dx.doi.org/10.1093/rpd/ncr114.

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Nunomiya, T., T. Nakamura, T. Koyama, D. Inui, and T. Ishikura. "Development of a light-weight portable neutron survey meter." Radiation Protection Dosimetry 146, no. 1-3 (June 1, 2011): 84–87. http://dx.doi.org/10.1093/rpd/ncr117.

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Lalrinmawia, J., K. S. Pau, and R. C. Tiwari. "Investigation of conventional diagnostic X-ray tube housing leakage radiation using ion chamber survey meter in Mizoram, India." Science Vision 19, no. 3 (September 30, 2019): 79–90. http://dx.doi.org/10.33493/scivis.19.03.02.

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Leakage radiation that transmitted the protected X-ray tube housing was measured and compared with national and international safety standard. To the best of the authors’ knowledge, no tube housing leakage measurement has been done so far in the present study area. The authors considered all the conventional diagnostic X-ray units in Mizoram, India. Ion chamber survey meter was used to measure leakage radiation and it was placed at 5 different positions (left, right, front, back, top) of the X-ray tube. Measurements were done at 1 m focus-to-detector distance by projecting X-ray tube vertically downward with collimator diaphragms closed completely. SPSS statistics for windows, version 17.0 (SPSS, Inc., Chicago, IL, USA) was used to derived mean, standard error of the mean etc. The tube housing leakage exposure rates ranged between 0.03 mRh-1 and 500 mR h-1; among the 5 positions, rate measured in the front direction has the highest mean at 41.61±8.63 mR h-1; whereas the top has the lowest 4.57±1.16 mRh-1. Tube housing radiation level ranged from 0.01 to 58 mR in one hour. Leakage radiation was minimum at the top position of the tube and maximum in the front direction. All the equipment were in compliance with national and international standard norms, the highest leakage radiation level was 50.43% of the safety limit.

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FARDELA, Ramacos, Gede Bayu SUPARTA, Ahmad ASHARI, and Kuwat TRIYANA. "RADIATION DOSE RATE MEASUREMENT FOR PROTECTION PROGRAMS IN THE WORK ENVIRONMENT FOR THE HEALTH WORKERS: AN EXPERIMENTAL STUDY." Periódico Tchê Química 17, no. 36 (December 20, 2020): 662–73. http://dx.doi.org/10.52571/ptq.v17.n36.2020.677_periodico36_pgs_662_673.pdf.

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Radiation is the energy emitted from electrons in particles or photons (waves) and is classified into nonionized and ionized. Ionizing radiation demonstrates the ability to disintegrate matter along its path and has proven beneficial in medicine. Exposure to this energy tends to instigate adverse effects on human health and heredity (genetics). However, the radiation is not directly measured but requires a nuclear detector to serve as a monitoring device. Radiation workers’ awareness of ionizing radiation levels in the work environment is one of the most important factors in preventing the negative effects of radioactivity. This is possibly identified using various types of detectors. This experiment aimed to provide an overview of radiation dose rate measurement under two conditions. First is the event of contamination in the work environment. The second involves using a detector to solely determine the dose rate from a single source, e.g., gamma radiation. Therefore, the radiation dose rate was evaluated by maximizing the use of detectors with a GUI as a survey meter for contamination. The highest rate (261.42 μSv / h) was observed at a distance of 5 mm, while the least (69.21 μSv / h) was recorded at 50 mm. Also, a dose rate of 5.4 μSv / h and 1.32 μSv / h was obtained at a 5 mm and 50 mm distance from the radiation source, respectively, following the operation as a gamma survey meter. This result shows strong linearity between both measurements and is estimated to accurately determine the contamination level of radioactive elements, alongside the doses rate of the gamma radiation emitting elements.

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Garba, Nuraddeen Nasiru, Rabiu Nasiru, Muniba Sufiyan, and Abdullahi Muhammad Vatsa. "Measurement of radiation dose level within Queen Amina Hall, Ahmadu Bello University, Zaria." Bayero Journal of Pure and Applied Sciences 12, no. 1 (April 14, 2020): 1–4. http://dx.doi.org/10.4314/bajopas.v12i1.1s.

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Measurement of background radiation is of great interest for it provides useful information in monitoring environmental radioactivity. The aim of the present study is to provide information and generate database on the natural background radiation dose levels of densely populated Queen Amina Hall, Ahmadu Bello University, Zaria. The radiation dose (outdoor and indoor dose rate) were measured at 29 rooms (Block 1- 4) and their compounds using RADOS survey meter held at 1m above the ground. The measured radiation dose ranged 0.13 nGyh-1 to 0.43 nGyh-1 and 0.54 nGyh-1 to 1.72 nGyh1 for indoor and outdoor respectively. Some of the high values recorded could be attributed due to the contribution of cosmic radiation emanating from the atmosphere as well as the geological settings of the location as there is no any artificial contributing factor within the area. The annual effective doses within the study area was found to be 0.01 mSvy-1 throughout which is quit below the world average value of 0.87 mSvy-1 for natural sources. Keywords: Radiation dose, Annual effective dose, RADOS meter, Queen Amina

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Tanaka, Kenichi, and Jun Takada. "Development of collimator for in-situ measurement of 90Sr specific activity by β-ray survey meter and Monte Carlo calculation." Applied Radiation and Isotopes 77 (July 2013): 1–4. http://dx.doi.org/10.1016/j.apradiso.2013.02.007.

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Abdullahi, S., A. S. Ahmad, B. Abdulkadir, Y. Kabir, S. Mustapha, M. R. Hayatudeen, and A. Usman. "Review on the diagnosis and antibiotic therapy of otitis media in children." Bayero Journal of Pure and Applied Sciences 12, no. 1 (April 15, 2020): 80–84. http://dx.doi.org/10.4314/bajopas.v12i1.14s.

