WorldWideScience

Sample records for monitor radiation levels

  1. Background compensation for a radiation level monitor

    Science.gov (United States)

    Keefe, D.J.

    1975-12-01

    Background compensation in a device such as a hand and foot monitor is provided by digital means using a scaler. With no radiation level test initiated, a scaler is down-counted from zero according to the background measured. With a radiation level test initiated, the scaler is up-counted from the previous down-count position according to the radiation emitted from the monitored object and an alarm is generated if, with the scaler having crossed zero in the positive going direction, a particular number is exceeded in a specific time period after initiation of the test. If the test is initiated while the scale is down-counting, the background count from the previous down- count stored in a memory is used as the initial starting point for the up-count.

  2. Radiation levels from computer monitor screens within Benue State ...

    African Journals Online (AJOL)

    Investigation of possible presence of soft X-ray levels from Computer Screens at distances of 0.5m and 1.0m was carried out within Benue State University, Makurdi, using ten different monitor models. Radiation measurement was carried out using a portable digital radiation meter, INSPECTOR 06250 (SE international Inc.

  3. Monitoring of low level environmental gamma exposure by the centralized radiation monitoring system

    International Nuclear Information System (INIS)

    Katagiri, Hiroshi; Kobayashi, Hideo; Obata, Kazuichi; Kokubu, Morinobu; Itoh, Naoji

    1981-07-01

    In the Japan Atomic Energy Research Institute (JAERI), a centralized automatic radiation monitoring system developed 20 years ago has recently been improved to monitor low level gamma radiation more accurately in normal operation of the nuclear facilities and to detect abnormal radioactive releases more effectively. The present state of the system is described. This system puts together environmental monitoring data such as gamma exposure rate (20 points), radioactive concentration in the air (4 points) and in water (2 drains), and meteorological items (14 including wind directions, wind speeds, solar radiation and air temperatures at a observation tower of 40 m height). Environmental monitoring around the JAERI site is carried out effectively using the system. Data processing system consists of a central processing unit, a magnetic disk, a magnetic tape, a line printer and a console typewriter. The data at respective monitoring points are transmitted to the central monitoring room by wireless or telephone line. All data are printed out and field in magnetic disk and magnetic tape every 10 minutes. When the emergency levels are exceeded, however, the data are automatically output on a line printer every 2 minute. This system can distinguish very low gamma exposure due to gaseous effluents, about 1 mR/y, from the background. Even in monthly exposures, calculated values based on the data of release amount and meteorology are in good agreement with the measured ones. (author)

  4. Modular remote radiation monitor

    International Nuclear Information System (INIS)

    Lacerda, Fabio; Farias, Marcos S.; Aghina, Mauricio A.C.; Oliveira, Mauro V.

    2013-01-01

    The Modular Remote Radiation Monitor (MRRM) is a novel radiation monitor suitable for monitoring environmental exposure to ionizing radiation. It is a portable compact-size low-power microprocessor-based electronic device which provides its monitoring data to other electronic systems, physically distant from it, by means of an electronic communication channel, which can be wired or wireless according to the requirements of each application. Besides its low-power highly-integrated circuit design, the Modular Remote Radiation Monitor is presented in a modular architecture, which promotes full compliance to the technical requirements of different applications while minimizing cost, size and power consumption. Its communication capability also supports the implementation of a network of multiple radiation monitors connected to a supervisory system, capable of remotely controlling each monitor independently as well as visualizing the radiation levels from all monitors. A prototype of the MRRM, functionally equivalent to the MRA-7027 radiation monitor, was implemented and connected to a wired MODBUS network of MRA-7027 monitors, responsible for monitoring ionizing radiation inside Argonauta reactor room at Instituto de Engenharia Nuclear. Based on the highly positive experimental results obtained, further design is currently underway in order to produce a consumer version of the MRRM. (author)

  5. Radiation monitoring: an introduction. Rev. ed.

    International Nuclear Information System (INIS)

    Hayward, P.; Arnott, D.

    1987-01-01

    This Greenpeace pamphlet has been produced in reponse to requests from members of the public wishing to set up monitoring groups. It lists some U.K. manufacturers of radiation monitoring equipment and the contributors have summarized information available from manufacturer's own catalogues describing the equipment, what it will and will not do and costing various programmes. Three types of monitoring are discussed: monitoring the level of background gamma radiation, monitoring radioactive contamination, (early warning systems), and monitoring food and environmental samples for very low levels of radiation. (UK)

  6. NRC TLD Direct Radiation Monitoring Network

    International Nuclear Information System (INIS)

    Struckmeyer, R.; McNamara, N.

    1992-06-01

    The US Nuclear Regulatory Commission (NRC) Direct Radiation Monitoring Network is operated by the NRC in cooperation with participating states to provide continuous measurement of the ambient radiation levels around licensed NRC facilities, primarily power reactors. Ambient radiation levels result from naturally occurring radionuclides present in the soil, cosmic radiation constantly bombarding the earth from outer space, and the contribution, if any, from the monitored facilities and other man-made sources. The Network is intended to measure radiation levels during routine facility operations and to establish background radiation levels used to assess the radiological impact of an unusual condition, such as an accident. This report presents the radiation levels measured around all facilities in the Network for the first quarter of 1992. All radiation measurements are made using small, passive detectors called thermoluminescent dosimeters (TLDs), which provide a quantitative measurement of the radiation levels in the area in which they are placed. Each site is monitored by arranging approximately 40 to 50 TLD stations in two concentric rings extending to about five miles from the facility. All TLD stations are outside the site boundary of the facility

  7. Radiation monitoring at Pakistan research reactor

    International Nuclear Information System (INIS)

    Ali, A.

    1984-05-01

    Area radiation monitoring is accomplished by using Tracer Lab. radiation monitor. Personnel monitoring is carried out using film badges, TLDs (Thermoluminescent Dosimeters) and pocket dosimeters. For the evaluation of monthly accumulated doses of radiation workers film badges/TLDs and for instantaneous/short term dose measurement in higher radiation zones pocket dosimeters are used in addition to film badge/TLD. Environmental monitoring is necessary to check the PARR operation effect on background radiation level in the vicinity of PINSTECH. (A.B.). 4 refs

  8. Computer-controlled radiation monitoring system

    International Nuclear Information System (INIS)

    Homann, S.G.

    1994-01-01

    A computer-controlled radiation monitoring system was designed and installed at the Lawrence Livermore National Laboratory's Multiuser Tandem Laboratory (10 MV tandem accelerator from High Voltage Engineering Corporation). The system continuously monitors the photon and neutron radiation environment associated with the facility and automatically suspends accelerator operation if preset radiation levels are exceeded. The system has proved reliable real-time radiation monitoring over the past five years, and has been a valuable tool for maintaining personnel exposure as low as reasonably achievable

  9. Radiation monitoring

    International Nuclear Information System (INIS)

    Larsson, L.Eh.; B'yuli, D.K.; Karmikel, Dzh.Kh.E.

    1985-01-01

    Recommendations on radiation monitoring of personnel, used medical ionizing radiation source, are given. The necessity to carry out radiation monitoring of situation at medical personnel's positions and personnel dosimetry is marked. It is convenient to subdivide radiation monitoring into 3 types: usual, surgical and special. Usual monitoring is connected with current work; surgical monitoring is carried out to receive information during a concrete operation; special monitoring is used to detect possible deviation from standard conditions of work or when suspecting them

  10. Development of an omnidirectional gamma-ray imaging Compton camera for low-radiation-level environmental monitoring

    Science.gov (United States)

    Watanabe, Takara; Enomoto, Ryoji; Muraishi, Hiroshi; Katagiri, Hideaki; Kagaya, Mika; Fukushi, Masahiro; Kano, Daisuke; Satoh, Wataru; Takeda, Tohoru; Tanaka, Manobu M.; Tanaka, Souichi; Uchida, Tomohisa; Wada, Kiyoto; Wakamatsu, Ryo

    2018-02-01

    We have developed an omnidirectional gamma-ray imaging Compton camera for environmental monitoring at low levels of radiation. The camera consisted of only six CsI(Tl) scintillator cubes of 3.5 cm, each of which was readout by super-bialkali photo-multiplier tubes (PMTs). Our camera enables the visualization of the position of gamma-ray sources in all directions (∼4π sr) over a wide energy range between 300 and 1400 keV. The angular resolution (σ) was found to be ∼11°, which was realized using an image-sharpening technique. A high detection efficiency of 18 cps/(µSv/h) for 511 keV (1.6 cps/MBq at 1 m) was achieved, indicating the capability of this camera to visualize hotspots in areas with low-radiation-level contamination from the order of µSv/h to natural background levels. Our proposed technique can be easily used as a low-radiation-level imaging monitor in radiation control areas, such as medical and accelerator facilities.

  11. Monitoring of external background radiation level in Asa dam ...

    African Journals Online (AJOL)

    An external background ionizing radiation study has been carried out within the Asa Dam Industrial Layout of Ilorin in Kwara State. The study was carried out in 5 stations within the industrial area using two Digilert Nuclear Radiation Monitors. The study has revealed that the external background ionizing radiation is ...

  12. Air and radiation monitoring stations

    CERN Multimedia

    AUTHOR|(SzGeCERN)582709

    2015-01-01

    CERN has around 100 monitoring stations on and around its sites. New radiation measuring stations, capable of detecting even lower levels of radiation, were installed in 2014. Two members of HE-SEE group (Safety Engineering and Environment group) in front of one of the new monitoring stations.

  13. Radiation monitoring system

    Energy Technology Data Exchange (ETDEWEB)

    Aghina, Mauricio A.C.; Farias, Marcos S. de; Lacerda, Fabio de; Heimlich, Adino [Instituto de Engenharia Nuclear (IEN/CNEN-RJ), Rio de Janeiro, RJ (Brazil)

    2015-07-01

    Design of a portable low-power multichannel analyzer with wireless connectivity for remote radiation monitoring, powered from a solar panel with a internal battery to be operated in field. The multichannel analyzer is based on a single microcontroller which performs the digital functions and an analog signal processing board for implementing a Gaussian shaper preamplifier, a Gaussian stretcher, sample and hold, pile-up rejector and a 10 bit ADC. Now this design is to be used with a NaI(Ti) scintillator detector. This multichannel analyzer is designed to be a part of radiation monitoring network. All of them are connected, by radio in a radius of 10 kilometers, to a supervisor computer that collects data from the network of multichannel analyzers and numerically display the latest radiation measurements or graphically display measurements over time for all multichannel analyzers. Like: dose rate, spectra and operational status. Software also supports remotely configuring operating parameters (such as radiation alarm level) for each monitor independently. (author)

  14. Radiation monitoring system

    International Nuclear Information System (INIS)

    Aghina, Mauricio A.C.; Farias, Marcos S. de; Lacerda, Fabio de; Heimlich, Adino

    2015-01-01

    Design of a portable low-power multichannel analyzer with wireless connectivity for remote radiation monitoring, powered from a solar panel with a internal battery to be operated in field. The multichannel analyzer is based on a single microcontroller which performs the digital functions and an analog signal processing board for implementing a Gaussian shaper preamplifier, a Gaussian stretcher, sample and hold, pile-up rejector and a 10 bit ADC. Now this design is to be used with a NaI(Ti) scintillator detector. This multichannel analyzer is designed to be a part of radiation monitoring network. All of them are connected, by radio in a radius of 10 kilometers, to a supervisor computer that collects data from the network of multichannel analyzers and numerically display the latest radiation measurements or graphically display measurements over time for all multichannel analyzers. Like: dose rate, spectra and operational status. Software also supports remotely configuring operating parameters (such as radiation alarm level) for each monitor independently. (author)

  15. Offsite environmental monitoring report: Radiation monitoring around United States nuclear test areas

    International Nuclear Information System (INIS)

    1990-01-01

    This report describes the Offsite Radiation Safety Program conducted during 1990 by the Environmental Protection Agency's (EPA's) Environmental Monitoring Systems Laboratory -- Las Vegas. This laboratory operates an environmental radiation monitoring program in the region surrounding the Nevada Test Site (NTS) and at former test sites in Alaska, Colorado, Mississippi, Nevada, and New Mexico. The surveillance program is designed to measure levels and trends of radioactivity, if present, in the environment surrounding testing areas to ascertain whether current radiation levels and associated doses to the general public are in compliance with existing radiation protection standards. The surveillance program additionally has the responsibility to take action to protect the health and well being of the public in the event of any accidental release of radioactive contaminants. Offsite levels of radiation and radioactivity are assessed by sampling milk, water, and air; by deploying thermoluminescent dosimeters (TLDs) and using pressurized ion chambers (PICs); and by biological monitoring of animals, food crops, and humans. Personnel with mobile monitoring equipment are placed in areas downwind from the test site prior to each nuclear weapons test to implement protective actions, provide immediate radiation monitoring, and obtain environmental samples rapidly after any occurrence of radioactivity release

  16. Radiation monitoring system

    International Nuclear Information System (INIS)

    Takeuchi, Nobuyoshi; Fujimoto, Toshiaki; Nagama, Hideyo

    2007-01-01

    A positive outlook toward nuclear power plants and a higher level of technologies for using radiation in the medical field are trends that are spreading throughout the world, and as a consequence, demand is increasing for equipment and systems that measure and control radiation. Equipment ranging from radiation detection and measurement devices to computer-based radiation management systems will be set up in overseas. Products that depend on overseas specifications based on IEC and other international standards are being developed. Fuji Electric is advancing the overseas deployment of radiation monitoring systems by adopting measures that will ensure the reliability and traceability of radiation equipment. (author)

  17. Professional exposure of medical workers: radiation levels, radiation risk and personal dose monitoring

    International Nuclear Information System (INIS)

    Bai Guang

    2005-01-01

    The application of radiation in the field of medicine is the most active area. Due to the rapid and strong development of intervention radiology at present near 20 years, particularly, the medical workers become a popularize group which most rapid increasing and also receiving the must high of professional exposure dose. Because, inter alias, radiation protection management nag training have not fully follow up, the aware of radioactive protection and appropriate approach have tot fully meet the development and need, the professional exposure dose received by medical workers, especially those being engaged in intervention radiology, are more higher, as well as have not yet fully receiving the complete personal dose monitoring, the medical workers become the population group which should be paid the most attention to. The writer would advice in this paper that all medical workers who being received a professional radiation exposure should pay more attention to the safety and healthy they by is strengthening radiation protection and receiving complete personal dose monitoring. (authors)

  18. RTP Radiation Monitoring System

    International Nuclear Information System (INIS)

    Alfred, S.L.; Mohd Fairus Abdul Farid; Ahmad Nabil Abdul Rahim; Nurhayati Ramli

    2015-01-01

    Radiation Monitoring System aiming to limiting dose exposed to personnel to the lowest level referring to the concept of ALARA (As Low As Reasonably Achievable). Atomic Energy Licensing (Basic Safety Radiation Protection) Regulation 2010 (Act 304) is a baseline to control employee and public radiation protection program and guideline, as well as to meet the requirement of the Occupational Safety and Health 1994 (Act 514). (author)

  19. Environmental radiation monitoring of Vizag City

    International Nuclear Information System (INIS)

    Sreekanth, B.; Narsaiah, M.V.R.; Saindane, Shashank; Pujari, Raju; Krishna, N.S.; Sambamurthy, T.; Chaudhury, Probal; Pradeepkumar, K.S.

    2014-01-01

    Radiological impact assessment is to be carried out following any radiological emergency to implement the required counter measures. A ground based environmental radiation monitoring of Vizag city has been carried out by installing various radiation monitoring instruments in a vehicle to generate the base line radiation data. It also helps to check the illicit trafficking of radioactive sources and also identifying the orphan sources. The average background radiation level observed in Vizag city was 80 nGy/h. Database of baseline radiation level with GPS location at all important locations of the whole city has been developed. No illicit trafficking of radioactive materials and orphan sources were detected during the survey. All the detectors used in the survey shown good correlation in their response. The study showed that mobile monitoring methodology will be useful in the quick assessment of radiological impact and strengthens the decision makers in reducing consequences by initiating immediate counter measures

  20. Environmental radiation monitoring from the decommission of TRIGA

    Energy Technology Data Exchange (ETDEWEB)

    Choi, Geun Sik; Lee, Chang Woo

    2000-03-01

    Environmental radiation monitoring was carried out with measurement of environmental radiation and environmental radioactivity analysis around TRIGA Research Reactor. The results of environmental radiation monitoring around TRIGA Research Reactor are the follows: The average level of environmental radiation measured by potable ERM and accumulated radiation dose by TLD was almost same level compared with thepast years. Gross {beta} radioactivity in environmental samples showed a environmental level. {gamma}-radionuclides in water samples were not detected. but only radionuclide K-40, which is natural radionuclide, was detected in the all samples and Cs-137 was detected in the surface soil and discharge sediment. (author)

  1. Environmental radiation monitoring around the nuclear facilities

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Chang Woo; Choi, Geun Sik and others

    2001-02-01

    Environmental Radiation Monitoring was carried out with measurement of environment. Radiation and environmental radioactivity analysis around KAERI nuclear facilities and Seoul Research Reactor. The results of environmental radiation monitoring around KAERI nuclear facilities and Seoul Research Reactor are the follows : The average level of environmental radiation dose measured by NaI scintillation counter and accumulated radiation dose by TLD was almost same level compared with the past years. Gross {alpha}, {beta} radioactivity in environmental samples showed a environmental level. {gamma}-radionuclides in water samples were not detected. But only radionuclide K-40, which is natural radionuclide, was detected in the all samples and Cs-137 was detected in the surface soil and discharge sediment. The average level of environmental radiation dose around Seoul Research Reactor was almost same level compared with the past years, and Be-7 and Cs-137 were detected in some surface soil and discharge sediment by {gamma}-spectrometry.

  2. Environmental radiation monitoring around the nuclear facilities

    International Nuclear Information System (INIS)

    Lee, Chang Woo; Choi, Young Ho

    2000-02-01

    Environmental radiation monitoring was carried out with measurement of environment radiation and environmental radioactivity analysis around KAERI nuclear facilities and Seoul Research Reactor. The results of environmental radiation monitoring around KAERI nuclear facilities and Seoul Research Reactor are the follows: The average level of environmental radiation dose measured by NaI scintillation counter and accumulated radiation dose by TLD was almost some level compared with the past years. Gross α, β radioactivity in environmental samples showed a environmental level. γ-radionuclides in water sample were not detected. But only radionuclide K-40, which is natural radionuclide, was detected in the all samples and Cs-137 was detected in the surface soil and discharge sediment. The average level of environmental radiation dose around Seoul Research Reactor was almost same level compared with the past years, and Be-7 and Cs-137 were detected in some surface soil and discharge sediment by γ-spectrometry. (author)

  3. Environmental radiation monitoring around the nuclear facilities

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Chang Woo; Choi, Young Ho

    2000-02-01

    Environmental radiation monitoring was carried out with measurement of environment radiation and environmental radioactivity analysis around KAERI nuclear facilities and Seoul Research Reactor. The results of environmental radiation monitoring around KAERI nuclear facilities and Seoul Research Reactor are the follows: The average level of environmental radiation dose measured by NaI scintillation counter and accumulated radiation dose by TLD was almost some level compared with the past years. Gross {alpha}, {beta} radioactivity in environmental samples showed a environmental level. {gamma}-radionuclides in water sample were not detected. But only radionuclide K-40, which is natural radionuclide, was detected in the all samples and Cs-137 was detected in the surface soil and discharge sediment. The average level of environmental radiation dose around Seoul Research Reactor was almost same level compared with the past years, and Be-7 and Cs-137 were detected in some surface soil and discharge sediment by {gamma}-spectrometry. (author)

  4. Environmental radiation monitoring around the nuclear facilities

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Chang Woo; Choi, Young Ho; Lee, M.H. [and others

    1999-02-01

    Environmental radiation monitoring was carried out with measurement of environment radiation and environmental radioactivity analysis around KAERI nuclear facilities and Seoul research reactor. The results of environmental radiation monitoring around KAERI nuclear facilities and Seoul research reactor are the follows : The average level of environmental radiation dose measured by NaI scintillation counter and accumulated radiation dose by TLD was almost same level compared with the past years. Gross {alpha}, {beta} radioactivity in environmental samples showed a environmental level. {gamma}-radionuclides in water samples were not detected. But only radionuclide K-40, which is natural radionuclide, was detected in the all samples and Cs-137 was detected in the surface soil and discharge sediment. The average level of environmental radiation dose around Seoul research reactor was almost same level compared with the past years, and Be-7 and Cs-137 were detected in some surface soil and discharge sediment by {gamma}-spectrometry. (author). 3 refs., 50 tabs., 12 figs.

  5. Environmental radiation monitoring around the nuclear facilities

    International Nuclear Information System (INIS)

    Lee, Chang Woo; Choi, Geun Sik and others

    2001-02-01

    Environmental Radiation Monitoring was carried out with measurement of environment. Radiation and environmental radioactivity analysis around KAERI nuclear facilities and Seoul Research Reactor. The results of environmental radiation monitoring around KAERI nuclear facilities and Seoul Research Reactor are the follows : The average level of environmental radiation dose measured by NaI scintillation counter and accumulated radiation dose by TLD was almost same level compared with the past years. Gross α, β radioactivity in environmental samples showed a environmental level. γ-radionuclides in water samples were not detected. But only radionuclide K-40, which is natural radionuclide, was detected in the all samples and Cs-137 was detected in the surface soil and discharge sediment. The average level of environmental radiation dose around Seoul Research Reactor was almost same level compared with the past years, and Be-7 and Cs-137 were detected in some surface soil and discharge sediment by γ-spectrometry

  6. Environmental radiation monitoring from the decommission of TRIGA

    Energy Technology Data Exchange (ETDEWEB)

    Choi Geun Sik; Lee, Chang Woo [Korea Atomic Energy Research Institute, Taejon (Korea)

    1999-02-01

    Environmental Radiation Monitoring was carried out with measurement of environment radiation and environment radioactivity analysis around TRIGA Research Reactor. The results of environmental radiation monitoring around TRIGA Research Reactor are the follows: The average level of environmental radiation dose measured by potable ERM and accumulated radiation dose by TLD was almost same level compared with the past years. Gross {beta} radioactivity in environmental samples showed a environmental level. v-radionuclides in water samples were not detected. But only radionuclide K-40, which is natural radionuclide, was detected in the all samples and Cs-137 was detected in the surface soil and discharge sediment. 37 refs., 12 figs., 31 tabs. (Author)

  7. Analysis of food radiation monitoring system in Belarus

    International Nuclear Information System (INIS)

    1992-01-01

    Food radiation monitoring system in Belarus due to the Chernobyl accident is analysed. Structure of radiation monitoring network, instrumentation and modern developments. Information on permissible concentration levels in foodstuffs and water is presented and calculations of radionuclide intake for man are performed. Proposals on the creation of social centres of food radiation monitoring for Belarussian population are considered. 4 tabs

  8. Environmental radiation monitoring around the research reactors

    International Nuclear Information System (INIS)

    Lee, Chang Woo; Lee, Hyun Duk; Kim, Sam Rang; Choi, Yong Ho; Kim, Jeong Moo; Lee, Myeon Joo; Lee, Myeong Ho; Hong, Kwang Hee; Lim, Moon Ho; Lee, Won Yoon; Park, Do Won; Choi, Sang Do

    1993-04-01

    Environmental radiation monitoring was carried out measurement of environmental radiation and environmental radioactivity analysis around KAERI nuclear facilities and Seoul research reactor. The results of environmental radiation monitoring around KAERI nuclear facilities and Seoul research reactor are the follows : The average level of environmental radiation dose measured by NaI scintillation counter and accumulated radiation dose by TLD was almost same level compared with the past years. Gross α, β radioactivity in environmental sample was not found abnormal data. γ-radionuclides in water samples were not detected. But only radionuclide K-40, which is natural radionuclide, was detected in the all samples and Cs-137 was detected in the surface soil and discharge sediment. The average level of environmental radiation dose around Seoul research reactor was almost same level compared with the past years, and Be-7 and Cs-137 were detected in some surface soil and discharge sediment by γ-spectrometry. (Author)

  9. NRC TLD Direct Radiation Monitoring Network

    International Nuclear Information System (INIS)

    Struckmeyer, R.

    1994-03-01

    This report presents the results of the NRC Direct Radiation Monitoring Network for the fourth quarter of 1993. It provides the ambient radiation levels measured in the vicinity of 75 sites throughout the United States. In addition, it describes the equipment used, monitoring station selection criteria, characterization of the dosimeter response, calibration procedures, statistical methods, intercomparison, and quality assurance program

  10. NRC TLD Direct Radiation Monitoring Network

    International Nuclear Information System (INIS)

    Struckmeyer, R.; McNamara, N.

    1993-03-01

    This report present the results of the NRC Direct Radiation Monitoring Network for the fourth quarter of 1992. It provides the ambient radiation levels measured in the vicinity of 75 sites throughout the United States. In addition, it describes the equipment used, monitoring station selection criteria, characterization of the dosimeter response, calibration procedures, statistical methods, intercomparison, and quality assurance program

  11. Routine sanitary radiation monitoring

    International Nuclear Information System (INIS)

    Marej, A.N.

    1984-01-01

    Hygienic bases and organization principles of radiation monitoring realized in the process of operation of nuclear power engineering enterprises are considered. The monitoring is aimed at prevention from a negative effect of ionizing radiations on public heath. It is achieved by solution of the following tasks: realization of control over radioactive waste disposal into environment, control over the level of radioactive substance content in evironmental objects, control over external and internal irradiation of population assessment of environmental radiactivity of certain regions and of the territory of the country with the subsequent informing the corresponding organizations and population

  12. Development of web monitoring radiation area monitor

    International Nuclear Information System (INIS)

    Jung, Hoon Jin; Lee, Jun Hee; Namkoong, Phil; Lee, Dong Hoon; Lee, Su Hong; Lee, Gun Bae

    2005-01-01

    Recently the increasing number of radioisotope industry and nuclear facility have ever raised the possibility of radiation safety accident. As such a result, radioisotope companies and nuclear facility operators have become to be much interested in radiation area monitoring for efficient radiation protection. At present, almost of the radiation area monitors which are imported products are outdated in aspect of their functions. Diversification of the monitoring work is urgently demanding additional functions to be added. Thus we have developed new-type digital area monitor which enables remote web monitoring with image and radiation dose rate value at distant places through using internet, the latest IT technology, and radiation measurement technology

  13. Integrated nuclear radiation detector and monitor

    International Nuclear Information System (INIS)

    Biehl, B.L.; Lieberman, S.I.

    1982-01-01

    A battery powered device which can continuously monitor and detect nuclear radiation utilizing fully integrated circuitry and which is provided with an alarm which alerts persons when the radiation level exceeds a predetermined threshold

  14. NRC TLD Direct Radiation Monitoring Network

    International Nuclear Information System (INIS)

    Struckmeyer, R.; McNamara, N.

    1991-04-01

    This report presents the results of the NRC [Nuclear Regulatory Commission] Direct Radiation Monitoring Network for the fourth quarter of 1990. It provides the ambient radiation levels measured in the vicinity of 75 sites throughout the United States. In addition, it describes the equipment used, monitoring station selection criteria, characterization of the dosimeter response, calibration procedures, statistical methods, intercomparison, and quality assurance program. 3 figs., 4 tabs

  15. Environmental radiation monitoring

    International Nuclear Information System (INIS)

    Watanabe, Isao

    2011-01-01

    The samples, pretreatment method, and measurement methods of 'Environmental radioactivity level by prefecture' of Ministry of Education, Culture, Sports, Science and Education (MEXT) is explained. It consists of 1), 'Environmental radioactivity level by prefecture' in normal period, 2) 'Strengthening of Monitoring of Environmental Radioactivity Level by Prefecture' of MEXT at emergency 3) strengthening of monitoring by Fukushima Daiichi nuclear accident, 4) radiation monitoring around the nuclear facility, 5) strengthening of monitoring by MEXT, and 6) quality of monitoring. The survey item and samples etc., of 'Environmental radioactivity level by prefecture', monitoring post, NaI (Tl) scintillation survey meter, sampling and pretreatment methods for radionuclide analysis in normal period, an example of germanium semiconductor detector, gamma ray spectrum of spaghetti from Italy by germanium semiconductor detector, flow chart of radionuclide analysis of fallout in normal period and emergency by germanium semiconductor detector, example of analytical method of radioactive strontium ( ion exchange method), outline of plutonium analytical method for emergency, sampling and pretreatment methods of radionuclides for strengthening, monitoring result around Fukushima Daiichi nuclear plant from June 23 to 24, 2011, change of air dose rate of monitoring post in Mito city from March 14 to 26, 2011, concentration of I-131 and Cs-137 in fallout in Hitachinaka city from March 19 to April 30, 2011, and change of concentration of I-131, Cs-134 and Cs-137 in tap water of Iitate village from March 20 to April 30, 2011, are illustrated. (S.Y.)

  16. Radiation monitor system for nuclear power plants

    International Nuclear Information System (INIS)

    Wu Bingzhe; Guo Shusheng

    1990-12-01

    The system has 8 kinds of radiation monitors and 2 stage microcomputers designed for processing the data from each monitor, storaging the information, printing out and displaying on the colour CRT. The function of the system includes high-value alarm, warm alarm and failure alarm, so called t hree-level alarms . Two functions of the alarms are the threshold alarm and the tendency alarm, so that this system is an intelligency system. This system has high reliability and very wide range when LOCA accident takes place. It is aseismic and immune to industrial interference. The system can meet IEC-761-1 standard and is of nuclear safety 3rd class. Also the following monitors were designed: 133 Xe monitor, 131 I monitor, low-level liquid monitor and high radiation γ area monitor. The system can meet the requirements of nuclear power plants

  17. NRC TLD Direct Radiation Monitoring Network

    International Nuclear Information System (INIS)

    Struckmeyer, R.; McNamara, N.

    1991-12-01

    This report provides the status and results of the NRC Thermoluminescent Dosimeter (TLD) Direct Radiation Monitoring Network. It presents the radiation levels measured in the vicinity of NRC licensed facilities throughout the country for the third quarter of 1991

  18. Radiation dose monitoring in the clinical routine

    Energy Technology Data Exchange (ETDEWEB)

    Guberina, Nika [UK Essen (Germany). Radiology

    2017-04-15

    Here we describe the first clinical experiences regarding the use of an automated radiation dose management software to monitor the radiation dose of patients during routine examinations. Many software solutions for monitoring radiation dose have emerged in the last decade. The continuous progress in radiological techniques, new scan features, scanner generations and protocols are the primary challenge for radiation dose monitoring software systems. To simulate valid dose calculations, radiation dose monitoring systems have to follow current trends and stay constantly up-to-date. The dose management software is connected to all devices at our institute and conducts automatic data acquisition and radiation dose calculation. The system incorporates 18 virtual phantoms based on the Cristy phantom family, estimating doses in newborns to adults. Dose calculation relies on a Monte Carlo simulation engine. Our first practical experiences demonstrate that the software is capable of dose estimation in the clinical routine. Its implementation and use have some limitations that can be overcome. The software is promising and allows assessment of radiation doses, like organ and effective doses according to ICRP 60 and ICRP 103, patient radiation dose history and cumulative radiation doses. Furthermore, we are able to determine local diagnostic reference doses. The radiation dose monitoring software systems can facilitate networking between hospitals and radiological departments, thus refining radiation doses and implementing reference doses at substantially lower levels.

  19. 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.

  20. Time-resolved monitoring of outdoor radiation levels in the Netherlands

    International Nuclear Information System (INIS)

    Smetsers, R.C.G.M.; Blaauboer, R.O.

    1994-01-01

    Risk management applied to human-induced radiological problems requires proper knowledge of what the situation would be without human interference. In cases where enhanced levels of natural radioactivity are present, this is far from simple, due to the existence of comparatively high and variable natural background levels. More knowledge on the spatial and temporal variety of natural radiation can help to decrease the uncertainty in the assessment of radiation doses from human activities. To obtain quantitative descriptions of natural processes one needs accurate data showing a high resolution in time and space. This paper first shows that data obtained from the Dutch National Radioactivity Monitoring network, although developed for nuclear emergency management, meets these requirements. Next, some early, but interesting, results from a current comprehensive study are reported. Parameter values are given which describe the influence of air pressure, airborne radioactivity and rainfall on ambient dose rate. From the analysis of data distributions of ambient dose rate, information is obtained on the probability of elevated recordings occurring in a certain time period; this information can be used to select warning levels for nuclear alarm systems. Data analysis of airborne radioactivity shows that concentrations of 222 Rn progeny are highly dependent on wind speed and direction. Results obtained for low wind speeds can be used to examine radon characteristics of the local environment while other results yield (aggregated) information about more remote areas. (Author)

  1. Radiation monitoring considerations for radiobiology facilities

    International Nuclear Information System (INIS)

    McClelland, T.W.; McFall, E.D.

    1976-01-01

    Battelle, Pacific Northwest Laboratories, conducts a wide variety of radiobiology and radioecology research in a number of facilities on the Hanford Reservation. Review of radiation monitoring problems associated with storage, plant and animal experiments, waste handling and sterile facilities shows that careful monitoring, strict procedural controls and innovative techniques are required to minimize occupational exposure and control contamination. Although a wide variety of radioactivity levels are involved, much of the work is with extremely low level materials. Monitoring low level work is mundane and often impractical but cannot be ignored in today's ever tightening controls

  2. Offsite environmental monitoring report: Radiation monitoring around United States nuclear test areas, calendar year 1991

    International Nuclear Information System (INIS)

    Chaloud, D.J.; Dicey, B.B.; Mullen, A.A.; Neale, A.C.; Sparks, A.R.; Fontana, C.A.; Carroll, L.D.; Phillips, W.G.; Smith, D.D.; Thome, D.J.

    1992-01-01

    This report describes the Offsite Radiation Safety Program conducted during 1991 by the Environmental Protection Agency's (EPA's) Environmental Monitoring Systems Laboratory-Las Vegas. This laboratory operates an environmental radiation monitoring program in the region surrounding the Nevada Test Site (NTS) and at former test sites in Alaska, Colorado, Mississippi, Nevada, and New Mexico. The surveillance program is designed to measure levels and trends of radioactivity, if present, in the environment surrounding testing areas to ascertain whether current radiation levels and associated doses to the general public are in compliance with existing radiation protection standards. The surveillance program additionally has the responsibility to take action to protect the health and well being of the public in the event of any accidental release of radioactive contaminants. Offsite levels of radiation and radioactivity are assessed by sampling milk, water, and air; by deploying thermoluminescent dosimeters (TLDs) and using pressurized ion chambers (PICs); and by biological monitoring of animals, food crops, and humans. Personnel with mobile monitoring equipment are placed in areas downwind from the test site prior to each nuclear weapons test to implement protective actions, provide immediate radiation monitoring, and obtain environmental samples rapidly after any occurrence of radioactivity release. Comparison of the measurements and sample analysis results with background levels and with appropriate standards and regulations indicated that there was no radioactivity detected offsite by the various EPA monitoring networks and no exposure above natural background to the population living in the vicinity of the NTS that could be attributed to current NTS activities. Annual and long-term trends were evaluated in the Noble Gas, Tritium, Milk Surveillance, Biomonitoring, TLD, PIC networks, and the Long-Term Hydrological Monitoring Program

  3. Radiation monitoring in interventional cardiology: a requirement

    Science.gov (United States)

    Rivera, T.; Uruchurtu, E. S.

    2017-01-01

    The increasing of procedures using fluoroscopy in interventional cardiology procedures may increase medical and patients to levels of radiation that manifest in unintended outcomes. Such outcomes may include skin injury and cancer. The cardiologists and other staff members in interventional cardiology are usually working close to the area under examination and they receive the dose primarily from scattered radiation from the patient. Mexico does not have a formal policy for monitoring and recording the radiation dose delivered in hemodynamic establishments. Deterministic risk management can be improved by monitoring the radiation delivered from X-ray devices. The objective of this paper is to provide cardiologist, techniques, nurses, and all medical staff an information on DR levels, about X-ray risks and a simple a reliable method to control cumulative dose.

  4. Monitoring of radiation exposure

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-02-01

    The guide specifies the requirements for the monitoring of radiation exposure in instances where radiation is used. In addition to workers, the guide covers students, apprentices and visitors. The guide shall also apply to exposure from natural radiation. However, the monitoring of radiation exposure in nuclear power plants is dealt with in YVL Guide 7.10 and 7.11. The guide defines the concepts relevant to the monitoring of radiation exposure and provides guidelines for determining the necessity of monitoring and subsequently arranging such in different operations. In addition, the guide specifies the criteria for the approval and regulatory control of the dosimetric service.

  5. Monitoring of radiation exposure

    International Nuclear Information System (INIS)

    2000-02-01

    The guide specifies the requirements for the monitoring of radiation exposure in instances where radiation is used. In addition to workers, the guide covers students, apprentices and visitors. The guide shall also apply to exposure from natural radiation. However, the monitoring of radiation exposure in nuclear power plants is dealt with in YVL Guide 7.10 and 7.11. The guide defines the concepts relevant to the monitoring of radiation exposure and provides guidelines for determining the necessity of monitoring and subsequently arranging such in different operations. In addition, the guide specifies the criteria for the approval and regulatory control of the dosimetric service

  6. Offsite environmental monitoring report. Radiation monitoring around United States nuclear test areas, calendar year 1997

    International Nuclear Information System (INIS)

    Davis, M.G.; Flotard, R.D.; Fontana, C.A.; Hennessey, P.A.; Maunu, H.K.; Mouck, T.L.; Mullen, A.A.; Sells, M.D.

    1999-01-01

    This report describes the Offsite Radiological Environmental Monitoring Program (OREMP) conducted during 1997 by the US Environmental Protection Agency's (EPAs), Radiation and Indoor Environments National Laboratory, Las Vegas, Nevada. This laboratory operated an environmental radiation monitoring program in the region surrounding the Nevada Test Site (NTS) and at former test sites in Alaska, Colorado, Mississippi, Nevada, and New Mexico. The surveillance program is designed to measure levels and trends of radioactivity, if present, in the environment surrounding testing areas to ascertain whether current radiation levels and associated doses to the general public are in compliance with existing radiation protection standards. The surveillance program additionally has the responsibility to take action to protect the health and well being of the public in the event of any accidental release of radioactive contaminants. Offsite levels of radiation and radioactivity are assessed by sampling and analyzing milk, water, and air; by deploying and reading thermoluminescent dosimeters (TLDs); and using pressurized ionization chambers (PICs) to measure ambient gamma exposure rates with a sensitivity capable of detecting low level exposures not detected by other monitoring methods

  7. Offsite environmental monitoring report: Radiation monitoring around United States nuclear test areas, calendar year 1997

    Energy Technology Data Exchange (ETDEWEB)

    Davis, M.G.; Flotard, R.D.; Fontana, C.A.; Hennessey, P.A.; Maunu, H.K.; Mouck, T.L.; Mullen, A.A.; Sells, M.D.

    1999-01-01

    This report describes the Offsite Radiological Environmental Monitoring Program (OREMP) conducted during 1997 by the US Environmental Protection Agency`s (EPAs), Radiation and Indoor Environments National Laboratory, Las Vegas, Nevada. This laboratory operated an environmental radiation monitoring program in the region surrounding the Nevada Test Site (NTS) and at former test sites in Alaska, Colorado, Mississippi, Nevada, and New Mexico. The surveillance program is designed to measure levels and trends of radioactivity, if present, in the environment surrounding testing areas to ascertain whether current radiation levels and associated doses to the general public are in compliance with existing radiation protection standards. The surveillance program additionally has the responsibility to take action to protect the health and well being of the public in the event of any accidental release of radioactive contaminants. Offsite levels of radiation and radioactivity are assessed by sampling and analyzing milk, water, and air; by deploying and reading thermoluminescent dosimeters (TLDs); and using pressurized ionization chambers (PICs) to measure ambient gamma exposure rates with a sensitivity capable of detecting low level exposures not detected by other monitoring methods.

  8. Offsite environmental monitoring report: Radiation monitoring around United States nuclear test areas, calendar year 1991

    Energy Technology Data Exchange (ETDEWEB)

    Chaloud, D.J.; Dicey, B.B.; Mullen, A.A.; Neale, A.C.; Sparks, A.R.; Fontana, C.A.; Carroll, L.D.; Phillips, W.G.; Smith, D.D.; Thome, D.J.

    1992-01-01

    This report describes the Offsite Radiation Safety Program conducted during 1991 by the Environmental Protection Agency`s (EPA`s) Environmental Monitoring Systems Laboratory-Las Vegas. This laboratory operates an environmental radiation monitoring program in the region surrounding the Nevada Test Site (NTS) and at former test sites in Alaska, Colorado, Mississippi, Nevada, and New Mexico. The surveillance program is designed to measure levels and trends of radioactivity, if present, in the environment surrounding testing areas to ascertain whether current radiation levels and associated doses to the general public are in compliance with existing radiation protection standards. The surveillance program additionally has the responsibility to take action to protect the health and well being of the public in the event of any accidental release of radioactive contaminants. Offsite levels of radiation and radioactivity are assessed by sampling milk, water, and air; by deploying thermoluminescent dosimeters (TLDs) and using pressurized ion chambers (PICs); and by biological monitoring of animals, food crops, and humans. Personnel with mobile monitoring equipment are placed in areas downwind from the test site prior to each nuclear weapons test to implement protective actions, provide immediate radiation monitoring, and obtain environmental samples rapidly after any occurrence of radioactivity release. Comparison of the measurements and sample analysis results with background levels and with appropriate standards and regulations indicated that there was no radioactivity detected offsite by the various EPA monitoring networks and no exposure above natural background to the population living in the vicinity of the NTS that could be attributed to current NTS activities. Annual and long-term trends were evaluated in the Noble Gas, Tritium, Milk Surveillance, Biomonitoring, TLD, PIC networks, and the Long-Term Hydrological Monitoring Program.

  9. Biological monitors for low levels of ionising radiation

    International Nuclear Information System (INIS)

    Mohankumar, M.N.; Jeevanram, R.K.

    1995-01-01

    The biological effects of high doses of ionising radiation are well understood and the methods of measurement of these doses well established. However the effects due to extremely low doses remain by and large uncertain. This is because of the fact that at such low doses no gross symptoms are seen. In fact, at these levels the occurrence of double strand breaks leading to the formation of chromosomal aberrations like dicentrics is rare and chances of mutation due to base damage are negligible. Hence neither chromosomal aberration studies nor mutational assays are useful for detecting doses of the order of a few milligray. Results of exhaustive work done by various laboratories indicate that below 20 mGy the chromosomal aberration technique based on scoring of dicentrics cannot distinguish between a linear or a threshold model. However indirect methods like unscheduled DNA synthesis (UDS) and sister chromatid exchanges (SCEs) appear to be promising for the detection of radiation exposures due to low levels of radiation. This report reviews the available literature on the biological effects of low levels of ionising radiation and highlights the merits and demerits of the various methods employed in the measurement of UDS and SCE. The phenomenon of radio-adaptive response (RAR) and its relation to DNA repair is also discussed. (author)

  10. Development of radiation alarm monitor

    International Nuclear Information System (INIS)

    Myung Jae Song; Myung Chan Lee; Jung Kwan Son

    1997-01-01

    The Radiation Alarm Monitor is developed domestically in order to protect radiation workers from over exposure. The Radiation Alarm Monitor with microprocessor installed can record the information of radiation field before and after accidents. It can also provide the data to analyze the accident and to set a counterplan. It features a wide detection range of radiation (I OmR/h - I OOR/h), radiation work and data storage, portability, high precision (5%) due to calibration, and adaptation of a powerful alarm system. In order to protect workers from over exposure, light and sound alarm had been designed to initiate when accident occurs such as an unexpected change of radiation field such as radiation rate and accumulated dosed between 90 min. before the alarm and 30 min. after the alarm. In addition, the Radiation Alarm Monitor interfaces with computer so that the accident can be analyzed. After the testing conditions in other countries for the Radiation Alarm Monitor were compared, the most stringent test, ANSI N42. 17-A, was selected. The performance testing was car-ried out under various conditions of temperature, humidity, vibration and electromagnetic wave hindrance by Korea Research Institute of Standards and Science (KRISS). As a result, the Radiation Alan-n Monitor passed all test. Also, for the Radiation Alarm Monitor, environmental adaptability tests under the environmental conditions of NPP sites had been performed. The Radiation Alan-n Monitor had been reviewed by radiation workers at NPPs and their opinions had been collected. Operating procedure will be written and distributed to every NPP sites. Radiation Alarm Monitor will be modified for use under the specific environmental conditions of each site. It will be distributed to NPP sites and will be used by radiation workers

  11. Occupational radiation exposure monitoring among radiation workers in Nepal

    International Nuclear Information System (INIS)

    Bhatt, Chhavi Raj; Shrestha, Shanta Lall; Khanal, Tara; Ween, Borgny

    2008-01-01

    Nepal was accepted as a member of the IAEA in 2007. Nepal is one of the world's least developed countries and is defined in Health Level IV. The population counted 26.4 millions in 2007. The health care sector increases with new hospitals and clinics, however, Nepal has no radiation protection authority or radiation protection regulation in the country until now. The radiation producing equipment in the health sector includes conventional X-ray and dental X-ray equipment, fluoroscopes, mammography, CT, catheterization laboratory equipment, nuclear medicine facilities, a few linear accelerators, Co 60 teletherapy and High Dose Rate brachytherapy sources. The situation regarding dosimetry service for radiation workers is unclear. A survey has been carried out to give an overview of the situation. The data collection of the survey was performed by phone call interviews with responsible staff at the different hospitals and clinics. Data about different occupationally exposed staff, use of personal radiation monitoring and type of dosimetry system were collected. In addition, it was asked if dosimetry reports were compiled in files or databases for further follow-up of staff, if needed. The survey shows that less of 25% of the procedures performed on the surveyed hospitals and clinics are performed by staff with personnel radiation monitoring. Radiation monitoring service for exposed staff is not compulsory or standardized, since there is no radiation protection authority. Nepal has taken a step forward regarding radiation protection, with the IAEA membership, although there are still major problems that have to be solved. An evaluation of the existing practice of staff dosimetry can be the first helpful step for further work in building a national radiation protection authority. (author)

  12. Biological monitors for low levels of ionising radiation

    Energy Technology Data Exchange (ETDEWEB)

    Mohankumar, M N; Jeevanram, R K [Safety Research and Health Physics Group, Indira Gandhi Centre for Atomic Research, Kalpakkam (India)

    1996-12-31

    The biological effects of high doses of ionising radiation are well understood and the methods of measurement of these doses well established. However the effects due to extremely low doses remain by and large uncertain. This is because of the fact that at such low doses no gross symptoms are seen. In fact, at these levels the occurrence of double strand breaks leading to the formation of chromosomal aberrations like dicentrics is rare and chances of mutation due to base damage are negligible. Hence neither chromosomal aberration studies nor mutational assays are useful for detecting doses of the order of a few milligray. Results of exhaustive work done by various laboratories indicate that below 20 mGy the chromosomal aberration technique based on scoring of dicentrics cannot distinguish between a linear or a threshold model. However indirect methods like unscheduled DNA synthesis (UDS) and sister chromatid exchanges (SCEs) appear to be promising for the detection of radiation exposures due to low levels of radiation. This report reviews the available literature on the biological effects of low levels of ionising radiation and highlights the merits and demerits of the various methods employed in the measurement of UDS and SCE. The phenomenon of radio-adaptive response (RAR) and its relation to DNA repair is also discussed. (author). 98 refs., 11 figs., 4 tabs.

  13. Offsite environmental monitoring report: Radiation monitoring around United States nuclear test areas, calendar year 1993

    International Nuclear Information System (INIS)

    Chaloud, D.J; Daigler, D.M.; Davis, M.G.

    1996-06-01

    This report describes the Offsite Radiation Safety Program conducted during 1993 by the Environmental Protection Agency's (EPA's) Environmental Monitoring Systems Laboratory - Las Vegas (EMSL-LV). This laboratory operates an environmental radiation monitoring program in the region surrounding the Nevada Test Site (NTS) and at former test sites in Alaska, Colorado, Mississippi, Nevada, and New Mexico. The surveillance program is designed to measure levels and trends of radioactivity, if present, in the environment surrounding testing areas to ascertain whether current radiation levels and associated doses to the general public are in compliance with existing radiation protection standards. The surveillance program additionally has the responsibility to take action to protect the health and well being of the public in the event of any accidental release of radioactive contaminants. Offsite levels of radiation and radioactivity are assessed by sampling milk, water, and air; by deploying thermoluminescent dosimeters (TLDs) and using pressurized ionization chambers (PICs); by biological monitoring of foodstuffs including animal tissues and food crops; and by measurement of radioactive material deposited in humans

  14. Offsite environmental monitoring report: Radiation monitoring around United States nuclear test areas, calendar year 1993

    Energy Technology Data Exchange (ETDEWEB)

    Chaloud, D.J; Daigler, D.M.; Davis, M.G. [and others

    1996-06-01

    This report describes the Offsite Radiation Safety Program conducted during 1993 by the Environmental Protection Agency`s (EPA`s) Environmental Monitoring Systems Laboratory - Las Vegas (EMSL-LV). This laboratory operates an environmental radiation monitoring program in the region surrounding the Nevada Test Site (NTS) and at former test sites in Alaska, Colorado, Mississippi, Nevada, and New Mexico. The surveillance program is designed to measure levels and trends of radioactivity, if present, in the environment surrounding testing areas to ascertain whether current radiation levels and associated doses to the general public are in compliance with existing radiation protection standards. The surveillance program additionally has the responsibility to take action to protect the health and well being of the public in the event of any accidental release of radioactive contaminants. Offsite levels of radiation and radioactivity are assessed by sampling milk, water, and air; by deploying thermoluminescent dosimeters (TLDs) and using pressurized ionization chambers (PICs); by biological monitoring of foodstuffs including animal tissues and food crops; and by measurement of radioactive material deposited in humans.

  15. Development of multi copter based autonomous unmanned aerial radiation monitoring system for the remote impact assessment of radiation emergencies

    International Nuclear Information System (INIS)

    Jose, Jis Romal; Gupta, Ashutosh; Bahadur, Shuchita; Chaudhury, Probal; Pradeepkumar, K.S.

    2016-01-01

    During any radiation emergency, the level and extent of radioactive contamination need to be monitored for the timely and effective implementation of countermeasures to reduce the radiation exposure to public. In such a scenario, radiation surveillance can be carried out using either ground based mobile monitoring techniques or aerial radiation monitoring. Aerial radiation monitoring is quick and capable of scanning the areas which are not easily accessible by the ground based mobile monitoring. Compact unmanned aerial vehicle based radiation surveillance system is ideal in above mentioned radiation emergency scenarios as it can be rapidly deployed in the affected area and radiation exposure to the monitoring personal can be totally avoided. This paper describes development of multi copter based autonomous unmanned aerial radiation monitoring system for the remote impact assessment of radiation emergencies

  16. Monitoring occupational exposure to ionizing radiation

    International Nuclear Information System (INIS)

    Button, J.B.C.

    1997-01-01

    A brief overview is presented of methods of monitoring occupational exposure to ionizing radiation together with reasons for such monitoring and maintaining dose histories of radiation occupationally exposed persons. The various Australian providers of external radiation monitoring services and the types of dosemeters they supply are briefly described together with some monitoring results. Biological monitoring methods, are used to determine internal radiation dose. Whole body monitors, used for this purpose are available at Australian Radiation Lab., ANSTO and a few hospitals. Brief mention is made of the Australian National Radiation Dose Register and its objectives

  17. Towards a novel modular architecture for CERN radiation monitoring

    CERN Document Server

    Boukabache, Hamza; Ducos, Gael; Cardines, Nicola; Bellotta, Antonio; Toner, Ciarán; Perrin, Daniel; Forkel-Wirth, Doris

    2017-01-01

    The European Organization for Nuclear Research (CERN) has the legal obligation to protect the public and the people working on its premises from any unjustified exposure to ionising radiation. In this context, radiation monitoring is one of the main concerns of the Radiation Protection Group. After 30 y of reliable service, the ARea CONtroller (ARCON) system is approaching the end of its lifecycle, which raises the need for new, more efficient radiation monitors with a high level of modularity to ensure better maintainability. Based on these two main principles, new detectors are currently being developed that will be capable of measuring very low dose rates down to 50 nSv h−1, whilst being able to measure radiation over an extensive range of 8 decades without any auto scaling. To reach these performances, CERN Radiation MOnitoring Electronics (CROME), the new generation of CERN radiation monitors, is based on the versatile architecture that includes new read-out electronics developed by the Instrumentation...

  18. Radiation monitoring around accelerator facilities

    Energy Technology Data Exchange (ETDEWEB)

    Sasaki, Shinichi [High Energy Accelerator Research Organization (KEK), Tsukuba, Ibaraki (Japan)

    2000-07-01

    The present status of a network of radiation monitors (NORM) working at KEK is described in detail. NORM consists of there parts; stand-alone radiation monitors (SARM), local-monitoring stations (STATION) and a central data-handling system (CENTER). NORM has developed to a large-scaled monitoring system in which more than 250 SARMs are under operation for monitoring the radiation fields and radioactivities around accelerators in KEK. (author)

  19. Monitoring occupational exposure to ionizing radiation

    Energy Technology Data Exchange (ETDEWEB)

    Button, J.B.C. [Radiation Safety Consultancy, Engadine, NSW (Australia)

    1997-12-31

    A brief overview is presented of methods of monitoring occupational exposure to ionizing radiation together with reasons for such monitoring and maintaining dose histories of radiation occupationally exposed persons. The various Australian providers of external radiation monitoring services and the types of dosemeters they supply are briefly described together with some monitoring results. Biological monitoring methods, are used to determine internal radiation dose. Whole body monitors, used for this purpose are available at Australian Radiation Lab., ANSTO and a few hospitals. Brief mention is made of the Australian National Radiation Dose Register and its objectives. 8 refs., 9 tabs.

  20. Citizen-based environmental radiation monitoring network

    International Nuclear Information System (INIS)

    Alemayehu, B.; Mckinzie, M.; Cochran, T.; Sythe, D.; Randrup, R.; Lafargue, E.

    2017-01-01

    This paper discusses a Citizen Radiation Monitoring project designed and implemented by the Natural Resources Defense Council . The goal of the project was to implement a radiation monitoring system that provides radiation data accessible to the public. The monitoring system consisted of usage of a radiation detector integrated with near real-time data collection and visualization. The monitoring systems were installed at five different locations and background radiation measurements were taken. The developed monitoring system demonstrated that citizen-based monitoring system could provide accessible radiation data to the general public and relevant to the area where they live. (author)

  1. Reusable radiation monitor

    International Nuclear Information System (INIS)

    Fanselow, D.L.; Ersfeld, D.A.

    1978-01-01

    An integrating, reusable device for monitoring exposure to actinic radiation is disclosed. The device comprises a substrate having deposited thereon at least one photochromic aziridine compound which is sealed in an oxygen barrier to stabilize the color developed by the aziridine compound in response to actinic radiation. The device includes a spectral response shaping filter to transmit only actinic radiation of the type being monitored. A color standard is also provided with which to compare the color developed by the aziridine compound

  2. Radiation monitoring network in Poland

    International Nuclear Information System (INIS)

    Grabowski, D.; Kurowski, W.; Muszynski, W.; Rubel, B.; Smagala, G.; Swietochowska, J.

    2001-01-01

    In Poland the radioactive contamination of the environment and food has been controlled since the early sixties by the Service for Measurements of Radioactive Contamination (SPSP). The service comprises a network of measuring stations and the Centre of Radioactive Contamination Measurements (COPSP). Actually, there are 100 measurement stations. The main task of such station is systematic measurement of radioactivity level in samples of environment components and food. Nine stations of SPSP acting within meteorological stations, ten stations of low level air radioactivity measurements (Aerosols Sampling Stations-500) and eleven permanent monitoring stations (PMS) form the radiation monitoring warning system in Poland. (author)

  3. USB-based radiation monitor

    International Nuclear Information System (INIS)

    Drndarevic, V.; Jevtic, N.; Djuric, R.

    2006-01-01

    The Universal Serial Bus has become a dominant interface for the connection of standard peripheral devices to a personal computer. This paper analyzes the possibilities of USB bus applications in the field of measurement and environmental monitoring. As a result, a gamma radiation monitor consisting of an USB-based universal peripheral device and a gamma probe with a GM counter, has been designed. For the interfacing monitor with the powerful and easy to use LabVIEW software package, an instrument driver as a set of virtual instruments has been developed. The proposed monitor is a flexible instrument which can be used for laboratory measurements, as an environmental radiation monitor or for training purposes. Connected to the laptop computer, the monitor becomes a portable instrument suitable for field measurements. Basic measurements and functionality properties of the radiation monitor are presented here

  4. The environmental radiation monitoring system and in-situ measurements for early notification and OIL (Operational Intervention Levels) calculations

    International Nuclear Information System (INIS)

    Haquin, G.; Ne'eman, E.; Brenner, S.; Lavi, N.

    1997-01-01

    The efficiency of the environmental radiation monitoring, low level laboratory and in-situ gamma-ray spectrometry are evaluated as the systems for early notification and for determination of dose rate in air, surface contamination and activity concentration in food during emergencies for Operational Intervention Levels (OIL) recalculation.The National Environmental Radiation Monitoring System has proved its efficiency in the early detection of unregistered radiography work. A mobile station of the network can be used for absorbed dose rate measurement during emergencies in contaminated areas. The calibrated in-situ gamma-ray spectrometry system in an open phosphate ore mine has showed the efficiency of this technique for fast and accurate determination of soil activity concentration. The calibration for an uniform depth distribution can be easily mathematically converted to an exponential depth distribution in cases of radioactive material fallout

  5. Maintenance experiences with hand and foot monitor for monitoring alpha and beta radiation of personnel in NFC

    International Nuclear Information System (INIS)

    Ramachandra Rao, A.; Kulkarni, R.S.; Banerjee, P.K.

    2010-01-01

    friendly, with better features in Display and monitoring software. This paper presents our experiences with these α and β radiation monitors while their maintenance and testing for proper functioning in monitoring of radiation contamination levels of persons in active plant areas. (author)

  6. Environmental monitoring of low-level radioactive materials

    International Nuclear Information System (INIS)

    Jester, W.A.; Yu, C.

    1985-01-01

    The authors discuss some of the current rationale behind the environmental monitoring of low-level radioactive materials are as follows: Committee 4 of the International commission on Radiological Protection (ICRP) defined three broad objectives for environmental monitoring: 1) assessment of the actual or potential exposure of humans to radioactive materials or radiation present in their environment or the estimation of the probable upper limits of such exposure; 2) scientific investigation, sometimes related to the assessment of exposures, sometimes to other objectives; 3) improved public relations. Various regulations have been written requiring environmental monitoring to ensure that the public is not being exposed to excessive amounts of radiation from natural sources or from human activities. An example of the monitoring of natural sources of radiation is a requirement of the Environmental Protection Agency's (EPA) National Interim Primary Drinking Water Regulations whereby U.S. water supply companies must have drinking water monitored at least once every four years for radionuclides, primarily the naturally occurring radium-226

  7. Environmental γ radiation monitor

    International Nuclear Information System (INIS)

    Qu Xiaopeng

    1993-01-01

    The environmental γ radiation monitor is a kind of dose or dose rate measuring devices, which can be used for monitoring environmental γ radiation around a nuclear site when normal or even abnormal events occur. The monitor is controlled by a single-chip microcomputer so that it can acquire synchronously the data from four detectors and transfer the data to a central computer. The monitor has good temperature property due to the technique of temperature correction. The monitor has been used in the environment monitoring vehicle for Qinshan Nuclear Power Plant

  8. Environmental radiation monitoring in Sao Paulo state

    International Nuclear Information System (INIS)

    Agudo, E.G.; Albuquerque, A.M. de; Vasconcellos, N.V. de

    1991-01-01

    The results of environmental radiation monitoring that CETESB (Technological Company of Environmental Sanitation of Sao Paulo) does in influence areas of radioactive materials store of Nuclemon Minero-Quimica S.A. in the municipality of Itu, Sao Paulo State, are presented. The data comprises the period of 1983-1990 with information about concentration levels of radium-225 in underground and superficial waters of the region. On March, 1989, was detected contamination in a well near of the stores. The levels observed, its implications in terms of health risks and possible causes of event are discussed too. The goals that CETESB intends to reach in terms of monitoring of environmental radiation in Sao Paulo State are also presented. (C.M.)

  9. Study of the navigation methods applicable to monitoring in sites with high level of radiation

    International Nuclear Information System (INIS)

    Segovia de los Rios, J.A.; Rivero G, T.; Garduno G, M.; Zapata, R.

