WorldWideScience

Sample records for radioactivity monitoring prior

  1. Monitoring of covering model of the National radioactive waste repository

    International Nuclear Information System (INIS)

    Jezikova, M.

    2009-01-01

    The subject of this rigorous report is justification of cover model building at radioactive waste repository in Mochovce as a very important engineering barrier preventing significant release of radioactive substances into the environment and providing protection against ionizing radiation. This rigorous report includes a theoretical part, which describes radioactive waste characterization, radioactive waste management and summary of the preliminary activities prior to the building cover model, particularly involving the selection of appropriate variables and parameters and creation of monitoring plan during the long term monitoring for evaluation of this barrier in order to ensure minimization of any leak of radioactive substances from RAW. The next part includes evaluation of the values of parameters and variables to build cover model of RAW in Mochovce during 2006-2008 (author)

  2. Radioactive substances monitoring programme. Report for 1995

    International Nuclear Information System (INIS)

    1995-01-01

    The Radioactive Substances Act 1993 provides for controls to be exercised over the use and keeping of radioactive materials and the accumulation and disposal of radioactive wastes. The Environment Agency (the Agency) has been responsible for administration and enforcement of the Act in England and Wales since its formation on 1 April 1996. Prior to this date the work was undertaken by Her Majesty's Inspectorate of Pollution (HMIP). In support of its regulatory functions HMIP commissioned independent monitoring. This report presents the results from monitoring undertaken in 1995. The 1995 HMIP programme required operators of certain sites to provide samples of their liquid effluents for independent radiochemical analysis. The results provide checks on site operators' returns and insights into their quality assurance (QA) procedures and analytical techniques. The analyses were undertaken by the Laboratory of the Government Chemist (LGC) at its laboratories in Teddington, Middlesex. The programme also included checks on solid low level radioactive waste destined for land disposal at the site operated by British Nuclear Fuels plc (BNFL) at Drigg in Cumbria. (author)

  3. Environmental radioactivity. Measurement and monitoring

    International Nuclear Information System (INIS)

    2009-11-01

    The contribution on environmental radioactivity covers the following issues: natural and artificial radioactivity; continuous monitoring of radioactivity; monitoring authorities and measurement; radioactivity in the living environment; radioactivity in food and feeding stuff; radioactivity of game meat and wild-growing mushrooms; radioactivity in mines; radioactivity in the research center Rossendorf.

  4. Radioactive Plumes Monitoring Simulator

    International Nuclear Information System (INIS)

    Kapelushnik, I.; Sheinfeld, M.; Avida, R.; Kadmon, Y.; Ellenbogen, M.; Tirosh, D.

    1999-01-01

    The Airborne Radiation Monitoring System (ARMS) monitors air or ground radioactive contamination. The contamination source can be a radioactive plume or an area contaminated with radionuclides. The system is based on two major parts, an airborne unit carried by a helicopter and a ground station carried by a truck. The system enables real time measurement and analysis of radioactive plumes as well as post flight processing. The Radioactive Plumes Monitoring Simulator purpose is to create a virtual space where the trained operators experience full radiation field conditions, without real radiation hazard. The ARMS is based on a flying platform and hence the simulator allows a significant reduction of flight time costs

  5. The national scheme for monitoring radioactive fallout in milk

    International Nuclear Information System (INIS)

    Green, B.M.R.

    1979-01-01

    The National Radiological Protection Board, Harwell, assumed responsibility for the national milk monitoring scheme on Jan. 1, 1979. Milk contamination provides a good guide to radioactivity in the British diet. Brief reference is made to U.K. surveys of radioactive fallout in human food prior to January 1979, and current arrangements for the sampling of milk in the U.K. are explained. The milk is analysed for 90 Sr, 137 Cs and stable calcium. Additional samples are collected to check for 131 I or other short-lived isotopes in the event of atmospheric nuclear tests or accidents involving possible releases of radioactivity. (U.K.)

