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Relevant bibliographies by topics / Radiation survey meter

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Academic literature on the topic 'Radiation survey meter'

Author: Grafiati

Published: 4 June 2021

Last updated: 17 February 2022

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Journal articles on the topic "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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Dissertations / Theses on the topic "Radiation survey meter"

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Johnson, William H. "Lost life expectancy rate survey meter." Thesis, Georgia Institute of Technology, 1992. http://hdl.handle.net/1853/16408.

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Philip, Long Nguyen. "Development of a Multi Radiation Type Survey Meter Using Aromatic Ring Polymers Undoped with Fluorescent Molecules." Kyoto University, 2016. http://hdl.handle.net/2433/217749.

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Kyoto University (京都大学)
0048
新制・課程博士
博士(農学)
甲第20066号
農博第2195号
新制||農||1045(附属図書館)
学位論文||H28||N5022(農学部図書室)
京都大学大学院農学研究科地域環境科学専攻
(主査)教授髙橋千太郎, 教授近藤直, 教授飯田訓久
学位規則第4条第1項該当

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Books on the topic "Radiation survey meter"

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McClure, D. R. Automess Szintomat 6134 Radiation Survey Meter (Instrument Evaluation, NRPB-IE). National Radiological Protection Board, 1987.

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Book chapters on the topic "Radiation survey meter"

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Brock, Fred V., and Scott J. Richardson. "Upper Air Measurements." In Meteorological Measurement Systems. Oxford University Press, 2001. http://dx.doi.org/10.1093/oso/9780195134513.003.0014.

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Measurements of atmospheric properties become progressively more difficult with altitude above the surface of the earth, and even surface measurements are difficult over the oceans. First balloons, then airplanes and rockets, were used to carry instruments aloft to make in-situ measurements. Now remote sensors, both ground-based and satellite-borne, are used to monitor the atmosphere. In this context, upper air means all of the troposphere above the first hundred meters or so and, in some cases, the stratosphere. There are many uncertainties associated with remote sensing, so there is a demand for in-situ sensors to verify remote measurements. In addition, the balloon- borne instrument package is relatively inexpensive. However, it should be noted that cost is a matter of perspective; a satellite with its instrumentation, ground station, etc. may be cost-effective when the mission is to make measurements all over the world with good space and time resolution, as synoptic meteorology demands. Upper air measurements of pressure, temperature, water vapor, and winds can be made using in-situ instrument packages (carried aloft by balloons, rockets, or airplanes) and by remote sensors. Remote sensors can be classified as active (energy emitters like radar or lidar) or passive (receiving only, like microwave radiometers), and by whether they “look” up from the ground or down from a satellite. Remote sensors are surveyed briefly before discussing in-situ instruments. Profiles of temperature, humidity, density, etc. can be estimated from satellites using multiple narrow-band radiometers. These are passive sensors that measure longwave radiation upwelling from the atmosphere. For example, temperature profiles can be estimated from satellites by measuring infrared radiation emitted by CO2 (bands around 5000 μm) and O2 (bands around 3.4μm and 15μm) in the atmosphere. Winds can be estimated from cloud movements or by using the Doppler frequency shift due to some component of the atmosphere being carried along with the wind. An active sensor (radar) is used to estimate precipitation and, if it is a Doppler radar, determine winds. The great advantage of satellite-borne instruments is that they can cover the whole earth with excellent spatial resolution.

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Conference papers on the topic "Radiation survey meter"

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Rahman, Nur Aira Abd, Lojius Lombigit, Nor Arymaswati Abdullah, Azraf Azman, Taufik Dolah, Amir Muzakkir, Zainudin Jaafar, et al. "Arduino based radiation survey meter." In ADVANCING NUCLEAR SCIENCE AND ENGINEERING FOR SUSTAINABLE NUCLEAR ENERGY INFRASTRUCTURE: Proceeding of the International Nuclear Science, Technology and Engineering Conference 2015 (iNuSTEC2015). AIP Publishing LLC, 2016. http://dx.doi.org/10.1063/1.4940081.