    2004-01-01

    In places in which high radiation levels exist is desirable to have a system that allows the realization of mensurations without the necessity of the exhibition of human resources. It is in fact in these types of situations where a robot system, or automated, in a sense but wide, it is directly applicable. So that a monitoring system, based on a mobile robot, for example, be autonomous, it is necessary to develop and to implement functional and efficient sailing algorithms that allow its use with the minimum of human intervention. Several methods exist to achieve this objective, some of them already proven and others in roads of experimentation. The present work presents some in the sailing ways but used, and specifically, the one that intends for a system of detection of flights in a place with high temperatures and high radiation levels. (Author)

  10. ERMS - Environmental Radiation Monitoring System

    International Nuclear Information System (INIS)

    Vax, Eran; Sarusi, Benny; Sheinfeld, Mati; Levinson, Shmuel; Brandys, Irad; Sattinger, Danny; Wengrowicz, Udi; Tshuva, Avi; Tirosh, Dan

    2008-01-01

    A new Environmental Radiation Monitoring System (ERMS) has been developed in the NRCN as an extensive tool to be applied in case of nuclear malfunction or Nuclear Disposal Device (NDD) incident, as well as for routine radiation monitoring of the reactor's vicinity. The system collects real-time environmental data such as: gamma radiation, wind speed, wind direction, and temperature for monitoring purposes. The ERMS consists of a main Control Center and an array of monitoring stations. Fixed, environmental, gamma radiation monitoring stations are installed at the reactor's surroundings while portable stations can be posted rapidly along the wind direction, enhancing the spatial sampling of the radiation measurements and providing better hazard assessment at an emergency event. The presented ERMS, based on industrial standards for hardware and network protocols, is a reliable standalone system which upgrades the readiness to face a nuclear emergency event by supplying real-time, integrated meteorological and radiation data. (author)

  11. Remote radiation environmental monitoring

    International Nuclear Information System (INIS)

    Pashayev, A.M.; Mehdiyev, A.Sh.; Bayramov, A.A.

    2003-01-01

    Full text: The project of the automated remote monitoring for a level of an environment background radiation in settlements along boundary of the Azerbaijan Republic is developed. The main purpose of the project is: increase of a level of a radiation safety on territory of the Azerbaijan Republic; controlling of a level of an environment background radiation on boundary of the Azerbaijan Republic with the purpose of well-timed warning and acceptance of indispensable measures at probable emergencies on Atomic Power Stations in a number adjacent from Azerbaijan countries, or other ecological catastrophes; controlling of a level of an environment background radiation along eastern suburbs of Azerbaijan regions occupied of Armenia's army and detection of the facts of wrongful disposals of atomic engineering of Armenia on territory of Azerbaijan. As is known, in a number adjacent from Azerbaijan countries the nuclear industry is advanced or develops. It has resulted in origin of threat of a radiation hazard in case of ecological catastrophes: widely scale leakage of radioactive wastes, explosions, or fires on nuclear generating sets, acts of sabotage, directional against Azerbaijan. In this case, at unfavorable meteorological conditions a radioactive waste may be brought by a wind or a rain on territory of Azerbaijan. Measurement is supposed a carry with the help of 'EKOMON' fixed stations. The results of round-the-clock a gamma and a neutron background measurement from the stations will be transmitted automatically to a dispatcher station in the central computer. Established on the stations telescopic sensors also will allow to determine a direction of a radiation and coordinates of radiation source. Stations will be located along boundary, and also in Kedabek, Akstafa, Terter, Agdam and Fizuli regions, and in Autonomous Republic of Nakhichevan

  12. Calibration of radiation monitoring instruments

    International Nuclear Information System (INIS)

    1973-01-01

    Radiation protection is dependent on good radiation monitoring, and properly calibrated instruments are essential for this work. Simple procedures for periodically checking and recalibrating different kinds of radiation monitoring instruments are shown in this training film

  13. Calibration of radiation monitoring instruments

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1974-12-31

    Radiation protection is dependent on good radiation monitoring, and properly calibrated instruments are essential for this work. Simple procedures for periodically checking and recalibrating different kinds of radiation monitoring instruments are shown in this training film

  14. Environmental Radiation Monitoring Around the Nuclear Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Choi, Geun Sik; Lee, Chang Woo

    2008-05-15

    Environmental Radiation Monitoring was carried out with measurement of environment. radiation and environmental radioactivity analysis on the sites of KAERI nuclear facilities and Seoul Research Reactors and their environments. The average level of environmental radiation dose measured by an ERM and the accumulated radiation dose by a TLD were almost same level compared with the previous years. The activity of gross {alpha} and gross {beta}, Tritium, Uraniu and Strontium in environmental samples showed a environmental level. The radioactivities of most {gamma}-radionuclides in air particulate, surface water and ground water were less than MDA except {sup 40}K or {sup 7}Be which are natural radionuclides. However, not only {sup 40}K or {sup 7}Be but also {sup 137}Cs were detected at the background level in surface soil, discharge sediment and fallout or pine needle.

  15. Radiation monitoring instrumentation for nuclear power plants

    International Nuclear Information System (INIS)

    Bharath Kumar, M.

    2013-01-01

    Measurement of nucleonic signals is required to control and operate the reactor in a safe and reliable manner. To achieve this, parameters like Neutron flux, other radiation fields, contamination levels, source strength, release thru stack etc. are required to be monitored and controlled. The above are required to be monitored throughout the life of the reactor whether it is operational or in shutdown condition. In addition such monitoring is also required during decommissioning phase of the reactor as needed. To measure these parameters a large number of instruments are used in Nuclear Power Plants (NPP) which includes sensors and electronics for detecting alpha, beta, gamma and neutron radiation with qualification to withstand harsh environment

  16. Biological monitoring of radiation using indicator plants

    International Nuclear Information System (INIS)

    Kim, Jin Kyoo; Chun, Ki Jung; Kim, Kook Chan; Kim, In Kyoo; Song, Heui Sub

    1994-12-01

    Some clones of Tradescantia had dose response relationship involving somatic mutations such as appearance of pink, colorless or giant cell, and/or loss of reproductive integrity of stamen hair cells when exposed to radiation. Since Tradescantia could respond to radiation level as low as human being could be exposed to, it could play an important role as scientific tool of botanical tester for radiation. Especially TSH system can be easily applied to in situ monitoring of radiation by virtue of its excellent radiation indicator ship and simpleness in detection of mutations by radiation. 10 figs, 6 tabs, 19 refs. (Author)

  17. Biological monitoring of radiation using indicator plants

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Jin Kyoo; Chun, Ki Jung; Kim, Kook Chan; Kim, In Kyoo; Song, Heui Sub [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1994-12-01

    Some clones of Tradescantia had dose response relationship involving somatic mutations such as appearance of pink, colorless or giant cell, and/or loss of reproductive integrity of stamen hair cells when exposed to radiation. Since Tradescantia could respond to radiation level as low as human being could be exposed to, it could play an important role as scientific tool of botanical tester for radiation. Especially TSH system can be easily applied to in situ monitoring of radiation by virtue of its excellent radiation indicator ship and simpleness in detection of mutations by radiation. 10 figs, 6 tabs, 19 refs. (Author).

  18. Radiation monitoring device

    International Nuclear Information System (INIS)

    Sato, Toshifumi.

    1993-01-01

    The device of the present invention concerns a reactor start-up region monitor of a nuclear power plant. In an existent start-up region monitor, bias voltage is limited, if the reactor moves to a power region, in order to prevent degradation of radiation detectors. Accordingly, since the power is lower than an actual reactor power, the reactor power can not be monitored. The device of the present invention comprises a memory means for previously storing a Plateau's characteristic of the radiation detectors and a correction processing means for obtaining a correction coefficient in accordance with the Plateau's characteristic to correct and calculate the reactor power when the bias voltage is limited. With such a constitution, when the reactor power exceeds a predetermined value and the bias voltage is limited, the correction coefficient can be obtained by the memory means and the correction processing means. Corrected reactor power can also be obtained from the start-up region monitor by the correction coefficient. As a result, monitoring of the reactor power can be continued while preventing degradation of the radiation detector even if the bias voltage is limited. (I.S.)

  19. Radiation environmental real-time monitoring and dispersion modeling

    International Nuclear Information System (INIS)

    Kovacik, A.; Bartokova, I.; Omelka, J.; Melicherova, T.

    2014-01-01

    The system of real-time radiation monitoring provided by MicroStep-MIS is a turn-key solution for measurement, acquisition, processing, reporting, archiving and displaying of various radiation data. At the level of measurements, the monitoring stations can be equipped with various devices from radiation probes, measuring the actual ambient gamma dose rate, to fully automated aerosol monitors, returning analysis results of natural and manmade radionuclides concentrations in the air. Using data gathered by our radiation probes RPSG-05 integrated into monitoring network of Crisis Management of the Slovak Republic and into monitoring network of Slovak Hydrometeorological Institute, we demonstrate its reliability and long-term stability of measurements. Data from RPSG-05 probes and GammaTracer probes, both of these types are used in the SHI network, are compared. The sensitivity of RPSG-05 is documented on data where changes of dose rate are caused by precipitation. Qualities of RPSG-05 probe are illustrated also on example of its use in radiation monitoring network in the United Arab Emirates. A more detailed information about radioactivity of the atmosphere can be obtained by using spectrometric detectors (e.g. scintillation detectors) which, besides gamma dose rate values, offer also a possibility to identify different radionuclides. However, this possibility is limited by technical parameters of detector like energetic resolution and detection efficiency in given geometry of measurement. A clearer information with less doubts can be obtained from aerosol monitors with a built-in silicon detector of alpha and beta particles and with an electrically cooled HPGe detector dedicated for gamma-ray spectrometry, which is performed during the sampling. Data from a complex radiation monitoring network can be used, together with meteorological data, in radiation dispersion model by MicroStep-MIS. This model serves for simulation of atmospheric propagation of radionuclides

  20. Environmental radiation monitoring around the nuclear facilities

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Chang Woo

    2012-03-15

    Environmental Radiation Monitoring was carried out with measurement of environment. radiation and environmental radioactivity analysis on the sites of KAERI nuclear facilities and Seoul Research Reactors and their environments. The average level of environmental radiation dose measured by an ERM and the accumulated radiation dose by a TLD were almost same level compared with the previous years. The activity of gross {alpha} and gross {beta}, Tritium, Uranium and Strontium in environmental samples showed a environmental level. The {gamma}-radionuclides such as natural radionuclides 40K or 7Be were detected in pine needle and food. The nuclear radionuclides 134Cs, 137Cs or 131I were temporarily detected in the samples of air particulate and rain in April and of fall out in 2nd quarter from the effect of Fukusima accident.

  1. Radiation monitor for surveillance of moving vehicles

    International Nuclear Information System (INIS)

    Dvorak, R.F.

    1985-09-01

    A radiation monitor has been developed that will scan each vehicle leaving the Clinton P. Anderson Los Alamos Meson Physics Facility site. If an increase in radiation level is sensed, an alarm light and a Klaxon horn are activated, inviting the driver to return to the Health Physics office for check. A photograph showing the vehicle license number is also taken. A radiation source that doubles the detector count rate when stationary will cause an alarm at vehicle speeds up to about 24 km/h (15 mph). The technique used to prevent false alarms because of radiations from nearby buildings or from plumes of low-level radioactive gas is described. 9 figs

  2. Advances in radiation protection monitoring

    International Nuclear Information System (INIS)

    1978-01-01

    The requirement to keep radiation exposure as low as reasonably achievable, linked with the growing number of workers whose exposure to radiation must be strictly controlled, requires intensified efforts directed towards the provision of adequate radiation monitoring programmes. This symposium was intended to review the advances that have been made in methods, techniques and instrumentation for radiation protection monitoring. Thus the symposium complemented the detailed consideration that had already been given to two closely related topics, that of environmental monitoring and of monitoring radioactive airborne and liquid discharges from nuclear facilities. The first topic had been dealt with in detail in an Agency symposium held in November 1973 in Warsaw and the second was treated in an Agency symposium held in September 1977 in Portoroz. The present symposium covered a broad range of topics under the following main headings: Monitoring of external exposure (three sessions),Contamination monitoring (three sessions), Radiation monitoring programmes (one session), Calibration, and use of computers (two sessions). An introductory paper described the purpose of radiation protection monitoring and its historical development. It drew attention to the gradual change from the threshold dose hypothesis to the hypothesis of direct proportionality between dose and effect and discussed practical implications of the recommendations recently issued by the International Commission on Radiological Protection (ICRP). It became apparent that guidance on the application of these recommendations is urgently needed. This guidance is presently being prepared by ICRP

  3. The environmental radiation monitoring system and in-situ measurements for early notification and OIL (Operational Intervention Levels) calculations

    Energy Technology Data Exchange (ETDEWEB)

    Haquin, G.; Ne`eman, E.; Brenner, S.; Lavi, N. [Tel Aviv Univ. (Israel). Sackler School of Medicine. Inst. for Environmental Research

    1997-12-31

    The efficiency of the environmental radiation monitoring, low level laboratory and in-situ gamma-ray spectrometry are evaluated as the systems for early notification and for determination of dose rate in air, surface contamination and activity concentration in food during emergencies for Operational Intervention Levels (OIL) recalculation.The National Environmental Radiation Monitoring System has proved its efficiency in the early detection of unregistered radiography work. A mobile station of the network can be used for absorbed dose rate measurement during emergencies in contaminated areas. The calibrated in-situ gamma-ray spectrometry system in an open phosphate ore mine has showed the efficiency of this technique for fast and accurate determination of soil activity concentration. The calibration for an uniform depth distribution can be easily mathematically converted to an exponential depth distribution in cases of radioactive material fallout 7 refs., 3 figs., 1 tab.; e-mail: envirad at post.tau.ac.il; env{sub r}ad at netvision,net.il

  4. Radiation monitoring program at nuclear scientific experimental and educational center - IRT-Sofia

    International Nuclear Information System (INIS)

    Mladenov, A.; Stankov, D.; Marinov, K.; Nonova, T.; Krezhov, K.

    2012-01-01

    Ensuring minimal risk of personnel exposure without exceeding the dose limits is the main task of the General Program for Radiation Monitoring of Nuclear Scientific Experimental and Education Centre (NSEEC) with research reactor IRT. Since 2006 the IRT-Sofia is equipped with a new and modern Radiation Monitoring System (RMS). All RMS detectors are connected to the server RAMSYS. They have online (real-time) visualization in two workstations with RAMVISION software. The RMS allows the implementation of technological and environmental monitoring at the nuclear facility site. Environmental monitoring with the RMS external system includes monitoring of dose rate; alpha and beta activity; radon activity; Po-218, Po-214, Po-212 activity; gamma control of vehicles. Technological control of reactor gases includes: Alpha beta particulate monitor; Iodine monitor; Noble gases monitor; Stack flow monitor. The General Program based on the radiation monitoring system allows real-time monitoring and control of radiation parameters in the controlled area and provides for a high level of radiation protection of IRT staff and users of its facilities. This paper presents the technical and functional parameters of the radiation monitoring system and radiation protection activities within the restricted zone in IRT facilities. (authors)

  5. Digital radiation monitor system

    International Nuclear Information System (INIS)

    Quan Jinhu; Zhai Yongchun; Guan Junfeng; Ren Dangpei; Ma Zhiyuan

    2003-01-01

    The article introduced digital radiation monitor system. The contents include: how to use advanced computer net technology to establish equipment net for nuclear facility, how to control and manage measuring instruments on field equipment net by local area net, how to manage and issue radiation monitoring data by internet

  6. Offsite environmental monitoring report; radiation monitoring around United States nuclear test areas, Calendar Year 1996

    International Nuclear Information System (INIS)

    Davis, M.G.; Flotard, R.D.; Fontana, C.A.; Huff, P.A.; Maunu, H.K.; Mouck, T.L.; Mullen, A.A.; Sells, M.D.

    1997-08-01

    This report describes the Offsite Radiation Safety Program. This laboratory operated an environmental radiation monitoring program in the region surrounding the Nevada Test Site (NTS) and at former test sites in Alaska, Colorado, Mississippi, Nevada, and New Mexico. The surveillance program is designed to measure levels and trends of radioactivity, if present, in the environment surrounding testing areas to ascertain whether current radiation levels and associated doses to the general public are in compliance with existing radiation protection standards. The surveillance program additionally has the responsibility to take action to protect the health and well being of the public in the event of any accidental release of radioactive contaminants. Offsite levels of radiation and radioactivity are assessed by sampling milk, water, and air; by deploying thermoluminescent dosimeters (TLDs); and using pressurized ionization chambers (PICs). No nuclear weapons testing was conducted in 1996 due to the continuing nuclear test moratorium. During this period, R and IE personnel maintained readiness capability to provide direct monitoring support if testing were to be resumed and ascertained compliance with applicable EPA, DOE, state, and federal regulations and guidelines. Comparison of the measurements and sample analysis results with background levels and with appropriate standards and regulations indicated that there was no airborne radioactivity from diffusion or resuspension detected by the various EPA monitoring networks surrounding the NTS. There was no indication of potential migration of radioactivity to the offsite area through groundwater and no radiation exposure above natural background was received by the offsite population. All evaluated data were consistent with previous data history

  7. Environmental Radiation Surveillance Results from over the Last Decade of Operational Experience at the Regional Radiation Monitoring Stations(RRMS)

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Hae Young [Daegu Regional Radiation Monitoring Station, Daegu (Korea, Republic of); Yoo, Dong Han [Ulsan Regional Radiation Monitoring Station, Ulsan (Korea, Republic of); Lee, Sang Hoon [Kyungpook National University, Daegu (Korea, Republic of)

    2015-10-15

    The objectives of the current program are to monitor environmental radiation/radioactivity level in Korea and to provide the base-line data on environmental radiation/radioactivity which will be useful in the case of radiological emergency situations. This program plays an important role in the view of protecting the public health against the potential hazards of radiation and maintaining a clean environment. This paper describes an introduction to the Regional Radiation Monitoring Stations (RRMS), and also presents some results of recent years (2001-2014). The environmental radiation surveillance results of years 2001-2014 have been described. It indicates normal levels of radiation in the past years. These kinds of studies are very important in providing references in understanding the environmental radioactivity level in a particular region.

  8. Radiation monitoring policy at the advanced light source

    International Nuclear Information System (INIS)

    Donahue, R.; Heinzelman, K.; Perdue, G.

    1998-01-01

    When the accelerator first began operation it was decided that, until we had the necessary dosimetry data to decide otherwise, we would badge the entire worker and experimental population. Each person was issued a dosimetry badge that contained 4 TLD elements. Badges were processed on a monthly basis. After three years of analyzing a total of 65,000 TLD elements, the decision was made to modify the radiation monitoring policy at the ALS. Only those individuals in the workforce that have any potential for exposure, no matter how small, would be badged. Subsequently, DOE conducted an independent review of the ALS radiation monitoring and dosimetry program. This review concluded that the ALS program, if expanded as proposed, would be adequate under the 10 CFR 835 Rule to establish radiation exposures to an acceptable level of confidence. The review team recommended the ALS provide more comprehensive documentation on the basis for its radiation protection and monitoring program. This document describes the technical justification for that program

  9. NRC TLD Direct Radiation Monitoring Network. Volume 5, No. 2. Progress report, April-June 1985

    International Nuclear Information System (INIS)

    Jang, J.; Kramaric, M.; Cohen, L.

    1985-09-01

    The US Nuclear Regulatory Commission (NRC) Direct Radiation Monitoring Network provides continuous measurement of the ambient radiation levels around licensed NRC facilities, primarily power reactors. The Network is intended to measure radiation levels during routine facility operations and to establish background radiation levels used to assess the radiological impact of an unusual condition, such as an accident. This report presents the radiation levels measured around all facilities in the Network for the second quarter of 1985. A complete listing of the site facilities monitored is included

  10. Basic principles for occupational radiation monitoring

    International Nuclear Information System (INIS)

    1987-01-01

    This Safety Guide sets forth the objectives of an adequate strategy for monitoring internal and external radiation exposures of workers. It covers individual monitoring, and workplace monitoring to the extent required for assessment and control of individual radiation doses. The responsibilities of authorities for organizing the monitoring of radiation workers are discussed, and brief descriptions are given of the rules governing the implementation of monitoring methods. The general principles to be considered in selecting instrumentation and appropriate monitoring techniques are described, as well as calibrating techniques, methods of record keeping and related aspects

  11. Mobile radiation monitoring of Mumbai and it's suburb through various road routes by using state-of-the-art radiation monitoring systems

    International Nuclear Information System (INIS)

    Divkar, J.K.; Chatterjee, M.K.; Patil, S.S.; Sharma, Ranjit; Singh, Rajvir; Pradeepkumar, K.S.

    2007-01-01

    The monitoring of environmental radiation in different parts of the country is being periodically carried out with an objective to establish the countrywide baseline dose rate data. The task of quick assessment of impact due to any large-scale radiological emergencies in public domain involves reliable and quick monitoring of dose rate levels using mobile monitoring techniques. In order to achieve higher accuracy and more confidence in measured values, various state-of-the-art monitoring systems are used for mapping a large area. It enables collection and processing of data for rapid and correct evaluation of the situation. The evaluation of measured data from the different systems provides comparable results. This paper describes the radiation mapping of Mumbai and its suburbs carried out through different road routes by installing state-of-the art monitoring systems like CARMS, PMGSS, gamma tracers and micro-R survey meters in a light motor vehicle with the objective of assessing the background radiation level of Mumbai city including Mumbai Suburb, Navi Mumbai and Thane, tagging each data with the positional coordinates and also to detect and locate the presence of orphan sources, if any. The average of measured dose rate levels of Mumbai and Mumbai Suburbs, Navi Mumbai and Thane are 53.3±9.1 nGy.h -1 , 50.9±10.0 nGy.h -1 and 52.1±10.8 nGy.h -1 respectively with maximum ∼ 160 nGy.h -l due to presence of high concentration of 40 K at some locations. (author)

  12. Radiation monitoring around United States nuclear test areas, calendar year 1989

    International Nuclear Information System (INIS)

    1990-05-01

    This report describes the Offsite Radiation Safety Program conducted during 1989 by the Environmental Protection Agency's (EPA's) Environmental Monitoring Systems Laboratory-Las Vegas (EMSL-LV). This laboratory operates an environmental radiation monitoring program in the region surrounding the Nevada Test Site (NTS) and at former test sites in Alaska, Colorado, Mississippi, Nevada, and New Mexico. The surveillance program is designed to measure levels, and trends of radioactivity, if present, in the environment surrounding testing areas to ascertain whether the testing is in compliance with existing radiation protection standards, and to take action to protect the health and well being of the public in the event of any accidental release of radioactive contaminants. Offsite levels of radiation and radioactivity are assessed by sampling milk, water, and air; by deploying thermoluminescent dosimeters (TLDs) and using pressurized ion chambers (PICs); and by biological monitoring of both animals and humans. To implement protective actions, provide immediate radiation monitoring, and obtain environmental samples rapidly after any release of radioactivity, personnel with mobile monitoring equipment are placed in areas downwind from the test site prior to each test. Comparison of the measurements and sample analysis results with background levels and with appropriate standards and regulations indicated that there was no radioactivity detected offsite by the various EPA monitoring networks and no exposure above natural background to the population living in the vicinity of the NTS that could be attributed to NTS activities. Trends were evaluated in the Noble Gas and Tritium, Milk Surveillance, TLD, and PIC networks, and the Long-Term Hydrological Monitoring Program. 35 refs., 68 figs., 32 tabs

  13. Radiation monitoring around United States nuclear test areas, calendar year 1989

    Energy Technology Data Exchange (ETDEWEB)

    1990-05-01

    This report describes the Offsite Radiation Safety Program conducted during 1989 by the Environmental Protection Agency's (EPA's) Environmental Monitoring Systems Laboratory-Las Vegas (EMSL-LV). This laboratory operates an environmental radiation monitoring program in the region surrounding the Nevada Test Site (NTS) and at former test sites in Alaska, Colorado, Mississippi, Nevada, and New Mexico. The surveillance program is designed to measure levels, and trends of radioactivity, if present, in the environment surrounding testing areas to ascertain whether the testing is in compliance with existing radiation protection standards, and to take action to protect the health and well being of the public in the event of any accidental release of radioactive contaminants. Offsite levels of radiation and radioactivity are assessed by sampling milk, water, and air; by deploying thermoluminescent dosimeters (TLDs) and using pressurized ion chambers (PICs); and by biological monitoring of both animals and humans. To implement protective actions, provide immediate radiation monitoring, and obtain environmental samples rapidly after any release of radioactivity, personnel with mobile monitoring equipment are placed in areas downwind from the test site prior to each test. Comparison of the measurements and sample analysis results with background levels and with appropriate standards and regulations indicated that there was no radioactivity detected offsite by the various EPA monitoring networks and no exposure above natural background to the population living in the vicinity of the NTS that could be attributed to NTS activities. Trends were evaluated in the Noble Gas and Tritium, Milk Surveillance, TLD, and PIC networks, and the Long-Term Hydrological Monitoring Program. 35 refs., 68 figs., 32 tabs.

  14. Environmental radiation levels around Nuclear Fuel Complex, Hyderabad during 1981-1988

    International Nuclear Information System (INIS)

    Mehta, Navnit; Lakshmanan, A.R.; Kathuria, S.P.; Nambi, K.S.V.

    1989-01-01

    This report presents environmental radiation monitoring results around Nuclear Ffuel Complex (NFC) at Hyderabad for the period, 1981-'88. During 1981-'83 only indoor radiations were monitored at 12 locations in the region of about 15 km. radius around NFC plant. However, during 1984-'88 both indoor and outdoor monitoring was done in a standardised manner at 8 locations. In this routine monitoring programme, environmental thermoluminescent dosimeters were used in quarterly integrating cycles. The average outdoor natural radiation level around NFC during 1984-'88 is found to be 227 ± 34 (σ) mR/y, which is the highest among the various sites in the country where DAE units are located. Such a high level of natural background radiation in and around Hyderabad is due to granitic terrains which normally have significant amounts of primordial radioactivity. The indoor to outdoor radiation ratio is found to be 1.35 ± 0.1 (σ). Application of this ratio on all the available indoor radiation monitoring results of 1981-'88 gives an estimate of 230 ± 26 mR/y as the average outdoor radiation level, and this is in very close agreement with the directly measured value mentioned earlier. The temporal variations seen in the quarterly results of each location have been tested for Normal and Log-Normal distributions and found to yield satisfactory correlations, although the plots reveal slight skewness; the latter however, could not be attributed to the NFC operations. (author). 7 refs., 4 tabs., 12 figs

  15. Modification of GNPS environment radiation monitoring network system

    International Nuclear Information System (INIS)

    Jiang Lili; Cao Chunsheng

    1999-01-01

    GNPS Environment Radiation Continuous Monitoring System (KRS), the only real time on-line system of site radiation monitoring, was put into service in 1993 prior to the first loading the the plant. It is revealed through several years of operation that this system has some deficiencies such as inadequate real time monitoring means, no figure and diagram display function on the central computer, high failures, frequent failure warning signals, thus making the availability of the system at a low level. In recent years, with the rapid development of computer network technology and increasingly strict requirements on the NPP environment protection raised by the government and public, KRS modification had become necessary and urgent. In 1996, GNPS carried out modification work on the measuring geometry condition of γ radiation monitoring sub-station and lightening protection. To enhance the functions of real time monitoring and data auto-processing, further modification of the system was made in 1998, including the update of the software and hardware of KRS central processor, set-up of system computer local network and database. In this way, the system availability and monitoring quality are greatly improved and effective monitoring and analysis means are provided for gaseous release during normal operation and under accident condition

  16. Radiation protection at workplaces with increased natural radiation exposure in Greece: recording, monitoring and protection measures

    International Nuclear Information System (INIS)

    Potiriadis, C.; Koukoliou, V.

    2002-01-01

    Greek Atomic Energy Commission (GAEC) is the regulatory, advisory and competent authority on radiation protection matters. It is the authority responsible for the introduction of Radiation Protection regulations and monitoring of their implementation. In 1997, within the frame of its responsibilities the Board of the GAEC appointed a task group of experts to revise and bring the present Radiation Protection Regulations into line with the Basic Safety Standards (BSS) 96/29/Euratom Directive and the 97/43/Euratom Directive (on health protection of individuals against the dangers of ionising radiation in relation to medical exposure). Concerning the Title 7. of the new European BSS Directive, which refers to the Radiation Protection at work places with increased levels of natural radiation exposure, the Radiation Protection Regulations provides that the authority responsible for recording, monitoring and introducing protection measures at these places is the GAEC. Practices where effective doses to the workers due to increased natural radiation levels, may exceed 1mSv/y, have to be specified and authorised by the GAEC. The identification procedure is ongoing

  17. Evaluation of the radiation monitor

    International Nuclear Information System (INIS)

    1996-05-01

    The Radiation Monitor is an information bulletin produced every three months by the Atomic Energy Control Board (AECB) and published in five local newspapers in the Durham Region of Ontario. The bulletin reports on the radiation doses to the public due to emissions from Pickering and Darlington nuclear generating stations. Comparative information on dose levels from other sources is also provided. To measure the communications effectiveness of the bulletin, the AECB contracted for a door-to-door survey of residents living near the two nuclear stations and within the circulation areas of the five local papers. The objectives of the survey were to measure the public's awareness of the existence of the Radiation Monitor, evaluate ease in understanding the information, assess the perceived usefulness of the bulletin, and assess the perceived accessibility of the AECB as an information source. The survey found that 61 per cent of adults had heard of the AECB, and 60 per cent of those correctly identified it as a regulator of the nuclear industry. Six per cent of the surveyed population had accurate unaided recall of the Radiation Monitor, while 26 per cent recognized the bulletin when shown a copy. Most respondents to the survey seemed content with the way technical details are presented in the bulletin, and 85 per cent of all persons interviewed found the information it contained to be useful. Thirty-six per cent said that it was very useful. For many, the bulletin was seen to put radiation in perspective and to reassure residents of the low risk. It was also judged by most to be factual and easy to understand. Suggestions for improvement focus largely on improving distribution. 14 tabs

  18. Evaluation of the radiation monitor

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-05-01

    The Radiation Monitor is an information bulletin produced every three months by the Atomic Energy Control Board (AECB) and published in five local newspapers in the Durham Region of Ontario. The bulletin reports on the radiation doses to the public due to emissions from Pickering and Darlington nuclear generating stations. Comparative information on dose levels from other sources is also provided. To measure the communications effectiveness of the bulletin, the AECB contracted for a door-to-door survey of residents living near the two nuclear stations and within the circulation areas of the five local papers. The objectives of the survey were to measure the public`s awareness of the existence of the Radiation Monitor, evaluate ease in understanding the information, assess the perceived usefulness of the bulletin, and assess the perceived accessibility of the AECB as an information source. The survey found that 61 per cent of adults had heard of the AECB, and 60 per cent of those correctly identified it as a regulator of the nuclear industry. Six per cent of the surveyed population had accurate unaided recall of the Radiation Monitor, while 26 per cent recognized the bulletin when shown a copy. Most respondents to the survey seemed content with the way technical details are presented in the bulletin, and 85 per cent of all persons interviewed found the information it contained to be useful. Thirty-six per cent said that it was very useful. For many, the bulletin was seen to put radiation in perspective and to reassure residents of the low risk. It was also judged by most to be factual and easy to understand. Suggestions for improvement focus largely on improving distribution. 14 tabs.

  19. Maintenance of radiation monitoring systems

    International Nuclear Information System (INIS)

    Aoyama, Kei

    2001-01-01

    As the safety and quality of atomic power facilities are more strongly required, the reliability improvement and preventive maintenance of radiation monitoring systems are important. This paper describes the maintenance of radiation monitoring systems delivered by Fuji Electric and the present status of preventive maintenance technology. Also it introduces the case that we developed a fault diagnosis function adopting a statistics technique and artificial intelligence (AI) and delivered a radiation monitoring system including this function. This system can output a fault analysis result and a countermeasure from the computer in real time. (author)

  20. Web design and development for centralize area radiation monitoring system in Malaysian Nuclear Agency

    Science.gov (United States)

    Ibrahim, Maslina Mohd; Yussup, Nolida; Haris, Mohd Fauzi; Soh @ Shaari, Syirrazie Che; Azman, Azraf; Razalim, Faizal Azrin B. Abdul; Yapp, Raymond; Hasim, Harzawardi; Aslan, Mohd Dzul Aiman

    2017-01-01

    One of the applications for radiation detector is area monitoring which is crucial for safety especially at a place where radiation source is involved. An environmental radiation monitoring system is a professional system that combines flexibility and ease of use for data collection and monitoring. Nowadays, with the growth of technology, devices and equipment can be connected to the network and Internet to enable online data acquisition. This technology enables data from the area monitoring devices to be transmitted to any place and location directly and faster. In Nuclear Malaysia, area radiation monitor devices are located at several selective locations such as laboratories and radiation facility. This system utilizes an Ethernet as a communication media for data acquisition of the area radiation levels from radiation detectors and stores the data at a server for recording and analysis. This paper discusses on the design and development of website that enable all user in Nuclear Malaysia to access and monitor the radiation level for each radiation detectors at real time online. The web design also included a query feature for history data from various locations online. The communication between the server's software and web server is discussed in detail in this paper.

  1. Radiation monitor reporting requirements

    International Nuclear Information System (INIS)

    Bates, W.F.

    1993-01-01

    Within High-Level Waste Management (HLWM), CAMs and VAMPs are currently considered Class B equipment, therefore, alarm conditions associated with the CAMs and VAMPs result in an Unusual Occurrence or Off-Normal notification and subsequent occurrence reporting. Recent equipment difficulties associated with Continuous Air Monitors (CAMs) and Victoreen Area Radiation Monitors (VAMPs) have resulted in a significant number of notification reports. These notification have the potential to decrease operator sensitivity to the significance of specific CAM and VAMP failures. Additionally, the reports are extremely costly and are not appropriate as a means for tracking and trending equipment performance. This report provides a technical basis for a change in Waste Management occurrence reporting categorization for specific CAM and VAMP failure modes

  2. Assessment of radiation emitted by the colour video monitors using a silicon surface-barrier detection system

    International Nuclear Information System (INIS)

    Tykva, R.; Sabol, J.

    1998-01-01

    About 5% of the commonly used colour monitors tested showed radiation levels on the screen surface approaching the dose rate of 5 μGy/h. There is practically no difference between 'low radiation' monitors and other monitors. The level of radiation emitted to the sides is generally higher than that of X-ray photons emerging from the surface of the screen. Although the contribution to the effective dose of a person exposed to radiation from the monitors may be below the limit set for the general public, the skin and eye lens dose may reach significant levels, taking into account some factors such as a high density of monitors in small rooms, short distance, long exposure time, etc. (M.D.)

  3. A new-generation radiation monitoring vehicle

    International Nuclear Information System (INIS)

    Gryc, Lubomir; Cespirova, Irena; Sury, Jan; Hanak, Vitezslav; Sladek, Petr

    2015-01-01

    A new radiation monitoring vehicle has been developed within the MOSTAR (Mobile and Stationary Radiation monitoring systems for a new generation of radiation monitoring network) Security Research project. The vehicle accommodates a system for radiation survey using scintillation detectors. Basic spectroscopy is performed with a sodium iodine crystal system, directional measurement is based on two side-mounted plastic detectors, logging dose rates, GPS coordinates and displaying results in a map. A semiconductor spectrometric chain for rapid qualitative and quantitative evaluation of environmental samples is also included. (orig.)

  4. Radiation monitoring by minicomputer

    International Nuclear Information System (INIS)

    Seamons, M.

    1977-01-01

    Radiation monitoring at the Los Alamos Scientific Laboratory (LASL) ranges from measuring the potential build-up of alpha particle radiation in the offices and laboratories of LASL to the detection of radiation leakage from nuclear tests at the Nevada Test Site (NTS). This paper describes PDP-11 based systems to accomplish both types of monitoring. In the first system, filter papers are collected from monitoring stations around LASL. One filter paper is placed under any of 128 photomultiplier (PM) tubes exposing it to alpha radiation. Alpha particle ''hits'' are recorded in a 64-word hardware FIFO, which interrupts and is read by the computer. The FIFO makes it possible to handle short aggregate alpha particle bursts of up to 10 6 hits/s in a computer that can only process 10 4 hits/s. In the second system, up to 100 current measuring radiation probes feed data from the site of the nuclear test(s) to the computer by microwave. The software system can support three tests simultaneously. Both systems offer a high degree of flexibility in configuring for a new test and in real-time control of such things as channel assignment, selective data retrieval, and output formatting

  5. International conference on individual monitoring of ionising radiation

    International Nuclear Information System (INIS)

    Vanhavere, Filip

    2016-01-01

    This special issue of the journal Radiation Protection Dosimetry is dedicated to the Proceedings of the International Conference on Individual Monitoring of Ionising Radiation (IM2015), which is the fifth of a series of conferences dealing with individual monitoring. This conference series is initiated by EURADOS, the European Radiation Dosimetry Group, and is organised every 5 years. In 2015, the conference was jointly organised by the Belgian Nuclear Research Centre (SCK.CEN), AV Controlatom, and the Vrije Universiteit Brussel. It brought together scientists from regulatory authorities, individual monitoring services (IMS), research bodies, European networks and companies, for the purpose of facilitating the dissemination of knowledge, exchanging experiences and promoting new ideas in the field of individual monitoring. After the conference, 124 papers were submitted for publication in these peer-reviewed proceedings. From these, 103 were finally accepted for publication. The help of the numerous referees and the guest editors is very much appreciated. These proceedings provide a full image of the IM2015 conference. The high-level publications will be useful to improve the state of individual monitoring all over the world and aim to inspire many scientists to continue their work on a better monitoring of radiologically exposed workers

  6. Development of radiation monitoring and visualization systems for Fukushima. GPS monitoring system, Dose3DMap system, and LED-coupled scintillating fiber detector

    International Nuclear Information System (INIS)

    Nakao, Noriaki; Kosako, Kazuaki; Kinoshita, Norikazu; Kawaguchi, Masato

    2016-01-01

    Lands that were contaminated with radioactive elements following the Fukushima Daiichi Nuclear Power Plant accident in 2011 have been decontaminated, and the construction of an interim storage facility for radioactive waste is planned. A GPS monitoring system was developed to concomitantly determine a location and measure the radiation level at the location. Moreover, a mapping system that produces radiation maps at the measurement locations and also predicts post-decontamination radiation maps using the compiled Monte Carlo simulation program was constructed. These systems were used for decontamination planning and estimation of the decontamination effect. An LED-coupled scintillating fiber detector was developed for visually monitoring radiation in real time at the interim storage facility. The LEDs display different colors corresponding to different radiation levels at the measurement locations along the fiber detector, the maximum length of which is 50 m. Thus, the radiation levels at all positions along the length of the detector can be visually monitored in real time. Moreover, it is useful for radiation safety and for risk communication with radiation workers and residents close to the site. (author)

  7. Radiation monitor training program at Rocky Flats

    International Nuclear Information System (INIS)

    Medina, L.C.; Kittinger, W.D.; Vogel, R.M.

    The Rocky Flats Radiation Monitor Training Program is tailored to train new health physics personnel in the field of radiation monitoring. The purpose of the prescribed materials and media is to be consistent in training in all areas of Rocky Flats radiation monitoring job involvement

  8. NRC TLD [Nuclear Regulatory Commission thermoluminescent dosimeter] direct radiation monitoring network

    International Nuclear Information System (INIS)

    Struckmeyer, R.; McNamara, N.

    1990-03-01

    This report presents the results of the NRC Direct Radiation Monitoring Network for the fourth quarter of 1989. It provides the ambient radiation levels measured in the vicinity of 75 sites throughout the United States. In addition, it describes the equipment used, monitoring station selection criteria, characterization of the dosimeter response, calibration procedures, statistical methods, intercomparison, and quality assurance program

  9. Quality assurance of radiation protection monitoring instruments in India

    International Nuclear Information System (INIS)

    Tripathi, S.M.; Daniel, Liji; Rao, Suresh; Sharma, D.N.

    2008-01-01

    Bhabha Atomic Research Centre (BARC) is the National Metrology Institute (NMI) for developing, maintaining and disseminating standards for ionizing radiation in India. Radiation Safety Systems Division (RSSD) of BARC has the requisite infrastructure in the form of experts, trained manpower, laboratories, equipment and facilities for providing calibration services to users and ascertaining traceability to international standards. It periodically participates in various international inter-comparisons. RSSD maintains reference radiation fields that are required for calibrating Radiation Protection Monitoring Instruments that form the backbone of the radiation monitoring programme for harnessing the benefits of nuclear energy and ionizing radiations. These instruments are type-tested and periodically calibrated at standard reference radiation fields to ensure their healthy working condition and fitness for their intended use. This paper describes the details of the standardization procedures adopted for reference radiation fields and infrastructure established and maintained at RSSD, BARC in accordance with the recommendations of ISO-4037. The paper describes the various tests that are carried out for radiation protection monitoring instrument to study the variation of the calibration factor with influencing quantities like linearity of response, energy response, angular dependence and overload characteristics. The results of these tests for typical instruments are also discussed. The present work also describes various types of indigenously developed radiation protection monitoring instruments and their performance characteristics. Adaptability of these instruments for the implementation of operational quantities are discussed briefly. It also dwells on the IAEA Quality Audit for radiation protection level calibrations, which RSSD has been participating since 2001. Our results of the quality audit are well within the acceptance limit (±7%) set by IAEA for the

  10. TOWARDS A NOVEL MODULAR ARCHITECTURE FOR CERN RADIATION MONITORING.

    Science.gov (United States)

    Boukabache, Hamza; Pangallo, Michel; Ducos, Gael; Cardines, Nicola; Bellotta, Antonio; Toner, Ciarán; Perrin, Daniel; Forkel-Wirth, Doris

    2017-04-01

    The European Organization for Nuclear Research (CERN) has the legal obligation to protect the public and the people working on its premises from any unjustified exposure to ionising radiation. In this context, radiation monitoring is one of the main concerns of the Radiation Protection Group. After 30 y of reliable service, the ARea CONtroller (ARCON) system is approaching the end of its lifecycle, which raises the need for new, more efficient radiation monitors with a high level of modularity to ensure better maintainability. Based on these two main principles, new detectors are currently being developed that will be capable of measuring very low dose rates down to 50 nSv h-1, whilst being able to measure radiation over an extensive range of 8 decades without any auto scaling. To reach these performances, CERN Radiation MOnitoring Electronics (CROME), the new generation of CERN radiation monitors, is based on the versatile architecture that includes new read-out electronics developed by the Instrumentation and Logistics section of the CERN Radiation Protection Group as well as a reconfigurable system on chip capable of performing complex processing calculations. Beside the capabilities of CROME to continuously measure the ambient dose rate, the system generates radiation alarms, provides interlock signals, drives alarm display units through a fieldbus and provides long-term, permanent and reliable data logging. The measurement tests performed during the first phase of the development show very promising results that pave the way to the second phase: the certification. © The Author 2016. Published by Oxford University Press.

  11. Vehicle Radiation Monitoring Systems for Medical Waste Disposal - 12102

    Energy Technology Data Exchange (ETDEWEB)

    Kondrashov, Vladislav S.; Steranka, Steve A. [RadComm Systems Corp., 2931 Portland Dr., Oakville, ON L6H 5S4 (Canada)

    2012-07-01

    Hospitals often declare their waste as being 'non-radioactive'; however this material often has excessive levels of radiation caused either by an accident or lack of control. To ensure the best possible protection against the accidental receipt of radioactive materials and as a safety precaution for their employees, waste-handling companies have installed large-scale radiation portal monitors at their weigh scales or entry gates of the incinerator plant, waste transfer station, and/or landfill. Large-volume plastic scintillator-based systems can be used to monitor radiation levels at entry points to companies handling medical waste. The recent and intensive field tests together with the thousands of accumulated hours of actual real-life vehicle scanning have proven that the plastic scintillation based system is an appropriate radiation control instrument for waste management companies. The Real-Time background compensation algorithm is flexible with automatic adjustable coefficients that will response to rapidly changing environmental and weather conditions maintaining the preset alarm threshold levels. The Dose Rate correction algorithms further enhance the system's ability to meet the stringent requirements of the waste industries need for Dose Rate measurements. (authors)

  12. Environmental radiation monitoring system

    International Nuclear Information System (INIS)

    Kato, Tsutomu; Shioiri, Masatoshi; Sakamaki, Tsuyoshi

    2007-01-01

    Environmental radiation monitoring systems are used to measure and monitoring gamma-rays at the observation boundaries of nuclear facilities and in the surrounding areas. In recent years, however, few new nuclear facilities have been constructed and the monitoring systems shift to renewal of existing systems. In addition, in order to increase public acceptance, the facilities are being equipped with communication lines to provide data to prefectural environmental centers. In this text, we introduce the latest technology incorporated in replacement of environmental radiation monitoring systems. We also introduce a replacement method that can shorten the duration during which environmental dose rate measurement is interrupted by enabling both the replacement system and the system being replaced to perform measurements in parallel immediately before and after the replacement. (author)

  13. Community Radiation Monitoring Program

    International Nuclear Information System (INIS)

    Lucas, R.P. Jr.; Cooper, E.N.; McArthur, R.D.

    1990-05-01

    The Community Radiation Monitoring Program began its ninth year in the summer of 1989, continuing as an essential portion of the Environmental Protection Agency's long-standing off-site monitoring effort. It is a cooperative venture between the Department of Energy (DOE), the Environmental Protection Agency (EPA), the University of Utah (U of U), and the Desert Research Institute (DRI) of the University of Nevada System. The objectives of the program include enhancing and augmenting the collection of environmental radiation data at selected sites around the Nevada Test Site (NTS), increasing public awareness of that effort, and involving, in as many ways as possible, the residents of the off-site area in these and other areas related to testing nuclear weapons. This understanding and improved communication is fostered by hiring residents of the communities where the monitoring stations are located as program representatives, presenting public education forums in those and other communities, disseminating information on radiation monitoring and related subjects, and developing and maintaining contacts with local citizens and elected officials in the off-site areas. 8 refs., 4 figs., 4 tabs

  14. System of message for gamma-radiation monitor

    International Nuclear Information System (INIS)

    Bolic, M.D.; Koturovic, A.M.

    2001-01-01

    Paper describes a system of voice messages for gamma-radiation monitor based on PC. The systems reproduces recorded messages that is simpler than the process of their synthesis. Message choice is based on combination of recorded digital results and/or received reference messages or warnings. The system of generation of voice messages applies the Windows based software. The total memory array required to create independent voice system is maximum 1.7 mbyte. The monitor may be used for continuous monitoring of radioactivity level with 5-8 s period of message repetition. Another option of the system operation is based on monitor application for the environment monitoring. Period of messages in this case is equal to 5-30 min [ru

  15. Environmental radiation monitoring around Korea nuclear fuel company

    International Nuclear Information System (INIS)

    Choi, Yong Ho; Lee, C. W.; Choi, G. S.

    2004-12-01

    The environmental monitoring program for Korea Nuclear Fuel Company (KNFC) was implemented to investigate environmental radiation and radioactivity levels around the facilities. Accumulated environmental radiation doses were measured to be on almost the same level as those measured in the previous years. Total alpha and beta concentrations in air particulates were also similar to the past measurements. The concentrations of uranium isotopes in soil and underground water were investigated to be similar to natural levels. The concentrations of uranium isotopes in sediment around the facilities were not significantly different from those for the reference site. Surface water around the facilities showed somewhat higher uranium isotope concentrations than the reference samples but the activity levels were not much different from those reported before. The concentrations of uranium isotopes in rain water and foodstuffs such as rice seeds and Chinese cabbage were, on the whole, in the ranges of the previously reported levels. Based on the present results of the environmental monitoring, it can be estimated that the environmental impact resulting from the operation of KNFC in 2004 is negligible

  16. Upgrading of data acquisition software for centralized radiation monitoring system in Malaysian Nuclear Agency

    Energy Technology Data Exchange (ETDEWEB)

    Yussup, F., E-mail: nolida@nm.gov.my; Ibrahim, M. M., E-mail: maslina-i@nm.gov.my; Soh, S. C.; Hasim, H. [Instrumentation and Automation Centre, Technical Support Division, Malaysian Nuclear Agency, Bangi, 43000 Kajang. Selangor (Malaysia); Haris, M. F. [Information Technology Centre, Technical Support Division, Malaysian Nuclear Agency, Bangi, 43000 Kajang. Selangor (Malaysia); Azman, A. [Prototype and Development Centre, Technical Support Division, Malaysian Nuclear Agency, Bangi, 43000 Kajang. Selangor (Malaysia); Razalim, F. A. A.; Yapp, R. [Health Physics Group, Radiation Safety and Health Division, Malaysian Nuclear Agency, Bangi, 43000 Kajang. Selangor (Malaysia); Ramli, A. A. M. [Technical Support Division, Malaysian Nuclear Agency, Bangi, 43000 Kajang. Selangor (Malaysia)

    2016-01-22

    With the growth of technology, many devices and equipments can be connected to the network and internet to enable online data acquisition for real-time data monitoring and control from monitoring devices located at remote sites. Centralized radiation monitoring system (CRMS) is a system that enables area radiation level at various locations in Malaysian Nuclear Agency (Nuklear Malaysia) to be monitored centrally by using a web browser. The Local Area Network (LAN) in Nuclear Malaysia is utilized in CRMS as a communication media for data acquisition of the area radiation levels from radiation detectors. The development of the system involves device configuration, wiring, network and hardware installation, software and web development. This paper describes the software upgrading on the system server that is responsible to acquire and record the area radiation readings from the detectors. The recorded readings are called in a web programming to be displayed on a website. Besides the main feature which is acquiring the area radiation levels in Nuclear Malaysia centrally, the upgrading involves new features such as uniform time interval for data recording and exporting, warning system and dose triggering.

  17. Upgrading of data acquisition software for centralized radiation monitoring system in Malaysian Nuclear Agency

    International Nuclear Information System (INIS)

    Yussup, F.; Ibrahim, M. M.; Soh, S. C.; Hasim, H.; Haris, M. F.; Azman, A.; Razalim, F. A. A.; Yapp, R.; Ramli, A. A. M.

    2016-01-01

    With the growth of technology, many devices and equipments can be connected to the network and internet to enable online data acquisition for real-time data monitoring and control from monitoring devices located at remote sites. Centralized radiation monitoring system (CRMS) is a system that enables area radiation level at various locations in Malaysian Nuclear Agency (Nuklear Malaysia) to be monitored centrally by using a web browser. The Local Area Network (LAN) in Nuclear Malaysia is utilized in CRMS as a communication media for data acquisition of the area radiation levels from radiation detectors. The development of the system involves device configuration, wiring, network and hardware installation, software and web development. This paper describes the software upgrading on the system server that is responsible to acquire and record the area radiation readings from the detectors. The recorded readings are called in a web programming to be displayed on a website. Besides the main feature which is acquiring the area radiation levels in Nuclear Malaysia centrally, the upgrading involves new features such as uniform time interval for data recording and exporting, warning system and dose triggering

  18. Personal radiation monitoring and assessment of doses received by radiation workers (1991)

    International Nuclear Information System (INIS)

    Morris, N.D.

    1992-06-01

    The Australian Radiation Laboratory has operated a Personal Radiation Monitoring Service since the early 1930's so that people working with radiation can determine the radiation doses that they receive due to their occupation. Since late 1986, all persons monitored by the Service have been registered on a data base which maintains records of the doses received by each individual wearer. Ultimately, this data base will become a National Register of the doses received within Australia. At present, the Service regularly monitors approximately 20,000 persons, which is roughly 70 percent of those monitored in Australia, and maintains dose histories of over 35,000 people. The skin dose for occupationally exposed workers can be measured by using one of the four types of monitor issued by the Service: 1. Thermoluminescent Dosemeter (TLD monitor) 2. Finger TLD 3. Neutron Monitor 4. Special TLD. The technical description of the monitors is provided along with the method for calculating the radiation dose. 5 refs., 7 tabs., 4 figs

  19. Radiation monitoring programme in a university hot laboratory

    International Nuclear Information System (INIS)

    Tillander, M.; Heinonen, O.J.

    1979-01-01

    The Department of Radiochemistry in the University of Helsinki is the only institute teaching radiochemistry at the university level in Finland. The research programme of the Deparment must therefore include the uses of radiation and radionuclides in many branches of science. The students must receive adequate instruction in radiation protection for safe work in laboratories. This also has the educational benefit that the radiochemists will subsequently be able to observe the necessary safety precautions when employing ionizing radiation professionally. The Department of Radiochemistry consists of the following laboratories: a radiotracer laboratory, a neutron/electron and a gamma irradiation laboratory, an environmental low activity level laboratory, a whole-body counting laboratory, a reactor chemistry laboratory and a waste-treatment facility. The radiation protection organization of the Department is presented. Various methods of monitoring, including advantages and disadvantages are discussed. Emphasis is placed on the reactor chemistry laboratory where transuranic elements are utilized. These elements are highly radiotoxic and their monitoring in most cases requires destructive analysis. Different methods of determining external and internal doses are evaluated with regard to sensitivity and accuracy. Detection limits for radionuclides utilized in the laboratory are presented for different measurement systems, including non-destructive monitoring, spectrometry after chemical analysis, liquid scintillation counting and low-energy gamma spectrometry using a CsI-NaI scintillation detector. The guidelines laid down in the IAEA Safety Series Manuals are discussed in the light of practical experience. (author)

  20. NRC TLD Direct Radiation Monitoring Network. Progress report, October--December 1996

    International Nuclear Information System (INIS)

    Struckmeyer, R.

    1997-03-01

    This report presents the results of the NRC Direct Radiation Monitoring Network for the fourth quarter of 1996. It provides the ambient radiation levels measured in the vicinity of 74 sites throughout the United States. In addition, it describes the equipment used, monitoring station selection criteria, characterization of the dosimeter response, calibration procedures, statistical methods, intercomparison, and quality assurance program. 3 figs., 4 tabs

  1. NRC TLD Direct Radiation Monitoring Network. Progress report, October--December 1996

    Energy Technology Data Exchange (ETDEWEB)

    Struckmeyer, R.

    1997-03-01

    This report presents the results of the NRC Direct Radiation Monitoring Network for the fourth quarter of 1996. It provides the ambient radiation levels measured in the vicinity of 74 sites throughout the United States. In addition, it describes the equipment used, monitoring station selection criteria, characterization of the dosimeter response, calibration procedures, statistical methods, intercomparison, and quality assurance program. 3 figs., 4 tabs.

  2. Smarter radiation monitors for safeguards and security

    International Nuclear Information System (INIS)

    Fehlau, P.E.; Pratt, J.C.; Markin, J.T.; Scurry, T. Jr.

    1983-01-01

    Radiation monitors for nuclear safeguards and security depend on internal control circuits to determine when diversion of special nuclear materials is taking place. Early monitors depended on analog circuits for this purpose, subsequently, digital logic controllers made better monitoring methods possible. Now, versatile microprocessor systems permit new, more efficient, and more useful monitoring methods. One such method is simple stepwise monitoring, which has variable alarm levels to expedite monitoring where extended monitoring periods are required. Another method, sequential probability ratio logic, tests data as it accumulates against two hypothesis - background, or background plus a transient diversion signal - and terminates monitoring as soon as a decision can be made that meets false-alarm and detection confidence requirements. A third method, quantitative monitoring for personnel, calculates count ratios of high- to low-energy gamma-ray regions to predict whether the material detected is a small quantity of bare material or a larger quantity of shielded material. In addition, microprocessor system subprograms can assist in detector calibration and trouble-shooting. Examples of subprograms are a variance analysis technique to set bias levels in plastic scintillators and a state-of-health routine for detecting malfunctions in digital circuit components

  3. Radiation protection and monitoring

    International Nuclear Information System (INIS)

    Bruecher, L.; Langmueller, G.; Tuerschmann, G.

    1997-01-01

    The safety, the quality and efficiency of the radiological monitoring systems for block one and two of the NPP Mochovce, designed and delivered by the general designer, should be increased by EUCOM Siemens. Modern, accident resistant and/or more powerful monitoring systems have been designed by Siemens will be added to the existing systems. To achieve this radiation measuring units will be installed inside the hermetic zone, in the reactor hall, at the stack, at the release water system and in the environment in the vicinity of the NPP. The presentation, the storage distribution and the processing of all measuring results also will be optimised by installing a modern high-performance computer system, the so-called Central Radiological Computer System 'CRCS', featuring a high availability. The components will be installed in the relevant control rooms all over the plant. With this computer system it is easy to control the radiation level inside and outside the NPP during normal operation and during and after an accident. Special programs, developed by Siemens support the staff by interpreting the consequences of radioactive releases into the environment and by initiating protection procedures during and after an accident. All functions of the system are available for emergency protection drills and training the staff interruption of the normal control procedure. For the personal protection a digital personal dosimetry system completely considering with the requirements of ICRP 60 and several contamination monitors will be installed. (authors)

  4. Response of radiation monitoring labels to gamma rays and electrons

    DEFF Research Database (Denmark)

    Rahim, F. Abdel; Miller, Arne; McLaughlin, W.L.

    1985-01-01

    or location has been irradiated to high doses. Among labels available worldwide, a few are suitable for indicating absorbed dose regions of slightly less than 104 Gy (monitoring high dose ranges (i.e., sterilization dose levels of > 104 Gy or > 1 Mrad), and in some cases......, and differences in dose rate and radiation type (gamma rays and electron beams) were made on 15 kinds of labels. The results show that, for many types of indicators, diverse effects may give misleading conclusions unless countermeasures are taken. For example, some of the most commonly used labels, which contain...... permit somewhat more precise discrimination of dose levels, and may sometimes be useful for monitoring differences in local dose distributions or area monitoring of radiation damage probabilities around particle accelerators or large radionuclide sources....

  5. Legislation and litigation related to low-level radiation injury claims

    International Nuclear Information System (INIS)

    McCraw, T.

    1985-01-01

    Current legislation and litigation related to radiation exposure will have an enormous impact on the radiation protection and monitoring requirements of the future. A brief review of some proposed injury compensation bills for veterans and a recent court decision for low-level radiation injury claims are reviewed

  6. Radiation protection and monitoring

    International Nuclear Information System (INIS)

    Thomas, P.

    1982-01-01

    The present paper deals with the following topics: - Radiological quantities and units - Principles of radiological protection - Limits of doses and activity uptake - Activity discharges and monitoring - Radiation exposure and its calculation - Environmental monitoring - Personnel dosimetry. (orig./RW)

  7. EDGAR, a new plant radiation monitoring system

    International Nuclear Information System (INIS)

    Vuong, Q.M.; Da Costa Vieira, D.

    2004-01-01

    The EDGAR system is a new radiation monitoring system for nuclear power plant, reprocessing plant and nuclear research reactor for radioactive contamination, gamma and neutron field monitoring. Developed by French Atomic Energy Agency, this system provides not only complete functions of standard RMS, also allows spectroscopy level detection of alpha and beta particles based on a patented collimator unit. A complete computerized approach has been taken allowing full installation control in a single PC based display and communication unit. (author)

  8. First Results from the Online Radiation Dose Monitoring System in ATLAS experiment

    CERN Document Server

    Mandić, I; The ATLAS collaboration; Deliyergiyev, M; Gorišek, A; Kramberger, G; Mikuž, M; Franz, S; Hartert, J; Dawson, I; Miyagawa, P S; Nicolas, L

    2011-01-01

    High radiation doses which will accumulate in components of ATLAS experiment during data taking will cause damage to detectors and readout electronics. It is therefore important to continuously monitor the doses to estimate the level of degradation caused by radiation. Online radiation monitoring system measures ionizing dose in SiO2 and fluences of 1-MeV(Si) equivalent neutrons and thermal neutrons at several locations in ATLAS detector. In this paper measurements collected during two years of ATLAS data taking are presented and compared to predictions from radiation background simulations.

  9. Monitoring, Analyzing and Assessing Radiation Belt Loss and Energization

    Science.gov (United States)

    Daglis, I.; Balasis, G.; Bourdarie, S.; Horne, R.; Khotyaintsev, Y.; Mann, I.; Santolik, O.; Turner, D.; Anastasiadis, A.; Georgiou, M.; Giannakis, O.; Papadimitriou, C.; Ropokis, G.; Sandberg, I.; Angelopoulos, V.; Glauert, S.; Grison, B., Kersten T.; Kolmasova, I.; Lazaro, D.; Mella, M.; Ozeke, L.; Usanova, M.

    2013-09-01

    We present the concept, objectives and expected impact of the MAARBLE (Monitoring, Analyzing and Assessing Radiation Belt Loss and Energization) project, which is being implemented by a consortium of seven institutions (five European, one Canadian and one US) with support from the European Community's Seventh Framework Programme. The MAARBLE project employs multi-spacecraft monitoring of the geospace environment, complemented by ground-based monitoring, in order to analyze and assess the physical mechanisms leading to radiation belt particle energization and loss. Particular attention is paid to the role of ULF/VLF waves. A database containing properties of the waves is being created and will be made available to the scientific community. Based on the wave database, a statistical model of the wave activity dependent on the level of geomagnetic activity, solar wind forcing, and magnetospheric region will be developed. Multi-spacecraft particle measurements will be incorporated into data assimilation tools, leading to new understanding of the causal relationships between ULF/VLF waves and radiation belt dynamics. Data assimilation techniques have been proven as a valuable tool in the field of radiation belts, able to guide 'the best' estimate of the state of a complex system. The MAARBLE (Monitoring, Analyzing and Assessing Radiation Belt Energization and Loss) collaborative research project has received funding from the European Union’s Seventh Framework Programme (FP7-SPACE-2011-1) under grant agreement no. 284520.

