WorldWideScience

Sample records for distributed radiation monitoring

  1. 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.

  2. 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)

  3. 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

  4. 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

  5. The Performance Assessment of the Detector for the Portable Environmental Radiation Distribution Monitoring System with Rapid Nuclide Recognition

    International Nuclear Information System (INIS)

    Lee, Uk Jae; Kim, Hee Reyoung

    2015-01-01

    The environment radiation distribution monitoring system measures the radiation using a portable detector and display the overall radiation distribution. Bluetooth and RS-232 communications are used for constructing monitoring system. However RS-232 serial communication is known to be more stable than Bluetooth and also it can use the detector's raw data which will be used for getting the activity of each artificial nuclide. In the present study, the detection and communication performance of the developed detector with RS-232 method is assessed by using standard sources for the real application to the urban or rural environment. Assessment of the detector for the portable environmental radiation distribution monitoring system with rapid nuclide recognition was carried out. It was understood that the raw data of detector could be effectively treated by using RS-232 method and the measurement showed a good agreement with the calculation within the relative error of 0.4 % in maximum

  6. The Performance Assessment of the Detector for the Portable Environmental Radiation Distribution Monitoring System with Rapid Nuclide Recognition

    Energy Technology Data Exchange (ETDEWEB)

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

    2015-05-15

    The environment radiation distribution monitoring system measures the radiation using a portable detector and display the overall radiation distribution. Bluetooth and RS-232 communications are used for constructing monitoring system. However RS-232 serial communication is known to be more stable than Bluetooth and also it can use the detector's raw data which will be used for getting the activity of each artificial nuclide. In the present study, the detection and communication performance of the developed detector with RS-232 method is assessed by using standard sources for the real application to the urban or rural environment. Assessment of the detector for the portable environmental radiation distribution monitoring system with rapid nuclide recognition was carried out. It was understood that the raw data of detector could be effectively treated by using RS-232 method and the measurement showed a good agreement with the calculation within the relative error of 0.4 % in maximum.

  7. 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.

  8. HYPERION NET - a distributed measurement system for monitoring background ionizing radiation

    International Nuclear Information System (INIS)

    Saponjic, Dj.; Zigic, A.; Arandjelovic, V.

    2003-01-01

    The distributed measurement system - HYPERION NET, based on the concept of FieldBus technology, has been developed, implemented, and tested as a pilot project, the first WEB enabled on-line networked ionizing radiation monitoring and measurement system. The Net has layered the structure, tree topology, and is based on the Internet infrastructure and TCP/IP communication protocol. The Net's core element is an intelligent GM transmitter, based on GM tube, used for measuring the absorbed dose in air, in the range of 0.087 to 720 μGy/h. The transmitter makes use of an advanced count rate measurement algorithm capable of suppressing the statistical fluctuations of the measured quantity, which significantly improves its measurement performance mailing it suitable for environmental radiation measurements. (author)

  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. Radiation distribution sensing with normal optical fiber

    International Nuclear Information System (INIS)

    Kawarabayashi, Jun; Mizuno, Ryoji; Naka, Ryotaro; Uritani, Akira; Watanabe, Ken-ichi; Iguchi, Tetsuo; Tsujimura, Norio

    2002-01-01

    The purpose of this study is to develop a radiation distribution monitor using a normal plastic optical fiber. The monitor has a long operating length (10m-100m) and can obtain continuous radiation distributions. A principle of the position sensing is based on a time-of-flight technique. The characteristics of this monitor to beta particles, gamma rays and fast neutrons were obtained. The spatial resolutions for beta particles ( 90 Sr -90 Y), gamma rays ( 137 Cs) and D-T neutrons were 30 cm, 37 cm and 13 cm, respectively. The detection efficiencies for the beta rays, the gamma rays and D-T neutrons were 0.11%, 1.6x10 -5 % and 5.4x10 -4 %, respectively. The effective attenuation length of the detection efficiency was 18m. New principle of the position sensing based on spectroscopic analysis was also proposed. A preliminary test showed that the spectrum observed at the end of the fiber depended on the position of the irradiated point. This fact shows that the radiation distributions were calculated from the spectrum by mathematical deconvolution technique. (author)

  11. 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

  12. 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)

  13. Radiation distribution sensing with normal optical fiber

    Energy Technology Data Exchange (ETDEWEB)

    Kawarabayashi, Jun; Mizuno, Ryoji; Naka, Ryotaro; Uritani, Akira; Watanabe, Ken-ichi; Iguchi, Tetsuo [Nagoya Univ., Dept. of Nuclear Engineering, Nagoya, Aichi (Japan); Tsujimura, Norio [Japan Nuclear Cycle Development Inst., Tokai Works, Tokai, Ibaraki (Japan)

    2002-12-01

    The purpose of this study is to develop a radiation distribution monitor using a normal plastic optical fiber. The monitor has a long operating length (10m-100m) and can obtain continuous radiation distributions. A principle of the position sensing is based on a time-of-flight technique. The characteristics of this monitor to beta particles, gamma rays and fast neutrons were obtained. The spatial resolutions for beta particles ({sup 90}Sr{sup -90}Y), gamma rays ({sup 137}Cs) and D-T neutrons were 30 cm, 37 cm and 13 cm, respectively. The detection efficiencies for the beta rays, the gamma rays and D-T neutrons were 0.11%, 1.6x10{sup -5}% and 5.4x10{sup -4}%, respectively. The effective attenuation length of the detection efficiency was 18m. New principle of the position sensing based on spectroscopic analysis was also proposed. A preliminary test showed that the spectrum observed at the end of the fiber depended on the position of the irradiated point. This fact shows that the radiation distributions were calculated from the spectrum by mathematical deconvolution technique. (author)

  14. 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

  15. Radiation distribution sensor with optical fibers for high radiation fields

    International Nuclear Information System (INIS)

    Takada, Eiji; Kimura, Atsushi; Hosono, Yoneichi; Takahashi, Hiroyuki; Nakazawa, Masaharu

    1999-01-01

    Radiation distribution sensors with their feasibilities have been described in earlier works. However, due to large radiation induced transmission losses in optical fibers, especially in the visible wavelength region, it has been difficult to apply these techniques to high radiation fields. In this study, we proposed a new concept of optical fiber based radiation distribution measurements with near infrared (IR) emission. Near IR scintillators were attached to the ends of optical fibers, where the fibers were bundled and connected to an N-MOS line sensor or a cooled CCD camera. From the measurements of each area density, the radiation levels at the positions of the scintillators can be known. The linearity between the gamma dose rate at each scintillator and the registered counts has been examined. For correcting the radiation induced loss effects, we applied the Optical Time Domain Reflectometry technique to measure the loss distribution and from the results, a possibility for correction of the loss effect has been demonstrated. The applicable dose rate range was evaluated to be from 0.1 to 10 3 Gy/h. This system can be a promising tool as a flexible dose rate distribution monitor in radiation facilities like nuclear plants and accelerator facilities. (author)

  16. 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)

  17. 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)

  18. 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)

  19. 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)

  20. Distributed radiation protection console system

    International Nuclear Information System (INIS)

    Chhokra, R.S.; Deshpande, V.K.; Mishra, H.; Rajeev, K.P.; Thakur, Bipla B.; Munj, Niket

    2004-01-01

    Radiation exposure control is one of the most important aspects in any nuclear facility . It encompasses continuous monitoring of the various areas of the facility to detect any increase in the radiation level and/or the air activity level beyond preset limits and alarm the O and M personnel working in these areas. Detection and measurement of radiation level and the air activity level is carried out by a number of monitors installed in the areas. These monitors include Area Gamma Monitors, Continuous Air Monitors, Pu-In-Air Monitors, Criticality Monitors etc. Traditionally, these measurements are displayed and recorded on a Central Radiation Protection Console(CRPC), which is located in the central control room of the facility. This methodology suffers from the shortcoming that any worker required to enter a work area will have to inquire about the radiation status of the area either from the CRPC or will get to know the same directly from the installed only after entering the area. This shortcoming can lead to avoidable delays in attending to the work or to unwanted exposure. The authors have designed and developed a system called Distributed Radiation Protection Console (DRPC) to overcome this shortcoming. A DRPC is a console which is located outside the entrance of a given area and displays the radiation status of the area. It presents to health physicist and the plant operators a graphic over-view of the radiation and air activity levels in the particular area of the plant. It also provides audio visual annunciation of the alarm status. Each radioactive area in a nuclear facility will have its own DRPC, which will receive as its inputs the analog and digital signals from radiation monitoring instruments installed in the area and would not only show those readings on its video graphic screen but will also provide warning messages and instructions to the personnel entering the active areas. The various DRPCs can be integrated into a Local Area Network, where the

  1. 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.

  2. 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

  3. 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

  4. 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

  5. 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)

  6. 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)

  7. 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.

  8. 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.

  9. 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.

  10. 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)

  11. 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

  12. 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

  13. Radiation distribution sensing with normal optical fiber

    CERN Document Server

    Kawarabayashi, J; Naka, R; Uritani, A; Watanabe, K I; Iguchi, T; Tsujimura, N

    2002-01-01

    The purpose of this study is to develop a radiation distribution monitor using a normal plastic optical fiber. The monitor has a long operating length (10m-100m) and can obtain continuous radiation distributions. A principle of the position sensing is based on a time-of-flight technique. The characteristics of this monitor to beta particles, gamma rays and fast neutrons were obtained. The spatial resolutions for beta particles ( sup 9 sup 0 Sr sup - sup 9 sup 0 Y), gamma rays ( sup 1 sup 3 sup 7 Cs) and D-T neutrons were 30 cm, 37 cm and 13 cm, respectively. The detection efficiencies for the beta rays, the gamma rays and D-T neutrons were 0.11%, 1.6x10 sup - sup 5 % and 5.4x10 sup - sup 4 %, respectively. The effective attenuation length of the detection efficiency was 18m. New principle of the position sensing based on spectroscopic analysis was also proposed. A preliminary test showed that the spectrum observed at the end of the fiber depended on the position of the irradiated point. This fact shows that t...

  14. 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

  15. 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.

  16. 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

  17. 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

  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. 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)

  20. 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)

  1. 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)

  2. Charged particle beam monitoring by means of synchrotron radiation

    International Nuclear Information System (INIS)

    Panasyuk, V.S.; Anevskij, S.I.

    1984-01-01

    Optical methods for monitoring the number of accelerated electrons and electron energy by means of beam synchrotron radiation (SR) as well as peculiarities of SR characteristics of beams with a small radius of the orbit are considered. Optical methods for charged particle beam monitoring are shown to ensure operative and precise monitoring the number of particles and particle energy. SR sources with large axial dimensions of an electron beam have specific spectral angular and polarization characteristics. If electron angular distribution at deflection from the median plane is noticeably wider than angular distribution of SR of a certain electron, relative SR characteristics of these soUrces are calculated with high accuracy

  3. 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)

  4. 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

  5. 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

  6. 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

  7. 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

  8. 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.)

  9. 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)

  10. 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

  11. 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

  12. 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

  13. 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)

  14. 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

  15. Examination of the component of the scattered radiation by external monitor chamber using the EGS4

    International Nuclear Information System (INIS)

    Shiota, Y.; Tabushi, K.; Kito, S.

    2005-01-01

    The output beams of the liner accelerator are radiated by an accelerated electron and a dose rate usually fluctuates. The variation affects the shape of a dose distribution in dosimetry. The external monitor chamber is often used for monitoring the variation. Generally the external monitor chamber is set above the water phantom. Therefore, if the irradiation field is small, the scattered radiation due to the external monitor chamber may affect a measurement dose. This work is to examine the component of the scattered radiation generated by external monitor chamber, and to investigate the effect on measurement dose using the EGS4 code and the Klein-Nishina formula. The shapes and the peak energies were corresponding to the spectra of EGS4 and the Klein-Nishina formula. Therefore the main interaction at the external monitor chamber is Compton scatter. The effect of the scattered radiation and the change of the dose distribution were few. However the dose decreased to about 1% under the position of the external monitor chamber. Therefore we should pay the attention to the distance between the external monitor chamber and the measurement chamber. (author)

  16. 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)

  17. Radiation monitoring of Syr-Darya river (II)

    International Nuclear Information System (INIS)

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

    2004-01-01

    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 radionuclide distribution of uranium and thorium rows in bottom and soil is presented. Reasons of formation of the observed dependence of the obtained results on the distance from the source are discussed. (author)

  18. 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.)

  19. 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)

  20. 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

  1. 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.

  2. 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

  3. 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....

  4. 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)

  5. 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

  6. 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

  7. Reactor power distribution monitor

    International Nuclear Information System (INIS)

    Hoizumi, Atsushi.

    1986-01-01

    Purpose: To grasp the margin for the limit value of the power distribution peaking factor inside the reactor under operation by using the reactor power distribution monitor. Constitution: The monitor is composed of the 'constant' file, (to store in-reactor power distributions obtained from analysis), TIP and thermocouple, lateral output distribution calibrating apparatus, axial output distribution synthesizer and peaking factor synthesizer. The lateral output distribution calibrating apparatus is used to make calibration by comparing the power distribution obtained from the thermocouples to the power distribution obtained from the TIP, and then to provide the power distribution lateral peaking factors. The axial output distribution synthesizer provides the power distribution axial peaking factors in accordance with the signals from the out-pile neutron flux detector. These axial and lateral power peaking factors are synthesized with high precision in the three-dimensional format and can be monitored at any time. (Kamimura, M.)

  8. 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

  9. 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.

  10. 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)

  11. Distributed radiation data acquisition system for KAPP

    International Nuclear Information System (INIS)

    Narsaiah, A.; Anantakrishnan, T.S.; Bairi, B.R.

    1992-01-01

    Increased concern for the safety of personnel working in Nuclear Power Stations demands an efficient centralized Radiation Data Acquisition System (RADAS) to monitor different types of radiation at distributed locations of the plant. The system provides a comprehensive picture of radio-activity level distribution in the reactor building to facilitate prompt and correct decision making to take care of any emergency situation. The system is build around an industrial IBM-PC connected to remote intelligent data acquisition units using serial data communication links. To ensure high system availability and ease of maintenance the mechanical moving disk storage has been replaced by solid state memory storage (RAM Disk). Functional CRT displays have been substituted by the assembly of IBM-PC Mother Board with built-in firmware and standard TV Monitor. The computer handles a variety of processing functions which include the conversion to engineering units, checking of alarms, display/printing of plant radiation level status and system diagnostics. Intelligent terminals have been provided with graphic and text formatting capabilities. A hot standby computer connected to analog and digital inputs takes over the system functions on the failure of the host system. Modular software written in the higher level C-language runs under a standard real-time operating system Kernel. This provides for easy modification and expandability at site. Based on the experience of its commissioning at Kakrapar Power Station a new compact version is being designed for a specific application in another class of reactor. (author). 3 refs., 1 fig

  12. Radiation detection and situation management by distributed sensor networks

    International Nuclear Information System (INIS)

    Jan, Frigo; Mielke, Angela; Cai, D. Michael

    2009-01-01

    Detection of radioactive materials in an urban environment usually requires large, portal-monitor-style radiation detectors. However, this may not be a practical solution in many transport scenarios. Alternatively, a distributed sensor network (DSN) could complement portal-style detection of radiological materials through the implementation of arrays of low cost, small heterogeneous sensors with the ability to detect the presence of radioactive materials in a moving vehicle over a specific region. In this paper, we report on the use of a heterogeneous, wireless, distributed sensor network for traffic monitoring in a field demonstration. Through wireless communications, the energy spectra from different radiation detectors are combined to improve the detection confidence. In addition, the DSN exploits other sensor technologies and algorithms to provide additional information about the vehicle, such as its speed, location, class (e.g. car, truck), and license plate number. The sensors are in-situ and data is processed in real-time at each node. Relevant information from each node is sent to a base station computer which is used to assess the movement of radioactive materials

  13. Development of wide-area radiation monitor using an optical fiber

    International Nuclear Information System (INIS)

    Kawata, Naoki; Kato, Masatoshi; Baba, Mamoru; Yamadera, Akira; Miura, Takako

    2002-01-01

    We have developed a method for radiation distribution measurement by combining an optical fiber of wave-length shift type with a plastic scintillator, and studied its properties to apply as a wide-area radiation monitor. The detector employs two photomultipliers in both ends of the fiber and locate the radiation position by using the difference of light arrival time from scintillators. We tested the detector with gamma-rays and neutrons concerning with the position-response and pulse-height response of the detector. From the experiment, we confirmed the proper operation of the detector and position response with spatial resolution of 30-60 cm

  14. 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.

