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

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.

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

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

The development of web monitoring digital area monitor

International Nuclear Information System (INIS)

Jung, Hoon-Jin; Lee, Jun-Hee; Namkoong, Phil; Lee, Dong-Hoon; Lee, Su-Hong; Kim, We-Su

2005-01-01

As CCTV and radiation area monitor have been used separately to date, there have existed inconveniences in managing the view images and radiation dose rates from them. Thus we became to develop the web monitoring digital area monitor which incorporated the existing two factors, CCTV and radiation area monitor, into one. As incorporated with digitalisation, this device will usually become linked with PC, so that the view image and radiation dose rate can be concurrently identified in convenience. These measured figures automatically become data-based on PC by SW program, and become displayed in various format. Moreover, they can be monitored in remote and real time basis in the internet environment. Its local unit uses the cost-effective GM tube and CMOS image sensor, and has the small LCD which directly indicates the measured dose rate. The image sensor is designed to be operated with pan and tilt motion, thus can eliminate the dead view zone. It is thought that the developed device at this time could make the radiation safety management of each work field be done with low cost-high efficiency manner, making role of the CCTV inspection system

The development of web monitoring digital area monitor

Energy Technology Data Exchange (ETDEWEB)

Jung, Hoon-Jin; Lee, Jun-Hee; Namkoong, Phil; Lee, Dong-Hoon; Lee, Su-Hong; Kim, We-Su [Iljin Radiation Engineering Co., Seoul (Korea, Republic of)

2005-11-15

As CCTV and radiation area monitor have been used separately to date, there have existed inconveniences in managing the view images and radiation dose rates from them. Thus we became to develop the web monitoring digital area monitor which incorporated the existing two factors, CCTV and radiation area monitor, into one. As incorporated with digitalisation, this device will usually become linked with PC, so that the view image and radiation dose rate can be concurrently identified in convenience. These measured figures automatically become data-based on PC by SW program, and become displayed in various format. Moreover, they can be monitored in remote and real time basis in the internet environment. Its local unit uses the cost-effective GM tube and CMOS image sensor, and has the small LCD which directly indicates the measured dose rate. The image sensor is designed to be operated with pan and tilt motion, thus can eliminate the dead view zone. It is thought that the developed device at this time could make the radiation safety management of each work field be done with low cost-high efficiency manner, making role of the CCTV inspection system.

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

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

X-ray area monitor

International Nuclear Information System (INIS)

Nintrakit, N.

1983-01-01

The X-ray area monitor is a nuclear electronic device that is essential in radiation protection in high radiation laboratories, e.g. in medical diagnosis using X-rays and in industrial X-radiography. Accidentally the level of X-radiator may arise above the safe permissible level and in such a case the alarm system of the area monitor will work and disconnect the ac power supply form the X-ray unit. Principally the device is a radiation counter using G.M.tube as radiation detector with high voltage supply variable form 200 to 2,000 volts. The maximum count rate of the scaler is 1.5 MHz and the total count is displayed on 4 digit LED's. A time base is used to control the counting time, the frequency multiplier, radiation safety limit, comparator and the radiation hazard warning signal. The reliability of the instrument is further enhanced through the addition of the random correction circuit, and it is applicable both in X- and γ -radiation

Offsite environmental monitoring report. Radiation monitoring around United States nuclear test areas, calendar year 1982

International Nuclear Information System (INIS)

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

1983-07-01

A principal activity of the Offsite Radiological Safety Program is routine environmental monitoring for radioactive materials in various media and for radiation in areas which may be affected by nuclear tests. It is conducted to document compliance with standards, to identify trends, and to provide information to the public. This report summarizes these activities for CY 1982

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

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)

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

Area monitoring intelligent system - SIMA

International Nuclear Information System (INIS)

Bhoem, P.; Hisas, F.; Gelardi, G.

1990-01-01

The area monitoring intelligent system (SIMA) is an equipment to be used in radioprotection. SIMA has the function of monitoring the radiation levels of determined areas of the installations where radioactive materials are handled. (Author) [es

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

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

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)

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

Radiation-ecological monitoring in the area of «Ruppur» NPP in the People's Republic of Bangladesh

International Nuclear Information System (INIS)

Panov, A.V.; Sanzharova, N.I.; Tsygvintsev, P.N.; Isamov, N.N.; Kurbakov, D.N.

2016-01-01

The program of radiation-ecological monitoring of the region of «Ruppur» NPP is developed, survey points are chosen and examined; the monitoring objects, list of observing parameters, regulation of observation are determined as well as the techniques of observation and regulatory and engineering provisions. On the base of radiation-ecological monitoring of atmospheric air, aquatic and terrestrial ecosystems carried out in 30-km area of the NPP in 2014-2015 it is possible to make a conclusion that ecological situation in the region is good in whole. Formed monitoring network of atmosphere, aquatic and terrestrial ecosystems will allow to record the change of situation in 30-km NPP area and to reveal the effect of the NPP operation on ecology in the region [ru

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

The radiation monitoring system for the LHC experiments and experimental areas

CERN Document Server

Ilgner, C

2004-01-01

With the high energies stored in the beams of the LHC, special attention needs to be paid to accident scenarios involving beam losses which may have an impact on the installed experiments. Among others, an unsynchronized beam abort and a D1 magnet failure are considered serious cases. According to simulations, the CMS inner tracker in such accident scenarios can be damaged by instantaneous rates which are many orders of magnitude above normal conditions. Investigations of synthetic diamond as a beam condition monitor sensor, capable of generating a fast beam dump signal, will be presented. Furthermore, a system to monitor the radiation fields in the experimental areas is being developed. It must function in the radiation fields inside and around the experiments, over a large dynamic range. Several new active and passive sensors, such as RadFET, OSL (Optically Stimulated Luminescence) sensors, p-i-n diodes, Polymer-Alanine Dosimeters and TLDs (Thermoluminescent Dosimeters) are under investigation. Recent resul...

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.

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.

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.

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.

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

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

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)

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

Online fault diagnostics and testing of area gamma radiation monitor using wireless network

Science.gov (United States)

Reddy, Padi Srinivas; Kumar, R. Amudhu Ramesh; Mathews, M. Geo; Amarendra, G.

2017-07-01

Periodical surveillance, checking, testing, and calibration of the installed Area Gamma Radiation Monitors (AGRM) in the nuclear plants are mandatory. The functionality of AGRM counting electronics and Geiger-Muller (GM) tube is to be monitored periodically. The present paper describes the development of online electronic calibration and testing of the GM tube from the control room. Two electronic circuits were developed, one for AGRM electronic test and another for AGRM detector test. A dedicated radiation data acquisition system was developed using an open platform communication server and data acquisition software. The Modbus RTU protocol on ZigBee based wireless communication was used for online monitoring and testing. The AGRM electronic test helps to carry out the three-point electronic calibration and verification of accuracy. The AGRM detector test is used to verify the GM threshold voltage and the plateau slope of the GM tube in-situ. The real-time trend graphs generated during these tests clearly identified the state of health of AGRM electronics and GM tube on go/no-go basis. This method reduces the radiation exposures received by the maintenance crew and facilitates quick testing with minimum downtime of the instrument.

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

International Nuclear Information System (INIS)

Mueller-Lyda, I.; Meyer, H.

1988-07-01

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

Automated System of Area Radiation Measurement (ASARM)

International Nuclear Information System (INIS)

Hernandez G, J.

2013-10-01

The realized activities in nuclear facilities involve the determination of the presence of ionizing radiation fields in the workspaces. The instruments designed to detect and to measure these radiation fields provide useful information (specific type of radiation, intensity, etc.) to take the appropriate radiological protection measures, with the purpose of reducing to the minimum the workers exposition and the people in general. The radiological protection program of Reactor TRIGA Mark III contains the instructions and procedures to implement a periodic radiological monitoring, surveillance, rising of contamination levels, type and number of the instruments required for the radiological monitoring of areas and personal. The ana logical monitoring system model Rms II used to detect and measuring exposition speed and neutron radiation fields in several areas of the installation, provides the information in a logarithmic scale measurer of 4 or 5 decades located in a shelf where the previously mentioned measurement channels are centralized. Also inside the reactor monitoring system are two monitors of radioactive material concentration in the air: The particles continuous monitor and the gaseous effluents monitor which present the referred information of the diverse detectors through ana logical readers. These monitors when operating with an ana logical indication does not present the possibility to generate historical files electronically of each monitor previously mentioned neither to generate visual and audible indications of the alarms. This work presents the Automated System of Area Radiation Measurement which potentiated the functionality of the area monitors for gamma and neutron radiation, as well as of the particles continuous monitor and the gaseous effluents of reactor TRIGA Mark III, when being developed a computer system that captures in real time the information of all the monitors, generating this way an electronic binnacle, a visual and audible alarm

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

Preliminary Study of Position-Sensitive Large-Area Radiation Portal Monitor

Energy Technology Data Exchange (ETDEWEB)

Lim, Chang Hwy; Kim, Hyunok; Moon, Myung Kook [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Kim, Jongyul [Korea Advanced Institute of Science and Technology, Daejeon (Korea, Republic of); Park, Jong Won; Lim, Yong Kon [Korea Institute of Ocean Science and Technology, Daejeon (Korea, Republic of)

2013-10-15

An RPM, which is a passive inspection method, is a system for monitoring the movement of radioactive materials at an airport, seaport, border, etc. To detect a γ-ray, an RPM using the plastic scintillator is generally used. The method of γ-ray detection using an RPM with a plastic scintillator is to measure lights generated by an incident γ-ray in the scintillator. Generally, a large-area RPM uses one or two photomultiplier tubes (PMT) for light collection. However, in this study, we developed a 4-ch RPM that can measure the radiation signal using 4 PMTs. The reason for using 4 PMTs is to calculate the position of the radiation source. In addition, we developed an electric device for acquisition of a 4-ch output signal at the same time. To estimate the performance of the developed RPM, we performed an RPM test using a {sup 60}Co γ-ray check source. In this study, we performed the development of a 4-ch RPM. The major function of the typical RPM is to measure the radiation. However, we developed a position-sensitive 4-ch RPM, which can be used to measure the location of the radiation source, as well as the radiation measurement, at the same time. In the future, we plan to develop an algorithm for a position detection of the radiation. In addition, an algorithm will be applied to an RPM.

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

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.

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

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)

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)

Off-site environmental monitoring report: Radiation monitoring around United States Nuclear Test areas, Calendar year 1986

International Nuclear Information System (INIS)

Patzer, R.G.; Fontana, C.A.; Grossman, R.F.; Black, S.C.; Dye, R.E.; Smith, D.D.; Thome', D.J.; Mullen, A.A.

1987-05-01

The principal activity at the NTS is testing of nuclear devices, though other related projects are also conducted. The principal activities of the Off-Site Radiological Safety Program are routine environmental monitoring for radioactive materials in various media and for radiation in areas which may be affected by nuclear tests; and protective actions in support of the nuclear testing program. These are conducted to document compliance with standards, to identify trends, and to provide information to the public. 28 refs., 37 figs., 30 tabs

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

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.)

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

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

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)

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

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

Automated System of Area Radiation Measurement (ASARM); Sistema Automatizado de Medicion de Radiacion de Area (SAMRA)

Energy Technology Data Exchange (ETDEWEB)

Hernandez G, J., E-mail: jaime.hernandez@inin.gob.mx [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

2013-10-15

The realized activities in nuclear facilities involve the determination of the presence of ionizing radiation fields in the workspaces. The instruments designed to detect and to measure these radiation fields provide useful information (specific type of radiation, intensity, etc.) to take the appropriate radiological protection measures, with the purpose of reducing to the minimum the workers exposition and the people in general. The radiological protection program of Reactor TRIGA Mark III contains the instructions and procedures to implement a periodic radiological monitoring, surveillance, rising of contamination levels, type and number of the instruments required for the radiological monitoring of areas and personal. The ana logical monitoring system model Rms II used to detect and measuring exposition speed and neutron radiation fields in several areas of the installation, provides the information in a logarithmic scale measurer of 4 or 5 decades located in a shelf where the previously mentioned measurement channels are centralized. Also inside the reactor monitoring system are two monitors of radioactive material concentration in the air: The particles continuous monitor and the gaseous effluents monitor which present the referred information of the diverse detectors through ana logical readers. These monitors when operating with an ana logical indication does not present the possibility to generate historical files electronically of each monitor previously mentioned neither to generate visual and audible indications of the alarms. This work presents the Automated System of Area Radiation Measurement which potentiated the functionality of the area monitors for gamma and neutron radiation, as well as of the particles continuous monitor and the gaseous effluents of reactor TRIGA Mark III, when being developed a computer system that captures in real time the information of all the monitors, generating this way an electronic binnacle, a visual and audible alarm

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

International Nuclear Information System (INIS)

Meyer, H.; Mueller-Lyda, I.

1995-01-01

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

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

International Nuclear Information System (INIS)

Meyer, H.; Mueller-Lyda, I.

1994-01-01

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

Nevada Test 1999 Waste Management Monitoring Report, Area 3 and Area 5 radioactive waste management sites

International Nuclear Information System (INIS)

Yvonne Townsend

2000-01-01

Environmental monitoring data were collected at and around the Area 3 and Area 5 Radioactive Waste Management Sites (RWMSs) at the Nevada Test Site (NTS). These monitoring data include radiation exposure, air, groundwater, meteorology, vadose zone, and biota data. Although some of these media (radiation exposure, air, and groundwater) are reported in detail in other Bechtel Nevada reports (Annual Site Environmental Report [ASER], the National Emissions Standard for Hazardous Air Pollutants [NESHAP] report, and the Annual Groundwater Monitoring Report), they are also summarized in this report to provide an overall evaluation of RWMS performance and environmental compliance. Direct radiation monitoring data indicate that exposure at and around the RWMSs is not above background levels. Air monitoring data indicate that tritium concentrations are slightly above background levels, whereas radon concentrations are not above background levels. Groundwater monitoring data indicate that the groundwater in the alluvial aquifer beneath the Area 5 RWMS has not been affected by the facility. Meteorology data indicate that 1999 was a dry year: rainfall totaled 3.9 inches at the Area 3 RWMS (61 percent of average) and 3.8 inches at the Area 5 RWMS (75 percent of average). Vadose zone monitoring data indicate that 1999 rainfall infiltrated less than one foot before being returned to the atmosphere by evaporation. Soil-gas tritium data indicate very slow migration, and tritium concentrations in biota were insignificant. All 1999 monitoring data indicate that the Area 3 and Area 5 RWMSs are performing as expected at isolating buried waste

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)

Radiation protection and ambient radioactivity monitoring in the area of the Asse mine. Annual report 2000

International Nuclear Information System (INIS)

Meyer, H.; Stippler, R.