  10. Monitoring System For Improving Radiation Safety Management

    International Nuclear Information System (INIS)

    Osovizky, A.; Paran, J.; Tal, N.; Ankry, N.; Ashkenazi, B.; Tirosh, D.; Marziano, R.; Chisin, R.

    1999-01-01

    Medi SMARTS (Medical Survey Mapping Automatic Radiation Tracing System), a gamma radiation monitoring system, was installed in a nuclear medicine department. In this paper the evaluation of the system's ability to improve radiation safety management is presented. The system is based on a state of the art software that continuously collects on line radiation measurements for display, analysis and logging. Radiation is measured by GM tubes; the signal is transferred to a data processing unit and then via an RS-485 communication line to a computer. The system automatically identifies the detector type and its calibration factor, thus providing compatibility, maintainability and versatility when changing detectors. Radiation levels are displayed on the nuclear medicine department map at six locations. The system has been operating continuously for more than one year, documenting abnormal events caused by routine operation or failure incidents. In cases where abnormal working conditions were encountered, an alarm message was sent automatically to the supervisor via his tele-pager. An interesting issue observed during the system evaluation, was the inability to distinguish between high radiation levels caused by proper routine operation and those caused by safety failure incidents. The solution included examination of two parameters, radiation levels as well as their duration period. A careful analysis of the historical data, applying the appropriated combined parameters determined for each location, verified that such a system can identify abnormal events, provide alarms to warn in case of incidents and improve standard operating procedures

  11. NRC [Nuclear Regulatory Commission] TLD [thermoluminescent dosimeter] direct radiation monitoring network

    International Nuclear Information System (INIS)

    Struckmeyer, R.; McNamara, N.

    1989-09-01

    This report provides the status and results of the NRC Thermoluminescent Dosimeter (TLD) Direct Radiation Monitoring Network. It presents the radiation levels measured in the vicinity of NRC licensed facility sites throughout the country for the second quarter of 1989

  12. NRC TLD direct radiation monitoring network: Progress report, April--June 1988

    International Nuclear Information System (INIS)

    Struckmeyer, R.; McNamara, N.

    1988-09-01

    This report provides the status and results of the NRC Thermoluminescent Dosimeter (TLD) Direct Radiation Monitoring Network. It presents the radiation levels measured in the vicinity of NRC licensed facility sites throughout the country for the second quarter of 1988

  13. Biological monitoring of radiation exposure

    Science.gov (United States)

    Horneck, G.

    1998-11-01

    Complementary to physical dosimetry, biological dosimetry systems have been developed and applied which weight the different components of environmental radiation according to their biological efficacy. They generally give a record of the accumulated exposure of individuals with high sensitivity and specificity for the toxic agent under consideration. Basically three different types of biological detecting/monitoring systems are available: (i) intrinsic biological dosimeters that record the individual radiation exposure (humans, plants, animals) in measurable units. For monitoring ionizing radiation exposure, in situ biomarkers for genetic (e.g. chromosomal aberrations in human lymphocytes, germ line minisatellite mutation rates) or metabolic changes in serum, plasma and blood (e.g. serum lipids, lipoproteins, lipid peroxides, melatonin, antibody titer) have been used. (ii) Extrinsic biological dosimeters/indicators that record the accumulated dose in biological model systems. Their application includes long-term monitoring of changes in environmental UV radiation and its biological implications as well as dosimetry of personal UV exposure. (iii) Biological detectors/biosensors for genotoxic substances and agents such as bacterial assays (e.g. Ames test, SOS-type test) that are highly sensitive to genotoxins with high specificity. They may be applicable for different aspects in environmental monitoring including the International Space Station.

  14. Application of maximum radiation exposure values and monitoring of radiation exposure

    International Nuclear Information System (INIS)

    1996-01-01

    The guide presents the principles to be applied in calculating the equivalent dose and the effective dose, instructions on application of the maximum values for radiation exposure, and instruction on monitoring of radiation exposure. In addition, the measurable quantities to be used in monitoring the radiation exposure are presented. (2 refs.)

  15. A microprocessor based area monitor system for neutron and gamma radiation

    International Nuclear Information System (INIS)

    Wilhelm, R.; Heusser, G.

    1980-01-01

    The conventional electronics of the area monitors at the MPI-Heidelberg accelerators have been replaced by a microprocessor system consisting of individual detector-microprocessors and a central microcomputer. The detector microprocessors convert the count rates of BF3 and GM counter tubes into dose rates and control three different radiation thresholds (failure, low and high level). Different warning signals are operated directly by the detector processors, whereas the dose rates are transferred to the central microcomputer. Here the data are processed for recording on tape and displaying on TV monitors. The detector as well as the central processors have been developed on the basis of a 16-bit microprocessor. In the control rooms the dose rates of the individual monitors are displayed and on an indicator board showing the different locations, the high radiation level and the state of the doors (open, locked, and closed, locked but open) are sianaled by different LED. If a high radiation threshold is surpassed, the doors adjacent to that area can be locked either by switches on the indicator board or automatically. Within the experimental area, the low and high radiation level is indicated by acoustic and light signals. The whole concept permits keeping the absorbed doses of the personnel as low as possible without affecting the flexibility of the experimental operations. The independence of the microprocessor driven area monitors guarantees a high reliability. Compared to conventional electronics the advantages of the system are its reliability and cost. (Author)

  16. Position-sensitive radiation monitoring (surface contamination monitor). Innovative technology summary report

    International Nuclear Information System (INIS)

    1999-06-01

    The Shonka Research Associates, Inc. Position-Sensitive Radiation Monitor both detects surface radiation and prepares electronic survey map/survey report of surveyed area automatically. The electronically recorded map can be downloaded to a personal computer for review and a map/report can be generated for inclusion in work packages. Switching from beta-gamma detection to alpha detection is relatively simple and entails moving a switch position to alpha and adjusting the voltage level to an alpha detection level. No field calibration is required when switching from beta-gamma to alpha detection. The system can be used for free-release surveys because it meets the federal detection level sensitivity limits requires for surface survey instrumentation. This technology is superior to traditionally-used floor contamination monitor (FCM) and hand-held survey instrumentation because it can precisely register locations of radioactivity and accurately correlate contamination levels to specific locations. Additionally, it can collect and store continuous radiological data in database format, which can be used to produce real-time imagery as well as automated graphics of survey data. Its flexible design can accommodate a variety of detectors. The cost of the innovative technology is 13% to 57% lower than traditional methods. This technology is suited for radiological surveys of flat surfaces at US Department of Energy (DOE) nuclear facility decontamination and decommissioning (D and D) sites or similar public or commercial sites

  17. Position-sensitive radiation monitoring (surface contamination monitor). Innovative technology summary report

    Energy Technology Data Exchange (ETDEWEB)

    1999-06-01

    The Shonka Research Associates, Inc. Position-Sensitive Radiation Monitor both detects surface radiation and prepares electronic survey map/survey report of surveyed area automatically. The electronically recorded map can be downloaded to a personal computer for review and a map/report can be generated for inclusion in work packages. Switching from beta-gamma detection to alpha detection is relatively simple and entails moving a switch position to alpha and adjusting the voltage level to an alpha detection level. No field calibration is required when switching from beta-gamma to alpha detection. The system can be used for free-release surveys because it meets the federal detection level sensitivity limits requires for surface survey instrumentation. This technology is superior to traditionally-used floor contamination monitor (FCM) and hand-held survey instrumentation because it can precisely register locations of radioactivity and accurately correlate contamination levels to specific locations. Additionally, it can collect and store continuous radiological data in database format, which can be used to produce real-time imagery as well as automated graphics of survey data. Its flexible design can accommodate a variety of detectors. The cost of the innovative technology is 13% to 57% lower than traditional methods. This technology is suited for radiological surveys of flat surfaces at US Department of Energy (DOE) nuclear facility decontamination and decommissioning (D and D) sites or similar public or commercial sites.

  18. On results of monitoring of environmental radiation around Rokkasho reprocessing facilities (fiscal year 1995) (acknowledgement)

    International Nuclear Information System (INIS)

    1997-01-01

    The Nuclear Safety Commission received the report on this matter from the expert committee on environmental radiation monitoring central evaluation on August 30, 1996, and acknowledged it after the deliberation. The report was recognized as appropriate. The monitoring was carried out according to the monitoring plan for environmental radiation around Rokkasho reprocessing facilities. The monitoring plan is outlined. At the time of the deliberation, the propriety of the techniques of monitoring and technical level carried out by Japan Nuclear Fuel Service Co. was examined. As the result, it was confirmed that the techniques of monitoring and technical level were appropriate. The results of monitoring are reported. (K.I.)

  19. National Environmental Radiation Warning And Monitoring Network And Proposed Radiation Monitoring Programme For The 1st Nuclear Power Plant Ninth Thuan

    International Nuclear Information System (INIS)

    Vuong Thu Bac

    2011-01-01

    National Environmental Radiation Warning and Monitoring Network has been gradually setting up based on some of legislative documents which have been issued in recent years. Studies and surveys to build an environmental radiation monitoring program for nuclear power plant (NPP) have also been implemented. This paper aims to introduce National Environmental Radiation Warning and Monitoring Network in Vietnam which has been approved by the government, the draft program for environmental radiation monitoring Ninh Thuan NPP and some initial results of research about environmental radiation in the planning area for building first NPP in Vietnam. (author)

  20. The design of radiation monitor passageway system

    International Nuclear Information System (INIS)

    Chu Chengsheng

    2006-10-01

    The Radiation Monitor Passageway System is designed as four modules, the radiation detection modules, the control modules, the mechanism modules and the optional modules. this system integrate the radiation detection technology and door ban control technology. It is a effective radiation monitor equipment with high detect sensitiveness, it will be hopeful devoted to national nuclear safeguard. (authors)

  1. Area radiation monitor at the intense pulsed-neutron source

    International Nuclear Information System (INIS)

    Eichholz, J.J.; Lynch, F.J.; Mundis, R.L.; Howe, M.L.; Dolecek, E.H.

    1981-01-01

    A tissue-equivalent ionization chamber with associated circuitry has been developed for area radiation monitoring in the Intense Pulsed-Neutron Source (IPNS) facility at Argonne National Laboratory. The conventional chamber configuration was modified in order to increase the electric field and effective volume thereby achieving higher sensitivity and linearity. The instrument provides local and remote radiation level indications and a high level alarm. Twenty-four of these instruments were fabricated for use at various locations in the experimental area of the IPNS-1 facility

  2. Radiation monitoring of uranium workers

    International Nuclear Information System (INIS)

    1998-12-01

    In order to manage radiological hazards in the workplace, it is necessary to have reliable measurements of workplace radiation levels and estimates of exposures and doses to workers. Over the past several years there have been many changes not only to the science of monitoring and dose assessment, but also to the regulatory framework. New International Commission on Radiological Protection (ICRP) recommendations on dose in ICRP Publication 60 (1991) and the implications of the ICRP's new respiratory tract model in ICRP Publication 66 (1994) are of particular importance. In addition, triggered by the act establishing the Canadian Nuclear Safety Commission (CNSC), which will replace the Atomic Energy Control Board (AECB), there is considerable activity in the review and development of regulatory guidance. Concurrent with these activities is the introduction of innovative mining procedures in Saskatchewan in order to extract uranium ore of particularly high grade. In view of these developments, the ACRP considered that a formal review of current monitoring practices would benefit both the CNSC and its licensees. In this report, 'uranium workers' refers to workers at uranium mines and mills, and workers at natural-uranium refineries, conversion, and fuel fabrication facilities; issues relating to long-term tailings management and to the handling of enriched materials are not addressed in this document. The report will have some relevance to workers in non-uranium mines and in industries handling naturally occurring radioactive materials (NORM) since, in some circumstances, these activities can present similar workplace radiation hazards. The report outlines the radiological hazards encountered in the Canadian uranium industry, and reviews current radiological monitoring practices and options; appendices include a glossary, a more technical discussion of monitoring methods, and an examination of errors and uncertainties in measurements of radon progeny and long

  3. Operation of radiation monitoring system in radwaste form test facility

    International Nuclear Information System (INIS)

    Ryu, Young Gerl; Kim, Ki Hong; Lee, Jae Won; Kwac, Koung Kil

    1998-08-01

    RWFTF (RadWaste Form Test Facility) must have a secure radiation monitoring system (RMS) because of having a hot-cell capable of handling high radioactive materials. And then in controlled radiation zone, which is hot-cell and its maintenance and operation / control room, area dose rate, radioactivities in air-bone particulates and stack, and surface contamination are monitored continuously. For the effective management such as higher utilization, maintenance and repair, the status of this radiation monitoring system, the operation and characteristics of all kinds of detectors and other parts of composing this system, and signal treatment and its evaluation were described in this technical report. And to obtain the accuracy detection results and its higher confidence level, the procedure such as maintenance, functional check and system calibration were established and appended to help the operation of RMS. (author). 6 tabs., 30 figs

  4. Radiation contamination monitors

    International Nuclear Information System (INIS)

    Kato, Tsutomu; Iba, Hiroshi; Sato, Hiroshi

    1999-01-01

    To make sure of no contamination on people, used articles and working uniforms coming out of the radiation controlled area, nuclear power plants are equipped with radioactive contamination monitors. This paper outlines the basic specifications and advantages of our personnel surface contamination monitors to inspect whole-body surface contamination of people coming out, article surface contamination monitors to inspect the surface and inside contamination of used articles brought out, laundry monitors to inspect surface contamination of working uniforms used in the area before and after a wash, and whole-body counters to inspect and measure the internal contamination of a person out of the area. (author)

  5. Centralized environmental radiation monitoring system in JAERI

    International Nuclear Information System (INIS)

    Katagiri, Hiroshi; Kobayashi, Hideo

    1993-03-01

    Japan Atomic Energy Research Institute (JAERI) has continued the radiation background survey and environmental radiation monitoring to ensure the safety of the residents around the Institute. For the monitoring of β and γ radiations and α and β radioactivities in air, the centralized automatic environmental radiation monitoring system (EMS) applying a computer with monitoring stations (MS) was established. The system has been renewed twice in 1973 and 1988. In 1962, a new concept emergency environmental γ-ray monitoring system (MP) was begun to construct and completed in 1965 independent of EMS. The first renewal of the EMS was carried out by focusing on the rapid and synthetic judgement and estimation of the environmental impacts caused by radiation and radioactive materials due to the operation of nuclear facilities by centralizing the data measured at MS, MP, a meteorological station, stack monitors and drainage monitoring stations under the control of computer. Present system renewed in 1988 was designed to prevent the interruption of monitoring due to computer troubles, communication troubles and power failures especially an instant voltage drop caused by thunder by reflecting the experiences through the operation and maintenance of the former system. Dual telemeters whose power is constantly supplied via batteries (capable of 10 min. monitoring after power failure) are equipped in the monitoring center to cope with telemeter troubles, which has operated successfully without any suspension being attributable to the power failures and telemeter troubles. (J.P.N.)

  6. Radiation monitoring system based on EPICS

    International Nuclear Information System (INIS)

    Wang Weizhen; Li Jianmin; Wang Xiaobing; Hua Zhengdong; Xu Xunjiang

    2008-01-01

    Shanghai Synchrotron Radiation Facility (SSRF for short) is a third-generation light source building in China, including a 150 MeV injector, 3.5 GeV booster, 3.5 GeV storage ring and an amount of beam line stations. During operation, a mass of Synchrotron Radiation will be produced by electrons in the booster and the storage ring. Bremsstrahlung and neutrons will also be produced as a result of the interaction between the electrons, especially the beam loss, and the wall of the vacuum beam pipe. SSRF Radiation Monitoring System is established for monitoring the radiation dosage of working area and environment while SSRF operating. The system consists of detectors, intelligent data-collecting modules, monitoring computer, and managing computer. The software system is developed based on EPICS (Experimental Physics and Industrial Control System), implementing the collecting and monitoring the data output from intelligent modules, analyzing the data, and so on. (authors)

  7. Multi-detector environmental radiation monitor with multichannel data communication for Indian Environmental Radiation Monitoring Network (IERMON)

    International Nuclear Information System (INIS)

    Patel, M.D.; Ratheesh, M.P.; Prakasha, M.S.; Salunkhe, S.S.; Vinod Kumar, A.; Puranik, V.D.; Nair, C.K.G.

    2011-01-01

    A solar powered system for online monitoring of environmental radiation with multiple detectors has been designed, developed and produced. Multiple GM tube detectors have been used to extend the range of measurement from 50 nano Gy/hr to 20 Gy/hr and to enhance the reliability of the system. Online data communication using GSM based and direct LAN based communication has been incorporated. Options for use of power supply from mains powered and battery powered have been enabled. Care has been taken to make it weather-proof, compact, elegant and reliable. The development is a part of the ongoing program of country-wide deployment of radiation monitors under 'Indian Environmental Radiation MOnitoring Network' (IERMON). (author)

  8. Testing of environmental radiation monitors using the Risø low-level radiation measurement stations

    DEFF Research Database (Denmark)

    Bøtter-Jensen, L.

    2000-01-01

    June, 1999. The chief aims of such experiments are to allow the participants to check their home calibrations of their detectors and to compare the responses of the individual environmental radiation measurement systems used in the different EU member states and making a link between the different...... a simulation of a radioactive plume passing over the monitors during a certain time was made using a specially designed source set up in the field that was able to vary the air kerma rate from low activity Cs-137 sources additional to the natural air kerma rate. It is demonstrated that a typical environmental...

  9. Applications Geiger-Muller detectors monitor the level of radioactivity in the human body

    International Nuclear Information System (INIS)

    Gunarwan Prayitno

    2008-01-01

    Nuclear technology is the technology high risk, because of an application and implementation have to support by human skill. The support facility has to complete and up to date, or modern. It means if the accident occurs in mistake have to do or delayed something, they can solved that problem. So the probability the risk of accident can be minimized. The specific problem is in the implementation nuclear technology on the human safety which is works in the radiation field or in the environment where they are working. The pointer that the problems have to design the tools monitor to monitoring the value radiation maximum was allowed. The tools monitor design is giving the information signal, if the radiation level maximum have over limit. Whereas the high and low level radiation can be just depend on the needed. (author)

  10. Radiation environmental real-time monitoring and dispersion modeling: A comprehensive solution

    International Nuclear Information System (INIS)

    Kovacik, A.; Bartokova, I.; Omelka, J.; Melicherova, T.

    2014-01-01

    The system of real-time radiation monitoring provided by MicroStep-MIS is a turn-key solution for measurement, acquisition, processing, reporting, archiving and displaying of various radiation data. At the level of measurements, the monitoring stations can be equipped with various devices from radiation probes, measuring the actual ambient gamma dose rate, to fully automated aerosol monitors, returning analysis results of natural and manmade radionuclides concentrations in the air. Using data gathered by our radiation probes RPSG-05 integrated into monitoring network of Crisis Management of the Slovak Republic and into monitoring network of Slovak Hydrometeorological Institute, we demonstrate its reliability and long-term stability of measurements. Data from RPSG-05 probes and GammaTracer probes, both of these types are used in the SHI network, are compared. The sensitivity of RPSG-05 is documented on data where changes of dose rate are caused by precipitation. Qualities of RPSG-05 probe are illustrated also on example of its use in radiation monitoring network in the United Arab Emirates. A more detailed information about radioactivity of the atmosphere can be obtained by using spectrometric detectors (e.g. scintillation detectors) which, besides gamma dose rate values, offer also a possibility to identify different radionuclides. However, this possibility is limited by technical parameters of detector like energetic resolution and detection efficiency in given geometry of measurement. A clearer information with less doubts can be obtained from aerosol monitors with a built-in silicon detector of alpha and beta particles and with an electrically cooled HPGe detector dedicated for gamma-ray spectrometry, which is performed during the sampling. Data from a complex radiation monitoring network can be used, together with meteorological data, in radiation dispersion model by MicroStep-MIS. This model serves for simulation of atmospheric propagation of radionuclides

  11. Guide for the monitoring of radiation protection during national modification and maintenance operations. Report nr 307

    International Nuclear Information System (INIS)

    Bataille, C.; Michelet, M.; Schieber, C.

    2010-02-01

    This methodological guide aims at helping the different involved actors in designing and implementing the monitoring of radiation protection during modification and maintenance operations performed at the national level. It describes actions to be performed by each actor in order to comply with the objectives of the four steps related to the radiation protection monitoring of an operation: the design of the radiation protection monitoring during the study phase, the adaptation of this monitoring to the concerned CNPE (electricity production nuclear centre), the radiation protection monitoring during the operation performance, and the analysis of the return on experience

  12. Centralized environmental radiation monitoring system in JAERI

    International Nuclear Information System (INIS)

    Katagiri, H.; Kobalyashi, H.

    1993-01-01

    JAERI has continued the environmental radiation background survey and monitoring to ensure the safety of the peoples around the institute since one year before the first criticality of JRR-1 (Japan Research Reactor No.1) in August 1957. Air absorbed doses from β and γ radiation, α and β radioactivity in air and the radioactivities in environmental samples were the monitoring items. For the monitoring of β and γ radiation and α and β radioactivity in air, monitoring station and the centralized automatic environmental radiation monitoring system applying a computer were established as a new challenging monitoring system for nuclear facility, which was the first one not only in Japan but also in the would in 1960 and since then the system has been renewed two times (in 1973 and 1988) by introducing the latest technology in the fields of radiation detection and computer control at each stage. Present system renewed in 1988 was designed to prevent the interruption of monitoring due to computer troubles, communication troubles and power failures especially an instant voltage drop arisen from thunder by reflecting the experiences through the operation and maintenance of the former system. Dual telemeters whose power is constantly supplied via batteries (capable of 10 min monitoring after power failure) are equipped in the monitoring center to cope with telemeter troubles, which has operated successfully without any suspension being attributable to the power failures and telemeter troubles

  13. Ultra High Fluence Radiation Monitoring Technology for the Future Circular Collider at CERN

    CERN Document Server

    Gorine, Georgi; Mandic, Igor; Jazbec, Anže; Snoj, Luka; Capeans, Mar; Moll, Michael; Bouvet, Didier; Ravotti, Federico; Sallese, Jean-Michel

    2018-01-01

    The Future Circular Collider (FCC) is foreseen as the next generation ~100 km long synchrotron to be built in the Geneva area starting 2050. This machine is expected to reach an energy level of 100 TeV generating unprecedented radiation levels >100 times higher than in today`s Large Hadron Collider (LHC). Current Radiation Monitoring system, like the RADMONs employed in the LHC, will not be capable to function and withstand this harsh environment. The development of a new Ultra High Fluence and Dose Radiation Sensor is a key element to allow irradiation tests of FCC equipment and, at a later stage, to monitor radiation levels in the FCC itself. In this paper, we present an innovative dosimetry solution based on thin layers of metals, which resistivity is shown to increase significantly due to the accumulated displacement damage. After describing the fabrication techniques used to manufacture these Radiation Dependent Resistors (RDR), we show and discuss the results of the irradiation experiments carried out ...

  14. Emergency response and radiation monitoring systems in Russian regions

    International Nuclear Information System (INIS)

    Arutyunyan, R.; Osipiyants, I.; Kiselev, V.; Ogar, K; Gavrilov, S.

    2008-01-01

    Full text: Preparedness of the emergency response system to elimination of radiation incidents and accidents is one of the most important elements of ensuring safe operation of nuclear power facilities. Routine activities on prevention of emergency situations along with adequate, efficient and opportune response actions are the key factors reducing the risks of adverse effects on population and environment. Both high engineering level and multiformity of the nuclear branch facilities make special demands on establishment of response system activities to eventual emergency situations. First and foremost, while resolving sophisticated engineering and scientific problems emerging during the emergency response process, one needs a powerful scientific and technical support system.The emergency response system established in the past decade in Russian nuclear branch provides a high efficiency of response activities due to the use of scientific and engineering potential and experience of the involved institutions. In Russia the responsibility for population protection is imposed on regional authority. So regional emergence response system should include up-to-date tools of radiation monitoring and infrastructure. That's why new activities on development of radiation monitoring and emergency response system were started in the regions of Russia. The main directions of these activities are: 1) Modernization of the existing and setting-up new facility and territorial automatic radiation monitoring systems, including mobile radiation surveillance kits; 2) Establishment of the Regional Crisis Centres and Crisis Centres of nuclear and radiation hazardous facilities; 3) Setting up communication systems for transfer, acquisition, processing, storage and presentation of data for participants of emergency response at the facility, regional and federal levels; 4) Development of software and hardware systems for expert support of decision-making on protection of personnel, population

  15. Integrating working level monitor EML Type TF-11

    International Nuclear Information System (INIS)

    Latner, N.; Watnick, S.; Graveson, R.T.

    1981-01-01

    A time-integrating working level radiation monitor is described. The purpose of the instrument is the evaluation of the alpha emission from radon and its daughter products. It has been designed to be virtually silent in operation, making it suitable for residential studies

  16. Environmental radiation monitoring of Mumbai to Visakhapatnam by rail route

    International Nuclear Information System (INIS)

    Pujari, R.N.; Saindane, Shashank; Narsaiah, M.V.R.; Sreekanth, B.; Joshi, G.H.; Pradeepkumar, K.S.

    2014-01-01

    The paper describes study of variation of environmental radiation dose rates in natural background from Mumbai to Visakhapatnam by using various state of the art radiation monitoring instruments deployed in the railway coach. The study determines the radiation levels on the rail route of the region as a part of National Level Preparedness for response to Radiological Emergencies which will act as a baseline data for reference. The survey indicated a rising trend in the natural radiation background along Mumbai to Visakhapatnam route and maximum level in the Deccan plateau was observed near Hyderabad. The distance covered during the survey from Mumbai to Visakhapatnam via Pune, Solapur, Gulbarga, Hyderabad, Warangal and Vijayawada was 1650 kms, average speed was 55 km/h and around 10,500 data points were recorded

  17. Distributed hierarchical radiation monitoring system

    International Nuclear Information System (INIS)

    Barak, D.

    1985-01-01

    A solution to the problem of monitoring the radiation levels in and around a nuclear facility is presented in this paper. This is a private case of a large scale general purpose data acqisition system with high reliability, availability and short maintenance time. The physical layout of the detectors in the plant, and the strict control demands dictated a distributed and hierarchical system. The system is comprised of three levels, each level contains modules. Level one contains the Control modules which collects data from groups of detectors and executes emergency local control tasks. In level two are the Group controllers which concentrate data from the Control modules, and enable local display and communication. The system computer is in level three, enabling the plant operator to receive information from the detectors and execute control tasks. The described system was built and is operating successfully for about two years. (author)

  18. Application of maximum radiation exposure values and monitoring of radiation exposure

    International Nuclear Information System (INIS)

    1993-01-01

    According to the Section 32 of the Radiation Act (592/91) the Finnish Centre for Radiation and Nuclear Safety gives instructions concerning the monitoring of the radiation exposure and the application of the dose limits in Finland. The principles to be applied to calculating the equivalent and the effective doses are presented in the guide. Also the detailed instructions on the application of the maximum exposure values for the radiation work and for the natural radiation as well as the instructions on the monitoring of the exposures are given. Quantities and units for assessing radiation exposure are presented in the appendix of the guide

  19. Use of a microprocessor in a remote working level monitor

    International Nuclear Information System (INIS)

    Keffe, D.J.; McDowell, W.P.; Groer, P.G.

    1975-01-01

    A remote working level monitor was designed to measure short-lived radon-daughter concentrations in sealed chambers having potentially high radiation levels (up to 2000 WL). The system is comprised of surface barrier detectors, multiplexer and buffers, microprocessor and teletype

  20. NRC TLD [thermoluminescent dosimeter] Direct Radiation Monitoring Network: Progress report, October--December 1988

    International Nuclear Information System (INIS)

    Struckmeyer, R.; NcNamara, N.

    1989-04-01

    This report presents the results of the NRC Direct Radiation Monitoring Network for the fourth quarter of 1988. It provides the ambient radiation levels measured in the vicinity of 75 sites throughout the United States. In addition, it describes the equipment used, monitoring station selection criteria, characterization of the dosimeter response, calibration procedures, statistical methods, intercomparison, and quality assurance program. 4 tabs

  1. Design of Kartini reactor radiation monitor system using lab view

    International Nuclear Information System (INIS)

    Adi Abimanyu; Jumari; Achmad Fahrul Aji; Muhammad Khoiri

    2014-01-01

    Kartini Reactor operation will result in radiation exposure. Gamma radiation exposure rate at the Kartini Reactor monitored by several radiation monitors (Ludlum) that integrate with the computer, so that the rate of radiation exposure is always monitored. Current monitoring system combines six radiation monitor in one computer monitor radiation, and monitoring performed by operators and supervisors to see how the radiation exposure rate measured in the area around the reactor core in a periodic time manually. This research will develop a system to monitor radiation exposure in Kartini reactor based ATMega8 micro controller for interface between radiation monitor and computer and also Graphical User Interface (GUI) develop using Lab view software that makes monitoring is easier and documented regularly. This system is testing by simulation, it is done by replacing the function of the radiation monitoring devices (Ludlum) in Kartini Reactor with computers that send serial data with the same format with a format that is sent by Ludlum. The results show that the interface system has the ability to operate in a range of baud rate 1,200 bps, 2,400 bps, 4,800 bps, 9,600 bps, 14,400 bps, 19,200 bps and 38,400 bps, with the ability to provide realtime information every 6 seconds and able to document the rate of exposure to radiation in the form of logbook. (author)

  2. The purpose of radiation protection monitoring

    International Nuclear Information System (INIS)

    Morgan, K.Z.

    1979-01-01

    In the early period (1942-1960) of nuclear energy programmes with which I was associated, most radiation protection standards seem to have been formulated on the assumption that there is a threshold dose of ionizing radiation below which no radiation damage is expected to result in the lifetime of the exposed individual. It was in this climate of opinion that health physics began as a profession, and levels of maximum permissible exposure (MPE) to external sources of radiation, maximum permissible concentrations in air, water and food, and maximum permissible body burdens of radionuclides inside the human body were set and enforced. Some of the levels of MPE were quite high in comparison with present standards but, fortunately, the health physicists at the national laboratories in which most radiation workers were employed were very conservative; in most cases the average annual exposures were less than 10% of the MPE levels. However, there was not much concern with the man-rem concept, as exemplified by rather high levels of radioactive waste discharged from the plants or placed in temporary holding facilities - where there was a likely possibility of seepage into the environment. This situation was understandable and justifiable at a time when the purpose of radiation protection monitoring was simply to prevent individuals from exceeding a threshold dose. The period of the recent past up to the present time (1978) has been one in which there has been a gradual change from the concept of a threshold dose hypothesis to the linear hypothesis. In this period the International Commission on Radiological Protection (ICRP) and the national standards setting bodies have pointed out that the levels they have selected are based on the linear hypothesis, but in most respects they leave us with the impression that this is most probably a conservative assumption, subject to revision when better data become available. Also, during this period, the concept of exposure As Low As

  3. 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)

  4. Radiation monitoring at Sizewell B PWR

    International Nuclear Information System (INIS)

    Hills, O.C.

    1992-01-01

    Radiation monitoring in Sizewell-B Power Station most significantly differs from that in existing UK Power Stations in two respects: firstly in the large number of on-line radiation monitors and secondly in the way that the monitors are linked into a fully-integrated, centralised data acquisition and display system, which can be accessed and viewed by the operators. An overview is given of how full process data is transmitted along data links between the Auxiliary Shut-Down Room, Technical Support Centre and Main Control Room, enabling Health Physics and other staff to access information from any radiation monitor. The permanently installed monitors together with the safety category, type and location are listed. As part of the Sizewell-B Process Plant control and instrumentation contract, NEI is to supply the Health Physics Instrumentation (HPI) and Process and Effluent Activity Monitoring System (PEAMS) (excluding the Primary Protection System) plus the Nuclear Sampling System (NSS). This paper concentrates on the HPI, and parts of the PEAMS and NSS for which NEI have the responsibility for system design, detail design, manufacture, site installation and commissioning. Section 2 briefly describes the sources of radiation at Sizewell-B; Sections 3, 4 and 5 describe the PEAMS, HPI and NSS respectively. Section 6 details the design of two of the Sizewell-B PEAMS subsystems. (Author)

  5. Radiation detectors as surveillance monitors

    International Nuclear Information System (INIS)

    Fehlau, P.E.; Dowdy, E.J.

    1981-01-01

    The International Atomic Energy Agency (IAEA) proposes to use personnel dosimetry radiation detectors as surveillance monitors for safeguards purposes. It plans to place these YES/NO monitors at barrier penetration points declared closed under IAEA safeguards to detect the passage of plutonium-bearing nuclear material, usually spent fuel. For this application, commercially available dosimeters were surveyed as well as other radiation detectors that appeared suitable and likely to be marketed in the near future. No primary advantage was found in a particular detector type because in this application backgrounds vary during long counting intervals. Secondary considerations specify that the monitor be inexpensive and easy to tamper-proof, interrogate, and maintain. On this basis radiophotoluminescent, thermoluminescent, and electronic dosimeters were selected as possible routine monitors; the latter two may prove useful for data-base acquisition

  6. 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

  7. Radiation monitoring data representation for duty personnel

    Energy Technology Data Exchange (ETDEWEB)

    Gavrilov, S.L.; Kiselev, V.P.; Krasnoperov, S.N.; Kudeshov, E.V.; Maslov, S.Y.; Semin, N.N.; Sirotinskiy, S.E.; Yakovlev, V.Y. [Nuclear Safety Institute of the Russian Academy of Sciences (NSI RAS), Moscow (Russian Federation)

    2014-07-01

    Currently, Web-GIS technologies are widely used to generate a reliable and intuitive web-based interface to monitor the current radiation situation in various regions of the Russian Federation. The developed 'Server Web-Monitoring' web-application is intended for duty personnel and can operate not only on desktop computers but also on mobile devices. The subsystem of duty personnel notification about any Off-Normal Situation (ONS) (such as: critical threshold exceedances or failures in operation of monitoring systems) is also considered in the paper. Three types of Automated Radiation Monitoring Systems (ARMS) are available for monitoring: - regional ARMS; - facility-level ARMS; - ARMS of nuclear power plant surveillance areas. Google Maps and Google Maps API toolbox are used as the cartographic basis. In the general-monitoring window only general information on each of the local systems is available. Next, the operator can move to monitoring of local ARMS he is interested in. The operator can either view a list of Radiation Situation Monitoring Posts (RSMP) showing the current data in the right frame or hide it and use the map only. Viewing the log of critical threshold exceedances for 24 hours and a report on all RSMPs of a given system over the last 7 days is also possible. The report contains maximum values of measurements for every day and for each RSMP. The developed web-application includes: - monitoring of the radiation situation and its changes on the general map of the Russian Federation and on maps of local ARMS; - displaying 7-day reports for all RSMPs of the selected ARMS; - displaying the log of critical threshold exceedances recorded over the past day. The notification subsystem informs duty personnel on all ONS, namely, on critical threshold exceedances in the incoming data and failures in operation of monitoring systems. The key features of the notification subsystem are: - round-the-clock functioning; - automatic notification in case of

  8. Morsleben repository for radioactive waste (ERAM). Operational safety, radiation protection and environmental monitoring. Release: December 2009

    International Nuclear Information System (INIS)

    2010-01-01

    The report overviews the monitoring activities of the Federal Office for Radiation Protection at the Morsleben repository for radioactive waste (ERAM), focussing the ERAM inventory of radioactive waste and the measures and results of geomechanical and hydrogeological monitoring, operational radiation protection, the monitoring of discharges of radioactive substances, environmental monitoring, and the dose levels expected from discharges of radioactive substances. (orig.)

  9. Status of radiation detector and neutron monitor technology

    CERN Document Server

    Kim, Y K; Ha, J H; Han, S H; Hong, S B; Hwang, I K; Lee, W G; Moon, B S; Park, S H; Song, M H

    2002-01-01

    In this report, we describe the current states of the radiation detection technology, detectors for industrial application, and neutron monitors. We also survey the new technologies being applied to this field. The method to detect radiation is the measurement of the observable secondary effect from the interaction between incident radiation and detector material, such as ionization, excitation, fluorescence, and chemical reaction. The radiation detectors can be categorized into gas detectors, scintillation detectors, and semiconductor detectors according to major effects and main applications. This report contains the current status and operational principles of these detectors. The application fields of radiation detectors are industrial measurement system, in-core neutron monitor, medical radiation diagnostic device, nondestructive inspection device, environmental radiation monitoring, cosmic-ray measurement, security system, fundamental science experiment, and radiation measurement standardization. The st...

  10. Monitoring radiation use in cardiac fluoroscopy imaging procedures

    International Nuclear Information System (INIS)

    Stevens, Nathaniel T.; Steiner, Stefan H.; Smith, Ian R.; MacKay, R. Jock

    2011-01-01

    Purpose: Timely identification of systematic changes in radiation delivery of an imaging system can lead to a reduction in risk for the patients involved. However, existing quality assurance programs involving the routine testing of equipment performance using phantoms are limited in their ability to effectively carry out this task. To address this issue, the authors propose the implementation of an ongoing monitoring process that utilizes procedural data to identify unexpected large or small radiation exposures for individual patients, as well as to detect persistent changes in the radiation output of imaging platforms. Methods: Data used in this study were obtained from records routinely collected during procedures performed in the cardiac catheterization imaging facility at St. Andrew's War Memorial Hospital, Brisbane, Australia, over the period January 2008-March 2010. A two stage monitoring process employing individual and exponentially weighted moving average (EWMA) control charts was developed and used to identify unexpectedly high or low radiation exposure levels for individual patients, as well as detect persistent changes in the radiation output delivered by the imaging systems. To increase sensitivity of the charts, we account for variation in dose area product (DAP) values due to other measured factors (patient weight, fluoroscopy time, and digital acquisition frame count) using multiple linear regression. Control charts are then constructed using the residual values from this linear regression. The proposed monitoring process was evaluated using simulation to model the performance of the process under known conditions. Results: Retrospective application of this technique to actual clinical data identified a number of cases in which the DAP result could be considered unexpected. Most of these, upon review, were attributed to data entry errors. The charts monitoring the overall system radiation output trends demonstrated changes in equipment performance

  11. Monitoring radiation use in cardiac fluoroscopy imaging procedures

    Energy Technology Data Exchange (ETDEWEB)

    Stevens, Nathaniel T.; Steiner, Stefan H.; Smith, Ian R.; MacKay, R. Jock [Department of Statistics and Actuarial Sciences, Business and Industrial Statistics Research Group, University of Waterloo, Waterloo, Ontario N2L 3G1 (Canada); St. Andrew' s Medical Institute, St. Andrew' s War Memorial Hospital, Brisbane, Queensland 4000 (Australia); Department of Statistics and Actuarial Sciences, Business and Industrial Statistics Research Group, University of Waterloo, Waterloo, Ontario N2L 3G1 (Canada)

    2011-01-15

    Purpose: Timely identification of systematic changes in radiation delivery of an imaging system can lead to a reduction in risk for the patients involved. However, existing quality assurance programs involving the routine testing of equipment performance using phantoms are limited in their ability to effectively carry out this task. To address this issue, the authors propose the implementation of an ongoing monitoring process that utilizes procedural data to identify unexpected large or small radiation exposures for individual patients, as well as to detect persistent changes in the radiation output of imaging platforms. Methods: Data used in this study were obtained from records routinely collected during procedures performed in the cardiac catheterization imaging facility at St. Andrew's War Memorial Hospital, Brisbane, Australia, over the period January 2008-March 2010. A two stage monitoring process employing individual and exponentially weighted moving average (EWMA) control charts was developed and used to identify unexpectedly high or low radiation exposure levels for individual patients, as well as detect persistent changes in the radiation output delivered by the imaging systems. To increase sensitivity of the charts, we account for variation in dose area product (DAP) values due to other measured factors (patient weight, fluoroscopy time, and digital acquisition frame count) using multiple linear regression. Control charts are then constructed using the residual values from this linear regression. The proposed monitoring process was evaluated using simulation to model the performance of the process under known conditions. Results: Retrospective application of this technique to actual clinical data identified a number of cases in which the DAP result could be considered unexpected. Most of these, upon review, were attributed to data entry errors. The charts monitoring the overall system radiation output trends demonstrated changes in equipment

  12. Personal radiation monitoring

    International Nuclear Information System (INIS)

    Julius, H.W.

    1976-01-01

    This report reviews the context of a primary university course in individual radiation monitoring. A brief account of the regulations and permissible doses is given. The principles and design of film dosemeters, thermoluminescent dosemeters and the whole-body counting technique are treated

  13. A unique radiation area monitoring system

    International Nuclear Information System (INIS)

    Murphy, P.C.; Allen, G.C.

    1978-01-01

    The Remote Area Monitoring Systems (RAMS) monitors four radiation areas with two independent systems in each area. Each system consists of power supplies, four ionization chambers, and four analog and digital circuits. The first system controls the warning beacons, horns, annunciation panel and interlocks. The second system presents a quantitative dose rate indication at the console and in the radiation area

  14. Regulatory control of low level radiation exposure in Tanzania

    International Nuclear Information System (INIS)

    Nyanda, A.M.; Muhogora, W.E.

    1997-01-01

    In Tanzania, the radiation protection law was issued in 1983. Under this law, the National Radiation Commission is responsible for safe uses of ionizing radiation. The regulatory control of the resulting doses from the uses of radiation sources in medicine, industry, research and teaching is presented. The system of control reflects the existing interactions between the National Radiation Commission and users through the established radiation protection infrastructure. From the national dose registry data, it is found that the highest annual individual doses over 10 years ago, came from less than 5% of total monitored workers and were in the range 10 - 15 mSv y -1 . The experienced radiation levels in uncontrolled areas of potential workplaces is less than 1 μSv h -1 . The possibility for associating such low dose levels to the effectiveness of the existing regulatory dose control framework is discussed. Despite of this achievement, the need to improve further the radiation protection and safety programs is found necessary. (author)

  15. First Results from the Online Radiation Dose Monitoring System in ATLAS experiment

    CERN Document Server

    Mandić, I; The ATLAS collaboration; Deliyergiyev, M; Gorišek, A; Kramberger, G; Mikuž, M; Franz, S; Hartert, J; Dawson, I; Miyagawa, P; Nicolas, L

    2011-01-01

    High radiation doses which will accumulate in components of ATLAS experiment during data taking will causes damage to detectors and readout electronics. It is therefore important to continuously monitor the doses to estimate the level of degradation caused by radiation. Online radiation monitoring system measures ionizing dose in SiO2 , displacement damage in silicon in terms of 1-MeV(Si) equivalent neutron fluence and fluence of thermal neutrons at several locations in ATLAS detector. In this paper design of the system, results of measurements and comparison of measured integrated doses and fluences with predictions from FLUKA simulation will be shown.

  16. The Global Environment Radiation Monitoring Network (GERMON)

    International Nuclear Information System (INIS)

    Zakheim, B.J.; Goellner, D.A.

    1994-01-01

    Following the Chernobyl accident in 1986, a group of experts from the World Health Organization (WHO) and the United Nations Environment Program (UNEP) met in France to discuss and develop the basic principles of a global environmental radiation monitoring network (GERMON). The basic functions of this network were to provide regular reports on environmental radiation levels and to be in a position to provide reliable and accurate radiation measurements on a quick and accurate radiation measurements on a quick turnaround basis in the event of a major radiation release. By 1992, although 58 countries had indicated an interest in becoming a part of the GERMON system, only 16 were providing data on a regular basis. This paper traces the history of GERMON from its inception in 1987 through its activities during 1993-4. It details the objectives of the network, describes functions, lists its participants, and presents obstacles in the current network. The paper examines the data requirements for radiological emergency preparedness and offers suggestions for the current system. The paper also describes the growing need for such a network. To add a domestic perspective, the authors present a summary of the environmental monitoring information system that was used by the NRC in 1986 in its analyses of the Chernobyl incident. Then we will use this 1986 experience to propose a method for the use of GERMON should a similar occasion arise in the future

  17. The calibration procedure of the radiation monitoring system installed in radiation controlled area of KOMAC

    Energy Technology Data Exchange (ETDEWEB)

    Park, Sung-Kyun; Min, Yi-Sub; Park, Jeong-Min; Cho, Yong-Sub [Korea Atomic Energy Research Institute, Gyeongju (Korea, Republic of)

    2016-10-15

    The spaces, where these accelerators are installed, are defined as the radiation controlled area and the levels of the radiation in this area are monitored by the radiation monitoring system (RMS) to protect radiation workers and experiment users from the hazards of the ionizing radiation and the surface and air contamination tests are carried out periodically by the radiation secure team. The most of RMS instruments are installed in the accelerator building, where the 100-MeV proton linear accelerator is installed. All detectors of RMS should be calibrated every year to prove the reliability of RMS and almost all instruments for RMS was calibrated during this summer maintenance period of KOMAC this year. Almost all RMS instruments installed in KOMAC is calibrated between 2016-07-13 and 2016-08-24. As the calibration result, if the current reading value are within the 5% of the reference dose rate value, this RMS instrument can be used one more year. Otherwise, the detector of that RMS instrument should be repaired or replaced. The self-calibration certificate for each RMS instrument will be published only for the instrument to satisfy the condition.

  18. Standalone, battery powered radiation monitors for accelerator electronics

    CERN Document Server

    Wijnands, T; Spiezia, G

    2009-01-01

    A technical description of the design of a new type of radiation monitors is given. The key point in the design is the low power consumption inferior to 17 mW in radiation sensing mode and inferior to 0.3 mW in standby mode. The radiation monitors can operate without any external power or signal cabling and measure and store radiation data for a maximum period of 800 days. To read the radiation data, a standard PC can be connected via a USB interface to the device at any time. Only a few seconds are required to read out a single monitor. This makes it possible to survey a large network of monitoring devices in a short period of time, for example during a stop of the accelerator.

  19. Development Of Data Acquisition Software For Centralized Radiation Monitoring System

    International Nuclear Information System (INIS)

    Nolida Yussup; Maslina Mohd Ibrahim; Mohd Fauzi Haris; Syirrazie Che Soh; Harzawardi Hasim; Azraf Azman; Mohd Ashhar Khalid

    2014-01-01

    Nowadays, with the growth of technology, many devices and equipment's can be connected to the network and internet to enable online data acquisition. Centralized radiation monitoring system utilizes a Local Area Network (LAN) as a communication media for data acquisition of the area radiation levels from radiation detectors in Malaysian Nuclear Agency (Nuclear Malaysia). The development of the system involves device configuration, wiring, network and hardware installation, software and web development. This paper describes the software development on the system server that is responsible to acquire and record the area radiation readings from the detectors. Then the recorded readings are called in a web programming to be displayed on a web site. The readings with the time stamp are stored in the system database for query. Besides acquiring the area radiation levels in Nuclear Malaysia centrally, additional features such as data conversion from mR to μSv and line chart display are developed in the software for effective radiation level trend observation and studies. (author)

  20. Radiation Monitoring in a Newly Established Nuclear Medicine Facility

    International Nuclear Information System (INIS)

    Afroj, Kamila; Anwar-Ul-Azim, Md.; Nath, Khokon Kumar; Khan, Md. Rezaul Karim

    2010-05-01

    A study of area monitoring in a nuclear medicine department's new physical facility was performed for 3 months to ascertain the level of radiation protection of the staff working in nuclear medicine and that of the patients and patient's attendants. Exposure to nuclear medicine personnel is considered as occupational exposure, while exposure to patients is considered medical exposure and exposure to patients' attendants is considered public exposure. The areas for the sources of radiation considered were the hot laboratory, where unsealed isotopes, radionuclides, generators are stored and dosages are prepared, the patients' waiting room, where the radioactive nuclides are administered orally and intravenously for diagnosis and treatment and the SPECT rooms, where the patients' acquisition are taken. The monitoring process was performed using the TLD supplied and measured by the Health Physics Division of Bangladesh Atomic Energy Commission. The result shows no over-exposure of radiation from any of the working areas. The environment of the department is safe for work and free from unnecessary radiation exposure risk. (author)

  1. Suggestions for the Improvement of Environmental Radiation Monitoring in Kenya

    International Nuclear Information System (INIS)

    Shadrack, A. K.

    2012-01-01

    Environmental radiation monitoring in Kenya was started in 1990 following the 1979 Three Mile Island and the 1986 Chernobyl nuclear power plants accidents. The main purpose was to measure the radioactivity of foodstuffs imported from oversees and to carry out environmental radiation monitoring of soil, rock, water and air sample to check for contamination. Through environmental radiation monitoring, the Food and Environmental Monitoring Section (FEM) of the Kenya Radiation Protection Board (RPB) works to protect the public and environment from hazards associated with ionizing radiation. The purpose of this paper was to highlight suggestions for the improvement of environmental radiation monitoring in Kenya with respect to protecting the public and the environment against undue radiation risk by ensuring that potential exposures are kept As Low As Reasonably Achievable (ALARA). The suggestions for improvement will serve as a guideline for the strengthening of environmental radiation monitoring program in Kenya

  2. Radiation monitoring network of the Czech Republic

    International Nuclear Information System (INIS)

    Kuca, P.; Novak, L.; Rulik, P.; Tecl, J.

    2003-01-01

    The Radiation Monitoring Network (RMN) of the Czech Republic was established after the Chernobyl accident in 1986 and it is developed all the time. It is co-ordinated by the State Office for Nuclear Safety in co-operation with the National Radiation Protection Institute. Czech RMN consists of the several sub-networks, which include selected or all permanent parts of RMN. The sub-networks are following: the Early Warning Network (EWN), the TLD Territorial Network, the Network of the Measuring Sites of Air Contamination, the Network of Laboratories Equipped with Gamma-spectrometric and Radiochemical Analytical Instrumentation, the Ground and Airborne Mobile Groups. The Laboratory of Monitoring of Internal Contamination and the information system (IS) are a significant part of RMN, too. The data of RMN resulting from monitoring are transferred to the central database of CRMN, processed by the information system (IS). They are used in normal and emergency situations for an evaluation of radiation situation and for preparation of recommendations for protection of the public and the environment. In 2002 any extraordinary radioactivity in the environment was not detected and also none of the measuring points recorded any exceeding of established investigation levels. In components of environment and also in human beings a very low activity of 137 Cs was still measurable, that had been released into environment after the Chernobyl accident and by the nuclear weapon tests in sixties of the last century. (authors)

  3. Radiation environmental real-time monitoring and dispersion modelling

    International Nuclear Information System (INIS)

    Kovacik, Andrej; Bartokova, Ivana; Melicherova, Terezia; Omelka, Jozef

    2015-01-01

    The MicroStep-MIS system of real-time radiation monitoring, which provides a turn-key solution for measurement, acquisition, processing, reporting, archiving and displaying of various radiation data, is described and discussed in detail. The qualities, long-term stability of measurement and sensitivity of the RPSG-05 probe are illustrated on its use within the radiation monitoring network of the Slovak Hydrometeorological Institute and within the monitoring network in the United Arab Emirates. (orig.)

  4. Optimization of in-vivo monitoring program for radiation emergency response

    Energy Technology Data Exchange (ETDEWEB)

    Ha, Wi Ho; Kim, Jong Kyung [Dept. of Nuclear Engineering, Hanyang University, Seoul (Korea, Republic of)

    2016-12-15

    In case of radiation emergencies, internal exposure monitoring for the members of public will be required to confirm internal contamination of each individual. In-vivo monitoring technique using portable gamma spectrometer can be easily applied for internal exposure monitoring in the vicinity of the on-site area. In this study, minimum detectable doses (MDDs) for '1'3'4Cs, {sup 137}Cs, and {sup 131}I were calculated adjusting minimum detectable activities (MDAs) from 50 to 1,000 Bq to find out the optimal in-vivo counting condition. DCAL software was used to derive retention fraction of Cs and I isotopes in the whole body and thyroid, respectively. A minimum detectable level was determined to set committed effective dose of 0.1 mSv for emergency response. We found that MDDs at each MDA increased along with the elapsed time. 1,000 Bq for {sup 134}Cs and {sup 137}Cs, and 100 Bq for {sup 131}I were suggested as optimal MDAs to provide in-vivo monitoring service in case of radiation emergencies. In-vivo monitoring program for emergency response should be designed to achieve the optimal MDA suggested from the present work. We expect that a reduction of counting time compared with routine monitoring program can achieve the high throughput system in case of radiation emergencies.

  5. Personal radiation monitoring and assessment of doses received by radiation workers (1996)

    International Nuclear Information System (INIS)

    Morris, N.D.

    1996-12-01

    Since late 1986, all persons monitored by the Australian Radiation Laboratory have been registered on a data base which maintains records of the doses received by each individual wearer. At present, the Service regularly monitors approximately 30,000 persons, which is roughly 90 percent of those monitored in Australia, and maintains dose histories of over 75,000 people. The skin dose for occupationally exposed workers can be measured by using one of the five types of monitor issued by the Service: Thermoluminescent Dosemeter (TLD monitor), Finger TLD 3, Neutron Monitor, Special TLD and Environmental monitor. The technical description of the monitors is provided along with the method for calculating the radiation dose. 5 refs., 7 tabs., 5 figs

  6. A radiation monitoring system for nuclear power plants

    International Nuclear Information System (INIS)

    Iwai, Masaru; Nakamori, S.; Ikeda, H.; Oda, M.

    1974-01-01

    Safety with respect to radiation is vital factor, particularly in view of the increasing number of nuclear power plants. For this purpose, a radiation monitoring system is provided to perform constant supervision. This article describes the purpose, installation location, specifications and circuitry of a system which is divided into three units: the process monitor, area monitor and off-site monitor. (auth.)

  7. Federal Radiological Monitoring and Assessment Center Monitoring Manual Volume 2, Radiation Monitoring and Sampling

    Energy Technology Data Exchange (ETDEWEB)

    NSTec Aerial Measurement Systems

    2012-07-31

    The FRMAC Monitoring and Sampling Manual, Volume 2 provides standard operating procedures (SOPs) for field radiation monitoring and sample collection activities that are performed by the Monitoring group during a FRMAC response to a radiological emergency.

  8. NRC TLD [thermoluminescent dosimeter] Direct Radiation Monitoring Network: Progress report, January-March 1988

    International Nuclear Information System (INIS)

    Struckmeyer, R.; McNamara, N.

    1988-06-01

    This report provides the status and results of the NRC Thermoluminescent Dosimeter (TLD) Direct Radiation Monitoring Network. It presents the radiation levels measured in the vicinity of NRC licensed facility sites throughout the country for the first quarter of 1988

  9. Environmental radiation monitoring results for the period 1989-1999 in NAPS region using TLDs

    International Nuclear Information System (INIS)

    Basu, A.S.; Chougaonkar, M.P.; Mayya, Y.S.; Sadasivan, S.; Sharma, L.N.

    2001-06-01

    In this report, we present the results of environmental gamma radiation levels monitored around NAPS region using TLDs. The report gives quarterly environmental radiation monitoring data obtained during the period 1989-'99; i.e. during the operating phase of the reactor. Twenty eight TLD locations were selected within a radius of twenty six km. of which six were within the exclusion zone (radius 1.6 km). The mean gamma radiation level within the exclusion zone has been evaluated as 111 ± 6.6 mR/year and that for locations beyond the exclusion zone as 140 ± 14 mR/year. As these values are well within the corresponding pre-operational general background value of 142 ± 30 mR/year (Basu et. al 1989), it is concluded that the reactor operations have not contributed to any increase in the gamma radiation levels in the environs of the NAPS region. (author)

  10. 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

    length of 100 km was covered and the average gamma dose rate recorded was 66.6 nGy/h with standard deviation of ± 4.4 nGy/h. The background gamma levels have been substantially constant in the area of survey. A small difference of 10 nSv/h in average values between CARMS and Gamma Tracer is observed. This is due to different energy compensation technique used and calibration methods related to mounting of detectors and their size. It can be said that through such exercises by mobile radiation monitoring being carried out periodically are very useful in generation of nationwide baseline radiation dose rate and any future deviations due to industrial/malevolent activities can be identified and emergency measures can be implemented

  11. Monitoring of radiation exposure. Annual report 2000

    International Nuclear Information System (INIS)

    Rantanen, E.

    2001-03-01

    At the end of 2000, there were 1,779 valid safety licenses in Finland for the use of radiation. In addition, there were 2,038 responsible parties for dental x-ray diagnostics. The registry Radiation and Nuclear Safety Authority (STUK) listed 13,754 radiation sources and 270 radionuclide laboratories. In the year 2000 360 inspections were made concerning the safety licences and 53 concerning dental x-ray diagnostics. The import of radioactive substances amounted to 175,836 GBq and export to 74,420 GBq. Short-lived radionuclides produced in Finland amounted to 55,527 GBq. In the year 2000 there were 10,846 workers monitored for radiation exposure at 1,171 work sites. Of these employees, 27% received an annual dose exceeding the recording level. The annual effective dose limit was not exceeded. The total dose recorded in the dose registry(sum of the individual dosemeter readings) was 6.5 Sv in 2000

  12. Radiation-related monitoring and environmental research at the Nevada Test Site

    International Nuclear Information System (INIS)

    Anspaugh, L.R.; Patton, S.E.; Shinn, J.H.; Black, S.C.; Costa, C.F.; Elle, D.R.; Essington, E.H.; Gilbert, R.O.; Gonzalez, D.A.; Hunter, R.B.; Medica, P.A.; McArthur, R.D.; Thompson, C.B.; O'Farrell, T.P.; Romney, E.M.

    1990-01-01

    Beginning with the first nuclear-weapons-related tests at the Nevada Test Site (NTS) in 1951, a radiation-related monitoring program was established to determine the levels and distribution of radionuclides released. Primary methods involved survey-meter-equipped field-monitoring teams and placement of film badges and air-sampling devices at fixed locations. Beginning in the mid-1950s, more stringent standards, the results of this monitoring program, and the results of related research programs led to increased engineering efforts to reduce local fallout. With passage of the National Environmental Policy Act and increased concern about possible effects of radiation exposure, environmental activities related to the NTS increased. There is now an extensive monitoring program at the NTS to assess radiological conditions resulting from past tests and from continued testing of nuclear-weapons devices. In populated areas near NTS, there is also a monitoring effort that relies on assistance from local communities. Other efforts include reconstruction of radiation doses received by offsite residents during the 1950s and 1960s, determination of the current inventory and distribution of radionuclides in surface soil, and studies of the movement of radionuclides in the desert ecosystem

  13. 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

  14. Radiation protection monitoring. Proceedings of a regional seminar for Asia and the Far East on radiation protection monitoring

    International Nuclear Information System (INIS)

    1969-01-01

    Proceedings of a regional seminar for Asia and the Far East jointly organized by the IAEA and the World Health Organization, and held in Bombay, 9-13 December 1968. The meeting was attended by 83 participants from 12 countries In the region, and by eight experts from countries outside the region who presented review papers. Contents: Purpose of radiation protection monitoring (4 papers); Radiation monitoring and dosimetry (7 papers); Monitoring of the working environment (12 papers); Individual monitoring (14 papers); Monitoring instruments (7 papers); Calibration and maintenance of instruments (3 papers); List of participants; Author index. All papers, which are preceded by an abstract, as well as the discussions, are in English

  15. NRC TLD Direct Radiation Monitoring Network. Progress report, January-June 1981

    International Nuclear Information System (INIS)

    1982-04-01

    This report provides the status and results of the NRC Thermoluminescent Dosimeter (TLD) Direct Radiation Monitoring Network. It presents the radiation levels measured in the vicinity of 55 NRC-licensed facility sites throughout the country for the first half of 1981. The program objectives, scope, and methodology are given. The TLD system, dosimeter location, data processing scheme, and quality assurance program are outlined

  16. Environmental radiation monitoring system in nuclear power station

    International Nuclear Information System (INIS)

    Matsuoka, Sadazumi; Tadachi, Katsuo; Endo, Mamoru; Yuya, Hiroshi

    1983-01-01

    At the time of the construction of nuclear power stations, prior to their start of operation, the state of environmental radiation must be grasped. After the start of the power stations, based on those data, the system of environmental radiation monitoring is established. Along with the construction of Kashiwazaki-Kariwa Nuclear Power Station, The Tokyo Electric Power Co., Inc. jointly with Fujitsu Ltd. has developed a high-reliability, environmental radiation monitoring system, and adopted ''optical data highways'' using optical fiber cables for communication. It consists of a central monitoring station and 11 telemeter observation points, for collecting both radiation and meteorological data. The data sent to the central station through the highways are then outputted on a monitoring panel. They are analyzed with a central processor, and the results are printed out. (Mori, K.)