  6. Development of radioactive seawater monitors, 1

    International Nuclear Information System (INIS)

    Fukushima, Masanori

    1989-01-01

    Applicability of some adsorptive materials to monitoring of radioactive seawater is generalized. Studied techniques that allow utilization of adsorptive materials in monitoring radioactive seawater are the substitute methods using sampled seawater or indicator plants such as gulfweed and the method using adsorptive materials for continuous monitoring of underwater radioactivity, the method using them for field measurement of under water radioactivity from a boat, and the method using an adsorptive material moored underwater for integration monitoring of underwater radioactivity. Selected adsorptive materials that were judged suitable for monitoring radioactive seawater is the one composed of some kind of adsorptive compound (manganese dioxide or ferrocyan cobalt potassium) fixed to crylic cellulose. This adsorptive material permits selective scavenging radioactive Cs, Mn, Co, Zn, Ce, Fe, Ru, Ra Th, Pu and Am from seawater. (aurhor)

  7. Monitoring of radioactive wastes

    International Nuclear Information System (INIS)

    Houriet, J.Ph.

    1982-08-01

    The estimation of risks presented by final disposal of radioactive wastes depends, among other things, on what is known of their radioisotope content. The first aim of this report is to present the current state of possibilities for measuring (monitoring) radionuclides in wastes. The definition of a global monitoring system in the framework of radioactive waste disposal has to be realized, based on the information presented here, in accordance with the results of work to come and on the inventory of wastes to be stored. Designed for direct measurement of unpackaged wastes and for control of wastes ready to be stored, the system would ultimately make it possible to obtain all adaquate information about their radioisotope content with regard to the required disposal safety. The second aim of this report is to outline the definition of such a global system of monitoring. Designed as a workbase and reference source for future work by the National Cooperative for the Storage of Radioactive Waste on the topic of radioactive waste monitoring, this report describes the current situation in this field. It also makes it possible to draw some preliminary conclusions and to make several recommendations. Centered on the possibilities of current and developing techniques, it makes evident that a global monitoring system should be developed. However, it shows that the monitoring of packaged wastes will be difficult, and should be avoided as far as possible, except for control measurements

  8. Radioactivity monitoring in Romania

    International Nuclear Information System (INIS)

    Alexandrescu, M.; Milu, C.

    1996-01-01

    Radioactivity monitoring in Romania is based on National Regulations for Radiation Protection enforced in 1976, on other environment protection laws enforced in the last years and on the recommendations of IAEA. Accordingly two systems of radioactive monitoring are to date operational in this field: the first one is the self-control of the radioactive emissions in the environment generated by the own nuclear activities (of nuclear units like the Cernavoda NPP, the Institute of Atomic Physics at Magurele-Bucharest, the Institute for Nuclear Research at Pitesti, the R Plant at Feldioara, Uranium mining units, etc.), while the other is based on two national agencies (the National Network of Environment Radiation Monitoring of the Ministry of Waters, Forests and Environment Protection and the Network of Radiation Hygiene Laboratories of the Health Ministry). The authors review and discuss the radiation protection legislation, the structure and the organizational operations of the national monitoring systems and the co-operation of the national monitoring systems with international authorities or programmes. 3 Figs., 1 tab., 11 refs

  9. Environmental radioactivity. Measurement and monitoring; Umweltradioaktivitaet. Messung und Ueberwachung

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2009-11-15

    The contribution on environmental radioactivity covers the following issues: natural and artificial radioactivity; continuous monitoring of radioactivity; monitoring authorities and measurement; radioactivity in the living environment; radioactivity in food and feeding stuff; radioactivity of game meat and wild-growing mushrooms; radioactivity in mines; radioactivity in the research center Rossendorf.

  10. Measurement of liquid radioactive materials for monitoring radioactive emissions

    International Nuclear Information System (INIS)

    1977-10-01

    This draft regulation applies to measuring equipment for liquid radioactive materials for the monitoring of the radioactive discharges from stationary nuclear power plants with LWR and HTR reactors. Demands made on the measuring procedure, methods of concentration determination, balancing, indication of limiting values, and inspections are layed down. The draft regulation deals with: 1) Monitoring liquid radioactive discharges: Water and similar systems; radionuclides and their detection limits, radioactively contaminated water (waste water); secondary cooling water; power house cooling water; primary cooling water; flooding water; 2) Layout of the measuring and sampling equipment and demands made on continuous and discontinuous measuring equipment; demands made on discontinuous α and β measuring equipment; 3) Maintenance and repair work; inspections; repair of defects; 4) Demands made on documentation; reports to authorities; 5) Supplement: List of general and reference regulations. (orig./HP) [de

  11. 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)

  12. Monitoring of radioactivity in drinking water

    International Nuclear Information System (INIS)

    Legarda, F.; Herranz, M.; Letessier, P.