  15. 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

  16. 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.)

  17. 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)

  18. 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)

  19. 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)

  20. 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)

  1. 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.)

  2. 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)

  3. 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)

  4. 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

  5. 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

  6. 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)

  7. 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

  8. 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

  9. 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

    NFC is producing natural uranium and enriched uranium fuels for various reactors including PHWR etc. Monitoring of α and β radiations in the active plants of NFC is very much essential in many aspects. The personnel who are handling radiation materials have to be monitored for α radiation of hands and cloths and β radiation of feet. So the Alpha and Beta Monitor became important monitoring equipment for monitoring α and β radiations of persons working in active plants of NFC. Many Alpha and Beta Monitors of make, ECIL, PLA, and Nucleonix etc. were being used in active plants in NFC. Basically α and β radiation monitors consists of four PMT (Photo Multiplier Tubes) for detection of radiation of hands and one PMT for monitoring clothes. The PMT use ZnS (Ag) as the scintillator for detection of α radiation. GM tubes are used to detect β radiation of feet. The latest Hand and Foot Monitors have been incorporated with PC based monitoring system along with software for making the monitoring process more efficient and user friendly. As an instrumentation maintenance team for these monitors, our experiences are varied. These monitors are to be periodically maintained and tested for its effective functioning in monitoring the nuclear radiation. The monitors procured from M/s. ECIL were being used since long time in these areas. The instrumentation maintenance had faced some problems with these monitors such as frequent failure of High Voltage cards, Amplifier and Counter PCB cards. Modifications were made in the circuits of High Voltage and Counter cards to minimize the failure rate and for loading of Display and Monitoring Software through Hard disk instead of from floppy disk. So the availability of monitors for monitoring radiation got improved. Later the introduction of more sophisticated α and β radiation monitors of M/s. PLA make in these areas further improved monitoring of radiation of personnel working in active areas. These monitors are more user

  10. 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

  11. 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)

  12. 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)

  13. Analysis of radiation monitoring data by distribution-free statistical methods (a case of river system Techa-Iset'-Tobol-Irtysh contamination)

    International Nuclear Information System (INIS)

    Luneva, K.V.; Kryshev, A.I.; Nikitin, A.I.; Kryshev, I.I.

    2010-01-01

    The article presents the results of statistical analysis of radiation monitoring data of river system Techa-Iset'-Tobol-Irtysh contamination. A short description of analyzable data and the territory under consideration was given. The distribution-free statistic methods, used for comparative analysis, were described. Reasons of the methods selection and their application features were given. Comparative data analysis with traditional statistics methods was presented. Reliable decrease of 90 Sr specific activity in the river system object to object was determined, which is the evidence of the radionuclide transportation in the river system Techa-Iset'-Tobol-Irtysh [ru

  14. 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

  15. Radiation dose distribution monitoring at neutron radiography facility area, Nuclear Energy Unit, Malaysia

    International Nuclear Information System (INIS)

    Abdul Razak Daud

    1995-01-01

    One experiment was carried out to get the distribution of radiation doses at the neutron radiography facilities, Nuclear Energy Unit, Malaysia. The analysis was done to evaluate the safety level of the area. The analysis was used in neutron radiography work

  16. 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

  17. Monitoring the consequences of decreased ozone protection: The NSF ultraviolet radiation monitoring network

    International Nuclear Information System (INIS)

    Anon.

    1993-01-01

    The effects of decreased protection from ultraviolet radiation are as troubling as the continuing depletion of stratospheric ozone. Evidence exists to clearly link ozone depletion to changes in the antarctic marine environment. Results of two 1992 papers are summarized here. Enhanced exposure to mid-range UV radiation was found to be affecting marine ecosystems with a recorded 6-12 percent reduction in primary productivity directly related to the ozone layer depletion. In another experiment, a model was developed indicating that the ozone hole could reduce near-surface photosynthesis by as much as 12-15 percent. The NSF UV monitoring system in place for these and other experiments uses a spectroradiometer, making hourly, high-resolution measurements of the distribution of UV surface irradiance

  18. 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...

  19. 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

  20. 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

  1. 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

  2. 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

  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. 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.

  5. 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

  6. Annual dose distribution of Nuclear Malaysia radiation workers for monitoring period from year 2003 to 2007

    International Nuclear Information System (INIS)

    Hairul Nizam Idris; Azimawati Ahmad; Norain Ab Rahman

    2008-08-01

    Estimation of radiation dose (external exposure) received by Nuklear Malaysia's radiation workers are measured by using personal dosimetry device which are provided by SSDL-Nuklear Malaysia. Dose assessment report for monitoring period from year 2003 - 2007 shows that almost all radiation workers received annual doses less than 20 mSv, only in very small percentage of radiation workers received annual doses between 20.1 to 50 mSv and none of the workers received doses higher than 50 mSv/year. Exposure dose below 20 mSv/year (the new annual dose limit to be used in Malaysia soon) could be fully achieved by improving the compliance with the safety regulations and enhancing the awareness about radiation safety among the workers. (Author)

  7. 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

  8. 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

  9. 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.)

  10. 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

  11. 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.)

  12. 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.

  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. Power distribution monitor in a nuclear reactor

    International Nuclear Information System (INIS)

    Uematsu, Hitoshi

    1983-01-01

    Purpose: To enable accurate monitoring for the reactor power distribution within a short time in a case where abnormality occurs in in-core neutron monitors or in a case where the reactor core state changes after the calibration for the neutron monitors. Constitution: The power distribution monitor comprises a power distribution calculator adapted to be inputted counted values from a reactor core present state data instruments and calculate the neutron flux distribution in the reactor core and the power distribution based on previously incorporated physical models, an RCF calculator adapted to be inputted with the counted values from the in-core neutron monitors and the neutron flux distribution and the power distribution calculated in the power distribution calculator and compensate the counted errors included in the counted values form the in-core neutron monitors and the calculation errors included in the power distribution calculated in the power distribution calculator to thereby calculate the power distribution within the reactor core, and an input/output device for the input of the data required for said power distribution calculator and the display for the calculation result calculated in the RCF calculator. (Ikeda, J.)

  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. On the method of estimating the event of unusually high values in the radiation monitoring data

    International Nuclear Information System (INIS)

    Kumazawa, Shigeru; Matsui, Hiroshi

    1980-01-01

    The method was discussed for estimating a comparatively rare occurrence of monitoring data much greater than the average in the field of radiation protection. The features of and the mutual relationships among four types of probability distributions, i.e., normal, log-normal, double-exponential and log-double-exponential, were presented, and their application to various monitoring data of radiation protection was shown. For graphical analysis of empirical distributions the followings were concluded: 1. The upper probabilities are considerably affected by the method of calculating the quantiles and the method of logarithmic transformation of a stochastic variable after a fixed value being added to or subtracted from it to obtain the better straight-line fit on the probability paper. 2. A double-exponential distribution provided a good fit to the annual dose maxima, while a log-double-exponential distribution did to the radioactive contamination maxima in a fixed period of time or in a fixed region of space. 3. The monitoring data arranged in the order of their magnitude were expressed by an exponential function of the order for dose data and by a power function of the order for radioactive contamination data. (author)

  19. 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.

  20. Monitoring distributed object and component communication

    NARCIS (Netherlands)

    Diakov, N.K.

    2004-01-01

    This thesis presents our work in the area of monitoring distributed software applications (DSAs). We produce three main results: (1) a design approach for building monitoring systems, (2) a design of a system for MOnitoring Distributed Object and Component Communication (MODOCC) behavior in

  1. 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.)

  2. 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

  3. Radiation tolerance assurance of technical equipment in the LHC radiation monitoring for technical equipment at the LHC

    CERN Document Server

    Wijnands, Thijs; CERN. Geneva. TS Department

    2005-01-01

    In contrast with other accelerators at CERN, a large amount of technical equipment will be located in the LHC tunnel, the underground areas and in the experimental caverns where they will be exposed to radiation. Nearly all this equipment makes, to a certain extent, use of commercial microelectronics which is extremely sensitive to radiation damage, both instantaneous damage and cumulative damage. Examples in the TS Department are the electronics for the position sensors of the low beta quadrupoles, the access system, the cooling and ventilation units, the electronics for the electrical distribution, the oxygen deficiency monitors and fire detection systems. The basic effects of radiation on electronic systems and components are well understood because similar problems with radiation are encountered in the aerospace and aviation industry. Since 1998, an efficient and original Radiation Tolerance Assurance approach for the LHC machine has been established. Its aim is to minimise the effects of radiation damage...

  4. 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...

  5. 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.)

  6. 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.

  7. 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

  8. 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

  9. 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

  10. Monte Carlo simulation of the sequential probability ratio test for radiation monitoring

    International Nuclear Information System (INIS)

    Coop, K.L.

    1984-01-01

    A computer program simulates the Sequential Probability Ratio Test (SPRT) using Monte Carlo techniques. The program, SEQTEST, performs random-number sampling of either a Poisson or normal distribution to simulate radiation monitoring data. The results are in terms of the detection probabilities and the average time required for a trial. The computed SPRT results can be compared with tabulated single interval test (SIT) values to determine the better statistical test for particular monitoring applications. Use of the SPRT in a hand-and-foot alpha monitor shows that the SPRT provides better detection probabilities while generally requiring less counting time. Calculations are also performed for a monitor where the SPRT is not permitted to the take longer than the single interval test. Although the performance of the SPRT is degraded by this restriction, the detection probabilities are still similar to the SIT values, and average counting times are always less than 75% of the SIT time. Some optimal conditions for use of the SPRT are described. The SPRT should be the test of choice in many radiation monitoring situations. 6 references, 8 figures, 1 table

  11. 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

  12. 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)

  13. 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

  14. Emissions and doses from sources of ionising radiation in the Netherlands: radiation policy monitoring

    International Nuclear Information System (INIS)

    Eleveld, H.; Pruppers, M.

    2002-01-01

    In 1997 the Ministry of Housing, Spatial Planning and the Environment requested RIVM to develop an information system for policy monitoring. One of the motives was that the European Union requires that the competent authorities of each member state ensure that dose estimates due to practices involving exposure to ionising radiation are made as realistic as possible for the population as a whole and for reference groups in all places where such groups may occur. Emissions of radionuclides and radiation to the environment can be classified as follows: (1) emissions to the atmosphere, (2) emissions to the aquatic system and (3) emission of external radiation from radioactive materials and equipment that produces ionising radiation. Released radioactivity is dispersed via exposure pathways, such as the atmosphere, deposition on the ground and farmland products, drinking water, fish products, etc. This leads to radiation doses due to inhalation, ingestion and exposure to external radiation. To assess the possible radiation doses different kinds of models are applied, varying from simple multiplications with dispersion coefficients, transfer coefficients and dose conversion coefficients to complex dispersion models. In this paper an overview is given of the human-induced radiation doses in the Netherlands. Also, trends in and the effect of policy on the radiation dose of members of the public are investigated. This paper is based on an RIVM report published recently. A geographical distribution of radiation risks due to routine releases for a typical year in the Netherlands was published earlier

  15. 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)

  16. 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)

  17. 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

  18. 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.)

  19. 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)

  20. 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)

  1. 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

  2. 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.)

  3. 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.)

  4. 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.

  5. 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

  6. 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

  7. 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

  8. 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

  9. 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)

  10. 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.

  11. 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,...

  12. 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

  13. 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.)

  14. 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)

  15. 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.

  16. 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...

  17. 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.

  18. 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)

  19. 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)

  20. 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.

  1. 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

  2. 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)

  3. 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)

  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. 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)

  6. 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

  7. 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)

  8. Hybrid radiation background monitoring in operational control and forecasting of environmental contamination by nuclear power station discharges

    International Nuclear Information System (INIS)

    Ermeev, I.S.; Eremenko, V.A.; Makarov, Y.A.; Matueev, V.V.; Zhernov, V.S.

    1986-01-01

    Rapid developments in nuclear power have stimulated research on monitoring and forecasting environmental radiation pollution (ERP), and in particular the amounts, compositions, and distributions of radionuclides in the environment. A conceptual model is presented for hybrid environmental radiation pollution monitoring. When there is an emergency, the model operates in a fashion most closely corresponding to the actual meteorological conditions, and the ERP data given by the model enable one to distinguish changes due to the man-made component from random fluctuations in the natural background. The measurement system in general includes mobile and stationary data-acquisition facilities linked by wire or radio to the central point. The system also accumulates and stores data on the radiation environment, which are edited on the basis of radioactive, chemical, and other transformations. The purpose of hybrid monitoring is ultimately to analyze trends in order to detect elevated discharges and thus to output data to the regional monitoring system

  9. 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.

  10. Power distribution monitor for nuclear reactor

    International Nuclear Information System (INIS)

    Nishizawa, Yasuo; Kiguchi, Takashi.

    1974-01-01

    Object: To compare the measured local power region monitor (LPRM) index with the result of a primary calculation to correct the threshold condition for the primary calculation thereby to rapidly grasp and monitor the existing power distribution. Structure: The index of an LPRM disposed in a nuclear reactor is processed in a data processor to remove therefrom a noise, and transmitted to a threshold condition processor to be stored therein. The LPRM index measured by the threshold condition processor is compared with the calculated LPRM value transmitted from the primary processor, whereby the threshold condition is corrected and transmitted to the primary processor. After the completion of calculation, the traversing incore probe (TIP) indexing value is converted to a thermal output distribution or a linear output density distribution and transmitted to an output indicator or an output typewriter. The operator may monitor the existing power distribution by monitoring the output indicator. (Kamimura, M.)

  11. 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)

  12. 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

  13. 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

  14. 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

  15. 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

  16. 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

  17. 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

  18. 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

  19. 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

  20. 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

  1. 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

  2. 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

  3. 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).

  4. Distributed computing environment monitoring and user expectations

    International Nuclear Information System (INIS)

    Cottrell, R.L.A.; Logg, C.A.

    1996-01-01

    This paper discusses the growing needs for distributed system monitoring and compares it to current practices. It then goes to identify the components of distributed system monitoring and shows how they are implemented and successfully used at one site today to address the Local area Network (WAN), and host monitoring. It shows how this monitoring can be used to develop realistic service level expectations and also identifies the costs. Finally, the paper briefly discusses the future challenges in network monitoring. (author)

  5. 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

  6. 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)

  7. 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.)

  8. 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.

  9. 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 ...

  10. 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.

  11. 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)

  12. 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

  13. 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.

  14. 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

  15. Distributed intelligent monitoring and reporting facilities

    Science.gov (United States)

    Pavlou, George; Mykoniatis, George; Sanchez-P, Jorge-A.

    1996-06-01

    Distributed intelligent monitoring and reporting facilities are of paramount importance in both service and network management as they provide the capability to monitor quality of service and utilization parameters and notify degradation so that corrective action can be taken. By intelligent, we refer to the capability of performing the monitoring tasks in a way that has the smallest possible impact on the managed network, facilitates the observation and summarization of information according to a number of criteria and in its most advanced form and permits the specification of these criteria dynamically to suit the particular policy in hand. In addition, intelligent monitoring facilities should minimize the design and implementation effort involved in such activities. The ISO/ITU Metric, Summarization and Performance management functions provide models that only partially satisfy the above requirements. This paper describes our extensions to the proposed models to support further capabilities, with the intention to eventually lead to fully dynamically defined monitoring policies. The concept of distributing intelligence is also discussed, including the consideration of security issues and the applicability of the model in ODP-based distributed processing environments.