  17. Radiation monitoring in high energy research facility

    International Nuclear Information System (INIS)

    Miyajima, Mitsuhiro

    1975-01-01

    In High Energy Physics Research Laboratory, construction of high energy proton accelerator is in progress. The accelerator is a cascaded machine comprising Cockcroft type (50 keV), linac (20 MeV), booster synchrotron (500 MeV), and synchrotron (8-12 GeV). Its proton beam intensity is 1x10 13 photons/pulse, and acceleration is carried out at the rate of every 2 minutes. The essential problems of radiation control in high energy accelerators are those of various radiations generated secondarily by proton beam and a number of induced radiations simultaneously originated with such secondary particles. In the Laboratory, controlled areas are divided into color-coded four regions, red, orange, yellow and green, based on each dose-rate. BF 3 counters covered with thick paraffin are used as neutron detectors, and side-window GM tubes, NaI (Tl) scintillators and ionization chambers as γ-detectors. In red region, however, ionization chambers are applied to induced radiation detection, and neutrons are not monitored. NIM standards are adopted for the circuits of all above monitors considering easy maintenance, economy and interchangeability. Notwithstanding the above described systems, these monitors are not sufficient to complete the measurement of whole radiations over wide energy region radiated from the accelerators. Hence separate radiation field measurement is required periodically. An example of the monitoring systems in National Accelerator Laboratory (U.S.) is referred at the last section. (Wakatsuki, Y.)

  18. Environmental radiation monitoring around Korea nuclear fuel company

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Myung Ho; Lee, Chang Woo; Choi, Gyun Sik; Lee, Won Yun; Park, Hyu Gok; Park, Do Won [Korea Atomic Energy Research Institute, Taejeon (Korea)

    2002-01-01

    Environmental Radiation Monitoring was carried out with measurement of environmental radiation and environmental radioactivity analysis around Korea Nuclear Fuel Company. Environmental Radiation rates measured by portable ERM and accumulated dose rates measured by TLD were on the same level as those measured in the previous years. Total alpha and beta concentrations in the air particulates showed the similar values in all sampling points. The concentration of uranium isotopes in soils and underground waters were measured similar to natural uranium values. The concentration of uranium isotopes in surface waters and sediments around the nuclear facilities were somewhat higher than those from reference site. The concentrations of uranium isotopes in rain water and foods such as rices and vegetables were similar to natural uranium level, the environment around the nuclear facilities has been contaminated only to an insignificant extent. It is estimated that the environmental impact resulting from the operation of KNFC in 2001 was negligible. 31 refs., 30 figs., 41 tabs. (Author)

  19. Environmental radiation monitoring around Korea Nuclear Fuel Company

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Myung Ho; Lee, Chang Woo; Choi, Yong Ho; Cho, Yueng Hyun; Choi, Gyun Sik [Korea Atomic Energy Research Institute, Taejon (Korea)

    1999-12-01

    Environmental Radiation Monitoring was carried out with measurement of environmental radiation and environmental radioactivity analysis around Korea Nuclear Fuel Company. Environmental Radiation rates measured by Portable ERM and accumulated dose rates measured by TLD were same level compared with past years. Total alpha and beta concentrations in the air particulates showed the similar values in all sampling points. The concentration of uranium isotopes in soils and underground waters were measured similar to natural uranium values. The concentration of uranium isotopes in surface waters and sediments decreased with increasing distances from the point of discharge. The concentrations of uranium isotopes in rain water and foods such as rices and vegetables were not detected or measured similar to natural uranium level. Hence, the environment around the nuclear facilities in Korea has been contaminated only to an insignificant extent, although a small amount of disequilibated uranium was detected within 4 km downstream of the point of discharge of KNFC. 31 refs., 26 figs., 42 tabs. (Author)

  20. Increase in Efficiency of Use of Pedestrian Radiation Portal Monitors

    Science.gov (United States)

    Solovev, D. B.; Merkusheva, A. E.

    2017-11-01

    Most international airports in the world use radiation portal monitors (RPM) for primary radiation control organization. During the exploitation pedestrian radiation portal monitors operators (in the Russian Federation it is a special subdivision of customs officials) have certain problems related to the search of an ionizing radiation source causing the alarm signal of a radiation monitor. Radiation portal monitors at standard (factory) settings have to find out the illegal moving of the radioisotopes moved by physical persons passing through a controlled zone and having a steady radiation by the gamma or neutron channel. The problem is that recently the number of the ownerships who underwent treatment or medical diagnostics with the use of radio pharmaceuticals considerably increased, i.e,. ownerships represent such an ionizing radiation source. The operator of the radiation portal monitor has to define very quickly whether the ownership is a violator (takes unsolved radioisotopes illegally) or is just a patient of the clinic who underwent treatment/diagnostics with the use of radio pharmaceuticals. The research showing the radioisotopes which are most often used in the medical purposes are given in article, it is offered to use the new software developed by the authors allowing the operator of the radiation portal monitor to define the location of the ownership which has such ionizing radiation source by the activity of radiation similar to the radiation from radio pharmaceuticals.

  1. Environmental radiation monitoring around the nuclear facilities

    International Nuclear Information System (INIS)

    Lee, H.D.; Lee, Y.B.; Lee, W.Y.; Park, D.W.; Chung, B.G.

    1980-01-01

    For the KAERI site, various environmental samples were collected three times a month, and the natural environmental radiation levels were also measured at each sampling point. Measurements for gross alpha and beta radioactivities of the samples were routinely measured for all samples. Strontium-90 concentrations were also analysed for the fallout and air samples collected daily basis on the roof of the main building. Accumulated exposure including the possibility of determination of low level environmental radiation field by employing thermoluminescent dosimeter, CaSO 4 : Dsub(y)-0.4 teflon disc type, at 6 posts in on-site of the KAERI. As for Kori site, at 19 points of ON, OFF-site, and at the same time the environmental radiation exposure rate at each sampling point were measured. Several environmental samples such as surface soil, pine needles, water samples, milk sample and pasture samples were collected and analysed on a quarterly basis. As a result of the survey it can be said that no significant release of radiation to the environment due to the operations of nuclear facilities including research reactor at the KAERI and power reactor at the Kori has been found during the period of the survey and monitoring. (author)

  2. Monitoring of radiation exposure and registration of doses

    International Nuclear Information System (INIS)

    1993-01-01

    The Section 32 of the Finnish Radiation Act (592/91) defines the requirements to be applied to the monitoring of the radiation exposure and working conditions in Finland. The concepts relevant to the monitoring and guidelines for determining the necessity of the monitoring as well as its organizing are given in the guide. Instructions for reporting doses to the Dose Register of the Finnish Centre for Radiation and Nuclear Safety (STUK) are given, also procedures for situations leading to exceptional exposures are described. (9 refs.)

  3. Radiation detectors for personnel monitoring - current developments and future trends

    International Nuclear Information System (INIS)

    Kannan, S.

    2003-01-01

    The radiation detectors for personnel monitoring range from the conventional passive dosimeters like the film badge and the TLD, to sophisticated active dosimeters for integrated gamma, beta and neutron dose measurement. With the availability of high accuracy active dosimeters, the process of personnel monitoring, acceptability among radiation workers, record keeping and dose control have become more simplified. However the high level of sophistication in the active dosimeter has its own inevitable price tag and the new breed of active dosimeters are prohibitively costly. The silver lining, in the otherwise dark cost scenario of these dosimeters is the potential for cost reduction at least in some of the dosimeters in the near future

  4. Radiation protection and environmental monitoring in the area of the Asse shaft plant

    International Nuclear Information System (INIS)

    Meyer, H.; Mueller-Lyda, I.

    1990-08-01

    Personnel monitoring has been carried through in compliance with the Radiation Protection Ordinance. Environmental monitoring including measurement of local doses, local dose rates, and airborne radioactivity in the shaft has been made according to the provisions for radiation protection at the place of work. Maximum permissible personal doses or activity levels for occupationally exposed persons have not been exceeded in the reporting period. Exhaust air monitoring detected the nuclides H-3, C-14, Pb-210, and the short-lived daughter products of Rn-222 and Rn-220. The activity concentrations in the environment, determined from the measured annual release values, for some part have been lower than the average of natural concentrations of said nuclides. The radiation exposure due to emissions, measured at the least favourable point in the environment, has been far below the limits set by the Radiation Protection Ordinance. In conclusion: The radiation exposure of the personnel and of the population in the area of the Asse shaft plant due to the storage of radioactive is low, compared to the natural radiation exposure. (orig.) [de

  5. Radiation protection and environmental monitoring in the area of the Asse shaft plant

    International Nuclear Information System (INIS)

    Mueller-Lyda, I.; Meyer, H.

    1989-06-01

    Personnel monitoring has been carried through in compliance with the Radiation Protection Ordinance. Environmental monitoring including measurement of local doses, local dose rates, and airborne radioactivity in the shaft has been made according to the provisions for radiation protection at the place of work. Maximum permissible personal doses or activity levels for occupationally exposed persons have not been exceeded in the reporting period. Exhaust air monitoring detected the nuclides H-3, C-14, Pb-210, and the short-lived daughter products of Rn-222 and Rn-220. The activity concentrations in the environment, determined from the measured annual release values, for some part have been lower than the average of natural concentrations of said nuclides. The radiation exposure due to emissions, measured at the least favourable point in the environment, has been far below the limits set by the Radiation Protection Ordinance. In conclusion: The radiation exposure of the personnel and of the population in the area of the Asse shaft plant due to the storage of radioactive is low, compared to the natural radiation exposure. (orig.) [de

  6. GERMON. Global Environmental Radiation Monitoring Network

    International Nuclear Information System (INIS)

    1992-01-01

    Between 15-18 December 1987, a meeting of experts of WHO/UNEP met at Le Vesinet, France, to develop the basic principles of a global environmental radiation monitoring network (GERMON) which would have the function of reporting on a regular basis environmental radiation levels, and be positioned to provide rapid and reliable radiation measurements in the event of a major radiation release. To date, some 58 countries have indicated their willingness to become part of GERMON. About 40 of these have technical staff and equipment to meet the minimum requirements for joining the network, and about 30 have designated appropriate organizations within their country to serve as national Liaison Institutions for GERMON. Sixteen countries are now providing data on a regular basis to the CCC at SCPRI in Le Vesinet, France. Thirty-two countries responded to the request of WHO for readiness to take part in a IAEA radiation emergency exercise. The present meeting has been held in Montgomery, Alabama, USA at the National Air and Radiation Environmental Laboratory between 27 April 1992 and 30 April 1992, with the purpose of reviewing GERMON. One important topic considered was the implementation of GERMON in the Americas. Particular attention was given to the need for better coordination with IAEA in responding to the Convention on Early Notification, to the role of the CCC, to forms of data transmission, etc

  7. Radiation monitoring - the role of local authorities

    International Nuclear Information System (INIS)

    Duggan, Michael

    1988-01-01

    Seven reports of papers given at a symposium on the role of local authorities in radiation monitoring are given. The main theme is concerned with radiation monitoring, how to interpret the information and how it should be disseminated. The individual experiences in the aftermath of the Chernobyl reactor accident are used to illustrate several of the papers. (U.K.)

  8. A system for monitoring the radiation effects of a proton linear accelerator

    Energy Technology Data Exchange (ETDEWEB)

    Skorkin, V. M., E-mail: skorkin@inr.ru; Belyanski, K. L.; Skorkin, A. V. [Russian Academy of Sciences, Institute for Nuclear Research (Russian Federation)

    2016-12-15

    The system for real-time monitoring of radioactivity of a high-current proton linear accelerator detects secondary neutron emission from proton beam losses in transport channels and measures the activity of radionuclides in gas and aerosol emissions and the radiation background in the environment affected by a linear accelerator. The data provided by gamma, beta, and neutron detectors are transferred over a computer network to the central server. The system allows one to monitor proton beam losses, the activity of gas and aerosol emissions, and the radiation emission level of a linear accelerator in operation.

  9. Nuclear radiation sensors and monitoring following a nuclear or radiological emergencies

    International Nuclear Information System (INIS)

    Bhatnagar, P.K.

    2009-01-01

    Management of Nuclear and Radiological Emergencies arising from Radiological Dispersive Device (RDD), Improvised Nuclear Devices (IND), Nuclear Reactors/Power plants and Nuclear War require measurement of ionizing radiations and radioactivity on an enhanced scale relative to the levels encountered in peaceful uses of ionizing radiations and radioactivity. It is heartening that since Hiroshima, Nagasaki nuclear disaster, the world has been quiet but since early 2000 there has been a fear of certain devices to be used by terrorists, which could lead to panic, and disaster due to dispersal of radioactivity by RDD, IND. Nuclear attack would lead to blast, thermal, initial nuclear radiation, nuclear fall out leading to gamma and neutron dose, dose rates in range from few R, R/h to kR, kR/h, and determinations of k Bq or higher order. Such situations have been visualized at national levels and National Disaster Management Authority NDMA has been established and Disaster Management Act 2005 has come into existence. NDMA has prepared guidelines for Nuclear and radiological emergency management highlighting preparedness, mitigation, response, capacity building, etc. Critical point in all these issues is detection of emergency, quick intimation to the concerned for action in shortest possible time. Upper most requirement by those involved in pursuing action, is radiation sensor based radiation monitors for personnel, area, and to assess contamination due to radioactivity.This presentation briefly describes the Indian scenario in the development of the radiation sensors and the sensor-based radiation monitors. (author)

  10. Nuclear radiation sensors and monitoring following a nuclear or radiological emergencies

    Energy Technology Data Exchange (ETDEWEB)

    Bhatnagar, P K [Defence Laboratory, Jodhpur (India)

    2009-01-15

    Management of Nuclear and Radiological Emergencies arising from Radiological Dispersive Device (RDD), Improvised Nuclear Devices (IND), Nuclear Reactors/Power plants and Nuclear War require measurement of ionizing radiations and radioactivity on an enhanced scale relative to the levels encountered in peaceful uses of ionizing radiations and radioactivity. It is heartening that since Hiroshima, Nagasaki nuclear disaster, the world has been quiet but since early 2000 there has been a fear of certain devices to be used by terrorists, which could lead to panic, and disaster due to dispersal of radioactivity by RDD, IND. Nuclear attack would lead to blast, thermal, initial nuclear radiation, nuclear fall out leading to gamma and neutron dose, dose rates in range from few R, R/h to kR, kR/h, and determinations of k Bq or higher order. Such situations have been visualized at national levels and National Disaster Management Authority NDMA has been established and Disaster Management Act 2005 has come into existence. NDMA has prepared guidelines for Nuclear and radiological emergency management highlighting preparedness, mitigation, response, capacity building, etc. Critical point in all these issues is detection of emergency, quick intimation to the concerned for action in shortest possible time. Upper most requirement by those involved in pursuing action, is radiation sensor based radiation monitors for personnel, area, and to assess contamination due to radioactivity.This presentation briefly describes the Indian scenario in the development of the radiation sensors and the sensor-based radiation monitors. (author)

  11. Pre operational background radiation monitoring around Kudankulam Nuclear Power Project site - a decade long experience

    International Nuclear Information System (INIS)

    Vijayakumar, B.; George, Thomas; Sundara Rajan, P.; Selvi, B.S.; Balamurugan, M.; Pandit, G.G.; Ravi, P.M.; Tripathi, R.M.

    2014-01-01

    Pre-operational environmental background radiation monitoring around nuclear power plants is very important to understand baseline values existing in the site and also to identify any hot spots of naturally occurring high background radiation areas and their sources. These baseline measurements will act as a benchmark for future comparison after the reactors go into operation. The radiation measurements are continued during the operational phase of the plant and the results are compared to see whether there is any impact of the operation of the plant on the environment. A comprehensive background radiation monitoring plan has been in vogue at site from 2004 to meet this objective. This paper describes the different monitoring strategies adopted around Kudankulam Nuclear Power Project site and throws light on the pre operational background radiation levels in the environment

  12. NRC TLD Direct Radiation Monitoring Network. Progress report, October-December 1985. Volume 5, No. 4

    International Nuclear Information System (INIS)

    Jang, J.; Rabatin, K.; Cohen, L.

    1986-05-01

    This report presents the results of the NRC Direct Radiation Monitoring Network for the fourth quarter of 1985. It provides the ambient radiation levels measured in the vicinity of 74 sites throughout the United States. In addition, it describes the equipment used, monitoring station selection criteria, characterization of the dosimeter response, calibration procedures, statistical methods, intercomparison, and quality assurance program

  13. NRC TLD Direct Radiation Monitoring Network progress report, October--December 1994. Volume 14, No. 4

    Energy Technology Data Exchange (ETDEWEB)

    Struckmeyer, R.

    1995-03-01

    This report presents the results of the NRC Direct Radiation Monitoring Network for the fourth quarter of 1994. It provides the ambient radiation levels measured in the vicinity of 75 sites throughout the United States. In addition, it describes the equipment used, monitoring station selection criteria, characterization of the dosimeter response, calibration procedures, statistical methods, intercomparison, and quality assurance program.

  14. NRC TLD Direct Radiation Monitoring Network progress report, October--December 1994. Volume 14, No. 4

    International Nuclear Information System (INIS)

    Struckmeyer, R.

    1995-03-01

    This report presents the results of the NRC Direct Radiation Monitoring Network for the fourth quarter of 1994. It provides the ambient radiation levels measured in the vicinity of 75 sites throughout the United States. In addition, it describes the equipment used, monitoring station selection criteria, characterization of the dosimeter response, calibration procedures, statistical methods, intercomparison, and quality assurance program

  15. Remote level radiation monitoring system for the brazilian IEA-R1 nuclear research reactor for routine radiation protection procedures and as a support tool in case of radiological emergency

    International Nuclear Information System (INIS)

    Cardenas, Jose P.N.; Romero Filho, Christovam R.; Madi Filho, Tufic

    2008-01-01

    Nuclear facilities must monitoring radiation levels to establish procedures for radiological protection staff involving workers and the public. The Instituto de Pesquisas Energeticas e Nucleares - IPEN has 5 important plants and in case of accident in one of them, the Institute keeps operational an Emergency Response Plan (ERP). This document (ERP) is designed to coordinate all procedures to assure safe and secure conditions for workers, environment and the public. One of this plants is the IEA-R1 reactor, it is the oldest nuclear research reactor (pool type) in Latin America, reached it first criticality in September of 1957. The reactor is used 60 hours/week with continuous operation and with nominal power of 3.5 MW, with technical conditions to operate at 5 MW thermal power. This reactor has a Radiological Emergency Plan that establishes the implementation of rules for workers and people living at the exclusion area in the case of an emergency situation. This paper aims to describe the implementation of a computational system developed for remote radiation monitoring, in a continuous schedule of IEA-R1 nuclear research reactor containment building. Results of this action can be used as a support mean in a radiological emergency. All necessary modules for radiation detection, signals conditioners and processing, data acquisition board, software development and computer specifications are described. The data acquisition system operating in the reactor shows readings concerned to radiation environment such as activity, doses and concentration in real time and displays a periodical data bank (Data Base) of this features allowing through the surveillance of the operation records anytime, leading to studies and analysis of radiation levels. Results of this data acquisition are shown by means of computer graphics screens developed for windows environment using Visual Basic software. (author)

  16. Special nuclear material radiation monitors for the 1980's

    International Nuclear Information System (INIS)

    Fehlau, P.E.

    1985-01-01

    During the two decades that automatic gamma-radiation monitors have been applied to detecting special nuclear material (SNM), little attention has been devoted to how well the monitors perform in plant environments. Visits to 11 DOE facilities revealed poor information flow between developers, manufacturers, and maintainers of SNM radiation monitors. To help users achieve best performance from their monitors or select new ones, Los Alamos National Laboratory developed a hand-held monitor user's guide, calibration manuals for some commercial SNM pedestrian monitors, and an application guide for SNM pedestrian monitors. In addition, Los Alamos evaluated new commercial SNM monitors, considered whether to apply neutron detection to SNM monitoring, and investigated the problem of operating gamma-ray SNM monitors in variable plutonium gamma-radiation fields. As a result, the performance of existing SNM monitors will improve and alternative monitoring methods will become commerciallly available during the 1980s. 9 refs., 6 figs., 1 tab

  17. Occupational radiation exposure in Germany: many monitored persons = high exposure?

    International Nuclear Information System (INIS)

    Nitschke, J.

    1996-01-01

    Natural radiation affects the entire population in Germany, and most of Germany's inhabitants are exposed to medical radiation in their lifetime. Occupational radiation exposure, however, is a kind of exposure affecting only a limited and well-defined group of the population, and this radiation exposure has been recorded and monitored as precisely as technically possible ever since the radiation protection laws made occupational radiation exposure monitoring a mandatory obligation. Official personal dosimetry applying passive dosemeters in fact does not offer direct protection against the effects of ionizing radiation, as dosemeter read-out and dose calculation is a post-exposure process. But it nevertheless is a rewarding monitoring duty under radiation protection law, as is shown by the radiation exposure statistics accumulated over decades: in spite of the number of monitored persons having been increasing over the years, the total exposure did not, due to the corresponding improvements in occupational radiation protection. (orig.) [de

  18. Radiation monitoring network of the Czech Republic

    International Nuclear Information System (INIS)

    Drabova, D.; Prouza, Z.; Malatova, I.; Bucina, I.

    1996-01-01

    Radiation Monitoring Network of the Czech Republic (RMN) was established after the Chernobyl accident. It consists of technical centers, laboratories and monitoring groups of State Office for Nuclear Safety, National Radiation Protection Institute, nuclear power plants, hydrometeorological service, army and Civil Defense, research institutes and other institutions. The structure of RMN, its basic components and responsible institutions are described. (author)

  19. Organization and methods of radiation monitoring while working at nuclear critical assemblies

    International Nuclear Information System (INIS)

    Shishkin, G.V.; Komissarov, L.A.

    1980-01-01

    The organization and methods of environmental radiation monitoring while working at nuclear critical assemblies, are described. Necessary equipment for critical assemblies (signal and Ventilation systems, devices for recording accidental radiation levels of and for measuring radiation field distribution) and the personnel program of actions in case of nuclear accident. The dosimetric control at critical assemblies is usually ensured by telesystems. 8004-01 multi-channel dosimetric device is described as an example of such-system [ru

  20. Radiation protection monitoring at the JOYO experimental fast reactor

    International Nuclear Information System (INIS)

    Ouchi, S.; Endo, K.; Susaki, T.

    1979-01-01

    This paper describes the radiation protection monitoring programme for the JOYO experimental fast reactor and some of the health physics problems experienced during the low-power nuclear tests. These include: a detailed description of the centralized radiation monitoring system; the methods and results of the individual monitoring systems; the results of operational monitoring for the handling of new plutonium fuel subassemblies; the evaluation of the external radiation dose rate around the primary coolant system; and the results of an experiment on the thermal dependence of some personnel dose meters. (author)

  1. National environmental radiation monitoring program: towards formulating policy on radioactive waste management

    International Nuclear Information System (INIS)

    Sukiman Sarmani

    2002-01-01

    Though Malaysia has no nuclear power station, but the management of its low level radioactive waste generated from industrial activities involves most of the same issues that must be considered in countries with nuclear power. These include public consultation at all stages, an open approach, high level scientific and engineering input and political decision by the Government. A carefully planned approach, which involves the public and gives time to build trust and confidence, is necessary for success. It is also pertinent to establish accurate and reliable data on environmental radiation to accurately assess possible risk. This is where a national monitoring program on environmental radiation is very important. While accurate data will help formulate sound policy on radioactive waste management, it should also be readily available to the public to gain support and acceptance. This paper presents arguments on the importance of a national monitoring program for environmental radiation as an input for formulating a policy on radioactive waste management in Malaysia. (Author)

  2. Radiation monitoring systems: current status and future prospects

    International Nuclear Information System (INIS)

    McArthur, W.C.; Kniazewycz, B.G.

    1978-01-01

    The Radiation Monitoring System (RMS) in a nuclear power plant is used for assessing radiological impact of plant operation. A classical RMS consists of several types of radiation detectors strategically placed about a nuclear plant to ensure the safety of operating personnel and the surrounding environment. It serves in conjunction with, and as a backup to, a comprehensive sampling program to quantitatively evaluate process systems and effluent activity levels. The development of the computerized and digitalized RMS is reviewed with emphasis upon its added capability and flexibility. The potential future requirements for the RMS, as a result of regulatory criteria development, is briefly discussed

  3. Offsite environmental monitoring report. Radiation monitoring around United States nuclear test areas, calendar year 1983

    International Nuclear Information System (INIS)

    Patzer, R.G.; Black, S.C.; Grossman, R.F.; Smith, D.D.

    1984-07-01

    This report covers the routine radiation monitoring activities conducted by the Environmental Monitoring Systems Laboratory-Las Vegas in areas which may be affected by nuclear testing programs of the Department of Energy. This monitoring is conducted to document compliance with standards, to identify trends in environmental radiation, and to provide such information to the public. It summarizes these activities for calendar year 1983. No radioactivity attributable to NTS activities was detectable offsite by the monitoring networks. Using recorded wind data and Pasquill stability categories, atmospheric dispersion calculations based on reported radionuclide releases yield an estimated dose of 5 x 10 -5 man-rem to the population within 80 km of the Nevada Test Site during 1983. World-wide fallout of Kr-85, Sr-90, Cs-137, and Pu-239 detected by the monitoring networks would cause maximum exposure to an individual of less than 0.2 mrem per year. Plutonium and krypton in air were similar to 1982 levels while cesium and strontium in other samples were near the detection limits. An occasional net exposure to offsite residents has been detected by the TLD network. On investigation, the cause of such net exposures has been due to personal habits or occupational activities, not to NTS activities. 29 references, 35 figures, 30 tables

  4. REMOTE AREA RADIATION MONITORING (RARM) ALTERNATIVES ANALYSIS

    International Nuclear Information System (INIS)

    NELSON RL

    2008-01-01

    The Remote Area Radiation Monitoring (RARM) system will be used to provide real-time radiation monitoring information to the operations personnel during tank retrieval and transfer operations. The primary focus of the system is to detect potential anomalous (waste leaks) or transient radiological conditions. This system will provide mobile, real-time radiological monitoring, data logging, and status at pre-selected strategic points along the waste transfer route during tank retrieval operations. The system will provide early detection and response capabilities for the Retrieval and Closure Operations organization and Radiological Control personnel

  5. The regulations for delivery of subsidies to radiation monitoring

    International Nuclear Information System (INIS)

    1980-01-01

    This rule is established under the provisions of the law for the proper execution of budgets of subsidies and the enforcement ordinance for this law, and to carry out these provisions. This rule is applied to the grant of subsidies for the expenses of installing and operating radiation monitoring equipment in the surrounding areas of atomic power generating facilities. Basic terms are defined, such as atomic power generating facilities, redevelopment works for radiation monitoring facilities, preliminary survey works for radiation monitoring, radiation monitoring works, place of business and expected date of beginning operation, etc. The Director General of the Science and Technology Agency delivers subsidies to appropriate for all or a part of expenses required for the redevelopment works for radiation monitoring facilities, preliminary survey works for radiation monitoring and radiation monitoring works. Subsidies are given to those prefectures, where atomic power generating facilities are established or expected to be established, or the prefectures in their neighborhood, and to each place of business as a unit. The term of grant is stipulated for each of these places of business. The amount of subsidies for one place of business ranges from 224.4 million yen for the whole period to 20 million yen for each fiscal year according to the kinds of business. Prefectures which intend to request the grant of subsidies shall file to the Director General specified application attaching operation plans and the general explanation of atomic power generating facilities. The decision and the conditions of delivery, the reports on operation and business results, etc. are defined, respectively. (Okada, K.)

  6. BAKNET - Communication network for radiation monitoring devices

    International Nuclear Information System (INIS)

    Cohen, Y.; Wengrowicz, U.; Tirosh, D.; Barak, D.

    1997-01-01

    A system, based on a new concept of controlling and monitoring distributed radiation monitors, has been developed and approved at the NRCN. The system, named B AKNET Network , consists of a series of communication adapters connected to a main PC via an RS-485 communication network (see Fig. 1). The network's maximal length is 1200 meters and it enables connection of up to 128 adapters. The BAKNET adapters are designed to interface output signals of different types of stationary radiation monitors to a main PC. The BAKNET adapters' interface type includes: digital, analog, RS-232, and mixed output signals. This allows versatile interfacing of different stationary radiation monitors to the main computer. The connection to the main computer is via an RS-485 network, utilizing an identical communication protocol. The PC software, written in C ++ under MS-Windows, consists of two main programs. The first is the data collection program and the second is the Human Machine Interface (HMI). (authors)

  7. A suite of standards for radiation monitors and their revisions

    International Nuclear Information System (INIS)

    Noda, Kimio

    1991-01-01

    A suite of standards for radiation monitors applied in nuclear facilities in Japan was compiled mainly by Health Physicists in Power Reactor and Nuclear Fuel Development (PNC) and Japan Atomic Energy Research Institute (JAERI), and issued in 1971 as 'The Standard for Radiation Monitors'. PNC facilities such as Reprocessing Plant and Plutonium Fuel Fabrication Facility, as well as other nuclear industries have applied the standard, and contributed improvement of practical maintenability and availability of the radiation monitors. Meanwhile, the radiation monitors have remarkably progressed in its application and size of the monitors is growing. Furthermore, manufacturing techniques have significantly progressed especially in the field of system concepts and electronics elements. These progresses require revision of the standards. 'The Standard for Radiation Monitors' has been revised considering the problems in practical application and data processing capability. Considerations are given to keep compatibility of old and new modules. (author)

  8. Mobile environmental radiation monitoring station

    International Nuclear Information System (INIS)

    Assido, H.; Shemesh, Y.; Mazor, T.; Tal, N.; Barak, D.

    1997-01-01

    A mobile environmental radiation monitoring station has been developed and established for the Israeli Ministry of Environment. The radiation monitoring station is ready for immediate placing in any required location, or can be operated from a vehicle. The station collects data Tom the detector and transfers it via cellular communication network to a Computerized Control Center for data storage, processing, and display . The mobile station is fully controlled from the. Routinely, the mobile station responses to the data request accumulated since the last communication session. In case of fault or alarm condition in the mobile station, a local claim is activated and immediately initiates communication with the via cellular communication network. (authors)

  9. Workplace monitoring for radiation and contamination

    International Nuclear Information System (INIS)

    1995-01-01

    Ionizing radiations cannot be seen, felt or sensed by the human body in any way but excessive exposure to them may have adverse health effects. In order to avoid excessive exposure, appropriate and efficient radiation measuring instruments are needed. This Module explains the basic terminology associated with such measuring instruments and describes the principal types, their construction and typical applications in the workplace. It is important to ensure not only that monitoring is carried out where there is a potential radiation exposure but also that the monitoring instrument is appropriate to the task and that the user places correct interpretations on the results obtained. The Manual will be of most benefit if it forms part of more comprehensive training or is supplemented by the advice of a qualified expert in radiation protection. Some of the instrument tests and calibrations described in this Module require the services of a qualified expert

  10. Darwin: Dose monitoring system applicable to various radiations with wide energy ranges

    International Nuclear Information System (INIS)

    Sato, T.; Satoh, D.; Endo, A.; Yamaguchi, Y.

    2007-01-01

    A new radiation dose monitor, designated as DARWIN (Dose monitoring system Applicable to various Radiations with Wide energy ranges), has been developed for real-time monitoring of doses in workspaces and surrounding environments of high-energy accelerator facilities. DARWIN is composed of a Phoswitch-type scintillation detector, which consists of liquid organic scintillator BC501A coupled with ZnS(Ag) scintillation sheets doped with 6 Li, and a data acquisition system based on a Digital-Storage-Oscilloscope. DARWIN has the following features: (1) capable of monitoring doses from neutrons, photons and muons with energies from thermal energy to 1 GeV, 150 keV to 100 MeV and 1 MeV to 100 GeV, respectively, (2) highly sensitive with precision and (3) easy to operate with a simple graphical user-interface. The performance of DARWIN was examined experimentally in several radiation fields. The results of the experiments indicated the accuracy and wide response range of DARWIN for measuring dose rates from neutrons, photons and muons with wide energies. It was also found from the experiments that DARWIN enables us to monitor small fluctuations of neutron dose rates near the background level because of its high sensitivity. With these properties, DARWIN will be able to play a very important role for improving radiation safety in high-energy accelerator facilities. (authors)

  11. The regulations for delivery of subsidies to radiation monitoring

    International Nuclear Information System (INIS)

    1985-01-01

    The regulations provide for subsidies for equipment and operation of a radiation monitoring facility around a nuclear power generating facility. Subsidies are provided to the prefectures concerned for equipment, etc. required in radiation monitoring, pre-service radiation monitoring and in-service radiation monitoring conducted by a prefecture. The contents are as follows: terms of subsidy allocations, the sum of subsidy allocations, applications for subsidies, decisions on the allocation of subsidies, withdrawal of applications, conditions of the allocations, a report on the work proceedings, a report on the results, confirmation on the sum of the subsidies, withdrawal of the decision for subsidies, limitations for disposal of the properties, payment of the subsidy, accounting of the subsidy operations, and a record on the subsidy. (Kubozono, M.)

  12. The regulations for delivery of subsidies to radiation monitoring

    International Nuclear Information System (INIS)

    1984-01-01

    The regulations provide for subsidies for equipment and operation of a radiation monitoring facility around a nuclear power generating facility. Subsidies are provided to the prefectures concerned for equipment, etc. required in radiation monitoring, pre-service radiation monitoring and in-service radiation monitoring conducted by a prefecture. The contents are as follows: terms of subsidy allocations, the sum of subsidy allocations, applications for subsidies, decisions on the allocation of subsidies, withdrawal of applications, conditions of the allocations, a report on the work proceedings, a report on the results, confirmation on the sum of the subsidies, withdrawal of the decision for subsidies, limitations for disposal of the properties, payment of the subsidy, accounting of the subsidy operations, and a record on the subsidy. (Mori, K.)

  13. Radiation Monitoring System in Advanced Spent Fuel Conditioning Process Facility

    Energy Technology Data Exchange (ETDEWEB)

    You, Gil Sung; Kook, D. H.; Choung, W. M.; Ku, J. H.; Cho, I. J.; You, G. S.; Kwon, K. C.; Lee, W. K.; Lee, E. P

    2006-09-15

    The Advanced spent fuel Conditioning Process is under development for effective management of spent fuel by converting UO{sub 2} into U-metal. For demonstration of this process, {alpha}-{gamma} type new hot cell was built in the IMEF basement . To secure against radiation hazard, this facility needs radiation monitoring system which will observe the entire operating area before the hot cell and service area at back of it. This system consists of 7 parts; Area Monitor for {gamma}-ray, Room Air Monitor for particulate and iodine in both area, Hot cell Monitor for hot cell inside high radiation and rear door interlock, Duct Monitor for particulate of outlet ventilation, Iodine Monitor for iodine of outlet duct, CCTV for watching workers and material movement, Server for management of whole monitoring system. After installation and test of this, radiation monitoring system will be expected to assist the successful ACP demonstration.

  14. Radiation Monitoring System in Advanced Spent Fuel Conditioning Process Facility

    International Nuclear Information System (INIS)

    You, Gil Sung; Kook, D. H.; Choung, W. M.; Ku, J. H.; Cho, I. J.; You, G. S.; Kwon, K. C.; Lee, W. K.; Lee, E. P.

    2006-09-01

    The Advanced spent fuel Conditioning Process is under development for effective management of spent fuel by converting UO 2 into U-metal. For demonstration of this process, α-γ type new hot cell was built in the IMEF basement . To secure against radiation hazard, this facility needs radiation monitoring system which will observe the entire operating area before the hot cell and service area at back of it. This system consists of 7 parts; Area Monitor for γ-ray, Room Air Monitor for particulate and iodine in both area, Hot cell Monitor for hot cell inside high radiation and rear door interlock, Duct Monitor for particulate of outlet ventilation, Iodine Monitor for iodine of outlet duct, CCTV for watching workers and material movement, Server for management of whole monitoring system. After installation and test of this, radiation monitoring system will be expected to assist the successful ACP demonstration

  15. Environmental radiation monitoring system with GPS (global positioning system)

    International Nuclear Information System (INIS)

    Komoto, Itsuro

    2000-01-01

    This system combines a radiation monitoring car with GPS and a data processor (personal computer). It distributes the position information acquired through GPS to the data such as measured environmental radiation dose rate and energy spectrum. It also displays and edits the data for each measuring position on a map. Transmitting the data to the power station through mobile phone enables plan managers to easily monitor the environmental radiation dose rate nearby and proper emergency monitoring. (author)

  16. Searching for O-X-B mode-conversion window with monitoring of stray microwave radiation in LHD

    International Nuclear Information System (INIS)

    Igami, H.; Kubo, S.; Laqua, H. P.; Nagasaki, K.; Inagaki, S.; Notake, T.; Shimozuma, T.; Yoshimura, Y.; Mutoh, T.; LHD Experimental Group

    2006-01-01

    In the Large Helical Device, the stray microwave radiation is monitored by using so-called sniffer probes during electron cyclotron heating. In monitoring the stray radiation, we changed the microwave beam injection angle and search the O-X-B mode-conversion window to excite electron Bernstein waves (EBWs). When the microwave beam is injected toward the vicinity of the predicted O-X-B mode-conversion window, the electron temperature rises in the central part of overdense plasmas. In that case, the stray radiation level near the injection antenna becomes low. These results indicate that monitoring the stray radiation near the injection antenna is helpful in confirming the effectiveness of excitation of EBWs simply without precise analysis

  17. The communications in early warning network for radiation monitoring

    International Nuclear Information System (INIS)

    Oyoun, M.B.; Al-Hussin, Mohamad; Fares, Adnan; Al-Oulabi, Yasser; Othman, Ibrahim

    1992-07-01

    The objectives of early warning network are: The determination of gamma radiation (background) levels in air which depend on location and time, evaluation of any situation resulting from radiation or nuclear accident out of boarder, and after that reporting the emergency situation to relevant authorities on the national and international levels. Monitoring stations were installed using Gm tubes to cover boarder lines from south to north and east to west as follows: Damascus, Darra, Latakia, Tartous, Aleppo, Kamishly, Ragaa, and Qunitra. The following modes of communication: Telephone line, leased line, direct connection, and Syrian data network were used in the Syrian early network. This project was carried out in cooperation with IAEA under project no. RER/9/003. (author). 22 figs., 1 tab

  18. Workplace monitoring for radiation and contamination

    International Nuclear Information System (INIS)

    2004-01-01

    Ionizing radiations cannot be seen, felt or sensed by the human body in any way but excessive exposure to them may have adverse health effects. Radiation measuring instruments are needed in order to detect the presence of such radiations and avoid excessive exposure. The use of appropriate and efficient instruments enables exposures to be controlled and the doses received to be kept as low as reasonably achievable. This Manual explains the basic terminology associated with such measuring instruments and describes the principal types, their construction and typical applications in the workplace. It is important to ensure not only that monitoring is carried out where there is a potential radiation exposure but also that the monitoring instrument is appropriate to the task and that the user places correct interpretations on the results obtained. The Manual will be of most benefit if it forms part of more comprehensive training or is supplemented by the advice of a qualified expert in radiation protection. Some of the instrument tests and calibrations described in this Manual require the services of a qualified expert

  19. Health and radiation: Surveillance and monitoring

    International Nuclear Information System (INIS)

    Reitan, J.B.; Langmark, F.

    1988-01-01

    Assuming a zero risk of low-dose radiation would allow society to save a lot of resources currently used in radiation protection. If this assumption should turn out to be wrong, however, the society would face a serious cancer problem within 20-40 years. Thus, the present resources allocated to radiation protection seem justified from an ethical and moral point of view. Such radiation protection should also include monitoring of naturally enhanced radiation and possibilities of contamination, and ecological changes from energy production, waste deposition and fertilizing. The weaker parts of establishing the dose/effect relationship are radiation biology and radiation medicine. Therefore, continued research in these disciplines should be encouraged

  20. Radiation Monitoring - A Key Element in a Nuclear Power Program

    International Nuclear Information System (INIS)

    Hussein, A.S.; El-dally, T.A.

    2008-01-01

    For a nuclear power plant, radiation is especially of great concern to the public and the environment. Therefore, a radiation monitoring program is becoming a critical importance. This program covers all phases of the nuclear plant including preoperational, normal operation, accident and decommissioning. The fundamental objective of radiation monitoring program is to ensure that the health and safety of public inside and around the plant and to confirm the radiation doses are below the dose limits for workers and the public. This paper summarizes the environmental radiation monitoring program for a nuclear power plant

  1. Field test of a post-closure radiation monitor

    International Nuclear Information System (INIS)

    Reed, S.; Christy, C.E.; Heath, R.E.

    1995-01-01

    The DOE is conducting remedial actions at many sites contaminated with radioactive materials. After closure of these sites, long-term subsurface monitoring is typically required by law. This monitoring is generally labor intensive and expensive using conventional sampling and analysis techniques. The U.S. Department of Energy's Morgantown Energy Technology Center (METC) has contracted with Babcock and Wilcox to develop a Long-Term Post-Closure Radiation Monitoring System (LPRMS) to reduce these monitoring costs. A prototype LPRMS probe was built, and B ampersand W and FERMCO field tested this monitoring probe at the Fernald Environmental Management Project in the fall of 1994 with funding from the DOE's Office of Technology Development (EM-50) through METC. The system was used to measure soil and water with known uranium contamination levels, both in drums and in situ at depths up to 3 meters. For comparison purposes, measurements were also performed using a more conventional survey probe with a sodium iodide scintillator directly butt-coupled to detection electronics. This paper presents a description and the results of the field tests. The results were used to characterize the lower detection limits, precision and bias of the system, which allowed the DOE to judge the monitoring system's ability to meet its long-term post-closure radiation monitoring needs. Based on the test results, the monitoring system has been redesigned for fabrication and testing in a potential Phase III of this program. If the DOE feels that this system can meet its needs and chooses to continue into Phase III of this program, this redesigned full scale prototype system will be built and tested for a period of approximately a year. Such a system can be used at a variety of radioactively contaminated sites

  2. Development of a portable monitor for detecting gamma radiation and X-rays

    International Nuclear Information System (INIS)

    Silva Neto, Paulo J. da; Lira, Carlos A.B. de O.; Oliveira, Arno H. de

    2011-01-01

    There are several ways to prevent individuals from receiving excessive or unnecessary doses of radiation, and area monitoring contributes to the radiation protection in the assessment whether these means are really efficient. The area monitoring is used to give an indication of radiation levels in certain locations. Using this method, one can estimate the dose received by staff occupying a particular area for a certain period of time. Hence, the purpose of this work was the construction of a portable monitor, consisting of an ionization chamber, with a volume of approximately 517 cc and built from tissue-equivalent material, and of its associated electronics. Radiation measurements of gamma and X-rays beams were then possible. The results showed a linear response of the monitor for different dose rates. The stability test of the response also showed a good reproducibility within ± 1%. A low energy dependence for energies between 16 - 200keV was observed, and complied well with the IEC 60846 standard. However, for the energy range 200 - 1250keV, the discrepancies to the IEC standard are considerable, so that the interposition of filters is necessary and may improve the energy response curve to within acceptable limits. (author)

  3. Radiation area monitor device and method

    Science.gov (United States)

    Vencelj, Matjaz; Stowe, Ashley C.; Petrovic, Toni; Morrell, Jonathan S.; Kosicek, Andrej

    2018-01-30

    A radiation area monitor device/method, utilizing: a radiation sensor; a rotating radiation shield disposed about the radiation sensor, wherein the rotating radiation shield defines one or more ports that are transparent to radiation; and a processor operable for analyzing and storing a radiation fingerprint acquired by the radiation sensor as the rotating radiation shield is rotated about the radiation sensor. Optionally, the radiation sensor includes a gamma and/or neutron radiation sensor. The device/method selectively operates in: a first supervised mode during which a baseline radiation fingerprint is acquired by the radiation sensor as the rotating radiation shield is rotated about the radiation sensor; and a second unsupervised mode during which a subsequent radiation fingerprint is acquired by the radiation sensor as the rotating radiation shield is rotated about the radiation sensor, wherein the subsequent radiation fingerprint is compared to the baseline radiation fingerprint and, if a predetermined difference threshold is exceeded, an alert is issued.

  4. RadNet (Environmental Radiation Ambient Monitoring System)

    Data.gov (United States)

    U.S. Environmental Protection Agency — RadNet, formerly Environmental Radiation Ambient Monitoring System (ERAMS), is a national network of monitoring stations that regularly collect air, precipitation,...

  5. Low-level radiation

    International Nuclear Information System (INIS)

    Myers, D.K.

    1982-05-01

    It is known that the normal incidence of cancer in human populations is increased by exposure to moderately high doses of ionizing radiation. At background radiation levels or at radiation levels which are 100 times greater, the potential health risks are considered to be directly proportional to the total accumulated dose of radiation. Some of the uncertainties associated with this assumption and with the accepted risk estimates have been critically reviewed in this document. The general scientific consensus at present suggests that the accepted risk estimates may exaggerate the actual risk of low levels of sparsely ionizing radiations (beta-, gamma- or X-rays) somewhat but are unlikely to overestimate the actual risks of densely ionizing radiations (fast neutrons, alpha-particles). At the maximum permissible levels of exposure for radiation workers in nuclear power stations, the potential health hazards in terms of life expectancy would be comparable to those encountered in transportation and public utilities or in the construction industry. At the average radiation exposures received by these workers in practice, the potential health hazards are similar to those associated with safe categories of industries. Uranium mining remains a relativly hazardous occupation. In terms of absolute numbers, the genetic hazards, which are less well established, are thought to be smaller than the carcinogenic hazards of radiation when only the first generation is considered but to be of the same order of magnitude as the carcinogenic hazards when the total number of induced genetic disorders is summed over all generations

  6. Standardization of radioactive gaseous waste radiation monitoring equipment from the International Electrotechnical Commission

    International Nuclear Information System (INIS)

    Fitoussi, L.

    1983-01-01

    After having introduced the works performed by the International Electrotechnical Commission, the authors report on the results of the studies carried out to achieve the standardization of the radiation monitoring equipment concerning the control of the gaseous waste from nuclear installations. The authors present the most interesting aspects of the regulations and recommendations, which include not only a description of the minimum permissible levels of sensitivity for the monitors, but also a description of the set of assays to be established in order to verify the level of performance of the monitors

  7. Regulatory requirements and quality assurance of radiation monitoring instruments

    International Nuclear Information System (INIS)

    Narasimharao, K.L.; Sharma, Ranjit

    2005-01-01

    The successful utilisation of radiation sources in the fields of medicine and industry requires the accurate measurement of activity, exposure rate and dose. Many varieties of instruments are in use for measurement of these parameters and new ones are being developed. The criteria for the design of the radiation monitoring instrument include the type and intensity of the radiation, purpose of measurement and ruggedness of the instrument. Quality and reliability of radiation monitoring instruments ensure that individuals are adequately protected. Accuracy, response time and ruggedness are required to be as per the approved/ prescribed guidelines. Regulatory authorities outline the design and performance criteria for radiation monitoring instruments and prescribe the recommendations of international agencies such as IAEA, ICRU and ISO for radiological measurement assurance programme. National Standards Laboratories all over the world prescribe procedures for calibration of various radiation monitoring instruments. The instruments should be calibrated as per these guidelines and should be traceable to national standards. The calibration traceable to national/ international standards and documentation as well as limits stipulated by the competent authority ensures the expected performance of the instrument. (author)

  8. 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.

  9. The Juno Radiation Monitoring (RM) Investigation

    DEFF Research Database (Denmark)

    Becker, H. N.; Alexander, J. W.; Adriani, A.

    2017-01-01

    The Radiation Monitoring Investigation of the Juno Mission will actively retrieve and analyze the noise signatures from penetrating radiation in the images of Juno’s star cameras and science instruments at Jupiter. The investigation’s objective is to profile Jupiter’s > 10-MeV electron environmen...

  10. NRC TLD Direct Radiation Monitoring Network. Volume 15, No. 4: Quarterly progress report, October--December 1995

    International Nuclear Information System (INIS)

    Struckmeyer, R.

    1996-03-01

    This report presents the results of the NRC Direct Radiation Monitoring Network for the fourth quarter of 1995. It provides the ambient radiation levels measured in the vicinity of 75 sites throughout the United States. In addition, it describes the equipment used, monitoring station selection criteria, characterization of the dosimeter response, calibration procedures, statistical methods, intercomparison, and quality assurance program

  11. NRC TLD Direct Radiation Monitoring Network. Volume 15, No. 4: Quarterly progress report, October--December 1995

    Energy Technology Data Exchange (ETDEWEB)

    Struckmeyer, R.

    1996-03-01

    This report presents the results of the NRC Direct Radiation Monitoring Network for the fourth quarter of 1995. It provides the ambient radiation levels measured in the vicinity of 75 sites throughout the United States. In addition, it describes the equipment used, monitoring station selection criteria, characterization of the dosimeter response, calibration procedures, statistical methods, intercomparison, and quality assurance program.

  12. 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)

  13. The problem of creation of radiation monitoring system

    International Nuclear Information System (INIS)

    Pilipchak, S.I.

    1990-01-01

    The review of problem of radiation monitoring system (RMS) in the territory of the country is presented. Unsolved problems are discussed which are divided into three groups: the organization of structures in RMS; implementation of automated RMS; the solution of scientific problems of global monitoring of radiation situation. 12 refs.; 1 tab

  14. Distributed Radiation Monitoring System for Linear Accelerators based on CAN Bus

    CERN Document Server

    Kozak, T; Napieralski, A

    2010-01-01

    Abstract—Gamma and neutron radiation is produced during the normal operation of linear accelerators like Free-Electron Laser in Hamburg (FLASH) or X-ray Free Electron Laser (X-FEL). Gamma radiation cause general degeneration of electronics devices and neutron fluence can be a reason of soft error in memories and microcontrollers. X-FEL accelerator will be built only in one tunnel, therefore most of electronic control systems will be placed in radiation environment. Exposing control systems to radiation may lead to many errors and unexpected failure of the whole accelerator system. Thus, the radiation monitoring system able to monitor radiation doses produced near controlling systems is crucial. Knowledge of produced radiation doses allows to detect errors caused by radiation, make plans of essential exchange of control systems and prevent accelerator from serious damages. The paper presents the project of radiation monitoring system able to monitor radiation environment in real time.

  15. Calibration method of radiation monitoring system at TQNPC

    International Nuclear Information System (INIS)

    Liu Zhengshan; Zhang Qingli; Liu Jinjin; Miao Yuxing; Geng Lixin; Zhuang Yun; Dong Jianfeng; He Change

    2009-04-01

    The calibration methods and calibration device for standard monitor of radioactive particulate, iodine, noble gas and so on are not yet set up at home. On consideration of the present situation of the radiation monitoring system at the Third Qinshan Nuclear Power Co. Ltd., we have studied the calibration method of these radiation monitoring instruments used for measuring the waste liquid, particulate, iodine and noble gas produced during the operation of nuclear reactor. Through the check against these instruments during the No. 202 and No. 103 overhaul, we got initially the method of the calibration and obtained the transfer coefficient of calibration when secondary solid sources are used for calibration. Through the testing and calibration, the credibility of the radiation monitoring system is enhanced. And at the same time, the problems existing in the calibration are discussed. (authors)

  16. Monitor inspection device

    International Nuclear Information System (INIS)

    Ueshima, Yoshinobu.

    1995-01-01

    The device of the present invention reliably conducts monitoring by radiation monitors in a nuclear power plant thereby contributing to save the number of radiation operators and reduction of radiation exposure. Namely, radiation monitors continuously measure a plurality of γ-ray levels. A branched simultaneously counting circuit receives these signals. The output of the branched simultaneously counting circuit is inputted to a differentiation means. The differentiation means calculates a variation coefficient for each of the radiation monitoring values, namely, equivalent dose rates, and records and monitors change with time of the equivalent dose rates. With such procedures, the results of the monitoring of γ-ray levels can be judged objectively corresponding to the increase of the equivalent dose rates. As a result, the number of radiation operators can be saves and radiation exposure of the radiation operators can be reduced. (I.S.)

  17. Radiation monitoring and measuring instrument developed by Turkish Atomic Energy Authority

    International Nuclear Information System (INIS)

    Kuecuekarslan, N.; Gueven, A.

    2001-01-01

    Turkish Atomic Energy Authority (TAEA), Cekmece Nuclear Research and Training Center, Nuclear Electronics Department is working on research, development and production of radiation monitoring and measuring instruments in the aims of TAEA to serve our Country. Advanced micro controller technology is used to cover problems of radiation measurement. Control by micro controller enables reliable, stable measurement and display of low level dose rate fields. It makes possible the simultaneous measurement of both dose and dose rate values

  18. Radiation monitoring system for astronauts

    International Nuclear Information System (INIS)

    Thomson, I.; MacKay, G.; Ng, A.; Tomi, L.

    1996-01-01

    Astronauts in space are constantly under the bombardment of radiation particles from trapped electrons, and trapped proton. In addition, cosmic rays, while penetrating the spacecraft shell, generate secondary radiation of neutrons. As astronauts' stay in space is getting longer, the need for a real-time radiation monitoring device has become critical. Thermoluminescent dosemeter (TLD), used onboard both the MIR and the Space Transportation System (STS), cannot provide real-time dose reading. This paper describes a real-time direct read-out device, currently under development, which can measure skin, eye, and Blood Forming Organ (BFO) doses separately. (author)

  19. Sequential probability ratio controllers for safeguards radiation monitors

    International Nuclear Information System (INIS)

    Fehlau, P.E.; Coop, K.L.; Nixon, K.V.

    1984-01-01

    Sequential hypothesis tests applied to nuclear safeguards accounting methods make the methods more sensitive to detecting diversion. The sequential tests also improve transient signal detection in safeguards radiation monitors. This paper describes three microprocessor control units with sequential probability-ratio tests for detecting transient increases in radiation intensity. The control units are designed for three specific applications: low-intensity monitoring with Poisson probability ratios, higher intensity gamma-ray monitoring where fixed counting intervals are shortened by sequential testing, and monitoring moving traffic where the sequential technique responds to variable-duration signals. The fixed-interval controller shortens a customary 50-s monitoring time to an average of 18 s, making the monitoring delay less bothersome. The controller for monitoring moving vehicles benefits from the sequential technique by maintaining more than half its sensitivity when the normal passage speed doubles

  20. Environmental gamma radiation levels around various DAE research centres

    International Nuclear Information System (INIS)

    Takale, R.A.; Swarnakar, M.; Shetty, P.G.; Sahu, S.K.; Pandit, G.G.

    2014-01-01

    This paper presents the gamma radiation levels of four research centres viz. Bhabha Atomic Research Centre (BARC), Trombay; Indira Gandhi Centre for Atomic Research (IGCAR), Kalpakkam; Variable Energy Cyclotron Centre (VECC), Kolkata; Raja Ramanna Centre for Advanced Technology (RRCAT), Indore; and an industry Board of Radiation and Isotope Technology (BRIT), Vashi. BARC is India's premier nuclear research facility and is a multi-disciplinary research centre with extensive infrastructure for advanced research and development (R and D). IGCAR, Kalpakkam is engaged in scientific research and advanced engineering programme towards the development of Fast Breeder Reactor technology. VECC Kolkata is dedicated to carry out frontier R and D in the fields of Accelerator Science and Technology, Nuclear Science (Theoretical and Experimental), and Material Science etc. RRCAT, Indore has rapidly grown into a premier institute for R and D in lasers, accelerators and their applications. BRIT, Vashi unit is involved in production, development, and supply of radioisotope based products and provision of isotope applications, radiation processing, radio analytical services etc. With an objective to keep a watch on the prevailing environmental background gamma radiation level around all the DAE installations, routine monitoring programme are being carried out using the Thermo Luminescent Dosimeters (TLDs). TLDs provide the simple, inexpensive and precise measurement of small, integrated, external gamma radiation dose rate. The general practice of this programme is to observe the outdoor gamma radiation levels. This paper summarizes the methodology and gamma radiation levels of four research centres viz. BARC, IGCAR, VECC, RRCAT and an industry BRIT, Vashi

  1. Update on the independent radiation monitor (IRM)

    International Nuclear Information System (INIS)

    Kroening, P.M.; Mucha, R.

    1976-01-01

    The new independent radiation monitor (IRM), unlike its predecessor, is a reliable and sensitive safety device for any radiation therapy room. It shows unequivocally that the beam is on, and it is inexpensive and simple to construct

  2. Programmes and Systems for Source and Environmental Radiation Monitoring

    International Nuclear Information System (INIS)

    2010-01-01

    The discharge of radionuclides to the atmosphere and aquatic environments is a legitimate practice in the nuclear and other industries, hospitals and research. Where appropriate, monitoring of the discharges and of relevant environmental media is an essential regulatory requirement in order to ensure appropriate radiation protection of the public. Such monitoring provides information on the actual amounts of radioactive material discharged and the radionuclide concentrations in the environment, and is needed to demonstrate compliance with authorized limits, to assess the radiation exposure of members of the public and to provide data to aid in the optimization of radiation protection. Uncontrolled releases of radionuclides to the atmosphere and aquatic environments may occur as a result of a nuclear or radiological accident. Again, monitoring at the source of the release and of the environment is necessary. In this case, monitoring is used both to assess the radiation exposure of members of the public and to determine the actions necessary for public protection, including longer term countermeasures. Source and environmental monitoring associated with the release of radionuclides to the environment is the subject of a number of IAEA Safety Standards, particularly IAEA Safety Standard RS-G-1.8 (Environmental and Source Monitoring for Purposes of Radiation Protection). This publication is intended to complement this Safety Guide and, by so doing, replaces Safety Series No. 41 (Objectives and Design of Environmental Monitoring Programmes for Radioactive Contaminants) and Safety Series No. 46 (Monitoring of Airborne and Liquid Radioactive Releases from Nuclear Facilities to the Environment). Like Safety Standard RS-G-1.8, this Safety Report deals with monitoring at the source and in the environment associated with authorized releases of radionuclides to the environment. It also deals with the general issues of emergency monitoring during and in the aftermath of an

  3. A knowledge on environmental radiation monitoring about the influence from Fukushima Dai-ichi Nuclear Power accident

    International Nuclear Information System (INIS)

    Yoshioka, Mitsuo; Terakawa, Kazuyoshi; Kasai, Toshihiro

    2012-01-01

    A large amount of radioactive substances were released in the atmosphere and contaminated a large area across Japan due to the accident at Fukushima Daiichi Nuclear Power Plant of Tokyo Electric Power Company triggered by Great East Japan Earthquake and tsunami on May 11th 2011. At Fukui University of Technology, monitoring of air radiation (gamma ray) and radiation in environmental samples in Fukui prefecture and some areas of Fukushima prefecture were conducted in order to study the influence of radiation and radioactivity on the citizens as well as the perception of this study results by the citizens. Also, in order to study the dependency of the radiation influence on the distance from the accident location, radiation monitoring of fallouts (air-borne dust, rainwater, sediment mud, and so on) was conducted. In this article, the knowledge obtained on environmental radiation monitoring was summarized and reported. Especially, slightly modified dose-level evaluation for internal exposure was reported. (S.K.)

  4. Radiation protection and environmental monitoring in the area of the Asse mine. Annual report 1994

    International Nuclear Information System (INIS)

    Meyer, H.; Mueller-Lyda, I.

    1995-01-01

    The personnel at the site has been monitored in accordance with the provisions of the Radiation Protection Ordinance. In addition, ambient dose, ambient dose rate, and radioactivity levels of the air in the mine have been measured pursuant to the health physics provisions of the Radiation Protection Ordinance. None of the measured results indicated any dose received by the persons, or ambient radioactivity levels, exceeding the maximum permissible values determined for occupational exposure. Continuous monitoring of the mine off-gas has shown a minor accumulation of the nuclides. H-3, C-14, Pb-210 and of the short-lived daughter products of Rn-222 and Rn-220. The average annual emission values serving as input data, the concentration levels computed for the environment of the mine for some part have been below the levels of the naturally occurring concentrations of these nuclides. The emission-induced radiation dose measured at the least favourable place in the plant's vicinity has been far below the maximum permissible dose defined in the Radiation Protection Ordinance. All activities carried out in the Asse salt mine for the purpose of research work and storage of radioactive waste in the period under review have been contributing only a negligible amount to the radiation exposure of the population or personnel, as compared to the natural or other man-made radioactivity levels in that area. (orig.) [de

  5. Radiation protection and environmental monitoring in the area of the Asse mine. Annual report 1993

    International Nuclear Information System (INIS)

    Meyer, H.; Mueller-Lyda, I.