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Measurement of background radiation is of great interest for it provides useful information in monitoring environmental radioactivity. The aim of the present study is to provide information and generate database on the natural background radiation dose levels of densely populated Queen Amina Hall, Ahmadu Bello University, Zaria. The radiation dose (outdoor and indoor dose rate) were measured at 29 rooms (Block 1- 4) and their compounds using RADOS survey meter held at 1m above the ground. The measured radiation dose ranged 0.13 nGyh-1 to 0.43 nGyh-1 and 0.54 nGyh-1 to 1.72 nGyh-1 1 for indoor and outdoor respectively. Some of the high values recorded could be attributed due to the contribution of cosmic radiation emanating from the atmosphere as well as the geological settings of the location as there is no any artificial contributing factor within the area. The annual effective doses within the study area was found to be 0.01 mSvy-1 throughout which is quit below the world average value of 0.87 mSvy-1 for natural sources. Keywords: Radiation dose, Annual effective dose, RADOS meter, Queen Amina

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Nassef, Mohamed Hamed. "Image Quality Assessment and Radiation exposure in Intra Oral Dental Radiography." International Journal for Innovation Education and Research 5, no. 2 (February 28, 2017): 75–84. http://dx.doi.org/10.31686/ijier.vol5.iss2.623.

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In this study, an intra oral dental unit (Siemens-70) at King Abdul Aziz University (KAU) Dental Hospital was selected and investigated for visual image quality assessment and radiation protection purposes. Radiation dosimetry for determining the optimum image quality with the lowest radiation exposure to the patient was carried out. A DXTTR dental radiography trainer phantom head and neck, portable survey meter Model RAD EYE-B20, and radiation dosimetry system RADCAL Acuu-pro were used in this study. RADCAL Accu-pro is a non-invasive kV system, reliable instruments to measure and diagnose all X-ray machines including dental units. The radiation exposure to patients in (mGy) was measured using RADCAL ionization chamber Model 10×6-6. The best image quality with the lowest exposure dose was assessed for conventional intraoral X-ray film (Kodak type E) and the digital processing sensor (RVG 5200). Radiation survey level was done during this study for safety and protection purposes.

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Li, Taosheng, Dong Fang, and Hong Li. "A Monte Carlo design of a neutron dose-equivalent survey meter based on a set of 3He proportional counters." Radiation Measurements 42, no. 1 (January 2007): 49–54. http://dx.doi.org/10.1016/j.radmeas.2006.08.001.

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Gyuk, P. M., J. O. Anaegbu, H. O. Aboh, R. Daniel, A. Aruwa, and B. Ahmadu. "ESTIMATION ON THE RADIOLOGICAL LEVEL OF NATURAL OCCURRING RADIONUCLIDES PRESENT IN FLOODED SOIL SAMPLES IN KADUNA NORTH, NIGERIA." International Journal of Research -GRANTHAALAYAH 5, no. 10 (October 31, 2017): 81–91. http://dx.doi.org/10.29121/granthaalayah.v5.i10.2017.2275.

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The background radiation of the areas was collected at random for each point using a rados survey meter. The detectors (two rados survey meter were used) were placed 1 meter above the ground with the operator positioned a few meters away. Three (3) readings were taking from each detector in other to reduce error or reach accuracy in obtaining the background readings from each randomly selected point where soil samples were later collected. In the current study, the concentration levels of naturally occurring radioactive materials (NORMs) of 40K, 232Th, and 238U in the surface soil samples of selected areas in kigo road new extension Kaduna north, Kaduna in Nigeria were studied. The collected soil samples were analyzed by means of gamma-ray spectrometry. The mean activity concentrations of the natural occurring radionuclides of 226Ra, 232Th and 40K in the soil samples were estimated to be 62, 78.35, 227.17 Bq/kg respectively for kigo road new extension respectively. Radium equivalent activity, absorbed dose rate, annual effective dose equivalent were also calculated for assessment of radiological risk. External hazard value (Hex) is between 0.3163 and 0.9557 and Internal hazard value is between 0.4462 and 1.1618. The worldwide average activity concentrations of 226Ra, 232Th and 40K in soil samples from various studies around the world have values of 37, 30 and 400 Bq/kg respectively [UNSCEAR, 2000]. The values compared well with published data from UNSCEAR shows Ra-226, Th-232 from the location are well above the standards while K-40 below the risk value.

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Tanaka, Kenichi, and Jun Takada. "Development of in-situ measurement for 90Sr specific activity by β-ray survey meter combined with sensitivity correction by Monte Carlo calculation." Applied Radiation and Isotopes 69, no. 5 (May 2011): 814–17. http://dx.doi.org/10.1016/j.apradiso.2011.01.029.

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Birattari, C., A. Esposito, A. Ferrari, M. Pelliccioni, and M. Silari. "A Neutron Survey Meter with Sensitivity Extended up to 400 MeV." Radiation Protection Dosimetry 44, no. 1-4 (November 1, 1992): 193–97. http://dx.doi.org/10.1093/oxfordjournals.rpd.a081431.

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Yokoyama, S., N. Mori, M. Shimo, M. Fukushi, and S. Ohnuma. "Measurement of radon concentration in water using the portable radon survey meter." Radiation Protection Dosimetry 146, no. 1-3 (April 13, 2011): 23–26. http://dx.doi.org/10.1093/rpd/ncr098.

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KAMIMURA, Masaru, Yoshimitsu TAKANASHI, Akiko KIHARA, Toyoshige TSUTAKE, and Yoshio MITSUI. "Radiation Screening Test of Commercial Food Products and Foodstuffs for Food Services Using NaI (Tl) Scintillation Survey Meter." Food Hygiene and Safety Science (Shokuhin Eiseigaku Zasshi) 54, no. 2 (2013): 127–30. http://dx.doi.org/10.3358/shokueishi.54.127.