    2008-01-01

    Radioactivity is a physical phenomenon whose presence in water is monitored due to its potential capability to induce deleterious effects on human health. In this article the effects that can be caused by radioactivity as well as the way in which regulations establish how to perform a monitorization of water that enables us to ascertain that the radiological quality of water is in agreement with the accepted standard of quality of life are analyzed. Finally the means available to know the content of radioactivity in water together with some clues on how to remove it from water are described. (Author) 5 refs

  13. Survey monitoring of environmental radioactivity in Jeju area

    Energy Technology Data Exchange (ETDEWEB)

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

    2000-12-15

    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 2000. Also it contains the data of natural radioactivity levels of food stuff such as agricultural and marine products, including drinking waters. There was no significant difference in environmental radioactivities between 1999 and 2000.

  14. Radioactive monitoring of the marine environment

    International Nuclear Information System (INIS)

    Bologa, A. S.

    1991-01-01

    Radioactivity monitoring of marine environment was required by the development of nuclear power and the worldwide use of ionizing radiations in many different activities. Both natural and artificial radioactivity play an important role in marine ecology and human health. In respect of this, three major facts prevail, namely: the fallout, the proximity of Danube River and the future nuclear power production. Spatial and temporal monitoring of marine radioactivity along the Romanian Black Sea shore has been systematically performed in Romanian Marine Research Institute in close cooperation with Institute of Meteorology and Hydrology since 1981. Marine emerged and submerged sediments, coastal and offshore sea water, macroalgae, invertebrates and fish of Danube mouths and/or along the coast are monitored for natural and artificial radioactivity by means of gross beta measurements and gamma spectrometry. Concentrations of radionuclides such as: K-40, Cs-134 and Cs-137 in abiotic and biotic samples, environmental distribution coefficients and concentration factors (CFs) as well as experimentally derived CFs in marine biota as radioecological bioindicators are assessed and stored in a national data base. (author)

  15. Monitoring of environmental radioactivity

    International Nuclear Information System (INIS)

    1986-01-01

    The results are described of monitoring radioactivity of atmospheric fallout, surface waters, soils, plant feeds, cereals, and other agricultural produce. The results were obtained over a long time period. Radioactivity was also measured of milk, milk products, vegetables and fruits, meat and hen eggs, flour and bakery products with a view to radionuclide migration in the food chain. The daily intake of 90 Sr and 137 Cs from food was determined from the values obtained and the consumption of the individual types of food. Strontium-90 distribution was studied in the bones and the teeth of the population in Slovakia. With the commissioning of nuclear power plants, emissions and liquid wastes were monitored and their environmental impact assessed. (E.S.)

  16. 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.

  17. 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.

  18. 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.

  19. Calibration method based on direct radioactivity measurement for radioactive gas monitoring instruments

    International Nuclear Information System (INIS)

    Yoshida, Makoto; Ohi, Yoshihiro; Chida, Tohru; Wu, Youyang.

    1993-01-01

    A calibration method for radioactive gas monitoring instruments was studied. In the method, gaseous radioactivity standards were provided on the basis of the direct radioactivity measurement by the diffusion-in long proportional counter method (DLPC method). The radioactivity concentration of the gas mixture through a monitoring instrument was determined by sampling the known volume of the gas mixture into the proportional counter used for the DLPC method. Since oxygen in the gas mixture decreased the counting efficiency in a proportional counter, the influence on calibration was experimentally estimated. It was not serious and able to be easily corrected. By the present method, the relation between radioactivity concentration and ionization current was determined for a gas-flow ionization chamber with 1.5 l effective volume. It showed good agreement with the results in other works. (author)

  20. Developments in radioactive scrap monitoring

    International Nuclear Information System (INIS)

    Bellian, J.G.