  16. 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

  17. 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)

  18. 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.

  19. 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

  20. Distributed computing environment monitoring and user expectations

    International Nuclear Information System (INIS)

    Cottrell, R.L.A.; Logg, C.A.

    1995-11-01

    This paper discusses the growing needs for distributed system monitoring and compares it to current practices. It then goes on to identify the components of distributed system monitoring and shows how they are implemented and successfully used at one site today to address the Local Area Network (LAN), network services and applications, the Wide Area Network (WAN), and host monitoring. It shows how this monitoring can be used to develop realistic service level expectations and also identifies the costs. Finally, the paper briefly discusses the future challenges in network monitoring

  1. 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)

  2. 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).

  3. 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.)

  4. 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.

  5. 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.

  6. Metrology for γ-radiation spectrometry in a radiation monitoring system

    International Nuclear Information System (INIS)

    Khaikovich, I.M.; Shevrygin, O.N.; Fominykh, V.I.

    1993-01-01

    The rapid measurement of the characteristics of radionuclides is a priority when utilizing nuclear energy because of the needs of environmental conservation. This is particularly the case for long-lived nuclear-fuel fission products, 137,137 Cs, 144 Ce, 60 Co, etc., which as a rule are sources of high-energy γ-radiation. These can be measured by γ-ray spectrometry using scintillation or semiconductor devices. When choosing the metrological models, the starting points are the real characteristics of the distribution of the radionuclides in the soil (rock) and the need to estimate their surface activity and the reserves per unit area, i.e., the parameters from which one can estimate the influence of the radioactivity on nature and can decide the use of land areas. The methodology and the calculations presented show that a single metrological system for radiation monitoring can be constructed using multichannel geophysical radiometers (gamma spectrometers) while relying on a system of initial standard samples of small size. Such a metrological system at present provides all the necessary initial means for measuring the effective γ-radiation surface activity of 137,134 Cs and the mass fraction of the natural radioactive elements. Using these initial means of measurement, surveyed areas in the Leningrad and Tula provinces have been certified as State standard samples in terms of the eight parameters: the surface contamination activity of 137,134 Cs, the reserves of these per unit area, the mass fraction of the natural radioactive elements (potassium, uranium and thorium), the power of the equivalent (exposed) γ-radiation dose at a height of 1 m above the surface. It is intended to use the certified metrological surveyed areas to provide traceability and the required measurement accuracy when studying the contamination in European territories resulting from the accident at the Chernobyl nuclear power station

  7. 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.

  8. 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)

  9. Analysis of a control and data acquisition system for radiation protection monitors of spent fuel reprocessing plant

    International Nuclear Information System (INIS)

    Liu Boxue

    1997-01-01

    For the radiation protection monitoring of spent nuclear fuel reprocessing plant, the paper analyzes the composition and requirements of a control and data acquisition system. With the concepts of typical distributing and opening models, the hardware consists of IPC, communication of RS-485 bus lines and data multiplexer. The software consists of real-time multi-services operation system and modelling program. It can sample monitoring data, control monitor's operation, and process data and other information. It has good expansive and compatible features

  10. Organic liquid scintillation detectors for on-the-fly neutron/gamma alarming and radionuclide identification in a pedestrian radiation portal monitor

    Science.gov (United States)

    Paff, Marc Gerrit; Ruch, Marc L.; Poitrasson-Riviere, Alexis; Sagadevan, Athena; Clarke, Shaun D.; Pozzi, Sara

    2015-07-01

    We present new experimental results from a radiation portal monitor based on the use of organic liquid scintillators. The system was tested as part of a 3He-free radiation portal monitor testing campaign at the European Commission's Joint Research Centre in Ispra, Italy, in February 2014. The radiation portal monitor was subjected to a wide range of test conditions described in ANSI N42.35, including a variety of gamma-ray sources and a 20,000 n/s 252Cf source. A false alarm test tested whether radiation portal monitors ever alarmed in the presence of only natural background. The University of Michigan Detection for Nuclear Nonproliferation Group's system triggered zero false alarms in 2739 trials. It consistently alarmed on a variety of gamma-ray sources travelling at 1.2 m/s at a 70 cm source to detector distance. The neutron source was detected at speeds up to 3 m/s and in configurations with up to 8 cm of high density polyethylene shielding. The success of on-the-fly radionuclide identification varied with the gamma-ray source measured as well as with which of two radionuclide identification methods was used. Both methods used a least squares comparison between the measured pulse height distributions to library spectra to pick the best match. The methods varied in how the pulse height distributions were modified prior to the least squares comparison. Correct identification rates were as high as 100% for highly enriched uranium, but as low as 50% for 241Am. Both radionuclide identification algorithms produced mixed results, but the concept of using liquid scintillation detectors for gamma-ray and neutron alarming in radiation portal monitor was validated.

  11. 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.

  12. Unmanned Mobile Monitoring for Nuclear Emergency Response

    Energy Technology Data Exchange (ETDEWEB)

    Choi, YoungSoo; Park, JongWon; Kim, TaeWon; Jeong, KyungMin [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2016-10-15

    Severe accidents at nuclear power plant have led to significant consequences to the people, the environment or the facility. Therefore, the appropriate response is required for the mitigation of the accidents. In the past, most of responses were performed by human beings, but it was dangerous and risky. In this paper, we proposed unmanned mobile system for the monitoring of nuclear accident in order to response effectively. For the integrity of reactor cooling and containment building, reactor cooling pipe and hydrogen distribution monitoring with unmanned ground vehicle was designed. And, for the safety of workers, radiation distribution monitoring with unmanned aerial vehicle was designed. Unmanned mobile monitoring system was proposed to respond nuclear accidents effectively. Concept of reinforcing the integrity of RCS and containment building, and radiation distribution monitoring were described. RCS flow measuring, hydrogen distribution measuring and radiation monitoring deployed at unmanned vehicle were proposed. These systems could be a method for the preparedness of effective response of nuclear accidents.

  13. 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

  14. 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)

  15. 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

  16. 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

  17. 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

  18. Airborne radiation monitoring using a manned helicopter

    International Nuclear Information System (INIS)

    Sanada, Yukihisa; Nishizawa, Yukiyasu; Ishizaki, Azusa; Urabe, Yoshimi

    2017-01-01

    The Great East Japan Earthquake that occurred on 11 March 2011 generated a series of large tsunami waves that caused serious damage to the Fukushima Dai-ichi Nuclear Power Station, following which a large amount of radioactive material was discharged from the nuclear power plant into the environment. Airborne radiation measurements using a manned helicopter were applied to measure the radiation distribution immediately after accident as technique to quickly measure the radiation distribution over a wide area. In Japan, this technique was researched and developed in the 1980s. However, this technique and system were not applied immediately after the accident because standardization of analysis was not established and the Japanese system became deteriorated. This technique is important for post-accident studies at a nuclear facility. We summarized the methods of the airborne radiation measurement using a manned helicopter. In addition, measurement results of the dose rate distribution at the Fukushima Dai-ichi Nuclear Power Station are given in this paper. (author)

  19. Dose distribution following selective internal radiation therapy

    International Nuclear Information System (INIS)

    Fox, R.A.; Klemp, P.F.; Egan, G.; Mina, L.L.; Burton, M.A.; Gray, B.N.

    1991-01-01

    Selective Internal Radiation Therapy is the intrahepatic arterial injection of microspheres labelled with 90Y. The microspheres lodge in the precapillary circulation of tumor resulting in internal radiation therapy. The activity of the 90Y injected is managed by successive administrations of labelled microspheres and after each injection probing the liver with a calibrated beta probe to assess the dose to the superficial layers of normal tissue. Predicted doses of 75 Gy have been delivered without subsequent evidence of radiation damage to normal cells. This contrasts with the complications resulting from doses in excess of 30 Gy delivered from external beam radiotherapy. Detailed analysis of microsphere distribution in a cubic centimeter of normal liver and the calculation of dose to a 3-dimensional fine grid has shown that the radiation distribution created by the finite size and distribution of the microspheres results in an highly heterogeneous dose pattern. It has been shown that a third of normal liver will receive less than 33.7% of the dose predicted by assuming an homogeneous distribution of 90Y

  20. An intelligent and networking solution of radiation monitoring system for LHC

    International Nuclear Information System (INIS)

    Shao Beibei; Gong Guanghua

    2001-01-01

    The LHC (the Large Hadron Collider), the largest accelerator in the world, is under designing and construction at CERN. It shares the 27 km LEP tunnel and is expected to be on the air in 2005. The Radiation Monitoring System of LEP was a central system with non-intelligent detectors. While as the proposed new RMS for LHC is a distributing intelligent networked system. Around 350 detectors will be employed. To save the cost, the design should make the old LEP's non-intelligent detectors reusable. To allow the detector controller automatic reports the detector database and net location through the world Fip bus, 1 wire components are embedded into the detectors and the network sockets. The radiation tolerance and the reliability of the communication of the wire components have been tested in a strong radiation field at CERN. The low cost components based position detection technique is valuable for most networked control system

  1. 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)

  2. 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)

  3. Distributed remote temperature monitoring system for INDUS-2 vacuum chambers

    International Nuclear Information System (INIS)

    Bhange, N.J.; Gothwal, P.; Fatnani, P.; Shukla, S.K.

    2011-01-01

    Indus-2, a 2.5 GeV Synchrotron Radiation Source (SRS) at Indore has a large vacuum system. The vacuum envelope of Indus-2 ring comprises of 16 dipole chambers as vital parts. Each chamber has 4 photon absorbers and three beam line ports blanked with end flanges. Temperature monitoring of critical vacuum components during operation of Indus-2 ring is an important requirement. The paper discusses a distributed, 160 channel remote temperature monitoring system developed and deployed for this purpose using microcontroller based, modular Temperature Monitoring Units (TMU). The cabling has been extensively minimized using RS485 system and keeping trip relay contacts of all units in series. For ensuring proper signal conditioning of thermocouple outputs (K-type) and successful operation over RS485 bus, many precautions were taken considering the close proximity to the storage ring. We also discuss the software for vacuum chamber temperature monitoring and safety system. The software developed using LabVIEW, has important features like modularity, client-server architecture, local and global database logging, alarms and trips, event and error logging, provision of various important configurations, communications handling etc. (author)

  4. 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

  5. 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.

  6. 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

  7. 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.

  8. 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)

  9. 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)

  10. 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)

  11. 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)

  12. 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.

  13. 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

  14. An unshielded whole body radioactivity counter for monitoring persons after a radiation accident

    International Nuclear Information System (INIS)

    Katoch, D.S.; Somasundaram, S.

    1979-01-01

    An unshielded chair in which the subject sits, holding a 7.6 cm x 7.6 cm NaI (Tl) detector in his lap, was evaluated for monitoring of persons suspected of internal radioactive contamination following a radiation accident. The reduction in different energy bands of the background gamma-ray spectrum due to self-shielding of the subject was studied for two postures, designated ''upright'' and ''folding'' and the data were analysed in a CDC 3600 computer to obtain the best-fit regression equation relating the reduction factor with body weight and height. The response of the counter was evaluated using an in vitro method and the ranges of under/over-estimation of body burden resulting from assumption of partial/uniform distribution of activity were determined. Counting sensitivities were derived for 13 radioisotopes having gamma-ray energies in the range 145 keV-1.46 MeV. The results are presented and discussed. The study shows that this simple system may be used not only in radiation emergencies but also for operational monitoring of radiation workers for a number of radioisotopes of low and medium radiotoxicity. (auth.)

  15. 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)

  16. 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)

  17. 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

  18. 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

  19. 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

  20. 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

  1. Mathematical simulation of gamma-radiation angle distribution measurements

    International Nuclear Information System (INIS)

    Batij, V.G.; Batij, E.V.; Egorov, V.V.; Fedorchenko, D.V.; Kochnev, N.A.

    2008-01-01

    We developed mathematical model of the facility for gamma-radiation angle distribution measurement and calculated response functions for gamma-radiation intensities. We developed special software for experimental data processing, the 'Shelter' object radiation spectra unfolding and Sphere detector (ShD) angle resolution estimation. Neuronet method using for detection of the radiation directions is given. We developed software based on the neuronet algorithm, that allows obtaining reliable distribution of gamma-sources that make impact on the facility detectors at the measurement point. 10 refs.; 15 figs.; 4 tab

  2. 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.

  3. 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)

  4. 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)

  5. 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.

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

    International Nuclear Information System (INIS)

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

    2010-01-01

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

  7. 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.)

  8. Sensor distributions for structural monitoring

    DEFF Research Database (Denmark)

    Ulriksen, Martin Dalgaard; Bernal, Dionisio

    2017-01-01

    Deciding on the spatial distribution of output sensors for vibration-based structural health monitoring (SHM) is a task that has been, and still is, studied extensively. Yet, when referring to the conventional damage characterization hierarchy, composed of detection, localization, and quantificat......Deciding on the spatial distribution of output sensors for vibration-based structural health monitoring (SHM) is a task that has been, and still is, studied extensively. Yet, when referring to the conventional damage characterization hierarchy, composed of detection, localization......, and quantification, it is primarily the first component that has been addressed with regard to optimal sensor placement. In this particular context, a common approach is to distribute sensors, of which the amount is determined a priori, such that some scalar function of the probability of detection for a pre......-defined set of damage patterns is maximized. Obviously, the optimal sensor distribution, in terms of damage detection, is algorithm-dependent, but studies have showed how correlation generally exists between the different strategies. However, it still remains a question how this “optimality” correlates...

  9. 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

  10. 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.)

  11. 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)

  12. 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)

  13. The novel application of Benford's second order analysis for monitoring radiation output in interventional radiology.

    Science.gov (United States)

    Cournane, S; Sheehy, N; Cooke, J

    2014-06-01

    Benford's law is an empirical observation which predicts the expected frequency of digits in naturally occurring datasets spanning multiple orders of magnitude, with the law having been most successfully applied as an audit tool in accountancy. This study investigated the sensitivity of the technique in identifying system output changes using simulated changes in interventional radiology Dose-Area-Product (DAP) data, with any deviations from Benford's distribution identified using z-statistics. The radiation output for interventional radiology X-ray equipment is monitored annually during quality control testing; however, for a considerable portion of the year an increased output of the system, potentially caused by engineering adjustments or spontaneous system faults may go unnoticed, leading to a potential increase in the radiation dose to patients. In normal operation recorded examination radiation outputs vary over multiple orders of magnitude rendering the application of normal statistics ineffective for detecting systematic changes in the output. In this work, the annual DAP datasets complied with Benford's first order law for first, second and combinations of the first and second digits. Further, a continuous 'rolling' second order technique was devised for trending simulated changes over shorter timescales. This distribution analysis, the first employment of the method for radiation output trending, detected significant changes simulated on the original data, proving the technique useful in this case. The potential is demonstrated for implementation of this novel analysis for monitoring and identifying change in suitable datasets for the purpose of system process control. Copyright © 2013 Associazione Italiana di Fisica Medica. Published by Elsevier Ltd. All rights reserved.

  14. 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.

  15. Source term assessment using inverse modeling of radiation dose measured with environmental radiation monitors located at different positions

    International Nuclear Information System (INIS)

    Srinivas, C.V.; Rakesh, P.T.; Baskaran, R.; Venkatraman, B.

    2018-01-01

    Source term is an important input for consequence analysis using Decision Support Systems (DSS) to project radiological impact in the event of nuclear emergencies. A source term model called 'ASTER' is incorporated in the Online Nuclear Emergency Response System (ONERS) operational at Kalpakkam site for decision making during nuclear emergencies. This computes release rates using inverse method by employing an atmospheric dispersion model and gamma dose rates measured by environmental radiation monitors (ERM) deployed around the nuclear plant. The estimates may depend on the distribution of ERMs around the release location. In this work, data from various gamma monitors located at different radii 0.75 km and 1.5 km is used to assess the accuracy in the source term estimation for stack releases of MAPS-PHWR at Kalpakkam

  16. Moball-Buoy Network: A Near-Real-Time Ground-Truth Distributed Monitoring System to Map Ice, Weather, Chemical Species, and Radiations, in the Arctic

    Science.gov (United States)

    Davoodi, F.; Shahabi, C.; Burdick, J.; Rais-Zadeh, M.; Menemenlis, D.