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Reddy, K. Vinay Kumar, B. Sreenivasa Reddy, and B. Linga Reddy. "Natural background gamma radiation levels in dwellings constructed under the Double Bedroom Housing Scheme at Erravalli and Narasannapet model villages of Telangana state, India." Indoor and Built Environment 29, no. 7 (July 24, 2019): 1038–44. http://dx.doi.org/10.1177/1420326x19865998.

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Quantification of natural background gamma radiation levels in indoors has attracted mounting interest for the past few decades due to the detrimental effects of radiation. The indoor radiation levels depend on many parameters like geology, building materials, temperature, ventilation, etc. The natural background gamma radiation levels were estimated using a μR-Survey Meter in indoors and outdoors of dwellings constructed under the Double Bedroom Housing Scheme of Telangana state government at Erravalli and Narasannapet model villages. The average gamma radiation levels in the Erravalli village was found to be 2873 ± 413 μGyy−1, while in Narasannapet village it was 2621 ± 355 μGyy−1, which are relatively high as compared to the national average 775 ± 370 μGyy−1. The indoor to outdoor ratio of natural background radiation levels varied from 0.74 to 1.52 with an average of 1.08 which is in the global range. The variation of these levels with different types of dwellings has also been discussed.

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Daniel, Omojola Akintayo, and Isiodu Chinonye Xaviera. "Integrity test of lead apron and its effect on personnel and carer." Bangabandhu Sheikh Mujib Medical University Journal 11, no. 1 (March 5, 2018): 34. http://dx.doi.org/10.3329/bsmmuj.v11i1.35360.

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<p class="Abstract">The use of lead apron is known to protect radiation workers and carers (patient relatives) from the scatter radiation. The study intends to assess the integrity of lead apron by checking for defects and to estimate the mean dose rate to personnel and carers and also to compare the percentage mean absorbance of the apron with the related studies. Ten lead aprons were used involving three vendors. A fluoroscopy unit, floor mounted X-ray unit, survey meter, lead aprons and meter rule were used. Crack and tear were identified with some areas close to the critical organ site. Eighty percent of the aprons showed signs that they were defective. Correlation of the lead aprons mean age and the total number of defective lead aprons were not significant (p=0.866). The mean thickness of the aprons for the three brands affected the percentage absorbance (p<0.001). The mean dose rate was above 20 mSv recommended for radiation workers averaged over a single year. It is recommended that the defective apron close to the critical organ be replaced and those in areas distal from the critical organs be further evaluated using the rejection criteria test before they are replaced.</p>

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Lalrinmawia, Jonathan, Kham Suan Pau, and Ramesh Chandra Tiwari. "Study on the intensity of radiation attenuated by protective barriers in diagnostic X-ray installations." Science Vision 19, no. 2 (June 30, 2019): 43–50. http://dx.doi.org/10.33493/scivis.19.02.08.

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The main objective of the present study is to find out the intensity of radiation attenuated by different types of patient entrance doors (PED) as well as control panel (CP) protective barriers in diagnostic X-ray installations. To measure the intensity of ionizing radiation, ion chamber survey meter was used; all measurements were performed in freeze mode. In setting maximum accelerating potential, minimum tube current and fixed exposure time, a water phantom was exposed through maximum field size. Radiation exposure rates were measured at CPs as well as PEDs with and without barriers. In chest mission, radiation rates with PED ranged from 0.3 µSv/h to 0.7 mSv/h and without PED 0.2 mSv/h to 1.2 mSv/h. At the same time, in couch mission, radiation rates measured behind PED ranged from 0.3 µSv/h to 2.2 mSv/h and 0.03 mSv/h to 2.25 mSv/h in front of PED. All institutions showed higher exposure rates without PED; all types of doors considerably attenuated radiation. Among different types of door, lead-lined door attenuated 99.53% in chest mission and 97.44% in couch mission. While plywood doors attenuated approximately 40% of the incident radiation, it is more or less similar as air does in every half meter away from the phantom. Radiation rates in chest missions with CP barriers ranged from 2 µSv/h to 0.38 mSv/h, while 0.4 mSv/h to 2.35 mSv/h without CP barriers. In couch missions, radiation rates measured with CP barriers varied from 4 µSv/h to 0.6 mSv/h whereas without CP barriers from 0.7 mSv/h to 5 mSv/h. There was a significant difference between radiation measured behind and in front of the CP barriers. Among them, the percentage of attenuation was high in lead and concrete barriers.

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Shibamoto, Yuta, Yoshiaki Kamei, Koichi Kamei, Takahiro Tsuchiya, and Natsuto Aoyama. "Continuous Low-Dose-Rate Irradiation Promotes Growth of Silkworms." Dose-Response 15, no. 4 (October 1, 2017): 155932581773525. http://dx.doi.org/10.1177/1559325817735252.

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To investigate the influence of low-dose-rate irradiation on the growth of silkworms, Bombyx mori, eggs of silkworms were randomly divided into 2 groups and were grown on either low-dose-radiation-emitting sheets or control sheets. On the radiation-emitting sheets, the dose rate was measured as 66.0 (4.3) μSv/h (mean [standard deviation]) by a Geiger-Müller counter for α, β, and γ rays and 3.8 (0.3) μSv/h by a survey meter for γ rays. The silkworms became larger when bred on the radiation-emitting sheets, and their body weight was about 25% to 37% heavier on day 42 to 49 after starting the experiment. Continuous low-dose-rate irradiation promoted the growth of silkworms. It should be further investigated whether this phenomenon could be utilized by the silk industry.

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Maria Jose, Reeba, S. Ben Byju, S. Anilkumar, and M. P. Chougaonkar. "External Gamma Dose Levels In The Soil Samples of HBRAs of Kerala and Tamil Nadu, India." International Journal of Fundamental Physical Sciences 5, no. 2 (June 30, 2015): 54–57. http://dx.doi.org/10.14331/ijfps.2015.330086.