    1997-01-01

    Over the past ten years there have been major developments in radiation monitoring systems used for detecting shielded radioactive sources in scrap metal. The extent of the problem and industry's awareness of the problem have both grown significantly during that time. The multimillion dollar expenses associated with decontamination after a source passes into the melt and the potential health hazard to employees and the public have added further impetus to the development of monitoring systems. Early attempts at scrap monitoring could detect some radiation, but testing with real life situations showed them to be virtually incapable of detecting shielded sources of radioactivity in incoming vehicles. More sophisticated detector technology and the development of advanced software made useful by more powerful microprocessors led to successive generations of monitoring systems with order-of-magnitude improvement in detection capability. The next generation includes larger detectors and more complex algorithms offering further improvement in truck and rail car monitoring. Complete solutions require monitoring at additional locations within the site, such as the charge bucket and conveyor lines, and at the scrap processor's site

  1. Design of position monitor module in radioactive material transport monitoring system

    International Nuclear Information System (INIS)

    Adi Abimanyu; Dwi Yuliansari N

    2013-01-01

    Aspects of safety and security of radioactive substances from the sender to the receiver is to be secured so as not to harm humans. In general, monitoring is done through conversation by telephone to determine the location and rate of exposure of radioactive substances. Through the development of science and technology makes it possible to develop a system of monitoring the transport of radioactive substances in real time by combining radiation monitor module, position monitors module and sending information nir-cable. Position monitor module developed using GPS-receiver and a micro controller ATMega8 based serial interrupts communication. Testing is done by testing communication between micro controller and GPS and also testing reading position by GPS receiver. From the test results concluded that the developed modules is good in serial communication is based on serial interrupts, good position measurement to be used outdoors and is not good enough for measurements indoors because the GPS receiver used is not using an outdoor antenna. (author)

  2. Introducing radioactivity monitoring systems in the production of steel

    International Nuclear Information System (INIS)

    Sofilic, T.; Marjanovic, T.; Rastovcan-Mioc, A.

    2005-01-01

    Over the last twenty years, a significant number of cases of radioactive pollution has been recorded in metallurgical processes. However, it is not certain whether the pollution was caused by increased uncontrolled disposal of waste containing radionuclides or whether it was the result of increased radioactivity monitoring and control of metallic scrap. Many metal producers in the world have therefore implemented systematic monitoring of radioactivity in their production processes. Special attention was given to monitoring radioactivity in steel making processes, which is still the most applied construction material with an annual output of over billion tonnes all over the world. Drawing on the experience of the best known steel producers in Europe and world, Croatian steel mills find it necessary and justified to introduce radioactivity monitoring and control systems of radioactive elements in steel scrap, semi-finished and finished products. The aim of this paper is to point out the need to introduce the radioactivity monitoring and control in steel and steel-casting production, and to inform experts in Croatian steel mills and foundries about potential solutions and current systems. At the same time, we wanted to demonstrate how implementation of monitoring equipment can improve quality management and environmental management systems. This would render Croatian products competitive on the European market both in terms of physical and chemical properties and in terms of product quality certificates and radioactivity information. Since we lack our own standards and regulations to control both domestic and imported steel scrap, semi-finished products (crude steel, hot and cold rolled strip) and finished products, we need apply current international recommendations and guidelines, until we design our own monitoring system and adopt relevant legislation on the national level. This paper describes basic types of radioactivity monitoring and control systems, the most

  3. Radioactivity Monitoring of the Irish Environment 2006

    International Nuclear Information System (INIS)

    Smith, V.; Dowdall, A; Fegan, M.; Hayden, E.; Kelleher, K.; Long, S.; McEvoy, I.; Somerville, S.; Wong, J.; Pollard, D.