    2014-12-01

    The work had been funded by NASA HQ's office of Cryospheric Sciences Program. Recent observations of the Arctic have shown that sea ice has diminished drastically, consequently impacting the environment in the Arctic and beyond. Certain factors such as atmospheric anomalies, wind forces, temperature increase, and change in the distribution of cold and warm waters contribute to the sea ice reduction. However current measurement capabilities lack the accuracy, temporal sampling, and spatial coverage required to effectively quantify each contributing factor and to identify other missing factors. Addressing the need for new measurement capabilities for the new Arctic regime, we propose a game-changing in-situ Arctic-wide Distributed Mobile Monitoring system called Moball-buoy Network. Moball-buoy Network consists of a number of wind-propelled self-powered inflatable spheres referred to as Moball-buoys. The Moball-buoys are self-powered. They use their novel mechanical control and energy harvesting system to use the abundance of wind in the Arctic for their controlled mobility and energy harvesting. They are equipped with an array of low-power low-mass sensors and micro devices able to measure a wide range of environmental factors such as the ice conditions, chemical species wind vector patterns, cloud coverage, air temperature and pressure, electromagnetic fields, surface and subsurface water conditions, short- and long-wave radiations, bathymetry, and anthropogenic factors such as pollutions. The stop-and-go motion capability, using their novel mechanics, and the heads up cooperation control strategy at the core of the proposed distributed system enable the sensor network to be reconfigured dynamically according to the priority of the parameters to be monitored. The large number of Moball-buoys with their ground-based, sea-based, satellite and peer-to-peer communication capabilities would constitute a wireless mesh network that provides an interface for a global

  17. 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 ...

  18. Monitoring extensions for component-based distributed software

    NARCIS (Netherlands)

    Diakov, N.K.; Papir, Z.; van Sinderen, Marten J.; Quartel, Dick

    2000-01-01

    This paper defines a generic class of monitoring extensions to component-based distributed enterprise software. Introducing a monitoring extension to a legacy application system can be very costly. In this paper, we identify the minimum support for application monitoring within the generic

  19. 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

  20. 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)

  1. 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

  2. On precipitation monitoring with theoretical statistical distributions

    Science.gov (United States)

    Cindrić, Ksenija; Juras, Josip; Pasarić, Zoran

    2018-04-01

    A common practice in meteorological drought monitoring is to transform the observed precipitation amounts to the standardised precipitation index (SPI). Though the gamma distribution is usually employed for this purpose, some other distribution may be used, particularly in regions where zero precipitation amounts are recorded frequently. In this study, two distributions are considered alongside with the gamma distribution: the compound Poisson exponential distribution (CPE) and the square root normal distribution (SRN). They are fitted to monthly precipitation amounts measured at 24 stations in Croatia in the 55-year-long period (1961-2015). At five stations, long-term series (1901-2015) are available and they have been used for a more detailed investigation. The accommodation of the theoretical distributions to empirical ones is tested by comparison of the corresponding empirical and theoretical ratios of the skewness and the coefficient of variation. Furthermore, following the common approach to precipitation monitoring (CLIMAT reports), the comparison of the empirical and theoretical quintiles in the two periods (1961-1990 and 1991-2015) is examined. The results from the present study reveal that it would be more appropriate to implement theoretical distributions in such climate reports, since they provide better evaluation for monitoring purposes than the current empirical distribution. Nevertheless, deciding on an optimal theoretical distribution for different climate regimes and for different time periods is not easy to accomplish. With regard to Croatian stations (covering different climate regimes), the CPE or SRN distribution could also be the right choice in the climatological practice, in addition to the gamma distribution.

  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 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

  5. 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).

  6. 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)

  7. 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

  8. Quality monitored distributed voting system

    Science.gov (United States)

    Skogmo, David

    1997-01-01

    A quality monitoring system can detect certain system faults and fraud attempts in a distributed voting system. The system uses decoy voters to cast predetermined check ballots. Absent check ballots can indicate system faults. Altered check ballots can indicate attempts at counterfeiting votes. The system can also cast check ballots at predetermined times to provide another check on the distributed voting system.

  9. 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)

  10. 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)

  11. 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)

  12. 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

  13. 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

  14. 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)

  15. Distribution of natural radionuclides and radiation level measurements in Karnataka State, India. An overview

    International Nuclear Information System (INIS)

    Rangaswamy, D.R.; Sannappa, J.

    2016-01-01

    The exposure of human beings to ionizing radiation from natural sources is a continuing and inescapable feature of life on earth. A large number of natural radioactivity measurements were conducted throughout world, in order to know their distribution and to assess their radiological health hazards. In this regard, considerable studies have been conducted by different research groups in Karnataka state and more data are reported. In this article, all the studies of natural radioactivity measurements have been combined and reviewed. The majority of the reported articles are about monitoring, distribution and assessment of the radiological health hazards of naturally occurring radionuclides. (author)

  16. 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

  17. LCLS-S1 optical transition radiation monitor

    International Nuclear Information System (INIS)

    Berg, W.J.; Yang, B.; Erwin, L.L.; Shoaf, S.E.

    2008-01-01

    Argonne National Laboratory has developed a high- resolution optical transition radiation (OTR) imaging monitor for the Linac Coherent Light Source (LCLS) injection linac at SLAC. The imaging station,OTR-S1, will be located at the S1 spectrometer with a beam energy of 135 MeV. The system will be used to acquire 2-D transverse beam distributions of the accelerated photocathode-gun-generated electron beam. We anticipate an average beam current of 0.2 to 1 nC and nominal beam spot size of 130 mum (sigmax), 100 mum (sigmay). The imaging system was designed for a field of view x/y: 10 times 7.5 mm. The spatial resolution of ∼12 microns was verified over the central 5times4 mm region in the visible. A 12-bit digital camera acquires the image and a Mac-based digital frame-capturing system was employed for the initial lab-based performance testing of the device. We report on system development, testing methods, and data analysis.

  18. 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

  19. 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.

  20. 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.

  1. 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

  2. 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.

  3. 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)

  4. 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

  5. Monitoring fish distributions along electrofishing segments

    Science.gov (United States)

    Miranda, Leandro E.

    2014-01-01

    Electrofishing is widely used to monitor fish species composition and relative abundance in streams and lakes. According to standard protocols, multiple segments are selected in a body of water to monitor population relative abundance as the ratio of total catch to total sampling effort. The standard protocol provides an assessment of fish distribution at a macrohabitat scale among segments, but not within segments. An ancillary protocol was developed for assessing fish distribution at a finer scale within electrofishing segments. The ancillary protocol was used to estimate spacing, dispersion, and association of two species along shore segments in two local reservoirs. The added information provided by the ancillary protocol may be useful for assessing fish distribution relative to fish of the same species, to fish of different species, and to environmental or habitat characteristics.

  6. 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

  7. 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

  8. 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.

  9. 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

  10. 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

  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. Comptonization of low-frequency radiation in accretion disks Angular distribution and polarization of hard X-ray radiation

    International Nuclear Information System (INIS)

    Suniaev, R.A.; Titarchuk, L.G.

    1984-01-01

    Analytical consideration is given to the comptonization of photons and its effects on the radiation emitted from accretion disks of compact X-ray sources, such as black holes and neutron stars. Attention is given to the photon distribution during escape from the disk, the angular distribution of hard radiation from the disk, the polarization of hard radiation and the electron temperature distribution over the optical depth. It is shown that the hard radiation spectrum is independent of the low-frequency photon source distribution. The angular distribution and polarization of the outgoing X-rays are a function of the optical depth. A Thomson approximation is used to estimate the angular distribution of the hard radiation and the polarization over the disk. The polarization results are compared with OSO-8 satellite data for Cyg X-1 and show good agreement at several energy levels. 17 references

  13. Influence of topography on landscape radiation temperature distribution

    International Nuclear Information System (INIS)

    Florinsky, I.V.; Kulagina, T.B.; Meshalkina, J.L.

    1994-01-01

    The evaluation of the influence of topography on landscape radiation temperature distribution is carried out by statistical processing of digital models of elevation, gradient, aspect, horizontal, vertical and mean land surface curvatures and the infrared thermal scene generated by the Thermovision 880 system. Significant linear correlation coefficients between the landscape radiation temperature and elevation, slope, aspect, vertical and mean landsurface curvatures are determined, being —0-57, 0 38, 0-26, 015, 013, respectively. The equation of the topography influence on the distribution of the landscape radiation temperature is defined. (author)

  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. A novel detector based on dual-mode fiber polished half block's characteristics for sensitive monitorings of radiation and materials

    International Nuclear Information System (INIS)

    Saeed, Ghadirli

    2005-01-01

    Full text : The overlay index dependence characteristics of the power distribution between two modes of dual-mode fiber polished half blocks is studied. The heat dependence characteristics of a certain overlay index affects the modal power distributions at the input of interferometer sensors used for monitoring the sensitive heat radiation changes. The other fundamental applications such as material recognitions through the index dependence characteristics in the closed chambers is also suggested

  16. 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

  17. 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)

  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. 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

  1. 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)

  2. 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.

  3. 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

  4. 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)

  5. 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

  6. 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)

  7. The GBT-SCA, a radiation tolerant ASIC for detector control and monitoring applications in HEP experiments

    International Nuclear Information System (INIS)

    Caratelli, A.; Bonacini, S.; Kloukinas, K.; Marchioro, A.; Moreira, P.; Oliveira, R. De; Paillard, C.

    2015-01-01

    The future upgrades of the LHC experiments will increase the beam luminosity leading to a corresponding growth of the amounts of data to be treated by the data acquisition systems. To address these needs, the GBT (Giga-Bit Transceiver optical link [1,2]) architecture was developed to provide the simultaneous transfer of readout data, timing and trigger signals as well as slow control and monitoring data. The GBT-SCA ASIC, part of the GBT chip-set, has the purpose to distribute control and monitoring signals to the on-detector front-end electronics and perform monitoring operations of detector environmental parameters. In order to meet the requirements of different front-end ASICs used in the experiments, it provides various user-configurable interfaces capable to perform simultaneous operations. It is designed employing radiation tolerant design techniques to ensure robustness against SEUs and TID radiation effects and is implemented in a commercial 130 nm CMOS technology. This work presents the GBT-SCA architecture, the ASIC interfaces, the data transfer protocol, and its integration with the GBT optical link

  8. Estimation of the Vertical Distribution of Radiocesium in Soil on the Basis of the Characteristics of Gamma-Ray Spectra Obtained via Aerial Radiation Monitoring Using an Unmanned Helicopter.

    Science.gov (United States)

    Ochi, Kotaro; Sasaki, Miyuki; Ishida, Mutsushi; Hamamoto, Shoichiro; Nishimura, Taku; Sanada, Yukihisa

    2017-08-17

    After the Fukushima Daiichi Nuclear Power Plant accident, the vertical distribution of radiocesium in soil has been investigated to better understand the behavior of radiocesium in the environment. The typical method used for measuring the vertical distribution of radiocesium is troublesome because it requires collection and measurement of the activity of soil samples. In this study, we established a method of estimating the vertical distribution of radiocesium by focusing on the characteristics of gamma-ray spectra obtained via aerial radiation monitoring using an unmanned helicopter. The estimates are based on actual measurement data collected at an extended farm. In this method, the change in the ratio of direct gamma rays to scattered gamma rays at various depths in the soil was utilized to quantify the vertical distribution of radiocesium. The results show a positive correlation between the abovementioned and the actual vertical distributions of radiocesium measured in the soil samples. A vertical distribution map was created on the basis of this ratio using a simple equation derived from the abovementioned correlation. This technique can provide a novel approach for effective selection of high-priority areas that require decontamination.

  9. Estimation of the Vertical Distribution of Radiocesium in Soil on the Basis of the Characteristics of Gamma-Ray Spectra Obtained via Aerial Radiation Monitoring Using an Unmanned Helicopter

    Science.gov (United States)

    Ochi, Kotaro; Sasaki, Miyuki; Ishida, Mutsushi; Sanada, Yukihisa

    2017-01-01

    After the Fukushima Daiichi Nuclear Power Plant accident, the vertical distribution of radiocesium in soil has been investigated to better understand the behavior of radiocesium in the environment. The typical method used for measuring the vertical distribution of radiocesium is troublesome because it requires collection and measurement of the activity of soil samples. In this study, we established a method of estimating the vertical distribution of radiocesium by focusing on the characteristics of gamma-ray spectra obtained via aerial radiation monitoring using an unmanned helicopter. The estimates are based on actual measurement data collected at an extended farm. In this method, the change in the ratio of direct gamma rays to scattered gamma rays at various depths in the soil was utilized to quantify the vertical distribution of radiocesium. The results show a positive correlation between the abovementioned and the actual vertical distributions of radiocesium measured in the soil samples. A vertical distribution map was created on the basis of this ratio using a simple equation derived from the abovementioned correlation. This technique can provide a novel approach for effective selection of high-priority areas that require decontamination. PMID:28817098

  10. 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

  11. 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

  12. 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)

  13. Application of «Sensor signal analysis network» complex for distributed, time synchronized analysis of electromagnetic radiation

    Science.gov (United States)

    Mochalov, Vladimir; Mochalova, Anastasia

    2017-10-01

    The paper considers a developing software-hardware complex «Sensor signal analysis network» for distributed and time synchronized analysis of electromagnetic radiations. The areas of application and the main features of the complex are described. An example of application of the complex to monitor natural electromagnetic radiation sources is considered based on the data recorded in VLF range. A generalized functional scheme of stream analysis of signals by a complex functional node is suggested and its application for stream detection of atmospherics, whistlers and tweaks is considered.

  14. 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.

  15. 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.

  16. 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

  17. Distributed Monitoring System Based on ICINGA

    CERN Multimedia

    Haen, C; Neufeld, N

    2011-01-01

    The LHCb online system relies on a large and heterogeneous I.T. infrastructure : it comprises more than 2000 servers and embedded systems and more than 200 network devices. While for the control and monitoring of detectors, PLCs, and readout boards an industry standard SCADA system PVSSII has been put in production, we use a low level monitoring system to monitor the control infrastructure itself. While our previous system was based on a single central NAGIOS server, our current system uses a distributed ICINGA infrastructure.

  18. [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.

  19. Proposal for the award of an industrial support contract for radiation monitoring services for LEP dismantling

    CERN Document Server

    2000-01-01

    This document concerns the award of an Industrial Service contract for radiation monitoring services for LEP dismantling. Following a market survey carried out among 34 firms in nine Member States, a call for tenders (IT-2769/SL/LEP) was sent on 13 March 2000 to seven firms and three consortia in five Member States. By the closing date, CERN had received six tenders from three firms and three consortia in four Member States. The Finance Committee is invited to agree to the negotiation of a contract with the consortium ISS MULTISERVICE (CH), NFI (SE) and ISS GEBÄUDESERVICE (DE), the lowest technically qualified bidder, for radiation monitoring services for LEP dismantling for a total amount of 990 792 Swiss francs, not subject to revision. The firm has indicated the following distribution by country of the contract value covered by this adjudication proposal: CH-59%, DE-26%, SE-15%.

  20. 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.

  1. Monitoring Distributed Real-Time Systems: A Survey and Future Directions

    Science.gov (United States)

    Goodloe, Alwyn E.; Pike, Lee

    2010-01-01

    Runtime monitors have been proposed as a means to increase the reliability of safety-critical systems. In particular, this report addresses runtime monitors for distributed hard real-time systems. This class of systems has had little attention from the monitoring community. The need for monitors is shown by discussing examples of avionic systems failure. We survey related work in the field of runtime monitoring. Several potential monitoring architectures for distributed real-time systems are presented along with a discussion of how they might be used to monitor properties of interest.