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Knowledge on the distribution of these radionuclides in soil is of great importance for radiation protection and measurement. A systematic radiological survey has been carried out in the region of HBRAs in Kollam district of Kerala and Manavalakurichi in Tamilnadu in India to compare the natural gamma-radiation levels. 180 soil samples collected and were analyzed for 238U, 232Th and 40K by NaI(Tl) gamma-ray spectrometry. Heterogeneous distribution of radionuclides in the region may be attributed to the deposition phenomenon of soil in the region. The result of gamma dose rate measured at the sampling sites using survey meter showed an excellent correlation with dose rates computed from the natural radionuclides estimated from the soil samples. From these radioactivity levels, the radium equivalent activity and the external hazard index which resulted from the natural radionuclides in sediments are also tabulated for the analyzed samples and compared with internationally recommended values.

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Okeyode, I. C., J. A. Rabiu, O. O. Alatise, V. Makinde, F. G. Akinboro, D. Al-Azmi, and A. O. Mustapha. "AREA MONITORING OF AMBIENT DOSE RATES IN PARTS OF SOUTH-WESTERN NIGERIA USING A GPS-INTEGRATED RADIATION SURVEY METER." Radiation Protection Dosimetry 173, no. 1-3 (December 1, 2016): 263–67. http://dx.doi.org/10.1093/rpd/ncw336.

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NGUYEN, Philip, Hidehito NAKAMURA, Hisashi KITAMURA, Nobuhiro SATO, Tomoyuki TAKAHASHI, Daisuke MAKI, Masaya KANAYAMA, Yoshiyuki SHIRAKAWA, and Sentaro TAKAHASHI. "Alpha Particle Response for a Prototype Radiation Survey Meter Based on Poly(ethylene terephthalate) with Un-doping Fluorescent Guest Molecules." Japanese Journal of Health Physics 51, no. 1 (2016): 2. http://dx.doi.org/10.5453/jhps.51.2.

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NGUYEN, Philip, Hidehito NAKAMURA, Hisashi KITAMURA, Nobuhiro SATO, Tomoyuki TAKAHASHI, Daisuke MAKI, Masaya KANAYAMA, Yoshiyuki SHIRAKAWA, and Sentaro TAKAHASHI. "Alpha Particle Response for a Prototype Radiation Survey Meter Based on Poly(ethylene terephthalate) with Un-doping Fluorescent Guest Molecules." Japanese Journal of Health Physics 51, no. 1 (2016): 60–63. http://dx.doi.org/10.5453/jhps.51.60.

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Ciraj-Bjelac, Olivera, Danijela Arandjic, Dusko Kosutic, and Djordje Lazarevic. "An assessment of scattered radiation during fluoroscopic procedures in diagnostic radiology." Nuclear Technology and Radiation Protection 24, no. 3 (2009): 204–8. http://dx.doi.org/10.2298/ntrp0903204c.

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The results of measurements of scattered radiation in the vicinity of a fluoroscopic X-ray facility are presented in this paper. Two different fluoroscopic systems, one with an undercouch tube and one with an overcouch tube, were compared. The dose rate was measured during the simulation of a fluoroscopy procedure, using an ionization chamber as a dosemeter. The distribution of scattered radiation has been determined and results show a much higher dose rate in cases of an overcouch tube arrangement. When X-ray units with an undercouch tube are concerned, under same exposure conditions, the dose rate is higher in cases of a vertical beam. Prior to the measurements, the ionization chamber was examined in order to evaluate its suitability as a survey meter used in diagnostic radiology. Measurements show that below 1.2 s, the ionization chamber gives an underestimation of dose rates. Therefore, in order to perform accurate measurements using this instrument, exposure times should be above 1.2 s.

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Osanai, Minoru, Kohsei Kudo, Masahiro Hosoda, Hirofumi Tazoe, Naofumi Akata, Maiko Kitajima, Megumi Tsushima, et al. "THE IMPACT ON THE EYE LENS OF RADIATION EMITTED BY NATURAL RADIONUCLIDES (LEAD-210) PRESENT IN RADIATION PROTECTION GLASSES." Radiation Protection Dosimetry 188, no. 1 (November 11, 2019): 13–21. http://dx.doi.org/10.1093/rpd/ncz252.

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Abstract Most radiation protection items made from modern lead contain 210Pb. This study estimated the impact on eye lens of radiation derived from the 210Pb in three types of radiation protection glasses. The counts from the glasses were measured using a Geiger–Müeller survey meter. The net count rate was 92 ± 1 cpm at a distance of 0.5 cm for one type of glasses. Additionally, we conducted a qualitative γ-ray spectrum analysis using a high-purity germanium semiconductor detector. The absorbed dose in the eye lens was related to 210Pb and its daughter radionuclide, 210Bi; this dose was calculated by applying dose conversion coefficients provided by the International Commission on Radiological Protection. The absorbed dose rate in eye lens was conservatively calculated to be on the order of 10 nGy/h for the type of glasses containing the most 210Pb. The dose from β-rays accounted for >99%. In addition, we investigated the dose-reduction effect using a thin acrylic plate. The count rate approximately decreased to background level by inserting a plate with a thickness of 1 mm. We conclude that the impact of 210Pb contained in radiation protection glasses is negligibly small, particularly considering the usefulness of the significant external exposure reduction.

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Kameya, Hiromi, Shoji Hagiwara, Daisuke Nei, Yoshiteru Kakihara, Keitaro Kimura, Ushio Matsukura, Shinichi Kawamoto, and Setsuko Todoriki. "The Shielding of Radiation for the Detection of Radioactive Cesium in Cereal Sample by Using a NaI(T1) Scintillation Survey Meter." Nippon Shokuhin Kagaku Kogaku Kaishi 58, no. 9 (2011): 464–69. http://dx.doi.org/10.3136/nskkk.58.464.