    2007-10-01

    This report presents the results of the environmental radioactivity monitoring programme carried out by the Radiological Protection Institute of Ireland (RPII) in 2006. This programme aims to assess the exposure of the Irish population to artificial radioactivity in the environment, to review the temporal and geographical distribution of contaminating radionuclides and to maintain systems and procedures which would allow a rapid assessment of environmental contamination to be made in the event of a radiological emergency. Radioactivity is present in the environment due to natural processes, the testing of nuclear weapons in the atmosphere, past nuclear accidents such as that at Chernobyl in Ukraine and the routine discharge of radionuclides from nuclear installations. Liquid discharges from the British Nuclear Group reprocessing plant at Sellafield in Cumbria in the north-west of England, which are licensed by the UK Environment Agency, continue to be the dominant source of artificial radioactivity in the Irish marine environment. The key elements of the monitoring programme implemented by the RPII in 2006 included; assessment of ambient radioactivity based on measurements of radioactivity in air and of external gamma dose rate at permanent monitoring stations located throughout the country; assessment of levels of radioactivity in drinking water; assessment of levels of radioactivity in foodstuffs based on measurements of total diet, milk and various ingredients; assessment of levels of radioactivity in the Irish marine environment based on sampling and measurement of seawater, sediment, seaweed, fish and shellfish. The RPII monitored airborne radioactivity at ten stations located throughout the country. One of these stations is equipped with a high volume sampler, which allows concentrations of caesium-137 to be measured; another is equipped to detect the presence of the gas krypton-85. This gas is released into the environment primarily as a result of the

  4. AIR RADIOACTIVITY MONITOR

    Science.gov (United States)

    Bradshaw, R.L.; Thomas, J.W.

    1961-04-11

    The monitor is designed to minimize undesirable background buildup. It consists of an elongated column containing peripheral electrodes in a central portion of the column, and conduits directing an axial flow of radioactively contaminated air through the center of the column and pure air through the annular portion of the column about the electrodes. (AEC)

  5. Development of radioactive surface contamination monitor

    International Nuclear Information System (INIS)

    Hashimoto, Tadao; Hasegawa, Toru; Fukumoto, Keisuke; Ooki, Yasushi

    2008-01-01

    In the radiation facilities such as nuclear power plants, surface contamination of the people accessing or articles conveyed in and out of the radiation controlled areas is detected and monitored by installing contamination monitors at the boundary of controlled areas and uncontrolled areas against the expansion of the radioactive materials to out of the facilities. It is required for the surface contamination of articles to be tightened of control criteria as 'Guidelines for discrimination ways of nonradioactive waste (not classified as radioactive waste) generated from nuclear power plants' (hereinafter referred to as 'the Guideline') was established by the Nuclear and Industrial Safety Agency of the Ministry of Economy, Trade and Industry in August, 2005. It predicts that the control criteria of monitors other than article monitors are also tightened in the future. Fuji electric has been fabricating and delivering surface contamination detecting monitors. Now we are developing the new contamination monitor corresponding to the tightening of the control criteria. 'Large article transfer monitor', 'Clothing monitor' and 'Body surface contamination monitor' are introduced in this article. (author)

  6. Radioactivity Monitoring of the Irish Environment 2009

    International Nuclear Information System (INIS)

    McGinnity, P.; Currivan, L.; Dowdall, A.; Fegan, M.; Hanley, O.; Kelleher, K.; McKittrick, L.; Somerville, S.; Wong, J.; Pollard, D.

    2010-12-01

    This report presents the results of the environmental radioactivity monitoring programme carried out by the Radiological Protection Institute of Ireland (RPII) during 2009. The RPII has routinely monitored levels of radioactivity in the environment since 1982 and this is the latest in the RPII's series of environmental monitoring reports. The RPII reviews and updates its environmental programme annually so as to ensure it remains relevant and continues to focus on the most important sources of radioactivity in the environment. The principal aims of the RPII's monitoring programme are; to assess the level of radioactivity to which the Irish population is exposed as a result of radioactivity in the environment; to study trends and establish the geographical distribution of contaminating radionuclides so as to better understand the long term behaviour of artificial radioactivity in the food chain and the environment; to ensure that any increase in radiation levels resulting from an accidental release of radioactivity to the environment is detected and assessed rapidly. During 2009 radioactivity was measured in a wide range of foods and environmental materials including: air, water, milk, seafood, foodstuffs and complete meals. The most significant source of artificial radioactivity in the Irish marine environment is the discharge of low level liquid radioactive waste from the Sellafield Nuclear Fuel Reprocessing Plant on the north east coast of England. In order to assess the exposure arising from the source extensive sampling of fish and shellfish landed at ports along the north east coast of Ireland is undertaken. The most exposed group of individuals to discharges from Sellafield have been identified as commercial oyster and mussel farmers working along the north east coastline and their families. Manmade radioactivity is also present in the terrestrial environment due primarily to residual global fallout arising primarily from atmospheric testing of nuclear