  2. 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.

  3. The transition radiation. I: numerical study of the angular and spectral distributions

    International Nuclear Information System (INIS)

    Couillaud, Ch.; Haouat, G.

    1999-01-01

    The optical transition radiation (OTR) is extensively used since many years as a beam visualisation tool on electron accelerators and serves to monitor the beam during its transport adjustment. Its spatial and temporal characteristics make it very attractive as a diagnostic tool and allow measurements of the beam energy and transverse and longitudinal emittances. We present a numerical study of the transition radiation process in the optical region of the radiated spectrum (OTR) and in the higher part (XTR). Spatial and spectral properties are described. They are used to describe experimental observations performed on the ELSA electron-beam facility. An analytical description of the angular distributions of visible radiation emitted by birefringent targets, used as OTR sources, is also proposed. We also analyze interference phenomena between two OTR sources and show the advantage of using this interferometer as a diagnostic tool for tenth MeV electron accelerators. At last, we present an analytical model allowing to design a soft X-ray source to be installed on the ELSA facility and using either a multi-foil stack or a multilayer of two materials of different permittivities. (authors)

  4. 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.

  5. 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.

  6. 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

  7. 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.

  8. 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.

  9. 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.

  10. 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)

  11. Distributed intelligent urban environment monitoring system

    Science.gov (United States)

    Du, Jinsong; Wang, Wei; Gao, Jie; Cong, Rigang

    2018-02-01

    The current environmental pollution and destruction have developed into a world-wide major social problem that threatens human survival and development. Environmental monitoring is the prerequisite and basis of environmental governance, but overall, the current environmental monitoring system is facing a series of problems. Based on the electrochemical sensor, this paper designs a small, low-cost, easy to layout urban environmental quality monitoring terminal, and multi-terminal constitutes a distributed network. The system has been small-scale demonstration applications and has confirmed that the system is suitable for large-scale promotion

  12. 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

  13. Distributed computing for real-time petroleum reservoir monitoring

    Energy Technology Data Exchange (ETDEWEB)

    Ayodele, O. R. [University of Alberta, Edmonton, AB (Canada)

    2004-05-01

    Computer software architecture is presented to illustrate how the concept of distributed computing can be applied to real-time reservoir monitoring processes, permitting the continuous monitoring of the dynamic behaviour of petroleum reservoirs at much shorter intervals. The paper describes the fundamental technologies driving distributed computing, namely Java 2 Platform Enterprise edition (J2EE) by Sun Microsystems, and the Microsoft Dot-Net (Microsoft.Net) initiative, and explains the challenges involved in distributed computing. These are: (1) availability of permanently placed downhole equipment to acquire and transmit seismic data; (2) availability of high bandwidth to transmit the data; (3) security considerations; (4) adaptation of existing legacy codes to run on networks as downloads on demand; and (5) credibility issues concerning data security over the Internet. Other applications of distributed computing in the petroleum industry are also considered, specifically MWD, LWD and SWD (measurement-while-drilling, logging-while-drilling, and simulation-while-drilling), and drill-string vibration monitoring. 23 refs., 1 fig.

  14. DAMT - DISTRIBUTED APPLICATION MONITOR TOOL (HP9000 VERSION)

    Science.gov (United States)

    Keith, B.

    1994-01-01

    Typical network monitors measure status of host computers and data traffic among hosts. A monitor to collect statistics about individual processes must be unobtrusive and possess the ability to locate and monitor processes, locate and monitor circuits between processes, and report traffic back to the user through a single application program interface (API). DAMT, Distributed Application Monitor Tool, is a distributed application program that will collect network statistics and make them available to the user. This distributed application has one component (i.e., process) on each host the user wishes to monitor as well as a set of components at a centralized location. DAMT provides the first known implementation of a network monitor at the application layer of abstraction. Potential users only need to know the process names of the distributed application they wish to monitor. The tool locates the processes and the circuit between them, and reports any traffic between them at a user-defined rate. The tool operates without the cooperation of the processes it monitors. Application processes require no changes to be monitored by this tool. Neither does DAMT require the UNIX kernel to be recompiled. The tool obtains process and circuit information by accessing the operating system's existing process database. This database contains all information available about currently executing processes. Expanding the information monitored by the tool can be done by utilizing more information from the process database. Traffic on a circuit between processes is monitored by a low-level LAN analyzer that has access to the raw network data. The tool also provides features such as dynamic event reporting and virtual path routing. A reusable object approach was used in the design of DAMT. The tool has four main components; the Virtual Path Switcher, the Central Monitor Complex, the Remote Monitor, and the LAN Analyzer. All of DAMT's components are independent, asynchronously executing

  15. 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

  16. 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.

  17. 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)

  18. 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)

  19. 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)

  20. 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.

  1. 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

  2. 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)

  3. 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)

  4. 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

  5. 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.

  6. 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

  7. 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)

  8. 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

  9. 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

  10. Distributed optical fibre temperature measurements in a low dose rate radiation environment based on Rayleigh backscattering

    Science.gov (United States)

    Faustov, A.; Gussarov, A.; Wuilpart, M.; Fotiadi, A. A.; Liokumovich, L. B.; Kotov, O. I.; Zolotovskiy, I. O.; Tomashuk, A. L.; Deschoutheete, T.; Mégret, P.

    2012-04-01

    On-line monitoring of environmental conditions in nuclear facilities is becoming a more and more important problem. Standard electronic sensors are not the ideal solution due to radiation sensitivity and difficulties in installation of multiple sensors. In contrast, radiation-hard optical fibres can sustain very high radiation doses and also naturally offer multi-point or distributed monitoring of external perturbations. Multiple local electro-mechanical sensors can be replaced by just one measuring fibre. At present, there are over four hundred operational nuclear power plants (NPPs) in the world 1. Operating experience has shown that ineffective control of the ageing degradation of major NPP components can threaten plant safety and also plant life. Among those elements, cables are vital components of I&C systems in NPPs. To ensure their safe operation and predict remaining life, environmental monitoring is necessary. In particular, temperature and radiation dose are considered to be the two most important parameters. The aim of this paper is to assess experimentally the feasibility of optical fibre temperature measurements in a low doserate radiation environment, using a commercially available reflectometer based on Rayleigh backscattering. Four different fibres were installed in the Sub-Pile Room of the BR2 Material testing nuclear reactor in Mol, Belgium. This place is man-accessible during the reactor shut-down, allowing easy fibre installation. When the reactor operates, the dose-rates in the room are in a range 0.005-5 Gy/h with temperatures of 40-60 °C, depending on the location. Such a surrounding is not much different to some "hot" environments in NPPs, where I&C cables are located.

  11. System and Method for Monitoring Distributed Asset Data

    Science.gov (United States)

    Gorinevsky, Dimitry (Inventor)

    2015-01-01

    A computer-based monitoring system and monitoring method implemented in computer software for detecting, estimating, and reporting the condition states, their changes, and anomalies for many assets. The assets are of same type, are operated over a period of time, and outfitted with data collection systems. The proposed monitoring method accounts for variability of working conditions for each asset by using regression model that characterizes asset performance. The assets are of the same type but not identical. The proposed monitoring method accounts for asset-to-asset variability; it also accounts for drifts and trends in the asset condition and data. The proposed monitoring system can perform distributed processing of massive amounts of historical data without discarding any useful information where moving all the asset data into one central computing system might be infeasible. The overall processing is includes distributed preprocessing data records from each asset to produce compressed data.

  12. Estimation of monthly solar radiation distribution for solar energy system analysis

    International Nuclear Information System (INIS)

    Coskun, C.; Oktay, Z.; Dincer, I.

    2011-01-01

    The concept of probability density frequency, which is successfully used for analyses of wind speed and outdoor temperature distributions, is now modified and proposed for estimating solar radiation distributions for design and analysis of solar energy systems. In this study, global solar radiation distribution is comprehensively analyzed for photovoltaic (PV) panel and thermal collector systems. In this regard, a case study is conducted with actual global solar irradiation data of the last 15 years recorded by the Turkish State Meteorological Service. It is found that intensity of global solar irradiance greatly affects energy and exergy efficiencies and hence the performance of collectors. -- Research highlights: → The first study to apply global solar radiation distribution in solar system analyzes. → The first study showing global solar radiation distribution as a parameter of the solar irradiance intensity. → Time probability intensity frequency and probability power distribution do not have similar distribution patterns for each month. → There is no relation between the distribution of annual time lapse and solar energy with the intensity of solar irradiance.

  13. 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)

  14. 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

  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. Occupational radiation doses among diagnostic radiation workers in South Korea, 1996-2006

    International Nuclear Information System (INIS)

    Lee, W. J.; Cha, E. S.; Ha, M.; Jin, Y. W.; Hwang, S. S.; Kong, K. A.; Lee, S. W.; Lee, H. K.; Lee, K. Y.; Kim, H. J.

    2009-01-01

    This study details the distribution and trends of doses of occupational radiation among diagnostic radiation workers by using the national dose registry between 1996 and 2006 by the Korea Food and Drug Administration. Dose measurements were collected quarterly by the use of thermoluminescent dosemeter personal monitors. A total of 61 732 workers were monitored, including 18 376 radiologic technologists (30%), 13 762 physicians (22%), 9858 dentists (16%) and 6114 dental hygienists (9.9%). The average annual effective doses of all monitored workers decreased from 1.75 to 0.80 mSv over the study period. Among all diagnostic radiation workers, radiologic technologists received both the highest effective and collective doses. Male radiologic technologists aged 30-49 y composed the majority of workers receiving more than 5 mSv in a quarter. More intensive monitoring of occupational radiation exposure and investigation into its health effects on diagnostic radiation workers are required in South Korea. (authors)

  17. 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)

  18. 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

  19. 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.

  20. 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.

  1. 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.

  2. 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.

  3. 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

  4. 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

  5. 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)

  6. 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

  7. 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

  8. 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

  9. 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.

  10. 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

  11. 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

  12. 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.

  13. 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

  14. 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)

  15. 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.

  16. 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.

  17. 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)

  18. 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)

  19. 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

  20. 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)

  1. 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

  2. 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.

  3. 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)

  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. 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)

  8. 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.)

  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. 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

  12. 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

  13. 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)

  14. 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)

  15. 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

  16. 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)

  17. An inverse source location algorithm for radiation portal monitor applications

    International Nuclear Information System (INIS)

    Miller, Karen A.; Charlton, William S.

    2010-01-01

    Radiation portal monitors are being deployed at border crossings throughout the world to prevent the smuggling of nuclear and radiological materials; however, a tension exists between security and the free-flow of commerce. Delays at ports-of-entry have major economic implications, so it is imperative to minimize portal monitor screening time. We have developed an algorithm to locate a radioactive source using a distributed array of detectors, specifically for use at border crossings. To locate the source, we formulated an optimization problem where the objective function describes the least-squares difference between the actual and predicted detector measurements. The predicted measurements are calculated by solving the 3-D deterministic neutron transport equation given an estimated source position. The source position is updated using the steepest descent method, where the gradient of the objective function with respect to the source position is calculated using adjoint transport calculations. If the objective function is smaller than the convergence criterion, then the source position has been identified. This paper presents the derivation of the underlying equations in the algorithm as well as several computational test cases used to characterize its accuracy.

  18. 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).

  19. 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)

  20. 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)

  1. 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)

  2. GREENHOUSE PLASTIC FILMS CAPABLE OF MODIFYING THE SPECTRAL DISTRIBUTION OF SOLAR RADIATION

    Directory of Open Access Journals (Sweden)

    Evelia Schettini

    2010-03-01

    Full Text Available The aim of this paper was to investigate the radiometric properties of innovative covering films for protected cultivation capable of modifying the spectral distribution of the transmitted radiation and thus the vegetative activity. Two photoselective films, three photoluminescent films and one low-density polyethylene film were used as greenhouse coverings for cherry trees and peach trees, grown in pots. The photoselective films were characterised by a reduction of the R/FR ratio in comparison to the natural solar radiation. Tree growth parameters, such as the apical shoot of cherry trees and the shoot of peach trees, were monitored. Different responses to vegetative activities were observed under the films, depending on the species, with a higher shoots growth rate in the peach with respect to the cherry. The photoselective film characterised by the lowest R/FR ratio significantly enhanced the growth of cherry and peach trees in comparison to the trees cultivated under the other greenhouse films

  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. Distributed Monitoring of Voltage Collapse Sensitivity Indices

    OpenAIRE

    Simpson-Porco, John W.; Bullo, Francesco

    2016-01-01

    The assessment of voltage stability margins is a promising direction for wide-area monitoring systems. Accurate monitoring architectures for long-term voltage instability are typically centralized and lack scalability, while completely decentralized approaches relying on local measurements tend towards inaccuracy. Here we present distributed linear algorithms for the online computation of voltage collapse sensitivity indices. The computations are collectively performed by processors embedded ...

  5. 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.

  6. Film badge personnel monitoring and dose distribution of industrial and medical workers in the country (1994-1998)

    International Nuclear Information System (INIS)

    Mittal, Hariom; Pandey, R.L.; Massand, O.P.

    2001-03-01

    Personnel Monitoring Section, Bhabha Atomic Research Centre, Mumbai, is entrusted with the responsibility of providing a countrywide personnel monitoring to radiation workers using extemal radiation like X, beta, gamma and neutron. As per Radiation Protection Rules (RPR) of 1971 promulgated by the competent authority the personnel monitoring service is mandatory for all the workers working with radiation. The radiation exposures received by them should be within the limits stipulated by AERB. Nearly 43,000 radiation workers in about 3000 DAE and non DAE institutions using radiation and radioisotopes are monitored, using both the Film Badges and the Thermoluminescent dosimeters. This report presents various aspects of film dosimetry which was introduced more than four decades ago in the country and also analysis of doses received by the radiation workers in the five year block 1994-1998 covered by film badge service. (author)

  7. 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)

  8. 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)

  9. 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.

  10. 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

  11. 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)

  12. 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

  13. 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)

  14. 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

  15. 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

  16. 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.

  17. Distributed optical fiber sensors for integrated monitoring of railway infrastructures

    Science.gov (United States)

    Minardo, Aldo; Coscetta, Agnese; Porcaro, Giuseppe; Giannetta, Daniele; Bernini, Romeo; Zeni, Luigi

    2014-05-01

    We propose the application of a distributed optical fiber sensor based on stimulated Brillouin scattering, as an integrated system for safety monitoring of railway infrastructures. The strain distribution was measured dynamically along a 60 meters length of rail track, as well as along a 3-m stone arch bridge. The results indicate that distributed sensing technology is able to provide useful information in railway traffic and safety monitoring.

  18. 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

  19. 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.

  20. 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.)

  1. 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

  2. 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)

  3. 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

  4. 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.

  5. 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.

  6. 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

  7. 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.)

  8. Reactor power distribution monitor

    International Nuclear Information System (INIS)

    Sekimizu, Koichi

    1980-01-01

    Purpose: To improve the performance and secure the safety of a nuclear reactor by rapidly computing and display the power density in the nuclear reactor by using a plurality of processors. Constitution: Plant data for a nuclear reactor containing the measured values from a local power monitor LPRM are sent and recorded in a magnetic disc. They are also sent to a core performance computer in which burn-up degree distribution and the like are computed, and the results are sent and recorded in the magnetic disc. A central processors loads programs to each of the processors and applies data recorded in the magnetic disc to each of the processors. Each of the processors computes the corresponding power distribution in four fuel assemblies surrounding the LPRM string by the above information. The central processor compiles the computation results and displays them on a display. In this way, power distribution in the fuel assemblies can rapidly be computed to thereby secure the improvement of the performance and safety of the reactor. (Seki, T.)

