Instrument evaluation no. 33. Automess Szintomat 6134 radiation survey meter

International Nuclear Information System (INIS)

McClure, D.R.

1986-04-01

The various radiations encountered in radiological protection cover a wide range of energies and radiation measurements have to be carried out under an equally broad spectrum of environmental conditions. This report is one of a series intended to give information on the performance characteristics of radiological protection instruments, to assist in the selection of appropriate instruments for a given purpose, to interpret the results obtained with such instruments, and, in particular, to know the likely sources and magnitude of errors that might be associated with measurements in the field. The radiation, electrical and environmental characteristics of radiation protection instruments are considered together with those aspects of the construction which make an instrument convenient for routine use. To provide consistent criteria for instrument performance, the range of tests performed on any particular class of instrument, the test methods and the criteria of acceptable performance are based broadly on the appropriate Recommendations of the International Electrotechnical Commission. The radiations in the tests are, in general, selected from the range of reference radiations for instrument calibration being drawn up by the International Standards Organisation. Normally, each report deals with the capabilities and limitations of one model of instrument and no direct comparison with other instruments intended for similar purposes is made, since the significance of particular performance characteristics largely depends on the radiations and environmental conditions in which the instrument is to be used. The results quoted here have all been obtained from tests on instruments in routine production, with the appropriate measurements being made by the NRPB. This instrument evaluation report deals with the Automess Szintomat 6134 Radiation Survey Meter

Establishment of a procedure to calculate the measurement uncertainties in radiation survey meters calibration

International Nuclear Information System (INIS)

Manzoli, J.E.; Potiens, M.P.A.

2000-01-01

The Calibration Laboratory of Sao Paulo calibrates more than one thousand gamma ray survey meters a year; beside other kinds of radiotherapy, radiodiagnostic and radiation protection instruments. It has a standard (600 cm 3 ) cylinder ionization chamber (Nuclear Enterprises Ltd. model 2511/3) traceable to the Brazilian Secondary Standard Dosimetry Laboratory (SSDL) whose instruments are traceable to the BIPM. Annually the beam dosimetry is performed using this chamber and the results are used as the true values for calibration purposes. The uncertainties present in every direct or indirect measurement during the calibration procedure must be evaluated for purposes of laboratory quality control. All calculation steps in the propagation of errors are presented in this work staging from the ionization chamber charge measured with the standard instrument. Such a propagation was made in space and time, considering even the environmental quantities uncertainties. The propagation was necessary in space, because the ionization chamber measurements were performed at only one space position. The time propagation was essential due to the fact that the activity is a peculiar physical quantity which changes with time according to precise relations for a specific radionuclide. The clear indication of every measurement uncertainty is always important to quantify the quality of this measurement. Nowadays the achievement of calibration laboratory quality systems requires the expression of all uncertainties and the procedure used to evaluate it. An example of this procedure in the case of the calibration of a typical portable radiation survey meter is presented. The direct exposure rate instrument measurement was compared with the true value given by the standard instrument properly propagated and all quantities used have their uncertainties shown. (author)

User's guide for survey-meter- and film-badge-dosimetry data bases

International Nuclear Information System (INIS)

Phillips, W.G.; Sherman, S.; Young, R.

1981-05-01

This manual describes the data storage and retrieval system designed by Environmental Monitoring Systems Laboratory Las Vegas (EMSL-LV) for radiation exposure data recorded in offsite areas during and after nuclear weapons tests conducted at the Nevada Test Site in the 1950's and early 1960's. Referred to hereinafter as the EMSL-LV system, this system contains two distinct subsets of offsite radiological measurements collected during early nuclear atmospheric tests at the Nevada Test Site. The purpose of the manual is to present the methods for using the EMSL-LV system to examine all or any portion of either data subset. The two distinct subsets which comprise the EMSL-LV system are survey meter data and film badge dosimetry data. The survey meter data consist of readings obtained from portable radiation monitoring instruments used around the Nevada Test Site during the 1950's and early 1960's to measure radiation exposure rates resulting from the nuclear testing program. The dosimetry data consist of measurements of integrated radiation exposure made with film badge type dosimeters in areas surrounding the Nevada Test Site

A wide range survey meter for estimating γ- and β-dose rates

International Nuclear Information System (INIS)

Jones, A.R.

1980-09-01

A survey meter has been developed to measure β-dose rates in the range 0.1 - 100 rad/h (1 mGy/h - 1 Gy/h) and γ-dose rates in the range 1 mrad/h - 100 rad/h (10 μGy/h-1 Gy/h). It also provides an audible warning of high γ-dose rates and an audible and visible warning when a predetermined γ-dose is exceeded. The report describes the design of the survey meter and presents data measured on the performance of an engineering prototype. Factors which affect performance and have been investigated are temperature, battery voltage (and type of battery), GM counter counting loss, direction of incident radiation, and energy of γ-rays. Finally, the application and calibration of the survey meter are discussed. (auth)

Operational problems with radiation survey meters - The University and Accelerator perspectives

International Nuclear Information System (INIS)

McCall, R.C.

1984-06-01

This article describes problems encountered with commercial survey meters. The desired qualities of such instruments for use around accelerators are listed. Attempts to meet the accelerator monitoring needs by modifying commercial instruments and by in-house research and development are described

Examination of the long-term stability of radiation survey meters and electronic pocket dosemeters

International Nuclear Information System (INIS)

Chida, K.; Nishimura, Y.; Sato, Y.; Endo, A.; Sakamoto, M.; Hoshi, C.; Zuguchi, M.

2008-01-01

To describe the stability of radiation survey meters (RSMs) and electronic pocket dosemeters (EPDs), we examined 28 EPDs and 24 RSMs: 12 used NaI(Tl) scintillation RSMs and 12 used Geiger-Muller (GM) RSMs. We used simple methods for the relative calibration of the 24 RSMs and 28 EPDs. The RSM and EPD measurements were compared with a calibrated RSM and EPD (reference: traceable from the national standard of exposure) using a homemade measurement device to maintain the reproducibility of the measurements with reference radiation sources (i.e. 137 Cs, 90 Sr and 67 Ga). The response of RSMs and EPDs, especially after prolonged use, should be checked periodically. In particular, GMRSMs that have been in use for many years have very low sensitivity and poor reproducibility. Our simple method for the relative calibration of RSMs and EPDs was shown to be effective for quality assurance purposes in checking RSMs and EPDs. We recommend regular checks and calibration for sustained performance of RSMs and EPDs. (authors)

A convenient calibrator for tritium survey meters

International Nuclear Information System (INIS)

Cutler, J.M.; Janmohamed, S.R.; Surette, R.A.; Wood, M.J.

1993-06-01

Staff in Ontario Hydro's CANDU nuclear power stations were having difficulty calibrating their tritium-in-air survey meters. Chalk River Laboratories suggested using a standard silica gel collector loaded with tritiated water vapour as a radiation source. The collector is a polyethylene tube with a length of rubber tubing attached to each end. The plastic tube is filled with dry silica gel, and cotton wool is stuffed into each end to retain the gel. To load the source with tritiated vapour, a bubbler containing tritiated water is connected to the collector until the gel is completely pink. The end tubes of the source are then connected to each other to seal the source. To use the source, the rubber tubes are connected to the intake and exhaust fittings of the survey meter to be calibrated. No tritium vapour is released during loading or calibration. This source not only verifies that the ion chamber and electrometer are working, but also checks whether the air sample is reaching the detector. It is more direct and credible than a gamma source, and is inexpensive and convenient to construct and calibrate at the power station. 5 figs

Calibration of ionization chamber and GM counter survey meters, (1)

International Nuclear Information System (INIS)

Bingo, Kazuyoshi; Kajimoto, Yoichi; Suga, Shin-ichi

1978-01-01

Three types of ionization chamber survey meters and a type of GM counter survey meter were calibrated for measuring the β-ray absorbed dose rate in a working area. To estimate the β-ray absorbed dose rate, a survey meter was used without and with a filter. A reading of survey meter's indicator measured with the filter was subtracted from a reading measured without the filter, and then the absorbed dose rate was obtained by multiplying this remainder by a conversion coefficient. The conversion coefficients were roughly constant with distance more than 8 cm (ionization chamber survey meters) and with distance more than 5 cm (GM counter survey meter). The conversion coefficient was dependent on β-ray energies. In order to measure the absorbed dose rate of tissue whose epidermal thickness is 40 mg/cm 2 , the constant value, 4 (mrad/h)/(mR/h), was chosen independently of β-ray energies as the conversion coefficient of three types of ionization chamber survey meters. The conversion coefficient of the GM counter survey meter was more energy dependent than that of every type of ionization chamber survey meter. (author)

Development of a hand-held fast neutron survey meter

International Nuclear Information System (INIS)

Yoshida, T.; Tsujimura, N.; Yamano, T.

2011-01-01

A neutron survey meter with a ZnS(Ag) scintillator to measure recoil protons was built. The detection probe weighs ∼2 kg, therefore providing us with true portability. Performance tests exhibited satisfactory neutron dosimetry characteristics in unmoderated or lightly moderated fission neutron fields and in particular work environments at a mixed oxide fuel facility. This new survey meter will augment a routine of neutron monitoring that is inconveniently being carried out by moderator-based neutron survey meters. (authors)

Potential radiation doses likely to be received by the radiologists and paramedical staff in typical hospital in Pakistan (GM counter, survey meter measurements) (abstract)

International Nuclear Information System (INIS)

Ali, A.; Zeb, J.; Iqbal, S.; Orfi, S.D.

1998-01-01

Potential radiation doses likely to be received by the radiologists and para medical staff in a typical hospital in Pakistan have been measured using a very sensitive radiation survey meter (FAG FH40F2) employing a Geiger Muller counter (FHZ120) as a probe which is a probe extend able up to 4 meters in length. These measurements have been compared with internationally accepted Maximum Permissible Radiation Dose Level (MPDL). Radiation dose rates measured on the hands of two radiologists during fluoroscopy examination of the patient were of the order of 1mSv.h/sup -1/ and 540 mu Sv.h/sup -1/ which were 400% to 216% times higher than the MPDL (250 mu Sv.h/sup -1/). Radiation dose rates measured on the chest and neck were 300 and 50 mu Sv.h/sup -1/, which were 3000% to 500% times higher than those of MPDL (10 mu Sv.h/sup -1/. Such high dose rates present a serious situation and deserve attention of the hospital management and of national regulatory authority so as to minimize the potential radiation doses to the radiologists and para medical staff. As Low As Reasonably Achievable (ALARA) concept should be implemented in the health sector. (author)

WE-F-209-02: Radiation Safety Surveys of Linear Accelerators

International Nuclear Information System (INIS)

Martin, M.

2016-01-01

Over the past few years, numerous Accreditation Bodies, Regulatory Agencies, and State Regulations have implemented requirements for Radiation Safety Surveys following installation or modification to x-ray rooms. The objective of this session is to review best practices in performing radiation safety surveys for both Therapy and Diagnostic installations, as well as a review of appropriate survey instruments. This session will be appropriate for both therapy and imaging physicists who are looking to increase their working knowledge of radiation safety surveys. Learning Objectives: Identify Appropriate Survey Meters for Radiation Safety Surveys Develop best practices for Radiation Safety Surveys for Therapy units that include common areas of concern. Develop best practices for Radiation Safety Surveys of Diagnostic and Nuclear Medicine rooms. Identify acceptable dose levels and the factors that affect the calculations associated with performing Radiation Safety Surveys.

Potential radiation doses likely to be received by the radiologists and para medical staff in an hospital in Pakistan. (G. M. counter, survey meter measurements )

International Nuclear Information System (INIS)

Ali, A.; Zeb, J.; Iqbal, S.; Orfi, S.D.

1999-01-01

Potential radiation doses likely to received by the radiologists and paramedical staff in a typical hospital in Pakistan have been measured using a very sensitive radiation survey meter (FAG FH40F2) employing in Geiger Muller counter (FHZ 120] as a role which is extendable up to 4 meters in length. The measurements have been compared with internationally accepted Maximum Permissible Radiation Dos Level (MPDL). Radiation dose rates measured on the hands of two radiologist during fluoroscopy examination of the patient were of the order of 1 m Sv.h/sup -1/ and 540 u Sv. h/sup -1/ which were 400% to 21% higher than the MPDL (250 u Sv. h/sup -1/). Radiation dose rates measured on the chest of the nurses were 300 and 50 u Sv. h/sup -1/, which were 3000% to 500% higher than those of MPDL(10 u Sv. h/sup -1/). Such high dose rates present a serious situation from radiation damage point of view and deserve attention of the hospital management and of national regulatory authority so as to minimize the potential radiation doses to the radiologists and paramedical staff. As Low As Reasonably Achievable (ALARA) concept should be implemented in the health sector. (author)

Status of neutron monitoring meters for radiation protection purpose

International Nuclear Information System (INIS)

Li Taosheng

2003-01-01

The status of and trends towards the development of neutron monitoring meters, such as dose survey meter, workplace (ambient) spectrometer and individual dosimeters, are discussed in the present paper from the perspectives of workplace and individual dose monitoring. Over the past 4 decades, both neutron dose survey meter and workplace spectrometer have declined to be more reasonable in design of their probes, with more broaden applications. With the development of electronic technology, there is a trend towards being more small-compacted and smart. Although many technical difficulties in the practical measurement, some significant progresses have be made in the development and research of these kinds of meters. (authors)

Critical review of directional neutron survey meters

International Nuclear Information System (INIS)

Balmer, Matthew J.I.; Gamage, Kelum A.A.; Taylor, Graeme C.

2014-01-01

Having been overlooked for many years, research is now starting to take into account the directional distribution of the neutron work place field. The impact of not taking this into account has led to overly conservative estimates of dose in neutron workplace fields. This paper provides a critical review of this existing research into directional survey meters which could improve these estimates of dose. Instruments which could be adapted for use as directional neutron survey meters are also considered within this review. Using Monte-Carlo techniques, two of the most promising existing designs are evaluated; a boron-doped liquid scintillator and a multi-detector directional spectrometer. As an outcome of these simulations, possible adaptations to these instruments are suggested with a view to improving the portability of the instrument. -- Highlights: • We critically review the existing literature into directional survey meters. • Instruments which could be adapted for this purpose are also reviewed. • Investigate the potential of much lighter portable real-time instrument. • Improvements to existing instruments are suggested to improve their design. • Boron-Doped liquid scintillator design is the most promising, but needs further work

β-ray scintillation survey meter for small-sized pipes

International Nuclear Information System (INIS)

Yamano, Toshiya; Suzuki, Toshikazu; Yoshida, Yoshiteru; Higashidate, Takamichi; Yonemura, Kenji; Fujita, Michio.

1990-01-01

The outer surface of the small-sized pipes used as scaffolding is measured by beta/gamma survey meter when they are carried out from the controlled area in nuclear facilities. But, the measurement of the radioactive contamination on the inner surface, when it is needed, is done indirectly using the smear method. To improve these vexatious works, Fuji Electric Co., Ltd. and Chubu Electric Power Co., Inc. jointly developed a beta-ray scintillation survey meter which, when inserted directly into pipes, can detect radioactive contamination on the inner surface. This detector is made of cylindrical plastic scintillator and it can measure low energy beta-ray by using the coincidence method which reduces random noise. A field test carried out with this prototype survey meter brought favorable results for designing its final version. (author)

An energy-independent dose rate meter for beta and gamma radiation

International Nuclear Information System (INIS)

Heinzelmann, M.; Keller, M.

1986-01-01

An easy to handle dose rate meter has been developed at the Juelich Nuclear Research Centre with a small probe for the energy-independent determination of the dose rate in mixed radiation fields. The dose rate meter contains a small ionisation chamber with a volume of 15.5 cm 3 . The window of the ionisation chamber consists of an aluminised plastic foil of 7 mg.cm -2 . The dose rate meter is suitable for determining the dose rate in skin. With a supplementary depth dose cap, the dose rate can be determined in tissue at a depth of 1 cm. The dose rate meter is energy-independent within +-20% for 147 Pm, 204 Tl and 90 Sr/ 90 Y beta radiation and for gamma radiation in the energy range above 35 keV. (author)

Usage and conditions of radiation protection of nuclear meters in Brazil

International Nuclear Information System (INIS)

Guimarães, E.F.; Silva, F.C.A. da

2017-01-01

The industries of mining, pulp, oil, etc. which require a quality control in the processes, use the nuclear meters with sealed radioactive sources coupled to a radiation detector that generate accurate and fast answers regarding the level, thickness, density and humidity of different types of materials. Nuclear meters are classified as fixed or portable and use transmission, backscatter or reactive systems. As they use radioactive sources with various ranges of activities, they are classified by the International Atomic Energy Agency - AIEA as Category 3 and 4, of medium and low radiological risk, and must therefore have a suitable level of radiation protection for safe use in the installation. The Brazilian National Energy Commission - CNEN controls approximately 500 authorized facilities with nuclear meters. The paper technically describes the nuclear meters and the radiological protection procedures that must be followed for the safety of the IOEs (occupationally exposed individuals) and individuals from the public, based on the specific nuclear meter test program for CNEN radiation protection supervisor. The professionals who handle these nuclear meters should be aware of the radiological risk to their own protection and to individuals in the public. For safe operation with nuclear meters, a number of requirements must be observed according to the type and need of the installation

Gamin partable radiation meter with alarm threshold

International Nuclear Information System (INIS)

Payat, Rene.

1981-10-01

The Gamin Radiation meter is a direct reading, portable, battery-powered gamma doserate meter featuring alarm thresholds. Doserate is read on a micro-ammeter with a millirad-per-hour logarithmic scale, covering a range of 0,1 to 1000 millirads/hour. The instrument issues an audible warning signal when dose-rate level exceeds a threshold value, which can be selected. The detector tube is of the Geiger-Muller counter, energy compensated type. Because of its low battery drain, the instrument can be operated continously for 1000 hours. It is powered by four 1.5 volt alcaline batteries of the R6 type. The electronic circuitry is housed in a small lightweight case made of impact resistant plastic. Applications of the Gamin portable radiation monitor are found in health physics, safety departments, medical facilities, teaching, civil defense [fr

Induced radioactive nuclides of 10-MeV radiotherapy accelerators detected by using a portable Hp-Ge survey meter

International Nuclear Information System (INIS)

Fujibuchi, T.; Obara, S.; Yamaguchi, I.; Oyama, M.; Watanabe, H.; Sakae, T.; Katoh, K.

2012-01-01

The radioactivation of linear accelerator components for radiation therapy is interest for radiation protection in general, and particularly, when decommissioning these structures. The energy spectra of gamma rays emitted from the heads of two accelerator models, EXL-15SP and Clinac iX, after 10-MeV X-ray irradiation, were measured using a high-purity germanium semiconductor survey meter. After spectrum analyses, activities of 24 Na, 28 Al, 54 Mn, 56 Mn, 57 Ni, 58 Co, 60 Co, 64 Cu, 65 Zn, 122 Sb, 124 Sb, 181 W, 187 W, 196 Au, and 198 Au were detected. One centimetre deep dose-equivalent rate of the heads of the linear accelerator was measured using the survey meter. The dose rate decreased to ∼10 % of its initial rate after 1 week. Long-term activations were few, the radioactivity level was low, and a cooling time of several days was effective for reducing dose rate to an acceptable level for decommissioning. (authors)

Critical review of directional neutron survey meters

Science.gov (United States)

Balmer, Matthew J. I.; Gamage, Kelum A. A.; Taylor, Graeme C.

2014-01-01

Having been overlooked for many years, research is now starting to take into account the directional distribution of the neutron work place field. The impact of not taking this into account has led to overly conservative estimates of dose in neutron workplace fields. This paper provides a critical review of this existing research into directional survey meters which could improve these estimates of dose. Instruments which could be adapted for use as directional neutron survey meters are also considered within this review. Using Monte-Carlo techniques, two of the most promising existing designs are evaluated; a boron-doped liquid scintillator and a multi-detector directional spectrometer. As an outcome of these simulations, possible adaptations to these instruments are suggested with a view to improving the portability of the instrument.

Critical Review of Directional Neutron Survey Meters

International Nuclear Information System (INIS)

Balmer, M.J.I.; Gamage, K.A.A.; Taylor, G.C.

2013-06-01

Having been overlooked for many years, research is now starting to take into account the directional distribution of the neutron work place field. The impact of not taking this into account has led to overly conservative estimates of dose in neutron workplace fields. This paper provides a critical review of this existing research into directional survey meters which could improve these estimates of dose. Instruments which could be adapted for use as directional neutron survey meters are also considered within this review. Using Monte-Carlo techniques, two of the most promising existing designs are evaluated; a boron-doped liquid scintillator and a multi-detector directional spectrometer. As an outcome of these simulations, possible adaptations to these instruments are suggested with a view to improving the portability of the instrument. (authors)

A study of the responses of neutron dose equivalent survey meters with computer codes

International Nuclear Information System (INIS)

Sartori, D.E.; Beer, G.P. de

1983-01-01

The ANISN and DOT discrete-ordinates radiation transport codes for one and two dimensions have been proved as effective and simple techniques to study the response of dose equivalent neutron detectors. Comparisons between results of an experimental calibration of the Harwell 95/0075 survey meter and calculated results rendered satisfactory agreement, considering the different techniques and sources of error involved. Possible improvements in the methods and designs and causes of error are discussed. (author)

Do dose area product meter measurements reflect radiation doses ...

African Journals Online (AJOL)

Enrique

SA JOURNAL OF RADIOLOGY • August 2004. Abstract. This study determined the correlation between radiation doses absorbed by health care workers and dose area product meter (DAP) measurements at Universitas Hospital, Bloemfontein. The DAP is an instrument which accurately measures the radiation emitted from ...

Do dose area product meter measurements reflect radiation doses ...

African Journals Online (AJOL)

This study determined the correlation between radiation doses absorbed by health care workers and dose area product meter (DAP) measurements at Universitas Hospital, Bloemfontein. The DAP is an instrument which accurately measures the radiation emitted from the source. The study included the interventional ...

Handheld Multi-Gas Meters Market Survey Report

Energy Technology Data Exchange (ETDEWEB)

Williams, Gustavious [Brigham Young Univ., Provo, UT (United States); Wald-Hopkins, Mark David [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Obrey, Stephen J. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Akhadov, Valida Dushdurova [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2016-06-23

Handheld multi-gas meters (MGMs) are equipped with sensors to monitor oxygen (O2) levels and additional sensors to detect the presence of combustible or toxic gases in the environment. This report is limited to operational response-type MGMs that include at least four different sensors. These sensors can vary by type and by the chemical monitored. In real time, the sensors report the concentration of monitored gases in the atmosphere near the MGM. To provide emergency responders with information on handheld multi-gas meters, the System Assessment and Validation for Emergency Responders (SAVER) Program conducted a market survey. This market survey report is based on information gathered between November 2015 and February 2016 from vendors, Internet research, industry publications, an emergency responder focus group, and a government issued Request for Information (RFI) that was posted on the Federal Business Opportunities website.

Portable radiation meters evaluation in high rates of air kerma

International Nuclear Information System (INIS)

Damatto, Willian B.; Potiens, Maria da Penha A.; Vivolo, Vitor

2015-01-01

A set of portable meters of ionizing radiation high rates of air kerma (teletectors) commonly used in emergencies in Brazil and sent to the Calibration Laboratory of IPEN were under several tests and analyst is parameters for the detectors behavior were established, specifying their sensitivities and operating characteristics. Applied tests were: reading equipment variation with battery voltage, geotropism effect, energy dependence, the angular dependence and overload. Thus it was possible to determine the most common characteristic found in these equipment (quality control programs). The behavior of 17 portable meters was analyzed and in this study, 10 of them have been tested. It was performed to characterize the gamma irradiating system (radiation dosimetry field) that possesses higher activity in teletectors for testing of larger measuring range. New calibration criteria were established following international recommendations. Therefore, it was made the improvement of the quality control programme of portable meters of ionizing radiation high rates of air kerma calibration laboratory, benefiting the users of such equipment with better consistent calibration measurements. (author)

Determination for energy response and directionality of neutron survey meters

International Nuclear Information System (INIS)

Chen Changmao; Liu Jinhua; Xie Jianlun; Su Jingling

1992-01-01

The energy response and directionality of neutron survey meter type MK7 and 2202D are determined. The reactor thermal column beam, reactor filtered beams (6 eV, 24.4 keV and 144 keV), 226 Ra-Be, 241 Am-Be, 252 Cf and its moderated sources are used for the measurement. The results shows: the survey meters are influenced obviously by the direction; the response of middle-energy region is large, the energy response of 2202D is better than MK7

Establishment of an X radiation equipment quality control programme using non invasive meters

International Nuclear Information System (INIS)

Lucena, Rodrigo Ferreira de

2010-01-01

The objective of this work was to study the behavior of the mainly X ray equipment calibration laboratory of IPEN, operated in the range from 25 kV to 150 kV using a PTW non invasive meter, model Diavolt TM , and an ORTEC spectrometry system, model NOMAD-PLUS 92X, for the establishment of a quality control programme. The Diavolt meter was used for measurements of air kerma, peak voltage and practical peak voltage. The measurements were made varying parameters such as electrical current, X radiation quality for radiation diagnostic, angulations of the meter and its distance in relation to the focal spot of the X ray tube. The results were compared with data found in the literature. Several spectra were generated with the spectrometer system with the purpose of determine the peak voltage in function of the nominal voltage and to characterize the radiation qualities for radiation diagnostic previously determined. The established quality control programme enables the management of the appropriate functioning of the measurement instruments (ionization chambers, voltage and current meter and spectrometer) as well as of the X radiation system. This work also has proposed a time interval to run each one of the tests. (author)

Survey of environmental radiation dose rates in Tokushima prefecture

International Nuclear Information System (INIS)

Sakama, Minoru; Imura, Hiroyoshi; Akou, Natsuki; Takeuchi, Emi; Morihiro, Yukinori

2004-01-01

Survey of environmental radiation dose rates in Tokushima prefecture has been carried out using a portable NaI (Tl) scintillation survey meter and a CsI(Tl) pocket type one. To our knowledge, previous several surveys in Tokushima, for example by Abe et al. (1982) and Yoshino et al. (1991), have remained to report the environmental radiation dose rates merely about the major cities, that is Tokushima City and others along the Pacific. Up to now, there have been few efforts to survey the environmental radiation dose rates about mountain valleys in Tokushima. In this work, it is remarkable that we have for the first time made surveys of environmental radiation dose rates on the 6 routes across the Sanuki mountains and inside the pier of Onaruto Bridge, 'Naruto Uzu-no-michi', in the northern area of Tokushima. In the course of present surveys, the maximum value of the environmental radiation dose rates was 0.117±0.020 μGy/h at Higetouge in Sanuki City, and then it was found that the radiation dose rates across the Sanuki mountains tend to increase slightly with approaching Kagawa area from Tokushima one. Considering geological formation around the northern side of Sanuki mountains, there are mainly geological layers of granodiorite containing in the substantial amount of naturally occurring radionuclides, 40 K, U-series, and Th-series, than other geological rocks and it was found that the terrestrial gamma-rays have effect on the environmental radiation dose rates according to the geological formation. (author)

Measurement of ambient dose equivalent H*(10) and directional dose equivalent H'(0.07) with pocket sized survey meters

International Nuclear Information System (INIS)

Iwatschenko, Michael

2008-01-01

Full text: In many parts of the world, predominantly in Europe, small sized survey meters based on Geiger-Mueller or proportional counters are widely used for dose rate and dose equivalent rate measurements, while in other regions, especially in the U.S., ionisation chambers are preferred for this task. This paper tries to shed some light on the likely reasons for these two diverging instrumental inclinations. Their respective strengths and weaknesses is analyzed in respect to energy response, dose rate measuring range, size, weight and susceptibility to environmental influences. Furthermore the response and limitations regarding the measurement of pulsed radiation (medical X-ray and CT-devices, accelerators, non-destructive testing) is discussed. A newly developed pocket size instrument based on a pan-cake Geiger-Mueller tube is used as an example to explain the capability and flexibility of modern survey meters. The RadEye B20 is a compact multi-purpose dose rate meter and contamination meter for alpha, beta, gamma and X-ray radiation. By virtue of carefully designed multi-layer gamma energy filters, H*(10) (deep dose) or H'(0,07) (shallow dose) measurements from 17 - 1300 keV can be performed. The instrument can even be worn in a belt holster, so that the impact to the mobility of the user is minimized. For emergency response purposes alpha and beta contamination can be discriminated using another optional filter; a simple sample changer adapter can extend the scope of application. Immediate and reproducible counter measurements, e.g. of smear tests can be performed locally. (author)

Radiation survey of aircraft and heavy machinery scrap.

Science.gov (United States)

Idriss, Hajo; Salih, Isam; Gumaa, Elsadig; Yassin, Abbas; Yousif, E H; Abdel Hamid, Saad Eldeen M; Sam, A K

2012-12-01

This study was conducted primarily to survey aircraft and heavy machinery at 30 locations within Khartoum State using handheld radiation survey meters to detect and identify any radiation sources that might be present and to estimate radiation dose levels. The survey has resulted in detection of 16 sealed sources of (90)Sr and one of (226)Ra in aircraft scrap. Of course, (90)Sr sources are used in military aircraft as temperature sensors while (226)Ra is used for indicating fuel levels. These sources were found intact without spreading radioactivity contamination; however, none was detected in heavy machine scrap. The levels of radiation dose measured at 0.1m from the source fall within the range of 25.1-40.2 μSv/h with an average value of 33.52 ± 4.06 μSv/h. These orphan sources have been separated from the scrap, tested for possible leakage, conditioned and stored in waste management facility. The result of this study has revealed without doubt that the scrap constitute a serious source of public exposure and highlights the importance of legislation making radiation monitoring of scrap in the country mandatory before it is sold to metal industry for reprocessing. Copyright © 2012 Elsevier Ltd. All rights reserved.

Production of plastic scintillation survey meter for clearance verification measurement

International Nuclear Information System (INIS)

Tachibana, Mitsuo; Shiraishi, Kunio; Ishigami, Tsutomu; Tomii, Hiroyuki

2008-03-01

In the Nuclear Science Research Institute, the decommissioning of various nuclear facilities is carried out according to the plan for meeting the midterm goal of the Japan Atomic Energy Agency (JAEA). An increase in the clearance verification measurement of concrete on buildings and the radiation measurement for releasing controlled areas will be expected along with the dismantlement of nuclear facilities in the future. The radiation measurement for releasing controlled areas has been carried out in small-scale nuclear facilities including the JPDR (Japan Power Demonstration Reactor). However, the radiation measurement with an existing measuring device was difficult in effects of radiation from radioactive materials that remains in buried piping. On the other hand, there is no experience that the clearance verification measurement is executed in the JAEA. The generation of a large amount of clearance object will be expected along with the decommissioning of the nuclear facilities in the future. The plastic scintillation survey meter (hereafter, 'PL measuring device') was produced to apply to the clearance verification measurement and the radiation measurement for releasing controlled areas. The basic characteristic test and the actual test were confirmed using the PL measuring device. As a result of these tests, it was found that the evaluation value of radioactivity with the PL measuring device was accuracy equal with the existing measuring device. The PL measuring device has feature of the existing measuring device with a light weight and easy operability. The PL measuring device can correct the gamma ray too. The PL measuring device is effective to the clearance verification measurement of concrete on buildings and the radiation measurement for releasing controlled areas. (author)

A neutron survey meter with sensitivity extended up to 400 MeV

International Nuclear Information System (INIS)

Birattari, C.; Silari, M.

1992-01-01

The well-known Andersson-Braun rem counter is widely employed for radiation protection purposes, but its efficiency shows a marked decrease for neutron energies above about 10 MeV. Since the availability of a survey meter with a good sensitivity to higher energies can be very useful, for instance, at many particle accelerator facilities, a neutron monitor with a response function extended up to 400 MeV has been achieved by modifying the structure of the moderator-attenuator of a commercial instrument. The first experimental tests carried out to verify the response of the new monitor both to low and high energy neutrons are reported. A comparison with the response function of three conventional commercial rem counters is presented. (author)

Characteristic tests of ionization chamber and GM counter survey meters for beta-rays, (2)

International Nuclear Information System (INIS)

Suga, Shin-ichi; Bingo, Kazuyoshi; Kajimoto, Yoichi

1979-03-01

To estimate a beta-ray absorbed dose rate of contaminated skin, measurements were done twice by a survey meter without and with a filter, keeping the distance from the contaminated skin surface to the survey meter at 10 mm. The absorbed dose rate was obtained multiplying a net reading (equals a reading of survey meter's indicator measured without the filter minus that measured with the filter) by a multiplying factor. Calibrations were made with reference plane sources of natural uranium, 198 Au and 204 Tl, varying their area. The five types of ionization chamber survey meters had nearly same multiplying factors when the diameter of source was larger than the diameter of the chamber cylinder. Estimation of the absorbed doses due to beta-emitting nuclides was possible when the measured value without filter was larger by 20% or more than that of with filter. In the case of small sources, the multiplying factor varied significantly with area of the source. The multiplying factors agreed within +-30% in the respective types i.e. manufacturers and in maximum beta-ray energies from 0.7 up to 2.5 MeV. In the source to detector distance of 1 cm +-0.2 cm, the multiplying factor varied within +-20%. The multiplying factor of a GM counter survey meter varied with beta-ray energy, the multiplying factor for uranium was 1/3 that of 204 Tl. (author)

Radiation survey of aircraft and heavy machinery scrap

International Nuclear Information System (INIS)

Idriss, Hajo; Salih, Isam; Gumaa, Elsadig; Yassin, Abbas; Yousif, E.H.; Abdel Hamid, Saad Eldeen M.; Sam, A.K.

2012-01-01

This study was conducted primarily to survey aircraft and heavy machinery at 30 locations within Khartoum State using handheld radiation survey meters to detect and identify any radiation sources that might be present and to estimate radiation dose levels. The survey has resulted in detection of 16 sealed sources of 90 Sr and one of 226 Ra in aircraft scrap. Of course, 90 Sr sources are used in military aircraft as temperature sensors while 226 Ra is used for indicating fuel levels. These sources were found intact without spreading radioactivity contamination; however, none was detected in heavy machine scrap. The levels of radiation dose measured at 0.1 m from the source fall within the range of 25.1–40.2 μSv/h with an average value of 33.52±4.06 μSv/h. These orphan sources have been separated from the scrap, tested for possible leakage, conditioned and stored in waste management facility. The result of this study has revealed without doubt that the scrap constitute a serious source of public exposure and highlights the importance of legislation making radiation monitoring of scrap in the country mandatory before it is sold to metal industry for reprocessing. - Highlights: ► Sealed radioactive sources ( 90 Sr and 226 Ra) were detected in aircraft scrap. ► No source was detected in heavy machine scrap. ► Radiation dose measured at 0.1 m from the source can be used to estimate exposure to public. ► Monitoring of scrap was found to be useful for protection (from orphan sources).

Two survey meters for measuring low γ-ray dose rates

International Nuclear Information System (INIS)

Jones, A.R.

1979-01-01

Two low-level survey meters have been developed which have numerical displays. The first is of the light-emitting diode (LED) type. The second is a liquid crystal display (LCD). The design of both instruments is described and results of measurements of performance are presented. They measure γ dose rates from background up to 2 mrad/h (20 μGy/h) for γ-rays in the energy range 0.05-1.25 MeV. They can be used at temperatures between -20 deg C and +50 deg C. Statistical accuracy and battery life both depend upon a number of factors and this dependence is shown. A later section describes the intended application of the survey meters. An appendix describes the circuit adjustments which are necessary and when they must be made. (author)

Portable radiation meters developed in Boris Kidric Institute

International Nuclear Information System (INIS)

Sobajic, V.; Smelcerovic, M.

1989-01-01

Portable meters designed for X and gamma radiation measurements and beta detection are described. An instrument using ionization chamber is developed with new type of electrometer amplifier. It is designed for precise and reliable exposure and exposure rate measurements. Another instrument with GM counters covers 8 linear ranges: from background up to 10 Sv/h. Some specific solutions and basic measurement characteristics of these instruments are presented (author)

Density meters utilizing ionizing radiation: definitions and test methods

International Nuclear Information System (INIS)

Anon.

1981-01-01

This standard is applicable to density meters utilizing ionizing radiation, designed for the measurement of the density of liquids, slurries or fluidized solids. The standard applies to transmission-type instruments only. Reference to compliance with this standard shall identify any deviations and the reasons for such deviations. Safety aspects are not included but should fulfill the requirements of all relevant internationally accepted standards

Radiation survey of mobile and wireless technology masts in public places in Kaduna metropolis Nigeria

International Nuclear Information System (INIS)

Onoh, N. I.; Ogbanje, G. O.; Jonah, S. A.

2014-01-01

Work was done to measure radiation exposure of the populace in Kaduna metropolis from radiation emitted from global satellite communication masts. Base stations were surveyed in residential, school and office areas. Parameters sampled include the electric field strength, magnetic field strength, power density and ionizing radiation dose rate of the 20 surveyed masts belonging to four service providers. The instruments deployed include the Rf- EMF strength meter Model 480836 used to measure the first three parameters and Radiation Monitor Radex RD 1503 used to determine the forth parameter. The result obtained in this work was compared with the limits set by international regulatory bodies. Our result shows that electromagnetic and ionizing radiation exposures from the surveyed masts are far below the standard limits. Based on this, the population in Kaduna metropolis is not subjected to any adverse health effects from the Global System of Mobile Communication/Universal Mobile Telecommunication System masts at the moment.

Calibration and evaluation of neutron survey meters used at linac facility

Energy Technology Data Exchange (ETDEWEB)

Salgado, A.P. [Instituto de Radioprotecao e Dosimetria - IRD, Av. Salvador Allende s/n, Recreio dos Bandeirantes, CEP 22780-160 Rio de Janeiro (Brazil); Pereira, W.W., E-mail: walsan@ird.gov.b [Instituto de Radioprotecao e Dosimetria - IRD, Av. Salvador Allende s/n, Recreio dos Bandeirantes, CEP 22780-160 Rio de Janeiro (Brazil); Fonseca, E.S. da; Patrao, K.C.S. [Instituto de Radioprotecao e Dosimetria - IRD, Av. Salvador Allende s/n, Recreio dos Bandeirantes, CEP 22780-160 Rio de Janeiro (Brazil); Batista, D.V.S. [Instituto Nacional do Cancer - INCa, Praca Cruz Vermelha, 23 - centro, CEP 20230-130 Rio de Janeiro (Brazil)

2010-12-15

Calibrated survey meters from the Neutron Laboratory of the Instituto de Radioprotecao e Dosimetria (IRD) were used to determine the ambient dose-equivalent rate in a 15 MV linear accelerator treatment room at the Instituto Nacional do Cancer (INCa). Three different models of neutron survey meters were calibrated using four neutron radionuclide neutron sources: {sup 241}AmBe({alpha},n), {sup 252}Cf(f,n), heavy-water moderated {sup 252}Cf(f,n), and {sup 238}PuBe({alpha},n). All neutron sources were standardized in a Manganese Sulphate Bath (MSB) absolute primary system. The response of each of these instruments was compared with reference values of ambient dose-equivalent rate. The results demonstrate the complexity of making measurements in the mixed neutron/photon field produced in electron linear accelerator radiotherapy treatment rooms.

Advanced Metering Infrastructure based on Smart Meters

Science.gov (United States)

Suzuki, Hiroshi

By specifically designating penetrations rates of advanced meters and communication technologies, devices and systems, this paper introduces that the penetration of advanced metering is important for the future development of electric power system infrastructure. It examines the state of the technology and the economical benefits of advanced metering. One result of the survey is that advanced metering currently has a penetration of about six percent of total installed electric meters in the United States. Applications to the infrastructure differ by type of organization. Being integrated with emerging communication technologies, smart meters enable several kinds of features such as, not only automatic meter reading but also distribution management control, outage management, remote switching, etc.

Comparative investigation of three dose rate meters for their viability in pulsed radiation fields

International Nuclear Information System (INIS)

Gotz, M; Karsch, L; Pawelke, J

2015-01-01

Pulsed radiation fields, characterized by microsecond pulse duration and correspondingly high pulse dose rates, are increasingly used in therapeutic, diagnostic and research applications. Yet, dose rate meters which are used to monitor radiation protection areas or to inspect radiation shielding are mostly designed, characterized and tested for continuous fields and show severe deficiencies in highly pulsed fields. Despite general awareness of the problem, knowledge of the specific limitations of individual instruments is very limited, complicating reliable measurements. We present here the results of testing three commercial dose rate meters, the RamION ionization chamber, the LB 1236-H proportional counter and the 6150AD-b scintillation counter, for their response in pulsed radiation fields of varied pulse dose and duration. Of these three the RamION proved reliable, operating in a pulsed radiation field within its specifications, while the other two instruments were only able to measure very limited pulse doses and pulse dose rates reliably. (paper)

Double ionization chamber survey meter for the separate measurement of penetrating and non-penetrating dose

International Nuclear Information System (INIS)

Lucas, A.C.

1987-01-01

The full capabilities of an advanced 8-bit microprocessor have been utilized in construction of a wide range, multiplexing survey meter based on dual electrometers and ionization chambers. The ionization chambers are constructed of modular conducting and non-conducting parts in such a way that the angular dependence for measurement of beta radiation is controlled by design. Display functions for the high range instrument include logarithmic or linear analog display, digital display of rate or dose, SI or English units, optionally for either total, penetrating, or non-penetrating dose. The instrument is presently configured to operate in the range 0.1 R/hr to 50,000 R/hr in support of the requirements of Regulatory Guide 19.7

Response of six neutron survey meters in mixed fields of fast and thermal neutrons.

Science.gov (United States)

Kim, S I; Kim, B H; Chang, I; Lee, J I; Kim, J L; Pradhan, A S

2013-10-01

Calibration neutron fields have been developed at KAERI (Korea Atomic Energy Research Institute) to study the responses of commonly used neutron survey meters in the presence of fast neutrons of energy around 10 MeV. The neutron fields were produced by using neutrons from the (241)Am-Be sources held in a graphite pile and a DT neutron generator. The spectral details and the ambient dose equivalent rates of the calibration fields were established, and the responses of six neutron survey meters were evaluated. Four single-moderator-based survey meters exhibited an under-responses ranging from ∼9 to 55 %. DINEUTRUN, commonly used in fields around nuclear reactors, exhibited an over-response by a factor of three in the thermal neutron field and an under-response of ∼85 % in the mixed fields. REM-500 (tissue-equivalent proportional counter) exhibited a response close to 1.0 in the fast neutron fields and an under-response of ∼50 % in the thermal neutron field.

A review of neutron scattering correction for the calibration of neutron survey meters using the shadow cone method

Energy Technology Data Exchange (ETDEWEB)

Kim, Sang In; Kim, Bong Hwan; Kim, Jang Lyul; Lee, Jung Il [Health Physics Team, Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2015-12-15

The calibration methods of neutron-measuring devices such as the neutron survey meter have advantages and disadvantages. To compare the calibration factors obtained by the shadow cone method and semi-empirical method, 10 neutron survey meters of five different types were used in this study. This experiment was performed at the Korea Atomic Energy Research Institute (KAERI; Daejeon, South Korea), and the calibration neutron fields were constructed using a {sup 252}Californium ({sup 252}Cf) neutron source, which was positioned in the center of the neutron irradiation room. The neutron spectra of the calibration neutron fields were measured by a europium-activated lithium iodide scintillator in combination with KAERI's Bonner sphere system. When the shadow cone method was used, 10 single moderator-based survey meters exhibited a smaller calibration factor by as much as 3.1 - 9.3% than that of the semi-empirical method. This finding indicates that neutron survey meters underestimated the scattered neutrons and attenuated neutrons (i.e., the total scatter corrections). This underestimation of the calibration factor was attributed to the fact that single moderator-based survey meters have an under-ambient dose equivalent response in the thermal or thermal-dominant neutron field. As a result, when the shadow cone method is used for a single moderator-based survey meter, an additional correction and the International Organization for Standardization standard 8529-2 for room-scattered neutrons should be considered.

A review of neutron scattering correction for the calibration of neutron survey meters using the shadow cone method

International Nuclear Information System (INIS)

Kim, Sang In; Kim, Bong Hwan; Kim, Jang Lyul; Lee, Jung Il

2015-01-01

The calibration methods of neutron-measuring devices such as the neutron survey meter have advantages and disadvantages. To compare the calibration factors obtained by the shadow cone method and semi-empirical method, 10 neutron survey meters of five different types were used in this study. This experiment was performed at the Korea Atomic Energy Research Institute (KAERI; Daejeon, South Korea), and the calibration neutron fields were constructed using a 252 Californium ( 252 Cf) neutron source, which was positioned in the center of the neutron irradiation room. The neutron spectra of the calibration neutron fields were measured by a europium-activated lithium iodide scintillator in combination with KAERI's Bonner sphere system. When the shadow cone method was used, 10 single moderator-based survey meters exhibited a smaller calibration factor by as much as 3.1 - 9.3% than that of the semi-empirical method. This finding indicates that neutron survey meters underestimated the scattered neutrons and attenuated neutrons (i.e., the total scatter corrections). This underestimation of the calibration factor was attributed to the fact that single moderator-based survey meters have an under-ambient dose equivalent response in the thermal or thermal-dominant neutron field. As a result, when the shadow cone method is used for a single moderator-based survey meter, an additional correction and the International Organization for Standardization standard 8529-2 for room-scattered neutrons should be considered

THz calorimetry : An absolute power meter for TeraHertz radiation and the absorptivity of the Herschel Space Observatory telescope mirror coating

NARCIS (Netherlands)

Klaassen, T.O.; Hovenier, J.N.; Fischer, J.; Jakob, G.; Poglitsch, A.; Sternberg, O.

2004-01-01

A new calorimetric absolute power meter has been developed for THz radiation. This broad band THz power meter measures average power at ambient temperature and pressure, does not use a window, and is insensitive to polarization and time structure of THz radiation. The operation of the power meter is

Characteristics and correlation of various radiation measuring methods in spatial radiation measurement

International Nuclear Information System (INIS)

Yoneda, Kazuhiro; Tonouchi, Shigemasa

1992-01-01

When the survey of the state of natural radiation distribution was carried out, for the purpose of examining the useful measuring method, the comparison of the γ-ray dose rate calculated from survey meter method, in-situ measuring method and the measuring method by sampling soil was carried out. Between the in-situ measuring method and the survey meter method, the correlation Y=0.986X+5.73, r=0.903, n=18, P<0.01 was obtained, and the high correlation having the inclination of nearly 1 was shown. Between the survey meter method and the measuring method by sampling soil, the correlation Y=1.297X-10.30, r=0.966, n=20 P<0.01 was obtained, and the high correlation was shown, but as for the dose rate contribution, the disparities of 36% in U series, 6% in Th series and 20% in K-40 were observed. For the survey of the state of natural radiation distribution, the method of using in combination the survey meter method and the in-situ measuring method or the measuring method by sampling soil is suitable. (author)

Aerial radiological survey of the Palo Verde Nuclear Generating Station and surrounding area, Wintersburg, Arizona. Date of survey: November 1982

International Nuclear Information System (INIS)

Semmler, R.A.

1984-01-01

An aerial survey of terrestrial gamma radiation was performed during the period 4 November through 15 November 1982 over a 16-kilometer by 16-kilometer (10-mile by 10-mile) area approximately centered on the Palo Verde Nuclear Generating Station near Wintersburg, Arizona. Gamma radiation spectral data were collected while flying a helicopter over a regular pattern of parallel lines spaced 150 meters (500 feet) apart at an altitude of 90 meters (300 feet). All radiation measurements taken at the nominal flight altitude were corrected for altitude variations, cosmic radiation, and helicopter background to generate exposure rates from terrestrial sources extrapolated to 1 meter above ground level. The data are presented as isoradiation contour maps. The average terrestrial radiation levels fall between 8 and 14 microrentgens per hour (μR/h). All gamma radiation detected within the survey area was associated with naturally occurring radionuclides. Direct ground-based measurements at 1 meter height were also taken at four scattered sites within the survey area. These values agree with the contour intervals determined from the aerial measurements and differ from the mean value of adjacent contours by no more than 10%. 6 references, 5 figures, 2 tables

Application of a background-compensated Geiger-Mueller counter to a survey meter

International Nuclear Information System (INIS)

Mori, C.; Kumanomido, H.; Watanabe, T.

1984-01-01

A background-compensated Geiger-Mueller counter was used as a probe for a GM survey meter to obtain a net count rate of β-rays from a radioactive source in a quick survey. Although a background counting ratio between the two parts in the counter, front and rear, varied somewhat depending on the incident direction of background γ-rays, it was possible to compensate the background counts by subtracting a part of the rear counts, which were background counts, from the front counts, which contained β-ray counts and background counts. Undesirable small pulses generated during the recovering time after a full Geiger discharge were eliminated by an anticoincidence gating method. The survey meter with this counter and a differential ratemeter is useful for obtaining a net count rate of β-rays emitted from a surface radioactive-contamination or from a source being put near the window of the counter with nearly the same accuracy in half the measuring time as compared with conventional GM counters. (orig.)

Portable radiation monitors

International Nuclear Information System (INIS)

Masui, Kaoru; Ishikura, Takeshi; Inui, Daisuke

2007-01-01

This paper presents an overview of typical portable radiation monitors and introduces Fuji Electric's latest models. The overview describes the types, uses and performance of ion chamber survey meters, GM survey meters and neutron ambient dose equivalent rate meters. Fuji Electric's new model of a wide-energy-range X/gamma ray survey meter which measures low energy X-rays up to 8 keV, a battery-powered environmental dosemeter system which measures dose history and is capable of continuous measurement with batteries over a year, and a portable monitoring post which measures dose rates from background to 10 8 nGy/h and transmits data by cellular phone are introduced, and their specifications and performance are described. (author)

Optical cycle power meter

DEFF Research Database (Denmark)

2014-01-01

A bicycle power meter for measuring power generated when riding a bicycle, the power meter comprising a position-sensitive radiation detector (409) attachable to a component of a crank set (404) of bicycle, and a radiation source (408) attachable to the component of the crank set and configured t...