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Zeb, Jahan, Mohammad Wasim, Muhammad Awais, Asad Ullah, Talat Iqbal, and Sheraz Akhtar. "EVALUATION OF INDOOR/OUTDOOR GAMMA EXPOSURE RATES AND EXCESS LIFE TIME CANCER RISK IN DIFFERENT CITIES OF PAKISTAN." Radiation Protection Dosimetry 190, no. 4 (July 2020): 355–63. http://dx.doi.org/10.1093/rpd/ncaa115.

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Abstract This study presents a detailed measurement of indoor and outdoor terrestrial gamma radiation levels in different cities of Pakistan. The measurements covered dwellings in 27 cities, covering all provinces and region of Azad Kashmir. Most of the houses were of attached type, made of brick walls and concrete roofs. The measurements were made by a handheld radiation survey meter containing Geiger–Muller tube. The average absorbed dose rate in air was 100 ± 32 nGy h−1 for indoor and 74 ± 30 nGy h−1 for outdoor. The population-weighted mean terrestrial dose rates were 90 nGy h−1 for indoor and 78 nGyh−1 for outdoor. The ratio of indoor to outdoor absorbed dose rate was 1.5 as compared to 1.3 for the world average. The estimated average annual effective dose rate was 0.58 ± 0.18 mSv a−1 and the mean excess life time cancer risk was 2.0 × 10−3.

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Davydov, Vadim, and Andrei Nazarov. "Geophysical survey at the southern end of the Degtyarsky pyrite deposit." Izvestiya vysshikh uchebnykh zavedenii Gornyi zhurnal, no. 2 (March 30, 2020): 37–43. http://dx.doi.org/10.21440/0536-1028-2020-2-37-43.

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Research aim is to study features peculiar to geophysical fields over the main geological features of the southern part of the Degtyarsky pyrite deposit at the Middle Urals. Methodology. Electromagnetic survey included symmetrical electric profiling (SEP) with ERA-MAX equipment (ERA Research and Production Enterprise, St. Petersburg) and rapid audio-magnetotelluric sounding (ATMS) with OMAR-2m wideband receiver (Institute of Geophysics UB RAS, Ekaterinburg). Magnetic survey was carried out with the help of the proton procession magnetometer GSM-19T (GEM Systems, Canada), gamma field survey was carried out with a survey meter SRP-68-01 (Electron, Zhovti Vody). Results. According to the results of observational analysis, high-quality sections of electrophysical parameters of the environment were constructed at the parametric profile together with the charts of other geophysical fields. The studies have shown significant changes of resistivity and potential fields anomalies over various geological features of the ore field. Summary. Geophysical indications of border line of the main geologic features have been determined. Excessive electrical conductivity of ore control tectonic structures and radiation anomaly have been revealed in the promises of the ore body, which can serve a prospecting criterion for a similar ore body. Geophysical results are well within the existing geological data on the Degtyarsky mine.

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Sharma, Sunil, Ganesh Narayanasamy, Beata Przybyla, Jessica Webber, Marjan Boerma, Richard Clarkson, Eduardo G. Moros, Peter M. Corry, and Robert J. Griffin. "Advanced Small Animal Conformal Radiation Therapy Device." Technology in Cancer Research & Treatment 16, no. 1 (July 8, 2016): 45–56. http://dx.doi.org/10.1177/1533034615626011.

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We have developed a small animal conformal radiation therapy device that provides a degree of geometrical/anatomical targeting comparable to what is achievable in a commercial animal irradiator. small animal conformal radiation therapy device is capable of producing precise and accurate conformal delivery of radiation to target as well as for imaging small animals. The small animal conformal radiation therapy device uses an X-ray tube, a robotic animal position system, and a digital imager. The system is in a steel enclosure with adequate lead shielding following National Council on Radiation Protection and Measurements 49 guidelines and verified with Geiger-Mueller survey meter. The X-ray source is calibrated following AAPM TG-61 specifications and mounted at 101.6 cm from the floor, which is a primary barrier. The X-ray tube is mounted on a custom-made “gantry” and has a special collimating assembly system that allows field size between 0.5 mm and 20 cm at isocenter. Three-dimensional imaging can be performed to aid target localization using the same X-ray source at custom settings and an in-house reconstruction software. The small animal conformal radiation therapy device thus provides an excellent integrated system to promote translational research in radiation oncology in an academic laboratory. The purpose of this article is to review shielding and dosimetric measurement and highlight a few successful studies that have been performed to date with our system. In addition, an example of new data from an in vivo rat model of breast cancer is presented in which spatially fractionated radiation alone and in combination with thermal ablation was applied and the therapeutic benefit examined.

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Hoekstra, A., J. M. H. de Klerk, P. P. van Rijk, B. A. Zonnenberg, and M. G. E. H. Lam. "Radiation safety considerations for the bone seeking radiopharmaceuticals." Nuklearmedizin 48, no. 01 (2009): 37–43. http://dx.doi.org/10.3413/nukmed-0182.