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Uesaka, Akio, Ryuhei Nakamura, Hiroshi Ito, and Koji Tominaga. "Quantitative Comparison between a Gamma-Ray Visualization Analyzer and a Dose Rate Survey Meter." In Proceedings of the Second International Symposium on Radiation Detectors and Their Uses (ISRD2018). Journal of the Physical Society of Japan, 2019. http://dx.doi.org/10.7566/jpscp.24.011040.

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Kunimi, Yusuke, Hideki Tenzou, Ayumi Nagoshi, Kai Yokoyama, Tatsuhiko Miyatake, and Shiho Tokutake. "Development of an Educational Tool for Radiation Shielding by Using a Mock Survey Meter." In 2018 IEEE Nuclear Science Symposium and Medical Imaging Conference (NSS/MIC). IEEE, 2018. http://dx.doi.org/10.1109/nssmic.2018.8824377.

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Bordy, Jean-Marc, Valentin Blideanu, Arnaud Chapon, Gabriel Dupont, Dorin Dusciac, Jean Gouriou, Frederic Laine, and Maiwenn Le Roy. "Primary reference in terms of air kerma for ionizing radiation fields produced by an electrostatic electron accelerator." In 19th International Congress of Metrology (CIM2019), edited by Sandrine Gazal. Les Ulis, France: EDP Sciences, 2019. http://dx.doi.org/10.1051/metrology/201915003.

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Based on a radiation field produced by an electrostatic accelerator, a radiation survey meter test and calibration facility has been designed and characterized in terms of air kerma and ambient dose equivalent. The electron beam impinges a tantalum target to produce X-rays. The spectrum has been measured and calculated. Traceability to the International System of units is achieved by means of a calibration with a primary dosimeter for air kerma.

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Sasaki, Michiya, Haruyuki Ogino, Takeshi Ichiji, and Takatoshi Hattori. "Verification Test of Clearance Automatic Laser Inspection System for Surface Contamination Measurement." In ASME 2009 12th International Conference on Environmental Remediation and Radioactive Waste Management. ASMEDC, 2009. http://dx.doi.org/10.1115/icem2009-16109.

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Recently, a clearance automatic laser inspection system (CLALIS) has been developed for clearance measurement of scrap metals and concrete debris. It utilizes three-dimensional laser scanning, gamma-ray measurement and Monte Carlo calculation, and its outstanding detection ability has been verified. In Japan, when an object is removed from a radiation-controlled area, the activity level must be lower than the surface contamination density standard of 4 Bq/cm2 for beta and gamma emitters, which is one-tenth of the surface contamination density limit. According to the clearance inspection report published by the Nuclear Safety Commission of Japan, the activity level of waste must be compared with not only the clearance level but also the surface contamination density standard for clearance inspection. To demonstrate that CLALIS can also be used for the measurement of surface contamination, a verification test was carried out using actual metal waste samples of various shapes, sizes and activity levels at Kashiwazaki-Kariwa Nuclear Power Station of Tokyo Electric Power Company. As a result, it was clarified that CLALIS gives a conservative value for surface contamination compared with the conventional GM survey meter measurement. This because the activities of metal waste samples were estimated using the total count rate, a fixed average surface area of 100 cm2 and the conservative source position assumed in the Monte Carlo calculation for the calibration factor. In a nuclear power plant, the actual judgment of whether an object can removed from a radiation-controlled area is based on whether the result of surface contamination measurement is lower than the detection limit, which is significantly lower than 4 Bq/cm2. According to this criterion, CLALIS provides an almost identical judgment to the GM survey meter, which means that CLALIS can be used as a rational clearance monitor to carry out clearance level and surface contamination inspections in a single radiation measurement. The prospective detection limit for CLALIS at nuclear power plants is also discussed and compared with that for the conventional surface contamination monitors.

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Hattori, Takatoshi, and Michiya Sasaki. "Development of Waste Monitor of Clearance Level to Ensure Social Reliance on Recycled Metal From Nuclear Facilities." In ASME 2003 9th International Conference on Radioactive Waste Management and Environmental Remediation. ASMEDC, 2003. http://dx.doi.org/10.1115/icem2003-4534.