Properties of cellulose triacetate dose meter

International Nuclear Information System (INIS)

Tamura, N.; Tanaka, R.; Mitomo, S.; Matsuda, K.; Nagai, S.

1981-01-01

Several clear plastics and dyed plastics are commercially available for dosimetry in intense radiation field, especially for radiation processing applications. Among these dose meters cellulose triacetate (CTA) dose meter has two advantages for routine uses; (1) it has linear response in mega-rad dose region and (2) the main product form is long tape. However, the manufacture of Numelec CTA film so far used had been discontinued, and for this reason we developed a new film for dosimetry uses. To determine the manufacturing conditions of the film, we examined the influence of additives, triphenylphosphate (TPP) and others, and film thickness on the dosimetric properties, since these two conditions remarkably influence the sensitivity of the dose meter. It is necessary for the reliability of plastic dose meters that the radiation induced colorations should be understood as radiation chemical processes. In this paper we describe the determination of the manufacturing conditions of the new film, the feature of the new dose meter, and the coloration mechanism. (author)

Application of solid dosimeter to radiation control

International Nuclear Information System (INIS)

Tsujimoto, Tadashi

1988-01-01

Individual exposure dose measuring devices are used to measure the dose of each person in facilities using radiations. Major devices of this type currently used in Japan include the film badge, thermoluminescence dosimeter, portable radiation dosimeter and fluorescent glass dosimeter. All of these devices except the portable radiation dosimeter are of a solid type. Various portable-type spatial dose rate measuring devices, generally called survey meters, are available to determine the spatial distribution of radiations. Major survey meters incorporates an ionization chamber, GM counter tube or scintillation counter, while BF 3 counting tubes are available for neutron measurement. Of these, the scintillation dosimeter is of a solid type. A new scintillation survey meter has recently been developed which incorporated a discrimination bias modulation circuit. Dosimeters incorporating an ionization chamber or a GM counter tube are generally used as portable alarms. Recently, a new solid-type alarm has been developed which incorporates a solicon radiation detector. Microcomputers are also used for self-diagnosis, data processing, automatic calibration, etc. (Nogami, K.)

Mathematical modeling of a survey-meter used to measure radioactivity in human thyroids: Monte Carlo calculations of the device response and uncertainties

Science.gov (United States)

Khrutchinsky, Arkady; Drozdovitch, Vladimir; Kutsen, Semion; Minenko, Victor; Khrouch, Valeri; Luckyanov, Nickolas; Voillequé, Paul; Bouville, André

2012-01-01

This paper presents results of Monte Carlo modeling of the SRP-68-01 survey meter used to measure exposure rates near the thyroid glands of persons exposed to radioactivity following the Chernobyl accident. This device was not designed to measure radioactivity in humans. To estimate the uncertainty associated with the measurement results, a mathematical model of the SRP-68-01 survey meter was developed and verified. A Monte Carlo method of numerical simulation of radiation transport has been used to calculate the calibration factor for the device and evaluate its uncertainty. The SRP-68-01 survey meter scale coefficient, an important characteristic of the device, was also estimated in this study. The calibration factors of the survey meter were calculated for 131I, 132I, 133I, and 135I content in the thyroid gland for six age groups of population: newborns; children aged 1 yr, 5 yr, 10 yr, 15 yr; and adults. A realistic scenario of direct thyroid measurements with an “extended” neck was used to calculate the calibration factors for newborns and one-year-olds. Uncertainties in the device calibration factors due to variability of the device scale coefficient, variability in thyroid mass and statistical uncertainty of Monte Carlo method were evaluated. Relative uncertainties in the calibration factor estimates were found to be from 0.06 for children aged 1 yr to 0.1 for 10-yr and 15-yr children. The positioning errors of the detector during measurements deviate mainly in one direction from the estimated calibration factors. Deviations of the device position from the proper geometry of measurements were found to lead to overestimation of the calibration factor by up to 24 percent for adults and up to 60 percent for 1-yr children. The results of this study improve the estimates of 131I thyroidal content and, consequently, thyroid dose estimates that are derived from direct thyroid measurements performed in Belarus shortly after the Chernobyl accident. PMID:22245289

DNA Radiation Environments Program: Fall 1989 2-meter box experiments and analysis

International Nuclear Information System (INIS)

Santoro, R.T.

1991-05-01

This effort, sponsored by the Defense Nuclear Agency under the Radiation Environments Program, was carried out to obtain measured data for benchmarking MASH, the Monte Carlo Adjoint Code System. MASH was developed to replace the Vehicle Code System, VCS, that has been used by the Department of Defense and NATO for calculating neutron and gamma-ray radiation fields and shielding protection factors inside armored vehicles and structures from nuclear weapon radiation. Free-field data were obtained at distances of 170- and 400-meters from the APR while in-box measurements were made at 400 meters only. The box, included to obtain neutron and gamma-ray reduction factors, was a 2-meter cube configuration having 0.1016-m-thick steel walls. Calculated data were obtained using MASH by analysts from the Oak Ridge National Laboratory and Science Applications International Corporation. Calculated (C) results were compared with experimental (E) data in terms of C/E ratios. Free-field and in-box neutron kerma generally agreed within ±20%, although some C/E comparisons fell outside this range depending upon the detector against which the calculated data were compared. For those cases where the C/E ratio is marginal or unacceptable, problems in the detector systems were acknowledged to be principal cause of the discrepancy. Generally poor agreement (∼25-35%) was achieved among the C/E ratios for the free-field gamma-ray kerma at the 170- and 400-m locations while excellent (10%, or better) C/E values were obtained for the in-box conditions. The discrepancy for the free-field comparison was attributed to the failure by the analysts to include a tree line adjacent to the measurement site in the calculational geometry. C/E values for the neutron and gamma-ray reduction factors ranged from 1% to 23% depending on the detector. 4 refs., 2 figs., 14 tabs

Radiation meter

Energy Technology Data Exchange (ETDEWEB)

Burgess, P H

1990-05-30

Measuring means comprising first and second silicon PIN diode detectors both being covered with a thin layer of conducting material and the second detector being additionally covered with a relatively thick layer of material, the thickness being chosen such that beta radiation dose rate can be measured in beta radiation fields of high or medium energy, and in the presence of X and gamma radiation. (author). 2 figs.

Empowered? Examining self-disconnection in a postal survey of electricity prepayment meter consumers in New Zealand

International Nuclear Information System (INIS)

O'Sullivan, Kimberley C.; Howden-Chapman, Philippa L.; Fougere, Geoffrey M.; Hales, Simon; Stanley, James

2013-01-01

Prepayment metering is an electricity payment method often used by low-income consumers. Fuel poverty is an important public health problem in New Zealand, and is likely to be a particular problem for those using prepayment metering. This paper details a nationwide postal survey of consumers undertaken with the support of three major electricity retailers, which investigated the advantages and disadvantages of using prepayment metering from a consumer perspective. The study surveyed a total pool of 359 randomly selected consumers across the three companies, a response rate of 48%. The study found that while almost all respondents felt the benefits of using prepayment outweighed the risks of running out of credit or ‘self-disconnection’, 53% of respondents experienced self-disconnection in the past year. Of concern, over a third of respondents experiencing self-disconnection were without electricity for more than 12 h. The frequency of self-disconnection was also high, with 17% of those disconnecting reporting six or more events in the past year. Government intervention could reduce the risks and disadvantages involved with using prepayment metering, which could then support initiatives aimed at reducing fuel poverty. - Highlights: ► Results of a national postal survey of New Zealand electricity prepayment users. ► Self-disconnection is an extreme outcome of fuel poverty. ► 53% of respondents experienced self-disconnection in the past year. ► Self-disconnection is problematic, lasting 12 or more hours for 38% of those who disconnected. ► Government policies could minimise health effects and capture benefits of prepayment metering.

Radiation survey of first Hi-Art II Tomotherapy vault design in India

International Nuclear Information System (INIS)

Kinhikar, Rajesh A.; Jamema, S.V.; Pai, Rajeshree; Sharma, P.K. Dash; Deshpande, Deepak D.

2009-01-01

A vault as per government-regulation compliance with adequate shielding needs was designed and constructed for Hi-Art II Tomotherapy machine being the first in India. Radiation measurements around this Tomotherapy treatment vault were carried out to check the shielding adequacy of the source housing and the vault. It was mandatory to get this un-conventional machine 'Type Approved' by Atomic Energy Regulatory Board (AERB) in India. The aim of this paper was to report on the radiation levels measured during the radiation survey carried out for this machine. The radiation levels in and around the vault were measured for stationary as well as rotational treatment procedures with the largest open field size (5 cm x 40 cm) at the isocenter with and without scattering medium. The survey was performed at three locations near each wall surrounding the vault as well. The leakage radiation from the source housing was measured both in the patient plane outside the treatment field and one meter distance from the source outside the patient plane. The radiation levels both for stationary as well as rotational procedures were within 1 mR/h. No significance difference was observed in the radiation levels measured for rotational procedures with and without scattering medium. The leakage radiation in the patient plane was found to be 0.04% (Tolerance 0.2%), while the head leakage was 0.007% (Tolerance 0.5%) of the dose rate at the isocenter. The treatment delivery with Tomotherapy does play safe radiation levels around the installation layout and also passes the leakage criteria as well.

The measuring system and practical uses of the universal radiation meter type TSM-11

International Nuclear Information System (INIS)

Rozsa, S.; Szabo, Gy.; Szem, I.; Vereczky, L.

1980-01-01

The industrial radiation meter in its signal conversion follows the ratemeter principle and uses pulse detectors. By its built-in zero suppression and scale extension the device makes the display of two pulses differing from each other at least by 10% and their conversion onto the output signal range of 0-20 mA possible. The information from the different measuring sections developed for industrial purposes are processed by the same device. The operation principles of and the experience gathered with the radiometer in its use in industry as density, level, thickness gauge, moisture and quantity meter and belt scales are discussed. (author)

Measurement of radon concentration in water using the portable radon survey meter.

Science.gov (United States)

Yokoyama, S; Mori, N; Shimo, M; Fukushi, M; Ohnuma, S

2011-07-01

A measurement method for measuring radon in water using the portable radon survey meter (RnSM) was developed. The container with propeller was used to stir the water samples and release radon from the water into the air in a sample box of the RnSM. In this method, the measurement of error would be water was >20 Bq l(-1).

Borehole Gravity Meter Surveys at the Waste Treatment Plant, Hanford, Washington.

Energy Technology Data Exchange (ETDEWEB)

MacQueen, Jeffrey D.; Mann, Ethan

2007-04-06

Microg-LaCoste (MGL) was contracted by Pacfic Northwest National Laboratories (PNNL) to record borehole gravity density data in 3 wells at the HanfordWaste Treatment Plant (WTP) site. The survey was designed to provide highly accurate density information for use in seismic modeling. The borehole gravity meter (BHGM) tool has a very large depth of investigation (hundreds of feet) compared to other density tools so it is not influenced by casing or near welbore effects, such as washouts.

Radiation distribution measurement using plastic scintillating optical fibers for survey of radioactive contamination in wide area

International Nuclear Information System (INIS)

Ito, Chikara; Ito, Keisuke; Ishikawa, Takashi; Yoshida, Akihiro; Sanada, Yukihisa; Torii, Tatsuo; Nohtomi, Akihiro; Wakabayashi, Genichiro; Miyazaki, Nobuyuki

2013-01-01

It is important to examine distribution of environmental contamination due to the accident of Fukushima Daiichi Nuclear Power Station and to confirm the effect of decontamination works. We have applied radiation distribution measurement using plastic scintillating optical fibers (PSFs) in the survey of contamination in wide area including residential, farmland, forests, etc. In the measurements system, two scintillation lights that emitted at an incidence of a radiation transmit to photomultiplier tubes at the both end of PSFs. The position where scintillation light emitted is obtained from the detection time difference of each photomultiplier tube. The distribution of light emission quantity indicates the distribution of radiation incident in a PSF which is corresponds to the distribution of dose-rate. The radiation detection system using the PSFs has been applied to the radiation distribution measurement on grounds, trees, etc. The results show a good agreement with point data measured by survey meters using sodium iodide scintillators. As the PSFs which have water resistance, they have been successfully applied to the radiation distribution measurement in the river. We have also succeeded in measuring two-dimensional distribution of radiation by measuring the count rate while moving to the fiber at a constant speed. (author)

Vehicle-borne survey techniques for background radiations

International Nuclear Information System (INIS)

Minato, Susumu

1995-01-01

This paper presented methods for converting count rates measured inside cars and trains in the natural environment into outdoor terrestrial gamma-ray dose rates. First, (1) the method of calibration for a survey meter is described to be applicable to various geological terrains. Next, the regression formulas were acquired experimentally to correct (2) the shielding effects of cars and trains, and (3) the influence of pavements and ballasts. Furthermore, (4) a new method for removing interfering radiation components emitted from cliffs and tunnels was proposed, and the errors in the calculations were evaluated with numerical experiments. In addition, the degree of influence from the cliff was represented with the angle of elevation subtended to the detector. For the items (2)-(4), in particular, it could be explained with simple models that those methods are reasonable. The method for evaluating simply and accurately cosmic-ray dose rates by means of a portable barometer was also described. (author)

Survey of women's awareness about radiation

International Nuclear Information System (INIS)

Onishi, Keiko; Aomi, Yuki; Asada, Kiyoe; Kamiya, Masami; Mitsuishi, Haruko

2008-01-01

A project in a voluntary group 'Women's Energy Network' conducted two questionnaire surveys on Japanese women's awareness about radiation. The survey was conducted to investigate how women(non-experts) perceive radiation and radioactivity, what is their image about radiation, to what extent they are aware of the use of radiation in their daily life, and whether they find nuclear related information useful or not. The results of those surveys have led WEN to publish a booklet entitled 'Our Life and Radiation' to be used for public communication and to hold public forums in various cities in Japan. The first survey was conducted in 2001 to those living in big cities such as Tokyo and Osaka and to those living in the area where the nuclear power plant is installed. The response rate was 72.4% (1,028 out of 1,419). The second one was done in 2005 to those living in Tokyo and other big cities. The response rate was 84.7% (888 our of 983). It was derived from the two surveys that they were not so much aware of various applications of radiation for daily use (awareness rate was low), but they considered those information would be useful when it becomes available for them and they were interested in knowing about it. As for the image of radiation, about 80% have shown fear when they see or hear a word 'radiation'. This report provides the result of questionnaire surveys on women's awareness about radiation conducted by 'Our Daily Life and Radiation' project in Women's Energy Network. (author)

Gamma absorption meter

International Nuclear Information System (INIS)

Dincklage, R.D. von.

1984-01-01

The absorption meter consists of a radiation source, a trough for the absorbing liquid and a detector. It is characterized by the fact that there is a foil between the detector and the trough, made of a material whose binding energy of the K electrons is a little greater than the energy of the photons emitted by the radiation source. The source of radiation and foil are replaceable. (orig./HP) [de

Characterization of Various Survey Meters by Car-borne Survey in Java Island as Basis Data for Searching Orphan Sources

International Nuclear Information System (INIS)

Yus Rusdian Akhmad

2004-01-01

Recently, an international collaboration in securing and managing radioactive sources, particularly orphan sources, is established. For developing countries such as Indonesia which possesses relatively inadequate resources, an effective approach in dealing with the problem is crucial. In order to deal with this situation, an activity was performed including: 1) assessment of available technical means, 2) car-borne survey during the dry and rainy seasons to identify the impact of Rn daughter washout on the interpretation of search results, 3) search for anomalies in the radioactive exposure map of the Java island, and 4) investigation of anomalies found, using more sophisticated instrument, to detect and secure orphan and illicit radioactive sources. The performance of four selected instruments in a car-borne survey which covers a large area in western part of Java was evaluated. Data series of moving background were divided into two measurement groups; control group and test group. These data series were arranged in, order to determine the value of alarm level. For this purpose, statistic procedures relying on Mann-Whitney U test and a simple moving average test (Moving Background) were applied. Among the four selected survey meters, the most convenient detection system for implementing the activity is Exploranium GR-130. There was little concern on the effect of Rn-daughters washouts on the proposed methods, provided that the operator could recognise the transition period between the clear and rainy weather as it could give rise to false alarm. The Moving Background method was generally superior to Mann-Whitney U test for detecting anomalous radiation level. During the survey, an anomaly in steel industrial area was detected. Using portable gamma spectrometers, it was concluded that the anomaly was generated from naturally occurring radioactive materials (NORM). Analyses upon survey data in the big cities showed anomalies due to concrete structures, especially

Automatic radiation measuring system connected with GPS

International Nuclear Information System (INIS)

Tanigaki, Minoru

2014-01-01

The most serious nuclear disaster in Japan has broken out at Fukushima Daiichi Nuclear Power Plant due to Great East Japan Earthquake. Prompt and exact mapping of the contamination is of great importance for radiation protection and for the environment restoration. We have developed radiation survey systems KURAMA and KURAMA-2 for rapid and exact measurement of radiation dose distribution. The system is composed of a mobile radiation monitor and the computer in office which is for the storage and visualization of the data. They are connected with internet and are operated for continuous radiation measurement while the monitor is moving. The mobile part consists of a survey meter, an interface to transform the output of the survey meter for the computer, a global positioning system, a computer to process the data for connecting to the network, and a mobile router. Thus they are effective for rapid mapping of the surface contamination. The operation and the performance of the equipment at the site are presented. (J.P.N.)

Application of ranging technique of radar level meter for draft survey

Directory of Open Access Journals (Sweden)

SHEN Yijun

2017-12-01

Full Text Available [Objectives] This paper aims to solve the problems of the high subjectivity and low accuracy and efficiency of draft surveying relying on human visual inspection.[Methods] Radar-level oil and liquid measurement technology products are widely used in the petrochemical industry. A device is developed that uses radar to survey the draft of a boat, designed with data series optimization formulae to ensure that the data results are true and correct. At the same time, a test is designed to prove the accuracy of the results.[Results] According to the conditions of the ship,the device is composed of a radar sensor, triangular bracket and display,and is put to use in the test.[Conclusions] With 15 vessels as the research objects,the comparison experiment shows a difference in range between 0.001-0.022 meters, with an average difference rate of 0.028%, which meets the requirements for ship draft survey accuracy.

Your Glucose Meter

Science.gov (United States)

... Medical Devices Radiation-Emitting Products Vaccines, Blood & Biologics Animal & Veterinary Cosmetics Tobacco ... 164KB) En Español Basic Facts 7 Tips for Testing Your Blood Sugar and Caring for Your Meter ...

ORNL Pocket Meter Program: internal operating procedures

International Nuclear Information System (INIS)

Berger, C.D.; Miller, J.H.; Dunsmore, M.R.

1984-12-01

The ORNL Pocket Meter Program is designed for auditing the approximate photon radiation exposure of Oak Ridge National Laboratory (ORNL) radiation workers. Although pocket meters are considered to be a secondary personnel dosimetry system at ORNL, they are valuable indicators of unplanned exposures if proper procedures are followed for testing, calibrating, deploying, wearing, processing, and recording data. 4 figures, 1 table

Development of custom LCD based portable survey/contamination monitors

International Nuclear Information System (INIS)

Reddy, J.D.

2010-01-01

Equipments for carrying out radiation survey measurements for alpha, beta and gamma radiations have evolved considerably with the advancements in Electronics overtime. There are 2 major classes of portable instruments available from most manufacturers - (a) Analog indicator type (b) Direct digital readout type. Analog meters give a direct quantifying feel to radiation levels though they are not rich features nor they have smartness like a digital meter. Digital versions have advantages of direct readout numerically and configurable as per users requirements. To achieve best features of both the techniques a dual indicator type LCD module comprising of Analog indicating LCD segments and digital readout indicating 7 segments has been developed. This LCD comprising of LCD glass and its display driver has been deployed across various types of survey meters and contamination monitors manufactured by Nucleonix. This display now facilitates direct readout of dose rate/count rate in various units simultaneously in both analog LCD scale and direct digital indication. (author)

Radioisotope conveyor ash meter

International Nuclear Information System (INIS)

Savelov, V.D.

1994-01-01

Radioisotope conveyor ash meter realizes persistent measuring of ashiness of coal and products of its enrichment on the belt conveyor without contact. The principle of ash meter acting is based on functional dependence of the gamma radiation flows backscattering intensity of radioisotope sources from the ash volume content in the controlled fuel. Facility consists from the ashiness transducer and the processing and control device

Survey meter using novel inorganic scintillators

International Nuclear Information System (INIS)

Yoshikawa, Akira; Fukuda, Kentaro; Kawaguchi, Noriaki; Kamada, Kei; Fujimoto, Yutaka; Yokota, Yuui; Kurosawa, Shunsuke; Yanagida, Takayuki

2012-01-01

Single crystal scintillator materials are widely used for detection of high-energy photons and particles. There is continuous demand for new scintillator materials with higher performance because of increasing number of medical, industrial, security and other applications. This article presents the recent development of three novel inorganic scintillators; Pr-doped Lu 3 Al 5 O 12 (Pr:LuAG), Ce doped Gd 3 (Al, Ga) 5 O 12 (Ce:GAGG) and Ce or Eu-doped 6 LiCaAlF 6 (Ce:LiCAF, Eu:LiCAF). Pr:LuAG shows very interesting scintillation properties including very fast decay time, high light yield and excellent energy resolution. Taking the advantage of these properties, positron emission mammography (PEM) equipped with Pr:LuAG were developed. Ce:GAGG shows very high light yield, which is much higher than that of Ce:LYSO. Survey meter using Ce:GAGG is developed using this scintillator. Ce:LiCAF and Eu:LiCAF were developed for neutron detection. The advantage and disadvantage are discussed comparing with halide scintillators. Eu-doped LiCAF indicated five times higher light yield than that of existing Li-glass. It is expected to be used as the alternative of 3 He. (author)

Calibration of dose meters used in radiotherapy

International Nuclear Information System (INIS)

1979-01-01

This manual is a practical guide, not a comprehensive textbook, to the instrumentation and procedures necessary to calibrate a radiation dose meter used in clinical practice against a secondary standard dose meter

Aerial radiation surveys

International Nuclear Information System (INIS)

Jobst, J.

1980-01-01

A recent aerial radiation survey of the surroundings of the Vitro mill in Salt Lake City shows that uranium mill tailings have been removed to many locations outside their original boundary. To date, 52 remote sites have been discovered within a 100 square kilometer aerial survey perimeter surrounding the mill; 9 of these were discovered with the recent aerial survey map. Five additional sites, also discovered by aerial survey, contained uranium ore, milling equipment, or radioactive slag. Because of the success of this survey, plans are being made to extend the aerial survey program to other parts of the Salt Lake valley where diversions of Vitro tailings are also known to exist

Measurement of the unaccompanied pion-proton flux ratio at 2,900 meters using a transition radiation detector

International Nuclear Information System (INIS)

Ellsworth, R.W.; Ito, A.S.; MacFall, J.R.; Siohan, F.; Streitmatter, R.E.; Tonwar, S.C.; Yodh, G.B.

1975-01-01

A transition radiation dedector and an ionization calorimeter have been used to measure the unaccompanied pion to proton flux ratio for energies greater than 400 and 600 GeV at an altitude of 2,900 meters. (orig./BJ) [de

Pilot study for natural radiation survey

International Nuclear Information System (INIS)

Brown, L.; Driscoll, C.M.H.; Green, B.M.R.; Miles, J.C.H.

1983-01-01

NRPB's national survey of natural radiation exposure in homes commenced in 1982 and will run until 1984. A pilot survey was undertaken in over 100 homes for one year, using passive thermoluminescent dosemeters to measure external radiation from terrestrial and cosmic sources and passive radon dosemeters to measure the radon-222 gas concentration. A preliminary analysis of the results obtained from the pilot survey is given. The main value of the pilot survey was in providing experience and various administrative and scientific procedures have been simplified or automated for the national survey. (U.K.)

Radiation dose in the high background radiation area in Kerala, India.

Science.gov (United States)

Christa, E P; Jojo, P J; Vaidyan, V K; Anilkumar, S; Eappen, K P

2012-03-01

A systematic radiological survey has been carried out in the region of high-background radiation area in Kollam district of Kerala to define the natural gamma-radiation levels. One hundred and forty seven soil samples from high-background radiation areas and five samples from normal background region were collected as per standard sampling procedures and were analysed for (238)U, (232)Th and (40)K by gamma-ray spectroscopy. External gamma dose rates at all sampling locations were also measured using a survey meter. The activities of (238)U, (232)Th and (40)K was found to vary from 17 to 3081 Bq kg(-1), 54 to 11976 Bq kg(-1) and BDL (67.4 Bq kg(-1)) to 216 Bq kg(-1), respectively, in the study area. Such heterogeneous distribution of radionuclides in the region may be attributed to the deposition phenomenon of beach sand soil in the region. Radium equivalent activities were found high in several locations. External gamma dose rates estimated from the levels of radionuclides in soil had a range from 49 to 9244 nGy h(-1). 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.

Portable meter study of ionizing radiation Teletector in high rates of air kerma

International Nuclear Information System (INIS)

Damatto, Willian Behling; Potiens, Maria da Penha A.; Vivolo, Vitor

2015-01-01

A set of portable meters of ionizing radiation high rates of air kerma (teletectors) commonly used in emergencies in Brazil and sent to the Calibration Laboratory of IPEN were under several tests and analyst is parameters for the detectors behavior were established. Applied tests were: energy dependence and primarily overload with the new irradiation system. Thus it was possible to determine the most common characteristic found in these equipment (quality control programs) and new calibration criteria were established following international recommendations. (author)

Environmental gamma radiation monitoring at Visakhapatnam using thermoluminescence dosimeters

International Nuclear Information System (INIS)

Swarnkar, M.; Sahu, S.K.; Takale, R.A.; Shetty, P.G.; Pundit, G.G.; Puranik, V.D.

2012-01-01

The gamma rays are the most significant part of environmental dose due to its large range and deep penetrating power. The environmental gamma radiation is mainly originated from two sources natural radiation and artificially produced radiation. The natural radiation dose arises from the cosmic radiation (galactic and solar) and from the Earth (terrestrial) surface. In the last few decades there is a growing concern all over the world about radiation and their exposure to population. Thus it is necessary to conduct radiological environmental surveillance. The radiation survey data are useful to establish the natural background gamma radiation levels. Extensive gamma radiation survey was carried out around the surroundings of Vishakhapatnam using Thermoluminescence Dosimeters (TLDs). The CaSO 4 :(0.2 mole %) Dy Teflon TLD discs, specifically designed for environmental gamma radiation monitoring purpose were used. These TLD badge are having very high TL sensitivity, a negligible fading rate and a stable TL response. TLDs were deployed on quarterly basis for two years to obtain the cumulative gamma background radiation levels in the study area. The radiological survey was also carried out by using a calibrated radiation survey meter. The annual dose rates were computed from quarterly values actually found and normalised to 365 days. The environmental gamma radiation levels around Vishakhapatnam were found to be in the range of 0.79 mGy/y to 1.86 mGy/y. It is clearly seen from the results that location to location there is a large variation in external gamma radiation levels. During the cycle of the TLD survey, spot readings of the background radiation levels were taken, both while placing the TLDs and while removing them. The instantaneous dose rates measured using survey meter, are also following the large variation as found in TLDs. It varies between 110 nGy/hr to 210 nGy/hr. (author)

Problems Associated with the Use of the Radiochromic Dye Film as a Radiation Dose Meter

DEFF Research Database (Denmark)

Hansen, Johnny; Wille, Mads; Olsen, Kjeld J.

1984-01-01

of coloration. The dose response has been found to depend strongly on: the time span between irradiation and measurement; the irradiation temperature; and the dose rate at doses above 50 kGy for low-LET radiation. Irradiation in vacuum (right-pointing angle bracket1 Pa) and in air produced the same dose......A thorough investigation has been made of the problems involved in using a dye film dose meter for precision dosimetry at high doses, using both low- and high-LET radiation. The study includes: time course of coloration following irradiation at various dose levels; dose response after irradiation...

Some problems in calibrating surface contamination meters

International Nuclear Information System (INIS)

Chen Zigen; LI Xingyuan; Shuai Xiaoping.

1984-01-01

It is necessary that instruments are calibrated accurately in order to obtain reliable survey data of surface contamination. Some problems in calibrating surface contamination meters are expounded in this paper. Measurement comparison for beta surface contamination meters is organized within limited scope, thus survey quality is understood, questions are discovered, significance of calibration is expounded further. (Author)

Calibration methodology for instruments utilized in X radiation beams, diagnostic level

International Nuclear Information System (INIS)

Penha, M. da; Potiens, A.; Caldas, L.V.E.

2004-01-01

Methodologies for the calibration of diagnostic radiology instruments were established at the Calibration Laboratory of IPEN. The methods may be used in the calibration procedures of survey meters used in radiation protection measurements (scattered radiation), instruments used in direct beams (attenuated and non attenuated beams) and quality control instruments. The established qualities are recommended by the international standards IEC 1267 and ISO 4037-3. Two ionization chambers were used as reference systems, one with a volume of 30 cm 3 for radiation protection measurements, and the other with a volume of 1 cm 3 for direct beam measurements. Both are traceable to the German Primary Laboratory of Physikalisch-Technische Bundesanstalt (PTB). In the case of calibration of quality control instruments, a non-invasive method using the measurement of the spectrum endpoint was established with a portable gamma and X-ray Intertechnique spectrometer system. The methods were applied to survey meters (radiation protection measurements), ionization chambers (direct beam measurements) and k Vp meters (invasive and non-invasive instruments). (Author)

Calibration methodology for instruments utilized in X radiation beams, diagnostic level

Energy Technology Data Exchange (ETDEWEB)

Penha, M. da; Potiens, A.; Caldas, L.V.E. [Instituto de Pesquisas Energeticas e Nucleares, Comissao Nacional de Energia Nuclear, Sao Paulo (Brazil)]. E-mail: mppalbu@ipen.br

2004-07-01

Methodologies for the calibration of diagnostic radiology instruments were established at the Calibration Laboratory of IPEN. The methods may be used in the calibration procedures of survey meters used in radiation protection measurements (scattered radiation), instruments used in direct beams (attenuated and non attenuated beams) and quality control instruments. The established qualities are recommended by the international standards IEC 1267 and ISO 4037-3. Two ionization chambers were used as reference systems, one with a volume of 30 cm{sup 3} for radiation protection measurements, and the other with a volume of 1 cm{sup 3} for direct beam measurements. Both are traceable to the German Primary Laboratory of Physikalisch-Technische Bundesanstalt (PTB). In the case of calibration of quality control instruments, a non-invasive method using the measurement of the spectrum endpoint was established with a portable gamma and X-ray Intertechnique spectrometer system. The methods were applied to survey meters (radiation protection measurements), ionization chambers (direct beam measurements) and k Vp meters (invasive and non-invasive instruments). (Author)

Design of a statewide radiation survey

International Nuclear Information System (INIS)

Nagda, N.L.; Koontz, M.D.; Rector, H.E.; Nifong, G.D.

1989-01-01

The Florida Institute of Phosphate Research (FIPR) recently sponsored a statewide survey to identify all significant land areas in Florida where the state's environmental radiation rule should be applied. Under this rule, newly constructed buildings must be tested for radiation levels unless approved construction techniques are used. Two parallel surveys - a land-based survey and a population-based survey - were designed and conducted to address the objective. Each survey included measurements in more than 3000 residences throughout the state. Other information sources that existed at the outset of the study, such as geologic profiles mapped by previous investigators and terrestrial uranium levels characterized through aerial gamma radiation surveys, were also examined. Initial data analysis efforts focused on determining the extent of evidence of radon potential for each of 67 counties in the state. Within 18 countries that were determined to have definite evidence of elevated radon potential, more detailed spatial analyses were conducted to identify areas of which the rule should apply. A total of 74 quadrangles delineated by the U.S. Geological Survey, representing about 7% of those constituting the state, were identified as having elevated radon potential and being subject to the rule

An aerial radiological survey of the Ames Laboratory and surrounding area, Ames, Iowa

International Nuclear Information System (INIS)

Maurer, R.J.

1993-04-01

An aerial radiological survey of the Ames Laboratory and surrounding area in Ames, Iowa, was conducted during the period July 15--25, 1991. The purpose of the survey was to measure and document the terrestrial radiological environment at the Ames Laboratory and the surrounding area for use in effective environmental management and emergency response planning. The aerial survey was flown at an altitude of 200 feet (61 meters) along a series of parallel lines 350 feet (107 meters) apart. The survey encompassed an area of 36 square miles (93 square kilometers) and included the city of Ames, Iowa, and the Iowa State University. The results are reported as exposure rates at 1 meter above ground level (inferred from the aerial data) in the form of a gamma radiation contour map. Typical background exposure rates were found to vary from 7 to 9 microroentgens per hour (μR/h). No anomalous radiation levels were detected at the Ames Laboratory. However, one anomalous radiation source was detected at an industrial storage yard in the city of Ames. In support of the aerial survey, ground-based exposure rate and soil sample measurements were obtained at several sites within the survey perimeter. The results of the aerial and ground-based measurements were found to agree within the expected uncertainty of ±15%

2009 Canadian Radiation Oncology Resident Survey

International Nuclear Information System (INIS)

Debenham, Brock; Banerjee, Robyn; Fairchild, Alysa; Dundas, George; Trotter, Theresa; Yee, Don

2012-01-01

Purpose: Statistics from the Canadian post-MD education registry show that numbers of Canadian radiation oncology (RO) trainees have risen from 62 in 1999 to approximately 150 per year between 2003 and 2009, contributing to the current perceived downturn in employment opportunities for radiation oncologists in Canada. When last surveyed in 2003, Canadian RO residents identified job availability as their main concern. Our objective was to survey current Canadian RO residents on their training and career plans. Methods and Materials: Trainees from the 13 Canadian residency programs using the national matching service were sought. Potential respondents were identified through individual program directors or chief resident and were e-mailed a secure link to an online survey. Descriptive statistics were used to report responses. Results: The eligible response rate was 53% (83/156). Similar to the 2003 survey, respondents generally expressed high satisfaction with their programs and specialty. The most frequently expressed perceived weakness in their training differed from 2003, with 46.5% of current respondents feeling unprepared to enter the job market. 72% plan on pursuing a postresidency fellowship. Most respondents intend to practice in Canada. Fewer than 20% of respondents believe that there is a strong demand for radiation oncologists in Canada. Conclusions: Respondents to the current survey expressed significant satisfaction with their career choice and training program. However, differences exist compared with the 2003 survey, including the current perceived lack of demand for radiation oncologists in Canada.

2009 Canadian Radiation Oncology Resident Survey

Energy Technology Data Exchange (ETDEWEB)

Debenham, Brock, E-mail: debenham@ualberta.net [Department of Radiation Oncology, Cross Cancer Institute, University of Alberta, Edmonton, Alberta (Canada); Banerjee, Robyn [Department of Radiation Oncology, Tom Baker Cancer Centre, University of Calgary, Calgary, Alberta (Canada); Fairchild, Alysa; Dundas, George [Department of Radiation Oncology, Cross Cancer Institute, University of Alberta, Edmonton, Alberta (Canada); Trotter, Theresa [Department of Radiation Oncology, Tom Baker Cancer Centre, University of Calgary, Calgary, Alberta (Canada); Yee, Don [Department of Radiation Oncology, Cross Cancer Institute, University of Alberta, Edmonton, Alberta (Canada)

2012-03-15

Purpose: Statistics from the Canadian post-MD education registry show that numbers of Canadian radiation oncology (RO) trainees have risen from 62 in 1999 to approximately 150 per year between 2003 and 2009, contributing to the current perceived downturn in employment opportunities for radiation oncologists in Canada. When last surveyed in 2003, Canadian RO residents identified job availability as their main concern. Our objective was to survey current Canadian RO residents on their training and career plans. Methods and Materials: Trainees from the 13 Canadian residency programs using the national matching service were sought. Potential respondents were identified through individual program directors or chief resident and were e-mailed a secure link to an online survey. Descriptive statistics were used to report responses. Results: The eligible response rate was 53% (83/156). Similar to the 2003 survey, respondents generally expressed high satisfaction with their programs and specialty. The most frequently expressed perceived weakness in their training differed from 2003, with 46.5% of current respondents feeling unprepared to enter the job market. 72% plan on pursuing a postresidency fellowship. Most respondents intend to practice in Canada. Fewer than 20% of respondents believe that there is a strong demand for radiation oncologists in Canada. Conclusions: Respondents to the current survey expressed significant satisfaction with their career choice and training program. However, differences exist compared with the 2003 survey, including the current perceived lack of demand for radiation oncologists in Canada.

Physical requirements for measurement of radiation dose and their relationship to personnel dose meter design and use

International Nuclear Information System (INIS)

Chabot, G.E. Jr.; Jimenez, M.A.; Skrable, K.W.

1978-01-01

This paper stems from the concerns of the authors with both the design of current personnel dose meters and the interpretation of dose information from them in light of the actual physical requirements to measure dose. These concerns have been reinforced and extended following a comparative study of the responses of particular TLD and film systems and as the result of a recent national survey on personnel dosimetry conducted by the authors. Among the major points discussed are the systems available for penetrating and shallow dose assessment, dose meter calibration, the measurement and interpretation of skin dose, and the deficiencies of neutron albedo dose meters for routine personnel use. Calibration considerations address the questions of whether or not a phantom should be used and the difference in interpretation of responses with and without a phantom; the relationship between calculated and measured doses; and electronic equilibrium considerations in the measurement of photon doses. Matters of importance in relation to skin dose measurement include techniques in use to interpret skin dose from dose meter response; the appropriateness of evaluation of the surface dose to the live skin layer versus the average dose to the live skin layer and the limitations and requirements on dose meter design with respect to the dose being evaluated; and the significance of dose meter response in relationship to currently used beta calibration standards. Regarding the use of TLD albedo type neutron dose meters currently available, considerations are extended to the strong energy spectral dependence of the dose meter response and the possibility of making significant over or underestimations of neutron dose equivalent, depending on the calibration techniques used and the spectral quality encountered. (author)

Digital Survey Meter based on PIC16F628 Microcontroller

International Nuclear Information System (INIS)

Al-Mohamad, A.; Shliwitt, J.

2010-01-01

A Digital Survey Meter based on PIC16F628 Microcontroller was designed using simple Geiger-Muller Counter ZP1320 made by Centronic in the UK as detector. The sensitivity of this tube is about 9 counts/s at 10μGy/h. It is sensitive to gamma and beta particles over 0.25 MeV. It has a sensitive length of 28mm. Count rate versus dose rate is quite linear up to about 10 4 counts/s. Indication is given by a speaker which emits one click for each count. In addition to the acoustic alarm, the meter works according one of three different measurement modes selected using appropriate 3 states switch: 1- Measurement of Dose rate ( in μGy/h) and counting rate ( in CPS) , for High counting rates. 2- Measurement of Dose rate ( in μGy/h) and counting rate ( in CPM), for Low counting rates. 3- Accumulated Counting with continues display for No. of Counts and Counting Time with a period of 2 Sec. The results are Displayed on an Alphanumerical LCD Display, and the circuit will give many hours of operation from a single 9V PP3 battery. The design of the circuit combines between accuracy, simplicity and low power consumption. We built 2 Models of this design, the first only with an internal detector, and the second is equipped with an External Detector. (author)

Instrument evaluation no. 8. Nuclear Enterprises beta/gamma dose rate meter type 0500

International Nuclear Information System (INIS)

Iles, W.J.; Burgess, P.H.; Callowhill, K.

1977-04-01

This instrument is a portable, battery powered survey meter covering the dose rate range from 0 to 10,000 mrad h -1 and the dose range 0 to 1000 mrad. The instrument was designed to measure X and γ-radiation dose and dose rate over a wide energy range, and also β-radiation dose and dose rate. An unsealed ionisation chamber is used as the detector. The aluminised melinex thin end window of the chamber is provided with a detachable plastic end cap. The calibration plane of the chamber is indicated by a cross on the side of the instrument. The information is given under the following headings: facilities and controls; radiation characteristics; electrical characteristics; environmental characteristics; mechanical characteristics; summary of performance; conclusions. (U.K.)

Radiation dose rate meter

International Nuclear Information System (INIS)

Kronenberg, S.; Siebentritt, C.R.

1981-01-01

A combined dose rate meter and charger unit therefor which does not require the use of batteries but on the other hand produces a charging potential by means of a piezoelectric cylinder which is struck by a manually triggered hammer mechanism. A tubular type electrometer is mounted in a portable housing which additionally includes a geiger-muller (Gm) counter tube and electronic circuitry coupled to the electrometer for providing multi-mode operation. In one mode of operation, an rc circuit of predetermined time constant is connected to a storage capacitor which serves as a timed power source for the gm tube, providing a measurement in terms of dose rate which is indicated by the electrometer. In another mode, the electrometer indicates individual counts

Radiation measurement practice for understanding statistical fluctuation of radiation count using natural radiation sources

International Nuclear Information System (INIS)

Kawano, Takao

2014-01-01

It is known that radiation is detected at random and the radiation counts fluctuate statistically. In the present study, a radiation measurement experiment was performed to understand the randomness and statistical fluctuation of radiation counts. In the measurement, three natural radiation sources were used. The sources were fabricated from potassium chloride chemicals, chemical fertilizers and kelps. These materials contain naturally occurring potassium-40 that is a radionuclide. From high schools, junior high schools and elementary schools, nine teachers participated to the radiation measurement experiment. Each participant measured the 1-min integration counts of radiation five times using GM survey meters, and 45 sets of data were obtained for the respective natural radiation sources. It was found that the frequency of occurrence of radiation counts was distributed according to a Gaussian distribution curve, although the obtained 45 data sets of radiation counts superficially looked to be fluctuating meaninglessly. (author)

Calibration of dosemeters and survey instruments for photon

International Nuclear Information System (INIS)

Alamares, A.L.; Caseria, E.S.

1995-01-01

The Philippine Nuclear Research Institute (PNRI), the country's regulatory agency, through its Radiation Protection Unit of the Nuclear Regulations Licensing and Safeguard Division provides the calibration services of nuclear instruments used by various institutions. The periodic calibration and standardization of radiation and protection survey instruments are done to insure correct and valid radiation readings. It is also a regulatory requirement for radiation workers to use only operable and precalibrated survey instruments for their work with radioactive materials. The PNRI maintains and operates the Secondary Standard Dosimetry Laboratory (SSDL). It provides the periodic calibration and standardization of radiation monitoring and protection survey instruments, and also the radiological hazard and performance evaluation surveys of radiotherapy facilities and others. For the calibration of survey instruments, the standard sources of Cs-137 and Co-60 are used. The calibration procedures for survey meters and pocket dosimeters are explained. The clients served are shown. The personnel dosimetry using film badges, the application of ICRU operational quantities, and the problems encountered and recommendations are reported. (K.I.)

Background radiation measurements at 400 meter underground for dark matter search study

International Nuclear Information System (INIS)

Kim, T. Y.; Kim, H. J.; Lee, Y. C.; Won, E.; Kim, S. K.; Kim, Y. D.; So, W. Y.

1999-01-01

Recently we have performed measurements of background radiation, which is crucial for any dark matter search experiments. We measured muons, neutrons, and gamma backgrounds at approximately 400 meter underground tunnel in the electric generating facility located about 120 km east of Seoul. We believe this may be the first measurement at this depth in Korea. The muon flux measured with triple coincidence between 3 scintillating plates was reduced by a factor of 10 4 compared with the flux at ground level as expected at this depth. The unshielded gamma background measured with 15% relative efficiency germanium detector was rather high due to the surrounding rocks. Shielded with 15 cm normal lead and 2.5 cm electrode copper gave about 0.5 counts/second. (author)

Calibration of reference KAP-meters at SSDL and cross calibration of clinical KAP-meters

International Nuclear Information System (INIS)

Hetland, Per O.; Friberg, Eva G.; Oevreboe, Kirsti M.; Bjerke, Hans H.

2009-01-01

In the summer of 2007 the secondary standard dosimetry laboratory (SSDL) in Norway established a calibration service for reference air-kerma product meter (KAP-meter). The air-kerma area product, PKA, is a dosimetric quantity that can be directly related to the patient dose and used for risk assessment associated with different x-ray examinations. The calibration of reference KAP-meters at the SSDL gives important information on parameters influencing the calibration factor for different types of KAP-meters. The use of reference KAP-meters calibrated at the SSDL is an easy and reliable way to calibrate or verify the PKA indicated by the x-ray equipment out in the clinics. Material and methods. Twelve KAP-meters were calibrated at the SSDL by use of the substitution method at five diagnostic radiation qualities (RQRs). Results. The calibration factors varied from 0.94 to 1.18. The energy response of the individual KAP-meters varied by a total of 20% between the different RQRs and the typical chamber transmission factors ranged from 0.78 to 0.91. Discussion. It is important to use a calibrated reference KAP-meter and a harmonised calibration method in the PKA calibration in hospitals. The obtained uncertainty in the PKA readings is comparable with other calibration methods if the information in the calibration certificate is correct used, corrections are made and proper positioning of the KAP-chamber is performed. This will ensure a reliable estimate of the patient dose and a proper optimisation of conventional x-ray examinations and interventional procedures

Area monitoring of ambient dose rates in parts of South-Western Nigeria using a GPS-integrated radiation survey meter

International Nuclear Information System (INIS)

Okeyode, I.C.; Rabiu, J.A.; Alatise, O.O.; Makinde, V.; Akinboro, F.G.; Mustapha, A.O.; Al-Azmi, D.

2017-01-01

A radiation monitoring system comprising a Geiger-Muller counter connected to a smart phone via Bluetooth was used for a dose rate survey in some parts of south-western Nigeria. The smart phone has the Geographical Positioning System, which provides the navigation information and saves it along with the dose rate data. A large number of data points was obtained that shows the dose rate distribution within the region. The results show that the ambient dose rates in the region range from 60 to 520 nSv -1 and showed a bias that is attributable to the influence of geology on the ambient radiation dose in the region. The geology influence was demonstrated by superimposing the dose rate plot and the geological map of the area. The potential applications of the device in determining baseline information and in area monitoring, e.g. for lost or abandoned sources, radioactive materials stockpiles, etc., were discussed in the article, particularly against the background of Nigeria's plan to develop its nuclear power program. (authors)

Usage and conditions of radiation protection of nuclear meters in Brazil; Utilização e condições de proteção radiológica de medidores nucleares no Brasil

Energy Technology Data Exchange (ETDEWEB)

Guimarães, E.F. [Faculdade Casa Branca, SP (Brazil). Pós-Graduação de Proteção Radiológica em Aplicações Médicas, Industriais e Nucleares; Lima, C.M.A. [MAXIM Cursos, Rio de Janeiro-RJ (Brazil); Silva, F.C.A. da, E-mail: franciscodasilva13uk@gmail.com [Instituto de Radioproteção e Dosimetria (IRD/CNEN-RJ), Riode Janeiro, RJ (Brazil)

2017-07-01

The industries of mining, pulp, oil, etc. which require a quality control in the processes, use the nuclear meters with sealed radioactive sources coupled to a radiation detector that generate accurate and fast answers regarding the level, thickness, density and humidity of different types of materials. Nuclear meters are classified as fixed or portable and use transmission, backscatter or reactive systems. As they use radioactive sources with various ranges of activities, they are classified by the International Atomic Energy Agency - AIEA as Category 3 and 4, of medium and low radiological risk, and must therefore have a suitable level of radiation protection for safe use in the installation. The Brazilian National Energy Commission - CNEN controls approximately 500 authorized facilities with nuclear meters. The paper technically describes the nuclear meters and the radiological protection procedures that must be followed for the safety of the IOEs (occupationally exposed individuals) and individuals from the public, based on the specific nuclear meter test program for CNEN radiation protection supervisor. The professionals who handle these nuclear meters should be aware of the radiological risk to their own protection and to individuals in the public. For safe operation with nuclear meters, a number of requirements must be observed according to the type and need of the installation.

Faculty of Radiation Oncology 2010 workforce survey.

Science.gov (United States)

Leung, John; Vukolova, Natalia

2011-12-01

This paper outlines the key results of the Faculty of Radiation Oncology 2010 workforce survey and compares these results with earlier data. The workforce survey was conducted in mid-2010 using a custom-designed 17-question survey. The overall response rate was 76%. The majority of radiation oncologist respondents were male (n = 212, 71%), but the majority of trainee respondents were female (n = 59, 52.7%). The age range of fellows was 32-92 years (median: 47 years; mean: 49 years) and that of trainees was 27-44 years (median: 31 years; mean: 31.7 years). Most radiation oncologists worked at more than one practice (average: two practices). The majority of radiation oncologists worked in the public sector (n = 169, 64.5%), with some working in 'combination' of public and private sectors (n = 65, 24.8%) and a minority working in the private sector only (n = 28, 10.7%). The hours worked per week ranged from 1 to 85 (mean: 44 h; median: 45 h) for radiation oncologists, while for trainees the range was 16-90 (mean: 47 h; median: 45 h). The number of new cases seen in a year ranged from 1 to 1100 (mean: 275; median: 250). Most radiation oncologists considered themselves generalists with a preferred sub-specialty (43.3%) or specialists (41.9%), while a minority considered themselves as generalists (14.8%). There are a relatively large and increasing number of radiation oncologists and trainees compared with previous years. The excessive workloads evident in previous surveys appear to have diminished. However, further work is required on assessing the impact of ongoing feminisation and sub-specialisation. © 2011 The Authors. Journal of Medical Imaging and Radiation Oncology © 2011 The Royal Australian and New Zealand College of Radiologists.