2001-01-01

The measuring activities for radiological monitoring in the mine and the surrounding area have been continued as usual, in compliance with the relevant programmes. As in previous years, low amounts of the nuclides H 3, C 14, Pb 210 and Rn 222, including Rn 220, and the short-life radon daughter products have been detected. In some cases, the nuclide-specific concentrations in ambient air derived from the annual average were below the mean natural concentrations of those nuclides. The relevant exposure data at the most affected measuring points remained far below the maximum permissible doses given in the Radiation Protection Ordinance. As compared to the natural and anthropogenic ambient radiation levels, the radiation exposure of the population in the area and the personnel on site, emanating from radioactive waste storage and performance of research projects in the Asse mine, represent an unsignificant contribution. (orig./CB) [de

Radiation protection and ambient radioactivity monitoring in the area of the Asse mine. Annual report 1999

International Nuclear Information System (INIS)

Meyer, H.; Stippler, R.

2000-01-01

The measuring activities for radiological monitoring in the mine and the surrounding area have been continued as usual, in compliance with the relevant programmes. As in previous years, low amounts of the nuclides H 3, C 14, Pb 210 and Rn 222, including Rn 220, and the short-life radon daughter products have been detected. In some cases, the nuclide-specific concentrations in ambient air derived from the annual average were below the mean natural concentrations of those nuclides. The relevant exposure data at the most affected measuring points remained far below the maximum permissible doses given in the Radiation Protection Ordinance. As compared to the natural and anthropogenic ambient radiation levels, the radiation exposure of the population in the area and the personnel on site, emanating from radioactive waste storage and performance of research projects in the Asse mine, represent an insignificant contribution. (orig./CB) [de

Radiation protection and ambient radioactivity monitoring in the area of the Asse mine. Annual report 2001

International Nuclear Information System (INIS)

Meyer, H.; Stippler, R.

2002-01-01

The measuring activities for radiological monitoring in the mine and the surrounding area have been continued as usual, in compliance with the relevant programmes. As in previous years, low amounts of the nuclides H 3, C 14, Pb 210 and Rn 222, including Rn 220, and the short-life radon daughter products have been detected. In some cases, the nuclide-specific concentrations in ambient air derived from the annual average were below the mean natural concentrations of those nuclides. The relevant exposure data at the most affected measuring points remained far below the maximum permissible doses given in the Radiation Protection Ordinance. As compared to the natural and anthropogenic ambient radiation levels, the radiation exposure of the population in the area and the personnel on site, emanating from radioactive waste storage and performance of research projects in the Asse mine, represent an unsignificant contribution. (orig./CB) [de

Nevada Test Site 2001 Waste Management Monitoring Report Area 3 and Area 5 Radioactive Waste Management Sites

International Nuclear Information System (INIS)

Y. E. Townsend

2002-06-01

Environmental monitoring data, subsidence monitoring data, and meteorology monitoring data were collected at and around the Area 3 and Area 5 Radioactive Waste Management Sites (RWMSs) at the Nevada Test Site (NTS) (refer to Figure 1). These monitoring data include radiation exposure, air, groundwater, meteorology, vadose zone, subsidence, and biota data. Although some of these media (radiation exposure, air, and groundwater) are reported in detail in other Bechtel Nevada (BN) reports (Annual Site Environmental Report [ASER], the National Emissions Standard for Hazardous Air Pollutants [NESHAP] report, and the Annual Groundwater Monitoring Report), they are also summarized in this report to provide an overall evaluation of RWMS performance and environmental compliance. Direct radiation monitoring data indicate that exposure at and around the RWMSs is not above background levels. Air monitoring data indicate that tritium concentrations are slightly above background levels. Groundwater monitoring data indicate that the groundwater in the uppermost aquifer beneath the Area 5 RWMS has not been affected by the facility. Meteorology data indicate that 2001 was an average rainfall year: rainfall totaled 150 mm (5.9 in) at the Area 3 RWMS and 120 mm (4.7 in) at the Area 5 RWMS. Vadose zone monitoring data indicate that 2001 rainfall infiltrated less than one meter (3 ft) before being returned to the atmosphere by evaporation. Soil-gas tritium monitoring data indicate slow subsurface migration, and tritium concentrations in biota were lower than in previous years. All 2001 monitoring data indicate that the Area 3 and Area 5 RWMSs are performing within expectations of the model and parameter assumptions for the facility performance assessments

2016 Waste Management Monitoring Report Area 3 and Area 5 Radioactive Waste Management Sites

Energy Technology Data Exchange (ETDEWEB)

Black, David [National Security Technologies, LLC. (NSTec), Mercury, NV (United States)

2017-08-30

Environmental monitoring data are collected at and around the Area 3 and Area 5 Radioactive Waste Management Sites (RWMSs) within the Nevada National Security Site (NNSS). These data include direct radiation exposure, as well as radiation from the air, groundwater, meteorology, and vadose zone. This report summarizes the 2016 environmental data to provide an overall evaluation of RWMS performance and to support environmental compliance and performance assessment (PA) activities. Some of these data (e.g., radiation exposure, air, and groundwater) are presented in other reports, developed by National Security Technologies, LLC Direct radiation monitoring data indicate exposure levels at the RWMSs are within the range of background levels measured at the NNSS. Slightly elevated exposure levels outside the Area 3 RWMS are attributed to nearby historical aboveground nuclear weapons tests. Air monitoring data show that tritium concentrations in water vapor and americium and plutonium concentrations in air particles are below Derived Concentration Standards for these radionuclides. Groundwater monitoring data indicate the groundwater in the uppermost aquifer beneath the Area 5 RWMS is not impacted by RWMS operations. Results of groundwater analysis from wells around the Area 5 RWMS were all below established investigation levels. Leachate samples collected from the leachate collection system at the mixed low-level waste cell were below established contaminant regulatory limits. During 2016, precipitation at the Area 3 RWMS was 8% below average, and precipitation at the Area 5 RWMS was 8% above average. Water balance measurements indicate that evapotranspiration from the vegetated weighing lysimeter dries the soil and prevents downward percolation of precipitation more effectively than evaporation as measured from the bare-soil weighing lysimeter. Vadose zone monitoring on Area 5 and Area 3 RWMS cell covers shows no evidence of precipitation percolating through the covers

Area radiation monitoring on ISS Increments 17 to 22 using PADLES in the Japanese Experiment Module Kibo

International Nuclear Information System (INIS)

Nagamatsu, A.; Murakami, K.; Kitajo, K.; Shimada, K.; Kumagai, H.; Tawara, H.

2013-01-01

The measurement of radiation environmental parameters in space is essential to support radiation risk assessments for astronauts and establish a benchmark for space radiation models for present and future human space activities. The Japan Aerospace Exploration Agency (JAXA) is performing a continuous area radiation monitoring experiment using the “PAssive Dosimeters for Lifescience Experiments in Space” (PADLES) system inside the Japanese Experiment Module Kibo on board the International Space Station (ISS). The PADLES dosimeter consists of thermoluminescent dosimeters (TLDs) and CR-39 plastic nuclear track detectors (PNTDs). JAXA has run the Area PADLES experiment since the Kibo module was attached to the ISS in June 2008, using 17 dosimeters in fixed locations on the Pressurized Module (PM) and the Experiment Logistics Module-Pressurized Section (ELM-PS) of Kibo, which are replaced every 6 months or every Increment, respectively. For three monitoring periods, known as Area PADLES experiment series no. 1 to no. 3, of 301, 180, and 232 days in June 2008 to April 2010 over ISS Increments 17 to 22, the average absorbed dose (dose equivalent) rates of 12 positions in the PM of Kibo were 319 ± 30 μGy/day (618 ± 102 μSv/day), 276 ± 30 μGy/day (608 ± 94 μSv/day), and 293 ± 33 μGy/day (588 ± 84 μSv/day), respectively. The radiation measurement in the ELM-PS was conducted in only Area PADLES experiment series no. 3 from August 2009 to April 2010 (232 days) over ISS Increments 21 to 22, the average absorbed dose (dose equivalent) rates of 5 positions was 297 ± 28 μGy/day (661 ± 65 μSv/day). The directional dependence of the radiation field was also investigated by installing PADLES dosimeters located in the zenith of ELM-PS of Kibo. -- Highlights: • This article shows the first results of dose measurement inside the Japanese Experiment Module Kibo with the PADLES system. • Generating spatial dose distribution data with the PADLES system are key

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

International Nuclear Information System (INIS)

Dieguez Davila, L.E.

1998-01-01

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

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)

Nevada Test Site 2000 Waste Management Monitoring Report Area 3 and Area 5 Radioactive Waste Management Sites

International Nuclear Information System (INIS)

Yvonne Townsend

2001-01-01

Environmental monitoring data, subsidence monitoring data, and meteorology monitoring data were collected at and around the Area 3 and Area 5 Radioactive Waste Management Sites (RWMSs) at the Nevada Test Site (NTS) (refer to Figure 1). These monitoring data include radiation exposure, air, groundwater, meteorology, vadose zone, subsidence, and biota data. Although some of these media (radiation exposure, air, and groundwater) are reported in detail in other Bechtel Nevada reports (Annual Site Environmental Report [ASER], the National Emissions Standard for Hazardous Air Pollutants [NESHAP] report, and the Annual Groundwater Monitoring Report), they are also summarized in this report to provide an overall evaluation of RWMS performance and environmental compliance. Direct radiation monitoring data indicate that exposure at and around the RWMSs is not above background levels. Air monitoring data indicate that tritium concentrations are slightly above background levels, whereas radon concentrations are not above background levels. Groundwater monitoring data indicate that the groundwater in the uppermost aquifer beneath the Area 5 RWMS has not been affected by the facility. Meteorology data indicate that 2000 was an average rainfall year: rainfall totaled 167 mm (6.6 in) at the Area 3 RWMS (annual average is 156 mm [6.5 in]) and 123 mm (4.8 in) at the Area 5 RWMS (annual average is 127 mm [5.0 in]). Vadose zone monitoring data indicate that 2000 rainfall infiltrated less than one meter (3 ft) before being returned to the atmosphere by evaporation. Soil-gas tritium monitoring data indicate slow subsurface migration, and tritium concentrations in biota were lower than in previous years. All 2000 monitoring data indicate that the Area 3 and Area 5 RWMSs are performing well at isolating buried waste

Nevada Test Site 2001 Waste Management Monitoring Report Area 3 and Area 5 Radioactive Waste Management Sites; TOPICAL

International Nuclear Information System (INIS)

Y. E. Townsend

2002-01-01

Environmental monitoring data, subsidence monitoring data, and meteorology monitoring data were collected at and around the Area 3 and Area 5 Radioactive Waste Management Sites (RWMSs) at the Nevada Test Site (NTS) (refer to Figure 1). These monitoring data include radiation exposure, air, groundwater, meteorology, vadose zone, subsidence, and biota data. Although some of these media (radiation exposure, air, and groundwater) are reported in detail in other Bechtel Nevada (BN) reports (Annual Site Environmental Report[ASER], the National Emissions Standard for Hazardous Air Pollutants[NESHAP] report, and the Annual Groundwater Monitoring Report), they are also summarized in this report to provide an overall evaluation of RWMS performance and environmental compliance. Direct radiation monitoring data indicate that exposure at and around the RWMSs is not above background levels. Air monitoring data indicate that tritium concentrations are slightly above background levels. Groundwater monitoring data indicate that the groundwater in the uppermost aquifer beneath the Area 5 RWMS has not been affected by the facility. Meteorology data indicate that 2001 was an average rainfall year: rainfall totaled 150 mm (5.9 in) at the Area 3 RWMS and 120 mm (4.7 in) at the Area 5 RWMS. Vadose zone monitoring data indicate that 2001 rainfall infiltrated less than one meter (3 ft) before being returned to the atmosphere by evaporation. Soil-gas tritium monitoring data indicate slow subsurface migration, and tritium concentrations in biota were lower than in previous years. All 2001 monitoring data indicate that the Area 3 and Area 5 RWMSs are performing within expectations of the model and parameter assumptions for the facility performance assessments

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

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...

Artificial intelligence applications in fixed area monitor for TRIGA reactor building and service building

International Nuclear Information System (INIS)

Talpalariu, C.; Talpalariu, J.; Vaja, N.; Matei, C.

2008-01-01

This system is intended for the protection of personnel working in those areas of the Reactor Building and Service Building where high gamma radiation fields are expected. A detector, sensitive to gamma radiation, is installed in each of the areas to be monitored. The detector will send a signal, proportional to the radiation level in the area, to a corresponding electronic module (Alarm Unit), where the signal will be amplified and checked against alarm set points for possible alarming conditions. In case the field exceeds the alarm set values, the Alarm Unit will produce a signal that will trigger the field alarms (Horn and Beacon) located in the area where the condition occurred. Each Alarm Unit will send a numerical input to central computer command. he system is required to accomplish the following tasks: - Monitors the level of gamma radiation in those areas of the Station where high radiation fields are expected; - Provides a continuous and centralized display of the radiation level in each of the monitored areas. The display shall be in exposure rate units (R/h); - Provides a visual and audible alarm in each monitored areas; Allows the control room operator to check at any time the radiation levels and alarm conditions in each of the monitored areas; - Control room operator shall be alerted of any alarm conditions that occurs in the Station. A typical monitoring loop is composed of the following components: Detector Assembly type: CI-MA - 522 two channels, two ranges; Horn and Beacon Assembly; Remote Indicating Meter with Warning Lights; Central computer; common equipment for all 40 loops. (authors)

Citizen radiation monitoring program for the TMI area

International Nuclear Information System (INIS)

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

1981-07-01

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

Citizen radiation monitoring program for the TMI area

Energy Technology Data Exchange (ETDEWEB)

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

1981-07-01

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

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.