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SummaryThe radiation exposure to bystanders from 89SrCl2, 186Re-HEDP and 153Sm-EDTMP, is generally thought to be caused by “bremsstrahlung” and gamma-radiation, with negligible contribution from beta-radiation. The latter assumption may be erroneous. The aim of this prospective study was the investigation of radiation safety after treatment with these radiopharmaceuticals. The radiation field around treated patients was characterized and the magnitude estimated. Patients, methods: 33 patients (30 prostate carcinoma, 3 breast carcinoma) were treated with 150 MBq 89SrCl2 (9 patients), 1295 MBq 186Re-HEDP (12 patients) or 37 MBq/kg 153Sm-EDTMP (12 patients). External exposure rates at 30 cm from the patient were measured at times 0 to 72 h post-injection. To evaluate the respective contribution of Bremsstrahlung, beta- and gamma-radiation, a calibrated survey meter was used, equipped with a shutter. For each patient, the measured exposure rate-versus-time data were fit to a curve and the curve integrated (area under the curve) to estimate the total exposure. Results: For 29/33 patients the total ambient equivalent doses (mean ± 1 standard deviation [SD]) based on the integral of the fitted curve were 2.1 ± 1.2 mSv for 89SrCl2, 3.3 ± 0.6 mSv for 186Re-HEDP and 2.8 ± 0.6 mSv for 153Sm-EDTMP. Beta-radiation contributes significantly to these doses ( >99% for 89SrCl2, 87% for 186Re-HEDP and 27% for 153Sm-EDTMP). The effective doses (at 30 cm) are < 0.1 mSv for 89SrCl2, 0.3 mSv for 186Re-HEDP and 1.6 mSv for 153Sm-EDTMP. Conclusion: Patients treated with 89SrCl2, 186Re-HEDP or 153Sm-EDTMP emit a spectrum of radiation, including non-negligible beta-radiation. With specific instructions effective doses to bystanders are acceptable.

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Bello, I. A., O. O. Ige, N. Kure, and A. H. Momoh. "ASSESSMENT OF RADIATION DOSE LEVEL AT KABBA COLLEGE OF AGRICULTURE, DIVISION OF AGRICULTURAL COLLEGES, AHMADU BELLO UNIVERSITY, ZARIA." FUDMA JOURNAL OF SCIENCES 5, no. 1 (June 29, 2021): 524–28. http://dx.doi.org/10.33003/fjs-2021-0501-599.

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Background radiation involves the measure of the level of ionizing radiation present in the environment at a particular location. This research seek to generate data of the natural background radiation level of some selected Sections at Kabba College of Agriculture, using RadEye G20 survey meter. A total of 15 sections of the College were randomly selected and the background radiation dose rate of the sections were measured. The indoor dose rate ranged from (0.09 – 0.13) 𝜇Sv/yr, while the outdoor dose rate ranged from (0.07 - 0.10) 𝜇Sv/yr. The indoor annual effective dose were observed to be greater than the outdoor annual effective dose in all the College Sections measured. The lowest total annual effective dose 0.75 𝑚𝑆𝑣/𝑦𝑟 was found at the Academic staff block. The highest total annual effective dose of 1.09 𝑚𝑆𝑣/𝑦𝑟 was found at the livestock building, this might be due to the high-altitude nature of the area and the rocky materials used in the construction of the building. The highest total annual effective dose of the study area was slightly above the recommended limit of 1.0 𝑚𝑆𝑣/𝑦𝑟. The result obtained from this research may not constitute immediate health risk to the staff and student of the college

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Fujibuchi, T., S. Obara, I. Yamaguchi, M. Oyama, H. Watanabe, T. Sakae, and K. Katoh. "Induced radioactive nuclides of 10-MeV radiotherapy accelerators detected by using a portable HP-Ge survey meter." Radiation Protection Dosimetry 148, no. 2 (February 10, 2011): 168–73. http://dx.doi.org/10.1093/rpd/ncr005.

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Yoshimura, E. M., N. K. Umisedo, and E. Okuno. "Assessment of ambient dose equivalent rate: performance of an automatic survey meter as an instrument to quantify the presence of radiation in soils." Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment 487, no. 3 (July 2002): 457–64. http://dx.doi.org/10.1016/s0168-9002(01)02205-7.

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Echeweozo, E. O., and F. O. Ugbede. "Assessment of background ionizing radiation dose levels in quarry sites located in Ebonyi State, Nigeria." Journal of Applied Sciences and Environmental Management 24, no. 10 (November 3, 2020): 1821–26. http://dx.doi.org/10.4314/jasem.v24i10.17.

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The study presents a radiometric survey of Background Ionizing Radiation (BIR) dose levels in ten quarry sites located in Ebonyi State, Nigeria. In-situ BIR dose rate measurements, by means of nuclear radiation survey meter, at 1 m above ground level were carried out at the excavation section (ES) and quarrying section (QS) of the investigated quarry sites. The obtained results indicated dose rates ranging from from 0.14 to 0.18 μSv/h with mean of 0.15±0.01 μSv/h at the ES and 0.16 to 0.19 μSv/h with mean value of 0.18±0.01 μSv/h at the QS. While the values obtained at the QS are respectively higher than those measured at the ES, they are all higher than the worldwide average value of 84 nSv/h signifying BIR elevated environments. The estimated mean annual effective dose (AED) and excess lifetime cancer risk (ELCR) are 0.27±0.03 mSv/y and 0.94×10–3 respectively at the ES and 0.31±0.02 mSv/y and 1.07×10–3 at the QS. The obtained AED values for all the sites are well above the outdoor worldwide average value of 0.07 mSv/y but lower than the International Commission on Radiological Protection recommended permissible limits of 1.0 mSv/y for the general public. Generally, the BIR levels of the quarry sites are within acceptable limits and no immediate radiological health threat may be derived from the current levels. However, long-term health effects due to continuous exposure to low-level radiation doses may manifested in future over a lifetime exposure of 70 years as indicated by the ELCR values. Keywords: Background ionizing radiation, Dose rate, Annual effective dose, Quarry site, Ebonyi State

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Que, William, Nelson Videla, and Deanna Langer. "Ultrasound guided I–125 permanent prostate implants: seed calibration and radiation exposure levels." Journal of Radiotherapy in Practice 1, no. 3 (November 1999): 143–51. http://dx.doi.org/10.1017/s1460396999000230.