Sector smart meter audit review report

Energy Technology Data Exchange (ETDEWEB)

NONE

2010-03-31

This paper presented the results of an electricity distributor sector smart meter audit review conducted by the Ontario Energy Board (OEB) for the period of January 1, 2006 to September 30, 2009. The review summarized the results of a questionnaire related to distributors' smart meter regulatory accounting treatment. Seventy-eight distributors responded to the survey. The review included details of: (1) total investments in smart metering initiative for capital expenditures (CAPEX) and operating maintenance and administrative expenses (OM and A), (2) funding dollars received by the distributors, (3) board-approved recoveries for CAPEX and OM and A, (4) recorded stranded meter costs, and (5) number of smart meters installed in the review period. The audit review demonstrated that some distributors incorrectly recorded carrying charges related to smart meter OM and A expenses, and that some smart meter transactions were recorded in accounts other than OEB established accounts in the general ledger. Results of the audit will be used to provide further accounting assistance to electricity distributors. 7 tabs.

Research on the calibration methods of the luminance parameter of radiation luminance meters

Science.gov (United States)

Cheng, Weihai; Huang, Biyong; Lin, Fangsheng; Li, Tiecheng; Yin, Dejin; Lai, Lei

2017-10-01

This paper introduces standard diffusion reflection white plate method and integrating sphere standard luminance source method to calibrate the luminance parameter. The paper compares the effects of calibration results by using these two methods through principle analysis and experimental verification. After using two methods to calibrate the same radiation luminance meter, the data obtained verifies the testing results of the two methods are both reliable. The results show that the display value using standard white plate method has fewer errors and better reproducibility. However, standard luminance source method is more convenient and suitable for on-site calibration. Moreover, standard luminance source method has wider range and can test the linear performance of the instruments.

Development of aerial gamma radiation survey system, 1

International Nuclear Information System (INIS)

Tsutsumi, Masahiro; Saito, Komei; Sakamoto, Ryuichi; Nagaoka, Toshi; Moriuchi, Shigeru

1986-05-01

JAERI has started to develop an aerial gamma radiation survey system by a helicopter in 1980. The development of measuring instruments, the experiments in the field of natural and artificial radiation sources, and the imaginary emergency survey at a real site, were executed. This report describes mainly about the hardware and software of this system. The system consists of gamma-ray measuring instruments with NaI(Tl) scintillation detectors, microwave positioning instruments, and a data processing system for postflight data. A foreign-made geological survey system is improved on for radiation measurements. For covering the wide radiation range, detectors of various shapes and sizes are prepared, from a large volume detector, DET-1024 - four 4'' x 4'' x 16'' crystals assembly - to a 2'' diameter x 2'' NaI(Tl) crystal. Radiation and position data are recorded on a magnetic tape, and computer-processed afterwards. Moreover, scene below flight courses and internal communication are recorded on video tape with the information of clock and position superimposed. In consequence of field experiments carried out five times, basic radiation data for evaluating airborne acquired data are accumulated, and flight survey procedures are established. As more practical use, a system has been produced more compactly and functionally. Exposure rates (> 1 mR/h), energy distribution spectra, and energy window counts are obtained for radiation data. Using the Spectrum-Dose Conversion Method, the accurate exposure rates are directly calculated from pulse height spectra. Numerical tables of G(E) function converting pulse height spectra into exposures are shown in this report. As regards the analysis of survey data, process codes have been completed with either large-computer or mini-computer. (author)

An aerial radiological survey of the RMI facility and surrounding area, Ashtabula, Ohio: Date of survey, September 1985

International Nuclear Information System (INIS)

1986-11-01

An aerial radiological survey was conducted over a 75-square-kilometer (30-square-mile) area surrounding the RMI facility in Ashtabula, Ohio, during the period between September 4 and 13, 1985. The survey was conducted at an altitude of 46 meters (150 ft). A second, more detailed survey was also performed over the RMI facility. This survey was conducted at an altitude of 30 meters (100 ft) and covered an area of about 2.6 square kilometers (1 sq mi) centered over the facility. Over most of the survey area, exposure rates varied from about 8 to 11 microentgens per hour (μR/h). Several areas of increased radioactivity were observed in addition to increased radioactivity over the RMI facility (exposure rates of up to 44 μR/h were detected). The increased radioactivity over the RMI facility was due to uranium; however, no evidence of uranium was found off site. A second site exhibiting increased radioactivity was located near a railroad siding. The anomalous radiation there was due primarily to elevated concentrations of radium. Ground samples from this location were found to contain 130,000 picocuries per gram (pCi/g) of radium-226. Two other regions of anomalous radiation were found on the shore of Lake Erie, near Pinney Dock. One of these sites contained elevated concentrations of potassium-40 (K-40). The spectrum from the second site indicated the source to be thorium. A fifth site was a facility located a few hundred meters east of the RMI plant. The spectrum from this site also indicated an increased amount of thorium. Finally, a sixth source was located in the eastern portion of the survey area. The spectrum from this site was found to be high in cesium-137 (Cs-137). 7 refs., 14 figs., 2 tabs

Rate meter design and construction

International Nuclear Information System (INIS)

Peon Aguirre, R.; Fonseca Araujo, W.H.

1989-01-01

An electric diagram is proposed to build a geiger detector Rate Meter, to count gamma radiation and X ray. This idea was made up with the prototype construction which has a five scales analogue display (100, 300, 1000, 3000 and 10000 c/s). (Author)

Performance evaluation of domestic prototype dose area product meter SFT-1

International Nuclear Information System (INIS)

Lee, Ho Sun; Han, Seong Gyu; Roh, Young Roh; Lim, Hyun Jong; Kim, Jung Min; Kim, Jong Uk; Chae, Hyun Sik; Yoon, Yong Su

2016-01-01

The importance of radiation dose display of medical X-ray equipment was emphasized, while third edition of IEC(International Electrotechnical Commission) 60601 started to apply. The existing medical X-ray equipment selected a method for attaching the DAP(Dose Area Product) meter when the dose display. However, because the DAP meter was dependent on all of the income, And it did not yet produced in Korea. So, we received the support of Seoul R and BD Program(Grants No. C1152055) to produce DAP meter prototype of the Domestically technology. In this study, the performance of this prototype was evaluated by comparing the German company's product. Evaluation item was an electronic capture performance, radiation dose dependence, radiation quality dependence, energy transmittance, repeatability, light transmittance of 6 entries. And IEC 60580 was based on this evaluation. Evaluation results were electronic capture performance intrinsic error 9.5%, radiation dose dependence limits of variation 1%, repeatabilit y coefficient of variation 2%, energy transmittance 91% each assessment was passed. However radiation quality dependence limits of variation 29%, light transmittance 55% was less than acceptance criteria

Practical methods for radiation survey in nuclear installations

International Nuclear Information System (INIS)

Shweikani, R.

2001-12-01

This study is placed to those who are responsible to perform radiation survey in the nuclear installations, especially the beginners. Therefore, it gives a comprehensive view to all-important aspects related to their work starting from the structure of atoms to the practical steps for radiation survey works. So, it clarify how to perform personal monitoring, methods for monitoring surface contamination, methods for measuring radioactivity of gases and radioactive aerosols in air, monitoring radiation doses, measuring radiation influences in workplaces and finally measuring internal exposure of radiation workers in nuclear installations. Finally, The study shows some cases of breaches of radiation protection rules in some American nuclear installations and describes the final results of these breaches. The aim of this is to assure that any breach or ignore to radiation protection principles may produce bad results, and there is no leniency in implementing environmental radiation protection principles. (author)

An aerial radiological survey of the Fernald Environmental Management Project and surrounding area, Fernald, Ohio

International Nuclear Information System (INIS)

Phoenix, K.A.

1997-04-01

An aerial radiological survey was conducted from May 17--22, 1994, over a 36 square mile (93 square kilometer) area centered on the Fernald Environmental Management Project located in Fernald, Ohio. The purpose of the survey was to detect anomalous gamma radiation in the environment surrounding the plant. The survey was conducted at a nominal altitude of 150 feet (46 meters) with a line spacing of 250 feet (76 meters). A contour map of the terrestrial gamma exposure rate extrapolated to 1 meter (3.3 feet) above ground was prepared and overlaid on an aerial photograph of the area. Analysis of the data for man made sources showed five sites within the boundaries of the Fernald Environmental Management Project having elevated readings. The exposure rates outside the plant boundary were typical of naturally occurring background radiation. Soil samples and pressurized ion chamber measurements were obtained at four locations within the survey boundaries to supplement the aerial data. It was concluded that although the radionuclides identified in the high-exposure-rate areas are naturally occurring, the levels encountered are greatly enhanced due to industrial activities at the plant

Methodical recommendations for power unit comprehensive engineering and radiation survey

International Nuclear Information System (INIS)

Nosovskij, A.V.

2000-01-01

The article describes power unit radiation survey methods developed and applied during conduction of Ch NPP unit I Comprehensive Engineering Radiation Survey. Special requirements for units under decommissioning, main survey principals, criteria for definition of volume and the order of survey for various systems of a NPP Unit are included

An aerial radiological survey of the Oyster Creek Nuclear Power Plant and surrounding area, Forked River, New Jersey. Date of survey: September 18--25, 1992

International Nuclear Information System (INIS)

Hopkins, H.A.; McCall, K.A.

1994-05-01

An aerial radiological survey was conducted over the Oyster Creek Nuclear Power Plant in Forked River, New Jersey, during the period September 18 through September 24, 1992. The survey was conducted at an altitude of 150 feet (46 meters) over a 26-square-mile (67-square-kilometer) area centered on the power station. The purpose of the survey was to document the terrestrial gamma radiation environment of the Oyster Creek Nuclear Power plant and surrounding area. The results of the aerial survey are reported as inferred gamma radiation exposure rates at 1 meter above ground level in the form of a contour map. Outside the plant boundary, exposure rates were found to vary between 4 and 10 microroentgens per hour and were attributed to naturally-occurring uranium, thorium, and radioactive potassium gamma emitters. The aerial data were compared to ground-based benchmark exposure rate measurements and radionuclide assays of soil samples obtained within the survey boundary. The ground-based measurements were found to be in good agreement with those inferred from the aerial measuring system. A previous survey of the power plant was conducted in August 1969 during its initial startup phase. Exposure rates and radioactive isotopes revealed in both surveys were consistent and within normal terrestrial background levels

Reactor Power Meter type SG-8

Energy Technology Data Exchange (ETDEWEB)

Glowacki, S W

1981-01-01

The report describes the principle and electronic circuits of the Reactor Power Meter type SG-8. The gamma radiation caused by the activity of the reactor first cooling circuit affectes the ionization chamber being the detector of the instrument. The output detector signal direct current is converted into the frequency of electric pulses by means of the current-to-frequency converter. The output converter frequency is measured by the digital frequency meter: the number of measured digits in time unit is proportional to the reactor power.

Preliminary study on the measurement of background radiation dose at Antarctica during 32nd expedition

International Nuclear Information System (INIS)

Bakshi, A.K.; Pal, Rupali; Chougaonkar, M.P.; Dhar, Ajay

2013-01-01

A significant proportion (10%) of the natural background radiation is of cosmic origin. Cosmic ray consists of gamma, protons, electrons, pions, muons, neutrons and low Z nuclei. Due to the geomagnetic effect, cosmic radiation levels at poles are higher. As a consequence, personnel working in Antarctica (or Arctic) are subjected to high level of cosmic radiation. The present study gives the details of the estimation of background radiation (neutrons, gamma and electrons) dose rate around the Indian station at Antarctica named 'Bharati' measured during 32 nd Indian scientific expedition to Antarctica (32 nd INSEA). The measurement was carried out by passive dosimeters such as TLDs and CR-39 and active dosimeter such as RadEye G portable gamma survey meter. Gamma and electron components were measured using TLDs and survey meter, whereas CR-39 SSNTDs and neutron sensitive TLDs were used for neutron measurements. These detectors were deployed at few selected locations around Bharati station for about 2½ months during summer expedition. The neutron detectors used in the study were pre-calibrated with 241 Am-Be fast/thermal neutron source. The fast neutron dose rate measured based on CR-39 detector was found to about 140-420 nSv/h. The gamma dose rate evaluated by TLDs/survey meter are in the range of 290-400 nSv/h. (author)

Aerial radiological survey of the Diablo Canyon Nuclear Power Plant and surrounding area, Diablo Canyon, California. Date of survey: September-October 1984

International Nuclear Information System (INIS)

1985-03-01

An aerial radiological survey was conducted over the area surrounding the Diablo Canyon Nuclear Power Plant in Diablo Canyon, California. The survey was conducted between 20 September and 3 October 1984. A series of flight lines parallel to the coastline were flown at an altitude of 91 meters (300 feet) and were spaced 152 meters (500 feet) apart. The survey covered an area of 250 square kilometers (100 square miles). The resulting background exposure rates over the survey area ranged from 5 to 21 microroentgens per hour (μR/h). The reported exposure rate values include an estimated cosmics ray contribution of 3.6 μR/h. Soil samples were also collected at several locations within the survey areas and analyzed in the laboratory for isotopic composition. The results of the survey showed only the presence of naturally occurring background radiation. No man-made radioactivity was detected. 4 refs., 4 figs., 4 tabs

American Society for Radiation Oncology (ASTRO) Survey of Radiation Biology Educators in U.S. and Canadian Radiation Oncology Residency Programs

International Nuclear Information System (INIS)

Rosenstein, Barry S.; Held, Kathryn D.; Rockwell, Sara; Williams, Jacqueline P.; Zeman, Elaine M.

2009-01-01

Purpose: To obtain, in a survey-based study, detailed information on the faculty currently responsible for teaching radiation biology courses to radiation oncology residents in the United States and Canada. Methods and Materials: In March-December 2007 a survey questionnaire was sent to faculty having primary responsibility for teaching radiation biology to residents in 93 radiation oncology residency programs in the United States and Canada. Results: The responses to this survey document the aging of the faculty who have primary responsibility for teaching radiation biology to radiation oncology residents. The survey found a dramatic decline with time in the percentage of educators whose graduate training was in radiation biology. A significant number of the educators responsible for teaching radiation biology were not fully acquainted with the radiation sciences, either through training or practical application. In addition, many were unfamiliar with some of the organizations setting policies and requirements for resident education. Freely available tools, such as the American Society for Radiation Oncology (ASTRO) Radiation and Cancer Biology Practice Examination and Study Guides, were widely used by residents and educators. Consolidation of resident courses or use of a national radiation biology review course was viewed as unlikely by most programs. Conclusions: A high priority should be given to the development of comprehensive teaching tools to assist those individuals who have responsibility for teaching radiation biology courses but who do not have an extensive background in critical areas of radiobiology related to radiation oncology. These findings also suggest a need for new graduate programs in radiobiology.

Measurement of Gamma Radiation in an Automobile Mechanic ...

African Journals Online (AJOL)

Environmental radiation measurement was carried out in an automobile mechanic village, Apo, Abuja, Nigeria. An in-situ measurement approach was adopted using RDS-200 Universal Survey Meter and a handheld Global Positioning System (Garmin GPS 76S) equipment. It was observed that the dose equivalent varied ...

KVP meter errors induced by plastic wrap

International Nuclear Information System (INIS)

Jefferies, D.; Morris, J.W.; White, V.P.

1991-01-01

The purpose of this study was to determine whether erroneous kVp meter readings, induced by plastic wrap, affected the actual kVp (output) of a dental X-ray machine. To evaluate the effect of plastic wrap on dental X-ray machine kVp meters, a radiation output device was used to measure output in mR/ma.s. An intraoral dental X-ray unit (S.S. White Model number-sign 90W) was used to make the exposures. First, the kVp meter was not covered with plastic wrap and output readings were recorded at various kVp settings with the milliamperage and time held constant. Secondly, the same kVp settings were selected before the plastic wrap was placed. Milliamperage and time were again held to the same constant. The X-ray console was then covered with plastic wrap prior to measuring the output for each kVp. The wrap possessed a static charge. This charge induced erroneous kVp meter readings. Out-put readings at the various induced kVp settings were then recorded. A kVp of 50 with no wrap present resulted in the same output as a kVp of 50 induced to read 40 or 60 kVp by the presence of wrap. Similar results were obtained at other kVp settings. This indicates that the plastic wrap influences only the kVp meter needle and not the actual kilovoltage of the X-ray machine. Dental X-ray machine operators should select kVp meter readings prior to placing plastic wrap and should not adjust initial settings if the meter is deflected later by the presence of wrap. The use of such a procedure will result in proper exposures, fewer retakes, and less patient radiation. If plastic wrap leads to consistent exposure errors, clinicians may wish to use a 0.5% sodium hypochlorite disinfectant as an alternative to the barrier technique

Measuring set: Reactor Power Meter (type of SG-8), Reactor Energy Meter (type of SG-11) and Digital Dose Meter (type of SG-9) for reactor rigs operation. Zestaw pomiarowy: miernik mocy reaktora (typ SG-8), miernik energii reaktora (typ SG-11) oraz cyfrowy miernik dawki (typ SG-9) dla potrzeb eksploatacji sond reaktorowych

Energy Technology Data Exchange (ETDEWEB)

Glowacki, S W

1982-01-01

A measuring set consisting of the Reactor Power Meter, Reactor Energy Meter and Digital Dose Meter is described. The gamma radiation of water in the reactor primary cooling circuit reaches the ionisation chamber and involves the output current, driving the Reactor Power Meter and Reactor Energy Meter. The Digital Dose Meter is controlled by the output current of the self-powered detector mounted inside the reactor rig.

Medium Access Control for Thermal Energy Harvesting in Advanced Metering Infrastructures

DEFF Research Database (Denmark)

Vithanage, Madava D.; Fafoutis, Xenofon; Andersen, Claus Bo

2013-01-01

In this paper we investigate the feasibility of powering wireless metering devices, namely heat cost allocators, by thermal energy harvested from radiators. The goal is to take a first step toward the realization of Energy-Harvesting Advanced Metering Infrastructures (EH-AMIs). While traditional...

Research progress in airborne surveys of terrestrial gamma radiation

International Nuclear Information System (INIS)

Burson, Z.G.

1974-01-01

Progress during the last few years in airborne surveys of terrestrial gamma radiation, i.e. in the measuring, recording, and interpreting of gamma ray signals in NaI(Tl) crystals, is discussed. Non-terrestrial background contributions have been accurately characterized. The feasibility of determining the water equivalent of snow cover by aerial survey techniques has been demonstrated. Repeat surveys over areas surrounding reactor sites can now be used to detect average differences of less than 1.0 μR/hr in terrestrial gamma radiation levels. New data acquisition and recording systems allow isotope concentrations and total inventories to be measured in spatial resolutions of a few hundred feet. Aerial survey data have been combined with population distribution data to obtain population exposure values from natural terrestrial gamma radiation around reactor sites

Reference radiation fields - Simulated workplace neutron fields - Part 2: Calibration fundamentals related to the basic quantities

International Nuclear Information System (INIS)

2008-01-01

ISO 8529-1, ISO 8529-2 and ISO 8529-3, deal with the production, characterization and use of neutron fields for the calibration of personal dosimeters and area survey meters. These International Standards describe reference radiations with neutron energy spectra that are well defined and well suited for use in the calibration laboratory. However, the neutron spectra commonly encountered in routine radiation protection situations are, in many cases, quite different from those produced by the sources specified in the International Standards. Since personal neutron dosimeters, and to a lesser extent survey meters, are generally quite energy dependent in their dose equivalent response, it might not be possible to achieve an appropriate calibration for a device that is used in a workplace where the neutron energy spectrum and angular distribution differ significantly from those of the reference radiation used for calibration. ISO 8529-1 describes four radionuclide based neutron reference radiations in detail. This part of ISO 12789 includes the specification of neutron reference radiations that were developed to closely resemble radiation that is encountered in practice

FY 1998 survey report. Petroleum substituting energy metering analysis survey; 1998 nendo chosa hokokusho. Sekiyu daitai energy keiryo bunseki chosa

Energy Technology Data Exchange (ETDEWEB)

NONE

1999-03-01

In this survey, metering models in the Asian/Pacific region where energy demand is rapidly increasing were constructed which are used for the comprehensive analysis of the relations between changes in social structure such as economic growth, change in industrial structure, and progress in energy conservation technology and new energy technology, and the energy supply/demand structure. The survey was carried out aiming at contributing to the international development of Japan's energy policy in future by quantitatively analyzing/evaluating influences of various energy policies/economic policies on the economy and energy supply/demand, through various kinds of simulation models. In FY 1998, information collection for modeling was made in China and Korea out of the Asian/Pacific region. At the same time, pilot models were constructed, and simulation was made for the standard case. Moreover, an analysis was conducted of the relation between economic growth and motorization in each country of the world as the basic data preparation on energy consumption in the transportation sector. (NEDO)

Status of Net Metering: Assessing the Potential to Reach Program Caps

Energy Technology Data Exchange (ETDEWEB)

Heeter, J.; Gelman, R.; Bird, L.

2014-09-01

Several states are addressing the issue of net metering program caps, which limit the total amount of net metered generating capacity that can be installed in a state or utility service territory. In this analysis, we examine net metering caps to gain perspective on how long net metering will be available in various jurisdictions under current policies. We also surveyed state practices and experience to understand important policy design considerations.

Investigations of actual conditions of medical radiation technologists

International Nuclear Information System (INIS)

2002-01-01

At 50 year after enactment of the law of medical radiation technologists, their actual conditions were investigated. The investigation was done in December 2001 by questionnaire to directors of 10,514 facilities and answers were obtained from 4,241 facilities (40.37%). Following 11 questions (major answers and their analysis in parenthesis) were made: Nature of the facility (Private hospitals 45.8%, public ones 20.8%); State of radiation department (Independent department of the technologists from medical one about 30%); Actual job of the technologists (X-ray about 81% of the facilities, angiography 34%, CT 78%, MRI 38% where 94% of technologists conduct, nuclear medicine 17%, ultrasound 51% where, 10%); Personnel of the radiation department (21,897 persons in total/male 85%); Fulfillment of the personnel number; Treatment of the personnel; Acknowledgement system of the Technologist Society; Management of radiation instruments like daily examination; Radiation control (Leak dose measurement by technologists by themselves about 50% facilities for X-ray and radio-therapy); Medical exposure (Measurement experience about 50%); and Possession of dose rate-meter/survey-meter (Possession in about 40% facilities). (N.I.)

Investigations of actual conditions of medical radiation technologists

Energy Technology Data Exchange (ETDEWEB)

NONE

2002-12-01

At 50 year after enactment of the law of medical radiation technologists, their actual conditions were investigated. The investigation was done in December 2001 by questionnaire to directors of 10,514 facilities and answers were obtained from 4,241 facilities (40.37%). Following 11 questions (major answers and their analysis in parenthesis) were made: Nature of the facility (Private hospitals 45.8%, public ones 20.8%); State of radiation department (Independent department of the technologists from medical one about 30%); Actual job of the technologists (X-ray about 81% of the facilities, angiography 34%, CT 78%, MRI 38% where 94% of technologists conduct, nuclear medicine 17%, ultrasound 51% where, 10%); Personnel of the radiation department (21,897 persons in total/male 85%); Fulfillment of the personnel number; Treatment of the personnel; Acknowledgement system of the Technologist Society; Management of radiation instruments like daily examination; Radiation control (Leak dose measurement by technologists by themselves about 50% facilities for X-ray and radio-therapy); Medical exposure (Measurement experience about 50%); and Possession of dose rate-meter/survey-meter (Possession in about 40% facilities). (N.I.)

2003 survey of Canadian radiation oncology residents

International Nuclear Information System (INIS)

Yee, Don; Fairchild, Alysa; Keyes, Mira; Butler, Jim; Dundas, George

2005-01-01

Purpose: Radiation oncology's popularity as a career in Canada has surged in the past 5 years. Consequently, resident numbers in Canadian radiation oncology residencies are at all-time highs. This study aimed to survey Canadian radiation oncology residents about their opinions of their specialty and training experiences. Methods and Materials: Residents of Canadian radiation oncology residencies that enroll trainees through the Canadian Resident Matching Service were identified from a national database. Residents were mailed an anonymous survey. Results: Eight of 101 (7.9%) potential respondents were foreign funded. Fifty-two of 101 (51.5%) residents responded. A strong record of graduating its residents was the most important factor residents considered when choosing programs. Satisfaction with their program was expressed by 92.3% of respondents, and 94.3% expressed satisfaction with their specialty. Respondents planning to practice in Canada totaled 80.8%, and 76.9% plan to have academic careers. Respondents identified job availability and receiving adequate teaching from preceptors during residency as their most important concerns. Conclusions: Though most respondents are satisfied with their programs and specialty, job availability and adequate teaching are concerns. In the future, limited time and resources and the continued popularity of radiation oncology as a career will magnify the challenge of training competent radiation oncologists in Canada

Organization of radiation survey

International Nuclear Information System (INIS)

Yatsenko, V.N.; Mazanov, V.L.

1995-01-01

The main organizing principles which guarantee efficient activities of medical-sanitary teams of disaster medicine in emergency situations connected with radiation injuries are studied in this paper. The study has demonstrated the priority measures being carried out by radiological team of the Russian Center on Disaster Medicine Zashchita during the current and preparatory periods and in the course of emergency situation, as well as the equipping of the teams. When arranging radiation survey the main emphasis should be placed on the detection of the injured, ascertaining the place and time of location of the personnel and population starting from the moment of the accident, as well as to determine the dynamics of the power of photon radiation in this place in the same period. Special attention is paid to the necessity of coordination on interaction of radiological team of the Russian Center of Disaster Medicine Zashchita with other similar departmental services. 5 refs

Survey of Radiation Protection Education and Training in Finland in 2003

International Nuclear Information System (INIS)

Havukainen, R.; Korpela, H.; Vaisala, S.; Piri, A.; Kettunen, E.

2004-01-01

The current state and need for radiation protection training in Finland have been surveyed by the Radiation and Nuclear Safety Authority STUK. The survey sought to determine whether the current requirements for radiation protection training had been met, and to promote radiation protection training. Details of the scope and quality of present radiation protection training were requested from all educational institutes and organizations providing radiation protection training. The survey covered both basic and further training, special training of radiation safety officers, and supplementary training. The questionnaire was sent to 77 educational organization units, 66 per cent of which responded. Radiation workers and radiation safety officers were asked about radiation protection knowledge and needs for additional training. The questionnaire was sent to 880 radiation users and 170 radiation safety officers, 70 per cent of whom responded. The survey covered all professional groups and fields of the use of ionizing radiation except nuclear energy. The amount of radiation protection training in basic and further (specialization) training in the same vocational or academic degree varied remarkably by educational organization. The average amounts of radiation protection included in most professional degrees met the requirements. 32 per cent of workers considered their radiation protection training inadequate for their duties, and 48 per cent had completed no supplementary training in radiation protection over the last five years. Nurses working in public sector hospitals and physicians working in health centres had the greatest need for radiation protection training. 78 per cent of radiation workers in industry felt that they had sufficient radiation protection training. Co-operation between educational organizations is necessary to harmonize radiation protection training. Guidance of the Ministry of Education (the competent authority for education) is needed in this

Measurement of Gamma Radiation in an Automobile Mechanic ...

African Journals Online (AJOL)

imeh james

Nuclear Technology Centre, Nigeria Atomic Energy Commission, ... An in-situ measurement approach was adopted using RDS-200 Universal Survey Meter and a handheld ... the people living and working within the area are safe and are not exposed to high doses of radiation as a result .... battery works, panel beating e.t.c..

An aerial radiological survey of the Vermont Yankee Nuclear Power Station and surrounding area, Vernon, Vermont

International Nuclear Information System (INIS)

Reiman, R.; Bluitt, C.M.

1993-10-01

An aerial radiological survey was conducted over the Vermont Yankee Nuclear Power Station in Vernon, Vermont, during the period August 7 through August 17, 1989. The survey was conducted at an altitude of 300 feet (91 meters) over a 65-square-mile (168-square-kilometer) area centered on the power station. The purpose of the survey was to document the terrestrial gamma radiation environment of the Vermont Yankee Power Station and surrounding area. The results of the aerial survey are reported as inferred gamma radiation exposure rates at 1 meter above ground level in the form of a contour map. Outside the plant boundary, exposure rates were found to vary between 6 and 10 microroentgens per hour (μR/h) and were attributed to naturally occurring uranium, thorium, and radioactive potassium gamma emitters. The aerial data were compared to ground-based open-quotes benchmarkclose quotes exposure rate measurements and radionuclide assays of soil samples obtained within the survey boundary. The ground-based measurements were found to be in good agreement with those inferred from the aerial measuring system

An aerial radiological survey of the Yankee Rowe Nuclear Power Station and surrounding area, Rowe, Massachusetts

International Nuclear Information System (INIS)

Boyns, P.K.; Bluitt, C.M.

1993-09-01

An aerial radiological survey was conducted over the Yankee Rowe Nuclear Power Station in Rowe, Massachusetts, during the period August 17--24, 1989. The survey was conducted at an altitude of 300 feet (91 meters) over an 87-square-mile (225-square-kilometer) area centered on the power station. The purpose of the survey was to document the terrestrial gamma radiation environment of the Yankee Rowe Power Station and the surrounding area. The results of the aerial survey are reported as inferred gamma radiation exposure rates at 1 meter above ground level in the form of a contour map. Outside the plant boundary, exposure rates were found to vary between 6 and 10 microroentgens per hour (μR/h) and were attributed to naturally-occurring uranium, thorium, and radioactive potassium gamma emitters. The aerial data were compared to ground-based ''benchmark'' exposure rate measurements and radionuclide assays of soil samples obtained within the survey boundary. The ground-based measurements were found to be in good agreement with those inferred from the aerial measuring system

Survey of Canadian hospitals radiation emergency plans

Energy Technology Data Exchange (ETDEWEB)

Davis, C [Social Data Research Ltd./The Flett Consulting Group, Inc., Ottawa, ON (Canada)

1996-02-01

This report documents the findings of a survey of Canadian hospitals conducted by Social Data Research Ltd. during the Spring and Summer, 1995. The main objective of the survey was to determine the state of readiness of Canadian hospitals in respect of radiation emergency planning. In addition, the AECB was interested in knowing the extent to which a report by the Group of Medical Advisors, `GMA-3: Guidelines on Hospital Emergency Plans for the Management of Minor Radiation Accidents`, which was sponsored and distributed in 1993, was received and was useful to hospital administrators and emergency personnel. A self-administered questionnaire was distributed to 598 acute care hospitals, and 274 responses were received. The main conclusion of this study is that, with the exception of a few large institutions, hospitals generally do not have specific action plans to handle minor radiation accidents. (author).

Survey of Canadian hospitals radiation emergency plans

International Nuclear Information System (INIS)

Davis, C.

1996-02-01

This report documents the findings of a survey of Canadian hospitals conducted by Social Data Research Ltd. during the Spring and Summer, 1995. The main objective of the survey was to determine the state of readiness of Canadian hospitals in respect of radiation emergency planning. In addition, the AECB was interested in knowing the extent to which a report by the Group of Medical Advisors, 'GMA-3: Guidelines on Hospital Emergency Plans for the Management of Minor Radiation Accidents', which was sponsored and distributed in 1993, was received and was useful to hospital administrators and emergency personnel. A self-administered questionnaire was distributed to 598 acute care hospitals, and 274 responses were received. The main conclusion of this study is that, with the exception of a few large institutions, hospitals generally do not have specific action plans to handle minor radiation accidents. (author)

Borehole gravity meter survey in drill hole USW G-4, Yucca Mountain Area, Nye County, Nevada

International Nuclear Information System (INIS)

Healey, D.L.; Clutsom, F.G.; Glover, D.A.

1986-01-01

Drill hole USW G-4 was logged with the US Geological Survey borehole gravity meter (BHGM) BH-6 as part of a detailed study of the lithostratigraphic units penetrated by this hole. Because the BHGM measures a larger volume of rock than the conventional gamma-gamma density tool, it provides an independent and more accurate measurement of the in situ average bulk density of thick lithologic units. USW G-4 is an especially important hole because of its proximity to the proposed exploratory shaft at Yucca Mountain. The BHGM data were reduced to interval densities using a free-air gradient (F) of 0.3083 mGal./m (0.09397 mGal/ft) measured at the drill site. The interval densities were further improved by employing an instrument correction factor of 1.00226. This factor was determined from measurements obtained by taking gravity meter BH-6 over the Charleston Peak calibration loop. The interval density data reported herein, should be helpful for planning the construction of the proposed shaft

Radiation surveys in contaminated communities

International Nuclear Information System (INIS)

Knight, G.B.

1977-01-01

Radiation surveys of uranium contamination in Uranium City and Port Hope, Canada, are described. Samples of soil, water, and crops grown in contaminated soil and air in homes were analyzed for radon content. Following decontamination, measurements were made of γ exposure rates both inside and outside of buildings

Smart meter adoption and deployment strategy for residential buildings in Indonesia

International Nuclear Information System (INIS)

Chou, Jui-Sheng; Gusti Ayu Novi Yutami, I

2014-01-01

Highlights: • Limited consumer awareness of smart meters contributes to skepticism. • Data obtained from a survey of energy users are analyzed using SEM. • A CAP index is developed via SEM results to measure consumer propensity for adopting smart meters. • The findings of this study enhance understanding of consumer perceptions and behaviors. • Concrete strategies are proposed to help policy makers and utility companies. - Abstract: For countries pursuing sustainable development and energy efficiency, the use of smart meters is considered a first step in allowing residential consumers to remotely control their energy consumption, and a promising technology for conserving limited energy resources. However, despite the growing interest in smart meters, limited consumer awareness, knowledge, and understanding of these devices contributes to skepticism. This study thus developed an index to measure consumer propensity to adopt smart meters in residential buildings. Data obtained from a survey of energy use by Indonesian households were analyzed using structural equation modeling to determine the interacting factors in consumer acceptance of smart meters. Consumer perceptions, expectations, and intentions regarding the potential use of smart meters in Indonesia were also discussed. The findings of this study enhance understanding of consumer perceptions and behaviors, and can help decision makers and energy utility companies develop policies and strategies for a “one-size-fits-all” program related to smart meter applications in future residential buildings

Development and pilot of an international survey: 'Radiation Therapists and Psychosocial Support'.

Science.gov (United States)

Elsner, Kelly L; Naehrig, Diana; Halkett, Georgia K B; Dhillon, Haryana M

2018-06-07

Up to one third of radiation therapy patients are reported to have unmet psychosocial needs. Radiation therapists (RTs) have daily contact with patients and can provide daily psychosocial support to reduce patient anxiety, fear and loneliness. However, RTs vary in their values, skills, training, knowledge and involvement in providing psychosocial support. The aims of this study were to: (1) develop an online survey instrument to explore RT values, skills, training and knowledge regarding patient anxiety and psychosocial support, and (2) pilot the instrument with RT professionals to assess content validity, functionality and length. An online cross-sectional survey, titled 'Radiation therapists and psychosocial support' was developed. Items included patient vignettes, embedded items from RT research, and the Professional Quality of Life Scale (ProQOL5). Four radiation oncology departments volunteered to pilot the survey; each nominated four RT staff to participate. Survey data were analysed descriptively and qualitative feedback grouped and coded to determine whether the survey needed to be refined. Thirteen of sixteen RTs completed the pilot survey and feedback form. Median time to completion was 35 mins, with 54% of respondents stating this was too long. Respondents reported content, questions and response options were relevant and appropriate. Feedback was used to: refine the survey instrument, minimise responder burden and drop out and improve functionality and quality of data collection. This pilot of the 'Radiation therapists and psychosocial support' survey instrument demonstrated content validity and usability. The main survey will be circulated to a representative sample of RTs for completion. © 2018 The Authors. Journal of Medical Radiation Sciences published by John Wiley & Sons Australia, Ltd on behalf of Australian Society of Medical Imaging and Radiation Therapy and New Zealand Institute of Medical Radiation Technology.

X and gamma reference radiation for calibrating dosemeters and doserate meters and for determining their response as a function of photon energy - Part 4: Calibration of area and personal dosemeters in low energy X reference radiation fields

International Nuclear Information System (INIS)

2004-01-01

ISO 4037 consists of the following parts, under the general title X and gamma reference radiation for calibrating dosemeters and doserate meters and for determining their response as a function of photon energy: Part 1: Radiation characteristics and production methods; Part 2: Dosimetry for radiation protection over the energy ranges from 8 keV to 1,3 MeV and 4 MeV to 9 MeV; Part 3: Calibration of area and personal dosemeters and the measurement of their response as a function of energy and angle of incidence; Part 4: Calibration of area and personal dosemeters in low energy X reference radiation fields. This part 4. of ISO 4037 gives guidelines on additional aspects of the characterization of low energy photon radiations. This part of ISO 4037 also describes procedures for calibration and determination of the response of area and personal dose(rate)meters as a function of photon energy and angle of incidence. This part of ISO 4037 concentrates on the accurate determination of conversion coefficients from air kerma to Hp(10) and H*(10) for the spectra of low energy photon radiations. As an alternative to the use of conversion coefficients, the direct calibration in terms of these quantities by means of appropriate reference instruments is described

FY 1998 survey report. Petroleum substituting energy metering analysis survey; 1998 nendo chosa hokokusho. Sekiyu daitai energy keiryo bunseki chosa

Energy Technology Data Exchange (ETDEWEB)

NONE

1999-03-01

In this survey, metering models in the Asian/Pacific region where energy demand is rapidly increasing were constructed which are used for the comprehensive analysis of the relations between changes in social structure such as economic growth, change in industrial structure, and progress in energy conservation technology and new energy technology, and the energy supply/demand structure. The survey was carried out aiming at contributing to the international development of Japan's energy policy in future by quantitatively analyzing/evaluating influences of various energy policies/economic policies on the economy and energy supply/demand, through various kinds of simulation models. In FY 1998, information collection for modeling was made in China and Korea out of the Asian/Pacific region. At the same time, pilot models were constructed, and simulation was made for the standard case. Moreover, an analysis was conducted of the relation between economic growth and motorization in each country of the world as the basic data preparation on energy consumption in the transportation sector. (NEDO)

Electro-optical equivalent calibration technology for high-energy laser energy meters

Energy Technology Data Exchange (ETDEWEB)

Wei, Ji Feng, E-mail: wjfcom2000@163.com [State Key Laboratory of Precision Measurement Technology and Instrument, Tsinghua University, Beijing 100084 (China); Institute of Applied Electronics, China Academy of Engineering Physics, Mianyang 621900 (China); Graduate School of China Academy of Engineering Physics, Beijing 100088 (China); Key Laboratory of Laser Science and Technology, China Academy of Engineering Physics, Mianyang 621900 (China); Chang, Yan; Zhang, Kai; Hu, Xiao Yang; Zhang, Wei [Institute of Applied Electronics, China Academy of Engineering Physics, Mianyang 621900 (China); Key Laboratory of Laser Science and Technology, China Academy of Engineering Physics, Mianyang 621900 (China); Sun, Li Qun [State Key Laboratory of Precision Measurement Technology and Instrument, Tsinghua University, Beijing 100084 (China)

2016-04-15

Electro-optical equivalent calibration with high calibration power and high equivalence is particularly well-suited to the calibration of high-energy laser energy meters. A large amount of energy is reserved during this process, however, which continues to radiate after power-off. This study measured the radiation efficiency of a halogen tungsten lamp during power-on and after power-off in order to calculate the total energy irradiated by a lamp until the high-energy laser energy meter reaches thermal equilibrium. A calibration system was designed based on the measurement results, and the calibration equivalence of the system was analyzed in detail. Results show that measurement precision is significantly affected by the absorption factor of the absorption chamber and by heat loss in the energy meter. Calibration precision is successfully improved by enhancing the equivalent power and reducing power-on time. The electro-optical equivalent calibration system, measurement uncertainty of which was evaluated as 2.4% (k = 2), was used to calibrate a graphite-cone-absorption-cavity absolute energy meter, yielding a calibration coefficient of 1.009 and measurement uncertainty of 3.5% (k = 2). A water-absorption-type high-energy laser energy meter with measurement uncertainty of 4.8% (k = 2) was considered the reference standard, and compared to the energy meter calibrated in this study, yielded a correction factor of 0.995 (standard deviation of 1.4%).

Development of a calibration methodology and tests of kerma area product meters

International Nuclear Information System (INIS)

Costa, Nathalia Almeida

2013-01-01

The quantity kerma area product (PKA) is important to establish reference levels in diagnostic radiology exams. This quantity can be obtained using a PKA meter. The use of such meters is essential to evaluate the radiation dose in radiological procedures and is a good indicator to make sure that the dose limit to the patient's skin doesn't exceed. Sometimes, these meters come fixed to X radiation equipment, which makes its calibration difficult. In this work, it was developed a methodology for calibration of PKA meters. The instrument used for this purpose was the Patient Dose Calibrator (PDC). It was developed to be used as a reference to check the calibration of PKA and air kerma meters that are used for dosimetry in patients and to verify the consistency and behavior of systems of automatic exposure control. Because it is a new equipment, which, in Brazil, is not yet used as reference equipment for calibration, it was also performed the quality control of this equipment with characterization tests, the calibration and an evaluation of the energy dependence. After the tests, it was proved that the PDC can be used as a reference instrument and that the calibration must be performed in situ, so that the characteristics of each X-ray equipment, where the PKA meters are used, are considered. The calibration was then performed with portable PKA meters and in an interventional radiology equipment that has a PKA meter fixed. The results were good and it was proved the need for calibration of these meters and the importance of in situ calibration with a reference meter. (author)

An aerial radiological survey of the Fort Calhoun Nuclear Power Plant and surrounding area, Fort Calhoun, Nebraska

International Nuclear Information System (INIS)

1994-05-01

An aerial radiological survey was conducted over the Fort Calhoun Nuclear Power Plant in Fort Calhoun, Nebraska, during the period June 19 through June 28, 1993. The survey was conducted at an altitude of 150 feet (46 meters) over a 25-square-mile (65-square-kilometer) area centered on the power station. The purpose of the survey was to document the terrestrial gamma radiation environment of the Fort Calhoun Nuclear Power Plant and surrounding area. The results of the aerial survey are reported as inferred gamma radiation exposure rates at 1 meter above ground level in the form of a contour map. Outside the plant boundary, exposure rates were found to vary between 6 and 12 microroentgens per hour and were attributed to naturally-occurring uranium, thorium, and potassium. The aerial data were compared to ground-based benchmark exposure rate measurements and radionuclide assays of soil samples obtained within the survey boundary. The ground-based measurements were found to be in good agreement with those inferred from the aerial measuring system. A previous survey was conducted on August 9 and 10, 1972, before the plant began operation. Exposure rates measured in both surveys were consistent with normal terrestrial background

CERN Radiation Protection (RP) calibration facilities

CERN Document Server

AUTHOR|(CDS)2082069; Macián-Juan, Rafael

Radiation protection calibration facilities are essential to ensure the correct operation of radiation protection instrumentation. Calibrations are performed in specific radiation fields according to the type of instrument to be calibrated: neutrons, photons, X-rays, beta and alpha particles. Some of the instruments are also tested in mixed radiation fields as often encountered close to high-energy particle accelerators. Moreover, calibration facilities are of great importance to evaluate the performance of prototype detectors; testing and measuring the response of a prototype detector to well-known and -characterized radiation fields contributes to improving and optimizing its design and capabilities. The CERN Radiation Protection group is in charge of performing the regular calibrations of all CERN radiation protection devices; these include operational and passive dosimeters, neutron and photon survey-meters, and fixed radiation detectors to monitor the ambient dose equivalent, H*(10), inside CERN accelera...

An aerial radiological survey of the Paducah Gaseous Diffusion Plant and surrounding area, Paducah, Kentucky

International Nuclear Information System (INIS)

1992-11-01

An aerial radiological survey of the Paducah Gaseous Diffusion Plant (PGDP) and surrounding area in Paducah, Kentucky, was conducted during May 15--25, 1990. The purpose of the survey was to measure and document the terrestrial radiological environment at the PGDP and surrounding area for use in effective environmental management and emergency response planning. The aerial survey was flown at an altitude of 61 meters (200 feet) along a series of parallel lines 107 meters (350 feet) apart. The survey encompassed an area of 62 square kilometers (24 square miles), bordered on the north by the Ohio River. The results of the aerial survey are reported as inferred exposure rates at 1 meter above ground level in the form of a gamma radiation contour map. Typical background exposure rates were found to vary from 5 to 12 microroentgens per hour (μR/h). Protactinium-234m, a radioisotope indicative of uranium-238, was detected at several facilities at the PGDR. In support of the aerial survey, ground-based exposure rate and soil sample measurements were obtained at several sites within the survey perimeter. The results of the aerial and ground-based measurements were found to agree within ±15%

Development of carborne gamma-ray survey system

International Nuclear Information System (INIS)

Sakamoto, Ryuichi; Tsutsumi, Masahiro

1999-01-01

A carborne γ-ray survey system was developed aiming at implementation of environmental radiation investigation in and around Chernobyl area after the accident. This system consists of a dose rate meter, a GPS and a personal computer, and acquires γ-ray dose rates and positional data using two serial ports of the computer. It is indispensable to acquire these two kinds of data simultaneously for carborne γ-ray survey in a large area. A feature of the system is to be able to get these data continuously by means of a simple programming. This system has been used in and around Chernobyl area for a few years, and it has worked without any troubles. The outline of this survey system, which is applicable for configuration of environmental radiation data acquisition system is reported with some results in Chernobyl. (author)

Measuring thyroid uptake with hand-held radiation monitors

International Nuclear Information System (INIS)

Deschamps, M.

1987-04-01

With the use of Iodine 123, 125 and 131 and some compounds of Technetium-99 m, a fraction of the isotopes can be trapped in the thyroid of the technicians. We used the hand-held radiation contamination or survey meters of the nine (9) Nuclear medicine departments we visited to see if they were adequate for the evaluation of thyroid uptake of the users. Measurements on a neck-phanton helped us to determine a minimum detectable activity for each isotope. We were then able to check if the measurements of investigations and action levels were possible. None of the hand-held radiation monitors are completely satisfactory for the measure of thyroid uptake of the user. We discuss a class of equipment capable of measuring radiation emissions at the investigation level. Measurement at the action level is possible with meters having scintillation or proportional probes but none of them permits the discrimination in energy required for a quantitative evaluation of the radioisotopes used

Literature survey: health effects of radiation

International Nuclear Information System (INIS)

Tveten, U.; Garder, K.

This report was originally written as a chapter of a report entitled 'Air pollution effects of electric power generation, a literature survey', written jointly by the Norwegian Institute for Air Research (NILU) and the Institutt for Atomenergi (IFA). (INIS RN242406). A survey is presented of the health effects of radiation. It has not, however, been the intention of the authors to make a complete list of all the literature relevant to this subject. The NILU/IFA report was meant as a first step towards a method of comparing the health effects of electric power generation by fission, gas and oil. Consequently information relevant to quantification of the health effects on humans has been selected. It is pointed out that quantitative information on the health effects of low radiation and dose rates, as are relevant to routine releases, does not exist for humans. The convention of linear extrapolation from higher doses and dose rates is used worldwide, but it is felt by most that the estimates are conservative. As an example of the use of the current best estimates, a calculation of normal release radiation doses is performed. (Auth.)

Natural radiation sources fabricated from potassic chemical fertilizers and application to radiation education

International Nuclear Information System (INIS)

Kawano, Takao

2010-01-01

Potassic chemical fertilizers contain potassium, a small part of which is potassium-40. Since potassium-40 is a naturally occurring radioisotope, potassic chemical fertilizers are often used for demonstrations of the existence of natural radioisotopes and radiation. To fabricate radiation sources as educational tools, the compression and formation method developed by our previous study was applied to 13 brands of commercially available chemical fertilizers containing different amounts of potassium. The suitability (size, weight, and solidness) of thus fabricated sources was examined and 12 of them were selected as easy-to-use radiation sources at radiation educational courses. The radiation strength (radiation count rate measured by a GM survey meter) and potassium content of the 12 sources were examined. It was found that the count rate was wholly proportional to the percentage of potassium, and a new educational application was proposed and discussed for understanding that the substance emitting radiation must be the potassium present in the raw fertilizers. (author)

A survey of research programs in radiation protection in Canada

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-07-01

A survey of research programs in Canada concerned with radiation protection was conducted in 1991-92 by the Joint Subcommittee on Regulatory Research (JSCRR) of the Atomic Energy Control Board (AECB) Advisory Committees on Radiological Protection and on Nuclear Safety. The purpose of this survey was to determine the current state of funding for this type of research in Canada. Funding for health-related radiation research in Canada is critical to establishing and maintaining a supply of trained professionals who can provide competent advice on health-related problems in radiation protection. The present report is an analysis of the information received in this survey. This survey concludes with the recommendation that the organization and definition of subprograms for the AECB Regulatory Research and Support Program should be completed as soon as possible. In this report the JSCRR should assist AECB staff in preparing a report in which priorities for research related to radiation protection are indicated. The sources of information noted at the end of the Discussion section of this report should be considered for this purpose. (author). 15 refs., 3 tabs.