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

Radiation monitoring. Quarterly report for the Greater Manchester Fire and Civil Defence Authority and the Manchester Area Pollution Advisory Council. Manchester Area Gamma Radiation Air Monitoring System (MANAGRAMS), report covering period of 3 months 01/04/1997 to 30/06/1997

International Nuclear Information System (INIS)

1997-01-01

Gamma radiation monitoring data from ten outstations in the Manchester area are presented. For each station there is a summary table, a background radiation graph showing 6 hour mean levels and a windrose graph showing the direction of the wind as a percentage of the total. A line graph comparison between stations is provided for the background 6 hour mean levels and a bar chart comparison of total dose. Graphs of temperature and barometric pressure taken from extra sensors at the Trafford station are presented. (Author)

Design of movable fixed area γ dose rate monitor

International Nuclear Information System (INIS)

Li Dongyu; Cheng Wen; Li Jikai; Huang Hong; Shen Qiming; Zhang Qiang; Liu Zhengshan

2005-10-01

Movable fixed area γ dose rate monitor has not only the characteristics of fixed area γ dose rate monitor, but that of portable meter as well. Its main function is to monitor the areas where dose rate would change without orderliness to prevent unplanned radiation exposure accidents from happening. The design way of the monitor, the main indicators description, the working principle and the comprising of software and hardware are briefly introduced. The monitor has the characteristics of simple installation, easy maintenance, little power consumption, wide range, notability of visual and audible alarm and so on. Its design and technique have novelty and advancement. (authors)

Thyroid monitoring for residents of disaster-affected and neighboring areas

International Nuclear Information System (INIS)

Ito, Shigeki

2014-01-01

The devastating environmental contamination caused by the nuclear disaster at the Fukushima Daiichi Nuclear Power Station of The Tokyo Electric Power Company is exposing the residents of the disaster-affected areas to health risks attributable to radiation exposure, and fear of the development of 131 I-induced thyroid cancer, which is a stochastic effect of radiation and is particularly high. As part of the response to nuclear disasters by the government of the municipality where the nuclear power station is located and in operation and by the governments of neighboring municipalities, it is necessary to conduct thyroid monitoring for the purpose of alleviating the fears of residents of the disaster-affected areas as well as those living in the contaminated, even if only slightly, neighboring areas (local residents). This health monitoring needs to be implemented without delay in the case of a disaster along with dissemination of a portable type thyroid monitoring system available at evacuation centers, etc. for assessing thyroid exposure doses. The establishment of a system for developing personnel ready to perform monitoring is also essential. Assessing thyroid exposure doses is indispensable as a means of assuring local residents not only of safety but also of security from the risks of radiation. To date, contamination has not been detected in people, except for residents contaminated by a large amount of iodine, by employing the mobile type of thyroid monitoring system. However, when local residents seeking security desire thyroid monitoring, it is preferable that a portable type simplified thyroid monitoring system be used as a means of ensuring security against radiation. (author)

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.

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)

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)

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.

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.

Technical Basis Document for PFP Area Monitoring Dosimetry Program

CERN Document Server

Cooper, J R

2000-01-01

This document describes the phantom dosimetry used for the PFP Area Monitoring program and establishes the basis for the Plutonium Finishing Plant's (PFP) area monitoring dosimetry program in accordance with the following requirements: Title 10, Code of Federal Regulations (CFR), part 835, ''Occupational Radiation Protection'' Part 835.403; Hanford Site Radiological Control Manual (HSRCM-1), Part 514; HNF-PRO-382, Area Dosimetry Program; and PNL-MA-842, Hanford External Dosimetry Technical Basis Manual.

Technical Basis Document for PFP Area Monitoring Dosimetry Program

International Nuclear Information System (INIS)

COOPER, J.R.

2000-01-01

This document describes the phantom dosimetry used for the PFP Area Monitoring program and establishes the basis for the Plutonium Finishing Plant's (PFP) area monitoring dosimetry program in accordance with the following requirements: Title 10, Code of Federal Regulations (CFR), part 835, ''Occupational Radiation Protection'' Part 835.403; Hanford Site Radiological Control Manual (HSRCM-1), Part 514; HNF-PRO-382, Area Dosimetry Program; and PNL-MA-842, Hanford External Dosimetry Technical Basis Manual

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

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.)

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 ...

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)

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.

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

Technical Basis Document for PFP Area Monitoring Dosimetry Program

Energy Technology Data Exchange (ETDEWEB)

COOPER, J.R.

2000-04-17

This document describes the phantom dosimetry used for the PFP Area Monitoring program and establishes the basis for the Plutonium Finishing Plant's (PFP) area monitoring dosimetry program in accordance with the following requirements: Title 10, Code of Federal Regulations (CFR), part 835, ''Occupational Radiation Protection'' Part 835.403; Hanford Site Radiological Control Manual (HSRCM-1), Part 514; HNF-PRO-382, Area Dosimetry Program; and PNL-MA-842, Hanford External Dosimetry Technical Basis Manual.

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

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)

Radiation monitoring: Quarterly report for the Greater Manchester Fire and Civil Defence Authority and the Manchester Area Pollution Advisory Council. Manchester Area Gamma Radiation Air Monitoring System (MANAGRAMS): report covering period of 3 months 01/07/1996 to 30/09/1996

International Nuclear Information System (INIS)

1996-01-01

Gamma radiation monitoring data from ten outstations in the Manchester area for the period 01/07/1996 to 30/09/1996 are presented. For each station there is a summary table, a background radiation graph showing 6 hour mean levels and a wind rose graph showing the direction of the wind as a percentage of the total. A line graph comparison between stations is provided for the background 6 hour mean levels and a bar chart comparison of total dose during the reporting period. Graphs of barometric pressure and temperature taken from extra sensors at the Trafford station are also presented. (UK)

Radiation monitoring. Quarterly report for the Greater Manchester Fire and Civil Defence Authority and the Manchester Area Pollution Advisory Council. Manchester Area Gamma Radiation Air Monitoring System (MANAGRAMS), report covering period of 3 months 1 January to 31 March 1996

International Nuclear Information System (INIS)

1996-01-01

Gamma radiation monitoring data from nine outstations in the Manchester area for the period 01/01/96 to 31/03/96 are presented. For each station there is a summary table, a background radiation graph showing 6 hour mean levels and a windrose graph showing the direction of the wind as a percentage of the total. A line graph comparison between stations is provided for the background 6 hour mean levels and a bar chart comparison of total dose. Graphs of temperature and barometric pressure taken from extra sensors at the Trafford station are presented. (UK)

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)

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.

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)

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

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)

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

Radiation environmental real-time monitoring and dispersion modeling

International Nuclear Information System (INIS)

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

2014-01-01

escaping from nuclear facility and for estimation and forecasting of area contamination, concentrations of various radionuclides in different altitudes and dose rates. The radiation dispersion model can be also used for identification of unknown source of atmospheric radioactivity if it's used complementary with aerosol monitors in radiation monitoring network. (authors)

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

Gamma-ray and neutron area monitoring system of linear IFMIF prototype accelerator building

International Nuclear Information System (INIS)

Takahashi, Hiroki; Kojima, Toshiyuki; Narita, Takahiro; Tsutsumi, Kazuyoshi; Maebara, Sunao; Sakaki, Hironao; Nishiyama, Koichi

2013-01-01

Highlights: • Area monitoring system and control system are needed for LIPAc radiation management. • To secure the radiation safety, these systems are linked with two kinds of data path. • Hardwired data paths are adopted to realize the fast transfer of interlock signals. • Dual LAN and shared memory are adopted to the reliable transfer of monitoring data. • Data transfers without unnecessary load are designed and configured for these systems. -- Abstract: The linear IFMIF prototype accelerator (LIPAc) produces deuteron beam with 1 MW power. Since huge number of neutrons occur from such a high power beam, therefore, it is important for the radiation management to design a high reliability area monitoring system for gamma-rays and neutrons. To obtain the valuable operation data of the high-power deuteron beam at LIPAc, it is important to link and record the beam operation data and the area monitoring data. We realize the reliable data transfer to provide the area monitoring data to the accelerator control system which needs a high reliability using the shared-memory data link method. This paper describes the area monitoring system in the LIPAc building and the data-link between this system and the LIPAc control system

Environmental radiation monitoring system in Tokai and Oarai areas

International Nuclear Information System (INIS)

Morita, Shigeki

1983-01-01

In the Tokai and the Oarai areas there are total of seventeen enterprises, different in size and kind, connected with nuclear energy. Environmental monitoring is carried out in the cooperation of the Government, local governments and enterprises according to the plans by a prefectural monitoring committee. The purpose is in the following three aspects: (1) Estimation of the dose of general people, based on environmental radioactivity and released radioactivity data (2) Grasping the radioactive accumulation on long-terms (3) Detection of abnormal releases from the enterprises at an early stage. By environmental monitoring made thus far, no rise in environmental radioactivities due to the enterprises is indicated. (author)

Performance test of personal RF monitor for area monitoring at magnetic confinement fusion facility

International Nuclear Information System (INIS)

Tanaka, M.; Uda, T.; Wang, J.; Fujiwara, O.

2012-01-01

For safety management at a magnetic confinement fusion-test facility, protection from not only ionising radiation, but also non-ionising radiation such as the leakage of static magnetic and electromagnetic fields is an important issue. Accordingly, the use of a commercially available personal RF monitor for multipoint area monitoring is proposed. In this study, the performance of both fast- and slow-type personal RF monitors was investigated by using a transverse electromagnetic cell system. The range of target frequencies was between 10 and 300 MHz, corresponding to the ion cyclotron range of frequency in a fusion device. The personal RF monitor was found to have good linearity, frequency dependence and isotropic response. However, the time constant for the electric field sensor of the slow-type monitor was much longer than that for the fast-type monitor. Considering the time-varying field at the facility, it is found that the fast-type monitor is suitable for multipoint monitoring at magnetic confinement fusion test facilities. (authors)

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

International Nuclear Information System (INIS)

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

2017-01-01

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

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

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.)

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)

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)

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)

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

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

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

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

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.)

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

Background radiation study of Offa industrial area of Kwara State ...

African Journals Online (AJOL)

A study of the external background radiation in Offa industrial area of Kwara State is hereby reported. An in-situ measurement using two Digilert radiation monitors at five different stations were carried out. A mean exposure rate of 0.0132mR/hr, which represents 20% elevation from the standard background radiation, was ...

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.)

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)

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

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.

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

Nevada Test Site, 2006 Waste Management Monitoring Report, Area 3 and Area 5 Radioactive Waste Management Sites

International Nuclear Information System (INIS)

David B. Hudson

2007-01-01

Environmental monitoring data were collected at and around the Area 3 and Area 5 Radioactive Waste Management Sites (RWMSs) at the Nevada Test Site. These data are associated with radiation exposure, air, groundwater, meteorology, vadose zone, subsidence, and biota. This report summarizes the 2006 environmental data to provide an overall evaluation of RWMS performance and to support environmental compliance and performance assessment (PA) activities. Some of these data (e.g., radiation exposure, air, and groundwater) are presented in other reports (U.S. Department of Energy, 2006; Warren and Grossman, 2007; National Security Technologies, LLC, 2007). Direct radiation monitoring data indicate that exposure levels around the RWMSs are at or below background levels. Air monitoring data at the Area 3 and Area 5 RWMSs indicate that tritium concentrations are slightly above background levels. There is no detectable man-made radioactivity by gamma spectroscopy, and concentrations of americium and plutonium are only slightly above detection limits at the Area 3 RWMS. Measurements at the Area 5 RWMS show that radon flux from waste covers is no higher than natural radon flux from undisturbed soil in Area 5. Groundwater monitoring data indicate that the groundwater in the uppermost aquifer beneath the Area 5 RWMS is not impacted by facility operations. Precipitation during 2006 totaled 98.6 millimeters (mm) (3.9 inches [in.]) at the Area 3 RWMS and 80.7 mm (3.2 in.) at the Area 5 RWMS. Soil-gas tritium monitoring continues to show slow subsurface migration consistent with previous results. Moisture from precipitation at Area 5 remains at the bottom of the bare-soil weighing lysimeter, but this same moisture has been removed from the vegetated weighing lysimeter by evapotranspiration. Vadose zone data from the operational waste pit covers show that evaporation continues to slowly remove soil moisture that came from the heavy precipitation in the fall of 2004 and the spring of

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)

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

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.

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

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)

Radiation-Triggered Surveillance for UF6 Monitoring

Energy Technology Data Exchange (ETDEWEB)

Curtis, Michael M. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

2015-12-01

This paper recommends the use of radiation detectors, singly or in sets, to trigger surveillance cameras. Ideally, the cameras will monitor cylinders transiting the process area as well as the process area itself. The general process area will be surveyed to record how many cylinders have been attached and detached to the process between inspections. Rad-triggered cameras can dramatically reduce the quantity of recorded images, because the movement of personnel and equipment not involving UF6 cylinders will not generate a surveillance review file.

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)

Implementation of a remote system for monitoring of radiological areas of radiological areas

International Nuclear Information System (INIS)

Velazquez E, Walter; Galuppo G, Emiliano; Gutierrez G, Jorge; Reyes R, Jerson

2008-01-01

Full text: Introduction: The present work shows the development of a radiation remote monitoring system which control radiological areas in the principal facilities at CCHEN and the development in the last years to use this system called SMARR (Remote Radiological Area Monitoring System). This is an important issue in radiological safety is to know 'on line' and in a 'continuously way' the radiological variables of areas, especially if in these areas people manage radioactive sources or material, the monitoring system are operative on La Reina and Lo Aguirre Nuclear Centers. This 'knowledge' gets a good support to the radiological safety to safeguard the environment and people in the facilities. Nuclear Chilean Commission: Actually, this system is daily operating to register the background radiation and level operation, for example of the facilities research reactor, cyclone, irradiators, in order to probe the behaviors under operational requirements. The system was made using common Geiger Muller and NaI detectors. This signal is received, data by data, for a collector computer which uses a Labview program to do this displayed on a screen computer using graphics to show the activity on a radiological area, and when the lectures pass a setting value automatically the system send by e-mail and text message which also can be received for cell phones enabled for this for the supervisor. Each monitored facility is completely independent of each other and store a data backup, also every installation are monitoring with server computer, it's concentrating the information and allow to view it on line in real time, trough the intranet and internet network. In addition, the information is stored in the special report in the server and available for to do a statistics and identify the operation periods, and control of radioactive sources. The Industry: The radiological protection on industry is necessary today, the typical instrumentation on the industry is growing up in the

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)

Response of a neutron monitor area with TLDs pairs

Energy Technology Data Exchange (ETDEWEB)

Guzman G, K. A.; Borja H, C. G.; Valero L, C.; Hernandez D, V. M.; Vega C, H. R. [Universidad Autonoma de Zacatecas, Unidad Academica de Estudios Nucleares, Calle Cipres No. 10, Fracc. La Penuela, 98068 Zacatecas (Mexico); Gallego, E.; Lorente, A., E-mail: ing_karen_guzman@yahoo.com.mx [Universidad Politecnica de Madrid, Departamento de Ingenieria Nuclear, Jose Gutierrez Abascal 2, E-28006 Madrid (Spain)

2011-10-15

The response of a passive neutron monitor area has been calculated using the Monte Carlo code MCNP5. The response was the amount of n({sup 6}Li, T){alpha} reactions occurring in a TLD-600 located at the center of a cylindrical polyethylene moderator. Fluence, (n, a) and H*(10) responses were calculated for 47 monoenergetic neutron sources. The H*(10) relative response was compared with responses of commercially available neutron monitors being alike. Due to {sup 6}Li cross section (n, {alpha}) reactions are mainly produced by thermal neutrons, however TLD-600 is sensitive to gamma-rays; to eliminate the signal due to photons monitor area was built to hold 2 pairs of TLD-600 and 2 pairs of TLD-700, thus from the difference between TLD-600 and TLD-700 readouts the net signal due to neutrons is obtained. The monitor area was calibrated at the Universidad Politecnica de Madrid using a {sup 241}AmBe neutron source; net TLD readout was compared with the H*(10) measured with a Bert hold Lb-6411. Performance of the neutron monitor area was determined through two independent experiments, in both cases the H*(10) was statistically equal to H*(10) measured with a Bert hold Lb-6411. Neutron monitor area with TLDs pairs can be used in working areas with intense, mixed and pulsed radiation fields. (Author)

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)

Neutron area monitor with TLD pairs

International Nuclear Information System (INIS)

Guzman G, K. A.; Borja H, C. G.; Valero L, C.; Hernandez D, V. M.; Vega C, H. R.