  9. 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)

  10. 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)

  11. 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)

  12. The software design of area γ radiation monitoring system

    International Nuclear Information System (INIS)

    Song Chenxin; Deng Changming; Cheng Chang; Ren Yi; Meng Dan; Liu Yun

    2007-01-01

    This paper main introduction the system structure, software architecture, design ideas of the area γ radiation monitoring system. Detailed introduction some programming technology about the computer communication with the local display unit. (authors)

  13. The software design of area γ radiation monitoring system

    International Nuclear Information System (INIS)

    Song Chenxin; Deng Changming; Cheng Chang; Ren Yi; Meng Dan; Liu Yun

    2008-01-01

    This paper main introduction the system structure, software architecture, design ideas of the area γ radiation monitoring system. Detailed introduction some programming technology about the computer communication with the local display unit. (authors)

  14. Workplace monitoring of mixed neutron-photon radiation fields and its contribution to external dosimetry

    International Nuclear Information System (INIS)

    Schuhmacher, H.

    2011-01-01

    Workplace monitoring is a common procedure for determining measures for routine radiation protection in a particular working environment. For mixed radiation fields consisting of neutrons and photons, it is of increased importance because it contributes to the improved accuracy of individual monitoring. An example is the determination of field-specific correction factors, which can be applied to the readings of personal dosemeters. This paper explains the general problems associated with individual dosimetry of neutron radiation, and describes the various options for workplace monitoring. These options cover a range from the elaborate field characterisation using transport calculations or spectrometers to the simpler approach using area monitors. Examples are given for workplaces in nuclear industry, at particle accelerators and at flight altitudes. (authors)

  15. Environmental Radiation Monitoring In The Chernobyl Exclusion Zone - History And Results 25 Years After

    International Nuclear Information System (INIS)

    Farfan, E.; Jannik, T.

    2011-01-01

    This article describes results of the radiation environmental monitoring performed in the Chernobyl Exclusion Zone (ChEZ) during the period following the 1986 Chernobyl Nuclear Power Plant accident. This article presents a brief overview of five comprehensive reports generated under Contract No. DE-AC09-96SR18500 (Washington Savannah River Company LLC, Subcontract No. AC55559N, SOW No. ON8778) and summarizes characteristics of the ChEZ and its post-accident status and the history of development of the radiation monitoring research in the ChEZ is described. This article addresses characteristics of the radiation monitoring in the ChEZ, its major goals and objectives, and changes of these goals and objectives in the course of time, depending on the tasks associated with the phase of mitigation of the ChNPP accident consequences. The results of the radiation monitoring in the ChEZ during the last 25 years are also provided.

  16. ENVIRONMENTAL RADIATION MONITORING IN THE CHERNOBYL EXCLUSION ZONE - HISTORY AND RESULTS 25 YEARS AFTER

    Energy Technology Data Exchange (ETDEWEB)

    Farfan, E.; Jannik, T.

    2011-10-01

    This article describes results of the radiation environmental monitoring performed in the Chernobyl Exclusion Zone (ChEZ) during the period following the 1986 Chernobyl Nuclear Power Plant accident. This article presents a brief overview of five comprehensive reports generated under Contract No. DE-AC09-96SR18500 (Washington Savannah River Company LLC, Subcontract No. AC55559N, SOW No. ON8778) and summarizes characteristics of the ChEZ and its post-accident status and the history of development of the radiation monitoring research in the ChEZ is described. This article addresses characteristics of the radiation monitoring in the ChEZ, its major goals and objectives, and changes of these goals and objectives in the course of time, depending on the tasks associated with the phase of mitigation of the ChNPP accident consequences. The results of the radiation monitoring in the ChEZ during the last 25 years are also provided.

  17. Radiation monitor

    International Nuclear Information System (INIS)

    Pao, C.T.; Green, W.K.

    1978-01-01

    A system for indicating radiation from a radioactive fluid such as a gas wherein simultaneous indications of the activity concentration of radioactivity of the gas, the radiation dose rate and average energy of the radiation are provided

  18. Status of eye lens radiation dose monitoring in European hospitals

    International Nuclear Information System (INIS)

    Carinou, Eleftheria; Ginjaume, Merce; O’Connor, Una; Kopec, Renata; Sans Merce, Marta

    2014-01-01

    A questionnaire was developed by the members of WG12 of EURADOS in order to establish an overview of the current status of eye lens radiation dose monitoring in hospitals. The questionnaire was sent to medical physicists and radiation protection officers in hospitals across Europe. Specific topics were addressed in the questionnaire such as: knowledge of the proposed eye lens dose limit; monitoring and dosimetry issues; training and radiation protection measures. The results of the survey highlighted that the new eye lens dose limit can be exceeded in interventional radiology procedures and that eye lens protection is crucial. Personnel should be properly trained in how to use protective equipment in order to keep eye lens doses as low as reasonably achievable. Finally, the results also highlighted the need to improve the design of eye dosemeters in order to ensure satisfactory use by workers. (paper)

  19. 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

  20. 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

  1. Personnel radiation exposure in the Asse saltmine repository during 1967 to 2008. Health monitoring Asse

    International Nuclear Information System (INIS)

    2011-02-01

    The health monitoring Asse includes the following chapters: Introduction, background information including handling of radioactive materials and radiation protection issues, data on radiation exposure (personnel dosimetry, incorporation surveillance, local dose rate measurements, exhaust monitoring, radioactivity in the salt mine air and in the brine, contamination), concept of the data base, interrogation of the personnel, quantification of the individual radiation doses, results of the radiation exposure quantification; significance of the results and perspectives.

  2. 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

  3. Design, construction and characterization of special ionization chambers for X radiation beams monitoring

    International Nuclear Information System (INIS)

    Yoshizumi, Maira Tiemi

    2010-01-01

    X radiation equipment may show fluctuations in the radiation beam intensity, as they are connected to the power net. These intensity variations can, in turn, modify the air kerma rate produced by this radiation beam. In a calibration laboratory, where radiation detectors (from clinics and hospital services) are calibrated, variations in the radiation beam intensity may cause an error in the absorbed dose determination. The monitor ionization chambers are used to verify the radiation beam intensity constancy, and to provide a correction for possible fluctuations. In this work, monitor ionization chambers for X radiation beams were designed, assembled and characterized. The developed ionization chambers have an innovative design, ring-shaped, with aluminium or graphite electrodes. These ring-shaped ionization chambers have the advantage of not interfering in the direct radiation beams. A double-volume ionization chamber with graphite electrodes was also developed. This ionization chamber is similar to the commercial monitor ionization chamber used in the Calibration Laboratory of the Instituto de Pesquisas Energeticas e Nucleares. All developed ionization chambers were tested in several standardized radiation beams and their performances were compared with those of commercial ionization chambers. The results show that two of the four ionization chambers developed showed performance comparable to that of the commercial ionization chambers tested. Besides presenting good results, the ionization chambers were designed and manufactured using low cost materials, which are easily found on the Brazilian market. (author)

  4. Experiences in the monitoring of radiation workers in industry and hospitals in the Philippines

    International Nuclear Information System (INIS)

    Mateo, A.J.

    1976-08-01

    The task of monitoring of radiation doses among radiation workers employed either in industry and hospitals in the Philippines is presently being undertaken by the Philippine Atomic Energy Commission. These radiation monitoring devices cover not only radioactive materials or sources but also x-ray machines. The most common dosimetry used is the film badge. This paper presents some of the experiences gained in the use of the film badge and other dosimeters

  5. Radiation detectors as surveillance monitors for IAEA safeguards

    International Nuclear Information System (INIS)

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

    1980-10-01

    Radiation detectors used for personnel dosimetry are examined for use under IAEA Safeguards as monitors to confirm the passage or nonpassage (YES/NO) of plutonium-bearing nuclear material at barrier penetrations declared closed. In this application where backgrounds are ill defined, no advantage is found for a particular detector type because of intrinsic efficiency. Secondary considerations such as complexity, ease of tamper-proofing, and ease of readout are used to recommend specific detector types for routine monitoring and for data-base measurements. Recommendations are made for applications, data acquisition, and instrument development

  6. Radiation detectors as surveillance monitors for IAEA safeguards

    Energy Technology Data Exchange (ETDEWEB)

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

    1980-10-01

    Radiation detectors used for personnel dosimetry are examined for use under IAEA Safeguards as monitors to confirm the passage or nonpassage (YES/NO) of plutonium-bearing nuclear material at barrier penetrations declared closed. In this application where backgrounds are ill defined, no advantage is found for a particular detector type because of intrinsic efficiency. Secondary considerations such as complexity, ease of tamper-proofing, and ease of readout are used to recommend specific detector types for routine monitoring and for data-base measurements. Recommendations are made for applications, data acquisition, and instrument development.

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

    International Nuclear Information System (INIS)

    Sato, Tatsuhiko; Satoh, Daiki; Endo, Akira

    2006-01-01

    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 rapid response of DARWIN for measuring dose rates from neutrons, photons and muons with wide energies. With these properties, we conclude that DARWIN will be able to play a very important role for improving radiation safety in high energy accelerator facilities. (author)

  8. 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

  9. 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

  10. 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.)

  11. Results of the 1996-1998 IAEA co-ordinated research project on intercomparison for individual monitoring of external exposure to photon radiation

    International Nuclear Information System (INIS)

    Ouvrard, R.; Boehm, J.

    1999-01-01

    This paper presents the conclusions drawn at the end of the intercomparison, the purpose of which was to examine the performance of the dosimetry systems in radiation fields similar to those encountered in practical routine monitoring. These fields included, for a range of doses, mixed normally incident and wide angle fields of simulated direct source and room scatter radiation for some typical energy distributions and high-energy photons (6-7 MeV) with and without secondary electron equilibrium. Almost all of the participating services satisfied the evaluation criteria on overall accuracy for all fields. (author)

  12. Study of response of radiation monitors for environmental dose equivalent measurements

    International Nuclear Information System (INIS)

    Souza, Macilene N.; Khoury, H.J.

    2005-01-01

    The environmental dose equivalent H * (10), is the magnitude recommended by ICRU 39 for environmental monitoring in fields of radiation of photons. Most of the equipment used for area monitoring, only quantifies the magnitudes exposure or dose not being designed to this new magnitude. In Brazil, particularly, is not yet regulated the use of H * (10). However, with the revision of the standard 3.01 it will necessary the use of monitors that allow the achievement of measures according to H * (10). The transition for using new magnitudes will be a slow process and the contribution that the laboratories of metrology of ionizing radiation in the country can give is, at first, promote and create the habit of using the unit Sievert (Sv) in the calibration of the instruments, and that is the unit recommended for H * (10). In a second step, the tests for determining the response of the instruments for H * (10) should be made and this is the harder step, taking into account the large number of area monitors around the country. These tests will provide information about the limitations of the instrument to the new magnitude, that is, the range where the instrument will have the best performance in quantification of new magnitude. This paper evaluates the performance for H * (10), with the variation of energy and angle of incidence of radiation, of three of the most used monitors in the country

  13. Education and training issues in individual monitoring of ionising radiation

    International Nuclear Information System (INIS)

    Dimitriou, P.; Kamenopoulou, V.

    2011-01-01

    The present article deals with the education and training (E and T) issues of individual monitoring (IM) of ionising radiation, based on the requirements provided by the Basic Safety Standards EURATOM Directive and the European Commission Technical Recommendations for IM of external radiation. The structure and the objectives of E and T programmes addressed to the staff of dosimetry services, in order to allow the recognition and ensure the continuity of expertise are discussed. The necessity for the establishment of a national strategy for building competence in IM through information, education, training and retraining programmes, addressed to the individually monitored personnel is underlined. The train the trainers' concept is recognised as being an important tool for optimising resources and transferring the skills necessary for building competence. The conditions under which an efficient train the trainers' approach can be established are discussed. Examples of curricula concerning the key persons involved in the provision of E and T in occupational radiation protection are also given. (authors)

  14. 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

  15. Radiation leakage monitoring method and device from primary to secondary coolant systems in nuclear reactor

    International Nuclear Information System (INIS)

    Tajiri, Yoshiaki; Umehara, Toshihiro; Yamada, Masataka.

    1993-01-01

    The present invention monitors radiation leaked from any one of primary cooling systems to secondary cooling systems in a plurality of steam generators. That is, radiation monitoring means each corresponding to steam each generators are disposed to the upstream of a position where main steam pipes are joined. With such a constitution, since the detection object of each of radiation monitoring means is secondary coolants before mixing with secondary coolants of other secondary loops or dilution, lowering of detection accuracy can be avoided. Except for the abnormal case, that is, a case neither of radiation leakage nor of background change, the device is adapted as a convenient measuring system only with calculation performance. Once abnormality occurs, a loop having a value exceeding a standard value is identified by a single channel analyzer function. The amount of radiation leakage from the steam generator belonging to the specified loop is monitored quantitatively by a multichannel analyzer function. According to the method of the present invention, since specific spectrum analysis is conducted upon occurrence of abnormality, presence of radiation leakage and the scale thereof can be judged rapidly. (I.S.)

  16. 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.)

  17. Automated high-volume aerosol sampling station for environmental radiation monitoring

    International Nuclear Information System (INIS)

    Toivonen, H.; Honkamaa, T.; Ilander, T.; Leppaenen, A.; Nikkinen, M.; Poellaenen, R.; Ylaetalo, S.

    1998-07-01

    An automated high-volume aerosol sampling station, known as CINDERELLA.STUK, for environmental radiation monitoring has been developed by the Radiation and Nuclear Safety Authority (STUK), Finland. The sample is collected on a glass fibre filter (attached into a cassette), the airflow through the filter is 800 m 3 /h at maximum. During the sampling, the filter is continuously monitored with Na(I) scintillation detectors. After the sampling, the large filter is automatically cut into 15 pieces that form a small sample and after ageing, the pile of filter pieces is moved onto an HPGe detector. These actions are performed automatically by a robot. The system is operated at a duty cycle of 1 d sampling, 1 d decay and 1 d counting. Minimum detectable concentrations of radionuclides in air are typically 1Ae10 x 10 -6 Bq/m 3 . The station is equipped with various sensors to reveal unauthorized admittance. These sensors can be monitored remotely in real time via Internet or telephone lines. The processes and operation of the station are monitored and partly controlled by computer. The present approach fulfils the requirements of CTBTO for aerosol monitoring. The concept suits well for nuclear material safeguards, too

  18. Radiation monitoring of imported food to Saudi Arabia after Chernobyl

    International Nuclear Information System (INIS)

    Abulfaraj, W.H.; Abdul-Majid, S.; Abdul-Fattah, A.F.

    1987-01-01

    Saudi Arabia has been indirectly affected by the Chernobyl accident. Large amounts of food or products that may enter the food chain are daily imported from European countries. After April 27, the Saudi government assigned the responsibilities of radiation monitoring of imported food to some universities and governmental sectors. The nuclear engineering department at King Abdulaziz Univ. (KAU) has undertaken the monitoring duties for products coming to western and southern provinces of the country. The sampling and monitoring procedures and results are described

  19. A theoretical approach to calibrate radiation portal monitor (RPM) systems

    International Nuclear Information System (INIS)

    Nafee, Sherif S.; Abbas, Mahmoud I.

    2008-01-01

    Radiation portal monitor (RPM) systems are widely used at international border crossings, where they are applied to the task of detecting nuclear devices, special nuclear material, and radiation dispersal device materials that could appear at borders. The requirements and constraints on RPM systems deployed at high-volume border crossings are significantly different from those at weapons facilities or steel recycling plants, the former being required to rapidly detect localized sources of radiation with a very high detection probability and low false-alarm rate, while screening all of the traffic without impeding the flow of commerce [Chambers, W.H., Atwater, H.F., Fehlau, P.E., Hastings, R.D., Henry, C.N., Kunz, W.E., Sampson, T.E., Whittlesey, T.H., Worth, G.M., 1974. Portal Monitor for Diversion Safeguards. LA-5681, Los Alamos Scientific Laboratory, Los Alamos, NM]. In the present work, compact analytical formulae are derived and used to calibrate two RPM systems with isotropic radiating sources: (i) polyvinyltoluene (PVT) or plastic and (ii) thallium-doped crystalline sodium iodide, NaI(Tl), gamma-ray detector materials. The calculated efficiencies are compared to measured values reported in the literatures, showing very good agreement

  20. Environmental radiation monitoring on the CERN sites during 1995

    International Nuclear Information System (INIS)

    Moritz, L.; Wittekind, D.