    1994-01-01

    The personnel at the site has been monitored in accordance with the provisions of the Radiation Protection Ordinance. In addition, ambient dose, ambient dose rate, and radioactivity levels of the air in the mine have been measured pursuant to the health physics provisions of the Radiation Protection Ordinance. None of the measured results indicated any dose received by the persons, or ambient radioactivity levels, exceeding the maximum permissible values determined for occupational exposure. Continuous monitoring of the mine off-gas has shown a minor accumulation of the nuclides. H-3, C-14, Pb-210 and of the short-lived daughter products of Rn-222 and Rn-220. The average annual emission values serving as input data, the concentration levels computed for the environment of the mine for some part have been below the levels of the naturally occurring concentrations of these nuclides. The emission-induced radiation dose measured at the least favourable place in the plant's vicinity has been far below the maximum permissible dose defined in the Radiation Protection Ordinance. All activities carried out in the Asse salt mine for the purpose of research work and storage of radioactive waste in the period under review have been contributing only a negligible amount to the radiation exposure of the population or personnel, as compared to the natural or other man-made radioactivity levels in that area. (orig.) [de

  6. Environmental radiation monitoring during visits of nuclear powered warships to Australian ports: requirements, arrangements and procedures

    International Nuclear Information System (INIS)

    1988-05-01

    The Commonwealth Government has determined conditions to be met when nuclear powered warships visit Australian ports. These conditions include a requirement that appropriate State/Territory and Commonwealth authorities provide a radiation monitoring program to determine whether any radioactivity has been discharged or accidently released from a nuclear powered warship in port; to determine actual or potential levels of any consequent exposure to radiation of members of the public; and to provide this information within a timescale that allows remedial action to be taken. Part 1 of this document sets out the requirements of a radiation monitoring program capable of meeting these objectives. The fundamental arrangements and procedures for implementing the requirements are presented at Part 2 and provide a basis for the development of fully detailed, port specific, radiation monitoring programs

  7. The Role of Automatic Radiation Monitoring in Control of Illicit Trafficking of Radioactive Materials in Slovenia

    International Nuclear Information System (INIS)

    Mitic, D.

    2003-01-01

    Automatic radiation monitoring in Slovenia comprises monitoring of external gamma radiation, aerosol radioactivity, radon progeny concentration, and radioactive deposition measurements. The officer on duty has an important part in assuring proper and undisturbed functioning of our automatic radiation monitoring. He is the one who gets the first alert message on radiation levels when exceeded pre-set values in the territory of Slovenia. Together with continuous control over the functioning of automatic radiation monitoring, the officer on duty has been also assigned for receiving messages from users, who carry the 'Radiation pager' (it is a trade mark for Sensor Technology Engineering, inc. from USA). All valuable experiences of the officer on duty who has been accepting reports from customs officers, police officers, from Slovenian radiation and nuclear safety inspectors, are described in this article. The officer on duty with his new role contributes to prevention of the illicit trafficking and inadvertent movement of radioactive materials over the territory of Slovenia. In the last year there where many different causes of emergency calls: from many cases of patient after radioisotopes medical treatment to serious rejected shipment with exceeded radiation. This is only a beginning of responsible task how to introduce and assure the control of the inadvertent movement of radioactive materials in Slovenia. (author)

  8. Ultra Secure High Reliability Wireless Radiation Monitor

    International Nuclear Information System (INIS)

    Cordaro, J.; Shull, D.; Farrar, M.; Reeves, G.

    2011-01-01

    Radiation monitoring in nuclear facilities is essential to safe operation of the equipment as well as protecting personnel. In specific, typical air monitoring of radioactive gases or particulate involves complex systems of valves, pumps, piping and electronics. The challenge is to measure a representative sample in areas that are radioactively contaminated. Running cables and piping to these locations is very expensive due to the containment requirements. Penetration into and out of an airborne or containment area is complex and costly. The process rooms are built with thick rebar-enforced concrete walls with glove box containment chambers inside. Figure 1 shows high temperature radiation resistance cabling entering the top of a typical glove box. In some case, the entire processing area must be contained in a 'hot cell' where the only access into the chamber is via manipulators. An example is shown in Figure 2. A short range wireless network provides an ideal communication link for transmitting the data from the radiation sensor to a 'clean area', or area absent of any radiation fields or radioactive contamination. Radiation monitoring systems that protect personnel and equipment must meet stringent codes and standards due to the consequences of failure. At first glance a wired system would seem more desirable. Concerns with wireless communication include latency, jamming, spoofing, man in the middle attacks, and hacking. The Department of Energy's Savannah River National Laboratory (SRNL) has developed a prototype wireless radiation air monitoring system that address many of the concerns with wireless and allows quick deployment in radiation and contamination areas. It is stand alone and only requires a standard 120 VAC, 60 Hz power source. It is designed to be mounted or portable. The wireless link uses a National Security Agency (NSA) Suite B compliant wireless network from Fortress Technologies that is considered robust enough to be used for classified data

  9. ULTRA SECURE HIGH RELIABILITY WIRELESS RADIATION MONITOR

    Energy Technology Data Exchange (ETDEWEB)

    Cordaro, J.; Shull, D.; Farrar, M.; Reeves, G.

    2011-08-03

    Radiation monitoring in nuclear facilities is essential to safe operation of the equipment as well as protecting personnel. In specific, typical air monitoring of radioactive gases or particulate involves complex systems of valves, pumps, piping and electronics. The challenge is to measure a representative sample in areas that are radioactively contaminated. Running cables and piping to these locations is very expensive due to the containment requirements. Penetration into and out of an airborne or containment area is complex and costly. The process rooms are built with thick rebar-enforced concrete walls with glove box containment chambers inside. Figure 1 shows high temperature radiation resistance cabling entering the top of a typical glove box. In some case, the entire processing area must be contained in a 'hot cell' where the only access into the chamber is via manipulators. An example is shown in Figure 2. A short range wireless network provides an ideal communication link for transmitting the data from the radiation sensor to a 'clean area', or area absent of any radiation fields or radioactive contamination. Radiation monitoring systems that protect personnel and equipment must meet stringent codes and standards due to the consequences of failure. At first glance a wired system would seem more desirable. Concerns with wireless communication include latency, jamming, spoofing, man in the middle attacks, and hacking. The Department of Energy's Savannah River National Laboratory (SRNL) has developed a prototype wireless radiation air monitoring system that address many of the concerns with wireless and allows quick deployment in radiation and contamination areas. It is stand alone and only requires a standard 120 VAC, 60 Hz power source. It is designed to be mounted or portable. The wireless link uses a National Security Agency (NSA) Suite B compliant wireless network from Fortress Technologies that is considered robust enough to be

  10. Nuclear energy - Radioprotection - Procedure for radiation protection monitoring in nuclear installations for external exposure to weakly penetrating radiation, especially to beta radiation

    International Nuclear Information System (INIS)

    2002-01-01

    This International Standard specifies a procedure for radiation protection monitoring in nuclear installations for external exposure to weakly penetrating radiation, especially to beta radiation and describes the procedure in radiation protection monitoring for external exposure to weakly penetrating radiation in nuclear installations. This radiation comprises β - radiation, β + radiation and conversion electron radiation as well as photon radiation with energies below 15 keV. This International Standard describes the procedure in radiation protection planning and monitoring as well as the measurement and analysis to be applied. It applies to regular nuclear power plant operation including maintenance, waste handling and decommissioning. The recommendations of this International Standard may also be transferred to other nuclear fields including reprocessing, if the area-specific issues are considered. This International Standard may also be applied to radiation protection at accelerator facilities and in nuclear medicine, biology and research facilities

  11. Intercomparisons in the radiation monitoring network of the Czech Republic

    Energy Technology Data Exchange (ETDEWEB)

    Tuckova, S; Malatova, I [National Radiation Protection Inst., Prague (Czech Republic); Drabova, D [State Office for Nuclear Safety, Prague (Czech Republic)

    1996-12-31

    In Czech Republic, altogether 11 laboratories, equipped by semiconductor gamma spectrometry supply regularly to the Centre of Radiation Monitoring Network the measured data about the radionuclide activity concentration in different environmental samples, participating thus in monitoring of radiation situation in the country. The Center of Radiation Monitoring Network of Czech Republic periodically organizes through its reference laboratories interlaboratory comparison tests ensuring thus quality of the measurements within the radiation monitoring network. A ring intercomparison test was organized in 1994. The piece of steel rather highly contaminated by {sup 60}Co was used. In the intercomparison test 1994-1995 of pulverized concrete breeze-block containing fly ash with natural radionuclides were used. Results of this measurement is given as an example (authors).

  12. Gamma background radiation monitoring results (1990-95) in the environs around IRE OSCOM, Orissa using TLDs

    Energy Technology Data Exchange (ETDEWEB)

    Mehta, N K; Bapat, V N; Nambi, K S.V. [Bhabha Atomic Research Centre, Mumbai (India). Environmental Assessment Div.; Saha, S C [Bhabha Atomic Research Centre, Bombay (India). Health Physics Div.

    1997-09-01

    Quarterly environmental radiation monitoring data using TLDs in about 28 locations in and around IRE-OSCOM covering a six year period 1990-95 is presented in the report. While the indoor radiation levels in beach areas having monazite deposits recorded annual average of 653{+-}230 mR/y, that in IRE residential colony gave a value of 240 {+-}30 mR/y. The radiation levels recorded inside the OSCOM plant are well within the limits prescribed for occupational radiation exposures. (author). 3 refs., 7 figs., 1 tab.

  13. Radiation monitoring of PET staff

    International Nuclear Information System (INIS)

    Trang, A.

    2004-01-01

    Full text: Positron emission tomography (PET) is becoming a common diagnostic tool in hospitals, often located in and employing staff from the Nuclear Medicine or Radiology departments. Although similar in some ways, staff in PET departments are commonly found to have the highest radiation doses in the hospital environment due to unique challenges which PET tracers present in administration as well as production. The establishment of a PET centre with a dedicated cyclotron has raised concerns of radiation protection to the staff at the WA PET Centre and the Radiopharmaceutical Production and Development (RAPID) team. Since every PET centre has differing designs and practices, it was considered important to closely monitor the radiation dose to our staff so that improvements to practices and design could be made to reduce radiation dose. Electronic dosimeters (MGP DMC 2000XB), which have a facility to log time and dose at 10 second intervals, were provided to three PET technologists and three PET nurses. These were worn in the top pocket of their lab coats throughout a whole day. Each staff member was then asked to note down their duties throughout the day and also note the time they performed each duty. The duties would then correlate with the dose with which the electronic monitor recorded and an estimate of radiation dose per duty could be given. Also an estimate of the dose per day to each staff member could be made. PET nurses averaged approximately 20 μ8v per day getting their largest dose from caring for occasional problematic patients. Smaller doses of a 1-2 μ8v were recorded for injections and removing cannulas. PET technologists averaged approximately 15 μ8v per day getting their largest dose of 1-5μ8v mainly from positioning of patients and sometimes larger doses due to problematic patients. Smaller doses of 1-2 μ5v were again recorded for injections and removal of cannulas. Following a presentation given to staff, all WA PET Centre and RAPID staff

  14. 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)

  15. Quality assurance of environmental gamma radiation monitoring in Slovenia

    International Nuclear Information System (INIS)

    Stuhec, M.; Zorko, B.; Mitic, D.; Miljanic, S.; Ranogajec-Komor, M.

    2006-01-01

    Environmental gamma radiation monitoring established in Slovenia consists of a network of multifunctional gamma monitors (MFMs) based on pairs of Geiger-Mueller counters and a network of measuring sites with high-sensitive thermoluminescence dosemeters. The measuring points are evenly spread across Slovenia, located at the meteorological stations and more densely on additional locations around the Krsko NPP. The MFM network has a 2-fold function with one sensor used for the purpose of early warning system in near surroundings of the NPP and the other, more sensitive, for natural radiation monitoring. The paper summarises activities to establish quality assurance of the environmental gamma radiation measurements in Slovenia, with a critical view of the results in comparison with the international standards and recommendations. While the results of linearity and energy dependence tests were satisfying, on-field intercomparison showed that the inherent signal of one of the monitors (MFM) has to be taken into account in the range of environmental background radiation. (authors)

  16. Monitoring of radiation exposure and registration of doses

    International Nuclear Information System (INIS)

    1996-01-01

    The guide defines the concepts relevant to the monitoring of radiation exposure and working conditions and provides guidelines for determining the necessity of monitoring and subsequently organizing it. In addition, instructions are given for reporting doses to the Dose Register of the Finnish Centre for Radiation and Nuclear Safety (STUK). Also the procedures are described for situations leading to exceptional exposures. (10 refs., 1 tab.)

  17. Cytogenetic monitoring of hospital workers exposed to low-level ionizing radiation

    International Nuclear Information System (INIS)

    Bigatti, P.; Lamberti, L.; Ardito, G.; Armellino, F.

    1988-01-01

    In the present study the cytogenetic effects in hospital workers exposed to low-level radiation were evaluated. Samples of peripheral blood were collected from 63 subjects working in radiodiagnostics and from 30 subjects, working in the same hospitals, who were used as controls. A higher number of cells with chromosome-type aberrations (CA) was observed in the exposed workers vs. the controls and the difference was statistically significant (p<0.05). No correlation was, on the contrary, found between CA and years of exposure. A significant difference was observed in the incidence of cells with CA between smokers and non-smokers, but in the control group only. In contrast, in the workers exposed to ionizing radiation, the frequency of cells with CA was very similar in smokers and non-smokers. 13 refs.; 4 tabs

  18. Environmental radiation levels in and around Kalpakkam during 1983-1987

    International Nuclear Information System (INIS)

    Nambi, K.S.V.; Mehta, N.K.; Sundaram, Meenakshi; Viswambharan, K.R.

    1989-01-01

    Results of the environmental radiation monitoring around the Kalpakkam Atomic Power Station carried out routinely on quarterly integrating cycles using thermoluminescent dosimeters, are presented and analysed, for the five year period 1983-87. As the first reactor attained criticality in July 1983 and the second unit in August 1985 the results are compared with the previously published values for the period 1980-82. Only at two locations viz. the Micro-met laboratory situated at 800 meters from the station and the main gate located at the 1.6 km exclusion zone boundary, a possible indication of increases in the environmental radiation level associated with the power reactor operations could be discerned. However these were found to be statistically insignificant. The whole terrain is characterised by somewhat high levels of terrestrial radiations with quite wide temporal fluctuations which easily mask the small increases if any in the radiation levels, contributed by the reactors. Places located farther away from the power station and away from the monazite-bearing beaches, yielded an annual average background level of 117 ± 29 mR as against the value of 125 ± 24 mR obtained during the preoperational period of 1980-82. A declining general trend in the radiation levels is seen at many locations and this is thought to be associated with significant reduction in the 137 Cs fallout component of the environmental radiation. (author). 5 refs., 2 tabs., 11 figs

  19. Early notification of the environmental radiation monitoring system to a radioactive event

    International Nuclear Information System (INIS)

    Haquin, G.; Ne'eman, F; Brenner, S.

    1997-01-01

    The National Environmental Radiation Monitoring System managed by the Radiation Safety Division of the Ministry of tile Environment has been completed and is composed of a network of 10 stations; 6 terrestrial stations, 3 waterside stations and one mobile. The system was built by Rotem Co. and the control center is located at the Unit of Environmental Resources of the Ministry of the Environment in Tel Aviv University. Each station consists of a wide range Geiger Mueller detector and ambient dose rate meter that provides the level of the environmental dose rate. Low level radioactive particles are detected by air sampling with devices that collect suspended and settling particles . Each station is connected to the control center through telephone lines and RF communication system providing 24 hour a day the level of the environmental radiation. The background radiation dose rate level depends on the location of the station and varies from 8 - 16 μR/h. The system has proved its efficiency in a 'simulation like event' early detecting an unregistered gamma radiography work in the proximity of two stations performed in June 96 in Ashdod port and in December 96 at Maspenot Israel in Haifa. During the events the radiation level increased up to 20 times above the background level. Survey teams of the Ashdod port and Maspenot Israel were sent to place to check the sources for the radiation level increase. These teams found workers performing radiography work in the area of the stations. (authors)

  20. Radiation safety assessment and development of environmental radiation monitoring technology

    CERN Document Server

    Choi, B H; Kim, S G

    2002-01-01

    The Periodic Safety Review(PSR) of the existing nuclear power plants is required every ten years according to the recently revised atomic energy acts. The PSR of Kori unit 1 and Wolsong unit 1 that have been operating more than ten years is ongoing to comply the regulations. This research project started to develop the techniques necessary for the PSR. The project developed the following four techniques at the first stage for the environmental assessment of the existing plants. 1) Establishment of the assessment technology for contamination and accumulation trends of radionuclides, 2) alarm point setting of environmental radiation monitoring system, 3) Development of Radiation Safety Evaluation Factor for Korean NPP, and 4) the evaluation of radiation monitoring system performance and set-up of alarm/warn set point. A dynamic compartment model to derive a relationship between the release rates of gas phase radionuclides and the concentrations in the environmental samples. The model was validated by comparing ...

  1. Paper on operation and maintenance experiences on radiation monitoring instrumentation at NAPS

    International Nuclear Information System (INIS)

    Gupta, J.P.; Vinod Kumar; Sen, S.K.; Malhotra, S.

    2005-01-01

    Narora Atomic Power Station (NAPS) is the first standardized Pressurised Heavy Water Reactor in India commissioned in the year 1989. Many new Radiation Monitoring Systems like Portal Monitors and Ventilation Exhaust Activity Monitors were first time introduced at NAPS. All the Personnel Contamination Monitors and Area Radiation Monitors used at NAPS were designed and developed by Electronics Division, BARC. Only the Portal Monitor was supplied by M/S Herfurth, Germany. The paper highlights the operation and maintenance experiences on Radiation Monitoring Instrumentation at NAPS in the last 15 years of operation. The paper also highlights the different problems faced in Radiation Instruments and our suggestions for improvement in their design for their better availability and long term reliability. (author)

  2. Monitoring and analysis PET/CT workplace radioactivity level in Shanghai

    International Nuclear Information System (INIS)

    Wang Bin; Gao Linfeng; Qian Aijun; Yao Jie; Shen Jinfu; Ji Guiyi

    2012-01-01

    Objective: To understand the PET/CT basic information in Shanghai, through monitoring radioactivity level of PET/CT workplace, to get the radiological protection information about PET/CT place. Methods: Through the γ radiation air absorbed dose rate and the β surface contamination to investigate PET/CT medical institutions in Shanghai. Results: By the end of 2011, there were 13 sets of PET/CT. Detecting show that γ radiation air absorbed dose rate is at relatively higher level in waiting room and the injection rooms, the date of waiting room door was up to 19552 nSv/h, the maximum value of injection room desk surface was 6136 nSv/h, the middle of injection room was up to 5408 nSv/h. Any date was certain the limits of national standard of β surface contamination, the middle of in the injection room. It is still higher on the window and wastes barrel. Conclusion: The radiation protection of PET/CT workplace is proper, surface contamination levels can be controlled within in the standard limits, but there are a blank of limits about nuclear medicine place of γ radiation absorbed dose rate air in the national standard, and external exposure protection is still the key of radiation protection. (authors)

  3. Gamma background radiation monitoring results (1990-95) in the environs around IRE OSCOM, Orissa using TLDs

    International Nuclear Information System (INIS)

    Mehta, N.K.; Bapat, V.N.; Nambi, K.S.V.; Saha, S.C.

    1997-01-01

    Quarterly environmental radiation monitoring data using TLDs in about 28 locations in and around IRE-OSCOM covering a six year period 1990-95 is presented in the report. While the indoor radiation levels in beach areas having monazite deposits recorded annual average of 653±230 mR/y, that in IRE residential colony gave a value of 240 ±30 mR/y. The radiation levels recorded inside the OSCOM plant are well within the limits prescribed for occupational radiation exposures. (author). 3 refs., 7 figs., 1 tab

  4. Modernization of WWER-1000 radiation monitoring systems

    Energy Technology Data Exchange (ETDEWEB)

    Smith, T [General Atomics, San Diego, CA (United States)

    1996-12-31

    A modernization scheme of the radiation monitoring system for WWER-1000 is proposed. It has a purpose to comply with international standards and to reduce operational and maintenance cost by deleting obsolete components and reducing the number of detector channels. Detailed layouts of I/C system architecture, digital radiation monitoring system (DRAMS) architecture and LRP block diagram are presented. If planned and implemented properly, this program can provide cost savings by reducing time required to access and display data and maintenance cost by deleting obsolete parts and decreasing the number of detector channels. 3 figs.

  5. Modernization of WWER-1000 radiation monitoring systems

    International Nuclear Information System (INIS)

    Smith, T.

    1995-01-01

    A modernization scheme of the radiation monitoring system for WWER-1000 is proposed. It has a purpose to comply with international standards and to reduce operational and maintenance cost by deleting obsolete components and reducing the number of detector channels. Detailed layouts of I/C system architecture, digital radiation monitoring system (DRAMS) architecture and LRP block diagram are presented. If planned and implemented properly, this program can provide cost savings by reducing time required to access and display data and maintenance cost by deleting obsolete parts and decreasing the number of detector channels. 3 figs

  6. Radiation monitoring methodologies and their applications at BARC site

    International Nuclear Information System (INIS)

    Divkar, J.K.; Chatterjee, M.K.; Patra, R.P; Morali, S.; Singh, Rajvir

    2016-01-01

    Radiation monitoring methodology can be planned for various objectives during normal as well as emergency situations. During radiological emergency, radiation monitoring data provides useful information required for management of the abnormal situation. In order to assess the possible consequences accurately and to implement adequate measure, the emergency management authorities should have a well-prepared monitoring strategy in readiness. Fixed monitoring method is useful to analyze the behavior of nuclear plant site and to develop holistic model for it mobile monitoring is useful for quick impact assessment and will be the backbone of emergency response, particularly in case of non availability of fixed monitoring system caused due to natural disaster like floods, earthquake and tsunami

  7. Development of infrared communication in radiation protection and monitoring

    International Nuclear Information System (INIS)

    Thakur, Vaishali M.; Choithramani, S.J.; Sharma, D.N.; Abani, M.C.

    2003-01-01

    Infra-red communication has many important applications in instrumentation and control. Different types of nuclear instruments are used for radiation protection and surveillance program. The application of this mode of communication in these instruments helps in monitoring of inaccessible or high radiation field areas by avoiding undue exposure to the occupational worker. The demand for remotely controlled monitoring instruments and wireless data communication in the mobile computing environment has rapidly increased. This is due to the increasing need for on-line radiological data analysis with minimum human interventions, especially so if the monitoring is in hazardous environment. The wireless communication can be achieved using different communication methodology for short and long range communication. The infrared based communication is used for different applications for short range up to 9-10 meters. The use of this mode of communication has been implemented in some of the radiation monitoring instruments developed in house. The evaluation of data communication using this mode was conducted for the systems like Environmental Radiation Monitor (ERM) and results showed that data communication error is less than 0.1% up to 10 meter distance. (author)

  8. Radiation damage monitoring in the ATLAS pixel detector

    International Nuclear Information System (INIS)

    Seidel, Sally

    2013-01-01

    We describe the implementation of radiation damage monitoring using measurement of leakage current in the ATLAS silicon pixel sensors. The dependence of the leakage current upon the integrated luminosity is presented. The measurement of the radiation damage corresponding to an integrated luminosity 5.6 fb −1 is presented along with a comparison to a model. -- Highlights: ► Radiation damage monitoring via silicon leakage current is implemented in the ATLAS (LHC) pixel detector. ► Leakage currents measured are consistent with the Hamburg/Dortmund model. ► This information can be used to validate the ATLAS simulation model.

  9. Practical radiation monitoring

    International Nuclear Information System (INIS)

    Keightley, Lynsey; Burgess, Peter; Delahunty, Denise; Richards, Tony; Simpson, John; Woods, Mike

    2002-01-01

    This Good Practice Guide has been written by a working party of experts from the UK Ionising Radiation Metrology Forum. It describes procedures and methods for assessing radiation levels, outlines the thought processes needed to carry out the measurements and gives practical advice. The methods described are general and based on currently accepted good practice

  10. The regulations for delivery of subsidies to radiation monitoring

    International Nuclear Information System (INIS)

    1979-01-01

    The regulations are defined under the law concerning subsidies and the provisions of the order for execution of the law. Basic terms are explained, such as: nuclear power generating facilities; arrangement business of radiation monitoring facilities; pre-research business of radiation monitoring; radiation monitoring business; place of enterprise; and expected time of beginning of the use. The Director General of Science and Technology Agency delivers subsidies to those prefectures where nuclear power generating facilities are or are expected to be established, or their neighboring prefectures. Subsidies are paid for each place of enterprise to support all or a part of expenses necessary for arrangement, pre-research or radiation monitoring business. Limits of subsidies for a place of enterprise in a prefecture are 155.6 million yen for a term for arrangement business, 16 million yen for each fiscal year for pre-research and 16 million yen for each fiscal year for radiation monitoring. An application for subsidies shall be filed by a prefecture to the Director General with the business program and gists of nuclear power generating facilities according to the forms attached. Receiving the application, the Director General shall examine it and notify without delay to the applicant the decision of delivery and its conditions in writing, when such settlement is made. Terms and conditions of delivery and reports, etc. are prescribed respectively. (Okada, K.)

  11. TH-E-209-00: Radiation Dose Monitoring and Protocol Management

    International Nuclear Information System (INIS)

    2016-01-01

    Radiation dose monitoring solutions have opened up new opportunities for medical physicists to be more involved in modern clinical radiology practices. In particular, with the help of comprehensive radiation dose data, data-driven protocol management and informed case follow up are now feasible. Significant challenges remain however and the problems faced by medical physicists are highly heterogeneous. Imaging systems from multiple vendors and a wide range of vintages co-exist in the same department and employ data communication protocols that are not fully standardized or implemented making harmonization complex. Many different solutions for radiation dose monitoring have been implemented by imaging facilities over the past few years. Such systems are based on commercial software, home-grown IT solutions, manual PACS data dumping, etc., and diverse pathways can be used to bring the data to impact clinical practice. The speakers will share their experiences with creating or tailoring radiation dose monitoring/management systems and procedures over the past few years, which vary significantly in design and scope. Topics to cover: (1) fluoroscopic dose monitoring and high radiation event handling from a large academic hospital; (2) dose monitoring and protocol optimization in pediatric radiology; and (3) development of a home-grown IT solution and dose data analysis framework. Learning Objectives: Describe the scope and range of radiation dose monitoring and protocol management in a modern radiology practice Review examples of data available from a variety of systems and how it managed and conveyed. Reflect on the role of the physicist in radiation dose awareness.

  12. TH-E-209-00: Radiation Dose Monitoring and Protocol Management

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2016-06-15

    Radiation dose monitoring solutions have opened up new opportunities for medical physicists to be more involved in modern clinical radiology practices. In particular, with the help of comprehensive radiation dose data, data-driven protocol management and informed case follow up are now feasible. Significant challenges remain however and the problems faced by medical physicists are highly heterogeneous. Imaging systems from multiple vendors and a wide range of vintages co-exist in the same department and employ data communication protocols that are not fully standardized or implemented making harmonization complex. Many different solutions for radiation dose monitoring have been implemented by imaging facilities over the past few years. Such systems are based on commercial software, home-grown IT solutions, manual PACS data dumping, etc., and diverse pathways can be used to bring the data to impact clinical practice. The speakers will share their experiences with creating or tailoring radiation dose monitoring/management systems and procedures over the past few years, which vary significantly in design and scope. Topics to cover: (1) fluoroscopic dose monitoring and high radiation event handling from a large academic hospital; (2) dose monitoring and protocol optimization in pediatric radiology; and (3) development of a home-grown IT solution and dose data analysis framework. Learning Objectives: Describe the scope and range of radiation dose monitoring and protocol management in a modern radiology practice Review examples of data available from a variety of systems and how it managed and conveyed. Reflect on the role of the physicist in radiation dose awareness.

  13. Radiation monitoring of nuclear census intelligent data management and mobile monitoring data acquisition system

    International Nuclear Information System (INIS)

    Huang Libin; Zhong Zhijing; Zhou Yinhang; Guo Hongbo

    2014-01-01

    The system, employing advanced intelligent terminal, mobile applications, database technology, can achieve all kinds of field monitoring, mobile radiation monitoring data collected for laboratory analysis; employing GPS technology, can achieve the geographic information of the radiation monitoring data, time tagging and other anti-cheating measures; the system also established a mass database management system; the system is suitable for all types of nuclear-related units with special adaptive functions; system will be extended to GIS-based management capabilities of nuclear contamination distribution in latter stage. (authors)

  14. Environmental radiation monitoring around the nuclear facilities

    International Nuclear Information System (INIS)

    Lee, H.D.; Lee, W.Y.; Park, D.W.

    1981-01-01

    Measurements and monitoring of the environmental radiation levels, as well as radioactivity of the various environmental samples were carried out three times a month in the on-site and the off-site around the KAERI site. Measurements were made for both gross alpha and beta radioactivity of all environmental samples. Gross beta measurements were made for radioactivity of the fallout, airborne particulates and precipitations which were collected on a daily basis on the roof of the main building. Measurements of the accumulated doses were also carried out at 10 posts on a bimonthly basis by employing thermoluminescent dosimeters

  15. Radiation monitoring of Syr-Darya river

    International Nuclear Information System (INIS)

    Barber, D.S.; Howard, H.D.; Betsill, J.D.; Matthews, R.; Yuldashev, B.S.; Salikhbaev, U.S.; Radyuk, R.I.; Vdovina, E.D.; Solodukhin, V.P.; Poznyak, V.L.; Vasiliev, I.A.; Alekhina, V.M.; Juraev, A.A.

    2003-01-01

    The article contains the results obtained during the radiation monitoring of Syr-Darya River, which was conducted within the frames of international collaboration of Kazakhstan, Kyrgyzstan, Tajikistan, Uzbekistan, and USA. The data on the nature of salinity of water, alfa- and beta-activity of water, bottom, water plants, and soil was obtained. Dependence of the obtained results on the distance form the source is discussed. The major life-providing arteries for the great region of Central Asia are Syr-Darya and Amu Darya rivers. There are many countries next to the pools of these rivers: Tajikistan, Afghanistan, Turkmenistan, Uzbekistan, Kyrgyzstan, and Kazakhstan. There is a great concern caused by the shortage of supply of fresh water, severe epidemiological situation, and radiation conditions along of the pools of these rivers. Such conditions have developed as a result of intensive economic and industrial activities, and also of geological and geochemical features of this region. One of the most serious aspects of this problem is the weak scrutiny level of influence of large deposits of natural uranium and consequences of technological and industrial activities. Since November, 2000 Scientifics of four of the listed countries (Kazakhstan, Kyrgyzstan, Tajikistan, and Uzbekistan) have come to an agreement carrying out the teamwork on studying and monitoring the environment in the pools of Syr-Darya and Amu Darya rivers [1]. Collaborator of these works is Cooperative Monitoring Center at Sandia National Laboratories, USA. During three expeditions each country in 15 control sites on their territory has conducted field researches and has obtained the samples of elements of the environment. Laboratory researches were carried out in Kazakhstan and Uzbekistan. The first results were obtained in (2,3) and later in [4].Currently, the analysis of the data on salinity of water and alpha- and beta- activities of samples along Syr-Darya River is presented

  16. Autonomous Radiation Monitoring of Small Vessels

    International Nuclear Information System (INIS)

    Fabris, Lorenzo; Hornback, Donald Eric

    2010-01-01

    Small private vessels are one avenue by which nuclear materials may be smuggled across international borders. While one can contemplate using the terrestrial approach of radiation portal monitors on the navigable waterways that lead to many ports, these systems are ill-suited to the problem. They require vehicles to pass at slow speeds between two closely-spaced radiation sensors, relying on the uniformity of vehicle sizes to space the detectors, and on proximity to link an individual vehicle to its radiation signature. In contrast to roadways where lanes segregate vehicles, and motion is well controlled by inspection booths; channels, inlets, and rivers present chaotic traffic patterns populated by vessels of all sizes. We have developed a unique solution to this problem based on our portal-less portal monitor instrument that is designed to handle free-flowing traffic on roadways with up to five-traffic lanes. The instrument uses a combination of visible-light and gamma-ray imaging to acquire and link radiation images to individual vehicles. It was recently tested in a maritime setting. In this paper we present the instrument, how it functions, and the results of the recent tests.

  17. The automatic radiation monitor distributed System SRM-256C

    International Nuclear Information System (INIS)

    Stetsenko, G.N.; Rastsvetalov, Y.N.; Yanovich, A.A.

    1996-01-01

    The Controlled and Supervised Areas (CSA) of UNK proton accelerator built in Protvino (IHEP, Russia), borrows the significant area (more than 15 sq.km). Submitted in work results of accounts show, that by major factors, influencing to a radioecological conditions in region at the expense of work UNK are: 1) the output of pulsing radiation on day-time surface; 2) the radionuclides receipts with drinking water; 3) the pollution of radioactive air from system of ventilation. At normal mode of UNK operation the equivalent dose rates on daytime surface of pulsing radiation will changes in limits from 0.5 mcSv/hours near overmines buildings up to 0.1 mcSv / hour on the CSA border. The average equivalent dose rates per year due to internal irradiation at use (intakes) of drinking water will not exceed 5 - 50 mcSv/years. The Maximum equivalent dose rates on day-time surface, caused by pollution of radioactive air does not exceed 0.01... 0.03 mcSv/hour in limits of CSA, and the average equivalent dose per year caused by internal irradiation does not exceed 0.05 mcSv/years. At emergency-free operation the maximum degree of the UNK influence in limits of CSA is estimated in terms of average equivalent dose per year at levels, not exceeding 0.05... 0.10 mSv/year. For maintenance of integral environmental monitoring of total external radiation levels in limits of CSA network of passive monitor stations will be developed

  18. Response of radiation monitors for ambient dose equivalent, H*(10)

    International Nuclear Information System (INIS)

    Grecco, Claudio Henrique dos Santos

    2001-01-01

    Radiation monitors are used all over the world to evaluate if places with presence of ionising radiation present safe conditions for people. Radiation monitors should be tested according to international or national standards in order to be qualified for use. This work describes a methodology and procedures to evaluate the energy and angular responses of any radiation monitor for ambient dose equivalent, H*(10), according to the recommendations of ISO and IEC standards. The methodology and the procedures were applied to the Monitor Inteligente de Radiacao MIR 7026, developed by the Instituto em Engenharia Nuclear (IEN), to evaluate and to adjust its response for H*(10), characterizing it as an ambient dose equivalent meter. The tests were performed at the Laboratorio Nacional de Metrologia das Radiacoes Ionizantes (LNMRI), at Instituto de Radioprotecao e Dosimetria (IRD), and results showed that the Monitor Inteligente de Radiacao MIR 7026 can be used as an EI*(10) meter, in accordance to the IEC 60846 standard requirements. The overall estimated uncertainty for the determination of the MIR 7026 response, in all radiation qualities used in this work, was 4,5 % to a 95 % confidence limit. (author)

  19. Radiation protection and environmental monitoring in the area of the Asse shaft plant. Annual report 1987

    International Nuclear Information System (INIS)

    Mueller-Lyda, I.; Meyer, H.

    1988-07-01

    Personnel monitoring has been carried through in compliance with the Radiation Protection Ordinance. Environmental monitoring including measurement of local doses, local dose rates, and airborne radioactivity in the shaft has been made according to the provisions for radiation protection at the place of work. Maximum permissible personal doses or activity levels for occupationally exposed persons have not been exceeded in the reporting period. Exhaust air monitoring detected the nuclides H-3, C-14, Pb-210, and the short-lived daughter products of Rn-222 and Rn-220. The activity concentrations in the environment, determined from the measured annual release values, for some part have been lower than the average of natural concentrations of said nuclides. The radiation exposure due to emissions, measured at the least favourable point in the environment, has been far below the limits set by the Radiation Protection Ordinance. In conclusion: The radiation exposure of the personnel and of the population in the area of the Asse shaft plant due to the storage of radioactive is low, compared to the natural radiation exposure. (orig.) [de

  20. Monitoring and crisis system of radiation safety

    International Nuclear Information System (INIS)

    Bartok, J.; Borovansky, P.; Macica, J.; Petrovicova, M.

    2005-01-01

    In this paper we have briefly described our practical experiences with the most complex Radiation Monitoring System we have designed. This system consists of number of stations; those data are collected in the main crisis center of the whole system. The main center integrates RMS Central Database, the IMS Model Suite workstation and the Graphics workstation. The radiations probes of the RP series are the base for stationary , portable sets and for sets measuring underwater radiation. The radiation and meteorological data, which are necessary for reasonable interpretation of radiation data, are archived in RMS Central database. The Lagrangian trajectory model from the IMS Model Suite serves for radiation dispersion modeling. (authors)

  1. Monitoring of high-radiation areas for the assessment of operational and body doses

    International Nuclear Information System (INIS)

    Chen, T.J.; Tung, C.J.; Yeh, W.W.; Liao, R.Y.

    2004-01-01

    The International Commission on Radiological Protection (ICRP) recommended a system of dose limits for the protection of ionizing radiation. This system was established based on the effective dose, E, and the equivalent dose to an organ or tissue, H T , to assess stochastic and deterministic effects. In radiation protection monitoring for external radiation, operational doses such as the deep dose equivalent index, H I,d , shallow dose equivalent index, H I,s , ambient dose equivalent [1,4-6], H*, directional dose equivalent, H', individual dose equivalent-penetrating, H p , and individual dose equivalent-superficial, H s , are implemented. These quantities are defined in an International Commission on Radiation Units and Measurements (ICRU) sphere and in an anthropomorphic phantom under simplified irradiation conditions. They are useful when equivalent doses are below the corresponding limits. In the case of equivalent doses far below the limits, the exposure or air kerma is commonly applied. For workers exposed to high levels of radiation, accurate assessments of effective doses and equivalent doses may be needed in order to acquire legal and health information. In the general principles of monitoring for radiation protection of workers, ICRP recommended that: 'A graduated response is advocated for the monitoring of the workplace and for individual monitoring - graduated in the sense that a greater degree of monitoring is deemed to be necessary as doses increase of as unpredictability increases. Gradually more complex or realistic procedures should be adopted as doses become higher. Thus, at low dose equivalents (corresponding say to those within Working Condition B) dosimetric quantities might be used directly to assess exposure, since accuracy is not crucial. At intermediate dose equivalents (corresponding say to Working Condition A and slight overexposures) somewhat greater accuracy is warranted, and the conversion coefficients from dosimetric to radiation

  2. Continuous environmental radiation monitoring network at Kalpakkam

    International Nuclear Information System (INIS)

    Somayaji, K.M.; Mathiyarasu, R.; Prakash, G.S.; Meenakshisundaram, V.; Rajagopal, V.

    1997-01-01

    The report highlights our experience in the design and installation of monitoring stations as part of continuous environmental radiation monitoring network around the periphery of the nuclear complex at Kalpakkam. Five monitoring stations, one each in south-west sector (Main Gate I) and south-south west (Main Gate II) and the others in North sector (HASL and ESG) and in north-west section (WIP) have been set up. Two independent detector systems, based on high pressure ionisation chamber (HPIC) and energy compensated GM have been installed at each of these locations and the data has been logged continuously using a data logger. The data so gathered at each monitoring station is retrieved every week by means of a hand held terminal (HHT) with a built-in non-volatile memory and transferred to an IBM PC-AT for data analysis and archival. The report discusses in depth the design and developmental efforts undertaken to set up the network, starting from the basic detectors. The work involved the design of suitable electrometer circuits for measuring the low levels of current from HPICs, and the subsequent study of the performance of the highly sensitive preamplifier under diurnal variations of ambient conditions. The report includes, in detail the design aspects and fabrication details of low current measuring electrometer circuits

  3. 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

  4. Definition of priority areas for monitoring of gamma radiation on the surroundings of the CDTN installations

    International Nuclear Information System (INIS)

    Chagas, Claudio Jose; Carvalho Filho, Carlos A.; Peixoto, Claudia Marques; Rodrigues, Paulo C. Horta; Augustin, Cristina Helena R. Rocha

    2013-01-01

    To demonstrate compliance with regulations and legal requirements, the Environmental Monitoring Program of the - Development Center of Nuclear Technology - PMA/CDTN was created in 1985. However, at that time, no data was available to represent the background - the natural level for the pre operational period in terms of Gamma radiation. Thus, the lowest value obtained among the sentinel point sites from the early period of the environmental monitoring was adopted as benchmark. As these measurements were performed by procedures and conditions other than that currently in use, this reference value may not correspond to reality. Therefore, it may not be appropriate to use it as background in assessing the possible environmental impact generated by the activities of the facilities. The goal of this study is to propose an area of geographic distribution for 12 monitoring points, outside the CDTN facilities, so that the real natural Gamma radiation levels can be accurately measured without the interference of the radioactivity levels originating from the institution, enabling the determination of the most representative values of the natural gamma radiation in the area. This survey of the natural radiation determination in the study area, with the use of modern equipment and the application of methodology taking into account historical data, as well the geological, geomorphological and geographical studies of the region, pointed to an average background value of 0.095μSv/h. This result, together with other studies, indicated a maximum range of 25m beyond the CDTN boundaries to distribute the monitoring points. (author)

  5. Radiation and environmental monitoring at the nuclear legacy sites in Russia

    Energy Technology Data Exchange (ETDEWEB)

    Shandala, N.; Kiselev, S.; Titov, A.; Seregin, V.; Akhromeev, S.; Aladova, R.; Isaev, D. [SRC Burnasyan Federal Medical Biophysical Center (Russian Federation); Sneve, M. [Norwegian Radiation Protection Authority - NRPA (Norway)

    2014-07-01

    In 1960's, in the Northwest and Far East regions of Russia the technical bases of the Navy Fleet were built to maintain nuclear submarines by performing reloading of nuclear fuel, receiving and storing radioactive waste (RW) and spent nuclear fuel (SNF). In 2000, SevRAO enterprise in the northwest of Russia and DalRAO enterprise in the Far East were set up for the purposes of environmental remediation of the nuclear legacy sites. Regulatory supervision for radiation protection and safety at the nuclear legacy sites in Russian Far east and Northwest regions is one of regulatory functions of the Federal medical biological agency (FMBA of Russia). Improvement of the normative and regulatory basis has significant impact on effectiveness and efficiency of industrial projects aimed at reduction of nuclear and radiation hazard risk at the sites for the SNF and RW temporary storage (STS).To get unbiased comprehensive information on the current radiation conditions at the STSs and provide the effective response to changing radiation situation, the environmental radiation monitoring of the SevRAO and DalRAO facilities has been carried out during 2005-2013. The nature and peculiarity of the STS area radioactive contamination on the Kola Peninsula and in the Far East are the following: 1) high levels of radioactive contamination on the industrial site; 2) non-uniformity of the contamination distribution; 3) spread of contamination in the area of health protection zone. The following environmental components are contaminated: soil, vegetation, bottom sediments and seaweeds at the offshore sea waters. The dominant radionuclides are cesium-137 and strontium-90. At the facilities under inspection for the purpose of the dynamic control of the radiation situation the radio-ecological monitoring system was arranged. It presupposes regular radiometry inspections in-situ, their analysis and assessment of the radiation situation forecast in the course of the STS remediation main

  6. Citizen radiation monitoring program for the TMI area

    International Nuclear Information System (INIS)

    Baratta, A.J.; Gricar, B.G.; Jester, W.A.

    1981-07-01

    The purpose of the program was to develop a system for citizens to independently measure radiation levels in and around their communities. This report describes the process by which the Program was developed and operated. It also presents the methods used to select and train the citizens in making and interpreting the measurements. The test procedures used to select the equipment for the program are described as are the results of the testing. Finally, the actual monitoring results are discussed along with the citizens' reactions to the program

  7. Citizen radiation monitoring program for the TMI area

    Energy Technology Data Exchange (ETDEWEB)

    Baratta, A.J.; Gricar, B.G.; Jester, W.A.

    1981-07-01

    The purpose of the program was to develop a system for citizens to independently measure radiation levels in and around their communities. This report describes the process by which the Program was developed and operated. It also presents the methods used to select and train the citizens in making and interpreting the measurements. The test procedures used to select the equipment for the program are described as are the results of the testing. Finally, the actual monitoring results are discussed along with the citizens' reactions to the program.

  8. Natural radiation external exposures levels in Chilean Sub-Antarctic and country stations

    International Nuclear Information System (INIS)

    Stuardo, E.

    1988-01-01

    Since 1983 gamma exposures levels, at 1,5 m above the soil are being investigated using TLD detectors. A network of 12 stations have been established from ARICA (18 deg 20' S latitude) in Northern Chile to YELCHO (64 deg 52' S latitude) in Antartic territory. One year monitoring period was used at Antartic stations and a four months period in the country. The main subject of this study is to assess the average background radiation levels along the territory which is relevant to get a reference level and specially an estimate of the average natural radiation contribution to the population dose in Southern Chile

  9. Study of the response of radiation protection monitors in terms of H*(10) in X radiation

    International Nuclear Information System (INIS)

    Nonato, Fernanda B.C.; Carvalho, Valdir S.; Vivolo, Vitor; Caldas, Linda V.E.

    2009-01-01

    The ambient dose equivalent, H * (10), is an operational quantity recommended by the International Commission of radiation Units and Measurements Report 39 for measurements in area monitoring. However, most of the monitoring instruments used in radiation protection in Brazil still use the old quantities exposure rate and absorbed dose rate. Therefore, it is necessary to study how to change the operational quantity to H * (10). In this work, the response of radiation protection monitoring detectors was studied in terms of H * (10) for different energies using standard X-rays (narrow beams) at the Calibration Laboratory of IPEN. (author)

  10. Development of radiation safety monitoring system at gamma greenhouse gamma facility

    International Nuclear Information System (INIS)

    Hairul Nizam Idris; Azimawati Ahmad, Ahmad Zaki Hussain; Ahmad Fairuz Mohd Nasir

    2009-01-01

    This paper is discussing about installation of radiation safety monitoring system at Gamma Greenhouse Gamma facility, Agrotechnology and Bioscience Division (BAB). This facility actually is an outdoor type irradiation facility, which first in Nuclear Malaysia and the only one in Malaysia. Source Cs-137 (801 Curie) was use as radiation source and it located at the centre of 30 metres diameter size of open irradiation area. The radiation measurement and monitoring system to be equipped in this facility were required the proper equipment and devices, specially purpose for application at outside of building. Research review, literature study and discussion with the equipment manufacturers was being carried out, in effort to identify the best system should be developed. Factors such as tropical climate, environment surrounding and security were considered during selecting the proper system. Since this facility involving with panoramic radiation type, several critical and strategic locations have been fixed with radiation detectors, up to the distance at 200 meter from the radiation source. Apart from that, this developed system also was built for capable to provide the online real-time reading (using internet). In general, it can be summarized that the radiation safety monitoring system for outdoor type irradiation facility was found much different and complex compared to the system for indoor type facility. Keyword: radiation monitoring, radiation safety, Gamma Greenhouse, outdoor irradiation facility, panoramic radiation. (Author)

  11. Emergency monitoring strategy and radiation measurements document of the NKS project emergency management and radiation monitoring in nuclear and radiological accidents (EMARAD)

    Energy Technology Data Exchange (ETDEWEB)

    Lahtinen, J. [Radiation and Nuclear Safety Authority (STUK) (Finland)

    2006-04-15

    This report is one of the deliverables of the NKS Project Emergency management and radiation monitoring in nuclear and radiological accidents (EMARAD) (20022005). The project and the overall results are briefly described in the NKS publication 'Emergency Management and Radiation Monitoring in Nuclear and Radiological Accidents. Summary Report on the NKS Project EMARAD' (NKS-137, April 2006). In a nuclear or radiological emergency, all radiation measurements must be performed efficiently and the results interpreted correctly in order to provide the decision-makers with adequate data needed in analysing the situation and carrying out countermeasures. Managing measurements in different situations in a proper way requires the existence of pre-prepared emergency monitoring strategies. Preparing a comprehensive yet versatile strategy is not an easy task to perform because there are lots of different factors that have to be taken into account. The primary objective of this study was to discuss the general problematics concerning emergency monitoring strategies and to describe a few important features of an efficient emergency monitoring system as well as factors affecting measurement activities in practise. Some information concerning the current situation in the Nordic countries has also been included. (au)

  12. The development of remote wireless radiation dose monitoring system

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Jin-woo [KAERI - Korea Atomic Energy Research Institute, Jeongup-si (Korea, Republic of); Chonbuk National University, Jeonjoo-Si (Korea, Republic of); Jeong, Kyu-hwan [KINS - Korea Institute of Nuclear Safety, Daejeon-Si (Korea, Republic of); Kim, Jong-il [Chonbuk National University, Jeonjoo-Si (Korea, Republic of); Im, Chae-wan [REMTECH, Seoul-Si (Korea, Republic of)

    2015-07-01

    Internet of things (IoT) technology has recently shown a large flow of IT trends in human life. In particular, our lives are now becoming integrated with a lot of items around the 'smart-phone' with IoT, including Bluetooth, Near Field Communication (NFC), Beacons, WiFi, and Global Positioning System (GPS). Our project focuses on the interconnection of radiation dosimetry and IoT technology. The radiation workers at a nuclear facility should hold personal dosimeters such as a Thermo-Luminescence Dosimeter (TLD), an Optically Stimulated Luminescence Dosimeter (OSL), pocket ionization chamber dosimeters, an Electronic Personal Dosimeter (EPD), or an alarm dosimeter on their body. Some of them have functions that generate audible or visible alarms to radiation workers in a real working area. However, such devices used in radiation fields these days have no functions for communicating with other areas or the responsible personnel in real time. In particular, when conducting a particular task in a high dose area, or a number of repair works within a radiation field, radiation dose monitoring is important for the health of the workers and the work efficiency. Our project aims at the development of a remote wireless radiation dose monitoring system (RWRD) that can be used to monitor the radiation dose in a nuclear facility for radiation workers and a radiation protection program In this project, a radiation dosimeter is the detection device for personal radiation dose, a smart phone is the mobile wireless communication tool, and, Beacon is the wireless starter for the detection, communication, and position of the worker using BLE (Bluetooth Low Energy). In this report, we report the design of the RWRD and a demonstration case in a real radiation field. (authors)

  13. The development of remote wireless radiation dose monitoring system

    International Nuclear Information System (INIS)

    Lee, Jin-woo; Jeong, Kyu-hwan; Kim, Jong-il; Im, Chae-wan

    2015-01-01

    Internet of things (IoT) technology has recently shown a large flow of IT trends in human life. In particular, our lives are now becoming integrated with a lot of items around the 'smart-phone' with IoT, including Bluetooth, Near Field Communication (NFC), Beacons, WiFi, and Global Positioning System (GPS). Our project focuses on the interconnection of radiation dosimetry and IoT technology. The radiation workers at a nuclear facility should hold personal dosimeters such as a Thermo-Luminescence Dosimeter (TLD), an Optically Stimulated Luminescence Dosimeter (OSL), pocket ionization chamber dosimeters, an Electronic Personal Dosimeter (EPD), or an alarm dosimeter on their body. Some of them have functions that generate audible or visible alarms to radiation workers in a real working area. However, such devices used in radiation fields these days have no functions for communicating with other areas or the responsible personnel in real time. In particular, when conducting a particular task in a high dose area, or a number of repair works within a radiation field, radiation dose monitoring is important for the health of the workers and the work efficiency. Our project aims at the development of a remote wireless radiation dose monitoring system (RWRD) that can be used to monitor the radiation dose in a nuclear facility for radiation workers and a radiation protection program In this project, a radiation dosimeter is the detection device for personal radiation dose, a smart phone is the mobile wireless communication tool, and, Beacon is the wireless starter for the detection, communication, and position of the worker using BLE (Bluetooth Low Energy). In this report, we report the design of the RWRD and a demonstration case in a real radiation field. (authors)

  14. Personal monitoring and assessment of doses received by radiation workers

    International Nuclear Information System (INIS)

    Swindon, T.N.; Morris, N.D.

    1981-12-01

    The Personal Radiation Monitoring Service operated by the Australian Radiation Laboratory is outlined and the types of monitors used for assessment of doses received by radiation workers are described. The distribution of doses received by radiation workers in different occupational categories is determined. From these distributions, the average doses received have been assessed and the maximum likely additional increase in cancer deaths in Australia as a result of occupational exposure estimated. This increase is shown to be very small. There is, however, a considerable spread of doses received by individuals within occupational groups

  15. Radiation monitoring network of the Slovak Hydrometeorological Institute

    International Nuclear Information System (INIS)

    Melicherova, T.

    2005-01-01

    In 2000 Centre of Partial monitoring system 'Radioactivity of environment' was established on Slovak Hydrometeorology Institute (SHMI). Radiation monitoring network is one part of Radiation monitoring network of the Slovak Republic. At present SHMI operates in its monitoring network 23 detectors GammaTracer fy Genitron, one mobile detector and one stan by detector. All active detectors are placed in the professional meteorological stations in the selected parts of Slovakia. First one of these detectors was installed in 1999 and they replaced former type of detector (FAG). Last two detectors were installed in 2002. Detector GammaTracer has range of measurement from 20 nSv/h to 10 Sv/h. The detectors are calibrated every 2 years in the Slovak Institute of Metrology in compliance with the calibration plan. SHMI operates 4 aerosol monitors in Hurbanovo, Lucenec, Stropkov and Liesek. Filter 8 from these monitors are analysed in the Institute of Public Health (Cs-137, Be-7). On the base of bilateral agreement between the Austrian Ministry of Agriculture, Forestry, Environment and Water-Management and the Slovak Ministry of Environment Austrian side gave into the ownership of the Slovak side an automatic aerosol monitor AMS-02 including container and weather station. This monitor was installed in meteorological station Jaslovske Bohunice on 4-th October 2001. The Slovak Ministry of Environment provides the Austrian Ministry of Agriculture, Forestry, Environment and Water-Management with the readings of this monitor, free of charge, for at least 3 years and vice versa, the Austrian side gives the readings of the Austrian aerosol monitors to the Slovak Ministry of Environment free of charge. At present national monitoring center in Bratislava-Koliba is connected via ISDN line with Jaslovske Bohunice and Austrian center providing the data exchange. Radiation data (dose rate in the unit nSv/h) are collected via the Institute network to the MSS (message switch system) in the

  16. Report on environmental radiation monitoring associated with visits to Australian ports by nuclear powered warships in 1980; and, amendments to the guidelines for environmental radiation monitoring during visits of nuclear powered warships to Australian ports

    International Nuclear Information System (INIS)

    1981-04-01

    The Australian Government requires that an environmental radiation monitoring program be carried out in association with visits of nuclear ships to Australian ports. The objectives and requirements of the program are summarised and the results of the marine environmental sampling program undertaken at berths are presented, together with radiation measurements taken during visits. During 1980, no releases of radioactive material were detected, nor were any radiation measurements recorded in excess of natural background levels

  17. Development of dose monitoring system applicable to various radiations with wide energy ranges

    International Nuclear Information System (INIS)

    Sato, Tatsuhiko; Satoh, Daiki; Endo, Akira; Yamaguchi, Yasuhiro

    2005-01-01

    A new inventive radiation dose monitor, designated as DARWIN (Dose monitoring system Applicable to various Radiations with WIde energy raNges), has been developed for monitoring doses in workspaces and surrounding environments of high energy accelerator facilities. DARWIN is composed of a phoswitch-type scintillation detector, which consists of liquid organic scintillator BC501A coupled with ZnS(Ag) scintillation sheets doped with 6 Li, and a data acquisition system based on a Digital-Storage-Oscilloscope. Scintillations from the detector induced by thermal and fast neutrons, photons and muons were discriminated by analyzing their waveforms, and their light outputs were directly converted into the corresponding doses by applying the G-function method. Characteristics of DARWIN were studied by both calculation and experiment. The calculated results indicate that DARWIN gives reasonable estimations of doses in most radiation fields. It was found from the experiment that DARWIN has an excellent property of measuring doses from all particles that significantly contribute to the doses in surrounding environments of accelerator facilities - neutron, photon and muon with wide energy ranges. The experimental results also suggested that DARWIN enables us to monitor small fluctuation of neutron dose rates near the background-level owing to its high sensitivity. (author)

  18. Radiation exposure control by estimation of multiplication factors for online remote radiation monitoring systems at Vitrification Plant

    International Nuclear Information System (INIS)

    Deokar, Umesh V.; Kukarni, V.V.; Khot, A.R.; Mathew, P.; Kamlesh; Purohit, R.G.; Sarkar, P.K.

    2011-01-01

    Vitrification Plant is commissioned for vitrification of high-level liquid waste generated in Nuclear Fuel Cycle operations by using Joule Heated Ceramic Melter first time in India. Exposure control is a major concern in operating plant. Therefore, in addition to installed monitors, we have developed online remote radiation monitoring system to minimize number of entries in amber areas and to reduce the exposure to the surveyor and operator. This also helped in volume reduction of secondary waste. The reliability and accuracy of the online monitoring system is confirmed with actual measurements and by theoretical shielding calculations. The multiplication factors were estimated for remote online monitoring of Melter off Gas (MOG) filter, Hood filter, three exhaust filter banks, and overpack monitoring. This paper summarizes how the online remote monitoring system had helped in saving of 128.52 Person-mSv collective dose (14.28% of budgeted dose) and also there was 2.6 m 3 reduction in generation of Cat-I waste. (author)

  19. Development of the national register of radiation workers: subsystem for individual monitoring of external exposure

    International Nuclear Information System (INIS)

    Yu Haitao; Niu Haowei; Sun Quanfu; Fu Yinghua; Fan Yaohua; Yue Baorong

    2010-01-01

    Objective: To develop a national registry and reporting system of individual monitoring for workers occupationally exposed to ionizing radiation. Methods: In accordance with the relevant law, regulations, standards and the current health supervision practice for radiation workers in China, to ensure more effective collection of information on individual monitoring from all levels of service providers across the country and an easy query and analysis of the collected information for both service providers and administrative institutions, the register consisted of an offline-system and a web-based information system. The off-line system consisted of 8 tables, which could easily make annual and period monitoring reports, and upload individual monitoring data in compressed and encrypted format. Web-based system consisted of 6 modules, could easily make S customized tabulations of monitoring data and show 2 trend figures. SSLVPN secure remote access was used in the system. Arranged by the Ministry of Health, training courses provided to all individual monitoring service providers and provincial administrative institutions. Results: A new and individual-based national register and reporting system of individual monitoring for workers occupationally exposed to ionizing radiation was successfully developed, and would be officially run soon. Conclusions: The establishment and running of the register would be great improvement on the national radiological health reports and produce a far-reaching impact on the individual monitoring in China. (authors)

  20. Radiation levels at CERN's injectors and their impact on electronic equipment

    CERN Document Server

    AUTHOR|(SzGeCERN)649218; Brugger, Markus

    2013-01-01

    Electronic devices operating in hostile radiation environments, such as those found close to high-energy particle accelerators, can suffer from different types of radiation induced failures. At CERN, the mixed particle and energy radiation fields present at the Large Hadron Collider (LHC) and its injector chain can give rise to both stochastic and cumulative effects causing radiation induced failures of exposed electronics and materials, thus directly impacting components and system lifetimes, as well as maintenance requirements. With its original focus on the LHC, the Radiation to Electronics (R2E) project has been successfully implementing mitigation actions in order to avoid accelerator downtime due to radiation induced failures on active electronics. In a next step, the emphasis is put on CERN's injector chain, collecting the respective available information about radiation levels, the definition of additional monitoring requirements and a critical analysis of present and future equipment installations. T...

  1. Radiation survey meters used for environmental monitoring

    International Nuclear Information System (INIS)

    Bjerke, H.; Sigurdsson, T.; Meier Pedersen, K.; Grindborg, J.-E.; Persson, L.; Siiskonen, T.; Hakanen, A.; Kosunen, A.