2011-11-01

The response of a passive neutron area monitor with pairs of thermoluminescent dosimeters has been calculated using the Monte Carlo code MCNP5. The response was calculated for one TLD 600 located at the center of a polyethylene cylinder, as moderator. When neutrons collide with the moderator lose their energy reaching the TLD with thermal energies where the ambient dose equivalent is calculated. The response was calculated for 47 monoenergetic neutron sources ranging from 1E(-9) to 20 MeV. Response was calculated using two irradiation geometries, one with an upper source and another with a lateral source. For both irradiation schemes the response was calculated with the TLDs in two positions, one parallel to the source and another perpendicular to the source. The advantage of this passive neutron monitor area is that can be used in locations with intense, pulsed and mixed radiation fields. (Author)

Altitude control performance improvement via preview controller for unmanned airplane for radiation monitoring system

International Nuclear Information System (INIS)

Sato, Masayuki; Muraoka, Koji; Hozumi, Koki; Sanada, Yukihisa; Yamada, Tsutomu; Torii, Tatsuo

2017-01-01

This paper is concerned with the design problem of preview altitude controller for Unmanned Airplane for Radiation Monitoring System (UARMS) to improve its control performance. UARMS has been developed for radiation monitoring around Fukushima Dai-ichi nuclear power plant which spread radiation contaminant due to the huge tsunamis caused by the Great East Japan Earthquake. The monitoring area contains flat as well as mountain areas. The basic flight controller has been confirmed to have satisfactory performance with respect to altitude holding; however, the control performance for variable altitude commands is not sufficient for practical use in mountain areas. We therefore design preview altitude controller with only proportional gains by considering the practicality and the strong requirement of safety for UARMS. Control performance of the designed preview controller was evaluated by flight tests conducted around Fukushima Sky Park. (author)

Development Of Data Acquisition Software For Centralized Radiation Monitoring System

International Nuclear Information System (INIS)

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

2014-01-01

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

Environmental monitoring and radiation protection programs of Novi Han radioactive waste repository

International Nuclear Information System (INIS)

Christoskova, M.; Kostova, M.; Sheherov, L.; Bekiarov, P.; Iovtchev, M.

2000-01-01

The system for monitoring and control as an important part of the safety management of the Novi Han Radioactive Waste Repository contains two independent programs: environmental monitoring of the site (controlled area), the restricted access area and the surveillance area (supervised area) of the repository and radiation protection program including personal dosimetric control and indoor dosimetric control of workplaces in the buildings of the repository. The main activities related to the programs implementation are presented

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.)

Nevada Test Site 2005 Waste Management Monitoring Report Area 3 and Area 5 Radioactive Waste Management Sites

International Nuclear Information System (INIS)

David B. Hudson, Cathy A. Wills

2006-01-01

Environmental monitoring data were collected at and around the Area 3 and Area 5 Radioactive Waste Management Sites (RWMSs) at the Nevada Test Site. These data are associated with radiation exposure, air, groundwater, meteorology, vadose zone, subsidence, and biota. This report summarizes the 2005 environmental data to provide an overall evaluation of RWMS performance and to support environmental compliance and performance assessment activities. Some of these data (e.g., radiation exposure, air, and groundwater) are presented in other reports (U.S. Department of Energy, 2005; Grossman, 2005; Bechtel Nevada, 2006). Direct radiation monitoring data indicate that exposure levels around the RWMSs are at or below background levels. Air monitoring data at the Area 3 and Area 5 RWMSs indicate that tritium concentrations are slightly above background levels. There is no detectable man-made radioactivity by gamma spectroscopy, and concentrations of americium and plutonium are only slightly above detection limits at the Area 3 RWMS. Measurements at the Area 5 RWMS show that radon flux from waste covers is no higher than natural radon flux from undisturbed soil in Area 5. Groundwater monitoring data indicate that the groundwater in the uppermost aquifer beneath the Area 5 RWMS is not impacted by facility operations. Precipitation during 2005 totaled 219.1 millimeters (mm) (8.63 inches [in.]) at the Area 3 RWMS and 201.4 mm (7.93 in.) at the Area 5 RWMS. Soil-gas tritium monitoring continues to show slow subsurface migration consistent with previous results. Moisture from precipitation at Area 5 has percolated to the bottom of the bare-soil weighing lysimeter, but this same moisture has been removed from the vegetated weighing lysimeter by evapotranspiration. Vadose zone data from the operational waste pit covers show that precipitation from the fall of 2004 and the spring of 2005 infiltrated past the deepest sensors at 188 centimeters (6.2 feet) and remains in the pit cover

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)

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

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)

Fast Deploy Radiation Monitoring Array Emergency Solution Based on GPS and Cellular Network

International Nuclear Information System (INIS)

Vax, E.; Broide, A.; Manor, A.; Marcus, E.; Seif, R.; Nir, J.; Kadmon, Y.; Sattinger, D.; Levinson, S.; Tal, N.

2004-01-01

Radiation monitoring of a possible contaminating source is highly important for safety and risk analysis. Since the monitoring must cover the whole contaminated area, the standard solution is to scatter an array of numerous fixed detectors in advance. The Fast Deploy Radiation Monitoring Array (FDRMA) is a solution that does not require coverage of the entire area. The FDRMA is a compact, world wide applicative, seamless and novel solution, designed for emergency cases. The system consists of GPS and IP cellular network, which make it mobile and therefore suitable for global use. The most significant advantage of the FDRMA system is minimizing the exposure time of the monitoring teams, while maintaining flexibility of the deployment area, as opposed to the Vehicle Monitoring System (VMS) [1] or the standard solution mentioned above. A detailed description of the proposed FDRMA system and its comparison to a fixed detectors' array is presented in this work

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

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.

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)

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)

Nevada Test Site 2009 Waste Management Monitoring Report Area 3 and Area 5 Radioactive Waste Management Sites

International Nuclear Information System (INIS)

2010-01-01

Environmental monitoring data were collected at and around the Area 3 and Area 5 Radioactive Waste Management Sites (RWMSs) at the Nevada Test Site (NTS). These data are associated with radiation exposure, air, groundwater, meteorology, vadose zone, subsidence, and biota. This report summarizes the 2009 environmental data to provide an overall evaluation of RWMS performance and to support environmental compliance and performance assessment (PA) activities. Some of these data (e.g., radiation exposure, air, and groundwater) are presented in other reports. Direct radiation monitoring data indicate exposure levels at the RWMSs are within the range of background levels measured at the NTS. Air monitoring data at the Area 3 and Area 5 RWMSs indicate that tritium concentrations are slightly above background levels. All gamma spectroscopy results for air particulates collected at the Area 3 and Area 5 RWMS were below the minimum detectable concentrations, and concentrations of americium and plutonium are only slightly above detection limits. The measured levels of radionuclides in air particulates and moisture are below derived concentration guides for these radionuclides. Radon flux from waste covers is well below regulatory limits. Groundwater monitoring data indicate that the groundwater in the uppermost aquifer beneath the Area 5 RWMS is not impacted by facility operations. The 87.6 millimeters (mm) (3.45 inches (in.)) of precipitation at the Area 3 RWMS during 2009 is 43 percent below the average of 152.4 mm (6.00 in.), and the 62.7 mm (2.47 in.) of precipitation at the Area 5 RWMS during 2009 is 49 percent below the average of 122.5 mm (4.82 in.). Soil-gas tritium monitoring at borehole GCD-05 continues to show slow subsurface migration consistent with previous results. Water balance measurements indicate that evapotranspiration from the vegetated weighing lysimeter dries the soil and prevents downward percolation of precipitation more effectively than evaporation

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

Nevada Test Site 2007 Waste Management Monitoring Report Area 3 and Area 5 Radioactive Waste Management Sites

International Nuclear Information System (INIS)

NSTec Environmental Management

2008-01-01

Environmental monitoring data were collected at and around the Area 3 and Area 5 Radioactive Waste Management Sites (RWMSs) at the Nevada Test Site. These data are associated with radiation exposure, air, groundwater, meteorology, vadose zone, subsidence, and biota. This report summarizes the 2007 environmental data to provide an overall evaluation of RWMS performance and to support environmental compliance and performance assessment (PA) activities. Some of these data (e.g., radiation exposure, air, and groundwater) are presented in other reports (National Security Technologies, LLC, 2007a; 2008; Warren and Grossman, 2008). Direct radiation monitoring data indicate exposure levels at the RWMSs are at background levels. Air monitoring data at the Area 3 and Area 5 RWMSs indicate that tritium concentrations are slightly above background levels. A single gamma spectroscopy measurement for cesium was slightly above the minimum detectable concentration, and concentrations of americium and plutonium are only slightly above detection limits at the Area 3 RWMS. The measured levels of radionuclides in air particulates are below derived concentration guides for these radionuclides. Radon flux from waste covers is well below regulatory limits. Groundwater monitoring data indicate that the groundwater in the uppermost aquifer beneath the Area 5 RWMS is not impacted by facility operations. The 136.8 millimeters (mm) (5.39 inches [in.]) of precipitation at the Area 3 RWMS during 2007 is 13 percent below the average of 158.1 mm (6.22 in.), and the 123.8 mm (4.87 in.) of precipitation at the Area 5 RWMS during 2007 is 6 percent below the average of 130.7 mm (5.15 in.). Soil-gas tritium monitoring at borehole GCD-05U continues to show slow subsurface migration consistent with previous results. Water balance measurements indicate that evapotranspiration from the vegetated weighing lysimeter dries the soil and prevents downward movement percolation of precipitation more effectively

Area and environmental gamma dose monitoring at PINSTECH

International Nuclear Information System (INIS)

Javed, M.; Awan, M.A.; Ahmad, S.; Afsar, M.; Orfi, S.D.

1986-11-01

Radiation dose monitoring of various radioactive laboratories including PARR building, radioactive waste disposal area and the environment upto initial peripheral limits of PINSTECH has been carried out by TLD's installed at different locations. Average dose rates in terms of percentage of dose limits have been compiled. The results for the year 1985 have been discussed in this report. (author)

Radiation protection and ambient radioactivity monitoring in the area of the Asse mine. Annual report 2005

International Nuclear Information System (INIS)

Meyer, H.; Wanka, T.

2006-01-01

Radiation protection measurements in the Asse mine and its environment were continued. Programmes for monitoring off-air and the environment more or less summarize monitoring measures and measurements so far. 358 measurements were made, i.e. as many as in the year before. All values recorded were in the range of natural background activity. In some cases, also long-term effects of early nuclear weapons tests and of the Chernobyl accident were identified. All staff members were monitored in accordance with the Radiation Protection Ordinance, and local doses, local dose rates and mine air activity were recorded in the framework of occupational radiation protection. None of the measurements exceeded the permissible personal doses and activities for occulpationally exposed persons. In the off-air of the salt mine, low concentrations of H-3, C-14, Pb-10 and Rn-222 including Rn-220 as well as short-lived radon decay products were measured. Concentrations in the environment of the shaft as calculated from the annual measurements were lower in some instances than the average natural concentrations of these nuclides. Radiation exposure from emissions in the most unfavourable site in the vicinity was far below the limiting values set by the Radiation Protection Ordinance. Storage of radioactive waste and research activities in the Asse salt mine resulted in no significantly higher population exposure in the surrounding villages. (orig.)

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

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

Nevada National Security Site 2010 Waste Management Monitoring Report Area 3 and Area 5 Radioactive Waste Management Sites

International Nuclear Information System (INIS)

2011-01-01

Environmental monitoring data were collected at and around the Area 3 and Area 5 Radioactive Waste Management Sites (RWMSs) at the Nevada National Security Site (NNSS). These data are associated with radiation exposure, air, groundwater, meteorology, vadose zone, subsidence, and biota. This report summarizes the 2010 environmental data to provide an overall evaluation of RWMS performance and to support environmental compliance and performance assessment (PA) activities. Some of these data (e.g., radiation exposure, air, and groundwater) are presented in other reports (National Security Technologies, LLC, 2010a; 2010b; 2011). Direct radiation monitoring data indicate exposure levels at the RWMSs are within the range of background levels measured at the NNSS. Air monitoring data at the Area 3 and Area 5 RWMSs indicate that tritium concentrations are slightly above background levels. All gamma spectroscopy results for air particulates collected at the Area 3 and Area 5 RWMS were below the minimum detectable concentrations, and concentrations of americium and plutonium are only slightly above detection limits. The measured levels of radionuclides in air particulates and moisture are below derived concentration guides for these radionuclides. Groundwater monitoring data indicate that the groundwater in the uppermost aquifer beneath the Area 5 RWMS is not impacted by facility operations. The 246.9 millimeters (mm) (9.72 inches [in.]) of precipitation at the Area 3 RWMS during 2010 is 56 percent above the average of 158.7 mm (6.25 in.), and the 190.4 mm (7.50 in.) of precipitation at the Area 5 RWMS during 2010 is 50 percent above the average of 126.7 mm (4.99 in.). Soil-gas tritium monitoring at borehole GCD-05 continues to show slow subsurface migration consistent with previous results. Water balance measurements indicate that evapotranspiration from the vegetated weighing lysimeter dries the soil and prevents downward percolation of precipitation more effectively than

A universal measuring and monitoring system for nuclear radiation

International Nuclear Information System (INIS)

Genrich, V.