    1996-01-01

    The CERN environmental monitoring programme covers the Meyrin and Prevessin sites, the six isolated islands (BA1, BA2, BA3, BA4, BA5, BA6) along the SPS Main Ring, the neutrino cave (BA7), and the seven surface areas PA2-PA8 specific to LEP. The results of the routine environmental monitoring programme enable CERN's compliance with national regulations of the host states and CERN's own Radiation Protection Policy to be assessed. Part I of this Annual Report describes the results of measurements which are relevant for assessing the radiological impact of CERN operations on the environment and the population living in the vicinity of the CERN sites. Measurements of radioactivity released into the atmosphere and into water, as well as measurements of stray radiation at or near the CERN site boundaries are reported

  1. Monitoring and assessment of individual doses of occupationally exposed workers due to external radiation

    International Nuclear Information System (INIS)

    Kitaw, S. T.

    2015-05-01

    Exposure to external radiation occurs in many occupations. Any exposure to ionizing radiation has the tendency to change the biochemical make-up of the human body which may result in biological health effects of ionizing radiation. This study reviews the monitoring and assessment of external radiation doses in industrial radiography using thermoluminescence and direct reading dosimeters. Poor handling procedures such as inadequate engineering control of equipment, safety culture, management, and inadequate assessment and monitoring of doses are the causes of most of the reported cases of exposure to external radiation in industrial radiography. Occupational exposure data in industrial radiography from UNSCEAR report 2008 was discussed and recommendations were made to regulatory authorities, operating organizations and radiographers. (au)

  2. Distributing radiation management system of nuclear power plants

    International Nuclear Information System (INIS)

    Mihoya, Eiichi; Akashi, Michio

    1999-01-01

    The importance of radiation management for nuclear facilities including nuclear power plants has increased as the general public understanding has progressed, and necessary information for management must be processed exactly and quickly. In nuclear power plants, radiation management is performed by each individual operation, and collected information is managed by the system of each operation. The distributing radiation management system has been developed aiming to use a general-purpose LAN and make quick and efficient use of information managed by individual operations. This paper describes the system configuration and functions. (author)

  3. Radiation monitoring of the Slovak Hydrometeorological Institute - Present and future

    International Nuclear Information System (INIS)

    Melicherova, T.

    2008-01-01

    Network for air radioactivity monitoring was developed in the frame Slovak Hydrometeorological Institute (SHMI) since 1963. There are data available for many years for beta radioactivity of the air particulate and deposition. At present network consist from 26 monitoring points for measurement of dose rate and 3 monitoring points for aerosol monitors. Measuring instrument are placed in the professional stations of the selected parts of Slovakia. They are regularly verified and calibrated in the Slovak Institute for Metrology. Radiation monitoring in the SHMI is one part of the Environmental monitoring of Slovakia. All activities and operation of this system are financed from governmental budget of the Environmental monitoring. All information about this system are available on the web page http://enviroportal.sk/ in the part 'Informacny system monitoringu'. (authors)

  4. Radiation monitoring of the Slovak Hydrometeorological Institute - Present and future

    International Nuclear Information System (INIS)

    Melicherova, T.

    2009-01-01

    Network for air radioactivity monitoring was developed in the frame Slovak Hydrometeorological Institute (SHMI) since 1963. There are data available for many years for beta radioactivity of the air particulate and deposition. At present network consist from 26 monitoring points for measurement of dose rate and 3 monitoring points for aerosol monitors. Measuring instrument are placed in the professional stations of the selected parts of Slovakia. They are regularly verified and calibrated in the Slovak Institute for Metrology. Radiation monitoring in the SHMI is one part of the Environmental monitoring of Slovakia. All activities and operation of this system are financed from governmental budget of the Environmental monitoring. All information about this system are available on the web page http://enviroportal.sk/ in the part 'Informacny system monitoringu'. (authors)

  5. The World Radiation Monitoring Center of the Baseline Surface Radiation Network: Status 2017

    Science.gov (United States)

    Driemel, Amelie; König-Langlo, Gert; Sieger, Rainer; Long, Charles N.

    2017-04-01

    The World Radiation Monitoring Center (WRMC) is the central archive of the Baseline Surface Radiation Network (BSRN). The BSRN was initiated by the World Climate Research Programme (WCRP) Working Group on Radiative Fluxes and began operations in 1992. One of its aims is to provide short and long-wave surface radiation fluxes of the best possible quality to support the research projects of the WCRP and other scientific projects. The high quality, uniform and consistent measurements of the BSRN network can be used to monitor the short- and long-wave radiative components and their changes with the best methods currently available, to validate and evaluate satellite-based estimates of the surface radiative fluxes, and to verify the results of global climate models. In 1992 the BSRN/WRMC started at ETH Zurich, Switzerland with 9 stations. Since 2007 the archive is hosted by the Alfred-Wegener-Institut (AWI) in Bremerhaven, Germany (http://www.bsrn.awi.de/) and comprises a network of currently 59 stations in contrasting climatic zones, covering a latitude range from 80°N to 90°S. Of the 59 stations, 23 offer the complete radiation budget (down- and upwelling short- and long-wave data). In addition to the ftp-service access instituted at ETH Zurich, the archive at AWI offers data access via PANGAEA - Data Publisher for Earth & Environmental Science (https://www.pangaea.de). PANGAEA guarantees the long-term availability of its content through a commitment of the operating institutions. Within PANGAEA, the metadata of the stations are freely available. To access the data itself an account is required. If the scientist accepts to follow the data release guidelines of the archive (http://bsrn.awi.de/data/conditions-of-data-release/) he or she can get an account from amelie.driemel@awi.de. Currently, more than 9,400 station months (>780 years) are available for interested scientists (see also https://dataportals.pangaea.de/bsrn/?q=LR0100 for an overview on available data

  6. Radiation monitoring handbook for visits by nuclear powered warships to Australian ports

    International Nuclear Information System (INIS)

    Woods, D.A.

    1995-09-01

    The purpose of this handbook is to detail the Radiation Monitoring (RMG) roles and procedures, and to provide technical and background information useful to RMG personnel. It has been written on the assumption that all members of the RMG have had appropriate radiation safety (Health Physics) training. Separate standing procedures, for both routine and emergency activities, are required for each port. These are incorporated in Port Safety Plans and specify the routine monitoring requirements for individual berths or anchorages and the procedures to be followed after indication of a reactor accident to a nuclear powered warship. A Visit Operation Order, issued for each Nuclear Powered warships (NPW) visit, presents information specific to that visit. Routine monitoring is performed to confirm normal conditions. The objectives of emergency radiation monitoring are: to provide early detection of a reactor accident of sufficient severity to possibly cause a major release of fission products to the environment; to determine the nature and extent of any fission product release; to provide information to assist in evaluating the accident; to assess the need and extent of required countermeasures; and to determine when the release has terminated and when affected areas have returned to normal

  7. Harmonisation (legal, dosimetric, quality aspects) of individual monitoring, and integration of monitoring for external and internal exposures (EURADOS working group)

    International Nuclear Information System (INIS)

    Lopez, M.A.; Currivan, L.; Falk, R.; Olko, P.; Wernli, C.; Castellani, C.M.; Dijk, J.W.E. van

    2003-01-01

    The EURADOS Working Group II on 'Harmonisation of individual monitoring' consists of experts from almost all EU Member States and Newly Associated States (NAS), involved in tasks related to the assessment of doses for internal and external radiation. The final objective is to achieve harmonisation in individual monitoring for occupational exposures. Sub-group 2 activities are focused on investigating how the results from personal dosemeters for external radiation and workplace monitoring and from monitoring for internal exposure can be combined into a complete and consistent system of individual monitoring. Three questionnaires were prepared, covering Individual monitoring of external radiation (Questionnaire 1), 'Internal exposure' (Questionnaire 2) and 'Natural sources of radiation at workplace' (Questionnaire 3). With the agreement of a 'contact-person' selected in each country, the distribution of the three EURADOS 2002 questionnaires was carried out by e-mail among the dosimetry facilities of 28 European countries. The preliminary results of these actions are presented here. (author)

  8. Monitoring the Radiation Damage of the ATLAS Pixel Detector

    CERN Document Server

    Cooke, M; The ATLAS collaboration

    2012-01-01

    The Pixel Detector is the innermost charged particle tracking component employed by the ATLAS experiment at the CERN Large Hadron Collider (LHC). The instantaneous luminosity delivered by the LHC, now routinely in excess of 5x10^{33} cm^{-2} s^{-1}, results in a rapidly increasing accumulated radiation dose to the detector. Methods based on the sensor depletion properties and leakage current are used to monitor the evolution of the radiation damage, and results from the 2011 run are presented.

  9. Monitoring the radiation damage of the ATLAS pixel detector

    International Nuclear Information System (INIS)

    Cooke, M.

    2013-01-01

    The pixel detector is the innermost charged particle tracking component employed by the ATLAS experiment at the CERN Large Hadron Collider (LHC). The instantaneous luminosity delivered by the LHC, now routinely in excess of 5×10 33 cm −2 s −1 , results in a rapidly increasing accumulated radiation dose to the detector. Methods based on the sensor depletion properties and leakage current are used to monitor the evolution of the radiation damage, and results from the 2011 run are presented

  10. Annual environmental monitoring report of the Lawrence Berkeley Laboratory, 1986

    International Nuclear Information System (INIS)

    Schleimer, G.E.

    1987-04-01

    The Environmental Monitoring Program of the Lawrence Berkeley Laboratory is described. Data for 1986 are presented and general trends are discussed. Topics include radiation monitoring, wastewater discharge monitoring, dose distribution estimates, and ground water monitoring. 9 refs., 8 figs., 20 tabs

  11. Ionizing radiations and health. Exposures, epidemiological surveillance and sociological monitoring measurements

    International Nuclear Information System (INIS)

    Spira, Alfred; Boutou, Odile

    1999-01-01

    This paper draws attention to the epidemiological effect of natural and artificial ionizing radiation exposures on man. It describes ionizing radiation sources from nuclear facilities and medical establishments. The case here is in the region of La Hague in France where 4800 employees are exposed to ionizing radiations. The topic of leukemia research and thyroid studies for children in the region are discussed. The impact of radiations on fertility, life quality is covered. Finally, national propositions to establish a monitoring measurement system is also discussed including the personnel and the general population exposed

  12. Quality assurance in individual monitoring of ionizing radiation

    International Nuclear Information System (INIS)

    Julius, H.W.

    1988-01-01

    In todays world, where competition gets tougher, there is a growing consciousness of Quality Assurance (QA) and Quality Control (QC) being key elements to success. This does not only apply o manufacturing of industrial products, it is equally true for public services. Because of the increasing awareness in our modern societies of the quality of life and hence of optimal health care and general safety, it is also the general public that calls for 'products' of the highest possible quality. Good examples of the latter are the continuously improving safety standards for automobiles, for medical diagnostic imaging and for the working environment. Therefore, QA unquestionably plays a vital role in individual monitoring of ionizing radiation, especially since the media talked so many into some sort of radiation phobia. In the following an attempt is made to roughly outline some aspects that may come into play if QA is applied to routine personnel dosimetry. The author wants to emphasize that the subject, which has hardly been dealt with in the professional literature on radiation dosimetry, is a rather 'soft' one. There may be a large number of different approaches to QA, depending on special local situations and individual - sometimes national - views. It should therefore be considered as a general guide, provided in the form of (check)lists containing items of interest in routine monitoring

  13. Mobile radiation monitoring of Delhi for the prevention of malicious acts during the Common Wealth Games (CWG-2010)

    International Nuclear Information System (INIS)

    Saindane, Shashank S.; Chatterjee, M.K.; Romal, Jis; Pradeepkumar, K.S.; Singh, B.R.

    2012-01-01

    Radioactive sources are widely used in industry, research, agriculture and medical applications. In spite of various measures adopted for ensuring the safety and security of these sources, similar to Mayapuri incident, many cases of lost, misplaced, stolen radioactive sources and inadvertent radiation exposure due to radiological emergencies are reported world over. In the aftermath of the attack on the World Trade Center 2001, malicious acts using radioactive material is considered as a threat for which prevention and preparedness for response are recommended by IAEA. Hence radiation monitoring of all related area prior to and during Major Public Events (MPEs) like Olympics, World cup football etc are implemented by many nations for prevention and preparedness to such radiological threats/emergencies. Department of Atomic Energy (DAE) through their Emergency Response Centres planned and executed detailed radiation monitoring programme for the Delhi Common Wealth Games (CWG 2010) which covered all CWG stadiums. Commonwealth village etc. In addition to DAE emergency response teams of 15 members in readiness, source recovery and shielding facilities, Portable Personnel Decontamination Unit (PPDU), Radiation monitors, Protective gears, Aerial Gamma Spectrometry System (AGSS for Aerial surveys) etc. were maintained at two DAE control rooms. This paper discusses the mobile radiation monitoring carried out on Delhi city roads with the help of various state-of-the-art monitoring systems to detect the presence or movement of any orphan sources. The mobile radiation monitoring was focused on main road networks connecting to stadiums, areas surrounding stadiums, airport and Games village. For this state-of-the-art systems like Portable Mobile Gamma Spectrometry System (PMGSS), Portable Radiation Scanner (PRS), Compact Radiation Monitoring System integrated with GPS, GSM based Radiation Monitoring System (GRaMS), Gammatracers, Selection and placement of different monitoring

  14. 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)

  15. SEL monitoring of the earth's energetic particle radiation environment

    International Nuclear Information System (INIS)

    Sauer, H.H.

    1989-01-01

    The Space Environment Laboratory (SEL) of the National Oceanic and Atmospheric Administration (NOAA) maintains instruments on board the GOES series of geostationary satellites, and aboard the NOAA/TIROS series of low-altitude, polar-orbiting satellites, which provide monitoring of the energetic particle radiation environment as well as monitoring the geostationary magnetic field and the solar x-ray flux. The data are used by the SEL Space Environment Services Center (SESC) to help provide real-time monitoring and forecasting of the state of the near earth environment and its disturbances, and to maintain a source of reliable information to research and operational activities of a variety of users

  16. Development of a VxWorks-based distributed power quality monitoring system

    Energy Technology Data Exchange (ETDEWEB)

    Shin, M.J.; Kim, S.J.; Son, Y.I.; Kang, S.H. [Myongji Univ., Yongin (Korea, Republic of). Next-generation Power Technology Center

    2007-07-01

    Electric utilities are becoming increasingly concerned about power quality because end user equipment is more sensitive to disturbances within the power supply system and also within the consumer facilities. In order to improve the quality of electricity, the sources and causes of disturbances must be known. However, voltage sag and swell, wave-faults and momentary interruptions are difficult to detect and avoid unless power quality monitoring devices are installed permanently. The impact that alternative energy sources have on power quality was also discussed. When distributed generation is connected to the power grid, it can generate and supply more reliable power to the grid. For a reliable interconnection of distributed power to the grid, monitoring systems should display the status of distributed power and record power events. Lack of source stability in distributed generation such as solar-cells or wind-power creates events that should be measured and stored immediately. This paper presented a newly developed real-time power quality monitoring system for distributed power systems. The system is based on a real-time operating system (OS) and can therefore handle many events that happen simultaneously. The proposed system contains a digital signal processor (MPC7410, Motorola) and an A/D board (VMIVME3122, GE). VxWorks was used to implement the monitoring algorithm. This paper outlined the structure and the functions of the developed Distributed Power Quality Monitoring System. Some experiments were conducted to test the performance of the proposed system. According to test results, the system is compatible with standards of the Institute of Electrical and Electronics Engineers (IEEE) for power quality monitoring. 15 refs., 1 tab., 18 figs.