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Purpose: (1) To present data on I–125 seed calibration in a clinical setting so that reasonable tolerance levels can be set for the discrepancy in seed strength between manufacturer specified value and institution measured value; (2) To present data on measured exposure rates and estimate radiation exposure levels associated with I–125 prostate implants.Methods and Materials: Ten percent of each batch for 50 batches of I–125 seeds were calibrated using an HDR 1000 PLUS well chamber with a single source holder. Exposure rates due to I–125 were measured by survey meters with a scintillation probe designed for low energy photon counting, as well as a survey meter of the ionization chamber type. Exposure rates of an unshielded I–125 seed, a needle loaded with three seeds, and 54 prostate implant patients immediately after the implant were obtained.Results: Compared to the manufacturer stated midrange seed strength for a batch of seeds, the average seed strength of sampled seeds had maximum deviations of ±8%, however for 45 out of 50 batches the deviation was less than ±5%. Measured single seed strength deviated up to ±12% from the manufacturer stated midrange value, and between −11% to 7% from the mean of the sampled batch. The exposure rate of a 1.39×107 Bq (0.375 mCi) unshielded I–125 seed was about 1.548×10−8C/kgh (0.06 mR/h) at 1 m, and 1.29×10−6C/kgh (5 mR/h) at 10 cm. For a needle loaded with three seeds, the exposure rate was 1.29×10−8C/kgh (0.05 mR/h) at the handle, and 1.29×10−7C/kgh (0.5 mR/h) along the shaft. For patients implanted with I–125 seeds in the prostate, the average exposure rate was 3.61×10−8C/kgh (0.14 mR/h) at 1m, and 4.13×10−7C/kgh (1.6 mR/h) at the pelvis surface.Conclusions: For the mean seed strength a first action level should be set at a deviation of at least 5% deviation from the manufacturer stated midrange value. For individual seeds, a first action level set at 10% deviation from the manufacturer stated midrange value seems reasonable. A person performing I–125 seed calibration or seed loading could receive up to 0.5 mSv (50 mR) per case to the hands. In the first year following an I–125 prostate implant, the spouse of the patient could receive slightly over 1mSv from the I–125 in the patient. A co-worker should not receive more than 0.5 mSv from the patient.

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Goodman, William A. "3D Printed and Additively Manufactured RoboSiC™ for Space, Cryogenic, Laser and Nuclear Environments." International Symposium on Microelectronics 2018, no. 1 (October 1, 2018): 000099–103. http://dx.doi.org/10.4071/2380-4505-2018.1.000099.

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Abstract Goodman Technologies has been directly responsive to, and focused on, 3D printing and additive manufacturing techniques, and what it takes to manufacture in zero-gravity. During a NASA Phase I SBIR project, using a small multi-printhead machine, we showed that it was possible to formulate and 3D print silicon carbide into shapes appropriate for lightweight mirrors and structures at the production rate of 1.2 square-meter/day. Gradient lattice coupons with feature sizes on the order of 0.8mm were printed and were easily machined to very fine tolerances, ten-thousandths of an inch by Coastline Optics in Camarillo, CA. To further elaborate on the list of achievements, in Phase I, Team GT demonstrated three different ceramization techniques for 3D printing low areal cost, ultra-lightweight Silicon Carbide (SiC) mirrors and structures, radiation shielding, and electronics, several of which could be employed in microgravity The Goodman Technologies briefing presented at 2017 Mirror Technology Days “3D Printed Silicon Carbide Scalable to Meter-Class Segments for Far-Infrared Surveyor: NASA Contract NNX17CM29P along with sample coupons resulted in extreme interest from both Government and the Contractor communities. Our materials, which we call RoboSiC™, is suited for many other applications including heat sinks and radiation shielding for space electronics, and we have already started to make the first parts for these applications. The successful Phase I project suggests that we will meet or exceed all NASA requirements for the primary mirror of a Far-IR Surveyor such as the Origins Space Telescope (OST) and have a high probability solution for the LUVOIR Surveyor in time for the 2020 Decadal Survey. Results indicate that printing on the ground will achieve an areal density of 7.75 kg/square-meter (~39% of a James Webb Space Telescope (JWST) beryllium segment), a cost to print of $60K/segment, and an optical surface that has nanometer-scale tolerances. Printing in the microgravity environment of space we have the potential to achieve an areal density of 1.0–2.0 kg/square meter (<10% of a JWST beryllium segment), with a cost to print of ~$10K/segment. The areal density is 2–15 times better than the NASA goal of 15 kg/square meter, and the costs are substantially better than the NASA goal of $100K/square meter. The encapsulated gradient lattice construction provides a uniform CTE throughout the part for dimensional stability, incredible specific stiffness, and the added benefit of cryo-damping. For the extreme wavefront control required by the Large UV/Optical/IR Surveyor (LUVOIR) the regularly spaced lattice construction should also provide deterministic mapping of any optical distortions directly to the regular actuator spacing of a deformable mirror (DM). Some of our processes will also allow for direct embedding of electronics for active structures and segments. Encapsulation of the lattice structures will allow for actively cooling with helium for unprecedented low emissivity and thermal control. Several decades of experience and testing with SiC have shown that our materials will survive, nay thrive in, the most extreme Space, Cryogenic, Laser and Nuclear Environments.

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KOBAYASHI, Makoto I., Naoyuki SUZUKI, Takuya SAZE, Hitoshi MIYAKE, Kiyohiko NISHIMURA, Hiroshi HAYASHI, Takashi KOBUCHI, Kunihiro OGAWA, Mitsutaka ISOBE, and Masaki OSAKABE. "The Evaluation of a Simple Measurement Method using NaI(Tl) Scintillation Survey-Meter for Radiation Safety Management of Radioactivated Armor Tiles of LHD Vacuum Vessel." Radiation Safety Management 20 (2021): 20–28. http://dx.doi.org/10.12950/rsm.210416.

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Omojola, Akintayo Daniel, Funmilayo Ruth Omojola, Michael Onoriode Akpochafor, and Samuel Olaolu Adeneye. "Shielding assessment in two computed tomography facilities in South-South Nigeria: How safe are the personnel and general public from ionizing radiation?" ASEAN Journal of Radiology 21, no. 2 (August 30, 2020): 5–27. http://dx.doi.org/10.46475/aseanjr.v21i2.89.