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Metal and concrete wastes in the decommissioning of nuclear facilities are classified according to their radioactivity level after decontamination. Radioactive waste below the clearance level (e.g., 0.4Bq.g−1 for Co-60 in Japan) can be disposed of as general industrial waste or recycled. Metal wastes mainly originate from equipment in buildings, except for the metal bars in reinforced concrete. Since contaminated equipment must be decontaminated after dismantling, the main target of measurement would be fragments of equipment, of various shapes, numbers and sizes. In order to transport such metallic fragments out of controlled areas, a surface contamination survey must be performed to confirm that the contamination level is below the legal standard level (e.g., 4Bq.cm−2 for beta or gamma emitters in Japan) in addition to satisfying the clearance level. Taking account of social reliance on recycled metal after inspection of the clearance level and the surface contamination level, it is important to remove the possibility of overlooking contamination above these levels in the recycled metal. The measurement of beta rays is suitable for determining surface contamination on metal because almost none of the beta particles from inside the metal can be detected and the detected radiation can be mostly limited to that from the surface. This is the reason why a survey meter for measuring surface contamination has a detector with a higher sensitivity for beta particles than for gamma rays. Considering the characteristics of the survey meter, it may be difficult to measure the contamination level of the surface of a metal fragment, particularly when the surface is not flat. Moreover, in the case of internal contamination of a small metal pipe, measurement is impossible. The permeability of gamma rays is much greater than that of beta particles. Therefore, gamma rays can be detected even from internal contamination in metal. For gamma ray measurement, accurate and easy calibration of the actual radioactivity level and count rate obtained using a measurement instrument is important. If gamma ray measurement can confirm that the radioactivity level is less than about 400Bq, both the clearance level and the surface contamination level could be inspected simultaneously. In addition, the great amount of labor needed for manual inspection using a survey meter could be saved, and there will be no possibility of missing hot spots of radioactivity due to human error. In this study, a new technique for precise and automatic measurement of gamma emitters in metal waste has been developed using 3D noncontact shape measurement and Monte-Carlo calculation techniques to objectively confirm that the specific radioactivity level of metal waste satisfies the clearance level and furthermore, that the surface contamination level of the metal waste is below the legal standard level. The technique can yield a calibration factor for every measurement target automatically and realizes automatic correction for the reduction of the background count rate in gamma measurements due to the self-shielding effect of the measurement target. A practical monitor (Clearance Automatic Laser Inspection System, CLALIS) has been developed. The accuracy of the automatic calibration and correction of background reduction of the practical monitor has been clarified using mock metal wastes of various shapes, numbers and sizes. It was found that the values measured using the present monitor and the actual radioactivity level agreed within +/−20%, and the corrected and actual background reductions agreed within +/−2%. The detection limit of the present monitor was estimated as being 100Bq for Co-60, taking into consideration the calibration error and correction error of the reduction of the background count rate. The monitor accomplished precise measurements with a 100sec (30sec for gamma ray measurement, 30sec for background measurement) process time per inspection. This indicates that approximately 5 tons of metal waste can be measured per day (1,000 tons per year) in 20kg batches at that process speed.

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Davies, Mike, Robert Clark, and Ian Adsley. "High-Density Gamma Radiation Spectrometry Surveys of Contaminated Land." In ASME 2011 14th International Conference on Environmental Remediation and Radioactive Waste Management. ASMEDC, 2011. http://dx.doi.org/10.1115/icem2011-59076.