  7. Radioactivity Monitoring of the Irish Environment 2008

    International Nuclear Information System (INIS)

    Fegan, M.; Currivan, L.; Dowdall, A.; Hanley, O.; Hayden, E.; Kelleher, K.; Long, S.; McKittrick, L.; Somerville, S.; Wong, J.; Pollard, D.

    2010-01-01

    This report presents the results of the environmental radioactivity monitoring programme carried out by the Radiological Protection Institute of Ireland (RPII) during 2008. The RPII has routinely monitored levels of radioactivity in the environment since 1982 and this is the latest in the RPII's series of environmental monitoring reports. The RPII reviews and updates its environmental programme annually so as to ensure it remains relevant and continues to focus on the most important sources of radioactivity in the environment. The principal aims of the RPII's monitoring programme are; to assess the level of radioactivity to which the Irish population is exposed as a result of radioactivity in the environment; to study trends and establish the geographical distribution of contaminating radionuclides so as to better understand the long term behaviour of artificial radioactivity in the food chain and the environment; to ensure that any increase in radiation levels resulting from an accidental release of radioactivity to the environment is detected and assessed rapidly. During 2008 radioactivity was measured in a wide range of foods and environmental materials including: air, water, milk, seafood, foodstuffs and complete meals. The most significant source of artificial radioactivity in the Irish marine environment is the discharge of low level liquid radioactive waste from the Sellafield Nuclear Fuel Reprocessing Plant on the north east coast of England. In order to assess the exposure arising from the source extensive sampling of fish and shellfish landed at ports along the north east coast of Ireland is undertaken. The most exposed group of individuals to discharges from Sellafield have been identified as commercial oyster and mussel farmers working along the north east coastline and their families. Manmade radioactivity is also present in the terrestrial environment due primarily to residual global fallout arising primarily from atmospheric testing of nuclear

  8. 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.

  9. 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.

  10. 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.

  11. 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.

  12. 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

  13. 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

  14. Radioactive discharges and monitoring of the environment 1988

    International Nuclear Information System (INIS)

    1989-01-01

    This annual report on Radioactive Discharges and Monitoring the Environment, 1988, summarises the programmes of Sellafield, Drigg, Chapelcross, Springfields and Capenhurst for monitoring the discharges of radioactive materials to the sea and the environment. Critical groups and environmental exposure pathways are identified and collective doses to these groups estimated. The disposal of radioactive wastes at each site is discussed. Certificates of authorisation are presented. A summary of recommended doses of specific radionuclides is given. (Author)

  15. Radioactive source monitoring system based on RFID and GPRS

    International Nuclear Information System (INIS)

    He Haiyang; Zhou Hongliang; Zhang Hongjian; Zhang Sheng; Zhou Junru; Weng Guojie

    2011-01-01

    Nuclear radiation produced by radioactive source is harmful to the health of human body, and the lost and theft of radioactive source will cause environmental pollution and social panic. In order to solve the abnormal leaks, accidental loss, theft and other problems of the radioactive source, a radioactive source monitoring system based on RFID, GPS, GPRS and GSM technology is put forward. Radiation dose detector and GPS wireless location module are used to obtain the information of radiation dose and location respectively, RFID reader reads the status of a tag fixed on the bottom of the radioactive source. All information is transmitted to the remote monitoring center via GPRS wireless transmission. There will be an audible and visual alarm when radiation dose is out of limits or the state of radioactive source is abnormal, and the monitoring center will send alarming text messages to the managers through GSM Modem at the same time. Thus, the functions of monitoring and alarming are achieved. The system has already been put into operation and is being kept in functional order. It can provide stable statistics as well as accurate alarm, improving the supervision of radioactive source effectively. (authors)

  16. Radioactivity Monitoring of the Irish Environment 2007

    International Nuclear Information System (INIS)

    Fegan, M.; Dowdall, A.; Hanley, O.; Hayden, E.; Kelleher, K.; Long, S.; Smith, V.; Somerville, S.; Wong, J.; Pollard, D.