1988-01-01

Genitron Instruments, Frankfurt/Main, committed themselves to revise the 'conventional' concept of counting tube metrology. The goal was to develop a modular system that would allow large-area measuring tasks. The contribution in hand explains this development, which consists of a highly integrated measuring head that can be combined with various detector types, and complemented by various system components, to form a universal measuring and monitoring system for nuclear radiation. This modular design concept is capable of fulfilling a multitude of tasks, ranging from single, specific applications to non-stop monitoring tasks within a large-area measuring network. (orig./DG) [de

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

escaping from nuclear facility and for estimation and forecasting of area contamination, concentrations of various radionuclides in different altitudes and dose rates. The radiation dispersion model can be also used for identification of unknown source of atmospheric radioactivity if it's used complementary with aerosol monitors in radiation monitoring network. (authors)

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)

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.

How should work the thyroid monitoring for inhabitants of the destroyed area and its adjacent areas

International Nuclear Information System (INIS)

Nishizawa, Kunihide; Ito, Shigeki

2011-01-01

The general method of the exposure dose evaluation and the thyroid monitoring for it are explained and stressed. The vast area environmental contamination around the Fukushima Daiichi Nuclear Power Station accident brought about the anxiety of health risks for the inhabitants, especially probabilistic outbreak of cancer owing to radiation exposure. The report concludes that for the post traumatic stress disorder (PTSD) mental care and thyroid monitoring are necessary. (S. Ohno)

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)

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

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.

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)

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

International Nuclear Information System (INIS)

Yoshioka, Mitsuo; Terakawa, Kazuyoshi; Kasai, Toshihiro

2012-01-01

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

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)

Unmanned aerial complexes as a way of NPP and environment radiation monitoring

International Nuclear Information System (INIS)

Babak, V.P.; Kanchenko, V.A.; Klyuchnikov, A.A.; Krasnov, V.A.; Chepur, N.L.

2012-01-01

As a example of the using of unmanned aircraft for video monitoring and radiation background measurement in the accident area at the NPP Fukushima -1 are shown the efficiency of its use. The analyse of possible environmental monitoring remotely piloted ultralight unmanned aerial vehicle are carried out

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.

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.)

Controlled platform for the radiation dose data measured in Radiation controlled area of KOMAC

International Nuclear Information System (INIS)

Park, Sung Kyun; Min, Yi Sub; Park, Jeong Min; Cho, Yong Sub

2016-01-01

Korea multi-purpose accelerator complex (KOMAC), the branch institute of Korea atomic energy research institute (KAERI), is a multi-user facility to provide a high-intensity proton beam with the energy from 20 MeV to the 100 MeV. This proton beam is accelerated via the proton linear accelerator that is comprised of a 50-keV injector, 3-MeV radio frequency quadrupole (RFQ), and 100-MeV drift tube linac (DTL). The KOMAC site is classified into General public area and Radiation controlled area, according to the dose rate of 0.25 μSv/h. The system for the data made in Radiation controlled area should have the database to save and the data in the database could be expressed on the monitor in the any form which user wants. The control platform to satisfy these conditions will be made on the basis of the Qt program and MYSQL program. The place with the maximum average values about the alpha and beta detected is the entrance of Radiation controlled area. However, their values are very small in comparison to the criteria to decide the contamination area in KOMAC. That is, KOMAC is safe from the radioactive contamination. The reason why the radiation dose value is twice the background value in Klystron gallery is the klystron to generate the radiation. However, actually the klystron gallery is controlled by the control room when the proton beam is accelerated

Controlled platform for the radiation dose data measured in Radiation controlled area of KOMAC

Energy Technology Data Exchange (ETDEWEB)

Park, Sung Kyun; Min, Yi Sub; Park, Jeong Min; Cho, Yong Sub [KAERI, Daejeon (Korea, Republic of)

2016-05-15

Korea multi-purpose accelerator complex (KOMAC), the branch institute of Korea atomic energy research institute (KAERI), is a multi-user facility to provide a high-intensity proton beam with the energy from 20 MeV to the 100 MeV. This proton beam is accelerated via the proton linear accelerator that is comprised of a 50-keV injector, 3-MeV radio frequency quadrupole (RFQ), and 100-MeV drift tube linac (DTL). The KOMAC site is classified into General public area and Radiation controlled area, according to the dose rate of 0.25 μSv/h. The system for the data made in Radiation controlled area should have the database to save and the data in the database could be expressed on the monitor in the any form which user wants. The control platform to satisfy these conditions will be made on the basis of the Qt program and MYSQL program. The place with the maximum average values about the alpha and beta detected is the entrance of Radiation controlled area. However, their values are very small in comparison to the criteria to decide the contamination area in KOMAC. That is, KOMAC is safe from the radioactive contamination. The reason why the radiation dose value is twice the background value in Klystron gallery is the klystron to generate the radiation. However, actually the klystron gallery is controlled by the control room when the proton beam is accelerated.

Design and development of a Compact Aerial Radiation Monitoring System (CARMS)

International Nuclear Information System (INIS)

Raman, N.; Chaudhury, Probal; Padmanabhan, N.; Pradeepkumar, K.S.; Sharma, D.N.

2005-01-01

Operation of nuclear facilities, increasing usage of radioisotopes in industrial, scientific and medical applications and transport of nuclear and radioactive materials may have impact on the surrounding environment. There is thus a need to periodically monitor the environmental radiation background all over the country and particularly around the nuclear facilities for assessing any possible impact on the environment. Preparedness required for response to emergencies caused due to radiological/nuclear incidents/ accidents or due to radiological/nuclear terrorism also demands state of the art systems and methodology for quick assessment of radiological impact over large affected areas. In order to meet these requirements, a Compact Aerial Radiation Monitoring System (CARMS) has been designed and developed. This system is battery operated, portable and rugged for mobile radiation monitoring and can be placed in aerial platforms like helicopters or Unmanned Aerial Vehicles (UAVs) for unattended operation. CARMS uses energy compensated multiple GM detectors for enhancing sensitivity and is attached with commercially available Global Positioning System (GPS) for online acquisition of positional coordinates with time. The AT89LV52 microcontroller used in the system tags the dose rate data with time and positional information and stores contiguously in a serial data memory for radiological mapping of the area surveyed using any mobile platform such as aircraft/train/boat/road vehicle. The system consumes ∼150 mA including the GPS at 12 V DC enabling ∼50 hours of continuous monitoring with a 7 Ah battery source. The system has been used in aerial, rail and road based environmental radiation surveys carried out at various places of the country. With PC support, the system can map the radiological status online onto the map of the area being surveyed to help decision-making on countermeasures during the survey. (author)

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)

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

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)

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....

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

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

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

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)

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.)

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)

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)

Wireless remote radiation monitoring system (WRRMS). Innovative technology summary report

International Nuclear Information System (INIS)

1998-12-01

The Science Application International Corporation (SAIC) RadStar trademark wireless remote radiation monitoring system (WRRMS) is designed to provide real-time monitoring of the radiation dose to workers as they perform work in radiologically contaminated areas. WRRMS can also monitor dose rates in a room or area. The system uses radio-frequency communications to transmit dose readings from the wireless dosimeters worn by workers to a remote monitoring station that can be located out of the contaminated area. Each base station can monitor up to 16 workers simultaneously. The WRRMS can be preset to trigger both audible and visual alarms at certain dose rates. The alarms are provided to the worker as well as the base station operator. This system is particularly useful when workers are wearing personal protective clothing or respirators that make visual observation of their self-reading dosimeters (SRDs), which are typically used to monitor workers, more difficult. The base station is an IBM-compatible personal computer that updates and records information on individual workers every ten seconds. Although the equipment costs for this improved technology are higher than the SRDs (amortized at $2.54/hr versus $1.02/hr), total operational costs are actually less ($639/day versus $851/day). This is because the WRRMS requires fewer workers to be in the contaminated zone than the traditional (baseline) technology. There are also intangible benefits associated with improved worker safety and as low as reasonably achievable (ALARA) principles, making the WRRMS an attractive alternative to the baseline technology. The baseline technology measures only integrated dose and requires workers to check their own dosimeters manually during the task

Wireless remote radiation monitoring system (WRRMS). Innovative technology summary report

Energy Technology Data Exchange (ETDEWEB)

1998-12-01

The Science Application International Corporation (SAIC) RadStar{trademark} wireless remote radiation monitoring system (WRRMS) is designed to provide real-time monitoring of the radiation dose to workers as they perform work in radiologically contaminated areas. WRRMS can also monitor dose rates in a room or area. The system uses radio-frequency communications to transmit dose readings from the wireless dosimeters worn by workers to a remote monitoring station that can be located out of the contaminated area. Each base station can monitor up to 16 workers simultaneously. The WRRMS can be preset to trigger both audible and visual alarms at certain dose rates. The alarms are provided to the worker as well as the base station operator. This system is particularly useful when workers are wearing personal protective clothing or respirators that make visual observation of their self-reading dosimeters (SRDs), which are typically used to monitor workers, more difficult. The base station is an IBM-compatible personal computer that updates and records information on individual workers every ten seconds. Although the equipment costs for this improved technology are higher than the SRDs (amortized at $2.54/hr versus $1.02/hr), total operational costs are actually less ($639/day versus $851/day). This is because the WRRMS requires fewer workers to be in the contaminated zone than the traditional (baseline) technology. There are also intangible benefits associated with improved worker safety and as low as reasonably achievable (ALARA) principles, making the WRRMS an attractive alternative to the baseline technology. The baseline technology measures only integrated dose and requires workers to check their own dosimeters manually during the task.

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

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.

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)

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

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)

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.)

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

CERN Document Server

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

2014-01-01

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

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

Nevada National Security Site 2012 Waste Management Monitoring Report Area 3 and Area 5 Radioactive Waste Management Site

Energy Technology Data Exchange (ETDEWEB)

Hudson, David B.

2013-09-10

Environmental monitoring data are collected at and around the Area 3 and Area 5 Radioactive Waste Management Sites (RWMSs) at the Nevada National Security Site (NNSS). These data are associated with radiation exposure, air, groundwater, meteorology, and vadose zone. This report summarizes the 2012 environmental data to provide an overall evaluation of RWMS performance and to support environmental compliance and performance assessment (PA) activities. Some of these data (e.g., radiation exposure, air, and groundwater) are presented in other reports (National Security Technologies, LLC, 2012; 2013a; 2013b). Direct radiation monitoring data indicate exposure levels at the RWMSs are within the range of background levels measured at the NNSS. Slightly elevated exposure levels outside the Area 3 RWMS are attributed to nearby historical aboveground nuclear weapons tests. Air monitoring data show tritium concentrations in water vapor and americium and plutonium concentrations in air particles are only slightly above detection limits and background levels. The measured levels of radionuclides in air particulates and moisture are below Derived Concentration Standards for these radionuclides. Groundwater monitoring data indicate the groundwater in the uppermost aquifer beneath the Area 5 RWMS is not impacted by RWMS operations. Results of groundwater analysis from wells around the Area 5 RWMS were all below established investigation levels. Leachate samples collected from the leachate collection system at the mixed low-level waste cell were below established contaminant regulatory limits. The 133.9 millimeters (mm) (5.27 inches [in.]) of precipitation at the Area 3 RWMS during 2012 is 12% below the average of 153.0 mm (6.02 in.), and the 137.6 mm (5.42 in.) of precipitation at the Area 5 RWMS during 2012 is 11% below the average of 122.4 mm (4.82 in.). Water balance measurements indicate that evapotranspiration from the vegetated weighing lysimeter dries the soil and prevents

Nevada National Security Site 2013 Waste Management Monitoring Report Area 3 and Area 5 Radioactive Waste Management Site

Energy Technology Data Exchange (ETDEWEB)

Hudson, D. B. [National Security Technologies, LLC, Las Vegas, NV (United States)

2014-08-01

Environmental monitoring data are collected at and around the Area 3 and Area 5 Radioactive Waste Management Sites (RWMSs) within the Nevada National Security Site (NNSS). These data are associated with radiation exposure, air, groundwater, meteorology, and vadose zone. This report summarizes the 2013 environmental data to provide an overall evaluation of RWMS performance and to support environmental compliance and performance assessment (PA) activities. Some of these data (e.g., radiation exposure, air, and groundwater) are presented in other reports (National Security Technologies, LLC, 2013; 2014a; 2014b). Direct radiation monitoring data indicate exposure levels at the RWMSs are within the range of background levels measured at the NNSS. Slightly elevated exposure levels outside the Area 3 RWMS are attributed to nearby historical aboveground nuclear weapons tests. Air monitoring data show tritium concentrations in water vapor and americium and plutonium concentrations in air particles are close to detection limits and background levels. The measured levels of radionuclides in air particulates and moisture are below Derived Concentration Standards for these radionuclides. Groundwater monitoring data indicate the groundwater in the uppermost aquifer beneath the Area 5 RWMS is not impacted by RWMS operations. Results of groundwater analysis from wells around the Area 5 RWMS were all below established investigation levels. Leachate samples collected from the leachate collection system at the mixed low-level waste cell were below established contaminant regulatory limits. The 105.8 millimeters (mm) (4.17 inches [in.]) of precipitation at the Area 3 RWMS during 2013 is 30% below the average of 150.3 mm (5.92 in.), and the 117.5 mm (4.63 in.) of precipitation at the Area 5 RWMS during 2013 is 5% below the average of 123.6 mm (4.86 in.). Water balance measurements indicate that evapotranspiration from the vegetated weighing lysimeter dries the soil and prevents

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

Remote system for monitoring and control of controlled area of nuclear installation

Energy Technology Data Exchange (ETDEWEB)

Assuncao, Daniel Gomes de; Minhoni, Danilo Carlos Rossetto [Departamento de Ciencias da Administracao e Tecnologia. Centro Universitario de Araraquara (UNIARA) Araraquara, SP (Brazil); Farias, Marcos Sant' anna de; Santos, Isaac J.A. Luquetti dos, E-mail: luquetti@ien.gov.br [Instituto Engenharia Nuclear (IEN/CNEN-RJ), Rio Janeiro, RJ (Brazil). Divisao de Instrumentacao e Confiabilidade Humana

2011-07-01

The maintenance activities in controlled areas of nuclear facilities require adequate planning and control so that these activities do not cause to the worker an undue exposure to radioactivity. For maximum safety of workers from these places, there are standards that determine the maximum radiation dose that a worker can receive. From this context, the objective of this research is to develop a remote system that shows remotely the maintenance tasks being carried out in this work environment; monitors information provided by radiation monitoring devices installed at workplace; tracks the time to carry out scheduled maintenance, reporting alarm if this time is exceeded or not. The system has video camera, radiation monitoring device, interface card to transmit data via ethernet and graphical user interface, developed using the LABVIEW application. The principal objective is to improve the safety and to preserve the worker's health. (author)

Remote system for monitoring and control of controlled area of nuclear installation

International Nuclear Information System (INIS)

Assuncao, Daniel Gomes de; Minhoni, Danilo Carlos Rossetto; Farias, Marcos Sant'anna de; Santos, Isaac J.A. Luquetti dos

2011-01-01

The maintenance activities in controlled areas of nuclear facilities require adequate planning and control so that these activities do not cause to the worker an undue exposure to radioactivity. For maximum safety of workers from these places, there are standards that determine the maximum radiation dose that a worker can receive. From this context, the objective of this research is to develop a remote system that shows remotely the maintenance tasks being carried out in this work environment; monitors information provided by radiation monitoring devices installed at workplace; tracks the time to carry out scheduled maintenance, reporting alarm if this time is exceeded or not. The system has video camera, radiation monitoring device, interface card to transmit data via ethernet and graphical user interface, developed using the LABVIEW application. The principal objective is to improve the safety and to preserve the worker's health. (author)

Nevada Test Site 2008 Waste Management Monitoring Report Area 3 and Area 5 Radioactive Waste Management Sites

International Nuclear Information System (INIS)

2009-01-01

Environmental monitoring data were collected at and around the Area 3 and Area 5 Radioactive Waste Management Sites (RWMSs) at the Nevada Test Site. These data are associated with radiation exposure, air, groundwater, meteorology, vadose zone, subsidence, and biota. This report summarizes the 2008 environmental data to provide an overall evaluation of RWMS performance and to support environmental compliance and performance assessment (PA) activities

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

Directional Radiation Dosimeter for Area and Environmental Monitoring

International Nuclear Information System (INIS)

Manzoli, J.E.; Campos, V.P.; Moura, E.S.