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The design of gamma radiation surveys of contaminated land has always had to compromise between the density of sampling and the accuracy of measurement. Large-area contamination is readily detected by a variety of measurement techniques, while the detection of small areas or ‘particles’ requires a high density of measurement, generally one measurement per square metre. High Resolution Gamma-radiation Spectrometry (HRGS) can provide accurate qualitative (radionuclide identification) and quantitative (Bq.g−1 of the radionuclide for a stated scenario) assessment of the state of the land, but are not cost effective at high density. In contrast, simple walk-over or ‘scan’ surveys using standard Health Physics instruments can provide a high density of measurement, but cannot provide the qualitative and quantitative accuracy of HRGS. In 1996, Nuvia Limited adopted methods to address some of these issues, by allowing scan surveys to include a degree of qualitative analysis of the gamma radiation detected using Low Resolution Gamma-radiation Spectrometry systems with Sodium Iodide detectors, while maintaining a high density of measurement. While low-resolution systems (including medium-resolution Lanthanum Bromide) have become the de-facto standard for large area land surveys, the use of the technology has changed little. High density scan surveys can be conducted using, for example, simple gross-gamma techniques, doserate or region-of-interest logging. However, if spectra are required for qualitative purposes, they are normally collected at fixed locations and for inconveniently long counting periods. The ideal would be to collect spectra at every measurement location, preferably once per second, and then ‘aggregate’ the spectra using spatially-aware techniques. This would allow a scan survey to be performed rapidly, while losing no spectral information. It would thus be possible to analyse the data in a number of ways, for example, producing justifiable doserate measurements or using neural-network techniques to search the measurements for spectral anomalies. This paper describes the work done by Nuvia to develop a system to collect spectra efficiently and to make the spectra readily available for a number of analyses. The efficiency of spectrum acquisition and compression are discussed, along with methods of managing the potentially large volumes of data. The analysis of the data, using a customised Geographical Information System is described, including spatial aggregation of spectra and semi-automatic analysis of spectral structure for identifying common ‘background’ features. Examples of the use of these facilities in Nuvia’s ‘Groundhog’ site survey service are provided.

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Hussain, Mazzammal, Salah Ud-Din Khan, and Waqar A. Adil Syed. "Estimation of Emergency Planning Zones (EPZs) for Nuclear Research Reactor Using Plume Dispersion Code." In 2012 20th International Conference on Nuclear Engineering and the ASME 2012 Power Conference. American Society of Mechanical Engineers, 2012. http://dx.doi.org/10.1115/icone20-power2012-54964.

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After Fukushima nuclear power plant accident, a demand for re-evaluation of emergency planning zones for nuclear facilities has emerged to ensure that in case of nuclear accident, the population, the environment and the property should lie in the safe zone. Emergency planning zones (EPZs) around a facility are the designated areas where protective measures are adopted according to predefined emergency plan for different emergency situations. Deterministic and probabilistic approaches have been adopted to assess and design emergency planning zones for design base accidents (DBAs), however, after Fukushima nuclear power plant accident, multi-layer failure of the plant systems could not be ruled out. To estimate the dispersion of radioactive material and respective radiation doses received by the affected people, different techniques are used including on-field measurements through survey meters, on-line monitoring network and state-of the art codes for plume dispersion modeling. In this study plume dispersion modeling and estimation of emergency planning zones has been carried out using plume dispersion code for hypothetical accident scenarios at a 10MW nuclear research reactor. Different accident scenarios were considered with different release characteristic and environmental conditions to study the affect of the parameters including release height, heat content, release time, atmospheric stability. The simulation results have been analyzed to assess the existing emergency planning zones of nuclear research reactor.

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Falnes, Johannes. "Wave-Energy Conversion Avoiding Destructive Wave Interference." In ASME 2017 36th International Conference on Ocean, Offshore and Arctic Engineering. American Society of Mechanical Engineers, 2017. http://dx.doi.org/10.1115/omae2017-62617.

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Many of the various proposed wave-energy converter (WEC) units are immersed oscillating bodies, which, in the primary conversion stage, collect input power as the product of two oscillating factors, a velocity and wave-induced force. The latter factor is vulnerable to destructive wave interference, unless the extension of each WEC unit is sufficiently small. Two simple, elementary-mathematical, inequalities express two kinds of upper bounds for the wave power that may be absorbed by an oscillating immersed body. The first upper bound, published in the mid 1970s, is well-known, in contrast to the second one, Budal’s upper bound, which was derived a few years later, and which takes the WEC’s hull volume into consideration. Combining the two different upper bounds and considering also a typical wave climate, we may conclude that for a WEC array plant deployed in the North Atlantic, each point-absorber WEC unit volume should typically be about 300 cubic metre, and its primary-converted power take-off (PTO) capacity should be in the range of 50 to 300 kW. These heaving WEC units, being monopole wave radiators, may have a much higher PTO-capacity-to-immersed-hull-wet-surface ratio than any other type of WEC unit, such as those using dipole-mode (e.g. surge- or pitch-mode) radiation. For large-scale utilization of wave energy, arrays of WEC units are required.

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