  17. The Telemetric Early Warning Environmental Radiation Monitoring System of Cyprus

    Energy Technology Data Exchange (ETDEWEB)

    Christofides, S [Medical Physics Department, Nicosia General Hospital, Nicosia (Cyprus)

    1998-12-31

    This paper presents the hardware design, the development of the software and the use of the Telemetric Early Warning Environmental Radiation Monitoring System (TEWERMS) of Cyprus. (author). 3 refs, 6 figs.

  18. 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

  19. 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.

  20. 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

  1. Optical fiber-applied radiation detection system

    International Nuclear Information System (INIS)

    Nishiura, Ryuichi; Uranaka, Yasuo; Izumi, Nobuyuki

    2001-01-01

    A technique to measure radiation by using plastic scintillation fibers doped radiation fluorescent (scintillator) to plastic optical fiber for a radiation sensor, was developed. The technique contains some superiority such as high flexibility due to using fibers, relatively easy large area due to detecting portion of whole of fibers, and no electromagnetic noise effect due to optical radiation detection and signal transmission. Measurable to wide range of and continuous radiation distribution along optical fiber cable at a testing portion using scintillation fiber and flight time method, the optical fiber-applied radiation sensing system can effectively monitor space radiation dose or apparatus operation condition monitoring. And, a portable type scintillation optical fiber body surface pollution monitor can measure pollution concentration of radioactive materials attached onto body surface by arranging scintillation fiber processed to a plate with small size and flexibility around a man to be tested. Here were described on outline and fundamental properties of various application products using these plastic scintillation fiber. (G.K.)

  2. Off-site environmental monitoring report: radiation monitoring around United States nuclear test areas, calendar year 1984

    International Nuclear Information System (INIS)

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

    1985-04-01

    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 1984. 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 radionuclides releases yield an estimated dose of 1 x 10 -3 person-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 0.6 mrem per year. Plutonium in air was still detectable along with krypton-85, which continued its gradual increase, as has been reported previously. Cesium and strontium in air were near their 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. 32 refs., 36 figs., 27 tabs

  3. ATLAS Distributed Computing Monitoring tools during the LHC Run I

    CERN Document Server

    Schovancova, J; The ATLAS collaboration; Di Girolamo, A; Jezequel, S; Ueda, I; Wenaus, T

    2013-01-01

    This contribution summarizes evolution of the ATLAS Distributed Computing (ADC) Monitoring project during the LHC Run I. The ADC Monitoring targets at the three groups of customers: ADC Operations team to early identify malfunctions and escalate issues to an activity or a service expert, ATLAS national contacts and sites for the real-time monitoring and long-term measurement of the performance of the provided computing resources, and the ATLAS Management for long-term trends and accounting information about the ATLAS Distributed Computing resources.\\\\ During the LHC Run I a significant development effort has been invested in standardization of the monitoring and accounting applications in order to provide extensive monitoring and accounting suite. ADC Monitoring applications separate the data layer and the visualization layer. The data layer exposes data in a predefined format. The visualization layer is designed bearing in mind visual identity of the provided graphical elements, and re-usability of the visua...

  4. ATLAS Distributed Computing Monitoring tools during the LHC Run I

    CERN Document Server

    Schovancova, J; The ATLAS collaboration; Di Girolamo, A; Jezequel, S; Ueda, I; Wenaus, T

    2014-01-01

    This contribution summarizes evolution of the ATLAS Distributed Computing (ADC) Monitoring project during the LHC Run I. The ADC Monitoring targets at the three groups of customers: ADC Operations team to early identify malfunctions and escalate issues to an activity or a service expert, ATLAS national contacts and sites for the real-time monitoring and long-term measurement of the performance of the provided computing resources, and the ATLAS Management for long-term trends and accounting information about the ATLAS Distributed Computing resources.\\\\ During the LHC Run I a significant development effort has been invested in standardization of the monitoring and accounting applications in order to provide extensive monitoring and accounting suite. ADC Monitoring applications separate the data layer and the visualization layer. The data layer exposes data in a predefined format. The visualization layer is designed bearing in mind visual identity of the provided graphical elements, and re-usability of the visua...

  5. Personal monitoring services available at Institute for Radiation Protection of ENEA

    International Nuclear Information System (INIS)

    Fantuzzi, E.; Bonarelli, T.

    1999-01-01

    Personnel monitoring provides the means to measure and record the radiation doses received by individual workers. The ionising radiation decree (230/95) set out the circumstances when the assessment and recording of person's exposure is legally required. Many employers issue dosemeters to staff even though there is no legal requirement to do so. This may be part of a quality assurance programme or as a reassurance measure. Dosemeter readings will serve to ensure compliance with legal dose limits and assure the employer that radiation exposure is as low as reasonably achievable. The ENEA (National Agency for New Technology, Energy and the Environment) IRP (Institute for Radiation Protection) individual monitoring service has been running for over 30 years. It offers personnel dosemeters which are based on its expertise and backed up by continual research and development. The report provides details of the dosemeters in use at IRP enable to decide which ones most suit the needs and shows IMS's organisation, customer and communications, dose reports form and administrative items. A short mention of future development will also be given [it

  6. Modernisation of Radiation Monitoring Room as a Part of Slovenian Emergency Response Centre

    International Nuclear Information System (INIS)

    Sarvari, A.; Mitic, D.

    2003-01-01

    In the year 2002 the Slovenian Nuclear Safety Administration (SNSA) moved to the new premises therefore it had to rearrange some of its rooms for the emergency situation. SNSA does not operate with a dedicated Emergency Response Centre (ERC), instead of it the SNSA has to rearrange the existing rooms in case of an emergency. Modernisation of the equipment, with the help of government of the United Kingdom of Great Britain and Northern Ireland, for the emergency situation was carried out, especially in the monitoring room. The radiation monitoring system, which is placed in the monitoring room, continuously collects, processes and archives the incoming data of exposure to radiation and meteorological parameters on the Slovenian territory (A model national emergency response plan for radiological accidents, IAEA, Vienna, 1993. IAEA-TECDOC-718). In the emergency situation the monitoring room transforms into the room for the Dose Assessment Group (DAG), which is part of ERC (IAEA emergency response network, IAEA, Vienna, 2000, EPR-ERNET (2000)). The modernisation of monitoring room and within the DAG room with new equipment and its purpose is described in this article. Modernisation of the monitoring room and the room for DAG showed to be inevitably needed. Modernisation of the monitoring room has brought the SNSA a sophisticated and reliable system of controlling the external exposure to radiation on the Slovenian territory. The equipment, especially the equipment for the use in the emergency situation, brought novelties for the Dose Assessment Group. The group has now better and easier control of radiation situation in case of an accident. In overall this modernisation has put the Slovenian Nuclear Safety Administration a step forward in having a dedicated Emergency Response Centre, since it does not need to rearrange the room for the Dose Assessment Group. (author)

  7. 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

  8. A radiation monitoring system model for the Laguna Verde nuclear power training simulator

    International Nuclear Information System (INIS)

    Ocampo, M.H.; DeAlbornoz, B.A.

    1988-01-01

    A model for the Radiation Monitoring System of the Laguna Verde Boiling Water Reactor training simulator is presented. This model comprises enough definitions to assure interactions with the processes related, directly or indirectly, with the transport of radioisotopes. It is capable of following a dynamic behavior of the plant so an operator could be trained to become aware of nuclear radiation hazards. The model is composed of three parts: the electronics for the Process and Area Radiation Monitoring System; a lumped parameter transport model for the most representative radioisotopes; and the interactions with the modeled processes as well as with process not being simulated. The first part represents the radiation monitor controls in the vertical board panels of the nuclear station. The second part allows the carrying of nuclear isotopes between processes. The third part defines the way that the process interacts with the electronics at the point of release to environment or the point of detection. Each part of the model has been tested individually, and the transport model has been incorporated as a part of each process required to simulate nuclear radiation. The model parameters has been calculated using typical BWR nuclear radiation data, and Laguna Verde heat balance data at 100% design power. However, tunning will be necessary once the Simulator is integrated and tested. The tunning allows each detecting channel to behave as expected

  9. Applications in bridge structure health monitoring using distributed fiber sensing

    Science.gov (United States)

    Feng, Yafei; Zheng, Huan; Ge, Huiliang

    2017-10-01

    In this paper, Brillouin Optical Time Domain Analysis (BOTDA) is proposed to solve the problem that the traditional point sensor is difficult to realize the comprehensive safety monitoring of bridges and so on. This technology not only breaks through the bottleneck of traditional monitoring point sensor, realize the distributed measurement of temperature and strain on a transmission path; can also be used for bridge and other structures of the damage identification, fracture positioning, settlement monitoring. The effectiveness and frontier of the technology are proved by comparing the test of the indoor model beam and the external field bridge, and the significance of the distributed optical fiber sensing technology to the monitoring of the important structure of the bridge is fully explained.

  10. Installation of a variable-angle spectrometer system for monitoring diffuse and global solar radiation

    Science.gov (United States)

    Ormachea, O.; Abrahamse, A.; Tolavi, N.; Romero, F.; Urquidi, O.; Pearce, J. M.; Andrews, R.

    2013-11-01

    We report on the design and installation of a spectrometer system for monitoring solar radiation in Cochabamba, Bolivia. Both the light intensity and the spectral distribution affect the power produced by a photovoltaic device. Local variations in the solar spectrum (especially compared to the AM1.5 standard) may have important implications for device optimization and energy yield estimation. The spectrometer system, based on an Ocean Optics USB4000 (300-900nm) spectrometer, was designed to increase functionality. Typically systems only record the global horizontal radiation. Our system moves a fiber-optic cable 0-90 degrees and takes measurements in 9 degree increments. Additionally, a shadow band allows measurement of the diffuse component of the radiation at each position. The electronic controls utilize an Arduino UNO microcontroller to synchronizes the movement of two PAP bipolar (stepper) motors with the activation of the spectrometer via an external trigger. The spectrometer was factory calibrated for wavelength and calibrated for absolute irradiance using a Sellarnet SL1-Cal light source. We present preliminary results from data taken March-June, 2013, and comment on implications for PV devices in Cochabamba.

  11. 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.

  12. Cryogenic semiconductor high-intensity radiation monitors

    International Nuclear Information System (INIS)

    Palmieri, V.G.; Bell, W.H.; Borer, K.; Casagrande, L.; Da Via, C.; Devine, S.R.H.; Dezillie, B.; Esposito, A.; Granata, V.; Hauler, F.; Jungermann, L.; Li, Z.; Lourenco, C.; Niinikoski, T.O.; Shea, V. O'; Ruggiero, G.; Sonderegger, P.

    2003-01-01

    This paper describes a novel technique to monitor high-intensity particle beams by means of a semiconductor detector. It consists of cooling a semiconductor detector down to cryogenic temperature to suppress the thermally generated leakage current and to precisely measure the integrated ionization signal. It will be shown that such a device provides very good linearity and a dynamic range wider than is possible with existing techniques. Moreover, thanks to the Lazarus effect, extreme radiation hardness can be achieved providing in turn absolute intensity measurements against precise calibration of the device at low beam flux

  13. Quantitative radiation monitors for containment and surveillance

    International Nuclear Information System (INIS)

    Fehlau, P.E.

    1983-01-01

    Quantitative radiation monitors make it possible to differentiate between shielded and unshielded nuclear materials. The hardness of the gamma-ray spectrum is the attribute that characterizes bare or shielded material. Separate high- and low-energy gamma-ray regions are obtained from a single-channel analyzer through its window and discriminator outputs. The monitor counts both outputs and computes a ratio of the high- and low-energy region counts whenever an alarm occurs. The ratio clearly differentiates between shielded and unshielded nuclear material so that the net alarm count may be identified with a small quantity of unshielded material or a large quantity of shielded material. Knowledge of the diverted quantity helps determine whether an inventory should be called to identify the loss

  14. Basic study on radiation distribution sensing with normal optical fiber

    International Nuclear Information System (INIS)

    Naka, R.; Kawarabayashi, J.; Uritani, A.; Iguchi, T.; Kaneko, J.; Takeuchi, H.; Kakuta, T.

    2000-01-01

    Recently, some methods of radiation distribution sensing with optical fibers have been proposed. These methods employ scintillating fibers or scintillators with wavelength-shifting fibers. The positions of radiation interactions are detected by applying a time-of-flight (TOF) technique to the scintillation photon propagation. In the former method, the attenuation length for the scintillation photons in the scintillating fiber is relatively short, so that the operating length of the sensor is limited to several meters. In the latter method, a radiation distribution cannot continuously be obtained but discretely. To improve these shortcomings, a normal optical fiber made of polymethyl methacrylate (PMMA) is used in this study. Although the scintillation efficiency of PMMA is very low, several photons are emitted through interaction with a radiation. The fiber is transparent for the emitted photons to have a relatively long operating length. A radiation distribution can continuously be obtained. This paper describes a principle of the position sensing method based on the time of flight technique and preliminary results obtained for 90 Sr- 90 Y beta rays, 137 Cs gamma rays, and 14 MeV neutrons. The spatial resolutions for the above three kinds of radiations are 0.30 m, 0.37 m, 0.13 m, and the detection efficiencies are 1.1 x 10 -3 , 1.6 x 10 -7 , 5.4 x 10 -6 , respectively, with 10 m operation length. The results of a spectroscopic study on the optical property of the fiber are also described. (author)

  15. Experience in treatment of the radiation syndrome in accident victims exposed with non-uniform distribution of the dose within a body

    International Nuclear Information System (INIS)

    Guskova, A.; Barabanova, A

    1996-01-01

    Experience in diagnosis and treatment of radiation accident victims undergone to radiation expose with non-uniform distribution of the dose within a body is presented and the most significant features of medical management of such patients are discussed. The term 'compound radiation injure' is proposed to use for this form of radiation disease. Treatment of compound radiation injure demands a participation of very qualified specialists. The first medical aid and management should include careful body surface monitoring. Beside daily haematological observation and cytogenetic study with corresponding treatment, careful observation and registration of skin reaction are necessary. Some features of treatment are the following: more early administration of anti infection means, including isolation in sterile room, timely surgical intervention, prophylacsis and treatment of endorganic intoxication improving of microcirculation, long time follow up study with pathogenic therapy. (author)

  16. 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)

  17. 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)

  18. Standard guide for application of radiation monitors to the control and physical security of special nuclear material

    CERN Document Server

    American Society for Testing and Materials. Philadelphia

    1999-01-01

    1.1 This guide briefly describes the state-of-the-art of radiation monitors for detecting special nuclear material (SNM) (see 3.1.11) in order to establish the context in which to write performance standards for the monitors. This guide extracts information from technical documentation to provide information for selecting, calibrating, testing, and operating such radiation monitors when they are used for the control and protection of SNM. This guide offers an unobtrusive means of searching pedestrians, packages, and motor vehicles for concealed SNM as one part of a nuclear material control or security plan for nuclear materials. The radiation monitors can provide an efficient, sensitive, and reliable means of detecting the theft of small quantities of SNM while maintaining a low likelihood of nuisance alarms. 1.2 Dependable operation of SNM radiation monitors rests on selecting appropriate monitors for the task, operating them in a hospitable environment, and conducting an effective program to test, calibrat...

  19. 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

  20. Substantiation of the radiation monitoring scope in the region of nuclear power plant location

    Energy Technology Data Exchange (ETDEWEB)

    Zykova, A S; Zhakov, Yu A; Yambrovskii, Ya M

    1977-12-01

    To provide radiation safety of the population in the region of nuclear power plant location, it is necessary to define the character and quantity of radiation monitoring. On the basis of radiation monitoring of effluents from operating nuclear power plants it is found that the effluents can be registered at a distance of 5-7 km from the plant. The quantity of sample analysis of the main enviromental objectives must provide an exact definition of the content of radioactive substances produced by radioactive fallouts and effluents from nuclear power plants.