A survey of research programs in radiation protection in Canada

International Nuclear Information System (INIS)

1995-07-01

A survey of research programs in Canada concerned with radiation protection was conducted in 1991-92 by the Joint Subcommittee on Regulatory Research (JSCRR) of the Atomic Energy Control Board (AECB) Advisory Committees on Radiological Protection and on Nuclear Safety. The purpose of this survey was to determine the current state of funding for this type of research in Canada. Funding for health-related radiation research in Canada is critical to establishing and maintaining a supply of trained professionals who can provide competent advice on health-related problems in radiation protection. The present report is an analysis of the information received in this survey. This survey concludes with the recommendation that the organization and definition of subprograms for the AECB Regulatory Research and Support Program should be completed as soon as possible. In this report the JSCRR should assist AECB staff in preparing a report in which priorities for research related to radiation protection are indicated. The sources of information noted at the end of the Discussion section of this report should be considered for this purpose. (author). 15 refs., 3 tabs

Evaluation of patient radiation doses using DAP meter in interventional radiology procedures

Energy Technology Data Exchange (ETDEWEB)

Kang, Byung Sam [Dept. of Radiological Technology. Shingu University, Sungnam (Korea, Republic of); Yoon, Yong Su [Dept. of Health Sciences, Graduate School of Medical Sciences, Kyushu Univeristy, Kyushu (Japan)

2017-03-15

The author investigated interventional radiology patient doses in several other countries, assessed accuracy of DAP meters embedded in intervention equipment in domestic country, conducted measurement of patient doses for 13 major interventional procedures with use of Dose Area Product(DAP) meters from 23 hospitals in Korea, and referred to 8,415 cases of domestic data related to interventional procedures by radiation exposure after evaluation the actual effective of dose reduction variables through phantom test. Finally, dose reference level for major interventional procedures was suggested. In this study, guidelines for patient doses were 237.7 Gy·cm{sup 2} in TACE, 17.3 Gy·cm{sup 2} in AVF, 114.1 Gy·cm{sup 2} in LE PTA and STENT, 188.5 Gy·cm{sup 2} in TFCA, 383.5 Gy·cm{sup 2} in Aneurysm Coil, 64.6 Gy·cm{sup 2} in PTBD, 64.6 Gy·cm{sup 2} in Biliary Stent, 22.4 Gy·cm{sup 2} in PCN, 4.3 Gy·cm{sup 2} in Hickman, 2.8 Gy·cm{sup 2} in Chemo-port, 4.4 Gy·cm{sup 2} in Perm-Cather, 17.1 Gy·cm{sup 2} in PCD, and 357.9 Gy·cm{sup 2} in Vis, EMB. Dose reference level acquired in this study is considered to be able to use as minimal guidelines for reducing patient dose in the interventional radiology procedures. For the changes and advances of materials and development of equipment and procedures in the interventional radiology procedures, further studies and monitoring are needed on dose reference level Korean DAP dose conversion factor for the domestic procedures.

Survey of international personnel radiation dosimetry programs

International Nuclear Information System (INIS)

Swaja, R.E.

1985-04-01

In September of 1983, a mail survey was conducted to determine the status of external personnel gamma and neutron radiation dosimetry programs at international agencies. A total of 130 agencies participated in this study including military, regulatory, university, hospital, laboratory, and utility facilities. Information concerning basic dosimeter types, calibration sources, calibration phantoms, corrections to dosimeter responses, evaluating agencies, dose equivalent reporting conventions, ranges of typical or expected dose equivalents, and degree of satisfaction with existing systems was obtained for the gamma and neutron personnel monitoring programs at responding agencies. Results of this survey indicate that to provide the best possible occupational radiation monitoring programs and to improve dosimetry accuracy in performance studies, facility dosimetrists, regulatory and standards agencies, and research laboratories must act within their areas of responsibility to become familiar with their radiation monitoring systems, establish common reporting guidelines and performance standards, and provide opportunities for dosimetry testing and evaluation. 14 references, 10 tables

Scientific substantiation of approaches to organization and conducting radiation surveys at the rehabilitated radiation sites

Directory of Open Access Journals (Sweden)

I. K. Romanovich

2017-01-01

Full Text Available The article is concerned with the scientific justification of approaches to the organization of the final radiation survey of facilities having radioactive contamination, after their rehabilitation. Scientific publications on the previous experience in rehabilitation of facilities contaminated with radionuclides, the organization and conducting a radiation survey before the start of the decontamination, during its implementation and after its completion were analyzed. The experience in the rehabilitation of the site for the temporary storage of spent fuel and radioactive waste in Andreeva Bay in the North-West region of Russia, the locations of peaceful nuclear explosions, experimental nuclear power plants, a radiochemical laboratory, and metallurgical plants, that do not belong to radiation facilities, has been studied. It has been established that, besides the surface contamination of the soil, areas of radioactive contamination on sites of decommissioned radiation facilities with significant depth up to 15 m along the profile are available. These local zones with depth soil contamination are persistent contaminants of the groundwater. The experience in the radiation survey of the peaceful nuclear explosions sites shows the removal of radionuclides from cavities, formed with the use of nuclear explosive technologies for peaceful purposes, on the earth’s surface. An optimized list of radionuclides to be monitored during the radiological survey of rehabilitated facilities was proposed based on the analysis of the composition of radionuclides detected at radiation sites subjected to decontamination. The optimized list includes 14 radionuclides with the half-lives of more than three years. 

Verification Survey of Uranium Mine Remediation

International Nuclear Information System (INIS)

Ron, Stager

2009-01-01

The Canadian Nuclear Safety Commission (CNSC) contracted an independent verification of an intensive gamma radiation survey conducted by a mining company to demonstrate that remediation of disturbed areas was complete. This site was the first of the recent mines being decommissioned in Canada and experience gained here may be applied to other mines being decommissioned in the future. The review included examination of the site-specific basis for clean-up criteria and ALARA as required by CNSC guidance. A paper review of the company report was conducted to determine if protocols were followed and that the summarized results could be independently reproduced. An independent verification survey was conducted on parts of the site and comparisons were made between gamma radiation measurements from the verification survey and the original company survey. Some aspects of data collection using rate meters linked to GPS data loggers are discussed as are aspects for data management and analyses methods required for the large amount of data collected during these surveys. Recommendations were made for implementation of future surveys and reporting the data from those surveys in order to ensure that remediation was complete. (authors)

IEEE Committee on Man and Radiation--COMAR technical information statement radiofrequency safety and utility Smart Meters.

Science.gov (United States)

Bushberg, Jerrold T; Foster, Kenneth R; Hatfield, James B; Thansandote, Arthur; Tell, Richard A

2015-03-01

This Technical Information Statement describes Smart Meter technology as used with modern electric power metering systems and focuses on the radio frequency (RF) emissions associated with their operation relative to human RF exposure limits. Smart Meters typically employ low power (-1 W or less) transmitters that wirelessly send electric energy usage data to the utility company several times per day in the form of brief, pulsed emissions in the unlicensed frequency bands of 902-928 MHz and 2.4-2.48 GHz or on other nearby frequencies. Most Smart Meters operate as wireless mesh networks where each Smart Meter can communicate with other neighboring meters to relay data to a data collection point in the region. This communication process includes RF emissions from Smart Meters representing energy usage as well as the relaying of data from other meters and emissions associated with maintaining the meter's hierarchy within the wireless network. As a consequence, most Smart Meters emit RF pulses throughout the day, more at certain times and less at others. However, the duty cycle associated with all of these emissions is very small, typically less than 1%, and most of the time far less than 1%, meaning that most Smart Meters actually transmit RF fields for only a few minutes per day at most. The low peak power of Smart Meters and the very low duty cycles lead to the fact that accessible RF fields near Smart Meters are far below both U.S. and international RF safety limits whether judged on the basis of instantaneous peak power densities or time-averaged exposures. This conclusion holds for Smart Meters alone or installed in large banks of meters.

Survey of Regulatory and Technological Developments Concerning Smart Metering in the European Union Electricity Market

OpenAIRE

VASCONCELOS, Jorge

2008-01-01

Smart metering is a crucial factor for the efficient functioning of the Internal Electricity Market, as well as for the successful implementation of European Union policies related to energy efficiency, renewable energy and security of supply. The report first outlines the potential benefits of smart meters for consumers, suppliers, metering companies, distribution network operators and public interest. Next the report provides a short overview of the legal framework governing metering activi...

Metering Plan: Intelligent Operational Strategies Through Enhanced Metering Systems

Energy Technology Data Exchange (ETDEWEB)

Pope, Jason E.

2016-07-27

The Sustainability Program at Pacific Northwest National Laboratory (PNNL) has adopted a “triple-bottom-line” approach of environmental stewardship, social responsibility, and economic prosperity to its operations. Metering at PNNL works in support of all three, specifically to measure and inform building energy use and greenhouse gas emissions and minimize water use. The foundation for metering at PNNL is a core goal set, which consists of four objectives: providing accurate data without interruption, analyzing data while it is still new, providing actionable recommendations to operations management, and ensuring PNNL’s compliance with contract metering requirements. These core objectives guide the decisions that we make during annual planning and as we operate throughout the year. This 2016 edition of the Metering Plan conveys the metering practices for and vision of the Sustainability Program. Changes in this plan from the 2015 edition include updated tables and an enhanced discussion on energy tracking systems used at PNNL. This plan also discusses updated benchmarking strategies using PNNL’s graphics and analytics tool, BuildingOS by Lucid Design Group. This plan presents our progress toward the metering goals shared by all federal agencies and highlights our successful completion of metering requirements. Currently, PNNL is fully compliant with the applicable legislative and Executive Order metering requirements. PNNL’s approach to the installation of new meters will be discussed. Perhaps most importantly, this plan details the analysis techniques utilized at PNNL that rely on the endless streams of data newly available as a result of increased meter deployment over the last several years. Previous Metering Plans have documented specific meter connection schemes as PNNL focused on deploying meters in a first step toward managing energy and water use. This plan serves not only to highlight PNNL’s successful completion of agency metering goals, but

Laser Meter of Atmospheric Inhomogeneity Properties in UV Spectral Range

Directory of Open Access Journals (Sweden)

S. E. Ivanov

2015-01-01

Full Text Available Development of laser systems designed to operate in conditions of the terrestrial atmosphere demands reliable information about the atmosphere condition. The aerosol lidars for operational monitoring of the atmosphere allow us to define remotely characteristics of atmospheric aerosol and cloudy formations in the atmosphere.Today the majority of aerosol lidars run in the visible range. However, in terms of safety (first of all to eyes also ultra-violet (UF range is of interest. A range of the wavelengths of the harmful effect on the eye retina is from 0.38 to 1.4 mμ. Laser radiation with the wavelengths less than 0.38 mμ and over 1.4 mμ influences the anterior ambient of an eye and is safer, than laser radiation with the wavelengths of 0.38 – 1.4 mμ.The paper describes a laser meter to measure characteristics of atmospheric inhomogeneity propertis in UF spectral range at the wavelength of 0.355 mμ.As a radiation source, the meter uses a semiconductor-pumped pulse solid-state Nd:YAG laser. As a receiving lens, Kassegren's scheme-implemented mirror lens with a socket to connect optical fibre is used in the laser meter. Radiation from the receiving lens is transported through the optical fibre to the optical block. The optical block provides spectral selection of useful signal and conversion of optical radiation into electric signal.To ensure a possibility for alignment of the optical axes of receiving lens and laser radiator the lens is set on the alignment platform that enables changing lens inclination and turn with respect to the laser.The software of the laser meter model is developed in the NI LabVIEW 2012 graphic programming environment.The paper gives the following examples: a typical laser echo signal, which is back scattered by the atmosphere and spatiotemporal distribution of variation coefficient of the volumetric factor of the back scattered atmosphere. Results of multi-day measurements show that an extent of the recorded aerosol

Implementation of the Brazilian radiation metrology network

International Nuclear Information System (INIS)

Ramos, Manoel M.O.; Araujo, Margareth M. de

1998-01-01

The ever increasing need for calibration of survey, personal, and contamination meters in Brazil are not completely satisfied by the two operating laboratories. To overcome this deficiency a radiation metrology network is being implemented with the support of IAEA. In a near future this network will count other three calibration laboratories which are being installed in different regions of the country, and accredited through INMETRO. (author)

An aerial radiological survey of the Nevada Test Site

International Nuclear Information System (INIS)

Hendricks, T.J.; Riedhauser, S.R.

1999-01-01

A team from the Remote Sensing Laboratory conducted an aerial radiological survey of the US Department of Energy's Nevada Test Site including three neighboring areas during August and September 1994. The survey team measured the terrestrial gamma radiation at the Nevada Test Site to determine the levels of natural and man-made radiation. This survey included the areas covered by previous surveys conducted from 1962 through 1993. The results of the aerial survey showed a terrestrial background exposure rate that varied from less than 6 microroentgens per hour (mR/h) to 50 mR/h plus a cosmic-ray contribution that varied from 4.5 mR/h at an elevation of 900 meters (3,000 feet) to 8.5 mR/h at 2,400 meters (8,000 feet). In addition to the principal gamma-emitting, naturally occurring isotopes (potassium-40, thallium-208, bismuth-214, and actinium-228), the man-made radioactive isotopes found in this survey were cobalt-60, cesium-137, europium-152, protactinium-234m an indicator of depleted uranium, and americium-241, which are due to human actions in the survey area. Individual, site-wide plots of gross terrestrial exposure rate, man-made exposure rate, and americium-241 activity (approximating the distribution of all transuranic material) are presented. In addition, expanded plots of individual areas exhibiting these man-made contaminations are given. A comparison is made between the data from this survey and previous aerial radiological surveys of the Nevada Test Site. Some previous ground-based measurements are discussed and related to the aerial data. In regions away from man-made activity, the exposure rates inferred from the gamma-ray measurements collected during this survey agreed very well with the exposure rates inferred from previous aerial surveys

Pediatric radiation therapy. A Japanese nationwide survey

International Nuclear Information System (INIS)

Nemoto, Kenji; Nagata, Yasushi; Hirokawa, Yutaka

2006-01-01

A national survey on the current status of pediatric radiation therapy was performed in October 2004. We sent questionnaires to 638 radiotherapy facilities in Japan (except for Kansai area) and 245 responses were analyzed. According to the database of committee of Japanese Society of Therapeutic Radiology and Oncology (JASTRO), the number of pediatric patients who received radiation therapy during 2003 in Japan was 1,101. The most frequent pediatric malignancy was brain tumor, followed by leukemia and lymphoma. The total effort of radiation therapy for children was two to six times larger than that for adult patients. An additional fee seems to be necessary for the highly technical and laborious radiation therapy required for children. (author)

Risk management of radiation therapy. Survey by north Japan radiation therapy oncology group

International Nuclear Information System (INIS)

Aoki, Masahiko; Abe, Yoshinao; Yamada, Shogo; Hareyama, Masato; Nakamura, Ryuji; Sugita, Tadashi; Miyano, Takashi

2004-01-01

A North Japan Radiation Oncology Group (NJRTOG) survey was carried out to disclose the risk management of radiation therapy. During April 2002, we sent questionnaires to radiation therapy facilities in northern Japan. There were 31 replies from 27 facilities. Many incidents and accidents were reported, including old cases. Although 60% of facilities had a risk management manual and/or risk manager, only 20% had risk management manuals for radiation therapy. Eighty five percent of radiation oncologists thought that incidents may be due to a lack of manpower. Ninety percent of radiation oncologists want to know the type of cases happened in other facilities. The risk management system is still insufficient for radiation therapy. We hope that our data will be a great help to develop risk management strategies for radiation therapy for all radiation oncologists in Japan. (author)

Temperature differences within the detector of the Robertson-Berger sunburn meter, model 500, compared to global radiation

Science.gov (United States)

Kjeldstad, Berit; Grandum, Oddbjorn

1993-11-01

The Robertson-Berger sunburn meter, model 500, has no temperature compensation, and the effect of temperature on the instrument response has been investigated and discussed in several reports. It is recommended to control the temperature of the detector or at least measure it. The temperature sensor is recommended to be positioned within the detector unit. We have measured the temperature at three different positions in the detector: At the edge of the green filter where the phosphor layer is placed; at the glass tube covering the cathode; and, finally, the air temperature inside the instrument. These measurements have been performed outdoors since July 1991, with corresponding measurements of the global and direct solar radiation. There was no difference between the temperature of the glasstube covering the cathode and the air inside the instrument, at any radiation level. However, there was a difference between the green filter and the two others. The difference is linearly dependent on the amount of global radiation. The temperature difference, (Delta) T (temperature between the green filter and the air inside the sensor), increased 0.8 degree(s)C when the global irradiation increased by 100 W/m2. At maximum global radiation in Trondheim (latitude 63.4 degree(s)N) (Delta) T was approximately 5 - 6 K when the global radiation was about 700 W/m2. This was valid for temperatures between 7 degree(s)C and 30 degree(s)C. Only clear days were evaluated.

Public reaction to the natural radiation survey

Energy Technology Data Exchange (ETDEWEB)

Brown, L [National Radiological Protection Board, Harwell (UK)

1983-11-01

A natural radiation survey of a cross-section of homes in the UK has been under way for over a year. Members of the public are contacted by post by the NRPB and asked whether they would be willing to have dosemeters in their homes for 12 months. To date the survey has elicited approximately 50% positive response for over a year which is encouragingly high compared to response rates of postal surveys in general. The survey has attracted notable media attention; in the main the tenor of the stories has been accurate and informative and only a handful could be described as sensational.

Natural Sources of Radiation Exposure and the Teaching of Radioecology

Science.gov (United States)

Anjos, R. M.; Veiga, R.; Carvalho, C.; Sanches, N.; Estellita, L.; Zanuto, P.; Queiroz, E.; Macario, K.

2008-01-01

We have developed an experimental activity that introduces concepts of the natural ionizing radiation and its interaction with our contemporary environment that can be used with students from secondary to college level. The experiment is based on the use of traditional and cheap portable Geiger-Muller detectors as survey meters for "in situ"…

Natural sources of radiation exposure and the teaching of radioecology

International Nuclear Information System (INIS)

Anjos, R M; Veiga, R; Carvalho, C; Sanches, N; Estellita, L; Macario, K; Zanuto, P; Queiroz, E

2008-01-01

We have developed an experimental activity that introduces concepts of the natural ionizing radiation and its interaction with our contemporary environment that can be used with students from secondary to college level. The experiment is based on the use of traditional and cheap portable Geiger–Müller detectors as survey meters for in situ measurements

EMERGENCY RADIATION SURVEY DEVICE ONBOARD THE UAV

Directory of Open Access Journals (Sweden)

S. Bogatov

2013-08-01

Full Text Available Radiation survey device (RSD on the base of unmanned aerial vehicle (UAV was developed as an equipment of rescue forces for radiation situation reconnaissance in case of emergency. RSD is multi range radiometer with spectrometer functions capable to work within gamma ray fields of dose rate 10–7 – 10–1 Sievert per hour. UAV md4-1000 (Microdrones GmbH, Germany was selected as the RSD carrier as a reliable vehicle with appropriate properties. Short description of RSD, UAV and developed software features as well as sensitivity assessments for different radiation sources are presented.

Palliative care and palliative radiation therapy education in radiation oncology: A survey of US radiation oncology program directors.

Science.gov (United States)

Wei, Randy L; Colbert, Lauren E; Jones, Joshua; Racsa, Margarita; Kane, Gabrielle; Lutz, Steve; Vapiwala, Neha; Dharmarajan, Kavita V

The purpose of this study was to assess the state of palliative and supportive care (PSC) and palliative radiation therapy (RT) educational curricula in radiation oncology residency programs in the United States. We surveyed 87 program directors of radiation oncology residency programs in the United States between September 2015 and November 2015. An electronic survey on PSC and palliative RT education during residency was sent to all program directors. The survey consisted of questions on (1) perceived relevance of PSC and palliative RT to radiation oncology training, (2) formal didactic sessions on domains of PSC and palliative RT, (3) effective teaching formats for PSC and palliative RT education, and (4) perceived barriers for integrating PSC and palliative RT into the residency curriculum. A total of 57 responses (63%) was received. Most program directors agreed or strongly agreed that PSC (93%) and palliative radiation therapy (99%) are important competencies for radiation oncology residents and fellows; however, only 67% of residency programs had formal educational activities in principles and practice of PSC. Most programs had 1 or more hours of formal didactics on management of pain (67%), management of neuropathic pain (65%), and management of nausea and vomiting (63%); however, only 35%, 33%, and 30% had dedicated lectures on initial management of fatigue, assessing role of spirituality, and discussing advance care directives, respectively. Last, 85% of programs reported having a formal curriculum on palliative RT. Programs were most likely to have education on palliative radiation to brain, bone, and spine, but less likely on visceral, or skin, metastasis. Residency program directors believe that PSC and palliative RT are important competencies for their trainees and support increasing education in these 2 educational domains. Many residency programs have structured curricula on PSC and palliative radiation education, but room for improvement exists in

Safety practices, perceptions, and behaviors in radiation oncology: A national survey of radiation therapists.

Science.gov (United States)

Woodhouse, Kristina Demas; Hashemi, David; Betcher, Kathryn; Doucette, Abigail; Weaver, Allison; Monzon, Brian; Rosenthal, Seth A; Vapiwala, Neha

Radiation therapy is complex and demands high vigilance and precise coordination. Radiation therapists (RTTs) directly deliver radiation and are often the first to discover an error. Yet, few studies have examined the practices of RTTs regarding patient safety. We conducted a national survey to explore the perspectives of RTTs related to quality and safety. In 2016, an electronic survey was sent to a random sample of 1500 RTTs in the United States. The survey assessed department safety, error reporting, safety knowledge, and culture. Questions were multiple choice or recorded on a Likert scale. Results were summarized using descriptive statistics and analyzed using multivariate logistic regression. A total of 702 RTTs from 49 states (47% response rate) completed the survey. Respondents represented a broad distribution across practice settings. Most RTTs rated department patient safety as excellent (61%) or very good (32%), especially if they had an incident learning system (ILS) (odds ratio, 2.0). Only 21% reported using an ILS despite 58% reporting an accessible ILS in their department. RTTs felt errors were most likely to occur with longer shifts and poor multidisciplinary communication; 40% reported that burnout and anxiety negatively affected their ability to deliver care. Workplace bullying was also reported among 17%. Overall, there was interest (62%) in improving knowledge in patient safety. Although most RTTs reported excellent safety cultures within their facilities, overall, there was limited access to and utilization of ILSs by RTTs. Workplace issues identified may also represent barriers to delivering quality care. RTTs were also interested in additional resources regarding quality and safety. These results will further enhance safety initiatives and inform future innovative educational efforts in radiation oncology. Copyright © 2017 American Society for Radiation Oncology. Published by Elsevier Inc. All rights reserved.

In-situ calibration of clinical built-in KAP meters with traceability to a primary standard using a reference KAP meter.

Science.gov (United States)

Malusek, A; Helmrot, E; Sandborg, M; Grindborg, J-E; Carlsson, G Alm

2014-12-07

The air kerma-area product (KAP) is used for settings of diagnostic reference levels. The International Atomic Energy Agency (IAEA) recommends that doses in diagnostic radiology (including the KAP values) be estimated with an accuracy of at least ± 7% (k = 2). Industry standards defined by the International Electrotechnical Commission (IEC) specify that the uncertainty of KAP meter measurements should be less than ± 25% (k = 2). Medical physicists willing to comply with the IAEA's recommendation need to apply correction factors to KAP values reported by x-ray units. The aim of this work is to present and evaluate a calibration method for built-in KAP meters on clinical x-ray units. The method is based on (i) a tandem calibration method, which uses a reference KAP meter calibrated to measure the incident radiation, (ii) measurements using an energy-independent ionization chamber to correct for the energy dependence of the reference KAP meter, and (iii) Monte Carlo simulations of the beam quality correction factors that correct for differences between beam qualities at a standard laboratory and the clinic. The method was applied to the KAP meter in a Siemens Aristos FX plus unit. It was found that values reported by the built-in KAP meter differed from the more accurate values measured by the reference KAP meter by more than 25% for high tube voltages (more than 140 kV) and heavily filtered beams (0.3 mm Cu). Associated uncertainties were too high to claim that the IEC's limit of 25% was exceeded. Nevertheless the differences were high enough to justify the need for a more accurate calibration of built-in KAP meters.

The investigation in radiation protection of γ-rays material position meter in Guizhou Province

International Nuclear Information System (INIS)

Wei Fuxing

1997-01-01

The paper investigates the protective property of 38 γ-rays material position meters used in machine vertical kilns by 36 cement factories in Guizhou. Model FLW-II material position meter use the least radioactive source activity and the air absorption dose rate about one meter is equal to the natural background. For model FWJ-77A, the air absorption dose rate around one meter was 1.1-5.3 μGY/h and the average value is 2.1 +- 0.7 μGY/h; for Model LF-I, they are respectively 0.42-6.4 μGY/h and 2.4 +- 0.6 μGY/h. These value are lower than or near to the dose limit value which state stipulated. The biggest dose equivalent that maintenance workers accepted per year is only equal to 1/2∼1/3 of the dose limit value which state stipulated. Some management suggestions for the production, sellment and use of γ-rays material position meter were presented

Aerial radiological survey of the Brookhaven National Laboratory and surrounding area, Upton, New York. Date of survey: June 1983

International Nuclear Information System (INIS)

Hobaugh, J.L.

1985-02-01

An aerial radiological survey was performed from 11 to 13 June 1983, over approximately a 64-square-kilometer (25-square-mile) area surrounding the Brookhaven National Laboratory (BNL). BNL is located in the center of Suffolk County, Long Island, New York. All gamma radiation data were collected by flying east-west lines spaced 76 meters (250 feet) apart at an altitude of 46 meters (150 feet) above ground level. Count rates obtained from the aerial platform were converted to exposure rates at 1 meter above the ground. The average background exposure rate in the survey area ranged from 5 to 10 microroentgens per hour (μR/h). The reported exposure rate values include an estimated cosmic ray contribution of 4.0 μR/h. Ground-based measurements made during the same time period were compared to the aerial survey results. Pressurized ion chamber readings and soil samples were taken from two locations within the aerial survey boundaries. Exposure rate values obtained from these measurement techniques were in agreement with those obtained from the aerial data. A total of 23 areas of man-made radioactivity were identified. The dominant isotopes found over these areas were cesium-137, sodium-22, manganese-54, and cobalt-60. A similar survey was conducted in May 1980. The 1983 survey results were similar to the 1980 results. Three areas of low level man-made activity were not reproduced by the 1983 data. Ten new areas were detected. The major difference occurred because of the increased sensitivity and spatial reduction brought on by lowering the altitude and decreasing the line spacing. 8 refs., 28 figs., 4 tabs

Development of new portable radiation counters for promotion of better understanding of radiation by the public

International Nuclear Information System (INIS)

Tanabe, Hiroshi

1995-01-01

This study aims to promote the correct understanding of radiation to the public. All the questions asked by participants at forums held in Aomori, where commercial nuclear fuel cycle facilities are planned, were studied. More than half of these questions were concerned about radiation hazards. Measurements, using radiation counters at the meeting, provided the most effective means of explanation about radiation hazards to the public. For this purpose, portable β- and α-ray counters, being able to detect small amounts of radioactive substances around us, were developed. Each new counter is easily handled, is light-weight (about 10-20% that of domestic survey meters) and inexpensive (about 20-25% the price). The methods used to explain radiation with both counters have been also studied. This explanation has provided the public with a better understanding of the nature and hazards of radiation on human health than the former methods using textbooks. (author)

Health survey of radiation workers. Results of questionnaire

International Nuclear Information System (INIS)

Morikawa, Kaoru; Aoyama, Takashi; Kawagoe, Yasumitsu; Sunayashiki, Tadashi; Tanaka, Kiyoshi; Nishitani, Motohiro; Yoshinaga, Nobuharu

1998-01-01

The Japanese Society of Radiological Technology asked radiation workers about the radiation doses and the state of their health as well as family. The reports by the Health and Welfare Ministry were referenced to compare radiation workers with others. The questionnaire was sent to about 4,000 members, and returned from 2,479. The survey showed that 684 persons (27.6%) felt health anxiety, 455 persons (18.4%) had medical check for recent one year, and 1,645 persons (66.4%) had anamnesis. Radiation doses for one year and cumulated doses varied according to engaging duration. (K.H.)

Nuclear Enterprises portable dose rate meter type PDR 2

International Nuclear Information System (INIS)

Burgess, P.H.; Iles, W.J.

1978-06-01

This instrument is a portable battery powered dose rate meter covering the dose rate range from 0.05 to 500 mrad h -1 . It is designed to measure X- and γ-radiation dose rates over the energy range from 35 keV to 3 MeV. The radiation detector is an MX 164/S GM tube provided with a compensation sheath. The report describes the instrument under the headings: facilities and controls; radiation characteristics; electrical characteristics; environmental characteristics; mechanical characteristics; the manual; summary of performance. (U.K.)

Survey of radiation protection programmes for transport

International Nuclear Information System (INIS)

Lizot, M.T.; Perrin, M.L.; Sert, G.; Lange, F.; Schwarz, G.; Feet, H.J.; Christ, R.; Shaw, K.B.; Hughes, J.S.; Gelder, R.

2001-07-01

The survey of radiation protection programmes for transport has been jointly performed by three scientific organisations I.P.S.N. (France), G.R.S. ( Germany), and N.R.P.B. (United kingdom) on behalf of the European Commission and the pertaining documentation summarises the findings and conclusions of the work that was undertaken with the principal objectives to provide guidance on the establishment, implementation and application of radiation protection programmes for the transport of radioactive materials by operators and the assessment and evaluation of such programmes by the competent authority and to review currently existing radiation protection programmes for the transport of radioactive materials. (N.C.)

[A Survey about the Radiation Effects and A Health Survey of Fukushima Inhabitants after the Fukushima Daiichi Nuclear Power Plant Accident].

Science.gov (United States)

Okazaki, Ryuji; Ohga, Kazuhiro; Yoko-O, Makoto; Kohzaki, Masaoki

According to questionnaire surveys in 2011 and 2013 about the health effects of radiation after the Fukushima Daiichi Nuclear Power Plant Accident, the guardians of child patients were more anxious than doctors and medical students. Also, according to the thyroid examinations in a Fukushima health survey, 190 cases of thyroid cancer were reported, and anxiety about radiation effects remained. This study is based on a survey about the guardians of child patients anxiety about radiation effects six years after the nuclear power plant accident, and includes a questionnaire survey about radiation effects and thyroid examinations in a Fukushima health survey. Anonymous question sheets with 20 questions were sent to pediatric medical facilities in Fukushima, and the parents of children who consulted the pediatric and medical staff answered the questionnaire. Thirty percent of the guardians of child patients had never been educated about radiation and 67% had never been educated about the effects of radiation on humans. The guardians of child patients were more anxious than the medical staff about thyroid cancer, health effects on children and genetic effects. Our results indicate that the guardians of child patients think that the increase in the incidence of thyroid cancer is due to radiation effects after the nuclear power plant accident and they desire continued thyroid examinations.

Calibration procedures of area monitors in terms of the Ambient Dose Equivalent H*(10), for gamma, x-ray radiation fields

International Nuclear Information System (INIS)

Dieguez Davila, L.E.

1998-01-01

In the present thesis procedures for calibrating portable survey meters in terms of the new ICRU quantities H*(10) ambient dose equivalent are discussed. Also the remendations of International Comission on Radiation Protection in their report ICRP 60 that inludes the operational magnitudes that the International Comission of Radiation Units proposed for calibrating area monitors

GSM module for wireless radiation monitoring system via SMS

Science.gov (United States)

Rahman, Nur Aira Abd; Hisyam Ibrahim, Noor; Lombigit, Lojius; Azman, Azraf; Jaafar, Zainudin; Arymaswati Abdullah, Nor; Hadzir Patai Mohamad, Glam

2018-01-01

A customised Global System for Mobile communication (GSM) module is designed for wireless radiation monitoring through Short Messaging Service (SMS). This module is able to receive serial data from radiation monitoring devices such as survey meter or area monitor and transmit the data as text SMS to a host server. It provides two-way communication for data transmission, status query, and configuration setup. The module hardware consists of GSM module, voltage level shifter, SIM circuit and Atmega328P microcontroller. Microcontroller provides control for sending, receiving and AT command processing to GSM module. The firmware is responsible to handle task related to communication between device and host server. It process all incoming SMS, extract, and store new configuration from Host, transmits alert/notification SMS when the radiation data reach/exceed threshold value, and transmits SMS data at every fixed interval according to configuration. Integration of this module with radiation survey/monitoring device will create mobile and wireless radiation monitoring system with prompt emergency alert at high-level radiation.

Benign disease in radiation therapy: a survey in Belgium

International Nuclear Information System (INIS)

Beauduin, M.; Deneufbourg, J.M.; Deneve, W.; Hermans, J.; Hoornaert, M.T.; Scalliet, P.; Spaas, P.; Vanderick, J.; Dijcke, V.; Van Houtte, P.; Vynckier, S.; Weltens, C.

2001-01-01

In 1996 and 2000, a survey of radiation practice in Belgium was performed by sending a questionnaire to the different centers asking their opinion and number of patients treated. There was a great similarity between the two surveys both for indications and total number of patients irradiated. For the most common indications (prevention of cheloids, heterotopic bone formation, hyperthyroid ophthalmopathy), there was a trend to use similar radiation technique following recent publications. In contrast, if the number of cases of macular degeneration is declining, the prevention of vessels restenosis is becoming more and more an indication. (authors)

Underwater sediment-contact radiation survey method

International Nuclear Information System (INIS)

Lee, D.R.; St. Aubin, M.; Welch, S.J.

1991-01-01

The authors are striving to produce a practical system for mapping lateral distributions in gamma activity on submerged sediments. This is in response to the need for quality control and interpretation of data obtainable by sediment sampling and analyses near nuclear utilities. A prototype gamma probe has been constructed and tested. The prototype is essentially a background survey meter packaged in a 53-cm-long x 5.4-cm-diam waterproof vehicle. This usage-shaped vehicle is connected to a cable for towing in contact with bottom sediments of lakes, rivers, and coastal waters. This vehicle, or sediment probe as it is called, was initially developed for measuring sediment electrical conductances, a parameter that can be used to locate underwater areas of groundwater and contaminant upwelling. During towing, the probe does not roll or twist around its longitudinal axis by more than 10 deg, so that sensors, which have been fixed within the vehicle, can be oriented to look up, down, or sideways. In over 450 lin-km of underwater survey, only a single sediment probe has been irretrievably snagged on sunken rocks or other debris. Work in the Ottawa River near the Chalk River Laboratories has shown good agreement among point measurements of river sediment with continuous measurements using the moving probe

Evaluation of integrity of radiation sources of nuclear gauges

International Nuclear Information System (INIS)

Torohate, Wiclif Francisco

2016-01-01

Nuclear equipment meters are mainly used in the industry in quality control and process control. The principle of operation consists in a shielded radioactive source together with a radiation detector such that the radiation interacts with the material to be analyzed before reaching the detector, providing real time data. Can be as their fixed and mobile mobility, the unique properties of ionizing radiation are used in three basic modes, transmission, backscatter or dispersion or induced (reactive). With the advancement and technological modernization in the world, the demand for nuclear gauges becomes increasingly larger. Currently in Brazil there are about 465 process control plants and 21 portable systems and Mozambique about 45 facilities using nuclear gauges. This font registration is done through a process called source inventory that allows also to know the category of the source, the danger or risk to human health that the source offers. The handling of this equipment requires personnel, certified, skilled and well trained in radiation protection area in accordance with the requirements of the various CNEN Rules. Due to the presence of radioactive source and because these devices are used by workers risk because there external radiation. In this context, we made the smear test in two fixed meters from the IRD industry laboratory, which determines the integrity of the source package, mandatory item in periodic integrity testing of the radiation source of this type of device. A set of procedures is made for its implementation as an evaluation of the radiological risk by radiological survey. It was intended to contribute to the learning handling and safe use of these meters. (author)

Smart metering - energy data management at every meter point; Smart Metering - Energiedatenmanagement an jedem Zaehlpunkt

Energy Technology Data Exchange (ETDEWEB)

Keller-Giessbach, D.; Kiel, E. [LogicaCMG, Muenchen (Germany)

2007-09-15

The demise of monopolistic structures in the German energy market has also led to a change of perspective on metering. New requirements have to be met. Even in mass processing jobs such as meter reading it is no longer sufficient to simply read consumption data off a technically reliable meter or have customers do this themselves in preparation of billing. Currently used meters were not designed with a mind to demand management, environmental protection through energy conservation, changes in consumer behaviour or new service offers. This has been recognised in many European countries since the beginning of the present decade. The traditional task of metering is developing into a more comprehensive energy data management that takes account of the needs of customers, energy suppliers and regulatory requirements.

Jean Lafitte 2013, 1.0 Meter LiDAR, Classified point cloud

Data.gov (United States)

National Oceanic and Atmospheric Administration, Department of Commerce — The Light Detection and Ranging (LiDAR) dataset is a survey of the Jean Lafitte,G13PD00214, 1.0 Meter LiDAR Survey Area in south of New Orleans and encompasses 77...

The development of wireless radiation dose monitoring using smart phone

Energy Technology Data Exchange (ETDEWEB)

Lee, Jin Woo; Jeong, Gyo Seong; Lee, Yun Jong [Advanced Radiation Technology Institute, Korea Atomic Energy Research Institute, Jeongeup (Korea, Republic of); Kim, Chong Yeal [Chonbuk National University, Jeonju (Korea, Republic of); Lim, Chai Wan [REMTECH, Seoul (Korea, Republic of)

2016-11-15

Radiation workers at a nuclear facility or radiation working area should hold personal dosimeters. some types of dosimeters have functions to generate audible or visible alarms to radiation workers. However, such devices used in radiation fields these days have no functions to communicate with other equipment or the responsible personnel. our project aims at the development of a remote wireless radiation dose monitoring system that can be utilized to monitor the radiation dose for radiation workers and to notify the radiation protection manager of the dose information in real time. We use a commercial survey meter for personal radiation measurement and a smart phone for a mobile wireless communication tool and a Beacon for position detection of radiation workers using Blue tooth communication. In this report, the developed wireless dose monitoring of cellular phone is introduced.

Determining total sulfur content in coal by MSC radiometric sulfur meter

Energy Technology Data Exchange (ETDEWEB)

Czerw, B; Sikora, T; Golebiowski, W

1976-01-01

The MSC radiometric sulfur meter is used to determine total sulfur content in brown and black coals. Sulfur content is determined by measuring intensity of radiation beam which has travelled through a coal sample with the optimum constant surface mass. Construction of the MSC, consisting of a measuring head and the electronic measuring system, is shown in a scheme. AM-241 (with activity of 50 mCi) is the source of radiation. Energy of 25.3 keV (tin disc) is selected as the optimum. The SSU-70 probe with NaJ/Tl crystal is the radiation detector. The black coal sample weighs 10 g and the brown coal sample weighs 18 g. Duration of sulfur determination is 10 min. Error of sulfur determination ranges from plus or minus 0.2% to 0.3%. The results of operational tests of MSC radiometric sulfur meters in black and brown coal mines are discussed. Accuracy of measurement is shown in 5 tables. (8 refs.)

Survey of sexual educational needs in radiation oncology patients

International Nuclear Information System (INIS)

Chen, L.; Sweeney, P.; Wallace, G.; Neish, P.; Vijayakumar, S.

1997-01-01

Purpose: To assess the knowledge of and need for education about sexuality in oncology patients treated with radiation therapy. Methods and Materials: Patients who received radiation therapy for any disease site were given a self-assessment survey to complete to determine their opinions on sexuality and needs for sexual education. The surveys were given to patients on follow-up visit seen approximately 6 months to 2 years after radiation therapy. All patients were diagnosed with a malignancy and asked to participate on a voluntary basis; confidentiality was ensured by excluding any identifying patient information on the survey form. Respondents were polled with a survey that consisted of 17 questions about their sexual activity. Questions were broadly categorized into the following: definition of sexual activity, frequency of sexual activity prior to and after diagnosis and treatment of cancer, perception of sexual attractiveness, sexual satisfaction in the relationship, patient perception of partner's sexual satisfaction in the relationship, educational needs with regard to sexuality after therapy for cancer, and demographic information. Results: All patients were over age 18, and received radiation therapy as part of the treatment. Patients with all disease sites were included in the survey, regardless of stage or diagnosis. A total of 28 patients completed the survey form, which was approved by our institutional review board. Forty-three percent of patients felt that the cancer diagnosis or treatment effect was the cause of not engaging in sexual intercourse. Fifty percent reported not having the same sexual desire as before the diagnosis of cancer, while 46% reported having the same sexual desire as prior to the diagnosis of cancer. Forty-six percent felt less attractive than before the diagnosis of cancer, while 43% felt the same as before diagnosis. Thirty-six percent of patients received no information with regards to sexuality and cancer, while 18% received

Aerial radiological survey of the Weldon Spring Chemical Plant (St. Charles, Missouri)

International Nuclear Information System (INIS)

Jobst, J.E.

1975-01-01

Of the 27 lines flown over the Weldon Spring Chemical Plant drainage basins, five lines directly over the Plant site show uranium and thorium contamination probably due to Plant operations. Because the survey was done at an altitude of 152m, with a 300-meter line spacing, identification of individual radiation sources on the site is not possible from present data. One additional survey line over a quarry south of the Plant shows uranium contamination due to Plant wastes deposited there

Resolution no. 15/2012 Safety Guide for the practice of nuclear meters

International Nuclear Information System (INIS)

2012-01-01

1. This guide is Intended to complement the requirements for practice Nuclear meters out in September: • Joint Resolution CITMA-MINSAP Regulation Basic Standards Radiation safety of November 30, 2001, hereinafter NBS. • CITMA Resolution 121/2000, Regulations for the Safe Transport Radioactive Materials; hereinafter transport regulations. • Resolution 35/2003 of CITMA Regulation for the safe management of Radioactive waste of March 7, 2003, hereinafter Regulation waste. • Joint Resolution CITMA-MINSAP Regulations for the Selection, Training Authorization and Associated Personnel performing Employment Practices of Ionizing Radiation of December 19, 2003, hereinafter Staff Rules. 2. The requirements of this guide are applicable to entities and performing practice-related activities Nuclear Meters throughout the national territory.

Survey of Tsuruga inhabitants concerning radiation and its risks

International Nuclear Information System (INIS)

Shinoda, Yoshihiko; Yamano, Naoki

2015-01-01

The Fukushima Daiichi nuclear accident has led to changes in the acceptance of nuclear power in many people. The authors conducted an opinion survey of 300 adult inhabitants of Tsuruga city in Fukui prefecture, Japan. The aim of this survey is to obtain people's opinions concerning radiation and its risks. Authors classified Tsuruga inhabitants on the basis of responses to questions on the concept and knowledge of risk and the cognition of radiation by factor and cluster analyses of multivariable analysis. Using the results of these analyses, Tsuruga inhabitants have been assigned to five categories: “acceptance group,” “anxiety group,” and three intermediate groups. (author)

An aerial radiological survey of the Babcock and Wilcox Nuclear Facilities and surrounding area, Lynchburg, Virginia

International Nuclear Information System (INIS)

Guss, P.P.

1993-04-01

An aerial radiological survey was conducted from July 18 through July 25, 1988, over a 41-square-kilometer (16-square-mile) area surrounding the Babcock and Wilcox nuclear facilities located near Lynchburg, Virginia. The survey was conducted at a nominal altitude of 61 meters (200 feet) with line spacings of 91 meters (300 feet). A contour map of the terrestrial gamma exposure rate extrapolated to 1 meter above ground level (AGL) was prepared and overlaid on an aerial photograph. The terrestrial exposure rates varied from 8 to 12 microroentgens per hour (μR/h). A search of the data for man-made radiation sources revealed the presence of three areas of high count rates in the survey area. Spectra accumulated over the main plant showed the presence of cobalt-60 ( 60 Co) and cesium-137 ( 137 Cs). A second area near the main plant indicated the presence of uranium-235 ( 235 U). Protactinium-234m ( 234m Pa) and 60 Co Were detected over a building to the east of the main plant. Soil samples and pressurized ion chamber measurements were obtained at four locations within the survey boundaries in support of the aerial data

Preparing for smart grid technologies: A behavioral decision research approach to understanding consumer expectations about smart meters

International Nuclear Information System (INIS)

Krishnamurti, Tamar; Schwartz, Daniel; Davis, Alexander; Fischhoff, Baruch; Bruine de Bruin, Wändi; Lave, Lester; Wang, Jack

2012-01-01

With the enactment of the 2009 American Recovery and Reinvestment Act, U.S. President Obama made a public commitment to a new approach to energy production and transmission in the United States. It features installing smart meters and related technologies in residential homes, as part of transforming the current electrical grid into a “smart grid.” Realizing this transformation requires consumers to accept these new technologies and take advantage of the opportunities that they create. We use methods from behavioral decision research to understand consumer beliefs about smart meters, including in-depth mental models interviews and a follow-up survey with a sample of potential smart meter customers of a major U.S. mid-Atlantic electricity utility. In both the surveys and the interviews, most respondents reported wanting smart meters. However, these preferences were often based on erroneous beliefs regarding their purpose and function. Respondents confused smart meters with in-home displays and other enabling technologies, while expecting to realize immediate savings. They also perceived risks, including less control over their electricity usage, violations of their privacy, and increased costs. We discuss the policy implications of our results. - Highlights: ► We outline normative risks and benefits of smart meters from scientific literature. ► We examine consumer perceptions of smart meters via interviews and surveys. ► Smart meter desire stems from consumer misconceptions about purpose and function. ► Appropriate communications may prevent consumer protests against the smart grid.

Development of a hotspot detector with an acrylic filter and dose rate survey meters

International Nuclear Information System (INIS)

Shirakawa, Yoshiyuki; Yamano, Toshiya; Kobayashi, Yusuke; Hara, Masaki

2013-01-01

Fukushima and adjacent regions still have a large number of high dose rate areas called hotspots. It is necessary to know these hotspots for efficient decontamination of radioactive substances such as 137 Cs and for relief of residents coming home. To find the hotspots rapidly, we have to specify the direction of the area where the dose rate is at least 1μSv/h higher than those of surroundings. We have developed a detector that consists of an acrylic filter and three NaI(Tl) scintillation survey meters, and the detector can be expected to indicate the direction of the hotspot in the short time. A basic performance of the detector was examined by using acrylic filters of 10, 15, 20 and 25cm diameter and a tiny sealed 137 Cs source of 3 MBq as the alternative of a hotspot. It demonstrated the possibility of identifying the direction of γ-rays emitted from the source in 90 seconds. (author)

Smart Metering. Technological, economic and legal aspects. 2. ed.; Smart Metering. Technologische, wirtschaftliche und juristische Aspekte des Smart Metering

Energy Technology Data Exchange (ETDEWEB)

Koehler-Schute, Christiana (ed.)

2010-07-01

Smart metering comprises more than just meter technology, and the use of information and communication technologies is indispensable. Processes, roles and business models must be reconsidered as further challenges arise in the context of smart metering. For one, there is the operator of the metering points. Secondly, there is the end user who is in the role of an active market partner. Further, there is smart metering as a basic technology, e.g. for smart grids and smart homes. In spite of the need for action, many utilities are reluctant to introduce smart metering. Reasons for this are the cost, a lack of defined standards, and an unclear legal situation. On the other hand, smart metering offers potential for grids and distribution that should be made use of. The authors discuss all aspects of the subject. The point out the chances and limitations of smart metering and present their own experience. [German] Smart Metering geht weit ueber die Zaehlertechnologie hinaus und der Einsatz von Informations- und Kommunikationstechnologien ist unabdingbar. Damit einhergehend muessen Prozesse, Rollen und auch Geschaeftsmodelle neu durchdacht werden. Denn weitere Herausforderungen stehen im direkten Zusammenhang mit Smart Metering. Das ist zum einen die Rolle des Messstellenbetreibers / Messdienstleisters. Das ist zum anderen der Endnutzer, dem die Rolle des aktiven Marktpartners zugedacht wird. Das ist des Weiteren das Smart Metering als Basistechnologie beispielsweise fuer Smart Grid und Smart Home. Trotz des Handlungsdrucks stehen viele Unternehmen der Energiewirtschaft dem Smart Metering zurueckhaltend gegenueber. Drei gewichtige Gruende werden ins Feld gefuehrt: die Kostenfrage, nicht definierte Standards und die in vielen Bereichen ungeklaerte Gesetzeslage. Demgegenueber bietet das Smart Metering Potenziale fuer Netz und Vertrieb, die es zu nutzen gilt. Die Autoren setzen sich in ihren Beitraegen mit diesen Themen auseinander, zeigen Chancen, aber auch Grenzen des

Instrument evaluation no. 9. Mini-instruments dose rate meter type 5 - 1OR

International Nuclear Information System (INIS)

Iles, W.J.; Burgess, P.H.; Callowhill, K.

1977-04-01

This instrument is a portable, battery powered dose rate meter covering the dose rate range from 0 to 200 mrad h -1 . The instrument is designed to measure X- and γ-radiation dose rates over the energy range from 45 keV to 3 MeV. The radiation detector of the instrument is a GM tube with a specially designed energy compensation sheath. This detector is incorporated in a probe connected to the rate meter by an extensible cable which may be either hand-held or clipped on to the top of the instrument case. All the measurements in this report have been taken with the long axis of the probe normal to the direction of the incident radiation, the orientation recommended by the manufacturer. The information is given under the following headings: facilities and controls; radiation characteristics; electrical characteristics; effect of ambient temperature; mechanical characteristics; summary of performance; conclusions. (U.K.)

The records of radiation control division, No.22 (1985)

International Nuclear Information System (INIS)

Fukui, Masami; Katsurayama, Kousuke; Ishida, Masahiro

1987-03-01

This report is a summary of activities of the radiation control division on the safety management in FY 1985. This report describes the records of the radiation control based on the activities of Indoor Radiation Control Section, Field Radiation Control Section and Personnel Radiation Control Section. External radiation doses were monitored using survey meters and film badges in the working area. Radioactive concentrations in dust and air were monitored in the radiation controlled area and at a number of locations outside the KURRI facilities. Reports of routine tasks such as the meteorological records, and the control of human exposure to radiation are described. This report also summarizes number of unscheduled tasks performed, including the replacement of the centralized monitoring board for radiation control, radiation monitors related to the extension of the spent fuel storage building, and the computer processing system of some indoor radiation monitors. Measurements of environmental radioactivity at several field locations are also presented in this report. (author)

Multiagency radiation survey and site investigation manual (MARSSIM): Survey design

International Nuclear Information System (INIS)

Abelquist, E.W.; Berger, J.D.