    2012-01-01

    The Nordic dosimetry group set up the GammaRate project to investigate how its expertise could be used to assure appropriate usage of survey meters in environmental monitoring. Considerable expertise in calibrating radiation instruments exists in the Nordic radiation protection authorities. The Swedish, Finnish, Danish and Norwegian authorities operate Secondary Standard Dosimetry Laboratories (SSDLs) that provide users with calibration traceable to internationally recognised primary standards. These authorities together with the Icelandic authorities have formally cooperated since 2002 in the field of radiation dosimetry. Dosimetry is the base for assesment of risk from ionising radiation and calibration of instruments is an imported part in dosimetry. The Nordic dosimetry group has been focused on cancer therapy. This work extends the cooperation to the dosimetry of radiation protection and environmental monitoring. This report contains the formal, theoretical and practical background for survey meter measurements. Nordic standards dosimetry laboratories have the capability to provide traceable calibration of instruments in various types of radiation. To verify and explore this further in radiation protection applications a set of survey instruments were sent between the five Nordic countries and each of the authority asked to provide a calibration coefficient for all instruments. The measurement results were within the stated uncertainties, except for some results from NRPA for the ionchamber based instrument. The comparison was shown to be a valuable tool to harmonize the calibration of radiation protection instruments in the Nordic countries. Dosimetry plays an important role in the emergency situations, and it is clear that better traceability and harmonised common guidelines will improve the emergency preparedness and health. (Author)

  2. Radiation survey meters used for environmental monitoring

    Energy Technology Data Exchange (ETDEWEB)

    Bjerke, H. (ed.) (Norwegian Radiation Protection Authority, NRPA (Norway)); Sigurdsson, T. (Icelandic Radiation Safety Authority, Geislavarnir Rikisins, GR (IS)); Meier Pedersen, K. (National Board of Health, Statens Institut for Straalebeskyttelse (SIS) (Denmark)); Grindborg, J.-E.; Persson, L. (Swedish Radiation Safety Authority, Straalsaekerhetsmyndigheten (SSM) (Sweden)); Siiskonen, T.; Hakanen, A.; Kosunen, A. (Radiation and Nuclear Safety Authority, Saeteilyturvakeskus (STUK) (Finland))

    2012-01-15

    The Nordic dosimetry group set up the GammaRate project to investigate how its expertise could be used to assure appropriate usage of survey meters in environmental monitoring. Considerable expertise in calibrating radiation instruments exists in the Nordic radiation protection authorities. The Swedish, Finnish, Danish and Norwegian authorities operate Secondary Standard Dosimetry Laboratories (SSDLs) that provide users with calibration traceable to internationally recognised primary standards. These authorities together with the Icelandic authorities have formally cooperated since 2002 in the field of radiation dosimetry. Dosimetry is the base for assesment of risk from ionising radiation and calibration of instruments is an imported part in dosimetry. The Nordic dosimetry group has been focused on cancer therapy. This work extends the cooperation to the dosimetry of radiation protection and environmental monitoring. This report contains the formal, theoretical and practical background for survey meter measurements. Nordic standards dosimetry laboratories have the capability to provide traceable calibration of instruments in various types of radiation. To verify and explore this further in radiation protection applications a set of survey instruments were sent between the five Nordic countries and each of the authority asked to provide a calibration coefficient for all instruments. The measurement results were within the stated uncertainties, except for some results from NRPA for the ionchamber based instrument. The comparison was shown to be a valuable tool to harmonize the calibration of radiation protection instruments in the Nordic countries. Dosimetry plays an important role in the emergency situations, and it is clear that better traceability and harmonised common guidelines will improve the emergency preparedness and health. (Author)

  3. Micro Penning Trap for Continuous Magnetic Field Monitoring in High Radiation Environments

    Science.gov (United States)

    Latorre, Javiera; Bollen, Georg; Gulyuz, Kerim; Ringle, Ryan; Bado, Philippe; Dugan, Mark; Lebit Team; Translume Collaboration

    2016-09-01

    As new facilities for rare isotope beams, like FRIB at MSU, are constructed, there is a need for new instrumentation to monitor magnetic fields in beam magnets that can withstand the higher radiation level. Currently NMR probes, the instruments used extensively to monitor magnetic fields, do not have a long lifespans in radiation-high environments. Therefore, a radiation-hard replacement is needed. We propose to use Penning trap mass spectrometry techniques to make high precision magnetic field measurements. Our Penning microtrap will be radiation resistant as all of the vital electronics will be at a safe distance from the radiation. The trap itself is made from materials not subject to radiation damage. Penning trap mass spectrometers can determine the magnetic field by measuring the cyclotron frequency of an ion with a known mass and charge. This principle is used on the Low Energy Beam Ion Trap (LEBIT) minitrap at NSCL which is the foundation for the microtrap. We have partnered with Translume, who specialize in glass micro-fabrication, to develop a microtrap in fused-silica glass. A microtrap is finished and ready for testing at NSCL with all of the electronic and hardware components setup. DOE Phase II SBIR Award No. DE-SC0011313, NSF Award Number 1062410 REU in Physics, NSF under Grant No. PHY-1102511.

  4. The level of knowledge and radiation safety practice amongst cardiovascular technology, medical assistant, nursing and diagnostic radiography students and dose monitoring in radiography laboratory of Kolej Islam Sains dan Teknologi, Kelantan

    International Nuclear Information System (INIS)

    Ainul Fadhlin Othman; Amran Abdul Majid

    2013-01-01

    Full-text: This study investigated the knowledge level and practices regarding radiation safety among the cardiovascular technology, medical assistant nursing and radiography diagnostic students of Kolej Islam Sains dan Teknologi (KIST). The objectives of this study are to monitor the dose rate at radiography lab and to propose the guideline on radiation safety topics to improve the syllabus. 274 respondents including 30 psychology students acting as the control group were asked to answer questions from the questionnaires which cover the topics of basic knowledge of radiation and radiation safety practice. There was a significant difference (p < 0.05) between the correct answers and courses for 18 questions except for the question 4. There was a significant different (p < 0.05) between the correct answers and year of study for the questions 4, 5, 7, 12 to 15 and 18 to 20. There was a significance different (p < 0.05) between the correct answers and gender for questions 7, 11 and 19. For area dose monitoring in the radiography diagnostic lab, the assessment report on film batches of 4 walls in the lab were recorded and Victoreen451-RYR survey meter was used to monitor the dose rate for 7 selected areas with the exposure factors set for the chest, abdomen, upper extremity, lower extremity and skull radiography examinations. The dose rates at area 1 to 4, area 5 during the examination of chest, abdomen and skull, area 6 during the examination of abdomen and area 7 during the examination of abdomen, had exceeded the dose limit for radiation worker. The dose rate at the area 1 and 4 are slightly higher than the other areas. The contributing factors are the distance, tube potential, collimation and X-ray tube angulation. This study had shown that the cardiovascular technology and diagnostic radiography students have better knowledge and radiation safety practice level than the medical assistant and nursing students. In general, the level of knowledge and radiation safety

  5. Radiation monitoring data on the power-up test of HTTR. Results up to 20 MW operation

    International Nuclear Information System (INIS)

    Ashikagaya, Yoshinobu; Nakazawa, Takashi; Yoshino, Toshiaki; Yasu, Katsuji

    2002-01-01

    The High Temperature Engineering Test Reactor (HTTR) have completed the Power-up test of 9 MW (the single and parallel loaded operation) in the rated operation mode. After that the Power-up test in the rated operation mode and the high-temperature test operation mode with a thermal output of 20 MW (the single and parallel loaded operation) were performed between January 16, 2001 and June 10, 2001. This report describes the radiation monitoring data carried out during the HTTR Power-up test in the rated operation mode and the high-temperature test operation mode with a thermal output of 20 MW. The followings were concluded from these radiation monitoring data. The monitoring of radioactive gaseous effluents and the radiation protection for the works will be easy to do and the exposure dose of the workers will be kept the low level. (author)

  6. Development of a Compact Gamma-ray Detector for a Neural-Network Radiation Monitoring

    Energy Technology Data Exchange (ETDEWEB)

    Kim, H. S.; Ha, J. H.; Lee, K. H. [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Lee, C. H. [Hanyang Univ., Seoul (Korea, Republic of)

    2012-03-15

    Radiation monitoring is very important to secure safety in nuclear-related facilities and against nuclear terrorism. For wide range of radiation monitoring, neutral network system of radiation detection is most efficient way. Thus, a compact radiation detector is useful to install in wide range to be concerned. A compact gamma-ray detector was fabricated by using a CsI(Tl) scintillator, which was matched with the formerly developed PIN photodiode, for a neural network radiation monitoring. At room temperature, the fabricated compact gamma-ray detector demonstrates an energy resolution of 13.3 % for 662 keV 6.9% for 1330 keV. The compactness, the low-voltage power consumption and the physical hardness are very useful features for a neural network radiation monitoring. In this study, characteristics of a fabricated compact gamma-ray detector were presented. An important aspect to consider in a neural-network radiation monitoring such as reaction probability of the fabricated compact detector for angle of incident gamma-ray was also addressed.

  7. Personnel radiation monitoring by thermoluminescence dosimetry (2000-2001)

    International Nuclear Information System (INIS)

    Mi-Cho-Cho, Daw; Hla-Hla-Win, Daw; Thin-Thin-Kraing

    2001-01-01

    Thermoluminescence dosimetry service was introduced in 1991. Personnel who exposed directly or indirectly to radiation is monitored by thermoluminescent dosimeter. TL materials used for thermoluminescent dosimeter are in the form of thin disc. Personnel whole-body and extremity doses are measured by thermoluminescence dosimetry. The Harshaw Model 4500 TLD reader and Vinten 654E TLD reader are used for TLD evaluation. At present about 600 radiation workers are provided with TLD for routine monitoring. It was found that most personnel had received within permissible dose recommended by the International Commission on Radiological Protection (ICRP). (author)

  8. Autonomous radiation monitoring of small vessels

    International Nuclear Information System (INIS)

    Ziock, K.P.; Cheriyadat, A.; Fabris, L.; Goddard, J.; Hornback, D.; Karnowski, T.; Kerekes, R.; Newby, J.

    2011-01-01

    Small private vessels are one avenue by which nuclear materials may be smuggled across international borders. While one can contemplate using the land-based approach of radiation portal monitors on the navigable waterways that lead to many ports, these systems are ill-suited to the problem. In contrast to roadways, where lanes segregate vehicles, and motion is well controlled by inspection booths; channels, inlets, and rivers present chaotic traffic patterns populated by vessels of all sizes. A unique solution to this problem is based on a portal-less portal monitor designed to handle free-flowing traffic on roadways with up to five-traffic lanes. The instrument uses a combination of visible-light and gamma-ray imaging to acquire and link radiation images to individual vehicles. This paper presents the results of a recent test of the system in a maritime setting.

  9. Development of Nuclide Recognizing Prompt Radiation Distribution Monitoring System

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Uk Jae; Yoo, Dong Han; Kim, Hee Reyoung [Ulsan National Institute of Science and Technology, Ulsan (Korea, Republic of)

    2014-05-15

    The geographic data such as latitude, longitude and map image can be obtained by using GPS and digital map. Radiation data can be acquired by detector. Finally simultaneous visibility system can be operated by using CDMA. Existing radiation distribution monitoring system is based on random generated data. However the radiation distribution monitoring system is developed. It is based on real detected data. Connection between the detector and laptop which are located at a site place is operated by using Bluetooth. CDMA is used to simulate visibility system between laptop in a site place and server PC in the control office. Real map image is taken from digital map. Finally radiation distribution contour map on the real map image can be shown by using MATLAB. 5 figures appear which shows natural, {sup 137}Cs, {sup 131}I, artificial and total radiation dose rate. So this system can be used in everywhere to check the distribution of radiation with geographic information.

  10. The wireless sensor network monitoring system for regional environmental nuclear radiation

    International Nuclear Information System (INIS)

    Liu Chong; Liu Dao; Wang Yaojun; Xie Yuxi; Song Lingling

    2012-01-01

    The wireless sensor network (WSN) technology has been utilized to design a new regional environmental radiation monitoring system based on the wireless sensor networks to meet the special requirements of monitoring the nuclear radiation in certain regions, and realize the wireless transmission of measurement data, information processing and integrated measurement of the nuclear radiation and the corresponding environmental parameters in real time. The system can be applied to the wireless monitoring of nuclear radiation dose in the nuclear radiation environment. The measured data and the distribution of radiation dose can be vividly displayed on the graphical interface in the host computer. The system has functioned with the wireless transmission and control, the data storage, the historical data inquiry, the node remote control. The experimental results show that the system has the advantages of low power consumption, stable performance, network flexibility, range of measurement and so on. (authors)

  11. Demonstration of mobile radiation monitoring methodology for quick assessment of radiological impact of Mumbai City Using road, rail and sea routes

    International Nuclear Information System (INIS)

    Chatterjee, M.K.; Divkar, J.K.; Singh, Rajvir; Pradeepkumar, K.S.; Sharma, D.N.

    2008-01-01

    The study of background radiation levels by suitable mobile monitoring methodology through different routes (road, rail and sea) with the help of state of the art monitoring systems has been initiated with an objective to demonstrate the effectiveness of monitoring methodologies for quick radiological impact assessment during any radiological emergency and to detect the presence of orphan source(s), if any. The other objective was to establish a reliable base line data on the background radiation levels. The study was carried out in Mumbai city through different available routes. Mumbai is a densely populated city and everyday millions of commuters are crossing across the city using rail and road routes. In case of any unwarned radiological emergency in public domain, a large section of people of the city may get concerned of radioactive contamination/ high radiation exposure. In such scenario, environmental radiation monitoring and quick assessment of contamination in public domain will be a challenging task for the civil authorities. The monitoring techniques used for quick radiological impact assessment and the established base line dose rate data of Mumbai city will be very useful for planning counter measures, if required. During mobile monitoring programme of this highly populated city, the monitoring routes, selection and placement of different monitoring instruments/system within the mobile platform, data acquisition time of the respective monitoring equipments, speed of mobile monitoring station etc were optimized. State-of-the-art systems like Portable Mobile Gamma Spectrometry System (PMGSS), Compact Radiation Monitoring System integrated with GPS, Gammatracers, Portable low/high range survey meters and hand held spectrometers were used. The average of the dose rates recorded during monitoring through road routes and railway routes of Mumbai city were 60±10 nGy.h -1 and 65±15 nGy.h -1 respectively, which are attributable to terrestrial and cosmic

  12. Integrating existing radiation monitors into a microprocessor-based display system

    International Nuclear Information System (INIS)

    Kalita, R, S.; Bartucci, C.M.; Mason, R.G.; Greaves, C.

    1992-01-01

    Plantwide digital radiation monitoring systems (RMSs) have been generally installed as part of the original design for newer nuclear reactors. For older plants, area and process radiation monitors were either analog or a combination of analog and digital but were not part of an integrated system design. At some plants, individual monitors have been replaced or modified, resulting in a rainbow of different monitors and vendors being represented at the plant. Usually at some point, consideration is given to replacing these monitors with a state-of-the-art RMS to improve overall reliability and achieve the benefits of sound human factors engineering. This can be a very costly project in terms of expenditures for engineering, equipment, construction, startup, and time. When human engineering deficiencies (HEDs) became an issue at Zion station, Commonwealth Edison elected to install a computer-based radiation monitoring display system (RMDS) that would interface existing raidation monitors. After reviewing the existing as-built RMS configuration and internal circuits of the various monitors, it was concluded that a microprocessor-based RMDS could be successfully designed and installed that would solve the HEDs and would tie the older analog channels into a system configuration. Although in many cases, internal modifications were made to existing RMS monitors, the RMDS upgrade allowed the existing RMS monitors to retain their original functionality and location

  13. Radiation monitoring complete change by an unprecedented nuclear power plant accident

    International Nuclear Information System (INIS)

    Omura, Tomomi

    2011-01-01

    Hydrogen explosion at the Fukushima Daiichi Nuclear Power Station of Tokyo Electric Power Company that was triggered by the tsunami generated from the Great East Japan Earthquake led to a series of disasters up to meltdown and melt-through. A large amount of discharge of radioactive substances to the environment due to the disasters marked a sea change in the situation of radiation monitoring in Japan to date. The Japanese Government took the following actions. (1) Establishment of government-led monitoring system through the setup of the Monitoring Coordination Council, (2) Decision on 'Comprehensive Monitoring Program' that implements unified comprehensive radiation monitoring and publishes the results, and (3) Law establishment for radiation monitoring by stipulating immediate implementation systems and implementation points as well as budgetary backup for this purpose. This paper describes the plans to monitor the environment, public facilities, aquatic environment, agricultural land, food, etc., as well as the future challenges. (O.A.)

  14. Monitoring of Level of Radiation Hazards to the Community in the Settlement Around the Incandescent Gas Mantle Factory

    International Nuclear Information System (INIS)

    Suryawati

    2000-01-01

    The analyze of radiation internal hazards level of thoron (Rn-220) and its daughter to the community settlement around the incandescent gas mantle factory. The radiation hazard level can be indicated in the form of working level (WL) and sffsctive dose lungs received by the community. The working level and effective dose lungs is got from the measurement of radioactivity level of thoron (Rn-220) and its daugther and by using the mathematical formula calculation. The measurement of thoron radioactive concentration and its daughter. The value of woking level obtained, performance level for community range from 0,001-0,013 WL, equivalent with dose range from 0,014- 0,467 mSv. From the research result, it can be identified that the radiation hazard, because exceed the mean value of threshold thorium radioactive nuclide and its daughter product of natural radiation in back ground per year for word mean i.e. 0,336 mSv, but the value of this research result is far below the allowed value limit for the community is 0,12 WL and 1 mSv/year

  15. Emergency monitoring strategy and radiation measurements. Working document of the NKS project emergency management and radiation monitoring in nuclear and radiological accidents (EMARAD)

    International Nuclear Information System (INIS)

    Lahtinen, J.

    2006-04-01

    This report is one of the deliverables of the NKS Project Emergency management and radiation monitoring in nuclear and radiological accidents (EMARAD) (20022005). The project and the overall results are briefly described in the NKS publication 'Emergency Management and Radiation Monitoring in Nuclear and Radiological Accidents. Summary Report on the NKS Project EMARAD' (NKS-137, April 2006). In a nuclear or radiological emergency, all radiation measurements must be performed efficiently and the results interpreted correctly in order to provide the decision-makers with adequate data needed in analysing the situation and carrying out countermeasures. Managing measurements in different situations in a proper way requires the existence of pre-prepared emergency monitoring strategies. Preparing a comprehensive yet versatile strategy is not an easy task to perform because there are lots of different factors that have to be taken into account. The primary objective of this study was to discuss the general problematics concerning emergency monitoring strategies and to describe a few important features of an efficient emergency monitoring system as well as factors affecting measurement activities in practise. Some information concerning the current situation in the Nordic countries has also been included. (au)

  16. Health physics experience in commissioning and operation of radiation and air activity monitoring system at FBTR

    International Nuclear Information System (INIS)

    Raghunath, V.M.; Meenakshisundaram, V.; Viswanathan, S.; Bala Sundar, S.; Jose, M.T.; Suriyamurthy, N.; Ravi, T.; Subramanian, V.

    2001-01-01

    The Radiation and Air Activity Monitoring System (RAAMS) at Fast Breeder Test Reactor (FBTR) is meant to monitor and record the radiation and air activity levels at various potentially active areas in FBTR complex. Health Physics Group, FBTR was associated during commissioning of RAAMS in fixing the alarm settings for the monitors, their relocation and in formulating the surveillance procedures. The areas were surveyed to check for any release of activity for confirming the observed readings during operation of the reactor. In such cases, augmentation of shielding was recommended and was promptly implemented by the station management. The details of the long and fruitful experience gained by the Health Physics Group, FBTR are described in this paper. (author)

  17. Monitoring radiation damage in the ATLAS pixel detector

    CERN Document Server

    Schorlemmer, André Lukas; Quadt, Arnulf; Große-Knetter, Jörn; Rembser, Christoph; Di Girolamo, Beniamino

    2014-11-05

    Radiation hardness is one of the most important features of the ATLAS pixel detector in order to ensure a good performance and a long lifetime. Monitoring of radiation damage is crucial in order to assess and predict the expected performance of the detector. Key values for the assessment of radiation damage in silicon, such as the depletion voltage and depletion depth in the sensors, are measured on a regular basis during operations. This thesis summarises the monitoring program that is conducted in order to assess the impact of radiation damage and compares it to model predictions. In addition, the physics performance of the ATLAS detector highly depends on the amount of disabled modules in the ATLAS pixel detector. A worrying amount of module failures was observed during run I. Thus it was decided to recover repairable modules during the long shutdown (LS1) by extracting the pixel detector. The impact of the module repairs and module failures on the detector performance is analysed in this thesis.

  18. Radiation levels in Ecuadorian Cattle Milk

    International Nuclear Information System (INIS)

    Reinoso, Teresa; Vasquez, Ramiro

    2008-01-01

    Full text: The radiation and natural radioactivity present in the ground from a radioactive decay of 238 U, 235 U and 232 Th, and of the radioisotope 40 K can be transferred to the nutritional chain of the human being. Milk is a food considered basic within population's diet. The Ecuadorian Highlands has the greater production of cattle milk in the country, this industry needs great extensions of graze and available superficial water, which the cows consumed for crude milk production, with the consequent product industrialization. In the present research, gamma radiation levels where monitoring in 12 crude milk representative samples of the zone. The measurements where carried out using an equipment of spectrometry gamma ray system, with a detector of Hiperpuro Germanium (GeHp), which has been used in the analysis of standard and samples spectrums, with a constant geometry of the sample holder. The spectrums of the milk analysis show the presence of the radioisotopes coming from uranium radioactive decay. The majority of the values of activity concentration are below the minimum detection activity, unlike the potassium that presents a detectable but a non quantitative spectrum. So far, with the results obtained it is possible to guarantee the milk consumption and its derivatives in the Andean Region of the country. Related research will allow us implementing the radiological monitoring of this and other foods in the country, in order to protected population health. (author)

  19. FPGA-based prototype of portable environmental radiation monitor

    Energy Technology Data Exchange (ETDEWEB)

    Benahmed, A.; Elkarch, H. [CNESTEN -Centre National de l' Energie des Sciences et Techniques Nucleaires (Morocco)

    2015-07-01

    This new portable radiological environmental monitor consists of 2 main components, Gamma ionization chamber and a FPGA-based electronic enclosure linked to convivial software for treatment and analyzing. The HPIC ion chamber is the heart of this radiation measurement system and is running in range from 0 to 100 mR/h, so that the sensitivity at the output is 20 mV/μR/h, with a nearly flat energy response from 0,07 to 10 MEV. This paper presents a contribution for developing a new nuclear measurement data acquisition system based on Cyclone III FPGA Starter Kit ALTERA, and a user-friendly software to run real-time control and data processing. It was developed to substitute the older radiation monitor RSS-112 PIC installed in CNESTEN's Laboratory in order to improve some of its functionalities related to acquisition time and data memory capacity. As for the associated acquisition software, it was conceived under the virtual LabView platform from National Instrument, and offers a variety of system setup for radiation environmental monitoring. It gives choice to display both the statistical data and the dose rate. Statistical data shows a summary of current data, current time/date and dose integrator values, and the dose rate displays the current dose rate in large numbers for viewing from a distance as well as the date and time. The prototype version of this new instrument and its data processing software has been successfully tested and validated for viewing and monitoring the environmental radiation of Moroccan nuclear center. (authors)

  20. Overview of the atmospheric ionizing radiation environment monitoring by Bulgarian build instruments

    Science.gov (United States)

    Dachev, Tsvetan; Tomov, Borislav; Matviichuk, Yury; Dimitrov, Plamen; Spurny, Frantisek; Ploc, Ondrej; Uchihori, Yukio; Flueckiger, Erwin; Kudela, Karel; Benton, Eric

    2012-10-01

    Humans are exposed to ionizing radiation all the time, and it is known that it can induce a variety of harmful biological effects. Consequently, it is necessary to quantitatively assess the level of exposure to this radiation as the basis for estimating risks for their health. Spacecraft and aircraft crews are exposed to elevated levels of cosmic radiation of galactic and solar origin and to secondary radiation produced in the atmosphere, the vehicle structure and its contents. The aircraft crew monitoring is required by the following recommendations of the International Commission on Radiological Protection (ICRP) (ICRP 1990), the European Union (EU) introduced a revised Basic Safety Standards Directive (EC 1997) which, inter alia, included the exposure to cosmic radiation. This approach has been also adopted in other official documents (NCRP 2002). In this overview we present the results of ground based, mountain peaks, aircraft, balloon and rocket radiation environment monitoring by means of a Si-diode energy deposition spectrometer Liulin type developed first in Bulgarian Academy of Sciences (BAS) for the purposes of the space radiation monitoring at MIR and International Space Station (ISS). These spectrometers-dosemeters are further developed, calibrated and used by scientific groups in different countries. Calibration procedures of them are performed at different accelerators including runs in the CERN high-energy reference field, simulating the radiation field at 10 km altitude in the atmosphere and with heavy ions in Chiba, Japan HIMAC accelerator were performed also. The long term aircraft data base were accumulated using specially developed battery operated instrument in 2001-2009 years onboard of A310-300 aircrafts of Czech Air Lines, during 24 about 2 months runs with more than 2000 flights and 13500 flight hours on routes over the Atlantic Ocean mainly. The obtained experimental data are compared with computational models like CARI and EPCARD. The

  1. A cytogenetic bio-monitoring of industrial radiographers occupationally exposed to low levels of ionizing radiation by using CBMN assay

    International Nuclear Information System (INIS)

    Shakeri, Mahsa; Changizi, Vahid; Zakeri, Farideh; Rajabpour, Mohammad Reza; Farshidpour, Mohammad Reza

    2017-01-01

    Industrial radiography is the process of using either gamma-emitting radionuclide sources or X-ray machines to examine the safety of industrial materials. The average annual effective dose in industrial radiography is one of the highest among radiation workers. The aim of this study was to investigate the cytogenetic effects of ionizing radiation in the peripheral blood lymphocytes of 60 industrial radiographers and 40 non-exposed individuals as the control group by using cytokinesis-block micronucleus (CBMN) assay. Totally, the frequencies of micronuclei (MN), nucleoplasmic bridges (NPBs) and nuclear buds (NBUDs) were significantly higher in the industrial radiographers than in the controls (p = 0.000). The mean MN frequency per 1000 binucleated cells in the industrial radiographers with last 5-y radiation dose of >100 mSv was significantly higher than those with ≤100 mSv (34.81 ± 12.70 vs. 26.33 ± 7.940, p = 0.024). The effect of age was observed in the control group and subjects with the age of >30 y showed significantly higher MN frequency compared with the subjects with the age of ≤30 y (9.45 ± 3.710 vs. 6.81 ± 3.050, p = 0.02). No obvious trend of increased MN as a function of either duration of employment or age or smoking status was observed in the industrial radiographers. The results show the increased levels of cytogenetic damages in the industrial radiographers. Even the workers exposed to the permissible doses are subjected to elevated frequencies of DNA damages. These findings confirm the importance of cytogenetic bio-monitoring program beside physical dosimetry, surveying radiation safety of equipment and periodic training of workers for improvement of safety and radiation protection. (authors)

  2. Monitoring Your Blood Sugar Level

    Science.gov (United States)

    ... and NutritionHealth Insurance: Understanding What It CoversHigh Homocysteine Level: How It Affects Your Blood VesselsUnderstanding Your Medical ... Health Resources Healthcare Management Monitoring Your Blood Sugar Level Monitoring Your Blood Sugar Level Share Print What ...

  3. Evaluating a radiation monitor for mixed-field environments based on SRAM technology

    CERN Document Server

    Tsiligiannis, G; Bosio, A; Girard, P; Pravossoudovitch, S; Todri, A; Virazel, A; Mekki, J; Brugger, M; Wrobel, F; Saigne, F

    2014-01-01

    Instruments operating in particle accelerators and colliders are exposed to radiations that are composed of particles of different types and energies. Several of these instruments often embed devices that are not hardened against radiation effects. Thus, there is a strong need for mon- itoring the levels of radiation inside the mixed-field radiation areas, throughout different positions. Different metrics exist for measuring the radiation damage induced to electronic devices, such as the Total Ionizing Dose (TID), the Displacement Damage (DD) and of course the fluence of parti- cles for estimating the error rates of the electronic devices among other applications. In this paper, we propose an SRAM based monitor, that is used to define the fluence of High Energy Hadrons (HEH) by detecting Single Event Upsets in the memory array. We evaluated the device by testing it inside the H4IRRAD area of CERN, a test area that reproduces the radiation conditions inside the Large Hadron Collider (LHC) tunnel and its shield...

  4. Automatic national network of radiation environmental monitoring in Mexico

    International Nuclear Information System (INIS)

    Aguirre, Jaime; Delgado, Jose L.; Lopez, Manuel; Zertuche, Jorge V.

    2013-01-01

    The Direccion de Vigilancia Radiologica (DVR) of the Comision Nacional de Seguridad Nuclear y Salvaguardias (CNSNS) de Mexico, performs several function for environmental radiation monitoring. One of these functions is the permanent monitoring of the environmental gamma radiation. For this, it implemented the Red Nacional Automatica de Monitoreo Radiologico Ambiental (RENAMORA) - the National Automated Network for Environmental Radiation Monitoring,which currently comprises 60 detector probes for gamma radiation which with a programmable system that includes information technologies, data transmission and software can send the information in real time to a primary center of data located in the facilities of CNSNS. - When the data are received, the system performs the verification and extraction of the information organized in Tables and charts, and generates a report of environmental gamma radiation dose rate average for each of the probes and for each period of time determined bu CNSNS. The RENAMORA covers the main cities and allows to establish the bases of almost the entire country, as well as to warn about abnormal situations caused by incidents or natural events generated by human activities inside or outside the country which involves radioactive materials; paying special attention to main radiological sites, such as the surroundings of the Laguna Verde Nuclear Power Plants, research centers and the radioactive waste disposal sites

  5. Radiation monitoring in the NPP environment, control of radioactivity in NPP-environment system

    International Nuclear Information System (INIS)

    Egorov, Yu.A.

    1987-01-01

    Problems of radiation monitoring and control of the NPP-environment system (NPPES) are considered. Radiation control system at the NPP and in the environment provides for the control of the NPP, considered as the source of radioactive releases in the environment and for the environmental radiation climate control. It is shown, that the radiation control of the NPP-environment system must be based on the ecological normalization principles of the NPP environmental impacts. Ecological normalization should be individual for the NPP region of each ecosystem. The necessity to organize and conduct radiation ecological monitoring in the NPP regions is pointed out. Radiation ecological monitoring will provide for both environmental current radiation control and information for mathematical models, used in the NPPES radiation control

  6. Air gamma spectrometry in the radiation monitoring situation of Army of the Czech Republic

    International Nuclear Information System (INIS)

    Pavlik, J.; Sladek, P.

    2011-01-01

    In this poster authors deal with aerial radiation monitoring of territory of the Czech Republic. Army Radiation Monitoring Network (ARMS) are selected folder whirlwind Army of the Czech Republic (ACR), that are destined for the tasks of the National Radiation Monitoring Network (CRMS).

  7. Personnel radiation monitoring by thermoluminescence dosimetry (1995-96)

    International Nuclear Information System (INIS)

    Daw Mi Cho Cho; Daw Yi Yi Khin; Daw San San; U Maung Maung Tin; Daw Hla Hla Win

    2001-01-01

    Personnel radiation monitoring which is the dose assessment of individual doses from external radiation received by radiation workers has been carried out by Thermoluminescence Dosimetry system consisting of a Vinten Toledo TLD reader, LiF dosimeters and associated equipment. The exposed TLD dosimeters were measured by TLD reader and the dose evaluation and dose registration were done on personal computer. Due to the records of 1995-96, most of the radiation workers complied with the permissible dose recommended by IAEA and ICRP 60. (author)

  8. Neutron and gamma radiation levels analysis for 18 MeV cyclotron operation at IPEN-CNEN-SP

    Energy Technology Data Exchange (ETDEWEB)

    Silva, Paula P.N.; Fernandes, Ivani M.; Silva, Amanda J. da; Rodrigues, Demerval L.; Romero Filho, Christovam R., E-mail: ppsilva@ipen.b [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

    2011-07-01

    The Accelerator Cyclotron Facility provides activities that involve exposure to ionizing radiation, so it is necessary to establish a monitoring program that allows the dose control of the workers, based on the principles of the radiation protection. Besides the individual monitoring, the area monitoring is carried out aiming to evaluate the dose rates in areas that are occupied by workers during the execution of their tasks. This study aims to present the levels of neutron and gamma radiation results, obtained by monitoring the Accelerator Cyclotron Facility areas, during the Cyclone-18 operation. The study was based on data gathered from the area monitoring reports conducted by the radioprotection team in the years 2010 and 2011. To determine the dose rate, specific equipment was used. It was monitored 09 spots (from A to I), totalizing 280 and 205 measurements at each spot in the years 2010 and 2011, respectively. The 'B' spot showed the least influence for gamma and neutron radiation in both years. The spots with the highest neutron and gamma dose rates, in both years, were the 'E' and 'I' spots, respectively. With these results, we can say that the area monitoring is carrying out with its goal of preventing the doses that can be accumulated by the workers during the course of their work. (author)

  9. Signal Processing Device (SPD) for networked radiation monitoring system

    International Nuclear Information System (INIS)

    Dharmapurikar, A.; Bhattacharya, S.; Mukhopadhyay, P.K.; Sawhney, A.; Patil, R.K.

    2010-01-01

    A networked radiation and parameter monitoring system with three tier architecture is being developed. Signal Processing Device (SPD) is a second level sub-system node in the network. SPD is an embedded system which has multiple input channels and output communication interfaces. It acquires and processes data from first level parametric sensor devices, and sends to third level devices in response to request commands received from host. It also performs scheduled diagnostic operations and passes on the information to host. It supports inputs in the form of differential digital signals and analog voltage signals. SPD communicates with higher level devices over RS232/RS422/USB channels. The system has been designed with main requirements of minimal power consumption and harsh environment in radioactive plants. This paper discusses the hardware and software design details of SPD. (author)

  10. Quality management status of national radiation environmental monitoring network and strategy for development

    International Nuclear Information System (INIS)

    Huang Renjie; Zhang Rongsuo; Ni Shiying; Shen Gang

    2009-01-01

    During the period of 10th five-year plan, MEP has constructed a national radiation environmental monitoring network. In the running of the network, quality management on monitoring data is of vital importance. So all the members of the radiation environmental monitoring network are required to ensure the quality of monitoring method, equipment, reagent,quality of personnel, data processing and information management and so on. Thus the monitoring result would be typical and accuracy in science. The article introduced in detail the quality management status of the National Radiation Environmental Monitoring Network and put forward the strategy for development from the institutionalized and large-scale point of view of radioactive environmental monitoring work. (authors)

  11. Design of data acquisition, detection and monitoring radiation in robot tank

    International Nuclear Information System (INIS)

    Adhiyat Miftahudin Latif; Djiwo Harsono; Adi Abimanyu

    2016-01-01

    Research of radiation monitoring has been developing with needs, for example on industry. In this case, give a gap to research about radiation monitoring through data acquisition system. The purpose of this research is to produce radiation resource mapping data information that can be showed on web. The research method is processing data information that transmitting from robot tank by radio frequency. This consists of data position and voltage. Voltage information can be represented as radiation exposure. The result of this research is radiation resource mapping that showing on web. The contents of this web are data position and radiation exposure. Time computation that required from data reading to saving data on database is 1,001 second (s). (author)

  12. Immunological monitoring of the personnel at radiation hazardous facilities

    International Nuclear Information System (INIS)

    Kiselev, S.M.; Sokolnikov, M.E.; Lyss, L.V.; Ilyina, N.I.

    2017-01-01

    The study of possible mechanisms resulting in changes in the immune system after exposure to ionizing radiation is an area that has not been thoroughly evaluated during recent years. This article presents an overview of immunological monitoring studies of personnel from the radiation-hazardous factories that took place over the past 20 years in Russia. The methodology of these studies is based on: (1) the preclinical evaluation of immune status of workers whose occupation involves potential exposure to ionizing radiation; (2) selecting at risk groups according to the nature of immune deficiency manifestation; and (3) studying the changes of immune status of employees with regard to the potential effects of radiation exposure. The principal aim of these studies is accumulation of new data on the impact of radiation exposure on the human immune system and search for the relationship between the clinical manifestations of immune disorders and laboratory parameters of immunity to improve the monitoring system of the health status of the professional workers involved in radiation-hazardous industrial environments and the population living close to these facilities. (authors)

  13. Uzbekistan Radiation Portal Monitoring System

    International Nuclear Information System (INIS)

    Richardson, J; Knapp, R; Loshak, A; Yuldashev, B; Petrenko, V

    2005-01-01

    The work proposed in this presentation builds on the foundation set by the DTRA funded demonstration project begun in 2000 and completed in December of 2003. This previous work consisted of two phases whose overall objective was to install portal radiation monitors at four select ports-of-entry in Uzbekistan (Tashkent International Airport, Gisht-Kuprik (Kazakhstan border), Alat (Turkmenistan border), and Termez (Afghanistan border)) in order to demonstrate their effectiveness in preventing the illicit trafficking of nuclear materials. The objectives also included developing and demonstrating capabilities in the design, installation, operation, training, and maintenance of a radiation portal monitoring system. The system and demonstration project has proved successful in many ways. An effective working relationship among the Uzbekistan Customs Services, Uzbekistan Border Guards, and Uzbekistan Institute of Nuclear Physics has been developed. There has been unprecedented openness with the sharing of portal monitor data with Lawrence Livermore National Laboratory. The system has proved to be effective, with detection of illicit trafficking, and, at Alat, an arrest of three persons illegally transporting radioactive materials into Turkmenistan. The demonstration project has made Uzbekistan a model nonproliferation state in Central Asia and, with an expanded program, places them in a position to seal a likely transit route for illicit nuclear materials. These results will be described. In addition, this work is currently being expanded to include additional ports-of-entry in Uzbekistan. The process for deciding on which additional ports-of-entry to equip will also be described

  14. The RM-5000 system for radiation monitoring

    International Nuclear Information System (INIS)

    1997-01-01

    Eight models of radiation monitors can be assembled from independent modules for the agricultural firms, customs house, boundary transitions, for the control of transport and passenger flows and for prevention of the non-authorized moving of radioactive and fissionable materials. Two modules are a basis of the system - gamma radiation detector on the basis of plastic scintillator and neutrons detector on the basis of the proportional 3 He counters

  15. Ambient radiation levels in a microPET/CT research laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Sarmento, D.M.; Rodrigues, D.L.; Sanches, M.P.; Carneiro, J.C.G.G., E-mail: janetegc@ipen.br [Instituto de Pesquisas Energeticas e Nucleres (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

    2015-07-01

    This study focuses on initial radiological evaluation and the exposure situation related to the worker task in a micro-positron emission tomography/computed tomography laboratory (microPET/CT). Selected and calibrated thermoluminescent dosimeters, TLD, of CaSO{sub 4}:Dy were used to measure room radiation levels. The detectors were placed in several selected points inside the microPET/CT laboratory and adjacent rooms. In addition, the occupationally exposed workers were monthly evaluated for external and internal exposures. In none of the selected points the dose values exceeded the radiation dose limit established for supervised area, as well as the values obtained in individual monitoring. (author)

  16. Ambient radiation levels in a microPET/CT research laboratory

    International Nuclear Information System (INIS)

    Sarmento, D.M.; Rodrigues, D.L.; Sanches, M.P.; Carneiro, J.C.G.G.

    2015-01-01

    This study focuses on initial radiological evaluation and the exposure situation related to the worker task in a micro-positron emission tomography/computed tomography laboratory (microPET/CT). Selected and calibrated thermoluminescent dosimeters, TLD, of CaSO 4 :Dy were used to measure room radiation levels. The detectors were placed in several selected points inside the microPET/CT laboratory and adjacent rooms. In addition, the occupationally exposed workers were monthly evaluated for external and internal exposures. In none of the selected points the dose values exceeded the radiation dose limit established for supervised area, as well as the values obtained in individual monitoring. (author)

  17. 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

  18. Determination of radiation direction in environmental monitoring

    International Nuclear Information System (INIS)

    Campos, Vicente de Paulo de; Moura, Eduardo S.; Rocha, Felicia D.G.; Manzoli, Jose Eduardo

    2009-01-01

    The assessment of environmental exposure has been performed in Brazil using the thermoluminescence technique at Thermoluminescence Dosimetry Laboratory (LDT), at Nuclear and Energetic Research Institute (IPEN/CNEN-SP). To carry out these measurements, several thermoluminescent dosimeters (TLD's) were used to measure the expose. In this procedure, very few information of direction where the radiation came from is available. A vague supposition about the direction from where the radiation came from could be inferred only by evaluation of multiple dosimeters displaced at entire region of monitoring, but this demand to much effort or sometimes become impractical for certain situations. In this work, a single device is used to provide information about the direction from where the radiation came through. This device is called directional dosimeter (DD). Using more than one DD it is possible to reduce the uncertainty of the measurements and determine the radiation source position. The DD basically consists of a regular solid with high effective atomic number, where one TLD is positioned at each face. The DD allows evaluating the environmental exposure and the direction of the radiation by a simple vector sum. At each face of the DD, it is associated an orthogonal vector, and modulus of this vector represents the correspond exposure measured by the TLD. The direction of the radiation source is the sum of these faces vectors. The prototype used in this work was a lead cube with six TLDs of CaSO 4 :Dy/Teflon. The TLDs have high sensibility and are already used in area, environmental and personal monitoring. The measurements had shown the correct environmental exposure and a good indication of the radiation direction. (author)

  19. Radiation monitoring strategy in nuclear or radiological emergencies

    International Nuclear Information System (INIS)

    Lahtinen, J.

    2003-01-01

    Full text: Radiation measurements provide indispensable data needed for the management of a nuclear or radiological emergency. There must exist pre-prepared emergency monitoring strategies, with accompanying procedures and methods, that help the authorities to perform measurements efficiently and, consequently, to evaluate the radiological situation correctly and to carry out proper countermeasures on time. However, defining a realistic yet comprehensive radiation monitoring strategy for emergencies is far from being an easy task. The very concept of 'emergency monitoring strategy' should be understood in a broad sense. In an ideal case, a strategy has interfaces with all related emergency and information exchange arrangements and agreements both at the national and international level. It covers all activities from the recognition of a potential hazard situation to environmental sampling performed during the late phases of an accident. It integrates routine-monitoring practices with the special requirements set by emergency monitoring and the use of fixed monitoring stations with that of mobile measurement teams. It includes elements for gathering, analyzing, transmitting and presenting data, as well as for combining them with different kinds of forecasts. It also takes into account the various intrinsic characteristics of possible threat scenarios and contains options for adapting measuring activities according to prevailing environmental conditions. Furthermore, a strategy must have relevant links to the social and economical realities and to the primary interests of different stakeholders. In order to assist individual countries in establishing national strategies, international organisations (IAEA, OECD/NEA, EU) have published basic guidelines for emergency response and radiation measurements. Nuclear accidents, especially the Chernobyl case with its large-scale environmental consequences, and other kinds of shocking events (like the one on September 11, 2001

  20. Calibration of radiation monitors at nuclear power plants

    International Nuclear Information System (INIS)

    Boudreau, L.; Miller, A.D.; Naughton, M.D.

    1994-03-01

    This work was performed to provide guidance to the utilities in the primary and secondary calibration of the radiation monitoring systems (RMS) installed in nuclear power plants. These systems are installed in nuclear power plants to monitor ongoing processes, identify changing radiation fields, predict and limit personnel radiation exposures and measure and control discharge of radioactive materials to the environment. RMS are checked and calibrated on a continuing basis to ensure their precision and accuracy. This report discusses various approaches towards primary and secondary calibrations of the RMS equipment in light of accepted practices at typical power plants and recent interpretations of regulatory guidance. Detailed calibration techniques and overall system responses, trends, and practices are discussed. Industry, utility, and regulatory sources were contacted to create an overall consensus of the most reasonable approaches to optimizing the performance of this equipment

  1. Systemic effects of ionizing radiation at the proteome and metabolome levels in the blood of cancer patients treated with radiotherapy: the influence of inflammation and radiation toxicity.

    Science.gov (United States)

    Jelonek, Karol; Pietrowska, Monika; Widlak, Piotr

    2017-07-01

    Blood is the most common replacement tissue used to study systemic responses of organisms to different types of pathological conditions and environmental insults. Local irradiation during cancer radiotherapy induces whole body responses that can be observed at the blood proteome and metabolome levels. Hence, comparative blood proteomics and metabolomics are emerging approaches used in the discovery of radiation biomarkers. These techniques enable the simultaneous measurement of hundreds of molecules and the identification of sets of components that can discriminate different physiological states of the human body. Radiation-induced changes are affected by the dose and volume of irradiated tissues; hence, the molecular composition of blood is a hypothetical source of biomarkers for dose assessment and the prediction and monitoring of systemic responses to radiation. This review aims to provide a comprehensive overview on the available evidence regarding molecular responses to ionizing radiation detected at the level of the human blood proteome and metabolome. It focuses on patients exposed to radiation during cancer radiotherapy and emphasizes effects related to radiation-induced toxicity and inflammation. Systemic responses to radiation detected at the blood proteome and metabolome levels are primarily related to the intensity of radiation-induced toxicity, including inflammatory responses. Thus, several inflammation-associated molecules can be used to monitor or even predict radiation-induced toxicity. However, these abundant molecular features have a rather limited applicability as universal biomarkers for dose assessment, reflecting the individual predisposition of the immune system and tissue-specific mechanisms involved in radiation-induced damage.

  2. Status of contamination monitoring in radiation activities of National Atomic Energy Agency (NAEA) in Indonesia

    Energy Technology Data Exchange (ETDEWEB)

    Suhariyono, Gatot [National Atomic Energy Agency, Jakarta (Indonesia)

    1997-06-01

    National Atomic Energy Agency (NAEA) or Badan Tenaga Atom Nasional (BATAN) is a non departmental governmental agency, headed by a Director General who is directly responsible to the President. Center for Standardization and Radiation Safety Research (CSRSR) is one of the research centers within the deputy for the assessment of nuclear science and technology of the NAEA. The main task of the CSRSR is to implement research and development program, development and services in the field of radiation safety, standardization, dosimetry, radiation health as well as the application of nuclear techniques in medicine, according to the policy confirmed by the director general of BATAN. Task of radiation protection division is to set up programs and to develop radiation protection, personal monitoring system and radiation level of the working areas and their surroundings as well as dose limitation system, to carry out technical up grading of radiation protection officials skill and to help coping with radiation accident. The key factor on contamination monitoring is to reduce human error and mechanical failures. These problems can be achieved to the highest degree by developing knowledge and skill of staffs via trainings or courses on contamination and decontamination, so that they are hoped to become trained and qualified staffs. (G.K.)

  3. Ionising radiation and risk of death from leukaemia and lymphoma in radiation-monitored workers (INWORKS)

    Energy Technology Data Exchange (ETDEWEB)

    Lorenz, Bernd

    2015-07-01

    Since July 2015 the study ''ionising radiation and risk of death from leukaemia and lymphoma in radiation-monitored workers (INWORKS) - an international cohort study'' is available. INWORKS comprised data from 300.000 occupational exposed and dosimetric monitored persons from France, USA and UK. The contribution is a critical discussion of this study with respect to the conclusion of a strong evidence of positive associations between protracted low-dose irradiation exposure and leukemia.

  4. Gamma-ray detectors for intelligent, hand-held radiation monitors

    International Nuclear Information System (INIS)

    Fehlau, P.E.

    1983-01-01

    Small radiation detectors based on HgI 2 , bismuth germanate (BGO), plastic, or NaI(Tl) detector materials were evaluated for use in small, lighweight radiation monitors. The two denser materials, HgI 2 and BGO, had poor resolution at low-energy and thus performed less well than NaI(Tl) in detecting low-energy gamma rays from bare, enriched uranium. The plastic scintillator, a Compton recoil detector, also performed less well at low gamma-ray energy. Two small NaI(Tl) detectors were suitable for detecting bare uranium and sheilded plutonium. One became part of a new lightweight hand-held monitor and the other found uses as a pole-mounted detector for monitoring hard-to-reach locations

  5. Radiation Damage Monitoring in the ATLAS Pixel Detector

    CERN Document Server

    Seidel, S

    2013-01-01

    We describe the implementation of radiation damage monitoring using measurement of leakage current in the ATLAS silicon pixel sensors. The dependence of the leakage current upon the integrated luminosity is presented. The measurement of the radiation damage corresponding to integrated luminosity 5.6 fb$^{-1}$ is presented along with a comparison to the theoretical model.

  6. INSTALLATION OF A POST-ACCIDENT CONFINEMENT HIGH-LEVEL RADIATION MONITORING SYSTEM IN THE KOLA NUCLEAR POWER STATION (UNIT 2) IN RUSSIA

    Energy Technology Data Exchange (ETDEWEB)

    GREENE,G.A.; GUPPY,J.G.

    1998-09-01

    This is the final report on the INSP project entitled, ``Post-Accident Confinement High-Level Radiation Monitoring System'' conducted by BNL under the authorization of Project Work Plan WBS 1.2.2.6 (Attachment 1). This project was initiated in February 1993 to assist the Russians in reducing risks associated with the continued operation of older Soviet-designed nuclear power plants, specifically the Kola VVER-440/230 Unit 2, through improved accident detection capability, specifically by the installation of a dual train high-level radiation detection system in the confinement of Unit 2 of the Kola NPP. The major technical objective of this project was to provide, install and make operational the necessary hardware inside the confinement of the Kola NPP Unit 2 to provide early and reliable warning of the release of radionuclides from the reactor into the confinement air space as an indication of the occurrence of a severe accident at the plant. In addition, it was intended to provide hands-on experience and training to the Russian plant workers in the installation, operation, calibration and maintenance of the equipment in order that they may use the equipment without continued US assistance as an effective measure to improve reactor safety at the plant.

  7. INSTALLATION OF A POST-ACCIDENT CONFINEMENT HIGH-LEVEL RADIATION MONITORING SYSTEM IN THE KOLA NUCLEAR POWER STATION (UNIT 2) IN RUSSIA

    International Nuclear Information System (INIS)

    GREENE, G.A.; GUPPY, J.G.

    1998-01-01

    This is the final report on the INSP project entitled, ''Post-Accident Confinement High-Level Radiation Monitoring System'' conducted by BNL under the authorization of Project Work Plan WBS 1.2.2.6 (Attachment 1). This project was initiated in February 1993 to assist the Russians in reducing risks associated with the continued operation of older Soviet-designed nuclear power plants, specifically the Kola VVER-440/230 Unit 2, through improved accident detection capability, specifically by the installation of a dual train high-level radiation detection system in the confinement of Unit 2 of the Kola NPP. The major technical objective of this project was to provide, install and make operational the necessary hardware inside the confinement of the Kola NPP Unit 2 to provide early and reliable warning of the release of radionuclides from the reactor into the confinement air space as an indication of the occurrence of a severe accident at the plant. In addition, it was intended to provide hands-on experience and training to the Russian plant workers in the installation, operation, calibration and maintenance of the equipment in order that they may use the equipment without continued US assistance as an effective measure to improve reactor safety at the plant

  8. Real Time Environmental Radiation Monitoring System in the Philippines

    International Nuclear Information System (INIS)

    Garcia, Teofilo Y.

    2015-01-01

    The widespread release of radioactive materials caused by the Fukushima Daiichi Nuclear Power Plant Accident that occurred on 11 March 2011 raised concerns on the environmental radiation monitoring Presently, the Philippine Nuclear Research Institute (PNRI) can only perform limited incident. Country-wide radiation measurements by carrying out field-works in the different provinces of the country. This is due to limitation in the availability of appropriate equipment to carry-out the task of conducting radiation measurements, especially in remote and hart to access areas of the country. Although no nuclear reactor is currently operating in the Philippines, it is situated in a region surrounded by neighboring countries with several existing or planned nuclear power plants. While nuclear power has tremendous benefits in meeting the electricity needs of growing populations, and does not have the adverse environmental effects associated with burning of fossil fuels, there are potential risks from releases of radio nuclides into the environment. The PNRI, through the support of the International Atomic Energy Agency (IAEA), is establishing an on-line environmental radiation monitoring system that can provide real-time environmental during emergencies that lead to extensive spread of radioactive materials, such as nuclear power plant accidents, an on-line radiation monitoring system will enable the immediate detection of radiological emergencies affecting the country and will provide important information of authorities for appropriate emergency response. (author)

  9. Radiation exposure control by estimation of multiplication factors for online remote radiation monitoring systems at vitrification plant

    International Nuclear Information System (INIS)

    Deokar, U.V.; Kulkarni, V.V.; Khot, A.R.; Mathew, P.; Kamlesh; Purohit, R.G.; Sarkar, P.K.

    2012-01-01

    Vitrification Plant is commissioned for vitrification of high level liquid waste (HLW) generated in nuclear fuel cycle operations by using Joule Heated Ceramic Melter first time in India. Exposure control is a major concern in operating plant. Therefore in addition to installed monitors, we have developed online remote radiation monitoring system to minimize number of entries in amber areas and to reduce the exposure to the surveyor and operator. This also helped in volume reduction of secondary waste. The reliability and accuracy of the online monitoring system is confirmed with actual measurements and by theoretical shielding calculations. The multiplication factors were estimated for remote on line monitoring of Melter Off Gas (MOG) filter, Hood filter, three exhaust filter banks, and over-pack monitoring. This paper summarizes - how the online remote monitoring system helped in saving of 128.52 person-mSv collective dose (14.28% of budgeted dose). The system also helped in the reduction of 2.6 m 3 of Cat-I waste. Our online remote monitoring system has helped the plant management to plan in advance for replacement of these filters, which resulted in considerable saving in collective dose and secondary waste

  10. Radiological interference from personal articles in occupational radiation monitoring

    International Nuclear Information System (INIS)

    Krishnakumar, P.; Jayan, M.P; Pawar, V.J; Patil, S.L; Selvamani, N.; Vedram; Sureshkumar, M.K.; Chinnaesakki, S.

    2016-01-01

    This paper discusses the presence of radioactivity in some personal articles worn on sacred thread and the related difficulties faced by health physicists during occupational radiation monitoring in nuclear facilities. In an incident, the portal monitor installed at the exit gate of a nuclear facility indicated contamination on self of a radiation worker while passing through it. The worker was therefore, subjected to thorough check for external contamination by the plant health physicist, using a pan-cake contamination monitor. All the clothing of the person was also checked for contamination. On further detailed examination, a dark brownish personal article hanging on a sacred thread from his neck was found to be the source of contamination. This presentation aims at giving information to the health physics community on the possibility of such interferences during personal monitoring in nuclear facilities

  11. Automated TLD system for gamma radiation monitoring

    International Nuclear Information System (INIS)

    Nyberg, P.C.; Ott, J.D.; Edmonds, C.M.; Hopper, J.L.

    1979-01-01

    A gamma radiation monitoring system utilizing a commercially available TLD reader and unique microcomputer control has been built to assess the external radiation exposure to the resident population near a nuclear weapons testing facility. Maximum use of the microcomputer was made to increase the efficiency of data acquisition, transmission, and preparation, and to reduce operational costs. The system was tested for conformance with an applicable national standard for TLD's used in environmental measurements

  12. Evaluation of emplacement sensors for detecting radiation and volatile organic compounds and for long-term monitoring access tubes for the BWCS

    International Nuclear Information System (INIS)

    Lord, D.L.; Averill, R.H.

    1997-10-01

    This document evaluates sensors for detecting contaminants in the excavated waste generated by the Buried Waste Containment System (BWCS). The Barrier Placement Machine (BPM) removes spoils from under a landfill or plume and places it on a conveyor belt on the left and right sides of the BPM. The spoils will travel down the conveyor belts past assay monitors and be deposited on top of the site being worked. The belts are 5 ft wide and transport approximately 15 ft3 /minute of spoils. This corresponds to a 10 ft per hour BPM advance rate. With a 2 in. spoils height the belt speed would be 3.6 in. per second. The spoils being removed are expected to be open-quotes cleanclose quotes (no radiation or volatile organics above background levels). To ensure that the equipment is not digging through a contaminated area, assay equipment will monitor the spoils for mg radiation and volatile organic compounds (VOCs). The radiation monitors will check for gross radiation indication. Upon detection of radiation levels above a predetermined setpoint, further evaluation will be performed to determine the isotopes present and their quantity. This will require hand held monitors and a remote monitoring station. Simultaneously, VOC monitors will monitor for predetermined volatile/semi-volatile organic compounds. A Fourier-Transform Infrared Spectrometer (FTIR) monitor is recommended for this operation. Specific site requirements and regulations will determine setpoints and operation scenarios. If VOCs are detected, the data will be collected and recorded. A flat panel display will be mounted in the BPM operator''s cab showing the radio nuclide and VOC monitoring data. As the BPM advances, a 3-in. diameter PVC tube will be placed on the bottom of the barrier slot in front of the 12 to 16-in. containment barrier being emplaced

  13. Ionizing radiation

    International Nuclear Information System (INIS)

    Dennis, J.A.

    1982-01-01

    The subject is discussed under the headings: characteristics of ionizing radiations; biological effects; comparison of radiation and other industrial risks; principles of protection; cost-benefit analysis; dose limits; the control and monitoring of radiation; reference levels; emergency reference levels. (U.K.)

  14. The central monitoring station of Indian Environmental Radiation Monitoring Network (IERMON): the architecture and functions

    International Nuclear Information System (INIS)

    Garg, Saurabh; Ratheesh, M.P.; Mukundan, T.; Patel, M.D.; Nair, C.K.G.; Puranik, V.D.

    2010-01-01

    The Indian Environmental Radiation Monitoring Network (IERMON) is being established across the country by the Bhabha Atomic Research Centre, Mumbai. The network consists of stations with automated systems for environmental radiation monitoring with online data communication facility. Currently about 100 stations are operational and additional 500 stations are expected to be installed by March, 2012. The network is established with different objectives, the main objective being the detection and reporting of any nuclear emergency anywhere in the country. The central monitoring station of the network is established in Mumbai. This paper describes the architecture and functions of IERMON Central Station. The Central Station consists of server room for online data collection from remote stations and maintenance of databases for various applications; central monitoring room for user interaction with database and IERMON website maintenance and development room for the development of new applications. The functions of IERMON Central Station include detection and reporting of nuclear emergency, maintenance of remote stations, enhancement of public awareness on environmental radiation through public display systems and website, etc. The details on system layout and data protocols can be found in the paper. (author)

  15. Radionuclide dispersion calculation in environmental radiation monitoring system of the PAKS NPP

    International Nuclear Information System (INIS)

    Deme, S.; Janosy, J. S.; Lang, E.; Szabo, I. C.

    2003-01-01

    The new Environmental Radiation Monitoring System of the Paks NPP in Hungary consists of three radiation release measurement posts (placed into the two ventilation stacks of the four units and into the ventilation stack of the spent fuel intermediate storage building), 9 radiation monitoring stations and 11 gamma-radiation measurement posts placed more or less evenly around the plant. The basic goal of the Environmental Radiation Monitoring System is to provide complex and reliable information about the releases in all operating modes to facilitate the adequate estimation of the situation and to promote the decision making. Thanks to the astonishing development in the digital technology and to the state-of-the-art, up-to-date measurement techniques, a new level of confidence can be reached. Unpredictable radioactive leakage of the containment can be detected and the radiological situation of a relatively large area can be calculated and predicted. A very reliable system can be constructed withstanding earthquake and protected against single failure. Based on reliable and detailed measurement data, advanced simulation methodology and well-designed graphical user interface, an easy-to-use operator advisory system can be created to help the decision making in the very first and most difficult period of a nuclear accident. It is very important that the same system is used with the same features during the normal operation of the nuclear power plant, too; this means that the operators are able to get the necessary 'hands-on' training in order to be able to use the system during extreme stress and very unusual situations, too. Shaping the system in close cooperation with plant engineers and operators is indispensable in order to achieve the aforementioned goals. (authors)

  16. Radiation exposure of non-monitored hospital personnel

    International Nuclear Information System (INIS)

    Renaud, L.; Blanchette, J.; Galand, C.

    1993-02-01

    This project investigated the radiological impact of nuclear medicine patients on non-monitored personnel in hospital environments. More than 800 workers and 135 specific areas in three Quebec hospitals were surveyed daily during a six-month period with Geiger counters, TLD badges, and TLD chips. Average dose rates of up to 2.2 μSv/h were measured in some waiting areas. The radiation level of a nursing unit is a direct function of the ambulatory radioactivity carried by nuclear medicine patients. Three percent of the workers surveyed had a work-related dose in excess of 0.3 mSv/6 months (maximum 1.4 mSv/6 months). Over 88 percent were in the range between local background and 0.3 mSv/6 months. Less than 4 percent belong to groups of workers who were exposed to a level indistinguishable from background. Thus many workers surveyed in this study receive a work-related dose similar to those of medical workers monitored by Health and Welfare Canada. The average annual dose for these workers was 104 person-millisieverts. The authors recommend: better management of radioactive patients; the provision of information and education for all hospital workers having regular contact with radioactive patients; and the facilitation of the identification of nuclear medicine patients within the hospital environment. (28 tabs., 23 figs.)

  17. Statistical data processing with automatic system for environmental radiation monitoring

    International Nuclear Information System (INIS)

    Zarkh, V.G.; Ostroglyadov, S.V.

    1986-01-01

    Practice of statistical data processing for radiation monitoring is exemplified, and some results obtained are presented. Experience in practical application of mathematical statistics methods for radiation monitoring data processing allowed to develop a concrete algorithm of statistical processing realized in M-6000 minicomputer. The suggested algorithm by its content is divided into 3 parts: parametrical data processing and hypotheses test, pair and multiple correlation analysis. Statistical processing programms are in a dialogue operation. The above algorithm was used to process observed data over radioactive waste disposal control region. Results of surface waters monitoring processing are presented

  18. Transition in occupational radiation exposure monitoring methods in diagnostic and interventional radiology

    International Nuclear Information System (INIS)

    Loennroth, N.; Hirvonen-Kari, M.; Timonen, M.; Savolainen, S.; Kortesniemi, M.