2009-01-01

It is presented a dosimeter that is able to measure the photon exposure and the direction from where the radiation came from. Preliminary measurements performed by this new directional radiation dosimeter demonstrate its application. This dosimeter consists of a small lead cube with thermoluminescent discs on each face, placed in well known coordinates. Only one dosimeter of this kind indicates the direction of the radiation beam, if it came from a unique position. This study was conducted inside the radiation room of a Cobalt-60 Gamma Irradiator and the dosimeter indicated the source position

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)

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

Nevada National Security Site 2015 Waste Management Monitoring Report Area 3 and Area 5 Radioactive Waste Management Sites

International Nuclear Information System (INIS)

Black, David; Hudson, David

2016-01-01

Environmental monitoring data are collected at and around the Area 3 and Area 5 Radioactive Waste Management Sites (RWMSs) within the Nevada National Security Site (NNSS). These data include direct radiation exposure, as well as radiation from the air, groundwater, meteorology, and vadose zone. This report summarizes the 2015 environmental data to provide an overall evaluation of RWMS performance and to support environmental compliance and performance assessment (PA) activities. Some of these data (e.g., radiation exposure, air, and groundwater) are presented in other reports developed by National Security Technologies, LLC. Direct radiation monitoring data indicate exposure levels at the RWMSs are within the range of background levels measured at the NNSS. Slightly elevated exposure levels outside the Area 3 RWMS are attributed to nearby historical aboveground nuclear weapons tests. Air monitoring data show that tritium concentrations in water vapor and americium and plutonium concentrations in air particles are below Derived Concentration Standards for these radionuclides. Groundwater monitoring data indicate the groundwater in the uppermost aquifer beneath the Area 5 RWMS is not impacted by RWMS operations. Results of groundwater analysis from wells around the Area 5 RWMS were all below established investigation levels. Leachate samples collected from the leachate collection system at the mixed low-level waste cell were below established contaminant regulatory limits. During 2015, precipitation at the Area 3 RWMS was 0.9% above average, and precipitation at the Area 5 RWMS was 25% above average. Water balance measurements indicate that evapotranspiration from the vegetated weighing lysimeter dries the soil and prevents downward percolation of precipitation more effectively than evaporation as measured from the bare-soil weighing lysimeter. The 1.8 inches of precipitation in September reached the lowest sensors at 180 cm on the Cell 5S and 5N covers, however the

Nevada National Security Site 2015 Waste Management Monitoring Report Area 3 and Area 5 Radioactive Waste Management Sites

Energy Technology Data Exchange (ETDEWEB)

Black, David [National Security Technologies, LLC. (NSTec), Mercury, NV (United States); Hudson, David [National Security Technologies, LLC. (NSTec), Mercury, NV (United States)

2016-08-20

Environmental monitoring data are collected at and around the Area 3 and Area 5 Radioactive Waste Management Sites (RWMSs) within the Nevada National Security Site (NNSS). These data include direct radiation exposure, as well as radiation from the air, groundwater, meteorology, and vadose zone. This report summarizes the 2015 environmental data to provide an overall evaluation of RWMS performance and to support environmental compliance and performance assessment (PA) activities. Some of these data (e.g., radiation exposure, air, and groundwater) are presented in other reports developed by National Security Technologies, LLC. Direct radiation monitoring data indicate exposure levels at the RWMSs are within the range of background levels measured at the NNSS. Slightly elevated exposure levels outside the Area 3 RWMS are attributed to nearby historical aboveground nuclear weapons tests. Air monitoring data show that tritium concentrations in water vapor and americium and plutonium concentrations in air particles are below Derived Concentration Standards for these radionuclides. Groundwater monitoring data indicate the groundwater in the uppermost aquifer beneath the Area 5 RWMS is not impacted by RWMS operations. Results of groundwater analysis from wells around the Area 5 RWMS were all below established investigation levels. Leachate samples collected from the leachate collection system at the mixed low-level waste cell were below established contaminant regulatory limits. During 2015, precipitation at the Area 3 RWMS was 0.9% above average, and precipitation at the Area 5 RWMS was 25% above average. Water balance measurements indicate that evapotranspiration from the vegetated weighing lysimeter dries the soil and prevents downward percolation of precipitation more effectively than evaporation as measured from the bare-soil weighing lysimeter. The 1.8 inches of precipitation in September reached the lowest sensors at 180 cm on the Cell 5S and 5N covers, however the

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

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

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...

Offsite environmental monitoring report. Radiation monitoring around United States nuclear test areas, calendar year 1980

International Nuclear Information System (INIS)

Smith, D.D.; Grossman, R.F.; Corkern, W.D.; Thome, D.J.; Patzer, R.G.; Hopper, J.L.

1981-06-01

The US Environmental Protection Agency's (EPA) Environmental Monitoring Systems Laboratory in Las Vegas (EMSL-LV) continued its Offsite Radiological Safety Program for the Nevada Test Site (NTS) and other sites of past underground nuclear tests. For each test, the Laboratory provided airborne meteorological measurements, ground and airborne radiation monitoring teams, and special briefings to the Test Controller's Advisory Panel. Test-related radioactivity from the NTS was detected offsite following the Riola Test conducted on September 25, 1980. This consisted of xenon-133 (3.4 x 10 -11 μCi/m1) and xenon-135 (3.6 x 10 -10 μCi/m1) in a compressed air sample collected at Lathrop Wells, Nevada. The estimated dose equivalent to the whole body of a hypothetical receptor at Lathrop Wells from exposure to the radioxenon was 0.011 mrem, which is 0.006 percent of the radiation protection guide for a suitable sample of the general population. Whole-body counts of individuals residing in the environs of the NTS showed no manmade radionuclides attributable to the testing program. The only radioactivity from non-NTS sites of past underground nuclear tests was due to tritium in water samples collected from the Project Dribble Site near Hattiesburg, Mississippi, and the Project Long Shot Site on Amchitka Island, Alaska. The maximum concentrations measured at these locations were 1 and 0.1 percent of the Concentration Guide for drinking water, respectively. A small amount of airborne radioactivity originating from nuclear tests carried out by the People's Republic of China was detected during 1980 at some stations scattered throughout the Air Surveillance Network. The Laboratory's Animal Investigation Program sampled tissues from wildlife and domestic animals on and around the NTS. Data from analysis of these tissues are published separately in an annual report

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

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

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

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

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.

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

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

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

Development of a portable system to test area monitors for neutrons

International Nuclear Information System (INIS)

Souza, Luciane de Rezende

2011-02-01

The objective is to develop a portable system to test the reliability in terms of calibration of area monitors for neutrons. For the production of this system, thickness and location of the source within the system were simulated using the code of radiation transport MCNP5. The thicknesses were set for a 241 Am-Be source with an activity of 395 mCi, which will be in a polyethylene cylinder which will provide a ambient dose equivalent rate chosen through the points of calibration settings' used by the Laboratory of Neutrons (IRD / CNEN). The results obtained in this study show the feasibility of mounting the portable system as a tool to test the area monitors for neutrons, which will provide the user of neutron area monitors to check the instrument's response in the same field of operation, thus avoiding the use of an inadequate equipment. (author)

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

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

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.)

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.)

Experience in organizing and operating of local centers of radiation monitoring in Belarus

International Nuclear Information System (INIS)

Nesterenko, V.B.; Devojno, A.N.

1993-01-01

The paper analyzes the experience in the arrangement and activity of local centres for the radiation monitoring of foods and of articles of daily use established under the control of the rural and urban area administrations at the contaminated territories. The measurement results obtained by the local centres show the deep contamination of food from the local farms and from the local fields and forests, in particular, milk, ferries and mushrooms. RAPIT information system was established automate the processing and analyse of data from the local centres of the radiation monitoring

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

Environmental radiation monitoring plan for depleted uranium and beryllium areas, Yuma Proving Ground

International Nuclear Information System (INIS)

Ebinger, M.H.; Hansen, W.R.

1994-01-01

This Environmental Radiation Monitoring Plan (ERM) discusses sampling soils, vegetation, and biota for depleted uranium (DU) and beryllium (Be) at Yuma Proving Ground (YPG). The existing ERM plan was used and modified to more adequately assess the potential of DU and Be migration through the YPG ecosystem. The potential pathways for DU and Be migration are discussed and include soil to vegetation, soil to animals, vegetation to animals, animals to animals, and animals to man. Sample collection will show DU deposition and will be used to estimate DU migration. The number of samples from each area varies and depends on if the firing range of interest is currently used for DU testing (GP 17A) or if the range is not used currently for DU testing (GP 20). Twenty to thirty-five individual mammals or lizards will be sampled from each transect. Air samples and samples of dust in the air fall will be collected in three locations in the active ranges. Thirty to forty-five sediment samples will be collected from different locations in the arroys near the impact areas. DU and Be sampling in the Hard Impact and Soft Impact areas changed only slightly from the existing ERM. The modifications are changes in sample locations, addition of two sediment transport locations, addition of vegetation samples, mammal samples, and air sampling from three to five positions on the impact areas. Analysis of samples for DU or total U by inductively-coupled mass spectroscopy (ICP/MS), cc spectroscopy, neutron activation analysis (NAA), and kinetic phosphorimetric analysis (KPA) are discussed, and analysis for Be by ICP/MS are recommended. Acquiring total U (no isotope data) from a large number of samples and analysis of those samples with relatively high total U concentrations results in fewer isotopic identifications but more information on U distribution. From previous studies, total U concentrations greater than about 3 times natural background are usually DU by isotopic confirmation

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.

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

International Nuclear Information System (INIS)

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

2001-01-01

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

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

RADIATION HYGIENIC MONITORING AND ASSESSMENT OF POPULATION DOSES IN RADIOACTIVELY CONTAMINATED AREAS OF TULA REGION

Directory of Open Access Journals (Sweden)

T. M. Chichura

2016-01-01

Full Text Available The goal. The analyses of radiation hygienic monitoring conducted in Tula region territories affected by the Chernobyl NPP accident regarding cesium-137 and strontium- 90 in the local foodstuffs and the analyses of populational annual effective dose. The materials and methods. The survey was conducted in Tula Region since 1997 to 2015. Over that period, more than fifty thousand samples of the main foodstuffs from the post-Chernobyl contaminated area were analyzed. Simultaneously with that, the external gamma - radiation dose rate was measured in the fixed control points. The dynamics of cesium -137 and strontium-90 content in foodstuffs were assessed along with the maximum values of the mean annual effective doses to the population and the contribution of the collective dose from medical exposures into the structure of the annual effective collective dose to the population. The results. The amount of cesium-137 and strontium -90 in the local foodstuffs was identified. The external gamma- radiation dose rate values were found to be stable and not exceeding the natural fluctuations range typical for the middle latitudes of Russia’s European territory. The maximum mean annual effective dose to the population reflects the stable radiation situation and does not exceed the permissible value of 1 mSv. The contribution of the collective dose from medical exposures of the population has been continuously reducing as well as the average individual dose to the population per one medical treatment under the annual increase of the medical treatments quantities. The conclusion. There is no exceedance of the admissible levels of cesium-137 and strontium- 90 content in the local foodstuffs. The mean annual effective dose to the population has decreased which makes it possible to transfer the settlements affected by the Chernobyl NPP accident to normal life style. This is covered by the draft concept of the settlements’ transfer to normal life style.

Android Based Area Web Monitoring

Science.gov (United States)

Kanigoro, Bayu; Galih Salman, Afan; Moniaga, Jurike V.; Chandra, Eric; Rezky Chandra, Zein

2014-03-01

The research objective is to develop an application that can be used in the monitoring of an area by using a webcam. It aims to create a sense of security on the user's application because it can monitor an area using mobile phone anywhere. The results obtained in this study is to create an area with a webcam monitoring application that can be accessed anywhere as long as the monitoring results have internet access and can also be accessed through Android Based Mobile Phone.

Android Based Area Web Monitoring

Directory of Open Access Journals (Sweden)

Kanigoro Bayu

2014-03-01

Full Text Available The research objective is to develop an application that can be used in the monitoring of an area by using a webcam. It aims to create a sense of security on the user's application because it can monitor an area using mobile phone anywhere. The results obtained in this study is to create an area with a webcam monitoring application that can be accessed anywhere as long as the monitoring results have internet access and can also be accessed through Android Based Mobile Phone.

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.)

The Department of Energy Nevada Test Site Remote Area Monitoring System

International Nuclear Information System (INIS)

Sanders, L.D.; Hart, O.F.