1996-01-01

This paper describes the MultiAgency Radiation Survey and Site Investigation Manual (MARSSIM) strategy for designing a final status survey. The purpose of the final status survey is to demonstrate that release criteria established by the regulatory agency have been met. Survey design begins with identification of the contaminants and determination of whether the radionuclides of concern exist in background. The decommissioned site is segregated into Class 1, Class 2, and Class 3 areas, based on contamination potential, and each area is further divided into survey units. Appropriate reference areas for indoor and outdoor background measurements are selected. Survey instrumentation and techniques are selected in order to assure that the instrumentation is capable of detecting the contamination at the derived concentration guideline level (DCGL). Survey reference systems are established and the number of survey data points is determined-with the required number of data points distributed on a triangular grid Pattern. Two suitistical tests are used to evaluate data from final status surveys. For contaminants that are b, present in background, the Wilcoxon Rank Sum test is used; for contaminants that are not present in background, the Wilcoxon Signed Rank (or Sign) test is used. The number of data points needed to satisfy these nonparametric tests is based on the contaminant DCGL value, the expected Standard deviation of the contaminant in background and in the survey unit, and the acceptable probability of making Type I and Type II decision errors. The MARSSIM also requires a reasonable level of assurance that any small areas of elevated residual radioactivity that could be significant relative to regulatory limits are not missed during the final status survey. Measurements and sampling on a specified grid size are used to obtain an adequate assurance level that small locations of elevated radioactivity will Still satisfy DCGLs-applicable to small areas

Verification of radiation exposure using lead shields

International Nuclear Information System (INIS)

Hayashida, Keiichi; Yamamoto, Kenyu; Azuma, Masami

2016-01-01

A long time use of radiation during IVR (intervention radiology) treatment leads up to an increased exposure on IVR operator. In order to prepare good environment for the operator to work without worry about exposure, the authors examined exposure reduction with the shields attached to the angiography instrument, i. e. lead curtain and lead glass. In this study, the lumber spine phantom was radiated using the instrument and the radiation leaked outside with and without shields was measured by the ionization chamber type survey meter. The meter was placed at the position which was considered to be that for IVR operator, and changed vertically 20-100 cm above X-ray focus by 10 cm interval. The radiation at the position of 80 cm above X-ray focus was maximum without shield and was hardly reduced with lead curtain. However, it was reduced with lead curtain plus lead glass. Similar reduction effects were observed at the position of 90-100 cm above X-ray focus. On the other hand, the radiation at the position of 70 cm above X-ray focus was not reduced with either shield, because that position corresponded to the gap between lead curtain and lead glass. The radiation at the position of 20-60 cm above X-ray focus was reduced with lead curtain, even if without lead glass. These results show that lead curtain and lead glass attached to the instrument can reduce the radiation exposure on IVR operator. Using these shields is considered to be one of good means for IVR operator to work safely. (author)

A positioning and data logging system for surface geophysical surveys

International Nuclear Information System (INIS)

Nyquist, J.E.; Blair, M.S.

1988-01-01

The Ultrasonic Ranging and Data System (USRADS) developed at ORNL is being adapted to work with two commercially available geophysical instruments: a magnetometer and an EM31 terrain conductivity meter. Geophysical surveys have proven an important preliminary step in investigating hazardous waste sites. Magnetometers and terrain conductivity meters are used to locate buried drums, trenches, conductive contaminant plumes and map regional changes in geology. About half the field time of a typical geophysical investigation is spent surveying the position of the grid points at which the measurements will be made. Additional time is lost and errors may be made recording instrument values in field notebooks and transcribing the data to a computer. Developed for gamma radiation surveys, the USRAD system keeps track of the surveyor's position automatically by triangulating on an ultrasonic transmitter carried in a backpack. The backpack also contains a radio transmitter that sends the instrument's reading coincident with the ultrasonic pulse. The surveyor's position and the instrument's reading are recorded by a portable computer which can plot the data to check the survey's progress. Electronic files are stored in a form compatible with AutoCAD to speed report writing. 7 refs., 3 figs

Environmental radiation level, radiation anxiety, and psychological distress of non-evacuee residents in Fukushima five years after the Great East Japan Earthquake: Multilevel analyses

Directory of Open Access Journals (Sweden)

Maiko Fukasawa

2017-12-01

Full Text Available The present study aimed to clarify the associations among radiation exposure or psychological exposure to the Fukushima nuclear power plant accident (i.e., fear/anxiety immediately after the accident, current radiation anxiety, and psychological distress among non-evacuee community residents in Fukushima five years after the Great East Japan Earthquake, which occurred in March 2011. A questionnaire survey was administered to a random sample of non-evacuee community residents from 49 municipalities of Fukushima prefecture from February to April 2016, and data from 1684 respondents (34.4% were analyzed. Environmental radiation levels at the time of the accident were ascertained from survey meter data, while environmental radiation levels at the time of the survey were ascertained from monitoring post data. In the questionnaire, immediate fear/anxiety after the accident, current radiation anxiety, and psychological distress were measured using a single-item question, a 7-item scale, and K6, respectively. Multilevel linear or logistic regression models were applied to analyze the determinants of radiation anxiety and psychological distress. The findings showed that environmental radiation levels at the time of the survey were more strongly associated with radiation anxiety than radiation levels immediately after the accident. Disaster-related experiences, such as direct damage, disaster-related family stress, and fear/anxiety after the accident, and demographic characteristics (e.g., younger age, being married, low socioeconomic status were significantly associated with radiation anxiety. Environmental radiation levels at the time of the accident or survey were not significantly associated with psychological distress. Radiation anxiety largely mediated the association between fear/anxiety after the accident and psychological distress. In addition to environmental radiation levels, respondents’ radiation anxiety was affected by multiple factors

Guidance notes : safe practice for the use of nuclear density meters

International Nuclear Information System (INIS)

2000-06-01

These 'Guidance notes' have been written to provide information for owners and users on the safe care and use of instruments containing radioactive materials used for the measurement of moisture content and/or density of materials. They give practical guidance on compliance with the requirements of radiation protection legislation and the 'Code of safe practice for the use of nuclear density meters, NRL C15'. Some of these instruments have been known as 'soil moisture gauges' and others as 'nuclear density meters' or just 'NDMs'. For simplicity, these 'Guidance notes' will follow industry terminology and use the term 'nuclear density meter'. Some parts of these 'Guidance notes' and of the 'Code, NRL C15' are relevant for users of asphalt gauges containing radioactive sources. These are normally laboratory bench instruments, and are not portable field instruments. Nevertheless, the radioactive sources used are similar to those used for moisture measurement and the safety implications are similar. The units of measurement of radioactivity and radiation dose are discussed in Appendix 1. Appendix 2 contains consent application forms while sample transport forms can be found in Appendix 3. (author). 10 refs

Study on external beam radiation therapy

International Nuclear Information System (INIS)

Kim, Mi Sook; Yoo, Seoung Yul; Yoo, Hyung Jun; Ji, Young Hoon; Lee, Dong Han; Lee, Dong Hoon; Choi, Mun Sik; Yoo, Dae Heon; Lee, Hyo Nam; Kim, Kyeoung Jung

1999-04-01

To develop the therapy technique which promote accuracy and convenience in external radiation therapy, to obtain the development of clinical treatment methods for the global competition. The contents of the R and D were 1. structure, process and outcome analysis in radiation therapy department. 2. Development of multimodality treatment in radiation therapy 3. Development of computation using networking techniques 4. Development of quality assurance (QA) system in radiation therapy 5. Development of radiotherapy tools 6. Development of intraoperative radiation therapy (IORT) tools. The results of the R and D were 1. completion of survey and analysis about Korea radiation therapy status 2. Performing QA analysis about ICR on cervix cancer 3. Trial of multicenter randomized study on lung cancers 4. Setting up inter-departmental LAN using MS NT server and Notes program 5. Development of ionization chamber and dose-rate meter for QA in linear accelerator 6. Development on optimized radiation distribution algorithm for multiple slice 7. Implementation on 3 dimensional volume surface algorithm and 8. Implementation on adaptor and cone for IORT

Study on external beam radiation therapy

Energy Technology Data Exchange (ETDEWEB)

Kim, Mi Sook; Yoo, Seoung Yul; Yoo, Hyung Jun; Ji, Young Hoon; Lee, Dong Han; Lee, Dong Hoon; Choi, Mun Sik; Yoo, Dae Heon; Lee, Hyo Nam; Kim, Kyeoung Jung

1999-04-01

To develop the therapy technique which promote accuracy and convenience in external radiation therapy, to obtain the development of clinical treatment methods for the global competition. The contents of the R and D were 1. structure, process and outcome analysis in radiation therapy department. 2. Development of multimodality treatment in radiation therapy 3. Development of computation using networking techniques 4. Development of quality assurance (QA) system in radiation therapy 5. Development of radiotherapy tools 6. Development of intraoperative radiation therapy (IORT) tools. The results of the R and D were 1. completion of survey and analysis about Korea radiation therapy status 2. Performing QA analysis about ICR on cervix cancer 3. Trial of multicenter randomized study on lung cancers 4. Setting up inter-departmental LAN using MS NT server and Notes program 5. Development of ionization chamber and dose-rate meter for QA in linear accelerator 6. Development on optimized radiation distribution algorithm for multiple slice 7. Implementation on 3 dimensional volume surface algorithm and 8. Implementation on adaptor and cone for IORT.

Neutron dosimeters and survey meters in accelerators, reactors and other neutron environments

International Nuclear Information System (INIS)

1989-03-01

Neutron fields in occupationally accessible areas around nuclear reactors, radioisotope sources and medical and high energy accelerators have been characterized using currently available information. Neutron, rem meters, such as the Leake detector, are the most suitable instruments available for conducting neutron dose rate surveys in the vicinity of radioisotope neutron sources, nuclear reactors and medical accelerators. However, these instruments have been shown to be deficient in that they overrespond by a factor of four to neutrons in the 0.1 to 1 MeV range and are insensitive to neutrons from about 1 eV up to about 10 keV. Also, they are insensitive to neutrons above 20 MeV and their use must be restricted near high energy accelerators where significant numbers of neutrons above 20 MeV are known to be present. The most suitable instrument of measure dose from neutrons above 20 MeV is the 12 C(n,2n) 11 C scintillation chamber. Commercially available rem meters frequently use BF 3 counters in the pulse mode to detect thermal neutrons. Therefore, measurements around pulsed accelerators must be made with caution to ensure that the detector is not saturated during each pulse and that the accelerator pulse period is greater than the response time of the detector. The personal neutron dosimeters currently available either are known to be insensitive to neutrons above 20 MeV or have not been tested. Also, all except the albedo dosimeter are insensitive to or have not been tested for neutron energies in the range 1 eV to 10 keV. Several dosimeter types respond reasonably well to neutrons in the energy range 0.1 to 15 MeV, for example, CR-39, bubble and superheated drop detectors. However, the first gas a lower limit of sensitivity of about 0.3 mSv. The bubble detector can be designed to measure doses as small as 1μSv and offers the additional benefit of direct-reading capability. The superheated drop detector is not suitable for use around pulsed accelerators because

Aerial radiological survey of the Joseph M. Farley Nuclear Plant and surrounding area, Dothan, Alabama

International Nuclear Information System (INIS)

Maguire, T.C.; Shipman, G.R.

1982-03-01

An aerial radiological survey was performed during the period 8 to 19 December 1979 over a 2000 square kilometer area centered on the two unit Joseph M. Farley Nuclear Plant near Dothan, Alabama. Radiological data were collected by flying north-south lines spaced 900 meters apart at an altitude of 150 meters above ground level. Processed data showed that all gamma rays detected within the survey area were those expected from naturally occurring radionuclides. Count rates obtained from the aerial platform were converted to exposure rates at 1 meter above the ground and are presented in the form of a radiation contour map. The observed exposure rates were between 4 and 12 microroentgens per hour (μR/h), with most of the area ranging between 4 and 10 μR/h. These values include an estimated cosmic ray contribution of 4.0 μR/h but do not include any contribution from airborne radionuclides, i.e., radon. Exposure rates obtained from ground measurements taken within the survey area were in close agreement with the aerial data. The data were also in close agreement with those obtained from a similar survey conducted during March 1977. Comparison of the results from both surveys indicated that no detectable change in the radiological characteristics of the survey area has occurred due to the operation of unit number 1 during the intervening period. The same equipment and procedures were utilized for both surveys

How Radiation Oncologists Would Disclose Errors: Results of a Survey of Radiation Oncologists and Trainees

International Nuclear Information System (INIS)

Evans, Suzanne B.; Yu, James B.; Chagpar, Anees

2012-01-01

Purpose: To analyze error disclosure attitudes of radiation oncologists and to correlate error disclosure beliefs with survey-assessed disclosure behavior. Methods and Materials: With institutional review board exemption, an anonymous online survey was devised. An email invitation was sent to radiation oncologists (American Society for Radiation Oncology [ASTRO] gold medal winners, program directors and chair persons of academic institutions, and former ASTRO lecturers) and residents. A disclosure score was calculated based on the number or full, partial, or no disclosure responses chosen to the vignette-based questions, and correlation was attempted with attitudes toward error disclosure. Results: The survey received 176 responses: 94.8% of respondents considered themselves more likely to disclose in the setting of a serious medical error; 72.7% of respondents did not feel it mattered who was responsible for the error in deciding to disclose, and 3.9% felt more likely to disclose if someone else was responsible; 38.0% of respondents felt that disclosure increased the likelihood of a lawsuit, and 32.4% felt disclosure decreased the likelihood of lawsuit; 71.6% of respondents felt near misses should not be disclosed; 51.7% thought that minor errors should not be disclosed; 64.7% viewed disclosure as an opportunity for forgiveness from the patient; and 44.6% considered the patient's level of confidence in them to be a factor in disclosure. For a scenario that could be considerable, a non-harmful error, 78.9% of respondents would not contact the family. Respondents with high disclosure scores were more likely to feel that disclosure was an opportunity for forgiveness (P=.003) and to have never seen major medical errors (P=.004). Conclusions: The surveyed radiation oncologists chose to respond with full disclosure at a high rate, although ideal disclosure practices were not uniformly adhered to beyond the initial decision to disclose the occurrence of the error.

Survey and decontamination trial of boat wastes contaminated with radioactive cesium

International Nuclear Information System (INIS)

Takigami, Hidetaka; Yamamoto, Takashi; Suzuki, Go; Takeuchi, Yukio; Tanosaki, Takao; Takata, Mitsuyasu; Okubo, Takuro

2013-01-01

Field survey was conducted to investigate radioactive cesium contamination status of the fiber reinforced plastic (FRP) boats which were damaged by the Great East Japan Earthquake and resulting tsunami, and further affected by nuclear fallout from the accident at the Fukushima No. 1 nuclear power plant. Radiation dose rate was measured targeted at some selected boats and the surrounding environment by using radiation survey meters (i.e., NaI (Tl) scintillation counter and GM counter) and a radiation-sensing camera in order to visualize a dose rate distribution within the area. In addition, FRP parts, sediment deposits and stagnant waters in the boats were sampled and their "1"3"4Cs and "1"3"7Cs radioactivity were measured by gamma-ray spectrometry using NaI (Tl) scintillation or Ge detector. From the monitoring results, materials or sediments in the boats enhanced the radiation levels, however, which can be significantly reduced by decontamination operations such as removal and wash-out of the materials or sediments (i.e., countermeasures for surface-deposited radioactivity). Consequently, the conducted survey and decontamination approaches became a good model and promoted a prompt dismantlement, removal and further disposal/recycle by the local authorities concerned. (author)

Original signs and symptoms in patients surviving five years after atomic bomb exposure under 1000 meters

Energy Technology Data Exchange (ETDEWEB)

Lewis, J J; Patterson, H A

1959-01-01

Atomic bomb victims in Hiroshima who were exposed under 1000 meters and survived over five years were reinvestigated. There were 619 patients who comprised a total sample. Mechanical, blast, burn and radiation injuries were evaluated as to onset, duration, severity, body area affected and type of healing. The modal patient experienced severe radiation and mild trauma. Results were compared with similar earlier studies. The question emerges as to the possibility that patients exposed within 1000 meters with radiation and/or thermal injuries have been dying at a faster rate than those with mechanical or no injuries. A short history of the development of the Atomic Bomb Casualty Commission is included. 17 references, 11 tables.

Contemporary management of prostate cancer: a practice survey of Ontario genitourinary radiation oncologists

International Nuclear Information System (INIS)

Rodrigues, George; D'Souza, David; Crook, Juanita; Malone, Shawn; Sathya, Jinka; Morton, Gerard

2003-01-01

Objective: To survey radiation oncology practice in the utilization of hormonal and radiation therapy in the primary, adjuvant and salvage treatment of localized prostate cancer. Materials and methods: Genitourinary radiation oncologists practicing in Ontario were invited to participate in a practice survey examining staging, hormonal and radiation management, and radiation technique for a variety of common clinical scenarios. Background demographic information was collected on all respondents. The survey consisted of three cases relating to the hormonal/radiation management of low-, intermediate-, and high-risk prostate cancer as well as two adjuvant and one salvage post-prostatectomy scenarios. The survey response rate was 70% (26/37). Results: Clinicians were more likely to utilize laboratory and imaging studies for staging as the risk categorization increased. Low-risk disease was managed with radiation alone in 26/26 (70 Gy in 65%, 74-79.8 Gy in 35%). Intermediate-risk disease was managed with radiation (70 Gy in 46%, 74-79.8 Gy in 54%) with neoadjuvant hormones in 58%. All respondents managed high-risk disease with adjuvant hormones in addition to radiation therapy (70-71 Gy in 85%, and 76 Gy in 15%). In the pT3a, margin negative (PSA undetectable) scenario, most individuals would not recommend adjuvant radiation (73%). If margins were positive, 30% would still not recommend adjuvant radiation. In the salvage scenario (slowly rising PSA 4 years post-prostatectomy for pT2a close margin disease), all respondents would manage with radiation therapy. Hormones were not routinely recommended in the initial management of the adjuvant and salvage scenarios. Radiation doses utilized for both adjuvant and salvage treatment ranged from 60-70 Gy (median 66 Gy). Conclusions: General agreement exists for the management of low- and high-risk disease and in the post-prostatectomy salvage setting. Use of dose-escalation and neoadjuvant hormones in the intermediate

On the use of volumetric strain meters to infer additional characteristics of short-period seismic radiation

Science.gov (United States)

Borcherdt, R.D.; Johnston, M.J.S.; Glassmoyer, G.

1989-01-01

Volumetric strain meters (Sacks-Evertson design) are installed at 15 sites along the San Andreas fault system, to monitor long-term strain changes for earthquake prediction. Deployment of portable broadband, high-resolution digital recorders (GEOS) at several of the sites extends the detection band for volumetric strain to periods shorter than 5 ?? 10-2 sec and permits the simultaneous observation of seismic radiation fields using conventional short-period pendulum seismometers. Recordings of local and regional earthquakes indicate that dilatometers respond to P energy but not direct shear energy and that straingrams can be used to resolve superimposed reflect P and S waves for inference of wave characteristics not permitted by either sensor alone. Simultaneous measurements of incident P- and S-wave amplitudes are used to introduce a technique for single-station estimates of wave field inhomogeneity, free-surface reflection coefficients and local material P velocity. -from Authors

Testing and performance of electrolytic oxygen meters for use in liquid sodium

International Nuclear Information System (INIS)

Taylor, R.G.; Thompson, R.

1983-01-01

The performance of yttria-doped thoria ceramic electrochemical oxygen meters in liquid sodium is described. Tests were carried out using laboratory loops. Temperature coefficients of the oxygen meters have been measured between 380 0 C and 480 0 C, and the response to changes in oxygen level using cold-trap temperatures from 125 0 C to 250 0 C was determined. The ceramic has been shown to give good performance over lifetimes exceeding 400 days in some cases. The temperature coefficients and response to oxygen level changes are in good agreement with thermodynamic predictions. The effect of running the meters in high-oxygen sodium has been studied and a general mode of failure has been shown to be grain-boundary attack by oxygen/sodium solutions. The effect of #betta#-radiation on the meters has been studied. The meters with a metal/metal oxide reference electrode were unaffected by dose rates up to 52860 mGy h - 1 . Meters with an air reference electrode do show an effect as a voltage reduction at levels down to 2420 mGy h - 1 . This effect was temperature-dependent and was insignificant at 500 0 C. (orig.)

Passive Rn dose meters - measuring methods appropriate for large measurement series

International Nuclear Information System (INIS)

Urban, M.; Kiefer, H.

1985-01-01

Passive integrating measuring methods can be classified in several groups by their functioning principle, e.g. spray chambers or open chambers with nuclear trace detectors or TL detectors, open detectors, activated carbon dose meters with or without TL detectors. According to the functioning principle, only radon or radon and fission products can be detected. The lecture gives a survey of the present state of development of passive Rn dose meters. By the example of the Ra dose meter developed at Karlsruhe which was used in inquiry measurements carried out in Germany, Switzerland, the Netherlands, Belgium and Austria, etching technology, estimation of measuring uncertainties, reproducibility and fading behaviour shall be discussed. (orig./HP) [de

Ionizing radiation and non-ionizing radiation in educational environment

International Nuclear Information System (INIS)

Matsuzawa, Takao; Otsubo, Tomonobu; Ikke, Satoshi; Taguchi, Noriko; Takeda, Rie

2005-01-01

By chance, we measured gamma dose rates in our school, and around the JCO Tokai Plant during the criticality on September 30 in 1999, with our GM survey meter. At that time, we made sure to estimate the position of criticality reaction (source point), and the source intensity of criticality reaction, with our own data, measured along the public roads, route 6 and local road 62. The intensity of gamma dose rates along the road was analyzed as Lorentz functions. At the time, there were no environmental radiation data about the criticality accident, or all the data, especially radioactivity and dose rates around the JCO Tokai Plant, was closed to the public. Recently, we are interested in the intensity of non-ionizing radiation, especially extremely low frequency (ELF) magnetic field, and electric field, in our environment. We adopted the same method to analyze the source position and source intensity of an ELF magnetic field and electric behind a wall. (author)

Scintillator power meter applied on Z-pinch plasma soft X-ray yield measurement

International Nuclear Information System (INIS)

Zhang Siqun; Huang Xianbin; Li Jing; Dan Jiakun; Li Jun; Yang Libing; Cui Mingqi; Zhao Yidong

2010-01-01

This paper presents the configuration and measuring parameters of scintillator power meter applied in Z-pinch plasma soft X-ray yield measurement on Yang accelerator. It also introduces the calibration experiment on BSRF, and analyzes the defect of the power meter from calibration results, the possible errors and feasible method for correcting the errors. The measuring results are revised according to spectrum acquired from Dante spectrometer. The revised discrepancy of two instruments is decreased from over 30% to subter-15%. Finally, the result of yield measurement of the puff Z-pinch X-ray radiation is reported as well, i.e., hundreds of Joule, multigigawatt levels of soft X ray radiation were produced by puff Z-pinch on Yang accelerator. (authors)

Radiation level survey of a mobile phone base station

International Nuclear Information System (INIS)

Campos, M.C.; Schaffer, S.R.

2006-01-01

Electromagnetic field (E.M.F.) evaluations were carried out in the surroundings of a roof-top mobile-phone radio-base station (R.B.S.). Four of its sector-panel antennas are installed on two parallel vertical masts, each supporting two panels in a vertical collinear-array. The geometry is such that the vertical plane containing both masts is about 10 meters distant and parallel to the backside of an educational institution. This proximity provoked great anxiety among the local community members regarding potential health hazards.1. Introduction: To keep up with the expansion of the mobile-phone services, the number of Radio-Base Stations (R.B.S.) installations is increasing tremendously in Brazil. Efficient control and radiation monitoring to assess R.B.S. compliance to existing regulations are still lacking and particularly in big cities, clearly non - compliant R.B.S. can be seen which represent potentially hazardous E.M.F. sources to the nearby population. This first survey of an irregular R.B.S. revealed significant E-field strengths outside, as well as inside a classroom of an educational building where an usually prolonged stay is necessary. These results confirm that this problem deserves further attention, moreover, if one considers that public and occupational exposure limits set by I.C.N.I.R.P. (also adopted in Brazil) are exclusively based on the immediate thermal effects of acute exposure, disregarding any potential health risk from prolonged exposure to lower level radiation. Research activities focusing on quantitative aspects of electromagnetic radiation from R.B.S., as well as on biological and adverse health effects are still at a very incipient level, urging for immediate actions to improve this scenario in our country. 2. Material, methods and results Measurements were carried out with a broadband field strength monitor, E.M.R.-300 (W and G) coupled to an isotropic E-field probe (100 khz to 3 GHz). Preliminary measurements helped locating

Estimation of radiation dose received by the radiation workers during radiographic testing

International Nuclear Information System (INIS)

Mohammed, N. A. H. O.

2013-08-01

This study was conducted primarily to evaluate occupational radiation dose in industrial radiography during radiographic testing at Balil-Hadida, with the aim of building up baseline data on radiation exposure in the industrial radiography practice in Sudan. Dose measurements during radiographic testing were performed and compared with IAEA reference dose. In this research the doses measured by using hand held radiation survey meter and personal monitoring dosimeter. The results showed that radiation doses ranged between minimum (0.448 mSv/ 3 month) , and maximum (1.838 mSv / 3 month), with an average value (0.778 mSv/ 3 month), and the standard deviation 0.292 for the workers used gamma mat camera. The analysis of data showed that the radiation dose for all radiation worker are receives less than annual limit for exposed workers 20 mSv/ year and compare with other study found that the dose received while body doses ranging from 0.1 to 9.4 mSv/ year, work area design in all the radiography site followed the three standard rules namely putting radiation signs, reducing access to control area and making of boundaries. Thus the accidents arising from design faults not likely to occur at these site. Results suggest that adequate fundamental training of radiation workers in general radiography prior to industrial radiography work will further improve the standard of personnel radiation protection. (Author)

Radiation protection metrology at a high-energy neutron therapy facility

International Nuclear Information System (INIS)

Bonnett, D.E.; Sherwin, A.G.; More, B.R.

1991-01-01

A radiation protection survey has been carried out at a high-energy neutron therapy facility using a combination of different detectors and counters. Included in the survey were measurements with a tissue equivalent proportional counter (TEPC), a rem meter, a large volume ionisation chamber (LVI) and a Geiger counter. Dose equivalent rates, normalised to a proton beam current of 25 μA, of between 1 μSv.h -1 and 0.7 Sv.h -1 were recorded depending on the location. In general the results confirm the tendency of the rem meter to over-read in fields consisting mainly of low energy neutrons and illustrate the advantages of the diagnostic and gamma discriminating properties of the TEPC. The LVI-Geiger system was found to be the least favourable combination of dosemeters, substantially under-reading and being unable to estimate the neutron dose rate at levels below about 32 μGy.h -1 . (author)

Nuclear radiation monitoring instruments for personnel in nuclear disaster for defence needs

International Nuclear Information System (INIS)

Bhatnagar, P.K.; Vaijapurkar, S.G.; Yadav, Ashok

2005-01-01

Ever since the tragedy of nuclear device exploding over Japan by USA in 1945 awareness exists amongst the armed forces personnel all over the world that a requirement of implementing radiological protection is imminent. Towards this adoption of radiological safety programme is a criterion. In a nuclear war disaster scenario, one encounters initial nuclear radiation (gamma and neutron radiations), gamma radiations from fallout, heat and blast. At certain distances Tanks/ armoured vehicles will survive and 4 R/s radiation level sensing to actuate relays for closing the ports of vehicles is essential, leading to reduction in inhalation, ingestion of fallout radioactivity and reduction in radiation dose received by occupants of the vehicle. Towards this sturdy radiation monitors to indicate gamma dose rate of the order of 1000 R/h, gamma and neutron dosimeters of the order of 1000 cGy with reading instruments are to be developed. These must work in harsh environment and sustain JSS 55555 conditions of army. Defence Laboratory, Jodhpur over past one decade has been involved in developing personnel, area and field monitoring instruments like dosimeters, survey meters, which are useful, acceptable to army personnel, armoured and personnel carrier vehicles, field structures/shelters. Technology transfer after satisfaction of armed forces, product ionisation and supply, maintenance, training has been the endeavor of the DRDO. Herein it is proposed to highlight the techno electronics nuclear radiation monitoring sensors and associated electronics systems developed first time in the country and productionised in bulk for Services for implementing personnel protection. The sensors developed and described are - Radiophotoluminescent Glass (RPLG) for gamma radiation dosimetry , neutron sensitive PIN diode for fast neutron dosimetry, gamma radiation sensitive PIN diode, superheated liquid neutron and gamma sensors. The dosimeter, dose rate meter and field/area instruments are

Bone-and-muscle-equivalent solid chemical dose meters for photon and electron doses above one kilorad

International Nuclear Information System (INIS)

McLaughlin, W.L.; Rosenstein, M.; Levine, H.

1975-01-01

Conventional solid dose meters, such as plastic films, powders, emulsions, glasses, ceramics and gels, have a response to ionizing photons and electrons that varies markedly over a broad spectrum when compared with the absorption characteristics of biological tissues. New radiochromic dyed plastic dose meters have been developed with X- and gamma ray and electron energy absorption cross-sections (calculated) and radiation energy responses (experimental) corresponding approximately to those for human muscle and bone, for a spectrum from a few keV to at least 10 MeV. Three-dimensional solid dose meters useful over the absorbed dose range of 10 3 to 10 6 rad are formed by thermosetting a selected combination of monomers containing the radiochromic dye in solution. Thin-film dose meters for the dose range 10 5 to 10 7 rad are formed by casting on optically flat surfaces strippable layers of special combinations of polymers and dyes in solution. The response of these systems to X- and gamma rays and electrons has been studied over various radiation spectra, dose-rates and temperatures during irradiation. (author)

Is Individual Metering Socially Sustainable? The Case of Multifamily Housing in France

Directory of Open Access Journals (Sweden)

Bernard Barraqué

2011-06-01

Full Text Available Before generalising water metering and billing at the apartment level for consumer equity reasons, and alleviating the burden of water bills for poor families through increasing block tariffs (IBTs, Paris Council asked for some expert advice. The pros and cons of two separate issues – IBTs efficiency and justice; and individual household metering – were mixed. Our research first summarises various studies of the redistributive effects of tariff changes, first from flat rates to metering, and then from uniform prices to IBTs. We address the particular case of multifamily housing, where it is possible to retain collective billing, while relying on sub-metering to allocate the bill. The limitations of classical econometric surveys on large samples (in terms of understanding households’ strategies with tap water support the need for supplementary detailed sociological surveys at neighbourhood or building levels, if only to check the unexpected redistributive effects of tariff changes in practice. We review the specific French situation, peculiarly in Paris, to show that individual apartment billing is more costly and tends to have regressive effects. Like other cities in France, Paris abandoned the implementation of Art. 93 of the 2000 law, which encouraged individual billing; and we explain why.

77 FR 40586 - Draft NIST Interagency Report (NISTIR) 7823, Advanced Metering Infrastructure Smart Meter...

Science.gov (United States)

2012-07-10

...-01] Draft NIST Interagency Report (NISTIR) 7823, Advanced Metering Infrastructure Smart Meter... Technology (NIST) seeks comments on Draft NISTIR 7823, Advanced Metering Infrastructure Smart Meter... conformance test requirements for the firmware upgradeability process for the Advanced Metering Infrastructure...

Results of the Association of Directors of Radiation Oncology Programs (ADROP) Survey of Radiation Oncology Residency Program Directors

International Nuclear Information System (INIS)

Harris, Eleanor; Abdel-Wahab, May; Spangler, Ann E.; Lawton, Colleen A.; Amdur, Robert J.

2009-01-01

Purpose: To survey the radiation oncology residency program directors on the topics of departmental and institutional support systems, residency program structure, Accreditation Council for Graduate Medical Education (ACGME) requirements, and challenges as program director. Methods: A survey was developed and distributed by the leadership of the Association of Directors of Radiation Oncology Programs to all radiation oncology program directors. Summary statistics, medians, and ranges were collated from responses. Results: Radiation oncology program directors had implemented all current required aspects of the ACGME Outcome Project into their training curriculum. Didactic curricula were similar across programs nationally, but research requirements and resources varied widely. Program directors responded that implementation of the ACGME Outcome Project and the external review process were among their greatest challenges. Protected time was the top priority for program directors. Conclusions: The Association of Directors of Radiation Oncology Programs recommends that all radiation oncology program directors have protected time and an administrative stipend to support their important administrative and educational role. Departments and institutions should provide adequate and equitable resources to the program directors and residents to meet increasingly demanding training program requirements.

Evaluating natural radiation level by existing airborne radioactive data

International Nuclear Information System (INIS)

Mingkao, Hu; Changqing, Han; Jiangqi, Fang; Zhengxin, Shen

2002-01-01

Airborne Survey and Remote Sensing Center of Nuclear Industry, founded in the middle of 1950s, is a unique unit specialized in uranium exploration by airborne radioactive survey in China. Large numbers of airborne data of radioactivity and abundant experience have been accumulated for more than 40 years. All-round detailed investigation of environmental radiation levels in our country will not be completed in the near future. Thus, at present it is considered to evaluate natural radiation levels using the existing radioactive data. This paper introduces the results of analysis and study comparing airborne radioactive data for radiation environmental evaluation obtained from survey area in Gansu, China, in the 2001 with the measurement results by ground gamma ray radiation dose-rate instrument for environment. The air-earth inter-comparison error does not exceed 30% at radiation fields with a definite area, and the air-earth inter-comparison error does not exceed 60% at outcrop of granite. In 6km long profile that has various circumstances, such as desert, Gobi, farmland and residential area, minimum of air absorbed dose rate is 47nGy/h at an altitude of 1 meter above the soil plane, maximum is 68nGy/h. The inter-comparison errors are usually less than 20%, and maximum is 25.38%. This shows that it is feasible to obtain natural radiation levels rapidly if we could use the existing radioactive data adequately and make some correction, such as geology factor

A National Radiation Oncology Medical Student Clerkship Survey: Didactic Curricular Components Increase Confidence in Clinical Competency

Energy Technology Data Exchange (ETDEWEB)

Jagadeesan, Vikrant S. [Department of Radiation and Cellular Oncology, Pritzker School of Medicine, University of Chicago, Chicago, Illinois (United States); Raleigh, David R. [Department of Radiation Oncology, School of Medicine, University of California–San Francisco, San Francisco, California (United States); Koshy, Matthew; Howard, Andrew R.; Chmura, Steven J. [Department of Radiation and Cellular Oncology, Pritzker School of Medicine, University of Chicago, Chicago, Illinois (United States); Golden, Daniel W., E-mail: dgolden@radonc.uchicago.edu [Department of Radiation and Cellular Oncology, Pritzker School of Medicine, University of Chicago, Chicago, Illinois (United States)

2014-01-01

Purpose: Students applying to radiation oncology residency programs complete 1 or more radiation oncology clerkships. This study assesses student experiences and perspectives during radiation oncology clerkships. The impact of didactic components and number of clerkship experiences in relation to confidence in clinical competency and preparation to function as a first-year radiation oncology resident are evaluated. Methods and Materials: An anonymous, Internet-based survey was sent via direct e-mail to all applicants to a single radiation oncology residency program during the 2012-2013 academic year. The survey was composed of 3 main sections including questions regarding baseline demographic information and prior radiation oncology experience, rotation experiences, and ideal clerkship curriculum content. Results: The survey response rate was 37% (70 of 188). Respondents reported 191 unique clerkship experiences. Of the respondents, 27% (19 of 70) completed at least 1 clerkship with a didactic component geared towards their level of training. Completing a clerkship with a didactic component was significantly associated with a respondent's confidence to function as a first-year radiation oncology resident (Wilcoxon rank–sum P=.03). However, the total number of clerkships completed did not correlate with confidence to pursue radiation oncology as a specialty (Spearman ρ P=.48) or confidence to function as a first year resident (Spearman ρ P=.43). Conclusions: Based on responses to this survey, rotating students perceive that the majority of radiation oncology clerkships do not have formal didactic curricula. Survey respondents who completed a clerkship with a didactic curriculum reported feeling more prepared to function as a radiation oncology resident. However, completing an increasing number of clerkships does not appear to improve confidence in the decision to pursue radiation oncology as a career or to function as a radiation oncology resident. These

A national radiation oncology medical student clerkship survey: didactic curricular components increase confidence in clinical competency.

Science.gov (United States)

Jagadeesan, Vikrant S; Raleigh, David R; Koshy, Matthew; Howard, Andrew R; Chmura, Steven J; Golden, Daniel W

2014-01-01

Students applying to radiation oncology residency programs complete 1 or more radiation oncology clerkships. This study assesses student experiences and perspectives during radiation oncology clerkships. The impact of didactic components and number of clerkship experiences in relation to confidence in clinical competency and preparation to function as a first-year radiation oncology resident are evaluated. An anonymous, Internet-based survey was sent via direct e-mail to all applicants to a single radiation oncology residency program during the 2012-2013 academic year. The survey was composed of 3 main sections including questions regarding baseline demographic information and prior radiation oncology experience, rotation experiences, and ideal clerkship curriculum content. The survey response rate was 37% (70 of 188). Respondents reported 191 unique clerkship experiences. Of the respondents, 27% (19 of 70) completed at least 1 clerkship with a didactic component geared towards their level of training. Completing a clerkship with a didactic component was significantly associated with a respondent's confidence to function as a first-year radiation oncology resident (Wilcoxon rank-sum P=.03). However, the total number of clerkships completed did not correlate with confidence to pursue radiation oncology as a specialty (Spearman ρ P=.48) or confidence to function as a first year resident (Spearman ρ P=.43). Based on responses to this survey, rotating students perceive that the majority of radiation oncology clerkships do not have formal didactic curricula. Survey respondents who completed a clerkship with a didactic curriculum reported feeling more prepared to function as a radiation oncology resident. However, completing an increasing number of clerkships does not appear to improve confidence in the decision to pursue radiation oncology as a career or to function as a radiation oncology resident. These results support further development of structured didactic

A National Radiation Oncology Medical Student Clerkship Survey: Didactic Curricular Components Increase Confidence in Clinical Competency

International Nuclear Information System (INIS)

Jagadeesan, Vikrant S.; Raleigh, David R.; Koshy, Matthew; Howard, Andrew R.; Chmura, Steven J.; Golden, Daniel W.

2014-01-01

Purpose: Students applying to radiation oncology residency programs complete 1 or more radiation oncology clerkships. This study assesses student experiences and perspectives during radiation oncology clerkships. The impact of didactic components and number of clerkship experiences in relation to confidence in clinical competency and preparation to function as a first-year radiation oncology resident are evaluated. Methods and Materials: An anonymous, Internet-based survey was sent via direct e-mail to all applicants to a single radiation oncology residency program during the 2012-2013 academic year. The survey was composed of 3 main sections including questions regarding baseline demographic information and prior radiation oncology experience, rotation experiences, and ideal clerkship curriculum content. Results: The survey response rate was 37% (70 of 188). Respondents reported 191 unique clerkship experiences. Of the respondents, 27% (19 of 70) completed at least 1 clerkship with a didactic component geared towards their level of training. Completing a clerkship with a didactic component was significantly associated with a respondent's confidence to function as a first-year radiation oncology resident (Wilcoxon rank–sum P=.03). However, the total number of clerkships completed did not correlate with confidence to pursue radiation oncology as a specialty (Spearman ρ P=.48) or confidence to function as a first year resident (Spearman ρ P=.43). Conclusions: Based on responses to this survey, rotating students perceive that the majority of radiation oncology clerkships do not have formal didactic curricula. Survey respondents who completed a clerkship with a didactic curriculum reported feeling more prepared to function as a radiation oncology resident. However, completing an increasing number of clerkships does not appear to improve confidence in the decision to pursue radiation oncology as a career or to function as a radiation oncology resident. These results

Smart meters. Smart metering. A solution module for a future-oriented energy system; Intelligente Zaehler. Smart Metering. Ein Loesungsbaustein fuer ein zukunftsfaehiges Energiesystem

Energy Technology Data Exchange (ETDEWEB)

Grimm, Nadia; Seidl, Hans [comps.

2011-12-15

The German Energy Agency GmbH (Berlin, Federal Republic of Germany) reports on smart metering as a solution module for a future-oriented energy system by means of the following contributions: (1) Key role for smart meters; (2) What is smart metering? (3) Implementation of smart metering in Europe; (4) The market development to date in Germany; (5) Practical experiences with smart metering in Germany; (6) Frequently asked questions; (7) Smart metering in intelligent networks; (8) Legal framework conditions; (9) Data security and data protection in the utilisation of smart meters; (10) Ongoing information; (11) Efficient energy systems.

A review of net metering mechanism for electricity renewable energy sources

Energy Technology Data Exchange (ETDEWEB)

Poullikkas, Andreas; Kourtis, George; Hadjipaschalis, Ioannis [Electricity Authority of Cyprus, P.O. Box 24506, 1399 Nicosia (Cyprus)

2013-07-01

In this work, an overview of the net metering mechanism for renewable energy sources for power generation (RES-E) systems is carried out. In particular, the net metering concept is examined with its benefits and misconceptions. Furthermore, a survey of the current operational net metering schemes in different countries in the world, such as, in Europe, USA, Canada, Thailand and Australia, is carried out. The survey indicated that there are different net metering mechanisms depending on the particularities of each country (or state in the case of USA). Especially, in Europe, only five countries are using net metering in a very simple form, such as, any amount of energy produced by the eligible RES-E technology is compensated from the energy consumed by the RES-E producer, which results to either a less overall electricity bill or to an exception in payment energy taxes. In the USA and the USA territories, any customer’s net excess generation is credited to the customer’s next electricity bill for a 12-month billing cycle at various rates or via a combination between rates. The actual type of net excess generation (NEG) credit is decided by a number of set criteria, such as the type of RES-E technology, the RES-E capacity limit, the type of customer and the type of utility. Regarding any excess credit at the end of the 12-month billing cycle, this is either granted to the utilities, or carries over indefinitely to the customer’s next electricity bill, or is reconciled annually at any rate, or provides an option to the customer to choose between the last two options.

Investigation and Comparison of Separate Meter-In Separate Meter-Out Control Strategies

DEFF Research Database (Denmark)

Pedersen, Henrik C.; Andersen, Torben Ole; Skoubo, Tobias

2014-01-01

In the later years, there has been an increased focus on new valve types, which yield the possibility to do Separate Meter-In Separate Meter-Out (SMISMO) control. This includes both digital valves, but proportional valves with separate metering spools and build in pressure sensors are also emerging....... The possibility to independently control the meter-in and meter-out side not only increase the functionality of the system, but also opens up for better performance and/or lowered energy consumption. The focus of the current paper is therefore on investigation and comparison of what may be obtained using...

Beyond revenue metering -- a new age for automatic meter reading

Energy Technology Data Exchange (ETDEWEB)

Chebra, R. J. [RJC Consulting L.L.C., PQ (Canada)

2002-10-01

Advanced metering, data management, and communications possibilities of automated meter reading are explored. Applications in the area of demand side management, including load reduction, peak shaving and load shifting, new tariff structures based on the 'time of use incentive/penalty' approach, and information grade metering are emphasized. Based on trends and expectations, it is predicted that AMR will continue to experience rapid growth and deployment as new services are made available to the mass market. For example, technological advances will enable the industry to make 'time of use metering ' more attractive and beneficial to residential consumers, and embedded intelligence will make it possible to achieve more holistic energy environments.

Microprocessor based mobile radiation survey system

International Nuclear Information System (INIS)

Gilbert, R.W.; McCormack, W.D.

1983-12-01

A microprocessor-based system has been designed and constructed to enhance the performance of routine radiation surveys on roads within the Hanford site. This device continually monitors system performance and output from four sodium iodide detectors mounted on the rear bumper of a 4-wheel drive truck. The gamma radiation count rate in counts-per-second is monitored, and a running average computed, with the results compared to predefined limits. If an abnormal instantaneous or average count rate is detected, an alarm is sounded with responsible data displayed on a liquid crystal panel in the cab of the vehicle. The system also has the capability to evaluate detector output using multiple time constants and to perform more complex tests and comparison of the data. Data can be archived for later analysis on conventional chart recorders or stored in digital form on magnetic tape or other digital storage media. 4 figures

Survey of instrumentation for environmental monitoring: major update. Volume 3. Radiation

Energy Technology Data Exchange (ETDEWEB)

1979-09-01

This is the third volume of a four-volume (seven-part) series, the culmination of a comprehensive survey of instrumentation for environmental monitoring. Consideration is given to instruments and techniques presently in use and to those developed for other purposes but having possible applications to radiation monitoring. The results of the survey are given as descriptions of the physical and operating characteristics of available instruments, critical comparisons among instrumentation methods, and recommendations of promising methodology and development of new instrumentation. Information is also given regarding the pollutants to be monitored, their characteristics and forms, their sources and pathways, their effects on the ecosystem, and the means of controlling them through process and regulatory controls. The discussion is presented under sections entitled radiation sources; instrumentation: by type of radiation or instrument type; and, instrumentation for specific radionuclides. (JGB)

Survey of instrumentation for environmental monitoring: major update. Volume 3. Radiation

International Nuclear Information System (INIS)

1979-09-01

This is the third volume of a four-volume (seven-part) series, the culmination of a comprehensive survey of instrumentation for environmental monitoring. Consideration is given to instruments and techniques presently in use and to those developed for other purposes but having possible applications to radiation monitoring. The results of the survey are given as descriptions of the physical and operating characteristics of available instruments, critical comparisons among instrumentation methods, and recommendations of promising methodology and development of new instrumentation. Information is also given regarding the pollutants to be monitored, their characteristics and forms, their sources and pathways, their effects on the ecosystem, and the means of controlling them through process and regulatory controls. The discussion is presented under sections entitled radiation sources; instrumentation: by type of radiation or instrument type; and, instrumentation for specific radionuclides

Final report on the radiological surveys of designated DX firing sites at Los Alamos National Laboratory

International Nuclear Information System (INIS)

1996-01-01

CHEMRAD was contracted by Los Alamos National Laboratory to perform USRADS reg-sign (UltraSonic Ranging And Data System) radiation scanning surveys at designated DX Sites at the Los Alamos National Laboratory. The primary purpose of these scanning surveys was to identify the presence of Depleted Uranium (D-38) resulting from activities at the DX Firing Sites. This effort was conducted to update the most recent surveys of these areas. This current effort was initiated with site orientation on August 12, 1996. Surveys were completed in the field on September 4, 1996. This Executive Summary briefly presents the major findings of this work. The detail survey results are presented in the balance of this report and are organized by Technical Area and Site number in section 2. This organization is not in chronological order. USRADS and the related survey methods are described in section 3. Quality Control issues are addressed in section 4. Surveys were conducted with an array of radiation detectors either mounted on a backpack frame for man-carried use (Manual mode) or on a tricycle cart (RadCart mode). The array included radiation detectors for gamma and beta surface near surface contamination as well as dose rate at 1 meter above grade. The radiation detectors were interfaced directly to an USRADS 2100 Data Pack

Assessment of the implementation regulations for smart meters; Beoordeling uitvoeringsregelingen Slimme Meter

Energy Technology Data Exchange (ETDEWEB)

Boekema, J.

2011-03-15

TNO (Netherlands) assessed whether the smart meter is reliable and future proof. By request of the Dutch Ministry of Economic Affairs, Agriculture and Innovation (ELI) an assessment was conducted of the requirements for smart meters and, as formulated in the Order in Council 'Decree on remotely readable metering devices', based on 48 tests regarding security, privacy and future stability. Taking into account a number of described recommendations, TNO deems the legislation and implementation schemes sufficient to allow for safe, reliable and future proof implementation of smart meters in the Netherlands. [Dutch] TNO heeft beoordeeld of de slimme meter betrouwbaar en toekomstvast is. Ten behoeve van het ministerie van Economische Zaken, Landbouw en Innovatie (ELI) zijn de eisen die aan slimme meters worden gesteld, en zoals verwoord in de AmvB 'Besluit op afstand uitleesbare meetinrichtingen', beoordeeld aan de hand van 48 toetsen over zekerheid (security), persoonlijke levenssfeer (privacy) en toekomstvastheid. Met inachtneming van een aantal omschreven aanbevelingen, vindt TNO wetgeving en uitvoeringsregelingen zodanig dat daarmee een veilige, betrouwbare en toekomstvaste slimme meter geimplementeerd kan worden in Nederland.

Survey of Radiation Oncology Centres in Australia: report of the radiation oncology treatment quality program

International Nuclear Information System (INIS)

Klybaba, M.; Kenny, L.; Kron, T.; Harris, J.; O'Brien, P.

2009-01-01

Full text: One of the first steps towards the development of a comprehensive quality program for radiation oncology in Australia has been a survey of practice. This paper reports on the results of the survey that should inform the development of standards for radiation oncology in Australia. A questionnaire of 108 questions spanning aspects of treatment services, equipment, staff, infrastructure and available quality systems was mailed to all facilities providing radiation treatment services in Australia (n = 45). Information of 42 sites was received by June 2006 providing data on 113 operational linear accelerators of which approximately 2/3 are equipped with multi-leaf collimators. More than 75% of facilities were participating in a formal quality assurance (QA) system, with 63% following a nationally or internationally recognised system. However, there was considerable variation in the availability of policies and procedures specific to quality aspects, and the review of these. Policies for monitoring patient waiting times for treatment were documented at just 71% of all facilities. Although 85% of all centres do, in fact, monitor machine throughput, the number and types of efficiency measures varied markedly, thereby limiting the comparative use of these results. Centres identified workload as the single most common factor responsible for limiting staff involvement in both QA processes and clinical trial participation. The data collected in this 'snapshot' survey provide a unique and comprehensive baseline for future comparisons and evaluation of changes

Aerial radiological survey of the Brookhaven National Laboratory and surrounding area, May 1980

International Nuclear Information System (INIS)

Hobaugh, J.L.; Steiner, P.A.