    2008-01-01

    Radiation exposure monitoring is a traditional keystone of occupational radiation safety measures in medical imaging. The aim of this study was to review the data on occupational exposures in a large central university hospital radiology organisation and propose changes in the radiation worker categories and methods of exposure monitoring. An additional objective was to evaluate the development of electronic personal dosimeters and their potential in the digitised radiology environment. The personal equivalent dose of 267 radiation workers (116 radiologists and 151 radiographers) was monitored using personal dosimeters during the years 2006-2010. Accumulated exposure monitoring results exceeding the registration threshold were observed in the personal dosimeters of 73 workers (59 radiologists' doses ranged from 0.1 to 45.1 mSv; 14 radiographers' doses ranged from 0.1 to 1.3 mSv). The accumulated personal equivalent doses are generally very small, only a few angiography radiologists have doses >10 mSv per 5 y. The typical effective doses are -1 and the highest value was 0.3 mSv (single interventional radiologist). A revised categorisation of radiation workers based on the working profile of the radiologist and observed accumulated doses is justified. Occupational monitoring can be implemented mostly with group dosimeters. An active real-time dosimetry system is warranted to support radiation protection strategy where optimisation aspects, including improving working methods, are essential. (authors)

  19. Radiation control monitoring system on the High Temperature Engineering Test Reactor

    International Nuclear Information System (INIS)

    Minowa, Y.; Nakazawa, T.; Sato, K.; Kikuchi, H.; Nomura, T.

    1999-01-01

    Radiation control monitoring system of the HTTR is divided into three subsystems; exhaust monitoring equipment, room air monitoring equipment, dose equivalent rate monitoring equipment. The exhaust monitoring equipment consists of exhaust gas monitors, exhaust dust monitors, and a tritium and carbon sampling device at normal operation of the reactor. Accident gas monitors are also provided for the emergency. The tritium and carbon sampling device uses cupper oxide as a oxidizer, and ethanol amine as a sampling materials which collects continuously tritium and carbon in dust during about one month and is measured by a liquid scintillation counter. The accident gas monitors consist of two channels, for a low and a high range. The high range-gas monitor consists of two ionization chambers: one encloses argon gas and the other encloses xenon gas. Average energy of various gamma-rays, hence, accident exposure dose of the public can be estimated with the comparison of the sensitivity of two kinds of ionization chambers. The dose equivalent rate monitoring equipment consists of silicon semiconductor detectors for gamma-ray, a ionization chamber for gamma-ray, a BF 3 counter for neutron, and accident area monitors which are located in the reactor container. The message of 'check dose !' or 'temporary evacuation !' can be send to the workers in the reactor with a light and a sound. A computer system collects the radiation monitoring data every 10 sec cycle and accumulates them in a server computer. The leakage and the dispersion of helium gas must be taken into account on the radiation control monitoring system of the HTTR. (Suetake, M.)

  20. The introduction of radiation monitor produced by several nuclear instrument factories

    International Nuclear Information System (INIS)

    Yu Liying

    2005-01-01

    The paper introduce some radiation monitor products of several nuclear instrument factories include Xi'an Nuclear Instrument Factory, MGP Instruments Inc, and Canberra Industries Inc. The introduction aspects include the range, configuration, and application of products. So, the paper is reference for the designer with responsibility for radiation monitoring system of new nuclear project. (authors)

  1. SPACE RADIATION ENVIRONMENT MONITORED BY KITSAT-1 AND KITSAT-2

    Directory of Open Access Journals (Sweden)

    Y. H. Shin

    1996-06-01

    Full Text Available The results of space radiation experiments carried out on board the first two Korean technology demonstration microsatellites are presented in this paper. The first satellite, KITSAT-1, launched in August 1992, carries a radiation monitoring payload called cosmic ray experiment(CRE for characterizing the low-earth orbit(LEO radiation environment. The CRE consists of two sub-systems: the cosmic particle experiment (CPE and the total dose experiment(TDE. In addition, single event upset(SEUrates of the program memory and the RAM disk are also monitored. The second satellite, KITSAT-2, launched in September 1993, carries a newly developed 32-bit on-board computer(OBC, KASCOM(KAIST satellite computer in addition to OBC186. SEUs ocurred in the KASCOM, as well as in the program memory and RAM disk memory, have been monitored since the beginning of the satellite operation. These two satellites, which are very similar in structures but different in orbits, provide a unique opportunity to study the effects of the radiation environment characterized by the orbit.

  2. Basic requirements of dosemeter systems for individual monitoring of external radiation

    International Nuclear Information System (INIS)

    Boehm, J.; Ambrosi, P.

    1985-01-01

    A plea is made for detailed detector independent requirements for dosemeter systems for individual monitoring of external radiation. These requirements should have their origin in the fundamental aspects and concepts of radiation protection for workers, and should be something like a translation of the general principles of individual monitoring into a language easily understandable by producers and users. This work comprises a summary of the general objectives of individual monitoring and discussion of some relevant requirements for dosemeter systems. (orig.) [de

  3. External radiation monitoring in TAPS and RAPS environs (1980-81) using TLD

    International Nuclear Information System (INIS)

    Basu, A.S.; Nambi, K.S.V.; Sunta, C.M.

    1983-01-01

    Results of environmental external radiation monitoring using quarterly integrated TLD measurements are presented for environments of the Tarapur Atomic Power Station (TAPS) and the Rajasthan Atomic Power Station (RAPS) for the two year monitoring period (1980-81). The data fit into the unimodal log-normal distribution except for locations where gaseous radioactivity escaping from the plant makes a significant contribution. The average natural radiation background in TAPS and RAPS environment is estimated to be 59.6 +- 4.7 mR yr -1 and 65.1 +- 9.8 mR yr -1 respectively. Contribution from the plant superimposed over the natural level leads frequently to bi-normal distribution. The effect of stack-released gaseous radioactivity is seen in locations within 1.6 km of TAPS: for example Ghivoli village registered an excess of 9.3 mR yr -1 over the natural background. The quarterly background values indicate minor temporal and spatial variations which can be attributed to changes in natural as well as stack released radioactivity. (author)

  4. High power beam profile monitor with optical transition radiation

    International Nuclear Information System (INIS)

    Denard, J.C.; Piot, P.; Capek, K.; Feldl, E.

    1997-01-01

    A simple monitor has been built to measure the profile of the high power beam (800 kW) delivered by the CEBAF accelerator at Jefferson Lab. The monitor uses the optical part of the forward transition radiation emitted from a thin carbon foil. The small beam size to be measured, about 100 μm, is challenging not only for the power density involved but also for the resolution the instrument must achieve. An important part of the beam instrumentation community believes the radiation being emitted into a cone of characteristic angle 1/γ is originated from a region of transverse dimension roughly λγ; thus the apparent size of the source of transition radiation would become very large for highly relativistic particles. This monitor measures 100 μm beam sizes that are much smaller than the 3.2 mm λγ limit; it confirms the statement of Rule and Fiorito that optical transition radiation can be used to image small beams at high energy. The present paper describes the instrument and its performance. The authors tested the foil in, up to 180 μA of CW beam without causing noticeable beam loss, even at 800 MeV, the lowest CEBAF energy

  5. Radiation exposure monitoring and control in front-end fuel cycle facilities

    International Nuclear Information System (INIS)

    Khan, A.H.

    2003-01-01

    The front end nuclear fuel cycle facilities presently operational in India are the mining and processing of beach mineral sands along the southern coast of Kerala, Tamilnadu and Orissa, mining and processing of uranium ore in Singhbhum-East in Jharkhand and refining and fuel fabrication at Hyderabad and Trombay. Dedicated Health Physics Units set up at each site regularly carry out in-plant and personnel monitoring to ensure safe working conditions and evaluate radiation exposure of workers and advise appropriate control measures. External gamma radiation, radon, thoron, their progeny and airborne long-lived activity due to radioactive dust are monitored. Personal dosimeters are also issued to workers. The total radiation exposure of workers from external and internal sources is evaluated from the plant and personal monitoring data. Provision of adequate ventilation, control of dust and spillage of active solutions, prompt decontamination, use of personal protective appliances and worker education are the key factors in keeping the doses to the workers well within the regulatory limits. It has been observed that the total radiation dose to workers has been well below 20 mSv.y - 1 at all stages of operations. The monitoring methodologies and summary of radiation exposure data for different facilities during the last few years are presented in the paper. (author)

  6. Radiation doses in alternative commercial high-level waste management systems

    International Nuclear Information System (INIS)

    Schneider, K.J.; Pelto, P.J.; Lavender, J.C.; Daling, P.M.; Fecht, B.A.

    1986-01-01

    In the commercial high-level waste management system, potential changes are being considered that will augment the benefits of an integral monitored retrievable storage (MRS) facility. The US Department of Energy (DOE) has recognized that alternative options could be implemented in the authorized waste management system (i.e., without an integral MRS facility) to potentially achieve some of the same beneficial effects of the integral MRS system. This paper summarizes those DOE-sponsored analyses related to radiation doses resulting from changes in the waste management system. This report presents generic analyses of aggregated radiation dose impacts to the public and occupational workers, of nine postulated changes in the operation of a spent-fuel management system without an MRS facility

  7. Operational intervention levels and related requirements on radiation monitoring during pre-release / release phase of an accident

    International Nuclear Information System (INIS)

    Carny, P.; Cabanekova, H

    2003-01-01

    In this paper authors discusses required outputs of emergency radiological monitoring in various phases of an accident and rationale of these requirements. In various phases of an accident various intervention levels are important and consequently various radiological quantities should be preferably measured. Distinguished tasks or aims of monitoring in different phases of accident have strong influence on methods of monitoring, instrumentation and capabilities of monitoring groups. Required tasks and outputs of monitoring are discussed

  8. Assessment of environmental gamma radiation levels in the environs of Narora Atomic Power Station (NAPS)

    International Nuclear Information System (INIS)

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

    2011-01-01

    As a part of the assessment of the environmental impact of the Indian nuclear power programme, radiation surveys are being carried out on continuous basis in the environs of all the nuclear facilities in India using Thermoluminescent Dosimeters. This paper discusses the environmental gamma radiation levels based on the analysis of data generated for year 1989-2009 at twenty-eight locations currently being monitored in and around the environs of NAPS using passive dosimeter. Of these, six are within the exclusion zone (1.6 km) while the remaining twenty two locations are spread over an aerial distance of twenty six km from reactor stack. The annual background gamma levels for NAPS site beyond 1.6 km exclusion zone based on twenty-two monitoring locations are evaluated and seen to be 1.20 ± 0.15 mGy/a. This is comparable with earlier reported pre-operational value 1.24 ± 0.26 mGy/a. From this it can be said that the reactor operations have not contributed to any increase in the gamma radiation levels in the environs of the NAPS region. (author)

  9. A micro-controller based palm-size radiation monitor

    International Nuclear Information System (INIS)

    Bhingare, R.R.; Bajaj, K.C.; Kannan, S.

    2001-01-01

    A micro-controller based, palm-size radiation monitor, PALMRAD, using a silicon P-N junction diode as a detector has been developed. It is useful for radiation protection monitoring during radiation emergency as well as radioactive source loading operations. Some of the features of PALMRAD developed are the use of a semiconductor diode as the detector, simultaneous display of integrated dose and dose rate on a 16-digit alpha numeric LCD display, measurable integrated dose range from 1 μSv to 5000 μSv and dose rate range from 1 mSv/h to 1,000 mSv/h, RS 232C serial interface for connection to a Personal Computer,-storage of integrated dose and dose rate readings, recall of stored readings on LCD display, presentable integrated dose alarm from 1 μSv to 5000 μSv and dose rate from 1 mSv/h to 1,000 mSv/h, battery status and memory status check during measurement, LCD display with LED back-lighting, etc. (author)

  10. Radiation Level Changes at RAM Package Surfaces

    Energy Technology Data Exchange (ETDEWEB)

    Opperman, Erich [Washington Savannah River Company; Hawk, Mark B [ORNL; Kapoor, Ashok [U.S. Department of Energy, Office of Packaging and Transportation; Natali, Ronald [R. B. Natali Consulting, Inc.

    2010-01-01

    This paper will explore design considerations required to meet the regulations that limit radiation level variations at external surfaces of radioactive material (RAM) packages. The radiation level requirements at package surfaces (e.g. TS-R-1 paragraphs 531 and 646) invoke not only maximum radiation levels, but also strict limits on the allowable increase in the radiation level during transport. This paper will explore the regulatory requirements by quantifying the amount of near surface movement and/or payload shifting that results in a 20% increase in the radiation level at the package surface. Typical IP-2, IP-3, Type A and Type B packaging and source geometries will be illustrated. Variations in surface radiation levels are typically the result of changes in the geometry of the surface due to an impact, puncture or crush event, or shifting and settling of radioactive contents.

  11. Sensitivity of radiation monitoring systems in Manila Ports in detecting contamination in foodstuff shipments

    International Nuclear Information System (INIS)

    Romallosa, Kristine Marie D.; Caseria, Estrella S.; Piquero, Ronald E.; Agustin, Jan Aldrich A.

    2011-01-01

    During the Fukushima Nuclear Power Plant accident in Japan, one of the Philippines' measures to protect the public from radiological hazards of the accident is by monitoring agricultural and food imports for radioactive contamination. In this study, the sensitivity of the mobile Radiation Monitoring System (RM) in Manila Ports in detecting contamination in incoming foodstuff shipments was determined. Large volume synthetic 137 Cs reference sources were used to determine the minimum detectable concentration (MDC) of the RMS. The reference sources have radioactivity concentrations that are comparable to the PNRI guidance level of 1000 Bg/kg for 137 Cs that is destined for general consumption. Results of the MDC measurements show that the RMS units are sensitive enough to detect radioactivity levels that are within the guidance levels provided that a) the minimum package lot is approximately 200 kg, b) the package is positioned at the detector side, and c) the alarm setting of RMS is as calibrated. It was therefore established that the RMS can be used to initially screen incoming foodstuff shipments of possible contamination and thereby help minimize potential radiation exposures to the public. (author)

  12. [Experimental research on the electromagnetic radiation immunity of a kind of portable monitor].

    Science.gov (United States)

    Yuan, Jun; Xiao, Dongping; Jian, Xin

    2010-11-01

    The paper is focused on a kind of portable monitor that is widely used in military hospitals. In order to study the electromagnetic radiation immunity of the monitor, the experiments of electromagnetic radiation caused by radio frequency continuous wave in reverberation chamber and by ultra wide band (UWB) electromagnetic pulse have been done. The study results show that UWB electromagnetic pulse interferes observably the operating state of the monitor. It should be paid high attention to take protective measures. The monitor tested has some electromagnetic immunity ability for radio frequency continuous wave radiation. The frequent abnormal phenomena are baseline drift and waveform distortion. The electromagnetic sensitivity of the monitor is related to the frequency of interference source. The monitor tested is most sensitive to the frequency of 390 MHz.

  13. Experience and improved techniques in radiological environmental monitoring at major DOE low-level waste disposal sites

    International Nuclear Information System (INIS)

    1986-09-01

    A summary of routine radiological environmental surveillance programs conducted at major active US Department of Energy (DOE) solid low-level waste (LLW) disposal sites is provided. The DOE disposal sites at which monitoring programs were reviewed include those located at Hanford, Idaho National Engineering Laboratory (INEL), Nevada Test Site (NTS), Los Alamos National Laboratory (LANL), Oak Ridge National Laboratory (ORNL) and Savannah River Plant (SRP). The review is limited to activities conducted for the purpose of monitoring disposal site performance. Areas of environmental monitoring reviewed include air monitoring for particulates and gases, monitoring of surface water runoff, surface water bodies, ground water, monitoring of surface soils and the vadose zone, and monitoring of ambient penetrating radiation. Routine environmental surveillance is conducted at major LLW disposal sites at various levels of effort for specific environmental media. In summary, all sites implement a routine monitoring program for penetrating radiation. Four sites (INEL, NTS, LANL, and SRP) monitor particulates in air specifically at LLW disposal sites. Hanford monitors particulates at LLW sites in conjunction with monitoring of other site operations. Particulates are monitored on a reservationwide network at ORNL. Gases are monitored specifically at active LLW sites operated at NTS, LANL, and SRP. Ground water is monitored specifically at LLW sites at INEL, LANL, and SRP, in conjunction with other operations at Hanford, and as part of a reservationwide program at NTS and ORNL. Surface water is monitored at INEL, LANL, and SRP LLW sites. Surface soil is sampled and analyzed on a routine basis at INEL and LANL. Routine monitoring of the vadose zone is conducted at the INEL and SRP. Techniques and equipment in use are described and other aspects of environmental monitoring programs, such as quality assurance and data base management, are reviewed

  14. Effects of the new radiation protection act on the radiation protection register and the monitoring of occupational radiation exposure

    International Nuclear Information System (INIS)

    Frasch, G.

    2016-01-01

    The implementation of DIRECTIVE 2013/59 / EURATOM (EURATOM Basic Safety Standards) is via the new radiation protection law and brings in the monitoring of occupational radiation among others two significant new features and changes: - Introduction of a unique personal identifier, - update of the occupational categories. Both require technical and organizational changes in the data transmission of the licensees to the dosimetry services and the radiation protection register.

  15. Radiation monitoring with CVD diamonds and PIN diodes at BaBar

    Energy Technology Data Exchange (ETDEWEB)

    Bruinsma, M. [University of California Irvine, Irvine, CA 92697 (United States); Burchat, P. [Stanford University, Stanford, CA 94305-4060 (United States); Curry, S. [University of California Irvine, Irvine, CA 92697 (United States)], E-mail: scurry@slac.stanford.edu; Edwards, A.J. [Stanford University, Stanford, CA 94305-4060 (United States); Kagan, H.; Kass, R. [Ohio State University, Columbus, OH 43210 (United States); Kirkby, D. [University of California Irvine, Irvine, CA 92697 (United States); Majewski, S.; Petersen, B.A. [Stanford University, Stanford, CA 94305-4060 (United States)

    2007-12-11

    The BaBar experiment at the Stanford Linear Accelerator Center has been using two polycrystalline chemical vapor deposition (pCVD) diamonds and 12 silicon PIN diodes for radiation monitoring and protection of the Silicon Vertex Tracker (SVT). We have used the pCVD diamonds for more than 3 years, and the PIN diodes for 7 years. We will describe the SVT and SVT radiation monitoring system as well as the operational difficulties and radiation damage effects on the PIN diodes and pCVD diamonds in a high-energy physics environment.

  16. Monitoring of radiation via CT

    International Nuclear Information System (INIS)

    Atzinger, A.; Pfaendner, K.; Gfirtner, H.; Hoetzinger, H.

    1981-01-01

    The results presented in this article lead to the conclusion that it would be appropriate to demand control or monitoring of radiation via CT whenever complicated exposure to radiation is required. Such control appears mandatory in order to guarantee a sufficiently high tumour dosage and satisfactory protection or minimum burdening of the surrounding tissue. At first sight, it may seem that such CT operations are relatively costly. However, once the teamwork has been properly established, both the time required and the cost involved remain within reasonable limits and will probably not be greater than control via therapy simulator. The decisive factor is that computerised tomography should offer sufficient possibilities of translating such control into reality by effecting the necessary dosage adjustments in accordance with given requirements. (orig.) [de

  17. Monitoring the genetic health of persons in Goiania accidentally exposed to ionizing radiation from caesium-137

    International Nuclear Information System (INIS)

    Da Cruz, A.D.; Glickman, B.W.

    1998-01-01

    This work describes the long term genetic monitoring of the Goiania population exposed to ionizing radiation from 137 Cs, using cytogenetic and molecular endpoints. Cytogenetically, micronucleus frequencies differentiated groups exposed to different levels of radiation. Two molecular methods were employed: 1) the hprt clonal assay, involving in vitro selection of 6-thioguanine-resistant hprt mutant clones which were characterized at the molecular level using RT-PCR and genomic analysis. Ionizing radiation exposure initially elevated hprt mutation frequency which gradually diminished, so that no significant increase was observed four and a half years after original exposure. The spectrum of hprt mutations recovered from ten individuals exposed to relatively high doses of radiation revealed a fourfold increase in the frequency of A:T → G:C transitions. The increase is consistent with the effects of ionizing radiation in prokaryotes and lower eukaryotes. Additionally, a twofold increase in the frequency of deletions was observed which may reflect radiation induced DNA strand breakage; 2) determination of microsatellite instability using fluorescent PCR and genomic DNA from mononuclear cells. The frequency distributions of somatic microsatellite alterations in exposed and non-exposed populations were not different. Our assay lacked sensitivity to discriminate between spontaneous and induced microsatellite instability and therefore, is not suitable for population monitoring. Finally, we estimated the risk associated with radiation exposure for the exposed Goiania population. The estimated genetic risk of dominant disorders in the first post-exposure generation was increased nearly twenty-fourfold. The risk of carcinogenesis was increased by a factor of 1.5. (author)

  18. Monitoring the genetic health of persons in Goiania accidentally exposed to ionizing radiation from caesium-137

    Energy Technology Data Exchange (ETDEWEB)

    Da Cruz, A D; Glickman, B W [Centre for Environmental Health, Department of Biology, University of Victoria, Victoria, BC (Canada)

    1998-12-01

    This work describes the long term genetic monitoring of the Goiania population exposed to ionizing radiation from {sup 137}Cs, using cytogenetic and molecular endpoints. Cytogenetically, micronucleus frequencies differentiated groups exposed to different levels of radiation. Two molecular methods were employed: (1) the hprt clonal assay, involving in vitro selection of 6-thioguanine-resistant hprt mutant clones which were characterized at the molecular level using RT-PCR and genomic analysis. Ionizing radiation exposure initially elevated hprt mutation frequency which gradually diminished, so that no significant increase was observed four and a half years after original exposure. The spectrum of hprt mutations recovered from ten individuals exposed to relatively high doses of radiation revealed a fourfold increase in the frequency of A:T {yields} G:C transitions. The increase is consistent with the effects of ionizing radiation in prokaryotes and lower eukaryotes. Additionally, a twofold increase in the frequency of deletions was observed which may reflect radiation induced DNA strand breakage; (2) determination of microsatellite instability using fluorescent PCR and genomic DNA from mononuclear cells. The frequency distributions of somatic microsatellite alterations in exposed and non-exposed populations were not different. Our assay lacked sensitivity to discriminate between spontaneous and induced microsatellite instability and therefore, is not suitable for population monitoring. Finally, we estimated the risk associated with radiation exposure for the exposed Goiania population. The estimated genetic risk of dominant disorders in the first post-exposure generation was increased nearly twenty-fourfold. The risk of carcinogenesis was increased by a factor of 1.5. (author)

  19. Measurement and evaluation of the external radiation level at reactor Kartini

    International Nuclear Information System (INIS)

    Atok Suhartanto; Suparno

    2013-01-01

    Measurement and evaluation of external radiation level at reactor Kartini in 2012 has been done. The purpose of this activity is to know the external radiation level as a result of the radioactive or radiation source usage, toward the operational of limit condition. The measurement is using survey meter Inspector 11086, factor of calibration 0.991 mR/h, at 9 locations is: Control room area, Thermal column facilities, Demineralizer, Beamport radiography facilities, bulk shielding Deck, Subcritical facilities, Reactor hall, Deck reactor and on the surface of reactor water tank . The highest room average measurement result in 9 working areas for 12 months continuously are at the reactor tank location is between 13.05±1.09 (xlO -2 mSv/hour) to 16.80±1.40 (x10 -2 mSv/hour), and the lowest measurement result in 1 location (control room) is 0.02±0.005 (x10 -2 mSv/hour) to 0.035±0.009 (x10 -2 mSv/hour). The Kartini reactor is involved in the control area which has potentially contaminated and has radiation exposure at the level of 6 mSv/year. Radiation Protection Officer that work in interval will received radiation exposure dosage of 8.4 mSv/year. This dosage is still below the Below Dosage Value which is recommended by, BAPETEN decree No, 4, 2013 about Protection and Radiation Safety in Nuclear Energy Application at 20 mSv/year. The result of the evaluation above shows that the external radiation which occurred in each area is still below the operational of limit condition that is written on the Kartini reactor safety analysis report, on document number: C7/05/B2/LAK/2010, revision 7. So that the workplace is safe for work monitored. (author)

  20. Environmental radiation monitoring data for Point Lepreau Generating Station, 1988. Annual publication

    Energy Technology Data Exchange (ETDEWEB)

    Sutherland, J K

    1989-01-01

    Annual report presenting a compilation of the 1988 environmental radiation monitoring program data from samples collected around the Point Lepreau Nuclear Generating Station (PLNGS) and at reference stations remote from PLNGS. About 1,700 analyses were made on 1,200 samples to monitor environmental radiation, including air filters, airborne water vapour, sea water, well water, milk, beach sediments, clams, fish, lobster, dulse, crabs, scallops and lichen. Background radiation is measured by thermoluminescence dosimetry.

  1. Environmental radiation monitoring data for Point Lepreau Generating Station, 1987. Annual publication

    Energy Technology Data Exchange (ETDEWEB)

    Sutherland, J K

    1988-01-01

    Annual report presenting a compilation of the 1987 environmental radiation monitoring program data from samples collected around the Point Lepreau Nuclear Generating Station (PLNGS) and at reference stations remote from PLNGS. About 1,800 analyses were made on 1,300 samples to monitor environmental radiation, including air filters, airborne water vapour, sea water, well water, milk, beach sediments, clams, fish, lobster, dulse, crabs, scallops and periwinkles. Background radiation is measured by thermoluminescence dosimetry.

  2. Acute radiation effects on cutaneous microvasculature: evaluation with a laser Doppler perfusion monitor

    Energy Technology Data Exchange (ETDEWEB)

    Amols, H.I.; Goffman, T.E.; Komaki, R.; Cox, J.D.

    1988-11-01

    Laser Doppler perfusion monitoring is a noninvasive technique for measuring blood flow in epidermal microvasculature that makes use of the frequency shift of light reflected from red blood cells. Measurements in patients undergoing radiation therapy show increases in blood flow of ten to 25 times baseline at doses above 50 Gy, and increases are observed with doses as low as 2 Gy. Follow-up measurements show rapid decreases in flow levels after completion of therapy, but levels remain elevated even at 1 year.

  3. Acute radiation effects on cutaneous microvasculature: evaluation with a laser Doppler perfusion monitor

    International Nuclear Information System (INIS)

    Amols, H.I.; Goffman, T.E.; Komaki, R.; Cox, J.D.

    1988-01-01

    Laser Doppler perfusion monitoring is a noninvasive technique for measuring blood flow in epidermal microvasculature that makes use of the frequency shift of light reflected from red blood cells. Measurements in patients undergoing radiation therapy show increases in blood flow of ten to 25 times baseline at doses above 50 Gy, and increases are observed with doses as low as 2 Gy. Follow-up measurements show rapid decreases in flow levels after completion of therapy, but levels remain elevated even at 1 year

  4. Environmental radiation monitoring technology: Capabilities and needs

    International Nuclear Information System (INIS)

    Hofstetter, K.J.

    1994-01-01

    Radiation monitoring in the Savannah River Site (SRS) environment is conducted by a combination of automated, remote sampling and/or analysis systems, and manual sampling operations. This program provides early detection of radionuclide releases, minimizes the consequences, and assesses the impact on the public. Instrumentation installed at the release points monitor the atmospheric and aqueous releases from SRS operations. Ground water and air monitoring stations are strategically located throughout the site for radionuclide migration studies. The environmental radiological monitoring program at SRS includes: fixed monitoring stations for atmospheric radionuclide concentrations, aqueous monitors for surface water measurements, mobile laboratory operations for real-time, in-field measurements, aerial scanning for wide area contamination surveillance, and hand-held instruments for radionuclide-specific measurements. Rigorous environmentnal sampling surveillance coupled with laboratory analyses provide confirmatory results for all in-field measurements. Gaps in the technologies and development projects at SRS to fill these deficiencies are discussed in the context of customer needs and regulatory requirements

  5. The monitoring results of electromagnetic radiation of 110-kV high-voltage lines in one urban location in Chongqing P.R. China.

    Science.gov (United States)

    Qin, Qi-Zhong; Chen, Yu; Fu, Ting-Ting; Ding, Li; Han, Ling-Li; Li, Jian-Chao

    2012-03-01

    To understand electromagnetic radiation field strength and its influencing factors of certain 110-kV high-voltage lines in one urban area of Chongqing by measuring 110-kV high-voltage line's electromagnetic radiation level. According to the methodology as determined by the National Hygienic Standards, we selected certain adjacent residential buildings, high-voltage lines along a specific street and selected different distances around its vertical projection point as monitoring points. The levels of electromagnetic radiations were measured respectively. In this investigation within the frequency of 5-1,000 Hz both the electric field strength and magnetic field strength of each monitoring sites were lower than the public exposure standards as determined by the International Commission on Non-Ionizing Radiation Protection. However, the electrical field strength on the roof adjacent to the high-voltage lines was significantly higher than that as measured on the other floors in the same buildings (p electromagnetic radiation measurements of different monitoring points, under the same high-voltage lines, showed the location which is nearer the high-voltage line maintain a consistently higher level of radiation than the more distant locations (p Electromagnetic radiation generated by high-voltage lines decreases proportionally to the distance from the lines. The buildings can to some extent shield (or absorb) the electric fields generated by high-voltage lines nearby. The electromagnetic radiation intensity near high-voltage lines may be mitigated or intensified by the manner in which the high-voltage lines are set up, and it merits attention for the potential impact on human health.

  6. Comprehensive Approach for Monitoring and Analyzing the Activity Concentration Level of PET Isotopes

    International Nuclear Information System (INIS)

    Osovizky, A.; Paran, J.; Ankry, N.; Vulasky, E.; Ashkenazi, B.; Tal, N.; Dolev, E.; Gonen, E.

    2004-01-01

    A comprehensive approach for measuring and analyzing low concentration levels of positron emitter isotopes is introduced. The solution is based on a Continuous Air Monitoring Sampler (CAMS), Stack Monitoring System (SMS) and software package. Positron Emission Tomography (PET) is a major tool for both, biochemical research and non-invasive diagnostics for medicine imaging. The PET method utilizes short half life β + radioisotopes that are produced in cyclotron sites built especially for this purpose. The growing need for β + isotopes brought about a commonly wide use of cyclotrons next to populated areas. Isotopes production involves two possible radiation hazards deriving from the activity concentration; one refers to the nearby population by the activity released through the ventilation system and the other refers to the personnel working in the nuclear facility. A comprehensive system providing solution for both radiation hazards is introduced in this work

  7. Intercomparison of personal radiation monitoring services in the Asia/Pacific region

    International Nuclear Information System (INIS)

    Young, J.G.; Hargrave, N.J.

    1994-01-01

    The Australian Radiation Laboratory conducted an international intercomparison of personal radiation monitoring services in the Asia/Pacific region during 1991. Twenty nine organizations from sixteen countries took part in the study, with the People's Republic of China having eleven participants. Dosemeters incorporating thermoluminescent phosphors and conventional film were submitted for evaluation. Both types were irradiated at normal incidence on a phantom with 137 Cs gamma rays, X rays and beta radiation from a 90 Sr/ 90 Y source. Participants were requested to assess their dosemeters in terms of the new operational quantities of the ICRU for personal radiation monitoring, in particular the personal dose equivalents H p (0.07) and H p (10). (author)

  8. Atmospheric radiation monitor

    Energy Technology Data Exchange (ETDEWEB)

    Oliveira, M.A. Leigui de; Peixoto, C.J. Todero; Leao, M.S.A.B.; Luzio, V.P. [Universidade Federal do ABC (UFABC), SP (Brazil); Barbosa, A.F.; Lima Junior, H.P.; Vilar, A.B.; Gama, R.G.; Ferraz, V.A. [Centro Brasileiro de Pesquisas Fisicas (CBPF), Rio de Janeiro, RJ (Brazil)

    2011-07-01

    Full text: The Atmospheric Radiation Monitor (MonRAt) is a compact telescope designed to detect fluorescence photons generated in the atmosphere by ultra-high energy cosmic rays showers with energies in the interval between 10{sup 17} eV and 10{sup 18} eV. It is composite by a 64 pixels MultiAnodic PhotoMultiplier Tube (MAPMT) placed at the focus of a parabolic mirror mounted in a Newtonian telescope setup and the data acquisition system. In front of the MAPMT photocathode, filters will be positioned to select light with wavelength in the near ultraviolet region (300 nm < {lambda} < 450 nm) where the nitrogen fluorescent emissions occurs. The data acquisition system consists of a set of pre-amplifiers and FPGA-based boards able to record trigger times and waveforms from each channel and send the data to a computer by USB ports. MonRAt will be used to detect fluorescence photons under different atmospheric conditions (pressure, temperature, humidity, local geomagnetic field, etc) and will contribute with a detailed study of the fluorescence radiation yield. The assembly of the telescope is under way and we present in this work the status of the experiment and its first measurements in the laboratory. (author)

  9. Atmospheric radiation monitor

    International Nuclear Information System (INIS)

    Oliveira, M.A. Leigui de; Peixoto, C.J. Todero; Leao, M.S.A.B.; Luzio, V.P.; Barbosa, A.F.; Lima Junior, H.P.; Vilar, A.B.; Gama, R.G.; Ferraz, V.A.

    2011-01-01

    Full text: The Atmospheric Radiation Monitor (MonRAt) is a compact telescope designed to detect fluorescence photons generated in the atmosphere by ultra-high energy cosmic rays showers with energies in the interval between 10 17 eV and 10 18 eV. It is composite by a 64 pixels MultiAnodic PhotoMultiplier Tube (MAPMT) placed at the focus of a parabolic mirror mounted in a Newtonian telescope setup and the data acquisition system. In front of the MAPMT photocathode, filters will be positioned to select light with wavelength in the near ultraviolet region (300 nm < λ < 450 nm) where the nitrogen fluorescent emissions occurs. The data acquisition system consists of a set of pre-amplifiers and FPGA-based boards able to record trigger times and waveforms from each channel and send the data to a computer by USB ports. MonRAt will be used to detect fluorescence photons under different atmospheric conditions (pressure, temperature, humidity, local geomagnetic field, etc) and will contribute with a detailed study of the fluorescence radiation yield. The assembly of the telescope is under way and we present in this work the status of the experiment and its first measurements in the laboratory. (author)

  10. Electromagnetic Radiofrequency Radiation Emitted from GSM Mobile Phones Decreases the Accuracy of Home Blood Glucose Monitors

    Science.gov (United States)

    Mortazavi, SMJ; Gholampour, M; Haghani, M; Mortazavi, G; Mortazavi, AR

    2014-01-01

    Mobile phones are two-way radios that emit electromagnetic radiation in microwave range. As the number of mobile phone users has reached 6 billion, the bioeffects of exposure to mobile phone radiation and mobile phone electromagnetic interference with electronic equipment have received more attention, globally. As self-monitoring of blood glucose can be a beneficial part of diabetes control, home blood glucose testing kits are very popular. The main goal of this study was to investigate if radiofrequency radiation emitted from a common GSM mobile phone can alter the accuracy of home blood glucose monitors. Forty five female nondiabetic students aged 17-20 years old participated in this study. For Control-EMF group (30 students), blood glucose concentration for each individual was measured in presence and absence of radiofrequency radiation emitted by a common GSM mobile phone (HTC touch, Diamond 2) while the phone was ringing. For Control- Repeat group (15 students), two repeated measurements were performed for each participant in the absence of electromagnetic fields. The magnitude of the changes between glucose levels in two repeated measurements (|ΔC|) in Control-Repeat group was 1.07 ± 0.88 mg/dl while this magnitude for Control-EMF group was 7.53 ± 4.76 mg/dl (P electromagnetic interference in home blood glucose monitors. It can be concluded that electromagnetic interference from mobile phones has an adverse effect on the accuracy of home blood glucose monitors. We suggest that mobile phones should be used at least 50 cm away from home blood glucose monitors. PMID:25505778

  11. 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)

  12. Acceptance criteria for deposition of low-level and intermediate-level radiation levels radioactive wastes

    International Nuclear Information System (INIS)

    2002-09-01

    This norm establishes the criteria for acceptance low and intermediate radiation level for safe deposition in repositories, for assuring the protection of workers, population and environment against the hazardous effects of the ionizing radiations. The criteria of this norm applies to the low and intermediate radiation levels

  13. Radiation monitoring system based on Internet

    International Nuclear Information System (INIS)

    Drndarevic, V.R.; Popovic, A.T; Bolic, M.D.; Pavlovic, R.S.

    2001-01-01

    This paper presents concept and realization of the modern distributed radiation monitoring system. The system uses existing conventional computer network and it is based on the standard Internet technology. One personal computer (PC) serves as host and system server, while a number of client computers, link to the server computer via standard local area network (LAN), are used as distributed measurement nodes. The interconnection between the server and clients are based on Transmission Control Protocol/Internet Protocol (TCP/IP). System software is based on server-client model. Based on this concept distributed system for gamma ray monitoring in the region of the Institute of Nuclear Sciences Vinca has been implemented. (author)

  14. Tradescantia in studies of genetic effects of low level radiation

    International Nuclear Information System (INIS)

    Yamashita, Atsushi

    1976-01-01

    Tradescantia in studies on genetic effects of low level radiation is briefly introduced. Radiosensitivity, method of screening stamen hair mutation, materials in current uses, spontaneous mutation rate, and modifying factors are refered. For stamen hair mutation b values in exponential model were lower in irradiation with low dose rate at high environmental temperature. The dose response curves under these modifying conditions, when extrapolated to low dose range, well fit to the line which was obtained by Sparrow's experiment of low level irradiation. In chronic irradiation, the frequency of stamen hair mutation reaches to the constant value after 17 days from the start of irradiation, and is as much as 4 times higher than the peak value in one day irradiation at the same exposure rate. The spontaneous mutation rate of KU-7 varied with temperature. The increase with 1 0 C increment of mean temperature was -0.04%. Uses of Tradescantia in monitoring the environmental radiation is discussed. (auth.)

  15. Monitoring of Radiation Levels in Mines of Kaolin Located in the Region Serido-PB, Brazil

    International Nuclear Information System (INIS)

    Guerra Spacov, Isabel Cristina; Dos Santos Amaral, Milton; Araujo dos Santos Junior, Jose

    2015-01-01

    Kaolin is formed mainly by kaolinite and is used in many industrial sectors. Kaolin may be associated with by-products such as quartz, mica, feldspar and sand. The background radiation from nature is very important, since it represents the main source of human exposure to radiation. In kaolin, radionuclides are present as the 40 K and series 238 U and 232 Th. This study aimed to obtain the rates of effective doses of kaolin mines in the region of Serido-PB, Brazil, where there are several productions and mineral occurrences, including kaolin and uranium at nearby areas. Four kaolin mines located in the Serido-PB region were monitored by a portable discriminator detector NaI(Ti). Measurements were obtained outdoors in triplicate, at a distance of 1.0 meters from the Earth's surface. According to the report of UNSCEAR, the world average effective dose from exposure to natural radiation sources is 2.42 mSvy -1 . the rates of effective doses identified in this study ranged from 1.37 mSvy -1 , and provided the construction of isodose curves. The highest dose rate obtained may be related to pegmatite bodies in a nearby area that contain uranium minerals. However, based on the development of this research, the results indicate that further study in this area is needed in order to infer damage associated with mining of kaolin in the Serido-PB area. (Author)

  16. Seasonal variations of radon and the radiation exposure levels in Nerja cave, Spain

    International Nuclear Information System (INIS)

    Duenas, C.; Fernandez, M.C.; Canete, S.; Perez, M.; Gordo, E.

    2011-01-01

    222 Rn concentrations in the air in Nerja cave (Spain) (3 o 52'35''W 36 o 43'50''N) were measured by continuous monitoring using Alpha-Guard, Genitron instrument equipment. The 222 Rn measurements were carried out for a complete annual cycle in the different halls: Vestibule hall from July 2003 to June 2004, Ballet hall from July 2004 to June 2005 and Mirador hall from July 2005 to June 2006. Starting from the entrance of the cave we successively find the Vestibule hall, the Ballet hall and the Mirador hall. The range of 222 Rn levels were of 8-627 Bq m -3 for the Vestibule hall, 28-575 Bq m -3 for the Ballet hall and 38-578 Bq m -3 for the Mirador. The aim of this study was to detect seasonal variation patterns of 222 Rn concentrations. The seasonal variations of 222 Rn concentrations are discussed in relation to various meteorological factors measured inside and outside the cave. The radiation exposure levels for workers and tourists with different equilibrium factors have been evaluated. The radiation exposure levels for workers and tourists only represent a low percentage of the exposure guides for the general population. - Highlights: → The aim of the study was to detect seasonal variation of 222 Rn concentrations. → 222 Rn concentrations in the air-cave were measured by continuous monitoring. → The 222 Rn measurements were carried out in the different halls of the cave. → The radiation exposure levels for workers and tourists have been evaluated.

  17. Radionuclide identification algorithm for organic scintillator-based radiation portal monitor

    Energy Technology Data Exchange (ETDEWEB)

    Paff, Marc Gerrit, E-mail: mpaff@umich.edu; Di Fulvio, Angela; Clarke, Shaun D.; Pozzi, Sara A.

    2017-03-21

    We have developed an algorithm for on-the-fly radionuclide identification for radiation portal monitors using organic scintillation detectors. The algorithm was demonstrated on experimental data acquired with our pedestrian portal monitor on moving special nuclear material and industrial sources at a purpose-built radiation portal monitor testing facility. The experimental data also included common medical isotopes. The algorithm takes the power spectral density of the cumulative distribution function of the measured pulse height distributions and matches these to reference spectra using a spectral angle mapper. F-score analysis showed that the new algorithm exhibited significant performance improvements over previously implemented radionuclide identification algorithms for organic scintillators. Reliable on-the-fly radionuclide identification would help portal monitor operators more effectively screen out the hundreds of thousands of nuisance alarms they encounter annually due to recent nuclear-medicine patients and cargo containing naturally occurring radioactive material. Portal monitor operators could instead focus on the rare but potentially high impact incidents of nuclear and radiological material smuggling detection for which portal monitors are intended.

  18. Radionuclide identification algorithm for organic scintillator-based radiation portal monitor

    Science.gov (United States)

    Paff, Marc Gerrit; Di Fulvio, Angela; Clarke, Shaun D.; Pozzi, Sara A.

    2017-03-01

    We have developed an algorithm for on-the-fly radionuclide identification for radiation portal monitors using organic scintillation detectors. The algorithm was demonstrated on experimental data acquired with our pedestrian portal monitor on moving special nuclear material and industrial sources at a purpose-built radiation portal monitor testing facility. The experimental data also included common medical isotopes. The algorithm takes the power spectral density of the cumulative distribution function of the measured pulse height distributions and matches these to reference spectra using a spectral angle mapper. F-score analysis showed that the new algorithm exhibited significant performance improvements over previously implemented radionuclide identification algorithms for organic scintillators. Reliable on-the-fly radionuclide identification would help portal monitor operators more effectively screen out the hundreds of thousands of nuisance alarms they encounter annually due to recent nuclear-medicine patients and cargo containing naturally occurring radioactive material. Portal monitor operators could instead focus on the rare but potentially high impact incidents of nuclear and radiological material smuggling detection for which portal monitors are intended.

  19. Monitoring millimeter wave stray radiation during ECRH operation at ASDEX Upgrade

    Science.gov (United States)

    Schubert, M.; Honecker, F.; Monaco, F.; Schmid-Lorch, D.; Schütz, H.; Stober, J.; Wagner, D.

    2012-09-01

    Due to imperfection of the single path absorption, ECRH at ASDEX Upgrade (AUG) is always accompanied by stray radiation in the vacuum vessel. New ECRH scenarios with O2 and X3 heating schemes extend the operational space, but they have also the potential to increase the level of stray radiation. There are hazards for invessel components. Damage on electric cables has already been encountered. It is therefore necessary to monitor and control the ECRH with respect to the stray radiation level. At AUG a system of Sniffer antennas equipped with microwave detection diodes is installed. The system is part of the ECRH interlock circuit. We notice, however, that during plasma operation the variations of the Sniffer antenna signal are very large. In laboratory measurements we see variations of up to 20 dB in the directional sensitivity and we conclude that an interference pattern is formed inside the copper sphere of the antenna. When ECRH is in plasma operation at AUG, the plasma is acting as a phase and mode mixer for the millimeter waves and thus the interference pattern inside the sphere changes with the characteristic time of the plasma dynamics. In order to overcome the difficulty of a calibrated measurement of the average stray radiation level, we installed bolometer and pyroelectric detectors, which intrinsically average over interference structures due to their large active area. The bolometer provides a robust calibration but with moderate temporal resolution. The pyroelectric detector provides high sensitivity and a good temporal resolution, but it raises issues of possible signal drifts in long pulses.

  20. Monitoring millimeter wave stray radiation during ECRH operation at ASDEX Upgrade

    Directory of Open Access Journals (Sweden)

    Wagner D.

    2012-09-01

    Full Text Available Due to imperfection of the single path absorption, ECRH at ASDEX Upgrade (AUG is always accompanied by stray radiation in the vacuum vessel. New ECRH scenarios with O2 and X3 heating schemes extend the operational space, but they have also the potential to increase the level of stray radiation. There are hazards for invessel components. Damage on electric cables has already been encountered. It is therefore necessary to monitor and control the ECRH with respect to the stray radiation level. At AUG a system of Sniffer antennas equipped with microwave detection diodes is installed. The system is part of the ECRH interlock circuit. We notice, however, that during plasma operation the variations of the Sniffer antenna signal are very large. In laboratory measurements we see variations of up to 20 dB in the directional sensitivity and we conclude that an interference pattern is formed inside the copper sphere of the antenna. When ECRH is in plasma operation at AUG, the plasma is acting as a phase and mode mixer for the millimeter waves and thus the interference pattern inside the sphere changes with the characteristic time of the plasma dynamics. In order to overcome the difficulty of a calibrated measurement of the average stray radiation level, we installed bolometer and pyroelectric detectors, which intrinsically average over interference structures due to their large active area. The bolometer provides a robust calibration but with moderate temporal resolution. The pyroelectric detector provides high sensitivity and a good temporal resolution, but it raises issues of possible signal drifts in long pulses.

  1. Capacity training for the personnel of radiation monitoring in metal recycling

    International Nuclear Information System (INIS)

    Caveda Ramos, C.A.; Dominguez Ley, O.

    2013-01-01

    In this work it a course for training for the personnel involved in the radiation monitoring of metal recycling is presented. The contents were elaborated taken into account the IAEA recommendations for the development of capacity and training activities in radiological safety and in the Guide for the control of radioactive material in metal recycling. The program is divided in eleven parts and the duration time is two weeks. Among the main covered topics are the requirements for radiation monitoring in metal recycling; response to detection of radioactive material and effects of the ionizing radiation in man and environment

  2. Radiation monitoring systems and methodologies for radiological impact assessment

    International Nuclear Information System (INIS)

    Chaudhury, Probal

    2016-01-01

    Radioactive sources of various strengths are used in large number of applications in industry, healthcare, agriculture and research. Though all the sources are transported and used under regulatory control, there is always a possibility of some of the sources getting into the hands of committed antisocial non state actors. In addition to this, there is a possible threat of radioactive material being illegally brought into a country. These gives rise to an increase in the global radiological threat and security experts world over are concerned about the possibility of malicious use of radiation in the public domain. Radiation detection systems are installed at various entry and exit ports of some of the countries to detect illicit trafficking of radioactive materials. IAEA has recommended that all States should have a national response plan for nuclear security events to provide for an appropriate and coordinated response. Considering the requirement of radiological emergency preparedness, various radiation monitoring systems and methodologies have been developed. A few aerial radiation monitoring systems developed at Bhabha Atomic Research Centre (BARC) for radiological impact assessment are described here

  3. 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

  4. Survey monitoring of environmental radioactivity in Daejeon area

    Energy Technology Data Exchange (ETDEWEB)

    Jun, Jae Shik.; Noh, Hyung Ah [Taejon Radiation Monitoring Station, Daejeon (Korea, Republic of)

    2000-12-15

    Systematic understanding of the distribution of environmental radioactivity and radiation level in Taejon, including Chungchung area, in normal circumstance, and rapid detection of unusual variation of the radiation level in emergency situation thereby ensure public safety are the objectives of this project to be carried out. This report summarizes and interprets environmental radiation/radioactivity monitoring data obtained at Taejon Radiation Monitoring Station in 2000. In conclusion, the natural environmental radiation level in Taejon area has been preserved as usual and no significant artificial enhancement in environmental radioactivity was observed during the course of this survey and monitoring period.

  5. Survey monitoring of environmental radioactivity in Daejeon area

    Energy Technology Data Exchange (ETDEWEB)

    Jun, Jae Sik; Noh, Hyung Ah [Daejon Radiation Monitoring Station, Daejeon (Korea, Republic of)

    2001-12-15

    Systematic understanding of the distribution of environmental radioactivity and radiation level in Daejeon, including Chungchung area, in normal circumstance, and rapid detection of unusual variation of the radiation level in emergency situation thereby ensure public safety are the objectives of this project to be carried out. This report summarizes and interprets environmental radiation/radioactivity monitoring data obtained at Daejeon Radiation Monitoring Station in 2001. In conclusion, the natural environmental radiation level in Daejeon area has been preserved as usual and no significant artificial enhancement in environmental radioactivity was observed during the course of this survey and monitoring period.

  6. Survey monitoring of environmental radioactivity in Daejeon area

    Energy Technology Data Exchange (ETDEWEB)

    Jun, Jae Shik; Noh, Hyung Ah [Daejon Radiation Monitoring Station, Daejeon (Korea, Republic of)

    2002-12-15

    Systematic understanding of the distribution of environmental radioactivity and radiation level in Daejeon, including Chungchung area, in normal circumstance, and rapid detection of unusual variation of the radiation level in emergency situation thereby ensure public safety are the objectives of this project to be carried out. This report summarizes and interprets environmental radiation/radioactivity monitoring data obtained at Daejeon Radiation Monitoring Station in 2002. In conclusion, the natural environmental radiation level in Daejeon area has been preserved as usual and no significant artificial enhancement in environmental radioactivity was observed during the course of this survey and monitoring period.

  7. Survey monitoring of environmental radioactivity in Daejeon area

    Energy Technology Data Exchange (ETDEWEB)

    Jun, Jae Shik; Noh, Hyung Ah [Daejon Radiation Monitoring Station, Daejeon (Korea, Republic of)

    2003-12-15

    Systematic understanding of the distribution of environmental radioactivity and radiation level in Daejeon, including Chungchung area, in normal circumstance, and rapid detection of unusual variation of the radiation level in emergency situation thereby ensure public safety are the objectives of this project to be carried out. This report summarizes and interprets environmental radiation/radioactivity monitoring data obtained at Daejeon Radiation Monitoring Station in 2002. In conclusion, the natural environmental radiation level in Daejeon area has been preserved as usual and no significant artificial enhancement in environmental radioactivity was observed during the course of this survey and monitoring period.

  8. Survey monitoring of environmental radioactivity in Daejeon area

    International Nuclear Information System (INIS)

    Jun, J. S.; Kim, K. S.

    1998-01-01

    Systematic understanding of the distribution of environmental radioactivity and radiation level in Taejon, including Chungchung area, in normal circumstance, and rapid detection of unusual variation of the radiation level in emergency situation thereby ensure public safety are the objectives of this project to be carried out. This report summarizes and interprets environmental radiation/radioactivity monitoring data obtained at Taejon Radiation Monitoring Station in 1998. In conclusion, the natural environmental radiation level in Taejon area has been preserved as usual and no significant artificial enhancement in environmental radioactivity was observed during the course of this survey and monitoring period

  9. Survey monitoring of environmental radioactivity in Daejeon area

    International Nuclear Information System (INIS)

    Jun, Jae Sik; Noh, Hyung Ah

    2001-12-01

    Systematic understanding of the distribution of environmental radioactivity and radiation level in Daejeon, including Chungchung area, in normal circumstance, and rapid detection of unusual variation of the radiation level in emergency situation thereby ensure public safety are the objectives of this project to be carried out. This report summarizes and interprets environmental radiation/radioactivity monitoring data obtained at Daejeon Radiation Monitoring Station in 2001. In conclusion, the natural environmental radiation level in Daejeon area has been preserved as usual and no significant artificial enhancement in environmental radioactivity was observed during the course of this survey and monitoring period

  10. Radiation monitoring. Quarterly report for the Greater Manchester Fire and Civil Defence Authority and the Manchester Area Pollution Advisory Council. Manchester Area Gamma Radiation Air Monitoring System (MANAGRAMS), report covering period of 3 months 01/04/1997 to 30/06/1997

    International Nuclear Information System (INIS)

    1997-01-01

    Gamma radiation monitoring data from ten outstations in the Manchester area are presented. For each station there is a summary table, a background radiation graph showing 6 hour mean levels and a windrose graph showing the direction of the wind as a percentage of the total. A line graph comparison between stations is provided for the background 6 hour mean levels and a bar chart comparison of total dose. Graphs of temperature and barometric pressure taken from extra sensors at the Trafford station are presented. (Author)

  11. System-Level Model for OFDM WiMAX Transceiver in Radiation Environment

    International Nuclear Information System (INIS)

    Abdel Alim, O.; Elboghdadly, N.; Ashour, M.M.; Elaskary, A.M.

    2008-01-01

    WiMAX (Worldwide Inter operability for Microwave Access), an evolving standard for point-to-multipoint wireless networking, works for the l ast mile c onnections for replacing optical fiber technology network but with no need for adding more infra structure within crowded areas. Optical fiber technology is seriously considered for communication and monitoring applications in space and around nuclear reactors. Space and nuclear environments are characterized, in particular, by the presence of ionizing radiation fields. Therefore the influence of radiation on such networks needs to be investigated. This paper has the objective of building a System level model for a WiMAX OFDM (Orthogonal Frequency Division Multiplexing) based transceiver. Modeling irradiation noise as an external effect added to the Additive White Gaussian noise (AWGN). Then analyze, discuss the results based on qualitatively performance evaluation using BER calculations for radiation environment

  12. Status and trends of solid state track detector use in radiation protection monitoring

    International Nuclear Information System (INIS)

    Doerschel, B.

    1980-01-01

    The characteristic properties of solid state track detectors allow them to be used for determining the radiation fields of charged and uncharged particles and, consequently, for solving some problems involved in radiation protection monitoring. Aptitude of various detector materials is investigated on the basis of the track formation mechanism taking into account the properties of the particles to be detected. Use of these detectors in radiation protection monitoring presumes appropriate methods of intensifying the latent tracks, which are discussed as a function of various physical parameters. Readout methods of solid state track detectors are based on variations in detector properties determined by number and size of particle tracks in the detector. The choice of a special readout method, among other things, depends on the purpose, detector material, and pretreatment of the detectors. The most prospective methods are described and investigated with respect to their possible use in various fields of radiation protection monitoring. The trends of development of the application of solid state track detectors in radiation protection monitoring are discussed, using some typical applications as examples. (author)

  13. Overview of environmental radiological monitoring program of Institute of Radiation Protection And Dosimetry - IRD

    Energy Technology Data Exchange (ETDEWEB)

    Gomes, Sarah Barreto Oliveira de Christo; Peres, Sueli da Silva, E-mail: suelip@ird.gov.br, E-mail: sarah.barreto1@gmail.com [Instituto de Radioproteção e Dosimetria (IRD/CNEN-RJ), Rio de Janeiro, RJ (Brazil). Div. de Radioproteção

    2017-07-01

    As a branch of the Brazilian Nuclear Energy Commission (CNEN), the Institute of Radiation Protection and Dosimetry (IRD) performs extensive activities in the fields of radiation protection, metrology, and dosimetry, as well as specific education, onto a wide operational scope that includes the technical support to national regulatory authorities in the licensing process for nationwide nuclear and radioactive facilities. IRD has several laboratories where are performed radiometric and radiochemical analyses and others radioactivity evaluation procedures in different types of samples obtained in the inspection activities, production of radioactivity metrological standards and reference material by National Laboratory of Metrology of Ionizing Radiation (LMNRI), besides others research activities. In this laboratories can be used sealed or unsealed radioactive sources and radiation-producing devices and are classified with radioactive installations in accordance to national regulations. This way, radioactive liquid effluents can be eventually produced and released into the environment in the course of such activities and an effluent monitoring program to control and reduce the releases to environment is carried out. Additionally, IRD maintains the Radioactive Waste Management Program and Environmental Radiological Monitoring Program (ERMP) in accordance to national regulations requirements. The primary focus of ERMP comprises the validation of the dose prognostics for the public members due to effluents discharge and the provision of consistent projections of the radiation levels at the monitoring sites. In this study, a long term ERMP data survey is discussed, spanning the last thirteen years of activities. On the basis of such discussions and prognostics, it could be observed that the radiological environmental radiological impact due to operation of IRD installations is negligible. (author)

  14. Overview of environmental radiological monitoring program of Institute of Radiation Protection And Dosimetry - IRD

    International Nuclear Information System (INIS)

    Gomes, Sarah Barreto Oliveira de Christo; Peres, Sueli da Silva

    2017-01-01

    As a branch of the Brazilian Nuclear Energy Commission (CNEN), the Institute of Radiation Protection and Dosimetry (IRD) performs extensive activities in the fields of radiation protection, metrology, and dosimetry, as well as specific education, onto a wide operational scope that includes the technical support to national regulatory authorities in the licensing process for nationwide nuclear and radioactive facilities. IRD has several laboratories where are performed radiometric and radiochemical analyses and others radioactivity evaluation procedures in different types of samples obtained in the inspection activities, production of radioactivity metrological standards and reference material by National Laboratory of Metrology of Ionizing Radiation (LMNRI), besides others research activities. In this laboratories can be used sealed or unsealed radioactive sources and radiation-producing devices and are classified with radioactive installations in accordance to national regulations. This way, radioactive liquid effluents can be eventually produced and released into the environment in the course of such activities and an effluent monitoring program to control and reduce the releases to environment is carried out. Additionally, IRD maintains the Radioactive Waste Management Program and Environmental Radiological Monitoring Program (ERMP) in accordance to national regulations requirements. The primary focus of ERMP comprises the validation of the dose prognostics for the public members due to effluents discharge and the provision of consistent projections of the radiation levels at the monitoring sites. In this study, a long term ERMP data survey is discussed, spanning the last thirteen years of activities. On the basis of such discussions and prognostics, it could be observed that the radiological environmental radiological impact due to operation of IRD installations is negligible. (author)

  15. Community Radiation Monitoring Program

    International Nuclear Information System (INIS)

    Cooper, E.N.

    1993-05-01

    The Community Radiation Monitoring Program (CRMP) is a cooperative effort between the US Department of Energy (DOE); the US Environmental Protection Agency (EPA); the Desert Research Institute (DRI), a division of the University and Community College System of Nevada and the Nuclear Engineering Laboratory of the University of Utah (UNEL). The twelfth year of the program began in the fall of 1991, and the work continues as an integral part of the DOE-sponsored long-term offsite radiological monitoring effort that has been conducted by EPA and its predecessors since the inception of nuclear testing at the Nevada Test Site (NTS). The program began as an outgrowth of activities that occurred during the Three Mile Island incident in 1979. The local interest and public participation that took place there were thought to be transferrable to the situation at the NTS, so, with adaptations, that methodology was implemented for this program. The CRMP began by enhancing and centralizing environmental monitoring and sampling equipment at 15 communities in the existing EPA monitoring network, and has since expanded to 19 locations in Nevada, Utah and California. The primary objectives of this program are still to increase the understanding by the people who live in the area surrounding the NTS of the activities for which DOE is responsible, to enhance the performance of radiological sampling and monitoring, and to inform all concerned of the results of these efforts. One of the primary methods used to improve the communication link with people in the potentially impacted area has been the hiring and training of local citizens as station managers and program representatives in those selected communities in the offsite area. These managers, active science teachers wherever possible, have succeeded, through their training, experience, community standing, and effort, in becoming a very visible, able and valuable asset in this link

  16. 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)

  17. 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

  18. Radiation protection and ambient radioactivity monitoring in the area of the Asse mine. Annual report 1997

    International Nuclear Information System (INIS)

    Meyer, H.; Stippler, R.