1993-01-01

The Remote Area Monitoring System was developed by Los Alamos National Laboratory (LANL) for DOE test directors at the Nevada Test Site (NTS) to verify radiological conditions are safe after a nuclear test. In the unlikely event of a venting as a result of a nuclear test, this system provides radiological and meteorological data to Weather Service Nuclear Support Office (WSNSO) computers where mesoscale models are used to predict downwind exposure rates. The system uses a combination of hardwired radiation sensors and satellite based data acquisition units with their own radiation sensors to measure exposure rates in remote areas of the NTS. The satellite based data acquisition units are available as small, Portable Remote Area Monitors (RAMs) for rapid deployment, and larger, Semipermanent RAMs that can have meteorological towers. The satellite based stations measure exposure rates and transmit measurements to the GOES (Geostationary Operational Environmental Satellite) where they are relayed to Direct Readout Ground Stations (DRGS) at the NTS and Los Alamos. Computers process the data and display results in the NTS Operations Coordination Center. Los Alamos computers and NTS computers are linked together through a wide area network, providing remote redundant system capability. Recently, LANL, expanded the system to take radiological and meteorological measurements in communities in the western United States. The system was also expanded to acquire data from Remote Automatic Weather Stations (RAWS) that transmit through GOES. The addition of Portable and Semipermanent RAMs to the system has vastly expanded monitoring capabilities at NTS and can be used to take measurements anywhere in this hemisphere

Survey monitoring of environmental radioactivity in Daegu area

Energy Technology Data Exchange (ETDEWEB)

Kang, H. D.; Lee, S. Y. [Kyungpook National Univ., Daegu (Korea, Republic of)

1998-01-15

The objectives of the project are to monitor an abnormal radiation level in Taegu and Kyungpook region, and to enhance our ability to prepare for the radiological emergency situation by establishing the radioactivity monitoring system in Taegu and Kyungpook region. Gross beta activities were measured and gamma radionuclides were analysed for the environmental samples of air-borned dust. precipitation. fallout and drinking water collected in Taegu radioactivity monitoring center. and gamma exposure rates were also measured. To establish the basic data base on the environmental radioactivity, gamma radionuclide analyses were carried out for the samples of soil, drinking water, grain, vegetable, milk, and fish which were obtained from 31 different areas, and the spatial gamma exposure rates from 61 different points were also measured in Taegu and Kyungpook region. In conclusion, it didn't appear any evidence for newly pollution of artificial radioactivity in Taegu and Kyungpook region.

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.

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

Rock Burst Monitoring by Integrated Microseismic and Electromagnetic Radiation Methods

Science.gov (United States)

Li, Xuelong; Wang, Enyuan; Li, Zhonghui; Liu, Zhentang; Song, Dazhao; Qiu, Liming

2016-11-01

For this study, microseismic (MS) and electromagnetic radiation (EMR) monitoring systems were installed in a coal mine to monitor rock bursts. The MS system monitors coal or rock mass ruptures in the whole mine, whereas the EMR equipment monitors the coal or rock stress in a small area. By analysing the MS energy, number of MS events, and EMR intensity with respect to rock bursts, it has been shown that the energy and number of MS events present a "quiet period" 1-3 days before the rock burst. The data also show that the EMR intensity reaches a peak before the rock burst and this EMR intensity peak generally corresponds to the MS "quiet period". There is a positive correlation between stress and EMR intensity. Buckling failure of coal or rock depends on the rheological properties and occurs after the peak stress in the high-stress concentration areas in deep mines. The MS "quiet period" before the rock burst is caused by the heterogeneity of the coal and rock structures, the transfer of high stress into internal areas, locked patches, and self-organized criticality near the stress peak. This study increases our understanding of coal and rock instability in deep mines. Combining MS and EMR to monitor rock burst could improve prediction accuracy.

Radiation protection and ambient radioactivity monitoring in the area of the Asse mine. Annual report 1997

International Nuclear Information System (INIS)

Meyer, H.; Stippler, R.

1998-01-01

The number of annual sampling and measurements performed in compliance with the operator's monitoring duties have been the same as last year: 364. All measured radioactivity values were at the level of natural environmental radioactivity. Some samples and measurements reflected the fallout from former atmospheric nuclear weapons tests and the accident at the Chernobyl reactor. Personnel dosimetry was performed according to legal requirements of the Radiation Protection Ordinance, as were measurements for the monitoring of ambient doses, dose rates and radioactivity levels in the air of the mine structures. All measured values were below the maximum permissible personal doses and occupational dose limits. Ambient air measurements in the salt mine as in the preceding years detected low amounts of the nuclides H 3, C 14, Pb 210, and the short-lived daughter products of Rn 222 and Rn 220. The calculated radioactivity concentrations in the vicinity of the mine, derived from averaged annual effluents, to some part were below the average natural concentrations of the nuclides. The effluent-induced radiation dose at the most affected location was far below the limits set by the Radiation Protection Ordinance. (orig./CB) [de

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.)

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

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.)

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

The concept of an information analytical system monitoring of radiation situation and social-hygienic life conditions for residents in the areas influenced by Mayak production association (MPA)

International Nuclear Information System (INIS)

Kravtsova, E.M.; Kravtsova, O.S.

1996-01-01

The development of computerized informational-analytical system is started with the purpose to organize monitoring and to estimate radiation effect on population residing in the zone affected by MPA (1992). The data base includes a special information block containing social-economic characteristics. A specific feature of the method used to create the data base is the focus on the family connections. Currently the block meant for registration of environmental monitoring, in residential areas around Mayak plants has been developed most completely

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

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

CERN Document Server

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

2018-01-01

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

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

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)

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

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)

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)

Incidence of neural tube defects in the natural radiation coastal areas of Kerala

International Nuclear Information System (INIS)

Jaikrishan, G.; Sudheer, K.R.; Andrews, V.J.; Koya, P.K.M.; Cheriyan, V.D.; Seshadri, M.

2010-01-01

All consecutive births in selected government hospitals in and around the high level natural background radiation areas (HLNRA) of Kerala were monitored for congenital malformations observable at birth since 1995. The HLNR area, a coastal strip of land about 55 km in length and 0.5 km in breadth from Purakkad in the north in Alleppey district to Sakthikulangara in the south of Quilon district, stands out among the most prominent background radiation areas of the world. Natural deposit of monazite sand, containing Thorium (8-10%), Uranium (0.3%) and corresponding decay products, is the source of elevated background radiation, ranging from < 1 to 45 mGy/year. Wide variation in dose, due to the patchy and non-uniform distribution of Monazite sand, enables in built controls. High population density, limited migration, ethnic diversity, good literacy, health awareness, institutionalized births and acceptance of small family norm are some of the key features of the population. Areas with a mean radiation dose of more than 1.5 mGy/year were treated as HLNR areas and areas with a dose level of 1.5 mGy/year or less were treated as normal level radiation (NLNR) areas. The study carried out since 1995 does not seem to implicate HLNR in the incidence of neural tube defects among newborns

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)

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)

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)

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

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.)

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.)

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

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)

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

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

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.

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

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

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)

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,...

Coping with radiation measurement in Hippo area of Marumori Town, Miyagi Prefecture

International Nuclear Information System (INIS)

Yoshizawa, Takeshi

2013-01-01

The series is to report how general people, who are not at all radiological experts, have faced and understood the problems and tasks of radiation given by the Fukushima Daiichi Nuclear Power Plant Accident (Mar. 2011). The section 1 reports the process of its title and present status of the Hippo area. The area localizes at the most southern zone of Miyagi prefecture, borders on Fukushima and is 50 km distant from the Plant. Rapidly after the Accident, they required the precise measurement of ambient dose in the area, but it was 2 months later that it was conducted by Marumori Town office. The dose was found to much exceed 1 mc-Sv/h, being far higher than the dose reported by Miyagi prefecture. The monitoring was restricted at ten-odd fixed sites in the area as large as 75 km 2 , which was unsatisfactory for all residents who lived in houses scattered among hills. Accordingly, the author's area association bought GM-counters through internet, lent them, and also made a map of dose distribution at 137 spots along the roads covering the whole area to be passed out to all houses in July. This conceivably helped for them to learn their positioning in the radiation environment and how to live. In addition, the association could get (July 2012) an instrument (ATOMTEX, AT1320A, made in Belarus) for food monitoring on donations from past and present residents as the Town office, where the monitoring had been done, was too far from the area and had refused the economical assistance. The use of the machine was (still, is) difficult, and the speculation of data, sometimes more: however, the food monitoring is now essential for residents to live safely and easily. The author thinks that self-help is not desirable and hopes the wider means should be taken beyond the administrative border. (T.T.)

Data Quality Objectives Supporting the Environmental Direct Radiation Monitoring Program for the INL Site

Energy Technology Data Exchange (ETDEWEB)

Lundell, J. F. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Magnuson, S. O. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Scherbinske, P. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Case, M. J. [Idaho National Lab. (INL), Idaho Falls, ID (United States)

2015-07-01

This document presents the development of the data quality objectives (DQOs) for the Idaho National Laboratory (INL) Environmental Direct Radiation Monitoring Program and follows the Environmental Protection Agency (EPA) DQO process (EPA 2006). This document also develops and presents the logic to determine the specific number of direct radiation monitoring locations around INL facilities on the desert west of Idaho Falls and in Idaho Falls, at locations bordering the INL Site, and in the surrounding regional area. The selection logic follows the guidance from the Department of Energy (DOE) (2015) for environmental surveillance of DOE facilities.

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.)

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

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

Energy Technology Data Exchange (ETDEWEB)

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 Prepared on behalf of the Visiting Ship Panel (Nuclear), Department of Defence; 11 refs., 11 tabs., 21 figs.

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

Science.gov (United States)

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

2018-02-01

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

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)

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...

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.

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)

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)

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.

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

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)

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)

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

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.

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...

Monitoring the radiation dose to a multiprogrammable pacemaker during radical radiation therapy: A case report

International Nuclear Information System (INIS)

Muller-Runkel, R.; Orsolini, G.; Kalokhe, U.P.

1990-01-01

Multiprogrammable pacemakers, using complimentary metaloxide semiconductor (CMOS) circuitry, may fail during radiation therapy. We report about a patient who received 6,400 cGy for unresectable carcinoma of the left lung. In supine treatment position, arms raised above the head, the pacemaker was outside the treated area by a margin of at least 1 cm, shielded by cerrobend blocking mounted on a tray. From thermoluminescent dosimeter (TLD) measurements, we estimate that the pacemaker received 620 cGy in scatter doses. Its function was monitored before, during, and after completion of radiation therapy. The pacemaker was functioning normally until the patient's death 5 months after completion of treatment. The relevant electrocardiograms (ECGs) are presented

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)

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)

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)

Pneumatic radiator of transition radiation for large working area arrangements

International Nuclear Information System (INIS)

Shikhlyarov, K.K.; Gavalyan, V.G.

1993-01-01

An unconventional approach to the constructions of large area regular radiator of X-rays transition radiation is proposed based on the use of a pack of hermetically sealed bags, in which elastic helium layers are formed. A prototype of such a radiator of about 1m 2 area was made for test of the proposed device. 9 refs

[RADIATION HYGIENIC MONITORING AT THE AREA OF THE LOCATION OF THE FAR EASTERN CENTER FOR RADIOACTIVE WASTE MANAGEMENT (FEC "DALRAO"--BRANCH OF FSUE "ROSRAO")].

Science.gov (United States)

Kiselev, S M; Shandala, N K; Akhromeev, S V; Gimadova, T I; Seregin, V A; Titov, A V; Biryukova, N G

2015-01-01

Intensification ofactivities in the field of spent nuclear fuel (SNF) and radioactive waste (RW) management in the Far East region of Russia assumes an increase of the environmental load on the territories adjacent to the enterprise and settlements. To ensure radiation safety during works on SNF and radioactive waste management in the standard mode of operation and during the rehabilitation works in the contaminated territories, there is need for the optimization of the existing system of radiation-hygienic monitoring, aimed at the implementation of complex dynamic observation of parameters of radiation-hygienic situation and radiation amount of the population living in the vicinity of the Far Eastern Center for Radioactive Waste Management (FEC "DALRAO"). To solve this problem there is required a significant amount of total and enough structured information on the character of the formation of the radiation situation, the potential ways of the spread of man-made pollution to the surrounding area, determining the radiation load on the population living in the vicinity of the object. In this paper there are presented the results of field studies of the radiation situation at the plant FEC "DALRAO", which were obtained during the course of expedition trips in 2009-2012.

Community Radiation Monitoring Program annual report, October 1, 1987--September 30, 1988

International Nuclear Information System (INIS)

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

1989-03-01

In addition to enhancing and augmenting the collection of airborne radiation data from communities close-in to the test site, something that could easily be done with automated equipment, the Community Radiation Monitoring Program seeks to involve local residents of those areas. That is accomplished in two ways: hiring intelligent, well-respected members of the community as Station Managers and Alternates and providing them the training they need to respond to community concerns and questions; and then getting out to those and surrounding communities and holding meetings that serve not just as a forum for DOE and EPA spokesmen, but as a chance for concerned citizens to receive honest and credible answers to questions they might have. The Community Radiation Monitoring Program is, after more than seven years, sound and in focus. Continuous enhancements and ''fine tuning'' will serve to improve its ability to serve the people who live in communities surrounding the Nevada Test Site. 11 refs., 3 figs., 3 tabs

Offsite environmental monitoring report. Radiation monitoring around United States nuclear test areas, calendar year 1981

International Nuclear Information System (INIS)

Black, S.C.; Grossman, R.F.; Mullen, A.A.; Potter, G.D.; Smith, D.D.; Hopper, J.L.

1982-08-01

This report, prepared in accordance with the guidelines in DOE/E-0023 (DOE 1981), covers the program activities conducted around Nevada Test Site (NTS) for calendar year 1981. It contains descriptions of pertinent features of the NTS and its environs, summaries of the dosimetry and sampling methods, analytical procedures, and the analytical results from environmental measurements. Where applicable, dosimetry and sampling data are compared to appropriate guides for external and internal exposures of humans to ionizing radiation. The monitoring networks detected no radioactivity in the various media which could be attributed to US nuclear testing. Small amounts of fission products were detected in air samples as a result of the People's Republic of China nuclear test and atmospheric krypton-85 increased, following the trend beginning in 1960, due to increased use of nuclear technology. Strontium-90 in milk and cesium-137 in meat samples continued the slow decline as observed for the last several years

Offsite environmental monitoring report. Radiation monitoring around United States nuclear test areas, calendar year 1981

Energy Technology Data Exchange (ETDEWEB)

Black, S.C.; Grossman, R.F.; Mullen, A.A.; Potter, G.D.; Smith, D.D.; Hopper, J.L. (comps.)