1984-01-01

An aerial radiological survey was performed from 15 to 18 May 1980 over approximately a 21-square-kilometer (8-square-mile) area surrounding the Brookhaven National Laboratory (BNL). BNL is located in the center of Suffolk County, Long Island, New York. All gamma radiation data were collected by flying north-south lines spaced 91 meters (300 feet) apart at an altitude of 61 meters (200 feet) above ground level. A total of 17 anomalous areas were identified. The dominant isotopes found over these areas were cesium-137, manganese-54, and cobalt-60. All anomalies identified by the aerial measurements were correlated to site activities and storage facilities. 4 references, 18 figures, 1 table

Portable wireless metering

Energy Technology Data Exchange (ETDEWEB)

DiPaola, L [Powtel Monitoring Systems, Inc., Ajax, ON (Canada)

1996-12-31

Portable meters were discussed as alternatives to standard billing meters for temporary installations. Current, voltage and power factor at a distribution station were measured to calculate kW and kVAR, using an easy to install product that communicates live readings directly to the existing billing system. A background of situations where temporary metering is a possible alternative to regular meters was presented. Use of electronic, clamp on Electronic Recording Ammeters (ERA) and their drawbacks were discussed. An improved temporary metering solution using FM radio transmission to deliver live data to a receiving device, the Eagle Series 3500, was introduced. Improvements over previous ERA systems were discussed, including accuracy, lack of batteries, immediate confirmation of functionality, current, voltage and power factor monitoring, direct feed to billing system, line crew savings, need for only a single unit at any given site, bi-directional power flow metering, independent report storage media, and a portable voltage and P.F. diagnostic tool. Details of trial applications at the Utopia distribution station west of Barrie, ON were presented. This technology was said to be still in the testing stage, but its flexibility and economy were sonsidered to be very promising for future application.

Results of the 1993 Association of Residents in Radiation Oncology survey

International Nuclear Information System (INIS)

Ling, Stella M.; Flynn, Daniel F.

1996-01-01

In 1993, the Association of Residents in Radiation Oncology (ARRO) conducted its tenth annual survey of all residents training in radiation oncology in the United States. The characteristics of current residents are described. Factors influencing the choice of Radiation Oncology as a medical specialty, and posttraining career plans were identified. Residents raised issues on the adequacy of training, problems in work routine, and expressed concerns about board certification and recertification, and about decreased future practice opportunities

Survey of radiation protection, radiation transport, and shielding information needs of the nuclear power industry. Final report

International Nuclear Information System (INIS)

Maskewitz, B.F.; Trubey, D.K.; Roussin, R.W.; McGill, B.L.

1976-04-01

The Radiation Shielding Information Center (RSIC) is engaged in a program to seek out, organize, and disseminate information in the area of radiation transport, shielding, and radiation protection. This information consists of published literature, nuclear data, and computer codes and advanced analytical techniques required by ERDA, its contractors, and the nuclear power industry to improve radiation analysis and computing capability. Information generated in this effort becomes a part of the RSIC collection and/or data base. The purpose of this report on project 219-1 is to document the results of the survey of information and computer code needs of the nuclear power industry in the area of radiation analysis and protection

Survey of radiation protection, radiation transport, and shielding information needs of the nuclear power industry. Final report

Energy Technology Data Exchange (ETDEWEB)

Maskewitz, B.F.; Trubey, D.K.; Roussin, R.W.; McGill, B.L.

1976-04-01

The Radiation Shielding Information Center (RSIC) is engaged in a program to seek out, organize, and disseminate information in the area of radiation transport, shielding, and radiation protection. This information consists of published literature, nuclear data, and computer codes and advanced analytical techniques required by ERDA, its contractors, and the nuclear power industry to improve radiation analysis and computing capability. Information generated in this effort becomes a part of the RSIC collection and/or data base. The purpose of this report on project 219-1 is to document the results of the survey of information and computer code needs of the nuclear power industry in the area of radiation analysis and protection.

Smart metering. Conformance tests for electricity meters; Smart Metering. Konformitaetstests an Stromzaehlern

Energy Technology Data Exchange (ETDEWEB)

Bormann, Matthias; Pongratz, Siegfried [VDE Pruef- und Zertifizierungsinstitut, Offenbach (Germany)

2012-07-01

Introduction of communication technologies into today's energy network enables the interworking between the domains of smart metering, smart grid, smart home and e-mobility as well as the creation and provisioning of new innovative services such as efficient load adjustment. Due to this convergence the new energy networks are becoming increasingly complex. Ensuring the interworking between all network elements (e.g. electricity meters, gateways) in these smart energy networks is of utmost importance. To this end conformance and interoperability tests have to be defined to ensure that services work as expected. (orig.)

An Improved Measurement Method for the Strength of Radiation of Reflective Beam in an Industrial Optical Sensor Based on Laser Displacement Meter.

Science.gov (United States)

Bae, Youngchul

2016-05-23

An optical sensor such as a laser range finder (LRF) or laser displacement meter (LDM) uses reflected and returned laser beam from a target. The optical sensor has been mainly used to measure the distance between a launch position and the target. However, optical sensor based LRF and LDM have numerous and various errors such as statistical errors, drift errors, cyclic errors, alignment errors and slope errors. Among these errors, an alignment error that contains measurement error for the strength of radiation of returned laser beam from the target is the most serious error in industrial optical sensors. It is caused by the dependence of the measurement offset upon the strength of radiation of returned beam incident upon the focusing lens from the target. In this paper, in order to solve these problems, we propose a novel method for the measurement of the output of direct current (DC) voltage that is proportional to the strength of radiation of returned laser beam in the received avalanche photo diode (APD) circuit. We implemented a measuring circuit that is able to provide an exact measurement of reflected laser beam. By using the proposed method, we can measure the intensity or strength of radiation of laser beam in real time and with a high degree of precision.

Telecommunication Technologies for Smart Grid Projects with Focus on Smart Metering Applications

Directory of Open Access Journals (Sweden)

Nikoleta Andreadou

2016-05-01

Full Text Available This paper provides a study of the smart grid projects realised in Europe and presents their technological solutions with a focus on smart metering Low Voltage (LV applications. Special attention is given to the telecommunications technologies used. For this purpose, we present the telecommunication technologies chosen by several European utilities for the accomplishment of their smart meter national roll-outs. Further on, a study is performed based on the European Smart Grid Projects, highlighting their technological options. The range of the projects analysed covers the ones including smart metering implementation as well as those in which smart metering applications play a significant role in the overall project success. The survey reveals that various topics are directly or indirectly linked to smart metering applications, like smart home/building, energy management, grid monitoring and integration of Renewable Energy Sources (RES. Therefore, the technological options that lie behind such projects are pointed out. For reasons of completeness, we also present the main characteristics of the telecommunication technologies that are found to be used in practice for the LV grid.

Proposed Philippine radiation-sterilization plant, and a survey of market potential

International Nuclear Information System (INIS)

Singson, C.C.; Ibe, L.D.

1975-01-01

The paper deals with a study to assess the market potential of radiation sterilization in the Philippines. A market survey conducted with the technical assistance of an IAEA expert from India shows that most of the pharmaceutical industries engaged in the manufacture of medical products unanimously agree that there is an urgent need for a centralized radiation sterilization plant to meet the demands of sterilization of most of their products and packaging materials. The authorities of the government and some of the private hospitals surveyed are also very keen for the establishment of a sterilization facility since most modern medical products and devices are made of heat-sensitive thermoplastics which cannot be heat or steam sterilized. Availability of sterile products will help improve the public health standards of the population. The scope of the utilization of a radiation-sterilization facility in Diliman Quezon City is also discussed. (author)

Micro-gen metering solutions

Energy Technology Data Exchange (ETDEWEB)

Elland, J.; Dickson, J.; Cranfield, P.

2003-07-01

This report summarises the results of a project to investigate the regulation of domestic electricity metering work and identify the most economic options for micro-generator installers to undertake work on electricity meters. A micro-generation unit is defined as an energy conversion system converting non-electrical energy into electrical energy and can include technologies such as photovoltaic systems, small-scale wind turbines, micro-hydroelectric systems, and combined heat and power systems. Details of six tasks are given and cover examination of the existing framework and legal documentation for metering work, the existing technical requirements for meter operators, meter operator personnel accreditation, appraisal of options for meter changes and for micro-generation installation, document change procedures, industry consultation, and a review of the costs implications of the options.

Dosimetric methodology and reference system for diagnostic level X radiation

International Nuclear Information System (INIS)

Potiens, Maria da Penha Albuquerque

1999-01-01

Several methodologies for the calibration of diagnostic radiology instruments were developed and established at the Calibration Laboratory of IPEN. These established radiation qualities are recommended by international standards. The methods may be used in the calibration procedures of survey meters used in radiation protection measurements (scattered radiation), instruments used in direct beams (attenuated and non attenuated beams) and quality control instruments. A reference system was proposed using two identical ionization chambers developed at IPEN. They differ only by the collecting electrode material, one of aluminium and the other of graphite. The different energetic dependence of the chamber's response provided a ratio related to the tube potential. The variation of only 0.28%, from 14.3 to 111 keV, on the energetic dependence of the graphite electrode chamber, provided the possibility of air kerma rate determination in the studied radiation beams. (author)

Factors influencing perception of radiation risk in people around Chernobyl. Survey in Ukraine

International Nuclear Information System (INIS)

Shibata, Yoshisada

2010-01-01

To elucidate the factors influencing perception of radiation risk in people around Chernobyl, we conducted a survey in Ukraine using self-administered questionnaire consisting of 37 questions including 5 questions about radiation contamination of their living places and foodstuffs, and 9 questions about radiation and risk. The subjects were high school or university students and their parents living in Zhytomyr, Rivne, Kirovograd and Odesa regions, and Slavutych city. In each of these 5 survey areas, we distributed 330 questionnaires to students and their parents, respectively. A total of 1,536 students (93%) responded to the questionnaire, while in parents only 861 (52%) responded. In students, a significant difference by place of residence was observed in the frequency of those regarding radiation accident or radon in dwellings being highly dangerous. (author)

Determination of non-ionizing radiation at Ibrahim Yaakub College cafeteria facility, Universiti Kebangsaan Malaysia

International Nuclear Information System (INIS)

Mohamad Najmi Jahaya

2012-01-01

Radiation is a form of energy emitted by molecules or atoms and transmitted through matter in the form of a magnetic particle or wave. Every day we are exposed to various forms of radiation around us either we are aware of or not. Radiation is divided into two which are ionizing and non-ionizing radiation. Non-ionizing radiation is a radiation that cannot ionize the particles which pass through it such as electromagnetic waves. Electromagnetic waves consist of radio waves, micro waves, ultraviolet rays and infra-red. Radio frequency has range between 3 kHz and 300 GHz. The study was carried out at the cafeteria facility in Ibrahim Yaakub College. This study used RF EMF Strength Meter which can measure radio frequency (RF) in the range of 10 MHz to 8 GHz. Contour mapping is made 12 meters far and each interval with 2 meters far. Readings are taken every day for one month and taken at three different times which are at morning (8:00 am), lunch (12:00 noon) and afternoon (5:00 pm). This survey is to obtain radio frequency reading. Monitoring results will be compared with the standards sets by the Suruhanjaya Komunikasi Dan Multimedia Malaysia (SKMM) or Malaysian Communications and Multimedia Commission (MCMC), which is 450 x 104 μW/ m 2 , compared with exposure limit in New Zealand and Canada, which is 200 x 104 μW/ m 2 and 300 x 104 μW/ cm 2 , and also will be compared with the results of this study which has been done before with a different tool. The results showed only 0.188 %, 0.422 % and 0.281 % of the standard dose are radiated and this will not harm the students and staffs of Ibrahim Yaakub College. (author)

Remote Sensing of Radiation Dose Rate by Customizing an Autonomous Robot

International Nuclear Information System (INIS)

Kobayashi, T; Nakahara, M; Morisato, K; Takashina, T; Kanematsu, H

2012-01-01

Distribution of radiation dose was measured by customizing an autonomous cleaning robot 'Roomba' and a scintillation counter. The robot was used as a vehicle carrying the scintillation survey meter, and was additionally equipped with an H8 micro computer to remote-control the vehicle and to send measured data. The data obtained were arranged with position data, and then the distribution map of the radiation dose rate was produced. Manual, programmed and autonomous driving tests were conducted, and all performances were verified. That is, for each operational mode, the measurements both with moving and with discrete moving were tried in and outside of a room. Consequently, it has been confirmed that remote sensing of radiation dose rate is possible by customizing a robot on market.

Survey of Michigan dentists and radiation oncologists on oral care of patients undergoing head and neck radiation therapy.

Science.gov (United States)

Patel, Yoshita; Bahlhorn, Hannah; Zafar, Saniya; Zwetchkenbaum, Samuel; Eisbruch, Avraham; Murdoch-Kinch, Carol Anne

2012-07-01

Oral complications of radiation therapy for head and neck cancer (HNC) are associated with a significant decline in oral health-related quality of life (OHQOL). The dentist, working with the radiation oncologist and the rest of the health care team, plays an important role in the prevention and management of these complications, but patients do not always receive care consistent with current guidelines. This study investigated barriers to recommended care. There is variability in knowledge and practice among dentists and radiation oncologists regarding the dental management of patients treated with head and neck radiotherapy (HNRT), and inadequate communication and collaboration between members of the patient's health care team contribute to inconsistencies in application of clinical care guidelines. There is on interest and need for continuing dental (CDE) and medical education (CME) on this topic. A questionnaire was developed to assess dentists' knowledge and practice of dental management of HNC patients and their interest in CDE on this topic. All members of the Michigan Dental Association (MDA) with email addresses were asked to complete the survey online, and a random sample of MDA members without email addresses was invited to complete a paper version of the same survey. All Michigan members of the American Society for Radiation Oncology (ASTRO) were invited to complete an online version of the survey modified for radiation oncologists. The response rate for dentists was 47.9% and radiation oncologists was 22.3%. Of the dentists who responded, 81% reported that a major barrier to providing dental treatment before radiotherapy was a lack of time between initial dental consultation and the start of radiation; inadequate communication between health care providers was blamed most frequently for this. Ten percent of the dentists and 25% of the radiation oncologists reported that they did not treat HNC patients because they lacked adequate training, and 55% of

A precursive study of the time-domain survey of the Galactic Anti-center using the Nanshan 1-meter telescope with variable stars detected

Science.gov (United States)

Ma, Shu-Guo; Esamdin, Ali; Ma, Lu; Niu, Hu-Biao; Fu, Jian-Ning; Zhang, Yu; Liu, Jin-Zhong; Yang, Tao-Zhi; Song, Fang-Fang; Pu, Guang-Xin

2018-04-01

Following the LAMOST Spectroscopic Survey and the Xuyi's Photometric Survey of the Galactic Anti-center, we plan to carry out a time-domain survey of the Galactic Anti-center (TDS-GAC) to study variable stars by using the Nanshan 1-meter telescope. Before the beginning of TDS-GAC, a precursive sky survey (PSS) has been executed. The goal of the PSS is to optimize the observation strategy of TDS-GAC and to detect some strong transient events, as well as to find some short time-scale variable stars of different types. By observing a discontinuous sky area of 15.03 deg2 with the standard Johnson-Cousin-Bessel V filter, 48 variable stars are found and the time series are analyzed. Based on the behaviors of the light curves, 28 eclipsing binary stars, 10 RR Lyraes, 3 periodic pulsating variables of other types have been classified. The rest 7 variables stay unclassified with deficient data. In addition, the observation strategy of TD-GAC is described, and the pipeline of data reduction is tested.

An aerial radiological survey of the Oak Ridge Reservation and surrounding area, Oak Ridge, Tennessee

International Nuclear Information System (INIS)

Maurer, R.J.

1989-09-01

An aerial radiological survey of the Oak Ridge Reservation (ORR) and surrounding area in Oak Ridge, Tennessee, was conducted from September 12--29, 1989. The purpose of the survey was to measure and document the site's terrestrial radiological environment for use in effective environmental management and emergency response planning. The aerial survey was flown at an altitude of 91 meters (300 feet) along a series of parallel lines 152 meters (500 feet) apart. The survey encompassed an area of 440 square kilometers (170 square miles) as defined by the Tennessee Valley Authority Map S-16A of the entire Oak Ridge Reservation and adjacent area. The results of the aerial survey are reported as inferred exposure rates at 1 meter above ground level (AGL) in the form of a radiation contour map. Typical background exposure rates were found to vary from 5 to 14 microroentgens per hour (μR/h). The man-made radionuclides, cobalt-60, cesium-137, and protactinium-234m (a radioisotope indicative of depleted uranium), were detected at several facilities on the site. In support of the aerial survey, ground-based exposure rate and soil sample measurements were obtained at several locations within the survey boundary. In addition to the large scale aerial survey, two special flyovers were requested by the Department of Energy. The first request was to conduct a survey of a 1-mile x 2-mile area in south Knoxville, Tennessee. The area had been used previously to store contaminated scrap metals from operations at the Oak Ridge site. The second request was to fly several passes over a 5-mile length of railroad tracks leading from the Oak Ridge Y-12 Plant, north through the city of Oak Ridge. The railroad tracks had been previously used in the transport of cesium-137

Epidemiological surveys on the effects of low-level radiation dose: a comparative assessment

International Nuclear Information System (INIS)

Rose, K.S.B.

1988-01-01

In this report, the health effects of low-level doses of radiation are considered by reference to published epidemiological surveys. The work was carried out with three objectives in mind: 1. to provide a comprehensive and critical review of the subject; 2. to seek consistent indications of particular health effects by collating results and comparing with those from surveys at moderate-level doses; 3. to provide an authoritative view on the epidemiology of low-level radiation-induced health effects. Vol E (DRAFT A) is appended and contains group collation tables. Epidemiological surveys can be conveniently divided into four classes (A, B, C, D) according to the phase of life when irradiation occurs or the effect is diagnosed. The first of the classes (A) is addressed here; this class is concerned with possible effects arising from radiation received by a parent before conception. Possible effects of preconception irradiation were identified under four broad groupings. These are Down's syndrome, ''Indicators of Reproductive Damage'' (mainly Primary Sterility, Congenital Abnormalities, Sex Ratio, Fetal Mortality, Infant Mortality), Childhood Malignancies, and Chromosomal Changes in Abortuses. Information about each survey, and comparisons with results from moderate-level dose surveys, are contained in synopses that are set out in the Appendix. (author)

Development of gamma probe for radiation surveys of the bottoms of surface waters

International Nuclear Information System (INIS)

Lee, D.R.; Welch, S.J.; St Aubin, M.J.; Dal Bianco, R.

1992-01-01

We have developed a practical method for mapping variations in gamma activity and electrical conductivity of submerged sediments. Prototype probes are being constructed and tested. The first prototype was essentially a background survey meter (Jones, 1979) packaged in a 53-cm-long by 5.4-cm-diameter waterproof vehicle. This tubular vehicle was towed by boat in contact with the bottom sediments of lakes and rivers. Originally, this vehicle was designed (and is still frequently used) for locating groundwater and contaminant entry areas in surface waters. By logging geographic position and sediment variables, it has been possible to produce contour maps in areas of interest. Thus it is possible to optimize environmental analysis and avoid the 'hit or miss' approach of traditional bottom-sediment surveys. (author)

Results of the 2004 Association of Residents in Radiation Oncology (ARRO) Survey

International Nuclear Information System (INIS)

Patel, Shilpen; Jagsi, Reshma; Wilson, John; Frank, Steven; Thakkar, Vipul V.; Hansen, Eric K.

2006-01-01

Purpose: The aim of this study was to document adequacy of training, career plans after residency, use of the in-service examination, and motivation for choice of radiation oncology as a specialty. Methods and Materials: In 2004, the Association of Residents in Radiation Oncology (ARRO) conducted a nationwide survey of all radiation oncology residents in the United States. Results: The survey was returned by 297 residents (response rate, 54%). Of the respondents, 29% were female and 71% male. The most popular career choice was joining an established private practice (38%), followed by a permanent academic career (29%). Residents for whom a permanent academic career was not their first choice were asked whether improvements in certain areas would have led them to be more likely to pursue an academic career. The most commonly chosen factors that would have had a strong or moderate influence included higher salary (81%), choice of geographic location (76%), faculty encouragement (68%), and less time commitment (68%). Of respondents in the first 3 years of training, 78% believed that they had received adequate training to proceed to the next level of training. Of those in their fourth year of training, 75% believed that they had received adequate training to enter practice. Conclusions: Multiple factors affect the educational environment of physicians in training. Data describing concerns unique to resident physicians in radiation oncology are limited. The current survey was designed to explore a variety of issues confronting radiation oncology residents. Training programs and the Residency Review Committee should consider these results when developing new policies to improve the educational experiences of residents in radiation oncology

Identifying Potential Markets for Behind-the-Meter Battery Energy Storage: A Survey of U.S. Demand Charges

Energy Technology Data Exchange (ETDEWEB)

McLaren, Joyce A [National Renewable Energy Laboratory (NREL), Golden, CO (United States); Gagnon, Pieter J [National Renewable Energy Laboratory (NREL), Golden, CO (United States); Mullendore, Seth [Clean Energy Group, Montpelier, Vermont

2017-08-07

This paper presents the first publicly available comprehensive survey of the magnitude of demand charges for commercial customers across the United States -- a key predictor of the financial performance of behind-the-meter battery storage systems. Notably, the analysis estimates that there are nearly 5 million commercial customers in the United States who can subscribe to retail electricity tariffs that have demand charges in excess of $15 per kilowatt (kW), over a quarter of the 18 million commercial customers in total in the United States. While the economic viability of installing battery energy storage must be determined on a case-by-case basis, high demand charges are often cited as a critical factor in battery project economics. Increasing use of demand charges in utility tariffs and anticipated future declines in storage costs will only serve to unlock additional markets and strengthen existing ones.

The current state of radiation education in schools and results of the opinion survey on radiation

International Nuclear Information System (INIS)

Murai, Kenji

2013-01-01

In 2008, a new guideline about radioactivity was added to the government guidelines for teaching junior high school science. Since then people involved with school education have been trying to spread correct information about radioactivity. On the other hand, people's confusion in the aftermath of the Fukushima Daiichi Nuclear Power Plant accident has clearly shown that people do not know much about radioactivity. Considering the situation, the author conducted an investigation about the current state of radiation education and carried out an opinion survey about radioactivity among adults. The investigation about education showed the following: (1) the nature of radiation, such as its permeability, and its uses were described in the government-approved textbooks; (2) basic knowledge, such as what are radiation effects, were described comprehensively in the supplementary reading recommendations made by the Ministry of Education, Culture, Sports, Science, and Technology; and (3) locale education committees created teaching materials such as guidance to present topics. The opinion survey had questions to judge: (1) current public understanding of radioactivity; (2) the degree of general information that people collected for themselves; (3) the degree of specific knowledge about radioactivity that people had; and (4) people's attitudes toward various problems with radioactivity in the environment. The results suggested that for radiation education the following items are important: (1) to learn that radioactivity exists in people's daily lives and is used safely in various field; (2) to get basic knowledge and better quantitative understanding of such things as radioactivity units, radiation dose and radiation effects; and (3) to acquire practical experience to use the information effectively. (author)

A knowledge and awareness level survey of radiation protection among the radiation workers in Henan Province

International Nuclear Information System (INIS)

Cheng, Xiao-jun; Tian, Chong-bin; Zhang, Qin-fu; Liu, Cheng; Ding, Li

2008-01-01

Full text: Objective: To reveal the knowledge and awareness level of radiation protection among radiation workers in Henan province and to explore the methods to improve it. Methods: A questionnaire survey was carried out among 208 radiation workers. Results: The correct rate of the answer to radiation protection knowledge from radiation workers in Henan province is 53.78%. Most of them (88.9%) realized that it is important to protect patients and their companions. They adhere to the principles of justification of medial exposure and optimization of radiation protection and follow the management system of radiation protection. However, a few workers didn't follow the principles strictly. Sometime, during the radio diagnosis and radiotherapy services, the patients and their companions were not well protected from the radiation, and some patients were given unnecessary X-ray examine. Even worse, some workers did not attach importance to the regulations of radiation protection and disobey them frequently. Again, some hospital leaders disregard the regulation of radiation protection and didn't follow the regulation of health surveillance and radiation protection monitoring properly. And those behaviors and attitude, in fact, influence some workers' attitude to radiation protection. Conclusion: The level of radiation protection knowledge and awareness among the radiation workers in Henan province needs to be improved. It is necessary to strengthen radiation protection knowledge by strengthening training, and to improve safety awareness among the radiation staff, and, more important, the hospital leaders as well. (author)

Conducted interference on smart meters

NARCIS (Netherlands)

Keyer, Cornelis H.A.; Leferink, Frank

2017-01-01

The increasing conducted interference caused by modern electronic equipment is causing more problems for electronic, or static, energy meters. These meters are called smart meters when equipped with a communication link, and are replacing the conventional electromechanical meters. It is known that

Instrument evaluation no. 10. Scanray radiation meter type 751

CERN Document Server

Burgess, P H; White, D F

1978-01-01

The various radiations encountered in radiological protection cover a wide range of energies and radiation measurements have to be carried out under an equally broad spectrum of environmental conditions. This report is one of a series intended to give information on the performance characteristics of radiological protection instruments, to assist in the selection of appropriate instruments for a given purpose, to interpret the results obtained with such instruments, and, in particular, to know the likely sources and magnitude of errors that might be associated with measurements in the field. The radiation, electrical and environmental characteristics of radiation protection instruments are considered together with those aspects of the construction which make an instrument convenient for routine use. To provide consistent criteria for instrument performance, the range of tests performed on any particular class of instrument, the test methods and the criteria of acceptable performance are based broadly on the a...

Radiometric survey in mammography: problems and challenges; Levantamento radiometrico em mamografia: problemas e desafios

Energy Technology Data Exchange (ETDEWEB)

Navarro, M.V.T.; Navarro, V.C.C.; Garcia, I.F.M.; Ferreira, M.J.; Macedo, E.M., E-mail: navarro@ifba.edu.br [Instituto Federal da Bahia (LABPROSAUD/IFBA), Salvador, BA (Brazil). Laboratorio de Produtos para a Saude

2015-07-01

In addition to being mandatory, the radiometric survey is a necessity, especially in the Brazilian reality with the construction of smaller and smaller rooms. However, calibration conditions, the instrumentation and its use, can produce underestimated factors. Measures made at Labprosaud/IFBA, with five different instruments and the ISO N 25 radiation quality, show the possibility of the values presented in the radiometric surveys are underestimated by up to 10 times. The results indicate the need for meters to be calibrated in ISO N qualities, in mammography energy range, in integrated dose mode and exposure times shorter or equal to 1 s. (author)

Development of low cost wireless radiation monitoring station using GSM network

International Nuclear Information System (INIS)

Nur Aira Abd Rahman; Mohd Ashhar Khalid; Nor Arymaswati Abdullah; Roslan Md Dan

2006-01-01

SMS or Short Message Service is a mean of GSM wireless communication that allow text messages to be sent to and from mobile cell phones. While SMS communication is mainly utilized at personal level or person to person basis; the usage of SMS can be extended into nuclear application specifically in radiation monitoring. This paper explains the development of a wireless station assembled by using a recycled Siemens M50 cell phone as substitutes to GSM modem, a PIC micro controller, and MINT-ISG home made digital survey meter at the remote transmitting site. While at the receiving end; an online monitoring system is set-up by using a Bluetooth enabled cell phone, a Bluetooth dongle, and a PC with Labview 8.0 software written as the Data logger which also served as the PC-Bluetooth interface platform. Wireless station at the remote area operates by continuously sending SMS in every 3 minutes to a predefined cellular number located at the monitoring system. The SMS consists of 6 data which individually is a survey meter readings recorded at each 30 seconds duration. At the receiver, Data logger program will retrieve the SMS from the cell phone via Bluetooth and extract the original 6 readings to be displayed on PC. The system has been successfully tested to detect and log radiation data for extended period of time. (Author)

Relation between size of contrast meter and radiographic density difference for radiographic test aluminium welds

International Nuclear Information System (INIS)

Senda, Tomio; Hirayama, Kazuo; Masaoka, Naotoshi; Fujita, Minoru.

1977-01-01

The influence of contrast meter with difference surface area (5.0 mm x 5.0 mm, 10.0 mm x 10.0 mm, 15.0 mm x 15.0 mm, 30.0 mm x 30.0 mm) and separated type on radiographic density difference (Δ D) were investigated for radiographic test of aluminum welds. It was found that the effect of scattered radiation on contrast meter represented highest at test specimen thickness of 20 mm, and Δ D was constant as the size was increased from 10.0 mm x 10.0 mm to 15.0 mm x 15.0 mm for aluminum contrast meter. For this reason, a proposal of the contrast meter with 10.0 mm x 10.0 mm (surface area) has made to replace (15.0 mm x 15 mm) at amendment of JIS Z 3105. (auth.)

'Radiation Fair' for 15 years in Osaka, Japan, and survey of the participants attitude toward radiation

International Nuclear Information System (INIS)

Furuta, Masakazu; Asano, Takeyoshi; Hayashi, Toshio; Hosokawa, Yasushi; Kakefu, Tomohisa; Nishihara, Hideaki

1999-01-01

We have been successfully operating 'Radiation Fair--The relationship between daily life and radiation--' during summer vacation season in August every year for 15 years in Osaka, the largest city of western Japan. The purpose of this event is radiation education of public including school kids through efficient information transfer of radiation and radiation-related technology. Currently we set up the space of it on a floor of Kintetsu Department Store, one of the major department stores in downtown Osaka and display various irradiated products available in our daily life together with explanatory panels. We have been devising various attractions as efficient information transfer media so that even elementary-school kids understand the basic knowledge of radiation and irradiation technologies. The number of participants has increased year by year until more than 20,000 in recent years. We distributed questionnaires to the visitors for recent 3 years to inquire their status toward radiation and irradiated products as well as impression toward the displays. The survey results suggest that school education may contribute to establish the public image toward 'radiation' as well as mass media. (author)

An Improved Measurement Method for the Strength of Radiation of Reflective Beam in an Industrial Optical Sensor Based on Laser Displacement Meter

Directory of Open Access Journals (Sweden)

Youngchul Bae

2016-05-01

Full Text Available An optical sensor such as a laser range finder (LRF or laser displacement meter (LDM uses reflected and returned laser beam from a target. The optical sensor has been mainly used to measure the distance between a launch position and the target. However, optical sensor based LRF and LDM have numerous and various errors such as statistical errors, drift errors, cyclic errors, alignment errors and slope errors. Among these errors, an alignment error that contains measurement error for the strength of radiation of returned laser beam from the target is the most serious error in industrial optical sensors. It is caused by the dependence of the measurement offset upon the strength of radiation of returned beam incident upon the focusing lens from the target. In this paper, in order to solve these problems, we propose a novel method for the measurement of the output of direct current (DC voltage that is proportional to the strength of radiation of returned laser beam in the received avalanche photo diode (APD circuit. We implemented a measuring circuit that is able to provide an exact measurement of reflected laser beam. By using the proposed method, we can measure the intensity or strength of radiation of laser beam in real time and with a high degree of precision.

Net metering study of switching effects on electromechanical meters[Report prepared for the Measurement Canada Electricity Net Metering Project

Energy Technology Data Exchange (ETDEWEB)

Van Overberghe, L. [Measurement Canada, London, ON (Canada)

2006-03-03

The feasibility of introducing net metering in the electricity sector was evaluated with particular reference to a project administered by Measurement Canada and Electro-Federation Canada (MicroPower Connect) in collaboration with Natural Resources Canada. The objective of the Measurement Canada Electricity Net Metering Project is to identify and eliminate the barriers introduced by the Electricity and Gas Inspection Act regarding the introduction of net metering. The purpose was to design a device that would allow rotation reversal in a residential electromechanical single phase meter. The device should approximate any fluctuations found in a typical net metering system. A series of tests were conducted to understand the influences, on errors, of forward-to-reverse and reverse-to-forward transitions, specifically to find evidence of error migration and mechanical stress. The project was designed to find and measure the effects of forward reverse switching on an electromechanical meter resulting from a change in energy flow. Twenty metres were calibrated in the forward direction in series from light load to high load. Power factor was not adjustable. Test points were then applied in both the forward and reverse directions. The exercise yielded individual errors which were aggregated to show average found errors after 3,000 transitions. Small shifts in errors were apparent and there was no evidence to support a disk flutter theory. refs., tabs., figs.

Digital readout alpha survey instrument

International Nuclear Information System (INIS)

Jacobs, M.E.

1976-01-01

A prototype solid-state digital readout alpha particle survey instrument has been designed and constructed. The meter incorporates a Ludlum alpha scintillator as a detector, digital logic circuits for control and timing, and a Digilin counting module with reflective liquid crystal display. The device is used to monitor alpha radiation from a surface. Sample counts are totalized over 10-second intervals and displayed digitally in counts per minute up to 19,999. Tests over source samples with counts to 15,600 cpm have shown the device to be rapid, versatile and accurate. The instrument can be fabricated in one man-week and requires about $835 in material costs. A complete set of drawings is included

A patient dose survey for femoral arteriogram diagnostic radiographic examinations using a dose-area product meter

International Nuclear Information System (INIS)

Thwaites, J.H.; Rafferty, M.W.; Gray, N.; Black, J.; Stock, B.

1996-01-01

A patient dose survey was carried out for femoral arteriogram procedures at the Sir Charles Gairdner Hospital. The procedure involves fluoroscopy to the pelvic region to locate a guide wire and catheter, followed by a series of radiographs extending from the pelvic area to the feet to form a collage image of the entire arterial system. Radiographs are taken whilst a bolus of contrast media is injected into the arterial system. A dose-area product meter was used to determine the dose-area product delivered to patients. Radiographic and patient details were logged with dose-area product for each part of each procedure. Mean energy imparted, mean effective dose and effective dose equivalent are calculated for the examinations. Calculated effective doses are shown to produce results consistent with those of other authors. We present a method for dealing with a complex radiographic procedure including multiple radiographs and fluoroscopy in an attempt to provide a simple way of calculating effective dose from which a general risk factor can be determined. The effective dose varies considerably from examination to examination due to the large range in the number of radiographs taken in any one procedure. A useful index can be obtained by logging the number of radiographs in each region, and fluoroscopy time, from which the effective dose may be easily calculated. These measurements extend a continuing survey of doses for common diagnostic radiographic examinations which previously included the simple examinations: lumbar spine, abdoment and pelvis. (author)

ISO radiation protection standards

International Nuclear Information System (INIS)

Becker, K.; West, N.

1981-01-01

After a brief description of the International Organization for Standardization (ISO) and its Technical Committee (TC) 85 ''Nuclear Energy'', the work of its Sub-Committee (SC) 2 ''Radiation Protection'' is described in some detail. Several international standards on subjects closely related to radiation protection have already been published, for example ISO-361 (Basic radiation protection symbol), ISO-1757 (Photographic dosimeters), ISO-1758 and 1759 (Direct and indirect-reading pocket exposure meters), ISO-2889 (Sampling of airborne radioactive materials), ISO-4037 (X and gamma reference radiations for calibration) and ISO-4071 (Testing of exposure meters and dosimeters). TC 85/SC 2 has currently eight active Working Groups (WG) dealing with 14 standards projects, mostly in advanced stages, in such fields as neutron and beta reference radiations, and X and gamma radiations of high and low dose-rates and high energies for calibration purposes, reference radiations for surface contamination apparatus, ejection systems for gamma radiography apparatus, industrial and laboratory irradiators, lead shielding units, protective clothing, thermoluminescence dosemeters, radioelement gauges, and surface contamination and decontamination. (author)

Contemporary management of stage i testicular seminoma: a survey of Canadian radiation oncologists

Science.gov (United States)

Samant, R.; Alomary, I.; Genest, P.; Eapen, L.

2008-01-01

Recently published studies clearly indicate that there are now several acceptable options for managing stage i testicular seminoma patients after orchiectomy. We therefore decided to survey Canadian radiation oncologists to determine how they currently manage such patients and to compare the results with previous surveys. Our results demonstrate that adjuvant single-agent chemotherapy is being considered as an option by an increasing proportion of radiation oncologists (although it is not considered the preferred option), the routine use of radiotherapy is declining, and surveillance is becoming increasingly popular and is recommended most often. PMID:18769613

Noninvasive method for the calibration of the peak voltage (kVp) meters

International Nuclear Information System (INIS)

Macedo, E.M.; Navarro, M.V.T.; Pereira, L.; Garcia, I.F.M.; Navarro, V.C.C.

2015-01-01

Quality control in diagnostic radiology is one of the mechanisms that minimize radiation exposure, and the measurement of tube voltage is one of the main test in these procedures. So, the calibration of non-invasive tube voltage meters is essential to maintain the metrological reliability of quality control tests. Thus, this work describes the implementation of the calibration methodology of the quantity tube peak voltage by the substitution method, using non-invasive standard meter, at LABPROSAUD-IFBA. The results showed great performance and when compared with calibrations by invasive methods, showed maximum difference of 4%, contemplated in the uncertainty ranges of the calibrations. (author)

Identification of high-energetic particles by transition radiation

International Nuclear Information System (INIS)

Struczinski, W.

1986-01-01

This thesis gives a comprehensive survey on the application of the transition radiation for the particle identification. After a short historical review on the prediction and the detection of the transition radiation its theoretical foundations are more precisely explained. They form the foundations for the construction of an optimal transition radiation detector the principal construction of which is described. The next chapter shows some experiments by which the main predictions of the transition-radiation theory are confirmed. Then the construction and operation of two transition-radiation detectors are described which were applied at the ISR respectively SPS in the CERN in Geneva in complex experiments. The detector applied at the ISR served for the e ± identification. With two lithium radiators which were followed by xenon-filled proportional chambers an e/π separation of ≅ 10 -2 could be reached. The transition-radiation detector applied in the SPS was integrated into the European Hybrid Spectrometer. It served for the identification of high-energetic pions (> or approx. 90 GeV) against kaons and protons. With twenty units of carbon-fiber radiators which were followed by xenon-filled proportional chambers a π/K, p separation of better than 1:20 for momenta above 100 GeV could be reached. The cluster-counting method is then presented. Finally, a survey on the contemporary status in the development of transition-radiation detectors for the e/π separation is given. It is shown that by an about half a meter long detector the radiators of which consist of carbon fibers an e/π separation in the order of magnitude of ≅ 10 -2 can be reached. (orig./HSI) [de

Perceptions and practices regarding women's vaginal health following radiation therapy: A survey of radiation oncologists practicing in the United States.

Science.gov (United States)

Kachnic, Lisa A; Bruner, Deborah W; Qureshi, Muhammad M; Russo, Gregory A

Vaginal stenosis (VS) is a recognized complication of pelvic and vaginal radiation therapy (RT). A 26-item survey assessing the signs/symptoms, risk factors, diagnosis, prevention, treatment, and impact of VS on women's sexual health was distributed to radiation oncologists. Descriptive statistics were calculated. Chi-square tests examined differences in categorical responses. A total of 233 (10.5%) participants completed the entire survey. Twelve percent, 21%, and 68% report treating gynecologic (GYN) tumors only, non-GYN pelvic tumors only, or both, respectively. Regarding risk factors, 78% believed that VS can be caused by pelvic RT alone, 91% by vaginal brachytherapy alone, and 98% by combined pelvic RT and vaginal brachytherapy. Approximately one-half of respondents felt that being postmenopausal and having a hysterectomy before radiation therapy were risk factors for VS, whereas the other half felt that these were not risk factors. All respondents agreed that VS is a clinical diagnosis. Respondents indicated that VS symptoms include dyspareunia, vaginal pain, dryness, and/or bleeding (100%, 90%, 85%, and 72%, respectively); 65% indicated all 4. The most commonly recommended treatment for VS is vaginal dilator use. Radiation oncologists who treat GYN-only versus non-GYN cancers were more likely to perform a vaginal examination, to distribute written instructions regarding vaginal dilator use (P = .002), to have vaginal bleeding reported after RT (P = .001), and to refer patients to a sexual counselor (P = .007). Most providers (73%) expressed willingness to participate in prospective research on the diagnosis and treatment of VS. This is the first large-scale survey of radiation oncologists' perceptions and practices regarding VS. There is agreement among providers regarding the signs/symptoms of VS and strategies for its prevention/treatment using vaginal dilators. Further prospective and observational research is needed. This survey shows a willingness on

Field Surveys of Non-Residential Solar Water Heating Systems in Taiwan

Directory of Open Access Journals (Sweden)

Kung-Ming Chung

2012-02-01

Full Text Available To develop indigenous alternative and renewable energy resources, long-term subsidy programs (1986–1991 and 2000–present for solar water heaters have been enforced in Taiwan. By the end of 2010, the total installed area of solar collectors had exceeded 2 million square meters. However, over 98% of solar water heaters were used in residential systems for hot water production, with the areas of installed solar collector being less than 10 square meters. There were only 98 systems with area of solar collectors installed exceeding 100 square meters put into operation from 2001 to 2010. These systems were mainly installed for water heating in dormitories, swimming pools, restaurants, and manufacturing plants. In the present study, a comprehensive survey of these large-scale solar water heaters was conducted. The objectives of the survey were to assess the system performance and to collect feedback from individual users. It is found that lack of experience in system design and maintenance are the key factors affecting reliable operation of a system. Hourly, daily and long-term field measurements of a dormitory system were also examined to evaluate its thermal efficiencies. Results indicated that thermal efficiency of the system is associated with the daily solar radiation. Hot water use pattern and operation of auxiliary heater should be taken into account in system design.

A microprocessor based mobile radiation survey system

International Nuclear Information System (INIS)

Gilbert, R.W.; McCormack, W.D.

1984-01-01

A microprocessor-based system has been designed and constructed to enhance the performance of routine radiation surveys on roads within the Hanford site. This device continually monitors system performance and output from four sodium iodide detectors mounted on the rear bumper of a 4-wheel drive truck. The gamma radiation count rate in counts-per-second is monitored, and a running average computed, with the results compared to predefined limits. If an abnormal instantaneous or average count rate is detected, an alarm is sounded with responsible data displayed on a liquid crystal panel in the cab of the vehicle. The system also has the capability to evaluate detector output using multiple time constants and to perform more complex tests and comparison of the data. Data can be archived for later analysis on conventional chart recorders or stored in digital form on magnetic tape or other digital storage media

Studies of Nagasaki (Japan) children exposed in utero to the atomic bomb: a roentgenographic survey of the skeletal system. Response of human beings accidentally exposed to significant fall-out radiation

Energy Technology Data Exchange (ETDEWEB)

Sutow, W W; West, E; Cronkite, E P; Conard, R A; Farr, R S; Browning, E; Bond, V P; Shulman, R; Cohn, S H

1959-01-01

This document contains 2 reports. In the first report, a roentgenographic survey of the skeletal system was made on 74 children who were exposed in utero to the atomic bomb explosion in Nagasaki, Japan at distances under 2000 meters from the hypocenter. The findings were compared with those on a group of 91 children also exposed while in utero to the bomb but at distances of 4000 to 5000 meters. No differences in the incidence of skeletal abnormalities were found between the two groups. In the second report, a description of injuries suffered due to fallout after the explosion of a thermonuclear device on the Marshall Islands is presented. Marshallese and Americans were accidentally exposed on islands in this area, receiving whole-body gamma radiation, beta radiation injury to skin, and minimal internal contamination. The highest dose (an estimated 175 r) was received by a group of 64 Marshallese. The dose of radiation received proved to be sublethal. Though there was significant depression of hemopoiesis, no clinical signs or symptoms developed that could be attributed with certainty to this effect. Skin lesions and epilation developed in 90% of the group beginning about two weeks after the exposure. Minimal amounts of radioactive material were detected in the urine. The internal deposition was insufficient to contribute significantly to the acute reaction, and it is believed there is no long-term hazard. Examinations conducted one year after the exposure revealed these people to be in generally good health. Slight depression of lymphocytes and platelets persisted. A few pigment aberrations and minimal atrophy remained at the site of the deeper skin lesions.

Survey on radiation practices in Korea

International Nuclear Information System (INIS)

2006-06-01

This book introduces outline of the survey with title, purpose, target, timing and composition of statistical data, explanation of terms. It consists of three parts about statistical tables. The first part has state of licensed organizations with number of licensed users by category of organizations, utilization by nuclides and by usage purpose and regional distribution of RI using Hospitals and clinics. The second parts deals with production and import with state of production and import, import by category of organizations and by nuclides and annual trend of production and import. The third part includes radiation safety management with collection of radioactive wastes and annual collect of sealed RI wastes.

Economic and social impacts of converting to tenant metering in multi-family housing

International Nuclear Information System (INIS)

Palermini, D.; Hewitt, D.

1990-01-01

A current trend in the multifamily housing industry is to convert heating (gas and oil) systems to tenant-metered heating systems (electric zonal heat, individual gas furnaces, secondary metering systems for boilers). Moving responsibility for heating costs directly to tenants has been shown to save energy (on the order of 15%). However, there are social and economic aspects of this type of 'energy investment' such as the impact on vacancy rates, rent levels and comfort of tenants. This paper presents the findings from a research project that surveyed the owners and tenants of 37 multifamily buildings (a total of 741 units) that had been converted from central to individual metering. In addition to the behavioral analysis, the authors gathered utility billing data which they analyzed using the Princeton Scorekeeping Method. Survey findings indicate that energy use was decreased substantially by conversion to separate heating systems. Increases in tenant-paid utility bills after conversion were not sufficient to cause hardship for most tenants, even those with modest incomes. Rent and vacancy levels remained stable after the heating system changes were made or an allocation system was installed

Smart metering for Switzerland - Potential, success factors and measures to be taken to increase energy efficiency - Final report; Smart Metering fuer die Schweiz - Potenziale, Erfolgsfaktoren und Massnahmen fuer die Steigerung der Energieeffizienz - Schlussbericht

Energy Technology Data Exchange (ETDEWEB)

Dettli, R.; Philippen, D.; Reinhardt, R. [econcept AG, Zuerich (Switzerland); Schaeffler, H.; Heinemann, Ch. [Forschungsgruppe Energie- und Kommunikationstechnologien EnCT GmbH, Freiburg (Germany)

2009-11-15

This report examines the use of Smart Metering technology and what improvement of energy efficiency could be expected by its wide adoption in whole Switzerland. It examines the effects of feedback applications and of variable tariffs which are made possible with the use of this technology. A summary lists the ongoing system concepts and technologies of Smart Metering, feedback and variable tariffs as well as the general legal requirements for Switzerland. By means of a literature survey the worldwide experiences with feedback and variable tariffs were evaluated and the application of the results regarding their use in Switzerland examined. On this basis, the report lists suggestions for meter manufacturers, energy suppliers, distribution system operators as well as for federal and cantonal authorities as to how to use the Smart Meter technology to its full advantage. (authors)

SSDL for radiation protection of Thailand

International Nuclear Information System (INIS)

Wanitsuksombut, W.

1995-01-01

In Thailand, the Atomic Energy for Peace Act was enacted by the King in 1961, and Office of Atomic Energy for Peace was established to serve as the secretariat of the Atomic Energy for Peace Commission of Thailand. The import and export of radioactive materials, and the owners and users of radioactive materials must be licensed by the OAEP. The program for establishing the SSDL to calibrate radiation protection instruments started in 1981, and was completed in 1990. The calibration of survey meters and direct reading personnel dosimeters has been provided since 1986. The average number of the devices calibrated by the SSDL per month is shown. The categories of radiation utilization in Thailand are nucleonic gauging and control, nondestructive testing, oil and coal logging, radiation technology and research. The capability of the SSDL and the calibrated radiation measuring instruments for respective categories of utilization are reported. The number of the instruments used for radiography was 217, followed by 171 for nucleonic gauging and control. With the increasing use of radioactive materials, the work of radiation safety must be improved. Together with the license authority, the SSDL must expand its activity to assure the safe handling of radiation sources. (K.I.)

The Growth of Academic Radiation Oncology: A Survey of Endowed Professorships in Radiation Oncology

International Nuclear Information System (INIS)

Wasserman, Todd H.; Smith, Steven M.; Powell, Simon N.

2009-01-01

Purpose: The academic health of a medical specialty can be gauged by the level of university support through endowed professorships. Methods and Materials: We conducted a survey of the 86 academic programs in radiation oncology to determine the current status of endowed chairs in this discipline. Results: Over the past decade, the number of endowed chairs has more than doubled, and it has almost tripled over the past 13 years. The number of programs with at least one chair has increased from 31% to 65%. Conclusions: Coupled with other indicators of academic growth, such as the proportion of graduating residents seeking academic positions, there has been clear and sustained growth in academic radiation oncology.

Assessment of terrestrial gamma radiation dose rate (TGRD) of Kelantan State, Malaysia. Relationship between the geological formation and soil type to radiation dose rate

International Nuclear Information System (INIS)

Garba, N.N.; Gabdo, H.T.; Federal College of Education, Yola

2014-01-01

Terrestrial gamma radiation dose rates (TGRD) of Kelantan State were measured in situ using a portable [NaI(TI)] micro roentgen (μR) survey meter. The TGRD rates ranged between 44 and 500 nGy h -1 with a mean value of 209 ± 8 nGy h -1 . The distribution of these measurements in various districts of the state shows the statistically the influence of geology and soil types on the dose rate values. The data obtained could be used in formulating safety standard and radiological guidelines. (author)

The results of complex radiation-hygienic survey of the reference settlements in Mogilev region

International Nuclear Information System (INIS)

Ageeva, T.N.; Chegerova, T.I.; Shchur, A.V.; Shapsheeva, T.P.; Lipnitskij, L.V.