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Objective: The aims of this study were to estimate the instantaneous dose rate(IDR) and annual dose rate (ADR) to radiation staff and the general public withinthe controlled and supervised areas, respectively, to determine the shieldingdesign goals (P) of the 2 CT facilities and to determine the average annual dose(AD) to radiographer/operator in the control console during CT scans. Materials and Methods: The equipment used in this study consisted of twonewly installed General Electric (GE) Revolution ACTs CT machines. Technicalparameters used were a thoracic/dorsal spine scan, which was rarely done in both facilities. A calibrated Inspector USB (S.E. International, Inc.) survey meter was positioned < 50 cm from each barrier at various points to determine the average shielded air kerma Results: The average background radiation in the 2 facilities was 0.11 ?Sv/hr. The average ADR to the controlled and supervised areas in CT1 was 0.563±0.25 and 0.369±0.11 mSv/yr, respectively. Also, the average ADR to the controlled and supervised areas in CT2 were 0.410±0.28 and 0.354±0.04 mSv/yr, respectively. The average shielding design goal to the controlled and supervised areas for CT1 was 0.00898±0.0041 and 0.0059±0.0028 mSv/Week, respectively. Similarly, the average shielding design goal for the controlled and supervised areas for CT2 was 0.0066±0.0044 and 0.0057±0.0019 mSv/Week respectively. The estimated average AD to the operator in CT1 and CT2 was 2.5 and 1.3 ?Sv, respectively. Conclusion: The average ADR and shielding design goals in the controlled and supervised areas from both CTs were within acceptable limits for radiation staff and the public.

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Saïdou, Oumar Bobbo Modibo, Ndjana Nkoulou II Joseph Emmanuel, Olga German, Kountchou Noube Michaux, and Hamadou Yerima Abba. "Indoor Radon Measurements Using Radon Track Detectors and Electret Ionization Chambers in the Bauxite-Bearing Areas of Southern Adamawa, Cameroon." International Journal of Environmental Research and Public Health 17, no. 18 (September 17, 2020): 6776. http://dx.doi.org/10.3390/ijerph17186776.

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The current work deals with indoor radon (222Rn) concentrations and ambient dose-equivalent rate measurements in the bauxite-bearing areas of the Adamawa region in Cameroon before mining from 2022. In total, 90 Electret Ionization Chambers (EIC) (commercially, EPERM) and 175 Radon Track Detectors (commercially, RADTRAK2) were used to measure 222Rn concentrations in dwellings of four localities of the above region. A pocket survey meter (RadEye PRD-ER, Thermo Scientific, Waltham, MA, USA) was used for the ambient dose-equivalent rate measurements. These measurements were followed by calculations of annual doses from inhalation and external exposure. 222Rn concentrations were found to vary between 36 ± 8–687 ± 35 Bq m−3 with a geometric mean (GM) of 175 ± 16 Bq m−3 and 43 ± 12–270 ± 40 Bq m−3 with a geometric mean of 101 ± 21 Bq m−3 by using EPERM and RADTRAK, respectively. According to RADTRAK data, 51% of dwellings have radon concentrations above the reference level of 100 Bq m−3 recommended by the World Health Organization (WHO). The ambient dose equivalent rate ranged between 0.04–0.17 µSv h−1 with the average value of 0.08 µSv h−1. The inhalation dose and annual external effective dose to the public were assessed and found to vary between 0.8–5 mSv with an average value of 2 mSv and 0.3–1.8 mSv with an average value of 0.7 mSv, respectively. Most of the average values in terms of concentration and radiation dose were found to be above the corresponding world averages given by the United Nations Scientific Commission on the Effects of Atomic Radiation (UNSCEAR). Even though the current exposure of members of the public to natural radiation is not critical, the situation could change abruptly when mining starts.

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Aliyu, Abubakar Sadiq, Aminu Ismaila, A. M. Na'Inna, and Ahmed Mohammed. "MEASUREMENT OF RADON CONCENTRATION IN SOIL SAMPLES OF MAZAT AND KAFI-HABU MINING SITES, PLATEAU, NIGERIA." FUDMA JOURNAL OF SCIENCES 4, no. 4 (June 13, 2021): 295–301. http://dx.doi.org/10.33003/fjs-2020-0404-485.

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Radon and its short-lived progenies contributed significantly to natural background radiation. Long-term exposure to such radiation increases the probability of lung cancer to persons. To assess the radiological hazards associated with the inhalation of radon gas from ore dust in Mazat and Kafi-Habu mining sites of Plateau, Nigeria, 12 soil samples from an abandoned tailing dump ground were collected and analysed for radon using RAD-7 electronic detector. The dose rate of each sampling point was directly measured using RADOS RDS -120 portable survey meter. The results gave a mean radon concentration ranging from 771.51 ± 21.9 Bq/m3 to 5666.13 ± 28.8 Bq/m3 with 3451.13 ± 42.9 Bq/m3as the average value for all measurements. The average concentration of measurements from Mazat and Kafi-Habu is 3671.6 ± 41.2 Bq/m3 and 3010.16 ± 46.5 Bq/m3 respectively. The average values obtained from the analysis are significantly higher than the upper limit of 300 Bq/m3 set by the International Commission on Radiological Protection (ICRP) suggesting quick remediation on the host communities. The geometrical mean value of Dose Rate (DR) and Annual Effective Dose Equivalent (AEDE) were 870 nGy/hr and 1.04 mSv/yr respectively. Again, these values are above the global average limits of 59 nGy/hr and 1 mSv/yr. The result indicates that miners working in those sites and dwellers of the study areas are at higher risk of getting exposed to radon and need to employ protective measures. This work is useful in monitoring and control of radon level for the on-site workers and the

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Journal articles on the topic 'Radiation survey meter'

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