1982-08-01

This report, prepared in accordance with the guidelines in DOE/E-0023 (DOE 1981), covers the program activities conducted around Nevada Test Site (NTS) for calendar year 1981. It contains descriptions of pertinent features of the NTS and its environs, summaries of the dosimetry and sampling methods, analytical procedures, and the analytical results from environmental measurements. Where applicable, dosimetry and sampling data are compared to appropriate guides for external and internal exposures of humans to ionizing radiation. The monitoring networks detected no radioactivity in the various media which could be attributed to US nuclear testing. Small amounts of fission products were detected in air samples as a result of the People's Republic of China nuclear test and atmospheric krypton-85 increased, following the trend beginning in 1960, due to increased use of nuclear technology. Strontium-90 in milk and cesium-137 in meat samples continued the slow decline as observed for the last several years.

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)

Fault diagnosis method for area gamma monitors in Nuclear Facilities

International Nuclear Information System (INIS)

Srinivas Reddy, P.; Amudhu Ramesh Kumar, R.; Geo Mathews, M.; Amarendra, G.

2016-01-01

Area Gamma Monitors (AGM) using Geiger-Muller (GM) counter are deployed in nuclear facilities for detection of gamma radiation. The AGMs display the dose rate locally and in Data Acquisition System (DAS) at central monitoring station. It also provides local visual and audio alarms in case of dose rate exceeding alarm set point. Regular surveillance checking, testing and calibration of AGMs are mandatory as per safety guidelines. This paper describes quick testing the AGMs without using radioactive source. The four point High Voltages (HV) and Discriminator Bias (DB) voltage characteristics are used to diagnose the state of health of GM counter. The profiles of HV and DB voltage are applied during testing of the AGMs

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

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

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

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

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

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

International Nuclear Information System (INIS)

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

2011-01-01

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

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

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

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).

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

Radioactive surface contamination monitors

International Nuclear Information System (INIS)

Aoyama, Kei; Minagoshi, Atsushi; Hasegawa, Toru

1994-01-01

To reduce radiation exposure and prevent contamination from spreading, each nuclear power plant has established a radiation controlled area. People and articles out of the controlled area are checked for the surface contamination of radioactive materials with surface contamination monitors. Fuji Electric has repeatedly improved these monitors on the basis of user's needs. This paper outlines typical of a surface contamination monitor, a personal surface contamination monitor, an article surface contamination monitor and a laundry monitor, and the whole-body counter of an internal contamination monitor. (author)

Chernobyl'-92. Reports of the 3. All-Union scientific and technical meeting on results of accident effect elimination at the Chernobyl' NPP. V. 1. Radiation monitoring. Migration of radionuclides in environment. Part 2

International Nuclear Information System (INIS)

Senin, E.V.

1992-01-01

Section Radiation monitoring comprises: atlas of area radioactive contamination as a result of the Chernobyl' NPP accident, state of automated radiation monitoring control system, hydrological monitoring, radiation situation in different areas, problems of radiation monitoring and protection of water objects, methods for determining radionuclidescontents, radiochemical mechanisms of radionuclide migration mobility in the Chernobyl' effluents, the results of investigations into migration of radionuclides in soils, landscapes, bottom depositions, in the soil-plant chain

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)

The importance of geoprocessing tools in radiometric monitoring of large areas

Energy Technology Data Exchange (ETDEWEB)

Dias, Danila Carrijo da Silva [Universidade Federal de Alfenas (UNIFAL), Pocos de Caldas, MG (Brazil); Comissao Nacional de Energia Nuclear (LAPOC/CNEN-MG), Pocos de Caldas, MG (Brazil). Lab. de Pocos de Caldas; Silva, Nivaldo Carlos da; Alberti, Heber Luiz Caponi; Guerrero, Eder Tadeu Zenun, E-mail: ncsilva@cnen.gov.b, E-mail: heber@cnen.gov.b, E-mail: edertzg@cnen.gov.b [Comissao Nacional de Energia Nuclear (LAPOC/CNEN-MG), Pocos de Caldas, MG (Brazil). Lab. de Pocos de Caldas

2011-07-01

Throughout history, the natural tendency of men to physically characterize their different surroundings has played an important role on the evolution of societies. Today, that tendency combined to the development of computer technologies, has allowed the accelerated growth of the Geographical Information Systems, which permits the analysis and manipulation of spatial data from diverse sources, producing geo referenced databases. The gamma radiation, one of the main contributors of human exposure to natural radiation, is known for its high penetration energy. Today, the environmental gamma radiation is measured through radiometric tracking mobile units, allowing large scale samplings and precise assessments. As a geo processing case study, a radiometric monitoring work was conducted in the town of Aguas da Prata-SP using a tracking mobile system, composed by a scintillator detector, a GPS and a computer, all installed in a vehicle. The data made of collected points and their respective doses and geographical references were captured and stored in a computer software and then inserted and treated in a GIS environment. After a cartographic base was created using a digitalized map of Aguas da Prata, the sampled points were plotted and interpolated with the cartographic base, producing two maps that demonstrate the tracking route and the gamma radiation dose range throughout the monitored area. Geo processing tools have shown great efficiency in this study, allowing agile manipulation and management of a large quantity of data, thus promoting a spatial analysis of natural radiation levels in the studied region. (author)

The importance of geoprocessing tools in radiometric monitoring of large areas

International Nuclear Information System (INIS)

Dias, Danila Carrijo da Silva; Comissao Nacional de Energia Nuclear; Silva, Nivaldo Carlos da; Alberti, Heber Luiz Caponi; Guerrero, Eder Tadeu Zenun

2011-01-01

Throughout history, the natural tendency of men to physically characterize their different surroundings has played an important role on the evolution of societies. Today, that tendency combined to the development of computer technologies, has allowed the accelerated growth of the Geographical Information Systems, which permits the analysis and manipulation of spatial data from diverse sources, producing geo referenced databases. The gamma radiation, one of the main contributors of human exposure to natural radiation, is known for its high penetration energy. Today, the environmental gamma radiation is measured through radiometric tracking mobile units, allowing large scale samplings and precise assessments. As a geo processing case study, a radiometric monitoring work was conducted in the town of Aguas da Prata-SP using a tracking mobile system, composed by a scintillator detector, a GPS and a computer, all installed in a vehicle. The data made of collected points and their respective doses and geographical references were captured and stored in a computer software and then inserted and treated in a GIS environment. After a cartographic base was created using a digitalized map of Aguas da Prata, the sampled points were plotted and interpolated with the cartographic base, producing two maps that demonstrate the tracking route and the gamma radiation dose range throughout the monitored area. Geo processing tools have shown great efficiency in this study, allowing agile manipulation and management of a large quantity of data, thus promoting a spatial analysis of natural radiation levels in the studied region. (author)

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.)

Biological effects of low-dose radiation on human population living in high-background radiation areas of Kerala coast

International Nuclear Information System (INIS)

Das, Birajalaxmi

2016-01-01

High-level natural radiation areas (HLNRA) of Kerala coast is densely populated and known for its wide variation in background radiation dose levels due to uneven distribution of monazite in the beach sand. The background radiation dose varies from 1 to 45 mGv/y. The areas with >1.5mGy/y is considered as HLNRA. Human population inhabiting in this area are exposed to low-dose chronic radiation since generations. Hence, this population provides an ideal situation to study dose response and adaptive response, if any, due to natural chronic low-dose exposure. It has been investigated extensively to study the biological and health effects of long-term low-dose/low-dose radiation exposure. So far over 150, 000 newborns monitored from hospital-based study did not reveal any significant difference in the incidence of any of the malformations and stillbirth between HLNRA and adjacent control areas. A case-control study on cleft lip/palate and mental retardation did not show any association with background radiation dose. Cytogenetic investigation of over 27,000 newborns did not show any significant increase in the frequency of chromosome aberrations and karyotype anomalies. DNA damage endpoints, such as micronuclei, telomere length and DNA strand breaks, did not reveal any significant difference between control and exposed population. Studies on DNA damage and repair revealed efficient repair of DNA strand breaks in HLNRA individuals. Molecular studies using high throughput microarray analysis indicated a large number of genes involved in various molecular and cellular pathways. Indications of in vivo radioadaptive response due to natural chronic low-dose exposure in this population have important implications to human health. (author)

Survey monitoring of environmental radioactivity in Jeju area

Energy Technology Data Exchange (ETDEWEB)

U, Zang Kual; Kang, Tae Woo; Park, Won Pyo [Jeju National Univ., Jeju (Korea, Republic of)

2003-12-15

The project is carried out to monitor the change of environmental radioactivity in Jeju, and to provide a systematic data for radiation monitoring and counter measurement at a radiological emergency situation. Also the survey of natural environmental radioactivities in the samples was conducted to make the reliable data base for evaluation of internal exposure and environmental contamination of radiation. This report contains the data of gamma exposure rates and radioactivities of airborne dust, fallout, precipitation and tap water which were analyzed periodically by Jeju Regional Monitoring Station in 2002. Also it contains the data of natural radioactivity levels of food stuff such as agricultural and marine products, including drinking waters.

Survey monitoring of environmental radioactivity in Jeju area

Energy Technology Data Exchange (ETDEWEB)

U, Z. K.; Oh, S. H. [Jeju National Univ., Jeju (Korea, Republic of)

1998-01-15

The project is carried out to monitor the change of environmental radioactivity in Jeju, and to provide a systematic data for radiation monitoring and counter measurement at a radiological emergency situation. Also the survey of natural environmental radioactivities in the samples was conducted to make the reliable data base for evaluation of internal exposure and environmental contamination of radiation. This report contains the data of gamma exposure rates and radioactivities of airborne dust, fallout, precipitation and tap water which were analyzed periodically by Jeju Regional Monitoring Station in 1997. Also it contains the data of natural radioactivity levels of food stuff such as agricultural and marine products, including drinking waters.

Survey monitoring of environmental radioactivity in Jeju area

Energy Technology Data Exchange (ETDEWEB)

U, Zang Kual; Kang, Tae Woo; Park, Won Pyo [Jeju National Univ., Jeju (Korea, Republic of)

2002-12-15

The project is carried out to monitor the change of environmental radioactivity in Jeju, and to provide a systematic data for radiation monitoring and counter measurement at a radiological emergency situation. Also the survey of natural environmental radioactivities in the samples was conducted to make the reliable data base for evaluation of internal exposure and environmental contamination of radiation. This report contains the data of gamma exposure rates and radioactivities of airborne dust, fallout, precipitation and tap water which were analyzed periodically by Jeju Regional Monitoring Station in 2001. Also it contains the data of natural radioactivity levels of food stuff such as agricultural and marine products, including drinking waters.

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 ...

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

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.

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

Radiological protection and environmental monitoring in the area of the Asse mine

International Nuclear Information System (INIS)

Meyer, H.; Mueller-Lyda, I.

1993-01-01

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

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

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.

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

Energy response of neutron area monitor with silicon semiconductor detector

International Nuclear Information System (INIS)

Kitaguchi, Hiroshi; Izumi, Sigeru; Kobayashi, Kaoru; Kaihara, Akihisa; Nakamura, Takashi.

1993-01-01

A prototype neutron area monitor with a silicon semiconductor detector has been developed which has the energy response of 1 cm dose equivalent recommended by the ICRP-26. Boron and proton radiators are coated on the surface of the silicon semiconductor detector. The detector is set at the center of a cylindrical polyethylene moderator. This moderator is covered by a porous cadmium board which serves as the thermal neutron absorber. Neutrons are detected as α-particles generated by the nuclear reaction 10 B(n,α) 7 Li and as recoil protons generated by the interaction of fast neutrons with hydrogen. The neutron energy response of the monitor was measured using thermal neutrons and monoenergetic fast neutrons generated by an accelerator. The response was consistent with the 1 cm dose equivalent response required for the monitor within ±34% in the range of 0.025 - 15 Mev. (author)

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)

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).

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.)

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.

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.

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)

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

Energy Technology Data Exchange (ETDEWEB)

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

1997-09-01

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

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.

Radiation Protection Control Area Around Baggage Control X-ray Units

International Nuclear Information System (INIS)

Prlic, I.; Radalj, Z.; Milkovic-Kraus, S.; Cerovac, Z.

2003-01-01

The importance of prompt occupational dose reporting rises when dose is received within a short-time interval or when the radiation source suffers any technical failures. Radiation exposure is to be recognized as a private/or group hazard of each person alone. Actual radiation quality of the source is to be taken into account. To optimize the radiological radiation protection Quality Control measurements of the source are done. We have developed digital dosemeters of type ALARA OD2 for external dosimetry to be used for establishing the real pattern of occupational dose delivered to the workers or/and as the (Ort) professional environmental measuring station. We are using dosemeter to define the control areas and areas of concern - point (Ort) around the source. This upgrade to legal obligatory external (film badge) dosimetry will help us to ease defining the professional stuff and working places which are actually exposed to ionising radiation of concern and for which it is necessary to provide legally required, or even additional, occupational health care programme. This means the analysis of exposure situations for specific jobs near the X-ray equipment used for baggage control in the context of carrying out a detailed study for the optimisation of radiation protection. PC data readout from device forms a real time exposure dose rate pattern that proves that any worker or other employee working nearby the baggage X-ray unit is not obliged to undergo any legal occupational monitoring (dosimetry or health) hence the total dose per year will not exceed 1 mSv under the worst working conditions. (author)

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)

CREAM - a Cosmic Radiation Effects and Activation Monitor for space experiments: Pt. 1

International Nuclear Information System (INIS)

Mapper, D.; Stephen, J.H.; Farren, J.; Stimpson, B.P.; Bolus, D.J.; Ellaway, A.M.

1987-12-01

A detailed account is given of the design and construction of the experimental CREAM packages, intended for flight in the mid-deck area of the Space Transport System (Shuttle) Mission in 1986. The complete experiment involved; 1) a self-contained and battery powered activation monitor for measuring energy losses of charged particles; 2) CR-39 and Kapton polymer solid state nuclear track detectors for the detection of ionising particles; 3) metal foils of nickel, titanium and gold for neutron monitoring; and 4) thermoluminescent detectors for dosimetry measurements of the radiation background. The circuit design and detailed functioning of the active monitor is fully described, together with a complete discussion of the principles and operation of the passive monitors. (author)

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)

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.

GSM based real time remote radiation monitoring and mapping system