2011-01-01

The results of complex radiation-hygienic survey of the reference settlements located on the radioactively contaminated territory have been presents in the article. The four-year dynamics of the internal exposure doses of the reference settlements' inhabitants and their relationship with the 137 Cs content in foods consumed by the population have been shown. It was ascertained that there are still some isolated individuals with high doses of internal radiation among the surveyed population, which have the significant influence on the average annual radiation dose for the inhabitants and dose of its critical group. The external exposure individual doses of the inhabitants and the results of measuring of the gamma radiation dose rate in place of the settlements have been analyzed. It have been expressed the opinion about need entering adjustment in the measuring techniques of external doses. (authors)

Fundamental principles of rotary displacement meters

Energy Technology Data Exchange (ETDEWEB)

Rosen, J. [Schlumberger Industries, Owenton, KY (United States)

1995-12-01

The gas meter exists to continually and accurately measure the volume of gas supplied over the complete flow range of the load. In effect the gas meter serves as the {open_quotes}cash register{close_quotes} of the gas industry; its accurate and dependable performance ensures fair dealings for both the supplier and the user. An investment both in and of itself, the gas meter should be chosen as a function of its usefullness both over the short term and the long term. Thus in addition to initial cost, one must take into account various associated factors, costs and benefits, including the following: Design Characteristics Application, suitability, Meter features and options, Operation constraints, Installation, Service and maintenance, Repair and replacement, Life expectancy, Compatibility with complimentary products, Correcting devices, Remote reading capabilities, Data generation and gathering, Upgradeabilty. This paper will look at one positive displacement meter, the Rotary meter, and address the fundamentals principals of the technology as well as looking at some of the benefits derived from its application. Rotary positive displacement meters were introduced at the end of last century. Used primarily for metering transmission sized loads, the meters` measuring capabilities have extended to cover nearly all areas of distribution with exception of domestic applications. Rotary meters are available in rated capacities from 800 cfh to 102,000 cfh and operating pressures from 175 PSIG to 1440 PSIG. The use of rotary meters on load ranges in the 800 to 10,000 cfh category has increased and is replacing the use of diaphragm meters because of the smaller relative size of rotaries, and improvements in rangeabilities in the last few years. Turbine meters are usually the meter of choice on loads over 16,000 cfh unless a meter with high rangeability is required because of varying load characteristics, in which case a large foot mounted rotary might still be selected.

Lead exposure in radiator repair workers: a survey of Washington State radiator repair shops and review of occupational lead exposure registry data.

Science.gov (United States)

Whittaker, Stephen G

2003-07-01

Radiator repair workers in Washington State have the greatest number of very elevated (> or =60 microg/dL) blood lead levels of any other worker population. The goals of this study were to determine the number of radiator repair workers potentially exposed to lead; estimate the extent of blood lead data underreporting to the Occupational Lead Exposure Registry; describe current safety and health practices in radiator repair shops; and determine appropriate intervention strategies to reduce exposure and increase employer and worker awareness. Lead exposure in Washington State's radiator repair workers was assessed by reviewing Registry data and conducting a statewide survey of radiator repair businesses. This study revealed that a total of 226 workers in Washington State (including owner-operators and all employees) conduct repair activities that could potentially result in excessive exposures to lead. Approximately 26% of radiator repair workers with elevated blood lead levels (> or =25 microg/dL) were determined to report to Washington State's Registry. This study also revealed a lack of awareness of lead's health effects, appropriate industrial hygiene controls, and the requirements of the Lead Standard. Survey respondents requested information on a variety of workplace health and safety issues and waste management; 80% requested a confidential, free-of-charge consultation. Combining data derived from an occupational health surveillance system and a statewide mail survey proved effective at characterizing lead exposures and directing public health intervention in Washington State.

Evaluation of integrity of radiation sources of nuclear gauges; Avaliacao da integridade de fontes radioativas de medidores nucleares

Energy Technology Data Exchange (ETDEWEB)

Torohate, Wiclif Francisco

2016-11-01

Nuclear equipment meters are mainly used in the industry in quality control and process control. The principle of operation consists in a shielded radioactive source together with a radiation detector such that the radiation interacts with the material to be analyzed before reaching the detector, providing real time data. Can be as their fixed and mobile mobility, the unique properties of ionizing radiation are used in three basic modes, transmission, backscatter or dispersion or induced (reactive). With the advancement and technological modernization in the world, the demand for nuclear gauges becomes increasingly larger. Currently in Brazil there are about 465 process control plants and 21 portable systems and Mozambique about 45 facilities using nuclear gauges. This font registration is done through a process called source inventory that allows also to know the category of the source, the danger or risk to human health that the source offers. The handling of this equipment requires personnel, certified, skilled and well trained in radiation protection area in accordance with the requirements of the various CNEN Rules. Due to the presence of radioactive source and because these devices are used by workers risk because there external radiation. In this context, we made the smear test in two fixed meters from the IRD industry laboratory, which determines the integrity of the source package, mandatory item in periodic integrity testing of the radiation source of this type of device. A set of procedures is made for its implementation as an evaluation of the radiological risk by radiological survey. It was intended to contribute to the learning handling and safe use of these meters. (author)

A questionnaire survey about public's image of radiation after the Fukushima Dacha Nuclear Power Plant accident

International Nuclear Information System (INIS)

Okazaki, Ryuji; Ootsuyama, Akira; Kubo, Tatsuhiko; Abe, Toshiaki

2012-01-01

A questionnaire survey about the public's image of radiation was performed after the Fukushima Daiichi nuclear power plant (FDNPP) accident. The survey was taken by general citizens (200 and 1,640 in Fukushima and 52 outside of Fukushima) and doctors (63 in Fukushima and 1,942 outside of Fukushima (53 in Oita, 44 in Sagamihara and 1,845 in Kitakyushu) in and outside of Fukushima and second year medical students in the University of Occupational and Environmental Health, Japan. The questionnaire surveys were performed during lectures about radiation. The response rates were 86% for the general citizens in Fukushima, 91% for the general citizens outside of Fukushima, 86% for doctors in Fukushima, 85% and 86% for doctors in Sagamihara and Oita, respectively. The questionnaire surveys were sent to clinics and hospitals in Fukushima where the general citizens answered with a response rate of 50%. When the questionnaire surveys were sent to clinics and hospitals in Kitakyushu, doctors answered, with a response rate of 17%. The percentages of anxiety about future radiation effects after the FDNPP accident were the highest among the general citizens (71.6% in Fukushima and 40.4% outside of Fukushima), in the middle among the doctors (30.2% in Fukushima and 26.2% outside of Fukushima) and the lowest among the medical students (12.2%). The doctors in Fukushima and the medical students were anxious about food and soil pollution. The general citizens and the detectors outside of Fukushima were anxious about health problems and food and soil pollution. We concluded that a high level of education about radiation decreased the anxiety about the radiation effects. It is important to spread knowledge about radiation. (author)

Digital temperature meter

Energy Technology Data Exchange (ETDEWEB)

Glowacki, S

1982-01-01

Digital temperature meter for precise temperature measurements is presented. Its parts such as thermostat, voltage-frequency converter and digital frequency meter are described. Its technical parameters such as temperature range 50degC-700degC, measurement precision 1degC, measurement error +-1degC are given. (A.S.).

Ultrasonic flow meter

NARCIS (Netherlands)

Lötters, Joost Conrad; Snijders, G.J.; Volker, A.W.F.

2014-01-01

The invention relates to an ultrasonic flow meter comprising a flow tube for the fluid whose flow rate is to be determined. The flow meter comprises a transmitting element for emitting ultrasonic waves, which is provided on the outer jacket of the flow tube. A receiving element, which is provided on

Knowledge in Radiation Protection: a Survey of Professionals in Medical Imaging, Radiation Therapy and Nuclear Medicine Units in Yaounde

International Nuclear Information System (INIS)

Ongolo-Zogo, P.; Nguehouo, M.B.; Yomi, J.; Nko'o Amven, S.

2013-01-01

Medical use of ionizing radiation is now the most common radiation source of the population at the global level. The knowledge and practices of health professionals working with X-rays determine the level and quality of implementation of internationally and nationally recommended measures for radiation protection of patients and workers. The level of implementation and enforcement of international recommendations in African countries is an issue of concern due to weak laws and regulations and regulatory bodies. We report the results of a cross-sectional survey of health professionals working with ionizing radiation in Yaounde, the capital city of Cameroon. More than 50% of these professionals have a moderate level of knowledge of the norms and principles of radiation protection and more than 80% have never attended a continuing professional development workshop on radiation protection. (authors)

Investigation of quality assurance routines of DAP-meters in Swedish hospitals; Kartlaeggning av kvalitetssaekringsrutiner foer DAP-maetare i svensk sjukvaard

Energy Technology Data Exchange (ETDEWEB)

Almen, Anja; Grindborg, Jan-Erik; Leitz, Wolfram

2005-11-01

The Swedish Radiation Protection Authority has investigated quality control of dose area product meters (DAP meters) used in x-ray diagnostics. A questionnaire was sent out to medical physics experts who are working with diagnostic radiology in Swedish hospitals. This report presents information about the routines practised and gives examples of measures to improve the quality of these practices.

Radiation safety considerations and compliance within equine veterinary clinics: Results of an Australian survey

International Nuclear Information System (INIS)

Surjan, Y.; Ostwald, P.; Milross, C.; Warren-Forward, H.

2015-01-01

Objective: To examine current knowledge and the level of compliance of radiation safety principles in equine veterinary clinics within Australia. Method: Surveys were sent to equine veterinary surgeons working in Australia. The survey was delivered both online and in hardcopy format; it comprised 49 questions, 15 of these directly related to radiation safety. The participants were asked about their current and previous use of radiation-producing equipment. Information regarding their level of knowledge and application of radiation safety principles and practice standards was collected and analysed. Results: The use of radiation-producing equipment was evident in 94% of responding clinics (a combination of X-ray, CT and/or Nuclear Medicine Cameras). Of those with radiation-producing equipment, 94% indicated that they hold a radiation licence, 78% had never completed a certified radiation safety course and 19% of participants did not use a personal radiation monitor. In 14% of cases, radiation safety manuals or protocols were not available within clinics. Conclusions: The study has shown that knowledge and application of guidelines as provided by the Code of Practice for Radiation Protection in Veterinary Medicine (2009) is poorly adhered to. The importance of compliance with regulatory requirements is pivotal in minimising occupational exposure to ionising radiation in veterinary medicine, thus there is a need for increased education and training in the area. - Highlights: • Application of the Code of Practice for Veterinary Medicine is poorly adhered to. • Majority of veterinary clinics had not completed certified radiation safety course. • One-fifth of participants did not use personal radiation monitoring. • Increased education and training in area of radiation safety and protection required to generate compliance in clinics

Environmental radiation measurements and remedial actions (Hantepe/Ezine/Canakkale)

International Nuclear Information System (INIS)

2009-01-01

There are some regions in the world that are known as high background radiation areas. Intensive scientific investigations in the field of radiation dose and health effects, risk estimates, radiation protection, environmental transportation routes and ecological effects related with natural radiation have been carried out in these regions. Also natural radiation dosimetry, in vitro and in vivo biological studies which take into account the measurements in the field of low level radiation, radon, thoron and cosmic rays have been carried out, again in these regions. The well-known high natural background radiation areas in the world are Guarapari in Brazil, Ramsar in Iran, Kerala in India and Yangjiang in China. In addition to above mentioned areas, other relatively lower high background radiation areas are exist. Since 1960s, radiological, geological, epidemiological and ecological studies have been carried out in order to determine the risks and possible health effects of long-term low level natural radiation exposure. In the framework of surveying the background radiation of Turkey, the background radiation measurements were carried out in 56 different points around the area of Canakkale city. The radiation levels at Hantepe beach of Geyikli which is located in Ezine town of Canakkale was found higher than the mean background radiation level of the region. The radiation dose rates were measured in between 0.20 and 10.88 Gy h-1 in contact and 0.27 and 3.11 Gy h-1 above 1 meter of the ground level where the thorium-containing sand is dense. After the rehabilitation studies, the radiation dose rate were measured in between 0.15 and 8.09 Gy h-1 in contact and 0.17 and 2.88 Gy h-1 above 1 meter of the ground level. It was observed that the radiation dose rates were decreased seriously after the rehabilitation studies when the arithmetic mean value of the dose rates was taken into account. The effective dose calculations were performed by taking into account the

Federal Building Metering Guidance (per 42 U.S.C. 8253(e), Metering of Energy Use)

Energy Technology Data Exchange (ETDEWEB)

None

2014-11-01

Guidance defines which federal buildings are appropriate to meter, provides metering prioritization recommendations for agencies with limited resources, and discusses the requirement for agencies to submit metering implementation plans to the U.S. Department of Energy.

Smart meter status report from Toronto

International Nuclear Information System (INIS)

O'Brien, D.

2006-01-01

An update of Toronto Hydro's smart metering program was presented. Electricity demand is expected to keep increasing, and there is presently insufficient generation to match supply needs in Ontario. The smart metering program was introduced to aid in the Ontario government's energy conservation strategy, as well as to address peak supply problems that have led to power outages. It is expected that the smart metering program will reduce provincial peak supply by 5 per cent, as the meters support both time-of-use rates and critical peak pricing. Over 800,000 smart meters will be supplied to customers by 2007, and all 4.3 million homes in Toronto will have a smart meter by 2010. In order to meet targets for 2010, the utility will continue to install more 15,000 meters each month for the next 4 years. While the Ontario government has planned and coordinated the rollout and developed smart metering specifications and standards, Toronto Hydro is responsible for the purchase, installation, operation and maintenance of the meters. Advance testing of each meter is needed to ensure billing accuracy, and customer education on meter use is also. The complexity of the metering program has led the utility to establish a rigid project management process. Customer education pilot program are currently being conducted. Experience gained during the earlier phases of the program have enabled the utility to select appropriate metering systems based on density, topography and physical conditions. Project expenditures have been within budget due to improved project estimating and planning. The metering program has been conducted in tandem with the utility's peakSAVER program, a residential and small commercial load control program that has been successful in reducing summer peak demand by cycling air conditioners without causing discomfort. It was concluded that the utility will continue with its mass deployment of smart meters, and is currently preparing its call center to handled

Streamlining Smart Meter Data Analytics

OpenAIRE

Liu, Xiufeng; Nielsen, Per Sieverts

2015-01-01

Today smart meters are increasingly used in worldwide. Smart meters are the advanced meters capable of measuring customer energy consumption at a fine-grained time interval, e.g., every 15 minutes. The data are very sizable, and might be from different sources, along with the other social-economic metrics such as the geographic information of meters, the information about users and their property, geographic location and others, which make the data management very complex. On the other hand, ...

Proceedings of the workshop on radiation survey instruments and calibrations

International Nuclear Information System (INIS)

Selby, J.M.; Swinth, K.L.; Vallario, E.J.; Murphy, B.L.

1985-11-01

The workshop was held to discuss two topics: first, a performance standard for radiation survey instruments and the potential for a testing program based on that standard; and second, a system of secondary standards laboratories to provide instrument calibrations and related services. Separate abstracts have been prepared for the individual presentations

Marine chemistry, fish / shell-fish surveys, benthic organisms, and marine toxic substances and pollutants data from current meter and other instruments in the Gulf of Mexico from 1993-01-26 to 1994-06-13 (NODC Accession 9500088)

Data.gov (United States)

National Oceanic and Atmospheric Administration, Department of Commerce — Marine chemistry, fish / shell-fish surveys, benthic organisms, and marine toxic substances and pollutants data were collected using current meter and other...

Application of low-dose radiation protocols in survey CT scans

International Nuclear Information System (INIS)

Fu Qiang; Liu Ting; Lu Tao; Xu Ke; Zhang Lin

2009-01-01

Objective: To characterize the protocols with low-dose radiation in survey CT scans for localization. Methods: Eighty standard adult patients, head and body phantoms were recruited. Default protocols provided by operator's manual setting were that all the tube voltage for head, chest, abdomen and lumbar was 120 kV; the tube currents were 20,10,20 and 40 mA, respectively. Values of kV and mA in the low-dose experiments were optimized according to the device options. For chest and abdomen, the tube position were compared between default (0 degree) and 180 degree. Phantoms were scanned with above protocols, and the radiation doses were measured respectively. Paired t-test were used for comparisons of standard deviation in CT value, noise and exposure surface dose (ESD) between group with default protocols and group with optimized protocols. Results: The optimized protocols in low-dose CT survey scans were 80 kV, 10 mA for head, 80 kV, 10 mA for chest, 80 kV, 10 mA for abdomen and 100 kV, 10 mA for lumbar. The values of ESD for phantom scan in default and optimized protocols were 0.38 mGy/0.16 mGy in head, 0.30 mGy/0.20 mGy in chest, 0.74 mGy/0.30 mGy in abdomen and 0.81 mGy/0.44 mGy in lumbar, respectively. Compared with default protocols, the optimized protocols reduced the radiation doses 59%, 33%, 59% and 46% in head, chest, abdomen and lumbar. When tube position changed from 0 degree to 180 degree, the ESD were 0.24 mGy/0.20 mGy for chest; 0.37 mGy/0.30 mGy for abdomen, and the radiation doses were reduced 20% and 17%. Conclusion: A certain amount of image noise is increased in low-dose protocols, but image quality is still acceptable without problem in CT localization. The reduction of radiation dose and the radiation harm to patients are the superiority. (authors)

Survey of radiation doses received by atomic-bomb survivors residing in the United States

International Nuclear Information System (INIS)

Kerr, G.D.; Yamada, H.; Marks, S.

1976-01-01

A survey has been completed of 300 of an estimated 500 to 750 survivors of the atomic bombings in Hiroshima and Nagasaki who reside in the United States. Distributions with respect to age, sex, citizenship status, distance from the hypocenter at the time of bombing, and dose from immediate weapon radiation have been tabulated from the results and are presented for this group of 300 survivors. Also presented are survey results concerning exposures to residual radiation from fallout and neutron-induced radioactivity in the areas adjacent to the hypocenter

Analysis of current meter records at the northwest atlantic 2800 metre radioactive waste dumpsite. Final report

International Nuclear Information System (INIS)

Hamilton, P.

1982-01-01

In August, 1976, four current meter arrays were deployed for a period of three months at the Atlantic 2800 meter radioactive waste disposal site as part of a scientific survey by the U.S. Environmental Protection Agency to assess the environmental conditions at this formerly used site. The disposal site is located on the Continental Rise and is centered at 38 deg 30' N, 72 deg 06' W. The four arrays were placed in a rectangle near the periphery of the site, each with a current meter 5.1 meters off the bottom, with an additional meter located 96 meters from the bottom at the southwest mooring. The principal findings included a 3-4 cm/s southwesterly mean current observed near the bottom. The low frequency part of the spectrum is explained as bottom trapped topographic Rossby waves. The high frequency motions are dominated by inertial oscillations with a maximum amplitude of about 10 cm/s. The potential for sediment transport during the measurement period is considered very small based on the observed current speeds

Simple meters get smart? Cost benefit analysis of smart metering infrastructure

International Nuclear Information System (INIS)

Van Gerwen, R.J.F.; Jaarsma, S.A.; Koenis, F.T.C.

2005-08-01

The Dutch Ministry of Economic Affairs requested a cost-benefit analysis of the large scale introduction of a smart meter infrastructure for gas and electricity consumption by small consumers. The questions asked in the study need to be answered in order to enable a well-founded evaluation of the implementation of smart meters. [mk] [nl

Metering apparatus and tariffs for electricity supply

International Nuclear Information System (INIS)

1990-01-01

Conference papers presented cover system economies and tariff structure with papers on pricing of electricity and new metering technologies. Other topics reviewed include metering apparatus design, electronic metering apparatus and solid phase metering technology. Meter data retrieval, bulk supply metering, test equipment and maintenance, and legal requirements and standards are discussed. (author)

Cross-cultural differences in meter perception.

Science.gov (United States)

Kalender, Beste; Trehub, Sandra E; Schellenberg, E Glenn

2013-03-01

We examined the influence of incidental exposure to varied metrical patterns from different musical cultures on the perception of complex metrical structures from an unfamiliar musical culture. Adults who were familiar with Western music only (i.e., simple meters) and those who also had limited familiarity with non-Western music were tested on their perception of metrical organization in unfamiliar (Turkish) music with simple and complex meters. Adults who were familiar with Western music detected meter-violating changes in Turkish music with simple meter but not in Turkish music with complex meter. Adults with some exposure to non-Western music that was unmetered or metrically complex detected meter-violating changes in Turkish music with both simple and complex meters, but they performed better on patterns with a simple meter. The implication is that familiarity with varied metrical structures, including those with a non-isochronous tactus, enhances sensitivity to the metrical organization of unfamiliar music.

Multitasking metering enhances generation, transmission operations

Energy Technology Data Exchange (ETDEWEB)

Sullivan, E.

2008-11-15

The Dairyland Power Cooperative (DPC) which operates from La Crosse, Wisconsin has the capacity to generate and transmit 1000 MW of power to 25 member cooperatives and 20 municipalities who serve over 500,000 customers. When DPC was experiencing diminished service within its analog cellular-based data communications system, it was presented with an opportunity to install a new automated telecommunications system that would provide secure collection of meter readings from all of its substations. DPC decided to evaluate an advanced multifunctional digital meter from Schweitzer Engineering Laboratories (SEL). The SEL-734 Revenue Metering System offers complete instantaneous metering functions, including voltages, currents, power, energy and power factor. Other capabilities include predictive demand, time-of-use metering, automatic voltage monitoring, harmonics metering and synchrophasor measurement. From a metering perspective, DPC wanted to perform daily load profiles and interval-by-interval metering of their delivery points for billing purposes. They also wanted to provide real-time monitoring of electricity being delivered for both generation and transmission purposes and to make that information available to a distribution SCADA system for their members. The SEL-734 Revenue Meter was well suited to those needs. The SEL-734 provides very high-accuracy energy metering, load profile data collection, instantaneous power measurements, power quality monitoring, and communicates simultaneously over a modem, serial ports, and wide area networks (WAN). The meter is backed with a ten-year warranty as well as field support engineers. 5 figs.

RAM R-200 - A Portable Ruggedized Radiation Monitoring System

International Nuclear Information System (INIS)

Wengrowicz, U.; Mazor, T.; Assido, H.; Kadmon, Y.; Tirosh, D.; Shani, G.

1999-01-01

RAM R-200, a new generation of ruggedized portable radiation-monitoring systems, is presented. The system which is a result of interdisciplinary research, was developed at the NRCN in collaboration with Ben-Gurion University. It consists of RAM R-200 - a portable radiation meter, and a variety of external probes for wide range gamma radiation fields and beta-gamma contamination detection and measurement. The meter or each one of the external probes can be used as a portable system or a stand-alone radiation measurement station. All the system's components were specially designed to meet severe environmental conditions

Smart meter incorporating UWB technology

NARCIS (Netherlands)

Khan, T.A.; Khan, A.B.; Babar, M.; Taj, T.A.

2014-01-01

Smart Meter is a key element in the evolving concept of Smart Grid, which plays an important role in interaction between the consumer and the supplier. In general, the smart meter is an intelligent digital energy meter that measures the consumption of electrical energy and provides other additional

Good standards for smart meters

NARCIS (Netherlands)

Hoenkamp, R.A.; Huitema, G.B.

2012-01-01

This paper examines what lessons can be learned from the rollout of smart meters in the Netherlands to improve the European smart meter standardization. This study is based on the case of the Dutch meter rollout which preparations started in 2005 but finally was delayed until 2011 by governmental

RFID-BASED Prepaid Power Meter

OpenAIRE

Teymourzadeh, Rozita

2013-01-01

An Electric power meter is an important component in electric energy service. In the past, many consumers have complained about reading inaccurate of the electric meter. This research presents the development of an electrical power meter equipped with RFID reader. The RFID reader reads a valid RFID card and activates the power meter so that it can supply electricity. When the credit is about low or before the electricity is auto cut off, an SMS message will be sent to the user’s handphone to ...

Cancer-meter: measure and cure.

Science.gov (United States)

Kashyap, Sunil Kumar; Sharma, Birendra Kumar; Banerjee, Amitabh

2017-05-01

This paper presents a theory and system on "Cancer-Meter'. This idea came through the statement that "cancer is curable if it is measurable". The Cancer-Meter proves that it is possible. This paper proposes the cancer-meter in two ways, theoretical and electronically, as per the measurement and treatment. By the mathematics, first part is defined but the second part is based on computer programming, electrical and electronics. Thus, the cancer-meter is a programmed-electrical-electronic device which measures and cures the cancer both.

Record of radiation management inside KUR facilities, no. 13 (1976)

International Nuclear Information System (INIS)

Katsurayama, Kosuke; Tsujimoto, Tadashi; Saito, Masahiro; Tsuruta, Takao; Fukui, Masami.

1979-01-01

The record of radiation management inside the KUR buildings in 1976 is reported. Relating to the routine radiation management inside the facilities, the spatial dose rate has been always monitored, utilizing the area monitors which are composed of GM survey meters and BF 3 neutron survey meters, inside the reactor building, the hot laboratory, the tracer building, the waste treatment building, the linear accelerator building, the gamma irradiation building, the solid waste storage and the research building. The measured dose rate at 5000 kW power level was about 2 mrem/h in the reactor building and about 4 mrem/h in the hot laboratory at maximum. Inside the other buildings, the dose rates were almost background level. The cumulative dose was measured utilizing film badges, and the measured maximum value was about 450 mrem in one month in the spent fuel storage pool. The surface contamination was monitored, and about 10 -7 μCi/cm 2 was obtained on the reactor top and in several places in the hot laboratory. The monitoring of radioactivity concentration in water was conducted, and the concentration almost exceeded 1 x 10 -5 μCi/cm 3 in low level water. The monitoring was conducted for radioactive dust concentration, and about 100 x 10 -11 μCi/cm 3 was obtained at maximum in the hot cave. The gas concentration in the reactor room showed about 6 x 10 -7 μCi/cm 3 as the mean value of a month. The external exposure dose around the site was about 2 mrem in one year as the mean value. The status of operation of the KUR, the radiation monitoring systems for spatial dose rate, the cumulative spatial dose, the surface contamination and so on, the monitoring equipments and the regular inspection are explained. (Nakai, Y.)

Privacy friendly aggregation of smart meter readings, even when meters crash

NARCIS (Netherlands)

Hoepman, J.H.

2017-01-01

A well studied privacy problem in the area of smart grids is the question of how to aggregate the sum of a set of smart meter readings in a privacy friendly manner, i.e., in such a way that individual meter readings are not revealed to the adversary. Much less well studied is how to deal with

The 3R-WL working level survey meter

International Nuclear Information System (INIS)

Schiager, K.J.

1977-01-01

The design and operation of a direct-reading sampler for airborne radon progeny are described. The instrument was designed for use by ventilation personnel in uranium mines and is small, rugged, light-weight and easily carried and operated. Direct readout of the radon progeny concentration in units of working levels, in the range 0.01 - 10 WL, is accomplished by counting the alpha particles from 218 Po and 214 Po with a single detector and two energy discrimination channels. Unique features include a fixed-volume, gravity-operated pump requiring no power source and minimal calibration; automatic delay, counting and display sequencing; capacity for more than 50 samples on a single roll of membrane filter; and provisions for recording all data directly on the filter tape. For the prototype as built, calibration against the 2-count alpha spectroscopy method of measuring WL indicated an average error of less than 1% in the range from 0.25 to 25 WL. However, the standard deviation of measurements made with the 3R-WL meter increased from 7% above 10 WL to 71% at 0.25 WL. Sources of error and variability are analyzed and suggestions for improving the precision of the measurements are included. (author)

estimation of background radiation at rivers state university

African Journals Online (AJOL)

DJFLEX

State University of Science and Technology was measured using a specialize digital, radiation meter type, radalert ... KEYWORDS: Radiation, Radalert-50, electronic devices, radiation limit ... electron gun and the back of CRT (Philip and pick,.

Evaluation of area monitor response for neutrons in radiation field generated by a 15 MV clinic accelerator

International Nuclear Information System (INIS)

Salgado, Ana Paula

2011-01-01

The clinical importance and usage of linear accelerators in cancer treatment increased significantly in the last years. Coupled with this growth came the concern about the use of accelerators with energies over to 10 MeV which produce therapeutic beam contaminated with neutrons generated when high-energy photons interact with high-atomic-number materials such as tungsten and lead present in the accelerator itself. At these facilities, measurements of the ambient dose equivalent for neutrons present difficulties owing to the existence of a mixed radiation field and possible electromagnetic interference near the accelerator. The Neutron Laboratory of the IRD - Brazilian Institute for Radioprotection and Dosimetry, aiming to evaluate the survey meters performance at these facilities, initiated studies of instrumentation response in the presence of different neutron spectra. Neutrons sources with average energies ranging from 0.55 to 4.2 MeV, four different survey meters and one ionization chamber to obtain the ratio between the dose due to neutrons and gamma radiation were used in this work. The evaluation of these measurements, performed in a 15 MV linear accelerator room is presented. This work presents results that demonstrate the complexity and care needed to make neutrons measurements in radiotherapy treatment rooms containing high energy clinical accelerators. (author)

Digital reactivity meter

International Nuclear Information System (INIS)

Jiang Zongbing

1996-02-01

The importance and the usual methods of reactivity measurement in a nuclear reactor are presented. Emphasis is put upon the calculation principle, software and hardware components, main specifications, application, as well as the features of the digital reactivity meter. The test results of operation in various reactors shown that the meter possess the following features: high accuracy, short response time, low output noise, high resolution, wide measuring range, simple and flexible to operate, high stability and reliability. In addition, the reactivity meter can save the measuring data automatically and have a perfect capability of self-verifying. It not only meet the requirement of the reactivity measurement in nuclear power plant, but also can be applied to various types of reactors. (1 tab.)

Fifth nationwide survey on radiation oncology of China in 2006

International Nuclear Information System (INIS)

Yin Weibo; Yuyun; Chen Bo; Tian Fenghua

2007-01-01

Objective: In order to find out the present status of Chinese Radiation Oncology, the Chinese Society of Radiation Oncology did the fifth nationwide survey on Radiation Oncology in China. Methods: Questionnaire forms had been sent through the board member of Chinese Society of Radiation Oncology to each center throughout the country. The forms, after filing, were returned for analysis. Results: On September 30th, 2006, there were 952 radiation oncology centers. They possess personnel: 5247 doctors including 2 110 residents, 1181 physicists, 6864 nurses, 4559 technicians and 1141 engineers. For equipment: There were 918 linear accelerators, 472 telecobalt units, 146 deep X-ray machine, 827 simulators, 214 CT simulators, 400 brachytherapy units, 400 treatment planning system, 796 dosimeters, 467 X-knife, 149 γ-knife (74 for head only, 75 for the head and body). Treatment: 35 503 beds (35 centers did not report the number of beds), 42 109 patients treated per day, 409 440 new patients were treated per year (no report from 45 centers). Conclusion: Radiation oncology has been developing rapidly in the last 5 years either in quantity or in quality. They are still being considered insufficient in proportion to our population. Training programs and development of QA and QC system ate needed. (authors)

Smart metering design and applications

CERN Document Server

Weranga, K S K; Chandima, D P

2013-01-01

Taking into account the present day trends and the requirements, this Brief focuses on smart metering of electricity for next generation energy efficiency and conservation. The contents include discussions on the smart metering concepts and existing technologies and systems as well as design and implementation of smart metering schemes together with detailed examples.

'Radiation Fair' for 15 years in Osaka, Japan, and survey of the participants attitude toward radiation

Energy Technology Data Exchange (ETDEWEB)

Furuta, Masakazu; Asano, Takeyoshi; Hayashi, Toshio; Hosokawa, Yasushi [Research Institute for Advanced Science and Technology, Osaka Prefecture Univ., Sakai, Osaka (Japan); Kakefu, Tomohisa; Nishihara, Hideaki

1999-09-01

We have been successfully operating 'Radiation Fair--The relationship between daily life and radiation--' during summer vacation season in August every year for 15 years in Osaka, the largest city of western Japan. The purpose of this event is radiation education of public including school kids through efficient information transfer of radiation and radiation-related technology. Currently we set up the space of it on a floor of Kintetsu Department Store, one of the major department stores in downtown Osaka and display various irradiated products available in our daily life together with explanatory panels. We have been devising various attractions as efficient information transfer media so that even elementary-school kids understand the basic knowledge of radiation and irradiation technologies. The number of participants has increased year by year until more than 20,000 in recent years. We distributed questionnaires to the visitors for recent 3 years to inquire their status toward radiation and irradiated products as well as impression toward the displays. The survey results suggest that school education may contribute to establish the public image toward 'radiation' as well as mass media. (author)

Hydrogen meter prooftesting

International Nuclear Information System (INIS)

McCown, J.J.; Mettler, G.W.

1976-04-01

Two diffusion type hydrogen meters have been tested on the Prototype Applications Loop (PAL). The ANL designed unit was used to monitor hydrogen in sodium during FFTF startup and over a wide range of hydrogen concentrations resulting from chemical additions to the sodium and cover gas. A commercially available meter was added and its performance compared with the ANL unit. Details of the test work are described

Evaluation of management of radioactive waste in nuclear medicine department of radiation and isotopes center, Khartoum

International Nuclear Information System (INIS)

Ahmed, Amel Bushra Abaker

2001-01-01

Evaluation of management of radioactive waste in nuclear medicine department of radiation and isotopes center in Khartoum, Sudan, was conducted using radiation survey meter. The purpose of this study is to provide protection of workers, patients, co patients, an the environment by introducing good practice in management of radioactive waste generated in this lab. In this work measurement of radiation effective dose at different locations in the department were carried out. These locations were selected around the radioactive liquid and solid waste disposal position. It was found that the effective doses per year from radioactive wastes obtained through this work using the survey meter RDS-120 at these locations, are 1.47 mSv/y at the neighbouring patients room, 5.47 mSv/y at the hot lab., 0.09 mSv/y at the neighbouring toilet, 0.321 mSv/y at the water closet, and 1.4 mSv/y at the place down water closet. The results obtained shows that the dose levels waste at the location not exceed the recommended dose limits for workers 20 mSv/y, that set by basic safety standards (Bss 115) which published by the international atomic energy agency. Also it s comply with the national regulation, regulation on basic radiation protection requirement and dose limits 1996, issued by sudan atomic energy commission act 1996. The annual dose calculated for the patients and co-patients at rooms around the nuclear medicine department, the results shows that dose are fairly high. Measure should taken to improve the waste management in the department for better protection of workers, patients and co patients. (Author)

Radiofrequency (RF) radiation measurement for diathermy machine

International Nuclear Information System (INIS)

Rozaimah Abdul Rahim; Roha Tukimin; Mohd Amirul Nizam; Ahmad Fadzli; Mohd Azizi

2010-01-01

Full-text: Diathermy machine is one of medical device that use widely in hospital and clinic. During the diathermy treatment, high radiofrequency (RF) currents (shortwave and microwave) are used to heat deep muscular tissues through electromagnetic energy to body tissues. The heat increases blood flow, relieve pain and speeding up recovery. The stray RF radiation from the machine can exposes to unintended tissue of the patient, to the operator (physical therapist) and also can cause electromagnetic interference (EMI) effect to medical devices around the machine. The main objective of this study is to establish a database of the RF radiation exposure levels experienced by the operator and patient during the treatments. RF radiation (electric and magnetic field) produced by the diathermy machines were measured using special RF survey meters. The finding of this study confirms that radiation levels on the surface and near the applicator of the diathermy machine much more elevated due to the much closer distance to the source and they exceeding the occupational and general public exposure limit. The results also shows the field strengths drop very significantly when the distance of measurement increase. (author)

Aerial radiological survey of the La Salle County Station and surrounding area, Seneca, Illinois. Date of survey: July 1981

International Nuclear Information System (INIS)

Hobaugh, J.L.

1982-06-01

An aerial radiological survey was performed from 14 to 31 July 1981 over a 270-square-kilometer area centered on the La Salle County Station near Seneca, Illinois. The survey was conducted by EG and G for the US Nuclear Regulatory Commission. All gamma ray data were collected by flying lines spaced 152 meters (500 ft) apart at an altitude of 91 meters (300 ft) above ground level. Processed data showed that all gamma rays detected within the survey area were those expected from naturally occurring background emitters. Count rates obtained from the aerial platform were converted to exposure rates at 1 meter above the ground and are presented in the form of an isoradiation contour map. The observed exposure rates for the survey area were between 5 and 14 microroentgens per hour (μR/h), with most of the area ranging from 8 to 14 μR/h. The exposure rate obtained from soil samples taken from within the survey site displayed positive agreement with the aerial data

Development of dose equivalent meters based on microdosimetric principles

International Nuclear Information System (INIS)

Booz, J.

1984-01-01

In this paper, the employment of microdosimetric dose-equivalent meters in radiation protection is described considering the advantages of introducing microdosimetric methods into radiation protection, the technical suitability of such instruments for measuring dose equivalent, and finally technical requirements, constraints and solutions together with some examples of instruments and experimental results. The advantage of microdosimetric methods in radiation protection is illustrated with the evaluation of dose-mean quality factors in radiation fields of unknown composition and with the methods of evaluating neutron- and gamma-dose fractions. - It is shown that there is good correlation between dose-mean lineal energy, anti ysub(anti D), and the ICRP quality factor. - Neutron- and gamma-dose fractions of unknown radiation fields can be evaluated with microdosimetric proportional counters without recurrence to other instruments and methods. The problems of separation are discussed. The technical suitability of microdosimetric instruments for measuring dose equivalent is discussed considering the energy response to neutrons and photons and the sensitivity in terms of dose-equivalent rate. Then, considering technical requirements, constraints, and solutions, the problem of the large dynamic range in LET, the large dynamic range in pulse rate, geometry of sensitive volume and electrodes, evaluation of dose-mean quality factors, calibration methods, and uncertainties are discussed. (orig.)

1 meter Digital Elevation Models (DEMs) - USGS National Map 3DEP Downloadable Data Collection

Data.gov (United States)

U.S. Geological Survey, Department of the Interior — This is a tiled collection of the 3D Elevation Program (3DEP) and is one meter resolution.The 3DEP data holdings serve as the elevation layer of The National Map,...

Streamlining Smart Meter Data Analytics

DEFF Research Database (Denmark)

Liu, Xiufeng; Nielsen, Per Sieverts

2015-01-01

of the so-called big data possible. This can improve energy management, e.g., help utilities improve the management of energy and services, and help customers save money. As this regard, the paper focuses on building an innovative software solution to streamline smart meter data analytic, aiming at dealing......Today smart meters are increasingly used in worldwide. Smart meters are the advanced meters capable of measuring customer energy consumption at a fine-grained time interval, e.g., every 15 minutes. The data are very sizable, and might be from different sources, along with the other social......-economic metrics such as the geographic information of meters, the information about users and their property, geographic location and others, which make the data management very complex. On the other hand, data-mining and the emerging cloud computing technologies make the collection, management, and analysis...

5 Meter Alaska Digital Elevation Models (DEMs) - USGS National Map 3DEP Downloadable Data Collection

Data.gov (United States)

U.S. Geological Survey, Department of the Interior — This dataset is comprised of 5-meter ifsar-derived Digital Elevation Models (DEMs) over Alaska only. It is distributed as one-degree blocks with overedge. Horizontal...

Evaluation of different disinfectants on the performance of an on-meter dosed amperometric glucose-oxidase-based glucose meter.

Science.gov (United States)

Sarmaga, Don; Dubois, Jeffrey A; Lyon, Martha E

2011-11-01

Off-meter dosed photometric glucose-oxidase-based glucose meters have been reported to be susceptible to interference by hydrogen-peroxide-based disinfecting agents. The objective of this study was to determine if a single application of hydrogen-peroxide-containing Accel® wipe to disinfect an on-meter dosed amperometric glucose-oxidase-based glucose meter will influence its performance. The performance of five on-meter dosed amperometric glucose-oxidase-based glucose meters was determined before and after disinfecting the devices with a single application of either CaviWipes® (14.3% isopropanol and 0.23% diisobutyl-phenoxy-ethoxyethyl dimethyl benzyl ammonium chloride) or Accel (0.5% hydrogen peroxide) wipes. Replicate glucose measurements were conducted before disinfecting the devices, immediately after disinfecting, and then 1 and 2 min postdisinfecting, with measurements in triplicate. Analysis was sequentially completed for five different meters. Results were analyzed by a two-way analysis of variance (Analyze-it software). No clinical ( .05) in glucose concentration were detected when the on-meter dosed amperometric glucose-oxidase-based glucose meters were disinfected with either CaviWipes or Accel wipes and measured immediately or 1 or 2 min postdisinfecting. No clinically significant difference in glucose concentration was detected between meters (glucose oxidase amperometric-based glucose meters are not analytically susceptible to interference by a single application of hydrogen-peroxide-containing Accel disinfectant wipes. © 2011 Diabetes Technology Society.

Net metering: zero electricity bill

International Nuclear Information System (INIS)

Mangi, A.; Khan, Z.

2011-01-01

Worldwide move towards renewable energy sources, environmental concerns and decentralization of the power sector have made net metering an attractive option for power generation at small scale. This paper discusses the net metering, economical issues of renewable sources in Pakistan, technical aspects, installation suitability according to varying terrain, existing utility rules and formulation of legislation for net metering making it economically attractive. (author)

Terrestrial gamma radiation dose rates and radiological mapping of Terengganu state, Malaysia

International Nuclear Information System (INIS)

Garba, N.N.

2015-01-01

Measurement of terrestrial gamma radiation dose (TGRD) rates in Terengganu state, Malaysia was carried out from 145 different locations using NaI[Tl] micro roentgen survey meter. The measured TGRD rates ranged from 35 to 340 nGy h -1 with mean value of 150 nGy h -1 . The annual effective dose to population was found to be 0.92 mSv y -1 . The data obtained were used in constructing the gamma isodose map using ArcGis 9.3 which shows the distribution of TGRD rates across the state. (author)

Gaps in Radiation Therapy Awareness: Results From an Educational Multi-institutional Survey of US Internal Medicine Residents.

Science.gov (United States)

Shaverdian, Narek; Yoo, Sun Mi; Cook, Ryan; Chang, Eric M; Jiang, Naomi; Yuan, Ye; Sandler, Kiri; Steinberg, Michael; Lee, Percy

2017-08-01

Internists and primary care providers play a growing role in cancer care. We therefore evaluated the awareness of radiation therapy in general and specifically the clinical utility of stereotactic body radiation therapy (SBRT) for early-stage non-small cell lung cancer (NSCLC) among current US internal medicine residents. A web-based institutional review board-approved multi-institutional survey was distributed to US internal medicine residency programs. The survey evaluated trainee demographic characteristics, baseline radiation oncology awareness, knowledge of the role of SBRT for early-stage NSCLC, and whether the survey successfully improved awareness. Thirty US internal medicine programs participated, with an overall participant response rate of 46% (1177 of 2551). Of the trainees, 93% (n=1076) reported no radiation oncology education in their residency, 39% (n=452) reported confidence in knowing when to consult radiation oncology in an oncologic emergency, and 26% (n=293) reported confidence in knowing when to consult radiation oncology in the setting of a newly diagnosed cancer. Of the participants, 76% (n=850) correctly identified that surgical resection is the standard treatment in operable early-stage NSCLC, but only 50% (n=559) of participants would recommend SBRT to a medically inoperable patient, followed by 31% of participants (n=347) who were unsure of the most appropriate treatment, and 10% (n=117) who recommended waiting to offer palliative therapy. Ninety percent of participants (n=1029) agreed that they would benefit from further training on when to consult radiation oncology. Overall, 96% (n=1072) indicated that the survey increased their knowledge and awareness of the role of SBRT. The majority of participating trainees received no education in radiation oncology in their residency, reported a lack of confidence regarding when to consult radiation oncology, and overwhelmingly agreed that they would benefit from further training. These findings

The use of roentgen diagnostics in chiropractor activities. Project based survey according to new regulations regarding radiation protection and use of radiation

International Nuclear Information System (INIS)

Raaum, Aud; Widmark, Anders

2005-12-01

An audit has been performed in 17 chiropractic enterprises according to new radiation protection legislation. Before the audits a survey of the use of diagnostic imaging in Norwegian chiropractic enterprises was carried out. This report summarizes the results of the survey and the findings at the audits. (Author)

Balanced Flow Meters without Moving Parts

Science.gov (United States)

Kelley, Anthony R.; VanBuskirk, Paul

2008-01-01

Balanced flow meters are recent additions to an established class of simple, rugged flow meters that contain no moving parts in contact with flow and are based on measurement of pressure drops across objects placed in flow paths. These flow meters are highly accurate, minimally intrusive, easily manufacturable, and reliable. A balanced flow meter can be easily mounted in a flow path by bolting it between conventional pipe flanges. A balanced flow meter can be used to measure the flow of any of a variety of liquids or gases, provided that it has been properly calibrated. Relative to the standard orifice-plate flow meter, the balanced flow meter introduces less turbulence and two times less permanent pressure loss and is therefore capable of offering 10 times greater accuracy and repeatability with less dissipation of energy. A secondary benefit of the reduction of turbulence is the reduction of vibration and up to 15 times less acoustic noise generation. Both the balanced flow meter and the standard orifice-plate flow meter are basically disks that contain holes and are instrumented with pressure transducers on their upstream and downstream faces. The most obvious difference between them is that the standard orifice plate contains a single, central hole while the balanced flow meter contains multiple holes. The term 'balanced' signifies that in designing the meter, the sizes and locations of the holes are determined in an optimization procedure that involves balancing of numerous factors, including volumetric flow, mass flow, dynamic pressure, kinetic energy, all in an effort to minimize such undesired effects as turbulence, pressure loss, dissipation of kinetic energy, and non-repeatability and nonlinearity of response over the anticipated range of flow conditions. Due to proper balancing of these factors, recent testing demonstrated that the balanced flow-meter performance was similar to a Venturi tube in both accuracy and pressure recovery, but featured reduced

Specialized instrument for radiation assistance teams

International Nuclear Information System (INIS)

Applegate, J.A.

1985-08-01

A specialized multiradiation instrument for radiation assistance teams (RAT's) has been designed; a working prototype has been constructed and field tested. The instrument detects alpha, beta, and gamma radiation simultaneously with simple red, yellow, and green meter indications and audio outputs. It is basically intended for DOE radiation assistance teams but would have application to any government, military, or industrial radiation accident team

A survey of radiation doses received by atomic-bomb survivors residing in the U.S

International Nuclear Information System (INIS)

Kerr, G.D.; Yamada, H.; Marks, S.

1976-01-01

A survey has been completed of 300 of an estimated 500 to 750 survivors of the atomic bombings in Hiroshima and Nagasaki who reside in the U.S. Distributions with respect to age, sex, citizenship status, distance from the hypocenter at the time of bombing, and dose from immediate weapon radiation have been tabulated from the results and are presented for this group of 300 survivors. Also presented are survey results concerning exposures to residual radiation from fallout and neutral-induced radioactivity in the areas adjacent to the hypocenter. (author)

How to use your peak flow meter

Science.gov (United States)

... meter - how to use; Asthma - peak flow meter; Reactive airway disease - peak flow meter; Bronchial asthma - peak ... 2014:chap 55. National Asthma Education and Prevention Program website. How to use a peak flow meter. ...

Radiation and contamination survey of the Terengganu offshore facilities

International Nuclear Information System (INIS)

Amran Abd Majid; Sukiman Sarmani

1995-01-01

It is well known that low specific activity of technologically enhanced naturally occurring radioactive materials (LSA TENORM) such as U-238 and Th-232 and their daughter products have been associated with oil and gas fields. For the period of October 1988 and August 1989 UKM personels were involved in conducting the radiation and contamination survey at several offshore platforms in Terengganu. The results showed that the maximum external and internal radiation levels was 0. 45 μSv/hr whereas the maximum surface contamination level was 0. 124 Bq cm sup -2. These results indicate that the levels were below the level prescribed by the Malaysian Atomic Energy Licensing Board. However, several measures still need to be considered for the safety of the workers and will be discussed in this paper. (author)

Inspection surveys of x-ray inspection systems: results of five years and implications on future management of radiation risks

International Nuclear Information System (INIS)

Maharaj, H.P.

1999-01-01

Until the mid-1980s, federal inspectors performed radiation surveys annually on individual x-ray inspection systems which were operated for security screening purposes in federal facilities nationwide, and problems identified were corrected. The surveys were undertaken because of perceived high radiation risks and a need to ensure worker and public external exposures were minimized. The x-ray inspection systems are federally regulated under the Radiation Emitting Devices (RED) Act and, initially they were assessed by model type against the design, construction and performance criteria specified in the applicable RED regulations (Schedule II, Part IV) and were found compliant. A subsequent study not only demonstrated a much lower radiation risk attributed to a combination of technological advances in x-ray system design with narrow primary beams, high efficiency detectors and image processing capability, but also stressed the need for proper equipment maintenance and continued education of operators and maintenance personnel. Survey frequency was thus reduced to once every 2-3 years in accordance with a 1993 federal operational standard (Safety Code 29). The radiation protection principles in Safety Code 29 are similar to those of the 1996 International Atomic Energy Agency (IAEA) Basic Safety Standards for the protection against ionizing radiation and the safety of radiation sources. The purpose of this study was to assess inspection-survey data from 1993 through 1997 to elicit guidance toward the future management of radiation risks associated with the operation of such x-ray systems. (author)

Radiation oncology training in Poland: results of a national survey (2007)

International Nuclear Information System (INIS)

Niemiec, M.; Kepka, L.; Lindner, B.; Bujko, K.; Lindner, B.; Maciejewski, B.