    1998-01-01

    The number of annual sampling and measurements performed in compliance with the operator's monitoring duties have been the same as last year: 364. All measured radioactivity values were at the level of natural environmental radioactivity. Some samples and measurements reflected the fallout from former atmospheric nuclear weapons tests and the accident at the Chernobyl reactor. Personnel dosimetry was performed according to legal requirements of the Radiation Protection Ordinance, as were measurements for the monitoring of ambient doses, dose rates and radioactivity levels in the air of the mine structures. All measured values were below the maximum permissible personal doses and occupational dose limits. Ambient air measurements in the salt mine as in the preceding years detected low amounts of the nuclides H 3, C 14, Pb 210, and the short-lived daughter products of Rn 222 and Rn 220. The calculated radioactivity concentrations in the vicinity of the mine, derived from averaged annual effluents, to some part were below the average natural concentrations of the nuclides. The effluent-induced radiation dose at the most affected location was far below the limits set by the Radiation Protection Ordinance. (orig./CB) [de

  19. Radiation area monitoring by wireless-communicating area monitor with surveillance camera

    International Nuclear Information System (INIS)

    Shimura, Mitsuo; Kobayashi, Hiromitsu; Kitahara, Hideki; Kobayashi, Hironobu; Okamoto, Shinji

    2004-01-01

    Aiming at a dose reduction and a work efficiency improvement for nuclear power plants that have high dose regions, we have developed our system of wireless-communicating Area Monitor with Surveillance Camera, and have performed an on-site test. Now we are implementing this Area Monitor with Surveillance Camera for a use as a TV camera in the controlled-area, which enables a personal computer to simultaneously display two or more dose values and site live images on the screen. For the radiation detector of this Area Monitor System, our wireless-communicating dosimeter is utilized. Image data are transmitted via a wireless Local Area Network (LAN). As a test result, image transmission of a maximum of 20 frames per second has been realized, which shows that this concept is a practical application. Remote-site monitoring also has been realized from an office desk located within the non-controlled area, adopting a Japan's wireless phone system, PHS (Personal Handy Phone) for the transmission interface. (author)

  20. Method and apparatus for neutron radiation monitoring

    International Nuclear Information System (INIS)

    Schwarzmann, A.

    1985-01-01

    A self-calibrated neutron radiation monitor includes a flux responsive element comprised of intrinsic silicon neutron detectors and self-calibration resistors in a single structure. As the resistance of the flux responsive element increases to the value of successive calibration resistors, known increments of flux have been encountered

  1. Automation of metrological operations on measuring apparatuses of radiation monitoring system

    International Nuclear Information System (INIS)

    Kulich, V.; Studeny, J.

    1995-01-01

    (J.K.)In this paper the measuring apparatuses of ionizing radiation for the radiation monitoring of NPP Dukovany operation is described. The increase of metrological operations number has been made possible only by a timely reconstruction of the laboratory and by computerization of the measuring procedure and of administrative work which consists mainly of recording of a great number information pieces about the observed measuring apparatuses. There are three working places in the laboratory: 1) irradiation gamma stand with cesium-137 sources; 2) irradiation stand with plutonium-beryllium neutron sources; 3) spectrometric working place. With the regard to the uniqueness of the laboratory operation, all the works in the sphere of hardware as well as software has been implemented by own forces. The equipment of the laboratory makes possible to test metrologically all the radiation monitoring apparatuses used in NPP Dukovany. The quantity of operation of he laboratory of ionizing metrology qualifies the proper functioning of the radiation monitoring system, which directly influences the ensurance of nuclear safety of NPP Dukovany

  2. Automation of metrological operations on measuring apparatuses of radiation monitoring system

    Energy Technology Data Exchange (ETDEWEB)

    Kulich, V; Studeny, J [NPP Dukovany (Czech Republic)

    1996-12-31

    (J.K.)In this paper the measuring apparatuses of ionizing radiation for the radiation monitoring of NPP Dukovany operation is described. The increase of metrological operations number has been made possible only by a timely reconstruction of the laboratory and by computerization of the measuring procedure and of administrative work which consists mainly of recording of a great number information pieces about the observed measuring apparatuses. There are three working places in the laboratory: 1) irradiation gamma stand with cesium-137 sources; 2) irradiation stand with plutonium-beryllium neutron sources; 3) spectrometric working place. With the regard to the uniqueness of the laboratory operation, all the works in the sphere of hardware as well as software has been implemented by own forces. The equipment of the laboratory makes possible to test metrologically all the radiation monitoring apparatuses used in NPP Dukovany. The quantity of operation of he laboratory of ionizing metrology qualifies the proper functioning of the radiation monitoring system, which directly influences the ensurance of nuclear safety of NPP Dukovany.

  3. A beam radiation monitoring and protection system for AGS secondary beams

    International Nuclear Information System (INIS)

    Levine, G.S.

    1978-01-01

    A commercially available radiation monitor using a scintillation detector was modified for charged particle beam monitoring. The device controls access to secondary beams of the AGS and limits beam intensity

  4. 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

  5. Radiation monitoring for the HTTR rise-to-power test (1) and (2)'

    Energy Technology Data Exchange (ETDEWEB)

    Nakazawa, Takashi; Yoshino, Toshiaki; Yasu, Katsuji; Ashikagaya, Yoshinobu; Kikuchi, Toshiki [Japan Atomic Energy Research Inst., Oarai, Ibaraki (Japan). Oarai Research Establishment

    2001-02-01

    The High Temperature Engineering Test Reactor (HTTR) is the first high temperature gas-cooled research reactor in Japan. This reactor is a helium-gas-cooled and graphite-moderated reactor with a thermal output of 30 MW. The rated operation temperature of the outlet coolant is 850degC. (During high temperature test operation, this reaches 950degC). The first criticality of the HTTR was attained in November 1998. The single loaded, parallel loaded operation with a thermal output of 9 MW (called the HTTR Rise-to-Power Test (1)) was completed between September 16, 1999 and July 8, 2000. The single loaded, parallel loaded continuous operation with a thermal output of 20 MW (called the HTTR Rise-to-Power Test (2)) has also been carried out, but it was shutdown at the halfway stage by a single from the reactor, when the thermal output was 16.5 MW and the reactor outlet coolant temperature was 500degC. This report describes the radiation monitoring carried out during the HTTR Rise-to-Power Tests (1) and (2)'. The data measured by the various radiation monitors is also reported. These data will be used for the estimation of radiation levels (such as the radiation dose equivalent rate, the radioactive concentration in effluents, etc.) for the next HTTR Rise-to-Power Test, and for periodic inspections. (author)

  6. Environmental radiation monitoring data for Point Lepreau Generating Station, 1990. Annual publication

    Energy Technology Data Exchange (ETDEWEB)

    Sutherland, J K

    1991-01-01

    Annual report presenting a compilation of the 1990 environmental radiation monitoring program data from samples collected around the Point Lepreau Nuclear Generating Station (PLNGS) and at reference stations remote from PLNGS. About 1,500 analyses were made on 1,100 samples to monitor environmental radiation, including air particulates, airborne water vapour, carbon dioxide in air, sea water, well water, milk, beach sediments, clams, fish, lobster, dulse, crabs, scallops, periwinkles, sea plants and lichen. Background radiation is measured by thermoluminescence dosimetry. Radon is not assessed.

  7. Application of the ALARA principle to individual occupational radiation monitoring

    International Nuclear Information System (INIS)

    Aleinikov, V.E.

    1998-01-01

    Routine individual occupational radiation monitoring is necessary to ensure that exposure are kept as low as reasonably achievable (ALARA) and that the authorized dose limits are not exceeded. The type and extend of the monitoring depend on the nature and magnitude of occupational radiation exposure. Optimal choice of the wearing time for individual dosimeters, T, has important consequences for achievement of the individual monitoring objects. The choice of T depends on individual dose distribution, the lower detection limit for the detector used, the lost of an information during period of monitoring, the cost of the measurements and the benefits associated with the results. The paper describes the application of quantitative optimization techniques to optimize the wearing time for individual dosimeters. It was shown how optimal wearing time for individual dosimeters depends on dose distribution, the lower detection limit, dose limit, fading and cost of the measurements. (author)

  8. Vehicle tracking based technique for radiation monitoring during nuclear or radiological emergency

    International Nuclear Information System (INIS)

    Saindane, Shashank S.; Otari, Anil D.; Suri, M.M.K.; Patil, S.S.; Pradeepkumar, K.S.; Sharma, D.N.

    2010-01-01

    Radiation Safety Systems Division, BARC has developed an advanced online radiation measurement cum vehicle tracking system for use. For the preparedness for response to any nuclear/radiological emergency scenario which may occur anywhere, the system designed is a Global System for Mobile (GSM) based Radiation Monitoring System (GRaMS) along with a Global Positioning System (GPS). It uses an energy compensated GM detector for radiation monitoring and is attached with commercially available Global Positioning System (GPS) for online acquisition of positional coordinates with time, and GSM modem for online data transfer to a remote control centre. The equipment can be operated continuously while the vehicle is moving

  9. Application of GPRS in the remote X γ radiation monitoring system

    International Nuclear Information System (INIS)

    Wang Yanliang; Su Xiaohui; Jin Yu; Li Zhengcai; Wang Yuhong; Zhang Wentao

    2008-01-01

    This paper introduces a system sending radiation monitoring data wirelessly by GPRS network. Monitor terminal in this system can send the measured data to the monitor computer wirelessly by GPRS, then managing program of the monitor computer can process the data. When data is abnormal, there is an alarm, workers can deal with it on time. (authors)

  10. Real Time Radiation Monitoring Using Nanotechnology

    Science.gov (United States)

    Li, Jing (Inventor); Hanratty, James J. (Inventor); Wilkins, Richard T. (Inventor); Lu, Yijiang (Inventor)

    2016-01-01

    System and method for monitoring receipt and estimating flux value, in real time, of incident radiation, using two or more nanostructures (NSs) and associated terminals to provide closed electrical paths and to measure one or more electrical property change values .DELTA.EPV, associated with irradiated NSs, during a sequence of irradiation time intervals. Effects of irradiation, without healing and with healing, of the NSs, are separately modeled for first order and second order healing. Change values.DELTA.EPV are related to flux, to cumulative dose received by NSs, and to radiation and healing effectivity parameters and/or.mu., associated with the NS material and to the flux. Flux and/or dose are estimated in real time, based on EPV change values, using measured .DELTA.EPV values. Threshold dose for specified changes of biological origin (usually undesired) can be estimated. Effects of time-dependent radiation flux are analyzed in pre-healing and healing regimes.

  11. Monitoring of increased natural occuring radiation exposure; Arbeitsplatzueberwachung bei erhoehter natuerlicher Strahlenexposition

    Energy Technology Data Exchange (ETDEWEB)

    Guhr, Andreas [ALTRAC Radon-Messtechnik, Berlin (Germany); Leissring, Nick [Bergtechnisches Ingenieurbuero GEOPRAX, Chemnitz (Germany)

    2015-07-01

    The radiation exposure due to natural occurring sources is a special challenge for the health and safety protection at workplaces. The monitoring of the radon exposure of employees in mines, radon-spa and in water works is regulated by prescription of radiation protection. The relevant compounds of the radiation exposure are the inhalation of radon and radon daughter products; terrestrial irradiation; ingestion of radioactive contaminated materials and the inhalation of contaminated dust. The monitoring of the radiation workers is realized essentially by measurements by radiation safety officer of the performing company, by an external engineering firm as well as by control measurements of experts of local authorities. The experiences in the practice have shown that in the field of operational radiation protection only a combination of personal- and operational dosimetry is suitable to avoid health hazards by work in fields with increased natural occurring radiation exposures.

  12. Software for airborne radiation monitoring system

    International Nuclear Information System (INIS)

    Sheinfeld, M.; Kadmon, Y.; Tirosh, D.; Elhanany, I.; Gabovitch, A.; Barak, D.

    1997-01-01

    The Airborne Radiation Monitoring System monitors radioactive contamination in the air or on the ground. The contamination source can be a radioactive plume or an area contaminated with radionuclides. This system is composed of two major parts: Airborne Unit carried by a helicopter, and Ground Station carried by a truck. The Airborne software is intended to be the core of a computerized airborne station. The software is written in C++ under MS-Windows with object-oriented methodology. It has been designed to be user-friendly: function keys and other accelerators are used for vital operations, a help file and help subjects are available, the Human-Machine-Interface is plain and obvious. (authors)

  13. Radiation monitoring and dose distribution of medical workers in A.P. state 1999-2000

    International Nuclear Information System (INIS)

    Singh, D.R.; Reddy, K.S.; Kamble, M.K.; Roy, Madhumita

    2001-01-01

    Individual monitoring for external ionizing radiation is being conducted for all radiation workers in Andhra Pradesh State by TLD Unit located in Nuclear Fuel Complex, Hyderabad.The Unit comes under Personnel Monitoring Section of Bhabha Atomic Research Center, Mumbai. The aim of monitoring is to confirm that the radiation safety standards are strictly adhered in the institutions and also to investigate excessive exposures, if any. Personnel monitoring also provides data for epidemiological studies. In view of ICRP/AERB recommendations of 100 mSv dose limit for the five years block of 1994-98, the dose distribution among radiation workers in Andhra Pradesh State is analyzed for the period 1994-98. In continuation of above work, we have analyzed the data for the year 1999-2000 for various medical diagnostic procedures and these are presented

  14. Electromagnetic Radiofrequency Radiation Emitted from GSM Mobile Phones Decreases the Accuracy of Home Blood Glucose Monitors

    Directory of Open Access Journals (Sweden)

    SMJ Mortazavi

    2014-09-01

    Full Text Available Mobile phones are two-way radios that emit electromagnetic radiation in microwave range. As the number of mobile phone users has reached 6 billion, the bioeffects of exposure to mobile phone radiation and mobile phone electromagnetic interference with electronic equipment have received more attention, globally. As self-monitoring of blood glucose can be a beneficial part of diabetes control, home blood glucose testing kits are very popular. The main goal of this study was to investigate if radiofrequency radiation emitted from a common GSM mobile phone can alter the accuracy of home blood glucose monitors. Forty five female nondiabetic students aged 17-20 years old participated in this study. For Control-EMF group (30 students, blood glucose concentration for each individual was measured in presence and absence of radiofrequency radiation emitted by a common GSM mobile phone (HTC touch, Diamond 2 while the phone was ringing. For Control- Repeat group (15 students, two repeated measurements were performed for each participant in the absence of electromagnetic fields. The magnitude of the changes between glucose levels in two repeated measurements (ΔC in Control-Repeat group was 1.07 ± 0.88 mg/dl while this magnitude for Control-EMF group was 7.53 ± 4.76 mg/dl (P < 0.001, two-tailed test. To the best of our knowledge, this is the first study to assess the electromagnetic interference in home blood glucose monitors. It can be concluded that electromagnetic interference from mobile phones has an adverse effect on the accuracy of home blood glucose monitors. We suggest that mobile phones should be used at least 50 cm away from home blood glucose monitors.

  15. Automatic data acquisition system of environmental radiation monitor with a personal computer

    International Nuclear Information System (INIS)

    Ohkubo, Tohru; Nakamura, Takashi.

    1984-05-01

    The automatic data acquisition system of environmental radiation monitor was developed in a low price by using a PET personal computer. The count pulses from eight monitors settled at four site boundaries were transmitted to a radiation control room by a signal transmission device and analyzed by the computer via 12 channel scaler and PET-CAMAC Interface for graphic display and printing. (author)

  16. The application and development on radiation monitoring microcomputer management system in design of a certain project

    International Nuclear Information System (INIS)

    Zhang Hongyou

    1993-01-01

    A scheme of a radiation monitoring system with a RMMMS (Radiation Monitoring Microcomputer Management System) has been designed for the first time in the radiation protection design of a certain nuclear projection undertaken by the BINE (Beijing Institute of Nuclear Engineering). Meanwhile, we accepted the research task of the RMMMS that can manage 40 monitoring channel. The key factors of radiation monitors, microcomputer, information management and systematic design method are considered in the development of the RMMMS. This paper presents briefly the scheme and functions of the RMMMS

  17. Development of CaSO4:Dy based ring dosemeter for extremity monitoring of radiation workers in India

    International Nuclear Information System (INIS)

    Srivastava, Kshama; Meenal, P.; Bhagat, R.V.; Singh, R.; Kolambe, D.H.; Chougaonkar, M.P.; Sapra, B.K.

    2014-01-01

    Extremity dosemeters are required to be worn in cases where the dose to extremities is expected to be significantly greater than the dose to the whole body. In India, CaSO 4 :Dy based three element personnel monitoring TLD badge worn at chest and wrist level are used for whole body and extremity monitoring, respectively. Presently no official/legal finger dosemeter is available for extremity monitoring for radiation workers in the country. To cater to the long standing requirement of finger dosimeter, a new compact three-element Extremity Ring Badge Dosemeter (ERBD) has been developed for measurement of the equivalent doses received by the extremities of radiation workers in terms of operational quantity Hp(0.07). It was aimed to meet the performance requirement of IEC/ISO standards. This paper gives the design detail and result of experimental studies of ERB dosemeter

  18. Exploiting Novel Radiation-Induced Electromagnetic Material Changes for Remote Detection and Monitoring: Final Progress Report

    Science.gov (United States)

    2016-04-01

    Exploiting Novel Radiation -Induced Electromagnetic Material Changes for Remote Detection and Monitoring: Final Progress Report Distribution...assess the effects of ionizing radiation on at least three classes of electromagnetic materials. The proposed approach for radiation detection was...that was desired to be monitored remotely. Microwave or low millimeter wave electromagnetic radiation would be used to interrogate the device

  19. Radiation monitoring. Report covering period 1 Oct 1994 - 31 Dec 1994

    International Nuclear Information System (INIS)

    1995-01-01

    This quarterly report on radiation monitoring in the Manchester Area uses experimental data and graphs compiled using archive materials to present a picture of gamma radiation air monitoring between 1st October 1994 and 31st December 1994. Compiled for local fire and civil defense authorities and pollution advisory body, data was collected at ten outstations. Temperature, barometric pressure, UVA and UVB readings were taken. Performance of equipment, including maintenance and outages at outstations is included. (UK)

  20. UNLAMINATED GAFCHROMIC EBT3 FILM FOR ULTRAVIOLET RADIATION MONITORING.

    Science.gov (United States)

    Welch, David; Randers-Pehrson, Gerhard; Spotnitz, Henry M; Brenner, David J

    2017-11-01

    Measurement of ultraviolet (UV) radiation is important for human health, especially with the expanded usage of short wavelength UV for sterilization purposes. This work examines unlaminated Gafchromic EBT3 film for UV radiation monitoring. The authors exposed the film to select wavelengths in the UV spectrum, ranging from 207 to 328 nm, and measured the change in optical density. The response of the film is wavelength dependent, and of the wavelengths tested, the film was most sensitive to 254 nm light, with measurable values as low as 10 µJ/cm2. The film shows a dose-dependent response that extends over more than four orders of magnitude. The response of the film to short wavelength UV is comparable to the daily safe exposure limits for humans, thus making it valuable as a tool for passive UV radiation monitoring. © The Author 2017. Published by Oxford University Press. All rights reserved. For Permissions, please email: journals.permissions@oup.com.

  1. A national computerized system for monitoring operational radiation exposure

    International Nuclear Information System (INIS)

    Canipelle, A.D.

    1996-01-01

    In parallel to the expansion of the number of French nuclear power plant units in operation, maintenance actions have multiplied, which has meant calling upon the services of a growing number of increasingly specialized workers. It has therefore proved necessary to reinforce the radiation dose rate surveillance of these workers. As a result, certain companies decided to set up their own occupational radiation dose monitoring system, in addition to mandatory monitoring by the OPRI, using dosemeters, generally electronic or thermoluminescent film badges, supplied by the subcontractor companies or nuclear facility operators. This enables acquiring fast and accurate knowledge of the radiation doses received by the workers. For this type of surveillance to be fully efficient, a data centralization system was required, able to provide frequent, even daily readings if necessary, of the dose received during the current month or for any period of time, up to the sum of the doses accumulated over five years. (author)

  2. Low-level radioactive gas monitor for natural gas operations

    International Nuclear Information System (INIS)

    Armstrong, F.E.

    1969-11-01

    A portable radioactivity detection system for monitoring the tritium content of natural gas under field conditions has been developed. The sensing device employed is a complex proportional counting assembly operated without the use of massive shielding previously employed with such low-level radiation detectors. The practical limit of detection for the system is a tritium content of 10 -9 microcurie per cc of natural gas. All components of the system are packaged in three waterproof cases weighing slightly less than 30 kg each. Power requirement is 500 watts of 120 volt, 60 Hz current. Operation is fully automatic with a printed record produced at predetermined time intervals

  3. SGR-76 gamma radiation level indicator

    International Nuclear Information System (INIS)

    Chubinskij-Nadezhdin, I.V.

    1978-01-01

    The design of a gamma-radiation level indicator is described; the instrument is part of a mobile radiometric laboratory (MRL). The design of the instrument permits gamma-radiation dose rates recording at 0.2-200 R/hr, and signals on gamma-background levels. The instrument has two separate threshold levels of signalling actuation. The light signalling at the first level is precautionary, and the sound signalling at the second level indicates the necessity of taking a decision as to whether or not the MRL can remain in the gamma-radiation field. Halogenic counters operating in a current mode are used as detectors. The basic error in recording the dose rate amounts to +-25%. Overall dimensions of the instrument 150x280x100 mm; weight less than 2.5 kg

  4. Monitoring of contamination of atmospheric environment by radiation

    International Nuclear Information System (INIS)

    Ise, Hiroaki

    1995-01-01

    Atmospheric pollution has become a worldwide problem regardless of developed industrial nations and developing countries. In particular, the pollution due to automobile exhaust gas, the carcinogenic particles in diesel exhaust and their relation to various respiratory diseases are the problems. Nitrogen oxides and sulfur oxides in exhaust gas become the cause of acid rain. Radiation began to be utilized for the measurement of the concentration of floating particles and the amount of fallout dust, the forecast of the generation and diffusion of pollutants, the elucidation of the contribution of generation sources in wide areas and so on. In this report, the circumstances that radiation became to be utilized for monitoring atmospheric environment and the present status and the perspective of the radiation utilization in the field of the preservation of atmospheric environment are described. The progress of the method of measuring floating particles in Japan is explained. The automatic measurement of floating particles by β-ray absorption method and the application of β-ray absorption method to the measurement of the amount of fallout dust, generation source particles and the exposure to floating particles of individuals for health control are described. The utilization of radiation for real time monitoring, the investigation of the generation of blown-up dust, atmospheric diffusion experiment and the elucidation of the contribution of generation sources by PIXE radioactivation analysis are reported. (K.I.)

  5. Radiation ecological monitoring in NPP region

    International Nuclear Information System (INIS)

    Egorov, Yu.A.; Kazakov, S.V.

    1985-01-01

    The known principle of sanitary-hygienic regulation of NPP radiation effect on man and environment is analyzed. An ecological approach is required to optimize NPP relations with the environment and to regulate radioactivity of the NPP - environment system. The ecological approach envisages the development of standards of permissible concentrations of radioactive and chemical substances (as well as heat) in natural environment, taking into account their synergism, corresponding to ecologically permissible response reactions of biota to their effect. The ecological approach also comprises the sanitary-hygienic principle of radiation protection of man. Attention is paid to ecological monitoring in NPP region, comprising consideration of factors, affecting the environment, evaluation of the actual state of the environment, prediction of the environmental state, evaluation of the expected environmental state

  6. Radiation risks and monitoring of transboundary rivers of Kazakhstan

    International Nuclear Information System (INIS)

    Kadyrzhanov, K.K.; Solodukhin, V.P.; Khazhekber, S.; Poznyak, V.L.; Chernykh, E.E.; Passell, H.D.

    2006-01-01

    Full text: The condition of the water resources of the Republic of Kazakhstan is characterized with their whole deficiency as well as their high pollution and desiccation. The situation is also aggravated with much relaxation of work coordination on regulation of trans-boundary river flows and control of their water quality as a result of the USSR collapse and isolation of separate republics. The absence of objective information on water condition of rivers and their contamination sources creates a danger of high ecological risk and psychological stress for inhabitants, localities of that related to the basins of these rivers, and serves as reasoning for claims (occasionally unreasonable) to neighboring countries. Following rivers are the largest trans-boundary ones in Kazakhstan: Ile, Syrdarya, Ural and Irtysh. All these rivers are of great importance for people's life-support of the republic. At the same time presence of a number of large industrial centers, agricultural enterprises and radiation-dangerous objects in the basins of these rivers creates a potential danger of chemical and radiation contamination for their water flows. Objective information on its influence rate is required. The most acceptable form of the control of radiation and hydro-chemical situation in the basins of transboundary rivers is their monitoring based on modern nuclear-and-physical methods of analysis. Very important factor in organization of such monitoring system is participation of all the countries concerned with the basin of the river under the control. There is a work experience of many years in Central Asia on monitoring of large Syrdarya and Amudarya rivers. These works have been carried out since 2000 with the framework of the International project NAVRUZ. Participants of this project are organizations of nuclear profile from Uzbekistan, Kirghizia, Tajikistan and Kazakhstan. The collaborator of this project is the Sandia National Laboratories (SNL), USA. Experience of these

  7. Principles of monitoring for the radiation protection of the population

    International Nuclear Information System (INIS)

    Sowby, F.D.

    1984-01-01

    In this report all exposures are considered except occupational exposure and exposure to patients from medical uses of radiation. The subject is dealt with under the following headings: explanation of terms and relevant recommendations of the I.C.R.P., interaction between modelling and monitoring, general objectives and requirements of monitoring programmes, monitoring of source, environment and individuals within the population, quality assurance. (U.K.)

  8. Standard evaluation techniques for containment and surveillance radiation monitors

    International Nuclear Information System (INIS)

    Fehlau, P.E.

    1982-01-01

    Evaluation techniques used at Los Alamos for personnel and vehicle radiation monitors that safeguard nuclear material determine the worst-case sensitivity. An evaluation tests a monitor's lowest sensitivity regions with sources that have minimum emission rates. The result of our performance tests are analyzed as a binomial experiment. The number of trials that are required to verify the monitor's probability of detection is determined by a graph derived from the confidence limits for a binomial distribution. Our testing results are reported in a way that characterizes the monitor yet does not compromise security by revealing its routine performance for detecting process materials

  9. Application of real time spectrum measurement to radiation monitors

    International Nuclear Information System (INIS)

    Matsuno, K.; Watanabe, M.; Sakamaki, T.

    1996-01-01

    A multichannel analyzer (MCA) and two realtime spectrum monitoring methods have been developed for use in radiation monitors. The new MCA was designed to be installed at a local site as a component of a radiation monitor. The MCA repeats spectrum measurement at short intervals (Δt) and, after each measurement, transmits a spectrum datum to the operation console. The authors applied two methods to process Δt spectrum counts for each channel for longer time interval. One method of processing counts is the 'running average (RA) method'. The other method is the 'exponential smoothing (ES) method', which simulates RC rate meters by subtracting a fraction corresponding to the accumulated counts. Relative standard deviations for each channel can be made the same by selecting an appropriate value. The response with the 'ES' method is initially faster than that with the 'RA' method, but the 'RA' method allows a full response to be reached at a predictable time. (author)

  10. Calibration of radiation protection area monitoring instruments in Sudan

    International Nuclear Information System (INIS)

    Suliman, I.I.; Youssif, B.E.; Beineen, A.A.; Hassan, M.

    2010-01-01

    This article presents results of measurements for the calibration of radiation protection area monitoring instruments carried out during the period 2006-2008 at Secondary Standard Dosimetry Laboratory of Sudan. The work performed included quality assurance measurements, measurements for the dosimeter calibrations and uncertainty analysis. Calibrations were performed using 137 Cs gamma ray sources produced by OB 85 and OB 34/1 gamma calibrators producing air kerma rate that ranged from 10 μGy/h to 50 mGy/h. Area monitoring instruments were calibrated in terms of ambient dose equivalent, H*(10) derived using air kerma to ambient dose equivalent conversion coefficients. Results are presented for 78 area monitoring instruments representing most commonly used types in Sudan. Radioactive check source measurements for the reference chamber showed deviation within 1% limit. The accuracy in the beam output measurements was within 5% internationally considered as acceptable. The results highlighted the importance of radiation protection calibrations. Regulations are further need to ensure safety aspect really meet the required international standards.

  11. The design of intelligentized nuclear radiation monitoring detector

    International Nuclear Information System (INIS)

    Meng Yan; Fang Zongliang; Wen Qilin; Li Lirong; Hu Jiewei; Peng Jing

    2010-01-01

    This paper introduced an intelligentized nuclear radiation monitoring detector. The detector contains GM tubes, high voltage power supply and MCU circuit. The detector connect terminal via reformative serial port to provide power, accept the data and sent the command. (authors)

  12. General approaches to the reconstruction of radiation monitoring systems at the nuclear power plants

    International Nuclear Information System (INIS)

    Nosovskij, A.V.; Garin, E.V.; Istomin, N.I.; Perminov, V.G.

    1998-01-01

    The article deals with the issue of the Chernobyl NPP radiation monitoring systems and equipment to make them meet the latest safety requirements and take into account the radiation situation at the ChNPP site after the accident of 1986. The descriptions of the existing radiation monitoring systems are given. The appropriate modifications in the systems structure as the initial (first) stage in establishing a new radiation monitoring system (RMS) based on the NPP general radiation safety principles are proposed. It is noted that reconstruction shall include the number of technical means important for arranging the informational and analytical system in addition to the existing one without any violations in its features. Later, the system shall be extended due to the technological functions extension. 7 refs., 4 figs

  13. Guideline for design and construction radiation monitoring equipments for Tokai reprocessing plant

    International Nuclear Information System (INIS)

    Miyabe, Kenjiro; Ninomiya, Kazushige; Jin, Kazumi; Morifuji, Masayuki; Nemoto, Kazuhiko; Sato, Akira; Kawai, Keiichi

    1999-12-01

    Various kind of radiation monitoring equipment are used in radiation controlled area at each facility of Tokai reprocessing plant. These equipments have been designed and constructed based on the users requirements, and permitted by governmental regulation office. And, design has been carried out in consideration of the adoption of the new technology and our operational experience. Then, it has been used effectively for the radiation control of the facilities. This report summarizes the technical requirements that should be taken into consideration in the design and installation of radiation monitoring equipments. These requirements are fundamentally applicable when the equipments of the new facilities will be designed or the present instruments will be replaced. (author)

  14. External radiation levels in installations of nuclear technology center

    International Nuclear Information System (INIS)

    Maletta, Paulo Guilherme M.; Filipetto, Joao; Wakabayashi, Tetsuaki; Silva, Teogenes A. da

    2005-01-01

    The radiological protection is a basic activity of nuclear technology center so that can carry through its activities with security, having to be planned and executed with total effectiveness. One of the basic tools of the radiological protection is the adoption of monitoring programs, that have as objective generality to evaluate the radiological conditions of the workstation and to assure that these conditions are acceptable safe for the displayed individuals, either workers or members of the public, as established in the basic norms of radiological protection. The Centro de Desenvolvimento da Tecnologia Nuclear - CDTN, first institution in Brazil, created in 1952 to entirely dedicate the related works to the nuclear area, to own 39 building, of which they are kept the Triga Reactor, Irradiation Gamma Laboratory, Reject Laboratory, Calibration Dosemeters Laboratory and others. In such installations, radioactive materials are produced, handled, processed and stored, being necessary the levels of external radiation ambient monitoring. As part of the radioprotection plan, monitoring 63 points on strategically located in the external areas to the building of CDTN, using characterized and calibrated thermoluminescence dosemeters. This work describes the dose distribution of the points, the doses evaluation procedure and the 4 results carried through between 2001 and 2004. The data demonstrate the attendance to the level of security established in the basic norm, what it contributed for the operation licensing of to the IBAMA. (author)

  15. The status and prospective of environmental radiation monitoring stations in Saudi Arabia

    Science.gov (United States)

    Al-Kheliewi, Abdullah S.; Holzheimer, Clous

    2014-09-01

    The use of nuclear technology requires an environmental monitoring program to ensure the safety of the environment, and to protect people from the hazards of radioactive materials, and nuclear accidents. Nuclear accidents are unique, for they incur effects that surpass international frontiers, and can even have a long lasting impact on Earth. Such was the case of the Chernobyl accident in the Ukraine on April 6, 1986. For that purpose, international and national efforts come together to observe for any nuclear or radioactive accident. Many states, including Saudi Arabia which oversees the operation of the National Radiation, Environmental and Early Monitoring Stations, The Radiation Monitoring Stations(RMS's) are currently scattered across 35 cities in the country,. These locations are evaluated based on various technological criteria such as border cities, cities of high population density, wind direction, etc. For new nuclear power plants hovering around, it is strongly recommended to increase the number of radiation monitoring stations to warn against any threat that may arise from a nuclear leak or accident and to improve the performance of the existing RMS's. SARA (Spectroscopic Monitoring Station for air) should be implemented due to the high sensitivity to artificial radiation, automatic isotope identification, free of maintenance, and fully independent due to solar power supply (incl. battery backup) and wireless communication (GPRS).

  16. The status and prospective of environmental radiation monitoring stations in Saudi Arabia

    International Nuclear Information System (INIS)

    Al-Kheliewi, Abdullah S.; Holzheimer, Clous

    2014-01-01

    The use of nuclear technology requires an environmental monitoring program to ensure the safety of the environment, and to protect people from the hazards of radioactive materials, and nuclear accidents. Nuclear accidents are unique, for they incur effects that surpass international frontiers, and can even have a long lasting impact on Earth. Such was the case of the Chernobyl accident in the Ukraine on April 6, 1986. For that purpose, international and national efforts come together to observe for any nuclear or radioactive accident. Many states, including Saudi Arabia which oversees the operation of the National Radiation, Environmental and Early Monitoring Stations, The Radiation Monitoring Stations(RMS’s) are currently scattered across 35 cities in the country,. These locations are evaluated based on various technological criteria such as border cities, cities of high population density, wind direction, etc. For new nuclear power plants hovering around, it is strongly recommended to increase the number of radiation monitoring stations to warn against any threat that may arise from a nuclear leak or accident and to improve the performance of the existing RMS’s. SARA (Spectroscopic Monitoring Station for air) should be implemented due to the high sensitivity to artificial radiation, automatic isotope identification, free of maintenance, and fully independent due to solar power supply (incl. battery backup) and wireless communication (GPRS)

  17. The status and prospective of environmental radiation monitoring stations in Saudi Arabia

    Energy Technology Data Exchange (ETDEWEB)

    Al-Kheliewi, Abdullah S. [National Center for Radiation Protection, King Abdulaziz City for Science and Technology, 11442 Riyadh (Saudi Arabia); Holzheimer, Clous [ENVINET GmbH, Environmental Radiation Detection, Hans-Pinsel-Straße 4, 85540 Haar (Munich) (Germany)

    2014-09-30

    The use of nuclear technology requires an environmental monitoring program to ensure the safety of the environment, and to protect people from the hazards of radioactive materials, and nuclear accidents. Nuclear accidents are unique, for they incur effects that surpass international frontiers, and can even have a long lasting impact on Earth. Such was the case of the Chernobyl accident in the Ukraine on April 6, 1986. For that purpose, international and national efforts come together to observe for any nuclear or radioactive accident. Many states, including Saudi Arabia which oversees the operation of the National Radiation, Environmental and Early Monitoring Stations, The Radiation Monitoring Stations(RMS’s) are currently scattered across 35 cities in the country,. These locations are evaluated based on various technological criteria such as border cities, cities of high population density, wind direction, etc. For new nuclear power plants hovering around, it is strongly recommended to increase the number of radiation monitoring stations to warn against any threat that may arise from a nuclear leak or accident and to improve the performance of the existing RMS’s. SARA (Spectroscopic Monitoring Station for air) should be implemented due to the high sensitivity to artificial radiation, automatic isotope identification, free of maintenance, and fully independent due to solar power supply (incl. battery backup) and wireless communication (GPRS)

  18. Radiating confidence

    International Nuclear Information System (INIS)

    Rush, P.

    1988-01-01

    Radiation monitoring systems for operators handling radioactive wastes are described. These include a personnel monitoring system which is suitable for small groups (ie as few as 50) of personnel. The use of microelectronics enable facilities such as automatic personal dose recording with three accumulative registers and automatic reporting of exceeded dose limits. At a controlled entrance the user is identified with a personal identification number. Exit is then also monitored. The use of pocket dosimeters increase the flexibility of this system. In another system a 'rotary man lock' only allows exit from the radiation controlled zone when satisfactory radiation checks have been made. The radiation and security checks available with this system are described. A 'sack monitor' for low level wastes contained in plastic bags is illustrated. (U.K.)

  19. Can low-level radiation cause cancer?

    International Nuclear Information System (INIS)

    Trosko, J.E.

    1995-01-01

    Health in a multicellular organism is maintained by homeostatic processes. Disruption of these homeostatic controls at the molecular, biochemical, cellular, and organ systems levels can be brought about by irreversible changes in the genetic material (mutagenesis), cell death (cytotoxicity), or reversible changes in the expression of genes at the transcriptional, translational, or posttranslational levels (epigenesis). While radiation is known to induce DNA damage/mutations, cell, death and epigenetic changes, in addition to cancers that are found in radiation-exposed animals, experimentally, and in humans, epidemiologically, the question is, At low-level exposure, what is the risk that cancers are open-quotes causedclose quotes by the radiation?

  20. Comparison of a continuous working level monitor for radon daughters with conventional grab-sampling

    International Nuclear Information System (INIS)

    Bigu, J.; Grenier, M.

    1982-08-01

    An evaluation of a radon daughter monitor was carried out under laboratory controlled conditions. The monitor operates on continuous sampling and time integrating principles and was tested in conjunction with a newly designed, large radon/thoron room calibration facility. The monitor was tested under constant and rapidly fluctuating radiation conditions. Experimental data obtained with the monitor were compared with data obtained by conventional grab-sampling and with an automated radon daughter/thoron daughter 'grab-sampler'. The Working Level used in the tests ranged from less than 0.01 WL to approximately 10 WL. The measurements were carried out under low aerosol concentration (1 x 10 3 - 2 x 10 3 cm -3 , approximately) to study plate-out effects in the sampling head. Good agreement (within about 10 %) was found between the monitor, conventional grab-sampling and the automated grab-sampler. The monitor should prove quite flexible, useful and reliable for monitoring underground and surface environments in the uranium mining industry

  1. Environmental and Source Monitoring for Purposes of Radiation Protection. Safety Guide (Spanish ed.)

    International Nuclear Information System (INIS)

    2010-01-01

    The purpose of this Safety Guide is to provide international guidance, coherent with contemporary radiation protection principles and IAEA safety requirements, on the strategy of monitoring in relation to: (a) control of radionuclide discharges under practice conditions, and (b) intervention, such as in cases of nuclear or radiological emergencies or past contamination of areas with long lived radionuclides. Three categories of monitoring are discussed: monitoring at the source of the discharge (source monitoring), monitoring in the environment (environmental monitoring) and monitoring of individual exposure in emergencies (individual monitoring). The Safety Guide also provides general guidance on assessment of the doses to critical groups of the population due to the presence of radioactive materials or radiation fields in the environment both from routine operation of nuclear and other related facilities (practice) and from nuclear or radiological emergencies and past contamination of areas with long lived radionuclides (intervention). The dose assessments are based on the results of source monitoring, environmental monitoring, individual monitoring or their combinations. This Safety Guide is primarily intended for use by national regulatory bodies and other agencies involved in national systems of radiation monitoring, as well as by operators of nuclear installations and other facilities where natural or human made radionuclides are treated and monitored. Contents: 1. Introduction; 2. Meeting regulatory requirements for monitoring in practices and interventions; 3. Responsibilities for monitoring; 4. Generic aspects of monitoring programmes; 5. Programmes for monitoring in practices and interventions; 6. Technical conditions for monitoring procedures; 7. Considerations in dose assessment; 8. Interpretation of monitoring results; 9. Quality assurance; 10. Recording of results; 11. Education and training; Glossary.

  2. PRD3000: A novel Personnel Radiation Detector with Radiation Exposure Monitoring

    International Nuclear Information System (INIS)

    Fallu-Labruyere, A.; Micou, C.; Schulcz, F.; Fellinger, J.

    2015-01-01

    PRD3000 TM is a novel Personal Radiation Detector (PRD) with personnel radiation dose exposure monitoring. It is intended for First Responders, Law Enforcement, Customs Inspectors protecting critical infrastructures for detecting unexpected radioactive sources, who also need real time Hp(10) dose equivalent information. Traditional PRD devices use scintillator materials instrumented through either a photomultiplier tube or a photodiode photodetector. While the former is bulky and sensitive to magnetic fields, the latter has to compromise radiation sensitivity and energy threshold given its current noise per unit of photo-detection surface. Recently, solid state photodetectors (SiPM), based on arrays of Geiger operated diodes, have emerged as a scalable digital photodetector for photon counting. Their strong breakdown voltage temperature dependence (on the order of tens of milli-volts per K) has however limited their use for portable instruments where strong temperature gradients can be experienced, and limited power is available to temperature stabilize. The PRD3000 is based on the industry standard DMC3000 active dosimeter that complies with IEC 61526 Ed. 3 and ANSI 42.20 for direct reading personal dose equivalent meters and active personnel radiation monitors. An extension module is based on a CsI(Tl) scintillator readout by a temperature compensated SiPM. Preliminary nuclear tests combined with a measured continuous operation in excess of 240 hours from a single AAA battery cell indicate that the PRD3000 complies with the IEC 62401 Ed.2 and ANSI 42.32 without sacrificing battery life time. We present a summary of the device test results, starting with performance stability over a temperature range of - 20 deg. C to 50 deg. C, false alarm rates and dynamic response time. (authors)

  3. PRD3000: A novel Personnel Radiation Detector with Radiation Exposure Monitoring

    Energy Technology Data Exchange (ETDEWEB)

    Fallu-Labruyere, A.; Micou, C.; Schulcz, F.; Fellinger, J. [Mirion Technologies - MGPI SA (France)

    2015-07-01

    PRD3000{sup TM} is a novel Personal Radiation Detector (PRD) with personnel radiation dose exposure monitoring. It is intended for First Responders, Law Enforcement, Customs Inspectors protecting critical infrastructures for detecting unexpected radioactive sources, who also need real time Hp(10) dose equivalent information. Traditional PRD devices use scintillator materials instrumented through either a photomultiplier tube or a photodiode photodetector. While the former is bulky and sensitive to magnetic fields, the latter has to compromise radiation sensitivity and energy threshold given its current noise per unit of photo-detection surface. Recently, solid state photodetectors (SiPM), based on arrays of Geiger operated diodes, have emerged as a scalable digital photodetector for photon counting. Their strong breakdown voltage temperature dependence (on the order of tens of milli-volts per K) has however limited their use for portable instruments where strong temperature gradients can be experienced, and limited power is available to temperature stabilize. The PRD3000 is based on the industry standard DMC3000 active dosimeter that complies with IEC 61526 Ed. 3 and ANSI 42.20 for direct reading personal dose equivalent meters and active personnel radiation monitors. An extension module is based on a CsI(Tl) scintillator readout by a temperature compensated SiPM. Preliminary nuclear tests combined with a measured continuous operation in excess of 240 hours from a single AAA battery cell indicate that the PRD3000 complies with the IEC 62401 Ed.2 and ANSI 42.32 without sacrificing battery life time. We present a summary of the device test results, starting with performance stability over a temperature range of - 20 deg. C to 50 deg. C, false alarm rates and dynamic response time. (authors)

  4. Radiation environmental monitoring and assessment of plant-221 site ten years after decommissioning

    International Nuclear Information System (INIS)

    Li Yang; Gu Zhijie; Pan Wei; Ren Xiaona; Hu Xiaolin; She Haiqiang

    2011-01-01

    More than 10 years have passed since nuclear facility decommissioning practice for Plant-221 finished. Environmental radiation monitoring and post assessment of the decommissioning site of Plant-221 was carried out during 2003-2006, which was organized by Department of Environmental Protection and executed by China Institute for Radiation Protection, Environmental Radiation Monitoring station of Qinghai Province, etc. It shows that the decommissioning practice for Plant-221 complied with relevant limits for decommissioning, and its environmental radiation situation has not had significant change in general after 10 years, and the potential impact to the public and the environmental is acceptable. (authors)

  5. Study of radiation portal monitor and its application to metal recycling industry

    International Nuclear Information System (INIS)

    Pujol, L.; Lara-Calleja, S.; Suarez-Navarro, M. J.; Gonzalez-Gonzalez, J. A.

    2009-01-01

    The industry of the iron and the steel in one of the most important sectors in Spain for its economic development. the recycling of metallic materials as well as the import of metallic scrap is very significant. Several reports on accidental dispersion or smelting of radioactive sources in metal recycling industries confirm the possibility that radioactive material might be mixed with scrap. In consequence, this type of accident shows the necessity of a rigorous and specific radiation control of the sector. The control of these materials with radioactive content can be carried out with radiation portal monitors installed at the entrance of these industries. The detection of radioactive materials presents special features as the continuous background acquisition or the minimisation of the relatively large number of innocent/nuisance detections. In the present work, we study a radiation portal monitor, the FHT-1388-T Thermo-Eberline. This is one of the usual radiation portal systems installed at the entrance of the metal recycling industry. Se study the characteristics and parameters of this portal monitor to optimise its use. furthermore, we propose some rapid tests for radiation portal systems in metal recycling industry. (Author) 16 refs

  6. Un-laminated Gafchromic EBT3 film for ultraviolet radiation monitoring

    International Nuclear Information System (INIS)

    Welch, David; Randers-Pehrson, Gerhard; Brenner, David J.; Spotnitz, Henry M.

    2017-01-01

    Measurement of ultraviolet (UV) radiation is important for human health, especially with the expanded usage of short wavelength UV for sterilization purposes. This work examines un-laminated Gafchromic EBT3 film for UV radiation monitoring. The authors exposed the film to select wavelengths in the UV spectrum, ranging from 207 to 328 nm, and measured the change in optical density. The response of the film is wavelength dependent, and of the wavelengths tested, the film was most sensitive to 254 nm light, with measurable values as low as 10 μJ/cm 2 . The film shows a dose-dependent response that extends over more than four orders of magnitude. The response of the film to short wavelength UV is comparable to the daily safe exposure limits for humans, thus making it valuable as a tool for passive UV radiation monitoring. (authors)

  7. Towards a Long-Term Strategy for Voluntary-Based Internal Radiation Contamination Monitoring: Representativeness of the Monitoring Results in Fukushima, Japan

    Directory of Open Access Journals (Sweden)

    Shuhei Nomura

    2017-06-01

    Full Text Available Following Japan’s 2011 Fukushima nuclear incident, voluntary participation, rather than mandatory, was adopted as the default scenario for individual radiation monitoring. We evaluated the representativeness of the internal monitoring results from voluntary participants in Minamisoma City, which is located 10–40 km from the Fukushima nuclear plant. Of approximately 70,000 individuals who were residing in Minamisoma City before the incident, a total of 19,263 residents (aged ≥21 years participated in the monitoring from 1 October 2011 to 31 March 2015. Based on regression projection techniques with the available data obtained from the voluntary participants, the modeled probabilities of radiocesium (Cs detection in October 2011 for Cs-137 and Cs-134 were 66.9% and 52.9%, respectively, which declined dramatically within a year following the incident. The rate of decline had stagnated since mid-2012, and the probability was close to zero after mid-2014. Sufficient agreement between the modeled probabilities of Cs detection (for the whole population versus the measured Cs levels (for voluntary participants was observed, except for Cs-134 in October 2011, indicating that the voluntary monitoring participant group was a good representative sample. Our findings affirmed the clinical importance of voluntary-based monitoring as a screening and dose-assessment tool in a post-nuclear incident. Our study informs societal decision-making regarding the long-term maintenance of the monitoring program under the current low exposure levels.

  8. Characterisation of ionisation chambers for a mixed radiation field and investigation of their suitability as radiation monitors for the LHC.

    Science.gov (United States)

    Theis, C; Forkel-Wirth, D; Perrin, D; Roesler, S; Vincke, H

    2005-01-01

    Monitoring of the radiation environment is one of the key tasks in operating a high-energy accelerator such as the Large Hadron Collider (LHC). The radiation fields consist of neutrons, charged hadrons as well as photons and electrons with energy spectra extending from those of thermal neutrons up to several hundreds of GeV. The requirements for measuring the dose equivalent in such a field are different from standard uses and it is thus necessary to investigate the response of monitoring devices thoroughly before the implementation of a monitoring system can be conducted. For the LHC, it is currently foreseen to install argon- and hydrogen-filled high-pressure ionisation chambers as radiation monitors of mixed fields. So far their response to these fields was poorly understood and, therefore, further investigation was necessary to prove that they can serve their function well enough. In this study, ionisation chambers of type IG5 (Centronic Ltd) were characterised by simulating their response functions by means of detailed FLUKA calculations as well as by calibration measurements for photons and neutrons at fixed energies. The latter results were used to obtain a better understanding and validation of the FLUKA simulations. Tests were also conducted at the CERF facility at CERN in order to compare the results with simulations of the response in a mixed radiation field. It is demonstrated that these detectors can be characterised sufficiently enough to serve their function as radiation monitors for the LHC.

  9. Preparedness for response to the challenges from orphan sources: nationwide environmental radiation mapping with state of the art monitoring systems

    International Nuclear Information System (INIS)

    Saindane, Shashank S.; Pradeepkumar, K.S.; Suri, M.M.K.; Sharma, D.N.

    2008-01-01

    Based on the various international reports on orphan sources, the potential for radiological emergencies in public domain is recognized as a cause of concern. To detect the presence of any such orphan sources and to strengthen the preparedness for response to any radiological emergencies in public domain, a nationwide radiation mapping programme was initiated in India. Various radiation monitoring systems, few of them integrated with Global Positioning System (GPS) installed in mobile monitoring vans were used for this purpose. This monitoring also helped in generating the base line dose rate data of the cities and also in demonstrating the methodology of environmental monitoring for locating the presence of orphan sources, if any. During the detailed monitoring of various cities of the country, different systems such as GSM based Radiation Monitoring System (GRaMS), Compact Radiation Monitoring system, Portable Mobile Gamma Spectrometry System, Gamma Tracer System etc. installed in a vehicle were made to continuously acquire the data at a varying rate from 10 sec to 1 minute acquisition time. These systems can measure dose rate in the range of 0.01 - 100 μGy h -1 and can detect 7.4 MBq (200 μCi) of 60 Co and 25 MBq (675 μCi) of 137 Cs from a distance of 5 metre. Average dose rate recorded during these environmental monitoring was 81 ± 07 nGy h -1 with a maximum of 210 ± 11 nGyh -1 at Bangalore (attributed to the presence of K-40). The digital topographic map and the data acquired from the radiation mapping are used to generate terrestrial radiation map. This radiation profile stored in the database can be used as reference while carrying out the impact assessment following any nuclear / radiological emergencies. These systems also help to tag the radiation levels along with positional coordinates online onto the GIS map of the area. GRaMS also demonstrated its capability for online transmission of the data to the centralized data acquisition Base Station

  10. Course of radiation protection: technical level

    International Nuclear Information System (INIS)

    2002-01-01

    The course handbook on radiation protection and nuclear safety, technical level prepared by scientists of the Nuclear Regulatory Authority (ARN) of the Argentina Republic, describes the subjects in 19 chapters and 2 annexes. These topics detailed in the text have the following aspects: radioactivity elements, interaction of the radiation and the matter, radio dosimetry, internal contamination dosimetry, principles of radiation detection, biological radiation effects, fundamentals of radiation protection, dose limits, optimization, occupational exposure, radiation shielding, radioactive waste management, criticality accidents, safe transport of radioactive materials, regulatory aspects

  11. Development of natural radiation model for evaluation of background radiation in radiation portal monitor

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Jong Bum; Lee, Jin Hyung; Moon, Myung Kook [Radioisotope Research and Development Division, Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2016-11-15

    In ports and airports, radiation portal monitors (RPM) are deployed to detect illicit radioactive materials. Detected gamma rays in a RPM include background radiation and radiation from a freight. As a vehicle moves through the RPM, the vehicle causes the fluctuations in the natural background radiation signal, which ranges of up to 30%. The fluctuation increases the uncertainty of detection signal and can be a cause of RPM false alarm. Therefore, it is important to evaluate background radiation as well as radiation from a container. In this paper, a natural background radiation model was developed to evaluate RPM. To develop natural background radiation model, a Monte Carlo simulation was performed and compared with experimental measurements from a RPM for {sup 40}K, {sup 232}Th series, and {sup 235}U series, which are major sources of natural background radiation. For a natural radiation source, we considered a cylindrical soil volume with 300 m radius and 1 m depth, which was estimated as the maximum range affecting the RPM by MCNP6 simulation. The volume source model was converted to surface source by using MCNP SSW card for computational efficiency. The computational efficiency of the surface source model was improved to approximately 200 times better than that of the volume source model. The surface source model is composed of a hemisphere with 20 m radius in which the RPM and container are modelled. The natural radiation spectrum from the simulation was best fitted to the experimental measurement when portions of {sup 40}K, {sup 232}Th series, and {sup 235}U series were 0.75, 0.0636, and 0.0552 Bq·g{sup -1}, respectively. For gross counting results, the difference between simulation and experiment was around 5%. The background radiation model was used to evaluate background suppression from a 40 ft container with 7.2 m·s{sup -1} speed. In further study, background models and freight models for RPM in real container ports will be developed and applied to

  12. Design and implementation on wireless transmission platform of area radiation monitoring data

    International Nuclear Information System (INIS)

    Li Dan; Ge Liangquan; Lai Wanchang; Ren Yong; Liu Huijun; Wang Guangxi

    2011-01-01

    To solve data transmission problems of radiation area monitoring system, Wireless transmission platform is built based on ZigBee module, thus wireless transmission between the radiation area central node and the monitoring points is achieved. It introduces the framework of ZigBee protocol, APL applications between FFD and RFD module, FFD, module and central node host, and RFD module and monitoring equipment, are developed using simplified protocol stack. Wireless network is set up using a FFD module and two RFD modules, the results show that RSSI are above 50, and the data communication is normal for the transmission distance of 60 m. (authors)

  13. SEJV2 software package for radiation monitoring system of WWER 440 NPP

    International Nuclear Information System (INIS)

    Kapisovsky, V.; Jancik, O.; Kubik, I.; Bena, J.

    1993-01-01

    The main part of the radiation monitoring system at a WWER-440 (213 reactor type) nuclear power plant is the centralized 400-channel monitoring system 'SEJVAL' servicing twin reactor units. The SEJV2 software package is described developed to run on a PC with an IFS2 interface to the SEJVAL radiation monitoring system. It provides enhanced data presentation, record keeping and report generation, thus improving the efficiency of the health physics shift. The system was for the first time implemented at the Jaslovske Bohunice V-2 nuclear power plant with encouraging results. (Z.S.) 3 refs

  14. Radiation monitoring and beam dump system of the OPAL silicon microvertex detector

    CERN Document Server

    Braibant, S

    1997-01-01

    The OPAL microvertex silicon detector radiation monitoring and beam dump system is described. This system was designed and implemented in order to measure the radiation dose received at every beam crossing and to induce a fast beam dump if the radiation dose exceeds a given threshold.

  15. Radiation monitoring and actions in Finland after reactor accident in Chernobyl

    Energy Technology Data Exchange (ETDEWEB)

    Paakkola, Olli [Finnish Centre for Radiation and Nuclear Safety, Surveillance Department, Helsinki (Finland)

    1986-07-01

    In the event of a radiation hazard, the authorities participating in radiation control, act in accordance with a guide issued by the Ministry of the Interior. The guide defines the notification and warning limits to be applied between the various bodies. The institutes taking part in radiation control are the Institute of Seismology, the Finnish Meteorological Institute, the Defence Forces, the Ministry of the Interior, and the Finnish Centre for Radiation and Nuclear Safety. The continuously operated radiation monitoring stations of the Defence Forces and the Ministry of the Interior are obliged to notify the other institutes participating in the control if the dose rate of external radiation reaches the value 0.07 mR/h (0,7 microSv/h) and all radiation monitoring stations are obliged to give a warning to the other bodies if the dose rate reaches the value 1 mR/h (10 microSv/h). The Finnish Centre for Radiation and Nuclear Safety has the duty to report exceptional findings and to warn the other institutes as deemed appropriate. According to the guide, population must be warned of a sudden radiation hazard at least when the dose rate has reached the value 200 microSv/h. An alarm for seeking immediate shelter must be given at least when the dose rate exceeds the value 2000 microSv/h.

  16. Radiation monitoring and actions in Finland after reactor accident in Chernobyl

    International Nuclear Information System (INIS)

    Paakkola, Olli

    1986-01-01

    In the event of a radiation hazard, the authorities participating in radiation control, act in accordance with a guide issued by the Ministry of the Interior. The guide defines the notification and warning limits to be applied between the various bodies. The institutes taking part in radiation control are the Institute of Seismology, the Finnish Meteorological Institute, the Defence Forces, the Ministry of the Interior, and the Finnish Centre for Radiation and Nuclear Safety. The continuously operated radiation monitoring stations of the Defence Forces and the Ministry of the Interior are obliged to notify the other institutes participating in the control if the dose rate of external radiation reaches the value 0.07 mR/h (0,7 microSv/h) and all radiation monitoring stations are obliged to give a warning to the other bodies if the dose rate reaches the value 1 mR/h (10 microSv/h). The Finnish Centre for Radiation and Nuclear Safety has the duty to report exceptional findings and to warn the other institutes as deemed appropriate. According to the guide, population must be warned of a sudden radiation hazard at least when the dose rate has reached the value 200 microSv/h. An alarm for seeking immediate shelter must be given at least when the dose rate exceeds the value 2000 microSv/h

  17. A new system for radiation monitoring

    International Nuclear Information System (INIS)

    Toivonen, H.

    1993-01-01

    The Finnish authorities are acquiring a new radiation monitoring system enabling realtime transmission of information on the radiation situation. The system will also gather meteorological data and make predictions on the movements of a radioactive cloud. The data are stored in a database, from which they can be retrieved onto a user's workstation. Each user can get an overall picture of the current situation by viewing a set of files which are produced automatically by the system. Upon receiving notice of a hazard, the system contacts the paging devices of the officers on call. When the notice comes from a single station, the system automatically reads the measurement data of all stations within 50 kilometers. The system, development of which began in 1992, will be put to use early next year. (orig.)

  18. Radiation monitoring: Quarterly report for the Greater Manchester Fire and Civil Defence Authority and the Manchester Area Pollution Advisory Council. Manchester Area Gamma Radiation Air Monitoring System (MANAGRAMS): report covering period of 3 months 01/07/1996 to 30/09/1996

    International Nuclear Information System (INIS)

    1996-01-01

    Gamma radiation monitoring data from ten outstations in the Manchester area for the period 01/07/1996 to 30/09/1996 are presented. For each station there is a summary table, a background radiation graph showing 6 hour mean levels and a wind rose graph showing the direction of the wind as a percentage of the total. A line graph comparison between stations is provided for the background 6 hour mean levels and a bar chart comparison of total dose during the reporting period. Graphs of barometric pressure and temperature taken from extra sensors at the Trafford station are also presented. (UK)

  19. Radiation monitoring. Quarterly report for the Greater Manchester Fire and Civil Defence Authority and the Manchester Area Pollution Advisory Council. Manchester Area Gamma Radiation Air Monitoring System (MANAGRAMS), report covering period of 3 months 1 January to 31 March 1996

    International Nuclear Information System (INIS)

    1996-01-01

    Gamma radiation monitoring data from nine outstations in the Manchester area for the period 01/01/96 to 31/03/96 are presented. For each station there is a summary table, a background radiation graph showing 6 hour mean levels and a windrose graph showing the direction of the wind as a percentage of the total. A line graph comparison between stations is provided for the background 6 hour mean levels and a bar chart comparison of total dose. Graphs of temperature and barometric pressure taken from extra sensors at the Trafford station are presented. (UK)

  20. Flight controller design of unmanned airplane for radiation monitoring system via structured robust controller design using multiple model approach. Radiation monitoring flight in Namie-machi in Fukushima prefecture

    International Nuclear Information System (INIS)

    Sato, Masayuki; Muraoka, Koji; Hozumi, Koki; Sanada, Yukihisa; Yamada, Tsutomu; Torii, Tatsuo

    2015-01-01

    Due to the tragic accident of radioactive contaminant spread from Fukushima Dai-ichi nuclear power plant, the necessity of unmanned systems for radiation monitoring has been increasing. This paper concerns the flight controller design of an unmanned airplane which has been developed for radiation monitoring around the power plant. The flight controller consists of conventional control elements, i.e. Stability/Control Augmentation System (S/CAS) with PI controllers and guidance loops with PID controllers. The gains in these controllers are designed by minimizing appropriately defined cost functions for several possible models and disturbances to produce structured robust flight controllers. (This method is called as 'multiple model approach'.) Control performance of our flight controller was evaluated through flight tests and a primitive flight of radiation monitoring in Namie-machi in Fukushima prefecture was conducted in Jan. 2014. Flight results are included in this paper. (author)