2008-01-01

The aim of this survey was to evaluate the quality of training in radiation oncology in Poland in relation to the ESTRO recommendations, and to learn motivations, level of satisfaction, complaints, suggestions and career plans of radiation oncologists.The detailed questionnaire was addressed to radiation oncologists from all centres in Poland who have been certified as specialists after 1990. Of the 212 approached, 103 radiation oncologists responded to the questionnaire (49%). In general, 40% of respondents declared that the majority of tutors/supervisors devoted sufficient time to their training (60% in academic, 28% in regional centres); 60% had access to the literature, and 50% to the internet. The number of treated patients during the training period ranged from 10 to 3000 (median: 375). 69% of the respondents completed a training in another Polish oncology centre (median duration - 2 months), 21% underwent such training abroad, 55% attended international courses/ conferences. Respondents from academic centres had access and attended national and/or international training more often than those from regional centres. Financial matters have been listed as a major obstacle for out-door training by 93% of respondents. 64% of respondents were pleased or rather pleased with the general quality of training, and the remaining 36% were unsatisfied (these mainly from regional centres). Considering career plans, 72% respondents wanted to continue practice at their employing institutions; however 24% have declared a wish to continue their career abroad. This first national survey has shown some weak points in radiotherapy training in Poland, mainly the quality differences between the departments in favour of academic centres. Some of the problems can and should be solved by the Polish Society of Radiation Oncology, others need legislation changes and decisions at the level of the Ministry of Health. (authors)

Community Net Energy Metering: How Novel Policies Expand Benefits of Net Metering to Non-Generators

Energy Technology Data Exchange (ETDEWEB)

Rose, James; Varnado, Laurel

2009-04-01

As interest in community solutions to renewable energy grows, more states are beginning to develop policies that encourage properties with more than one meter to install shared renewable energy systems. State net metering policies are evolving to allow the aggregation of multiple meters on a customer’s property and to dissolve conventional geographical boundaries. This trend means net metering is expanding out of its traditional function as an enabling incentive to offset onsite customer load at a single facility. This paper analyzes community net energy metering (CNEM) as an emerging vehicle by which farmers, neighborhoods, and municipalities may more easily finance and reap the benefits of renewable energy. Specifically, it aims to compare and contrast the definition of geographical boundaries among different CNEM models and examine the benefits and limitations of each approach. As state policies begin to stretch the geographic boundaries of net metering, they allow inventive solutions to encourage renewable energy investment. This paper attempts to initiate the conversation on this emerging policy mechanism and offers recommendations for further development of these policies.

Present status of ambient dose equivalent rate and radioactive substance concentration measurements in working environment. (3) Measuring instruments for ionizing radiation in working environments

International Nuclear Information System (INIS)

Matsubara, Shohei

2006-01-01

In order to measure the airborne radioactive substance concentration in working environments, some kinds of sampler such as dust sampler and iodine sampler, measuring instruments (alpha and beta spectrometer, and liquid scintillation counter), monitor (dust-, iodine- and gas-monitor), survey meter for measuring gamma ray dose rate are stated. The measurement method of α, β and γ-ray nuclides and ambient dose-equivalent at 10 mm was explained. Some examples of the list of dust sampler, filter, tritium sampler, dust monitor, iodine monitor, gas monitor, and survey meter on the market are shown. There are so many kinds of measuring instruments for ionizing radiation in working environment that the best instrument for measurement should be selected. The environment conditions such as sample form, temperature and humidity have to be considered in order to evaluate the measurement values. (S.Y.)

Hardware Design of a Smart Meter

OpenAIRE

Ganiyu A. Ajenikoko; Anthony A. Olaomi

2014-01-01

Smart meters are electronic measurement devices used by utilities to communicate information for billing customers and operating their electric systems. This paper presents the hardware design of a smart meter. Sensing and circuit protection circuits are included in the design of the smart meter in which resistors are naturally a fundamental part of the electronic design. Smart meters provides a route for energy savings, real-time pricing, automated data collection and elimina...

Viability study of a construction of invasive high voltage meter for the National Reference Laboratory of the Brazilian Net Calibration in Diagnostic Radiology, the National Laboratory of Metrology of the Ionizing Radiation - LNMRI

International Nuclear Information System (INIS)

Quaresma, D.S.; Peixoto, J.G.P.; Pereira, M.A.G.

2007-01-01

This work has studied the parameters for the construction of an invasive high voltage meter for the National Reference Laboratory of the Brazilian Net Calibration in Diagnostic Radiology, the National Laboratory of Metrology of the Ionizing Radiation - LNMRI. This study took into consideration the necessity of quality control of the of X-rays equipment required by Ministry of Health - MS, through the regulation N.453. To satisfy the demands of the MS, the recommendation of the norm IEC 61676 was analyzed by using the quantity of Practical Peak Voltage (PPV) in the measurements of the voltage discharge applied to the X-rays tubes, the infra structures of metrology available in the country to offer tracking the components of the high voltage meter through INMETRO and the difficulty of adaptation of the high voltage meter analyser III U in relation to the Pan tak HF160 equipment in which respect the connection of the high voltage cable and the voltage limitations due to the electric configuration of the high voltage generator of the constant potential Pantak HF160 equipment. (author)

Radiation protection monitoring for #betta#-radiation at the Juelich Nuclear Research Centre

International Nuclear Information System (INIS)

Keller, M.; Heinzelmann, M.

1983-01-01

A complete system for radiation protection monitoring also includes #betta#-radiation monitoring. This requires suitable dose rate meters, personal dosemeters and last but not least detailed information about possible radiation exposure due to #betta#-radiation. Since there are at present no suitable #betta#-dosemeters available on the market yet, a large nuclear research centre such as the KFA Juelich, where radioactive substances are being handled by more than 1600 persons, has the task of developing and deploying suitable dosemeters. The centre's accomplishments in this area are described

Development of simple band-spectral pyranometer and quantum meter using photovoltaic cells and bandpass filters

Energy Technology Data Exchange (ETDEWEB)

Bilguun, Amarsaikhan, E-mail: bilguun@pes.ee.tut.ac.jp; Nakaso, Tetsushi; Harigai, Toru; Suda, Yoshiyuki; Takikawa, Hirofumi, E-mail: takikawa@ee.tut.ac.jp [Toyohashi University of Technology, 1-1 Habarigaoka, Tempaku, Toyohashi 441-8580 (Japan); Tanoue, Hideto [Kitakyushu National College of Technology, 5-20-1, Kokuraminami, Kitakyushu, Fukuoka 802-0985 (Japan)

2016-02-01

In recent years, greenhouse automatic-control, based on the measurement of solar irradiance, has been attracting attention. This control is an effective method for improving crop production. In the agricultural field, it is necessary to measure Photon Flux Density (PFD), which is an important parameter in the promotion of plant growth. In particular, the PFD of Photosynthetically Active Radiation (PAR, 400-700 nm) and Plant Biologically Active Radiation (PBAR, 300-800 nm) have been discussed in agricultural plant science. The commercial quantum meter (QM, PAR meter) can only measure Photosynthetically Photon Flux Density (PPFD) which is the integrated PFD quantity on the PAR wavelength. In this research, a band-spectral pyranometer or quantum meter using PVs with optical bandpass filters for dividing the PBAR wavelength into 100 nm bands (five independent channels) was developed. Before field testing, calibration of the instruments was carried out using a solar simulator. Next, a field test was conducted in three differing weather conditions such as clear, partly cloudy and cloudy skies. As a result, it was found that the response rate of the developed pyranometer was faster by four seconds compared with the response rate of the commercial pyranometer. Moreover, the outputs of each channel in the developed pyranometer were very similar to the integrated outputs of the commercial spectroradiometer. It was confirmed that the solar irradiance could be measured in each band separately using the developed band-spectral pyranometer. It was indicated that the developed band-spectral pyranometer could also be used as a PV band-spectral quantum meter which is obtained by converting the band irradiance into band PFD.

Development of simple band-spectral pyranometer and quantum meter using photovoltaic cells and bandpass filters

Science.gov (United States)

Bilguun, Amarsaikhan; Nakaso, Tetsushi; Harigai, Toru; Suda, Yoshiyuki; Takikawa, Hirofumi; Tanoue, Hideto

2016-02-01

In recent years, greenhouse automatic-control, based on the measurement of solar irradiance, has been attracting attention. This control is an effective method for improving crop production. In the agricultural field, it is necessary to measure Photon Flux Density (PFD), which is an important parameter in the promotion of plant growth. In particular, the PFD of Photosynthetically Active Radiation (PAR, 400-700 nm) and Plant Biologically Active Radiation (PBAR, 300-800 nm) have been discussed in agricultural plant science. The commercial quantum meter (QM, PAR meter) can only measure Photosynthetically Photon Flux Density (PPFD) which is the integrated PFD quantity on the PAR wavelength. In this research, a band-spectral pyranometer or quantum meter using PVs with optical bandpass filters for dividing the PBAR wavelength into 100 nm bands (five independent channels) was developed. Before field testing, calibration of the instruments was carried out using a solar simulator. Next, a field test was conducted in three differing weather conditions such as clear, partly cloudy and cloudy skies. As a result, it was found that the response rate of the developed pyranometer was faster by four seconds compared with the response rate of the commercial pyranometer. Moreover, the outputs of each channel in the developed pyranometer were very similar to the integrated outputs of the commercial spectroradiometer. It was confirmed that the solar irradiance could be measured in each band separately using the developed band-spectral pyranometer. It was indicated that the developed band-spectral pyranometer could also be used as a PV band-spectral quantum meter which is obtained by converting the band irradiance into band PFD.

Development of simple band-spectral pyranometer and quantum meter using photovoltaic cells and bandpass filters

International Nuclear Information System (INIS)

Bilguun, Amarsaikhan; Nakaso, Tetsushi; Harigai, Toru; Suda, Yoshiyuki; Takikawa, Hirofumi; Tanoue, Hideto

2016-01-01

In recent years, greenhouse automatic-control, based on the measurement of solar irradiance, has been attracting attention. This control is an effective method for improving crop production. In the agricultural field, it is necessary to measure Photon Flux Density (PFD), which is an important parameter in the promotion of plant growth. In particular, the PFD of Photosynthetically Active Radiation (PAR, 400-700 nm) and Plant Biologically Active Radiation (PBAR, 300-800 nm) have been discussed in agricultural plant science. The commercial quantum meter (QM, PAR meter) can only measure Photosynthetically Photon Flux Density (PPFD) which is the integrated PFD quantity on the PAR wavelength. In this research, a band-spectral pyranometer or quantum meter using PVs with optical bandpass filters for dividing the PBAR wavelength into 100 nm bands (five independent channels) was developed. Before field testing, calibration of the instruments was carried out using a solar simulator. Next, a field test was conducted in three differing weather conditions such as clear, partly cloudy and cloudy skies. As a result, it was found that the response rate of the developed pyranometer was faster by four seconds compared with the response rate of the commercial pyranometer. Moreover, the outputs of each channel in the developed pyranometer were very similar to the integrated outputs of the commercial spectroradiometer. It was confirmed that the solar irradiance could be measured in each band separately using the developed band-spectral pyranometer. It was indicated that the developed band-spectral pyranometer could also be used as a PV band-spectral quantum meter which is obtained by converting the band irradiance into band PFD

Net metering in British Columbia : white paper

International Nuclear Information System (INIS)

Berry, T.

2003-01-01

Net metering was described as being the reverse registration of an electricity customer's revenue meter when interconnected with a utility's grid. It is a provincial policy designed to encourage small-distributed renewable power generation such as micro-hydro, solar energy, fuel cells, and larger-scale wind energy. It was noted that interconnection standards for small generation is an important issue that must be addressed. The British Columbia Utilities Commission has asked BC Hydro to prepare a report on the merits of net metering in order to support consultations on a potential net metering tariff application by the utility. This report provides information on net metering with reference to experience in other jurisdictions with net metering, and the possible costs and benefits associated with net metering from both a utility and consumer perspective. Some of the barriers and policy considerations for successful implementation of net metering were also discussed. refs., tabs., figs

An aerial radiological survey of the Savannah River Site and surrounding area, Aiken, South Carolina, October--November 1991

International Nuclear Information System (INIS)

Vojtech, R.J.

1993-12-01

An aerial radiological survey was conducted during the period of October 14 to November 23, 1991, over an area surrounding the United States Department of Energy's Savannah River Site (SRS). The area is situated 15 kilometers south of Aiken, South Carolina. The purpose of the survey was to measure and document the gamma ray environment of the SRS and surrounding areas. Contour maps showing gamma radiation exposure rates at 1 meter above ground level were constructed from the aerial data and overlaid on a United States Geological Survey map of the area. The exposure rates measured within the survey region are generally uniform and typical of natural background. The reported exposure rate values include an estimated cosmic ray contribution. Enhanced exposure rates not attributable to natural background were measured over several areas within the survey region. The manmade radionuclides detected in these areas, cesium-137, cobalt-60, and protactinium-234m, were produced by the reactor operations and material processing conducted at the SRS. The radiation levels produced by these nuclides are consistent with those levels measured during previous SRS aerial surveys. Radionuclide assays of soil samples and pressurized ion chamber measurements were obtained at four locations within the survey boundaries

Use of a radiation therapy treatment planning computer in a hospital health physics program

International Nuclear Information System (INIS)

Addison, S.J.

1984-01-01

An onsite treatment planning computer has become state of the art in the care of radiation therapy patients, but in most installations the computer is used for therapy planning a diminutive amount of the day. At St. Mary's Hospital, arrangements have been negotiated for part time use of the treatment planning computer for health physics purposes. Computerized Medical Systems, Inc. (CMS) produces the Modulex radiotherapy planning system which is programmed in MUMPS, a user oriented language specially adapted for handling text string information. St. Mary's Hospital's CMS computer has currently been programmed to assist in data collection and write-up of diagnostic x-ray surveys, meter calibrations, and wipe/leak tests. The computer is setup to provide timely reminders of tests and surveys, and billing for consultation work. Programs are currently being developed for radionuclide inventories. Use of a therapy planning computer for health physics purposes can enhance the radiation safety program and provide additional grounds for the acquisition of such a computer system

A questionnaire survey of medical physicist and quality manager for radiation therapy

International Nuclear Information System (INIS)

Nishio, Teiji; Ashino, Yasuo; Onishi, Hiroshi

2008-01-01

A questionnaire survey of medical physicists and quality managers for radiation therapy was performed by the Japanese Society for Therapeutic Radiology and Oncology (JASTRO) Future Planning Committee. We mailed the questionnaire to 726 radiotherapy facilities with the answers returned from 353 radiotherapy facilities. The result showed 178 facilities were staffed by radiotherapy workers who were licensed medical physicists or quality managers. A staff of 289 was licensed radiotherapy workers. Most of the staff were radiotherapy technologists. Quality control for radiation therapy was rated satisfactory according to each facility's assessment. Radiation therapy of high quality requires continued education of medical physicists and quality managers, in addition to keeping up with times for quality control. (author)

Aerial radiation survey

International Nuclear Information System (INIS)

Pradeep Kumar, K.S.

1998-01-01

Aerial gamma spectrometry surveys are the most effective, comprehensive and preferred tool to delimit the large area surface contamination in a radiological emergency either due to a nuclear accident or following a nuclear strike. The airborne survey apart from providing rapid and economical evaluation of ground contamination over large areas due to larger ground clearance and higher speed, is the only technique to overcome difficulties posed by ground surveys of inaccessible region. The aerial survey technique can also be used for searching of lost radioactive sources, tracking of radioactive plume and generation of background data on the Emergency Planning Zone (EPZ) of nuclear installations

Development of a calibration methodology and tests of kerma area product meters; Desenvolvimento de uma metodologia de calibracao e testes de medidores de produto Kerma-Area

Energy Technology Data Exchange (ETDEWEB)

Costa, Nathalia Almeida

2013-07-01

The quantity kerma area product (PKA) is important to establish reference levels in diagnostic radiology exams. This quantity can be obtained using a PKA meter. The use of such meters is essential to evaluate the radiation dose in radiological procedures and is a good indicator to make sure that the dose limit to the patient's skin doesn't exceed. Sometimes, these meters come fixed to X radiation equipment, which makes its calibration difficult. In this work, it was developed a methodology for calibration of PKA meters. The instrument used for this purpose was the Patient Dose Calibrator (PDC). It was developed to be used as a reference to check the calibration of PKA and air kerma meters that are used for dosimetry in patients and to verify the consistency and behavior of systems of automatic exposure control. Because it is a new equipment, which, in Brazil, is not yet used as reference equipment for calibration, it was also performed the quality control of this equipment with characterization tests, the calibration and an evaluation of the energy dependence. After the tests, it was proved that the PDC can be used as a reference instrument and that the calibration must be performed in situ, so that the characteristics of each X-ray equipment, where the PKA meters are used, are considered. The calibration was then performed with portable PKA meters and in an interventional radiology equipment that has a PKA meter fixed. The results were good and it was proved the need for calibration of these meters and the importance of in situ calibration with a reference meter. (author)

Conceptual basis for the radiometric dye film dose meter as a test of particle track theory

International Nuclear Information System (INIS)

Hansen, J.W.

1980-05-01

This report is a summary of a lecture held at the Danish-Polish Symposium on Radiation Chemistry in Warsaw, October 1979, describing an initiated work connected to the particle track theory worked out by R. Katz and coworkers. A short description is given of the theory and the applicability of the theory in the use of the radiometric dye cyanide film dose meter as a detector in radiation of different qualities. A few experimental results are given. (author)

Laser power meter based on the Peltier effect

International Nuclear Information System (INIS)

Goldschmid, H.J.; Miller, L.A.; Paul, G.L.

1984-01-01

An isothermal power meter, in which the incoming radiation is balanced by thermoelectric cooling, has two substantial advantages: there are no heat losses to the surroundings, and a short response time should result from the smallness of the temperature excursions before balance is achieved. Experiments on prototype devices consisting of thermoelectric modules, made from bismuth telluride alloys, with nominally black-body receivers are reported. Laser powers in the range 100 to 550 mW were measured. In the most favoured arrangement, multijunction modules were used both to provide cooling through the Peltier effect and to detect any temperature excursions through the Seebeck effect. The results justify further work on the system

Assessment of background gamma radiation levels around Tummalapalle uranium mining and processing facility, Andhra Pradesh

International Nuclear Information System (INIS)

Rana, B.K.; Dhumale, M.R.; Molla, Samim; Rao, K.B.; Jha, S.K.; Tripathi, R.M.; Sahu, S.K.

2018-01-01

Natural environmental radioactivity and the associated external exposure due to gamma radiation depend primarily on the geological and geographical conditions, and appear at different levels in the soil of each region in the world. The dose received by the population in a region comprises of (i) external gamma radiation dose due to cosmic rays and primordial radionuclides; (ii) inhalation dose due to radon, thoron and their progeny, and (iii) ingestion dose due to the intake of radionuclides through the consumption of food, milk, water, etc. In this study, background gamma radiation level around Tummalapalle uranium mining and processing site was estimated by using radiation survey meter and deploying environmental TLDs. The generated data can be served as baseline for this area for future comparison for prolonged operation of the plant, for the upcoming adjacent projects and during decommissioning phase of the mine, mill and tailings pond

Current status of brachytherapy in Korea: a national survey of radiation oncologists.

Science.gov (United States)

Kim, Haeyoung; Kim, Joo Young; Kim, Juree; Park, Won; Kim, Young Seok; Kim, Hak Jae; Kim, Yong Bae

2016-07-01

The aim of the present study was to acquire information on brachytherapy resources in Korea through a national survey of radiation oncologists. Between October 2014 and January 2015, a questionnaire on the current status of brachytherapy was distributed to all 86 radiation oncology departments in Korea. The questionnaire was divided into sections querying general information on human resources, brachytherapy equipment, and suggestions for future directions of brachytherapy policy in Korea. The response rate of the survey was 88.3%. The average number of radiation oncologists per center was 2.3. At the time of survey, 28 centers (36.8%) provided brachytherapy to patients. Among the 28 brachytherapy centers, 15 (53.5%) were located in in the capital Seoul and its surrounding metropolitan areas. All brachytherapy centers had a high-dose rate system using (192)Ir (26 centers) or (60)Co (two centers). Among the 26 centers using (192)Ir sources, 11 treated fewer than 40 patients per year. In the two centers using (60)Co sources, the number of patients per year was 16 and 120, respectively. The most frequently cited difficulties in performing brachytherapy were cost related. A total of 21 centers had a plan to sustain the current brachytherapy system, and four centers noted plans to upgrade their brachytherapy system. Two centers stated that they were considering discontinuation of brachytherapy due to cost burdens of radioisotope source replacement. The present study illustrated the current status of brachytherapy in Korea. Financial difficulties were the major barriers to the practice of brachytherapy.

Experimental verification of preset time count rate meters based on adaptive digital signal processing algorithms

Directory of Open Access Journals (Sweden)

Žigić Aleksandar D.

2005-01-01

Full Text Available Experimental verifications of two optimized adaptive digital signal processing algorithms implemented in two pre set time count rate meters were per formed ac cording to appropriate standards. The random pulse generator realized using a personal computer, was used as an artificial radiation source for preliminary system tests and performance evaluations of the pro posed algorithms. Then measurement results for background radiation levels were obtained. Finally, measurements with a natural radiation source radioisotope 90Sr-90Y, were carried out. Measurement results, con ducted without and with radio isotopes for the specified errors of 10% and 5% showed to agree well with theoretical predictions.

Standardization of reference radiation field of beta for 85Kr using extrapolation chamber

International Nuclear Information System (INIS)

Nazaroh; Fendinugroho

2013-01-01

Standardization of reference radiation field of beta for 85 Kr in PTKMR-BATAN Laboratory has been performed at the SDD's 30 cm by using extrapolation chamber detector, coupled with Uni dose electrometer. The result was : (8.98±3 %) mGy/h, at 95 % confidence level. The aim of standardization of reference radiation field is to support radiation protection and safety program, provided by the International Atomic Energy Agency to its Member States, included BATAN-Indonesia, especially, PTKMR. The aim of radiation protection program and safety program is to promote an internationally harmonized approach for radiation measurement in protection level, besides for calibration of radiation measuring instrument, which users spread across Indonesia, with the number of about 795 firms in the year of 2012. These benefits can be felt by workers, communities and the environment, because by calibration, measurement survey meter, pocket dosimeter and TLD to be more accurate so that the radiation dose received by radiation workers is accurate and can be ascertained in a specified period, not to exceed a predetermined NBD by BAPETEN. The aim of this calibration is appropriate with the primary objective of calibration on IAEA/TRS16:2000. (author)

External gamma radiation survey for oil wellheads in Saudi Arabia

International Nuclear Information System (INIS)

Nassar, Rafat M.; Mously, Khalid A.; Cowie, Michael I.

2008-01-01

Naturally occurring radioactive material (NORM) is known to be associated with oil and gas extraction. As part of a comprehensive NORM management strategy, Saudi Aramco needed to determine the extent of NORM contamination associated with their oil and gas operations. As part of that strategy, this study focused on external gamma survey of oil producing wellheads at various locations. The study aimed to: 1-) Identify wellheads with elevated gamma radiation dose rate; 2-) Specify the exact locations of the high dose rates on the wellheads; 3-) Identify the radioisotopes responsible for the high dose rates; and 4-) Propose worker protection requirements during maintenance. The majority (∼92%) of the surveyed wellheads showed no enhanced gamma dose-rate above background level. From the remaining ∼8%, only a few wellheads showed dose rates between 1,000-3,700 n Sv/h. The study revealed that NORM contamination tends to accumulate at turns of the pipes, around pipe diameter changes, the joints, the back of valves, and at the base of the wellhead. Also, for a given location, NORM build up on the interior of pipework varies over time and continues to migrate down stream until it reaches the Gas and Oil Separation Plants (GOSP). There NORM is expected to accumulate and reside in the form of sludge. Gamma spectroscopy analysis revealed that 226 Ra and its progeny are responsible for the high radiation dose rates detected. It was concluded that NORM will not pose significant radiation hazards to workers as long as the tubing and piping are not opened. (author)

Evaluation of radiation doses received by the staff in nuclear medicine department of Rick

International Nuclear Information System (INIS)

Ali, Naemat Abdalla Mohamed

2001-01-01

Environmental monitoring in nuclear medicine rooms at Radiation and Isotopes Center Khartoum RICK were carried out using survey meter and thermoluminescent dosimetry. Staff bodies and hands doses measurements are being conducted using thermoluminescent dosimetry. The purpose of the study is to evaluate the radiation received by the staff work in the nuclear medicine department at RICK. Survey meter (RDS-120) and TLD clips of LiF. (Mg.Ti) were used to measure the environment leading of the staff. The associated annual doses have been determined to the staff bodies and hands. It was found that the dose-equivalent rates from bodies and hands of the staff obtained through this work using TLD clips are: nuclear medicine technologist body reading 6.75 mSv per year, physicist body reading 7.89 mSv per year, chemist body reading 6.1 mSv per year, and nurse body reading 8.1 mSv per year. On the other hand the nuclear medicine technologist hands reading 24.19 mSv per year, physicist hands reading 19.15 mSv per year, chemist hands reading 14.616 mSv per year, and nurse hands reading 277.96 mSv per year. All the staff reading in this study agree with the national regulations and international recommendations. It is clear that the dose of nurse hands is the highest one, this is because when they inject the patient with the Tc-99 m they use to spend relatively long time. (Author)

ATD-2 Surface Scheduling and Metering Concept

Science.gov (United States)

Coppenbarger, Richard A.; Jung, Yoon Chul; Capps, Richard Alan; Engelland, Shawn A.

2017-01-01

This presentation describes the concept of ATD-2 tactical surface scheduling and metering. The concept is composed of several elements, including data exchange and integration; surface modeling; surface scheduling; and surface metering. The presentation explains each of the elements. Surface metering is implemented to balance demand and capacity• When surface metering is on, target times from surface scheduler areconverted to advisories for throttling demand• Through the scheduling process, flights with CTOTs will not get addedmetering delay (avoids potential for ‘double delay’)• Carriers can designate certain flights as exempt from metering holds• Demand throttle in Phase 1 at CLT is through advisories sent to rampcontrollers for pushback instructions to the flight deck– Push now– Hold for an advised period of time (in minutes)• Principles of surface metering can be more generally applied to otherairports in the NAS to throttle demand via spot-release times (TMATs Strong focus on optimal use of airport resources• Flexibility enables stakeholders to vary the amount of delay theywould like transferred to gate• Addresses practical aspects of executing surface metering in aturbulent real world environment• Algorithms designed for both short term demand/capacityimbalances (banks) or sustained metering situations• Leverage automation to enable surface metering capability withoutrequiring additional positions• Represents first step in Tactical/Strategic fusion• Provides longer look-ahead calculations to enable analysis ofstrategic surface metering potential usage

Progress in high-dose radiation dosimetry

International Nuclear Information System (INIS)

Ettinger, K.V.; Nam, J.W.; McLaughlin, W.L.; Chadwick, K.H.

1981-01-01

The last decade has witnessed a deluge of new high-dose dosimetry techniques and expanded applications of methods developed earlier. Many of the principal systems are calibrated by means of calorimetry, although production of heat is not always the final radiation effect of interest. Reference systems also include a number of chemical dose meters: ferrous sulphate, ferrous-cupric sulphate, and ceric sulphate acidic aqueous solutions. Requirements for stable and reliable transfer dose meters have led to further developments of several important high-dose systems: amino acids and saccharides analysed by ESR or lyoluminescence, thermoluminescent materials, radiochromic dyes and plastics, ceric-cerous solutions analysed by potentiometry, and ethanol-chlorobenzene solutions analysed by high-frequency oscillometry. A number of other prospective dose meters are also treated in this review. In addition, an IAEA programme of high-dose standardization and intercomparison for industrial radiation processing is described. (author)

A Survey of Structural Design of Diagnostic X-ray Imaging Facilities and Compliance to Shielding Design Goals in a Limited Resource Setting

Directory of Open Access Journals (Sweden)

Flavious B. Nkubli

2017-11-01

Full Text Available Purpose: To survey structural designs of x-ray rooms and compliance to shielding design goals of three x-ray imaging facilities. Methods and Materials: The survey was conducted in three radiodiagnostic centers in South East Nigeria, labeled X, Y and Z for anonymity. A stretchable non-elastic meter rule was used to measure x-ray room dimensions. A Vernier caliper was used to measure lead thickness while a calibrated digital survey meter Radalert 100x was used for radiation survey of controlled and uncontrolled areas. Simple statistical tools such as mean and standard deviation were used for analysis with the aid of Microsoft Excel version 2007. Results: Center X had a room dimension of 2.4 m × 2.1 m, Center Y had an x-ray room dimension of 3.6 m × 3.3 m, and Center Z had two x-ray rooms with identical dimensions of 6.3 m × 3.6 m. Measured exit radiation doses for controlled areas in all the centers were: 0.00152 mSv/wk; 0.00496 mSv/wk; 0.00168 mSv/wk; 0.00224 mSv/wk respectively. Lead was the common shielding material used. Conclusion: Based on the parameters studied, Center Z had the ideal room size and layout. Relative distances from the x-ray tubes to the nearest walls were not optimized in all the centers except in Center Z. Measured exit doses were within recommended limits except in Center Y. The location of the control consoles and measured doses were appropriate and within recommended design goals.

Digital reactivity meter

International Nuclear Information System (INIS)

Akkus, B.; Anac, H.; Alsan, S.; Erk, S.

1991-01-01

Nowadays, various digital methods making use of microcomputers for neutron detector signals and determining the reactivity by numerical calculations are used in reactor control systems in place of classical reactivity meters. In this work, a calculation based on the ''The Time Dependent Transport Equation'' has been developed for determining the reactivity numerically. The reactivity values have been obtained utilizing a computer-based data acquisition and control system and compared with the analog reactivity meter values as well as the values calculated from the ''Inhour Equation''

Radiation mapping of Jaipur city using compact aerial radiation monitoring system (CARMS) installed in mobile platform

International Nuclear Information System (INIS)

Jain, Amit; Chaudhury, Probal; Padmanabhan, N.; Pradeepkumar, K.S.; Sharma, D.N.; Thandra, Manu

2010-01-01

Full text: Widespread use of radioisotopes for social benefits through industrial, scientific and medical applications poses a potential for occurrence of radiological emergencies due to loss or misuse of the radioactive sources. Besides, as there is increased societal concern for radiation safety of man and environment, monitoring is needed as a confidence building measure. It is necessary to assess any possible increase in background radiation due to the operation of nuclear facilities or any other man made events. Any observable increase in normal radiation background is a precursor for the abnormal presence of radioactivity. As a part of emergency preparedness for response to radiological emergencies, BARC has taken up radiation mapping of all major cities. A mobile ground based radiation monitoring has been conducted around Jaipur city using state-of-the-art radiation monitoring systems and instruments. The systems were mounted in a vehicle at a height of 1.0 meter from the ground and the GPS antenna was mounted on top for clear satellite visibility. It was ensured that the gamma attenuation due to the body of the vehicle was minimal. The average speed of the vehicle was maintained at 30 km/h to ensure uniformity in distance during the data acquisition interval. The monitoring was carried out over two days and resulted in establishment of baseline dose rate data of the city, which will be useful in case of any radiological emergency. The detailed environmental radiation monitoring demonstrated the utility of the systems and the methodology for the assessment of large area ground contamination and also search and detection of any orphan radioactive sources through variations in background gamma radiation observations. The methodology adopted for analysis of the surveyed data is based on the interpretation of the changes in the mean value and standard deviation in the values in different regions of the surveyed area. During this monitoring exercise, total road

A survey of radiation synovectomy in Europe, 1991-1993

International Nuclear Information System (INIS)

Clunie, G.; Ell, P.J.

1995-01-01

We have evaluated radiation synovectomy practice in Europe over the period 1991-1993 by means of a postal questionnaire. More than 2300 European members of the European Association of Nuclear Medicine were questioned about the number of treated patients and joints, disease prevalence in their patients and the use of radiopharmaceuticals. Overall, 119/490 (24%) of centres replying to the survey practised radiation synovectomy during the 3 years. There were 13450 different joint injections in 8578 patients. Rheumatoid arthritis was the most prevalent disease in patients treated (71%) and the most frequently treated joints were knee (46%) and finger joints (20%). Eight different radiopharmaceuticals were employed. Yttrium-90 colloids were most frequently and widely (100/119 centres) used, mainly employed for knee synovectomy but were also used to treat most appendicular joints. Erbium-169 colloid was almost exclusively used to treat finger joints (31/33 centres). Corticosteroid was routinely co-injected in 36/60 (60%) centres. Radiation synovectomy was widely practised throughout Europe during 1991-1993. There are variations in practice illustrated by the diversity of treated arthritides and injected joints and by the use and application of different radiopharmaceuticals. (orig.). With 7 figs., 1 tab

Radiation practices and radiation measurements

International Nuclear Information System (INIS)

2008-03-01

The guide presents the principal requirements on accuracy of radiation measurements and on the approval, calibration and operating condition inspections of radiation meters, together with requirements for dosimetric services measuring the individual radiation doses of workers engaged in radiation work (approved dosimetric services). The Guide also sets out the definitions of quantities and units used in radiation measurements. The radiation protection quantities used for assessing the harmful effects of radiation and for expressing the maximum values for radiation exposure (equivalent dose and effective dose) are set out in Guide ST 7.2. This Guide concerns measurements of ionizing radiation involved in radiation practices, the results of which are used for determining the radiation exposure of workers engaged in radiation work and members of the public, and of patients subject to the use of radiation in health services, or upon the basis of which compliance with safety requirements of appliances currently in use and of their premises of use or of the workplaces of workers is ensured. The Guide also concerns measurements of the radon concentration of inhaled air in both workplaces and dwellings. The Guide does not apply to determining the radiation exposure of aircrews, determination of exposure caused by internal radiation, or measurements made to protect the public in the event of, or in preparation for abnormal radiation conditions

Automated borehole gravity meter system

International Nuclear Information System (INIS)

Lautzenhiser, Th.V.; Wirtz, J.D.

1984-01-01

An automated borehole gravity meter system for measuring gravity within a wellbore. The gravity meter includes leveling devices for leveling the borehole gravity meter, displacement devices for applying forces to a gravity sensing device within the gravity meter to bring the gravity sensing device to a predetermined or null position. Electronic sensing and control devices are provided for (i) activating the displacement devices, (ii) sensing the forces applied to the gravity sensing device, (iii) electronically converting the values of the forces into a representation of the gravity at the location in the wellbore, and (iv) outputting such representation. The system further includes electronic control devices with the capability of correcting the representation of gravity for tidal effects, as well as, calculating and outputting the formation bulk density and/or porosity

A simple reactivity-meter system

International Nuclear Information System (INIS)

Ferreira, P.S.B.

1992-01-01

This paper describes a new version of a reactivity meter developed at the Institute of Nuclear Energy Research (IPEN) (Brazil). The reactivity meter computes the reactor reactivity utilizing a programmable electrometer that performs the data aquisition. The software commands the main functions of the electrometer, the data acquisition, data transfer, and reactivity calculation. The necessary hardware for this reactivity meter are a programmable electrometer, a microcomputer, and interfaces for the microcomputer to communicate with the electrometer. If it is necessary, it is possible to connect a graphic register to the microcomputer. With this conventional hardware, available in any nuclear reactor facility, one can build a powerful reactivity meter. Adding to these advantages, one can use the microcomputer on-line to analyze the data, store the data on diskettes, or create graphics

Measuring the greenhouse effect and radiative forcing through the atmosphere

Science.gov (United States)

Philipona, Rolf; Kräuchi, Andreas; Brocard, Emmanuel

2013-04-01

In spite of a large body of existing measurements of incoming shortwave solar radiation and outgoing longwave terrestrial radiation at the Earth's surface and at the top of the atmosphere, there are few observations documenting how radiation profiles change through the atmosphere - information that is necessary to fully quantify the greenhouse effect of the Earth's atmosphere. Using weather balloons and specific radiometer equipped radiosondes, we continuously measured shortwave and longwave radiation fluxes from the surface of the Earth up to altitudes of 35 kilometers in the upper stratosphere. Comparing radiation profiles from night measurements with different amounts of water vapor, we show evidence of large greenhouse forcing. We show, that under cloud free conditions, water vapor increases with Clausius-Clapeyron ( 7% / K), and longwave downward radiation at the surface increases by 8 Watts per square meter per Kelvin. The longwave net radiation however, shows a positive increase (downward) of 2.4 Watts per square meter and Kelvin at the surface, which decreases with height and shows a similar but negative increase (upward) at the tropopause. Hence, increased tropospheric water vapor increases longwave net radiation towards the ground and towards space, and produces a heating of 0.42 Kelvin per Watt per square meter at the surface. References: Philipona et al., 2012: Solar and thermal radiation profiles and radiative forcing measured through the atmosphere. Geophys. Res. Lett., 39, L13806, doi: 10.1029/2012GL052087.

Fundamental studies on miniature dose meter using variable capacitance Si-diode

International Nuclear Information System (INIS)

Inoue, Yoshio

1976-01-01

The results of fundamental studies on development of a miniature dose meter using a semiconductor applicable for dosimetry in both intracavitary and external radiotherapy are described. Many different instruments have been applied in clinical dosimetry for regional lesions, mostly in phantom studies, e. g. the small sized ionization chamber, the fluoroluminescence glass dose meter and the thermoluminescence dose meter. However, there are considerable problems regarding safety, reproducibility, and simplicity for regional dosimetry of intracavitary lesions, such as genitourinary, gastrointestinal and respiratory malignancies. To overcome these problems, an attempt was made to develop a miniature catheter type detector using a variable capacitance Si-diode for gamma ray dosimetry. The newly developed miniature dose meter using a semiconductor has the following characteristics. As the tip of detector (23mm long and 3mm in diameter) is very small, the apparatus unit is easy to manipulate in the dosimetry of intracavitary lesions. As no voltage is supplied to the detector, there is no danger of electric shock from in vivo studies. A strict linearity existed between the radiation dose rate and the generated voltage even when the range of experimental irradiation dose rate was extremely wide. The sensitivity of the detector was affected by the environmental temperature, but it was easy to correct the sensitivity by applying a special calibration chart to the value derived from a thermister enclosed in the detector. Even with the experimental irradiation of more than 50,000R, no changes in the sensitivity of the detector were observed. Thus, the durability of the apparatus was shown to be excellent. (auth.)

Radiation survey and management on the reconstructed radioactive work-site

International Nuclear Information System (INIS)

Yu Tao; Liang Shiqiang; Wang Youmei

2004-12-01

The experiences of radiation survey and administration in the prophase on reconstructed radioactive work-site are summarized. The advance works are to investigate the reconstructed work-site, settle working plans, devise inspecting flow charts, deal with something in time in the local and train the staffers. The works about prophasic decontaminating, removing and cleaning up the site have been finished, which have established the deep foundation to develop later task. (authors)

MULTICHANNEL DISTRIBUTION METER: A VERITABLE ...

African Journals Online (AJOL)

eobe

Usually, commercial home owners preferred the installation of one or few .... communication (GSM) based solution were presented. The authors ... meters. The proposed meters in their work uses .... The most probable data entry component to ...

Hydro Ottawa achieves Smart Meter milestone

International Nuclear Information System (INIS)

Anon.

2008-01-01

As Ontario's second largest municipal electricity company, Hydro Ottawa serves more than 285,000 residential and business customers in the city of Ottawa and the village of Casselman. Since 2006, the utility has installed more than 230,000 Smart Meters throughout its service territory in an effort to provide better services to its customers. This initiative represents the largest operational advanced metering infrastructure network in Canada. This move was necessary before time-of-use rates can be implemented in Ottawa. The Smart Meters deliver data wirelessly to Hydro Ottawa's Customer Information System for billing and eliminating manual readings. The Smart Meters are designed to promote more efficient use of electricity. The Government of Ontario has passed legislation requiring the installation of Smart Meters throughout the province by the end of 2010

Aerial radiological survey of the Grand Gulf Nuclear Station and surrounding area, Port Gibson, Mississippi. Date of survey: March 1982

International Nuclear Information System (INIS)

Ballatore, L.A.; Hilton, L.K.

1982-09-01

An aerial radiological survey was performed from 11 to 20 March 1982 over a 260-square-kilometer area centered on the Grand Gulf Nuclear Station at Port Gibson, Mississippi (the station was not yet in operation at the time of the survey). All gamma ray data were collected by flying east-west lines spaced 152 meters apart at an altitude 91 meters above ground level. Processed data showed that all gamma rays detected within the survey area were those expected from naturally occurring terrestrial background emitters. Count rates obtained from the aerial platform were converted to exposure rates at 1 meter above the ground and are presented in the form of an isoradiation contour map. The observed exposure rates were between 5 and 13 microroentgens per hour (μR/h), with most of the area ranging from 9 to 10 μR/h. These values include an estimated cosmic ray contribution of 3.6 μR/h. The exposure rate obtained from soil samples and ionization chamber measurements taken from within the survey site displayed positive agreement with the aerial data

Research on the method of establishing the total radiation meter calibration device

Science.gov (United States)

Gao, Jianqiang; Xia, Ming; Xia, Junwen; Zhang, Dong

2015-10-01

Pyranometer is an instrument used to measure the solar radiation, according to pyranometer differs as installation state, can be respectively measured total solar radiation, reflected radiation, or with the help of shading device for measuring scattering radiation. Pyranometer uses the principle of thermoelectric effect, inductive element adopts winding plating type multi junction thermopile, its surface is coated with black coating with high absorption rate. Hot junction in the induction surface, while the cold junction is located in the body, the cold and hot junction produce thermoelectric potential. In the linear range, the output signal is proportional to the solar irradiance. Traceability to national meteorological station, as the unit of the national legal metrology organizations, the responsibility is to transfer value of the sun and the earth radiation value about the national meteorological industry. Using the method of comparison, with indoor calibration of solar simulator, at the same location, standard pyranometer and measured pyranometer were alternately measured radiation irradiance, depending on the irradiation sensitivity standard pyranometer were calculated the radiation sensitivity of measured pyranometer. This paper is mainly about the design and calibration method of the pyranometer indoor device. The uncertainty of the calibration result is also evaluated.

Development of aerial gamma radiation survey system, 4

International Nuclear Information System (INIS)

Saito, Kimiaki; Nagaoka, Toshi; Sakamoto, Ryuichi; Tsutsumi, Masahiro; Moriuchi, Shigeru

1985-02-01

Field experiments have been performed by JAERI since 1982 to obtain fundamental data required for development of aerial radiation survey system. In order to supplement the fundamental radiation data, theoretical calculations have been carried out. The utilized Monte Carlo transport program was verified by simulative calculations of the field experiments, and characteristics data on environmental gamma rays have been accumulated. In this report, the field experiments in 1981 and 1982 were simulated making use of the Monte Carlo transport calculation code YURI developed in JAERI. Comparisons were made between experimental and calculated results for exposure rate and flux density originated from terrestrial sources, and from a point source at height of 2.5 m above the ground. Good agreements between the data verified the transport program. As fundamental characteristics data on environmental gamma rays, spatial distributions of exposure, fluence, energy spectra, angular spectra and average energy were reported and discussed, for terrestrial sources of 40 K, 232 Th-series and 238 U-series, for a plane source on the ground and for a point source at 2.5 m above the ground. (author)

A background radiation survey along the transcontinental railway in Australia

International Nuclear Information System (INIS)

Minato, Susumu; Kodaira, Kazuo; Ito, Masaru

1995-01-01

This article reports a survey, carried out during a period from October 31 to November 3, 1994 in Australia, as well as some basic techniques of train-borne measurements for estimating outdoor gamma-ray dose rates. Surface rock and bedrock data are presented for convenience for geological analysis. Cosmic-ray dose rates estimated from atmospheric pressure data are also presented for researchers who are interested in total background radiation dose rates. It was found that gamma levels can be high in the western area. The dose rate data were based on the shielding correction factor evaluated at platforms in many stations. To confirm the validity of this method, the data from train-borne surveys in central Japan were compared with the present Australian data. There were, to some extent, correlations between them. The present study suggests that the train-borne measurements are useful for surveying wide area in a short time with an error of about 20%. (N.K.)

Assessment of medical radiation exposure to patients and ambient doses in several diagnostic radiology departments

Science.gov (United States)

Sulieman, A.; Elhadi, T.; Babikir, E.; Alkhorayef, M.; Alnaaimi, M.; Alduaij, M.; Bradley, D. A.

2017-11-01

In many countries diagnostic medical exposures typically account for a very large fraction of the collective effective dose that can be assigned to anthropological sources and activities. This in part flags up the question of whether sufficient steps are being taken in regard to potential dose saving from such medical services. As a first step, one needs to survey doses to compare against those of best practice. The present study has sought evaluation of the radiation protection status and patient doses for certain key radiological procedures in four film-based radiology departments within Sudan. The radiation exposure survey, carried out using a survey meter and quality control test tools, involved a total of 299 patients their examinations being carried out at one or other of these four departments. The entrance surface air kerma (ESAK) was determined from exposure settings using DosCal software and an Unfors -Xi-meter. The mean ESAK for x-ray examination of the chest was 0.30±0.1 mGy, for the skull it was 0.96±0.7 mGy, for the abdomen 0.85±0.01 mGy, for spinal procedures 1.30±0.6 mGy and for procedures involving the limbs it was 0.43±0.3 mGy. Ambient dose-rates in the reception area, at the closed door of the x-ray room, recorded instantaneous values of up to 100 μSv/h. In regard to protection, the associated levels were found to be acceptable in three of the four departments, corrective action being required for one department, regular quality control also being recommended.

Performance of a glucose meter with a built-in automated bolus calculator versus manual bolus calculation in insulin-using subjects.

Science.gov (United States)

Sussman, Allen; Taylor, Elizabeth J; Patel, Mona; Ward, Jeanne; Alva, Shridhara; Lawrence, Andrew; Ng, Ronald

2012-03-01

Patients consider multiple parameters in adjusting prandial insulin doses for optimal glycemic control. Difficulties in calculations can lead to incorrect doses or induce patients to administer fixed doses, rely on empirical estimates, or skip boluses. A multicenter study was conducted with 205 diabetes subjects who were on multiple daily injections of rapid/ short-acting insulin. Using the formula provided, the subjects manually calculated two prandial insulin doses based on one high and one normal glucose test result, respectively. They also determined the two doses using the FreeStyle InsuLinx Blood Glucose Monitoring System, which has a built-in, automated bolus calculator. After dose determinations, the subjects completed opinion surveys. Of the 409 insulin doses manually calculated by the subjects, 256 (63%) were incorrect. Only 23 (6%) of the same 409 dose determinations were incorrect using the meter, and these errors were due to either confirmed or potential deviations from the study instructions by the subjects when determining dose with meter. In the survey, 83% of the subjects expressed more confidence in the meter-calculated doses than the manually calculated doses. Furthermore, 87% of the subjects preferred to use the meter than manual calculation to determine prandial insulin doses. Insulin-using patients made errors in more than half of the manually calculated insulin doses. Use of the automated bolus calculator in the FreeStyle InsuLinx meter minimized errors in dose determination. The patients also expressed confidence and preference for using the meter. This may increase adherence and help optimize the use of mealtime insulin. © 2012 Diabetes Technology Society.

Assessment of ambient dose equivalent rate performance of an automatic survey meter as an instrument to quantify the presence of radiation in soils

CERN Document Server

Yoshimura, E M; Okuno, E

2002-01-01

Those who work in radiation protection are faced with various quantities that were created to account for the effects of ionizing radiation in the human body. As far as the experimental point of view is concerned, each available equipment is planned to measure a distinct quantity, for a specific radiation protection application, and it is not always clear which one it is. This paper shows a series of tests, planned and applied to a portable gamma ray spectrometer, in order to assure that the monitoring low dose levels of radiation with it is reliable. The equipment is fully automated and does not allow modifications of the conversion factors from counts to ambient dose equivalent. It is therefore necessary to assure that the values provided by the equipment are correct and refer to the actual situation one expects to find in practice. The system is based on an NaI(Tl) scintillation detector, mounted with its electronics in a portable case, suitable for field measurements. It measures ambient dose equivalent r...

Sampling strategy for a large scale indoor radiation survey - a pilot project

International Nuclear Information System (INIS)

Strand, T.; Stranden, E.

1986-01-01

Optimisation of a stratified random sampling strategy for large scale indoor radiation surveys is discussed. It is based on the results from a small scale pilot project where variances in dose rates within different categories of houses were assessed. By selecting a predetermined precision level for the mean dose rate in a given region, the number of measurements needed can be optimised. The results of a pilot project in Norway are presented together with the development of the final sampling strategy for a planned large scale survey. (author)

Radiation exposure and radiation hazards of human population. Pt. 1

International Nuclear Information System (INIS)

Jacobi, W.

1982-01-01

The present Part I provides a survey on the various sources of natural and artificial radiation exposure of human population. Furthermore, biological radiation effects and radiation damages are surveyed. In an appendix, radiation types, radiation doses, and radiation dose units are explained. (orig./GSCH) [de

External gamma radiation dose studies in the proposed uranium mining areas of Andhra Pradesh, India

International Nuclear Information System (INIS)

Reddy, P.; Reddy, K.; Reddy, C.; Reddy, K.

2006-01-01

Natural radiation sources contribute the largest component to the total effective dose received by the human population. Among these sources, natural background gamma radiation shares a noteworthy amount. The present study aims at the establishment of baseline environmental gamma radiation data in the environs of proposed uranium mining areas of Andhra Pradesh, India. To this end, a systematic study has been undertaken using Thermoluminescence (T.L.) dosimeters and G.M. (Geiger - Muller) tube based survey meter. These levels are estimated both indoors and outdoors in the study area covering about 23 villages surrounding the proposed mining sites. The estimated external gamma radiation levels (air kerma) varied from 0.605 to 4.39 mGy.y -1 . The mean indoor to outdoor radiation level ratio is found to be 1.1 ± 0.1. The estimated mean equivalent doses due to external background radiation in the villages of the study area range from 1.03 to 2.83 mSv.y -1 with a mean of 2.34 ± 0.39 mSv.y -1 . (authors)

External radiation surveillance

Energy Technology Data Exchange (ETDEWEB)

Antonio, E.J.

1995-06-01

This section of the 1994 Hanford Site Environmental Report describes how external radiation was measured, how surveys were performed, and the results of these measurements and surveys. External radiation exposure rates were measured at locations on and off the Hanford Site using thermoluminescent dosimeters (TLD). External radiation and contamination surveys were also performed with portable radiation survey instruments at locations on and around the Hanford Site.