    2008-10-01

    This report presents the results of the environmental radioactivity monitoring programme carried out by the Radiological Protection Institute of Ireland (RPII) in 2007. This programme aims to assess the exposure of the Irish population to artificial radioactivity in the envorinment, to review the temporal and geographical distribution of contaminating radionuclides and to maintain systems and procedures which would allow a rapid assessment of environmental contamination to be made in the event of a radiological emergency. In additiopn, some natural radioactivity exposure pathways are included in the programme including radioactivity in surface and ground drinking water. Radioactivity is present in the environment due to natural oprocesses, the testing of nuclear weapons in the atmosphere, past nuclear accidents such as that at Chernobyl in the Ukraine and the routine discharge of radionuclides from nuclear installations. Liquid discharges from the British Nuclear Group reprocessing plant at Sellafield in Cumbria in the north-west of England continue to be the dominant source of artificial radioactivity in the Irish marine environment. The key elements of the monitoring programme implemented by the RPII in 2007 included; assessment of ambient radioactivity based on measurements of radioactivity in air and of external gamma dose rate at permanent monitoring stations located throughout the country; assessment of levels of radioactivity in drinking water; assessment of levels of radioactivity in foodstuffs based on measurements of total diet, milk and various ingredients; assessment of levels of radioactivity in the Irish marine environment based on sampling and measurement of seawater, sediment, seaweed, fish and shellfish. The RPII monitored airborne radioactivity at twelve stations located throughout the country. One of these stations is equipped with a high volume sampler, which allows background concentrations of caesium-137 to be measured; another is equipped to

  17. Partial monitoring system Radioactivity of the Environment, 2006

    International Nuclear Information System (INIS)

    Melicherova, T.

    2007-01-01

    In this report the Partial monitoring system 'Radioactivity of the Environment' for the year 2006 is presented. International co-operation of the Slovak Hydrometeorological Institute in the Partial monitoring system 'Radioactivity of the Environment' of the Slovak Republic, international co-operation as well as financial data are reviewed

  18. Monitoring device for radioactive leakage from steam system in nuclear power plant

    International Nuclear Information System (INIS)

    Ogawa, Tateo; Sato, Kohei

    1988-01-01

    Purpose: To improve the reliability for the monitor of radio-active leakage by accumulating small quantity of radioactivities each lower than the detectable level and increasing their dose rate. Constitution: Even if the steam system radiation monitor in the nuclear power plant is disposed for the detection of in-leak radioactivity, radioactive leakage can be monitored at high reliability by increasing the small quantity of radioactivities in the drains to a detectable sensitivity range of the monitor upon detection. In view of the above, in the present invention, radioactive material catching medium is incorporated to a radio-activity monitor spool piece for accumulating small quantity of radioactivities. Specifically as the catching medium, an ion exchange resin is used for the leakage of ionic radioactive material, while an ion exchange resin increased with the mixing ratio of a cationic resin or hollow thread membrane filter is used for crud-like radioactive material leakage. These catching media are incorporated into the spool piece, thereby enabling to catch even small quantity of radioactive leakage lower than the detectable sensitivity of the radiation monitor, if should occur, in the spool piece and enabling radioactive detection for the accumulated dose rate. (Horiuchi, T.)

  19. Environmental radioactivity monitoring in Republic of Serbia

    International Nuclear Information System (INIS)

    Joksic, J.; Radenkovic, M.; Tanaskovic, I.; Vujovic, M.; Vuletic

    2011-01-01

    According to environmental radioactivity monitoring programme continuous measurements of radioactivity in different samples are performed. Measurements are performed in aerosol samples, fallout, soil, surface waters, drinking water, food of animal and plant origin, milk and feeding stuffs. [sr

  20. 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.

  1. Monitoring programme. Radioactive substances - report for 1994

    International Nuclear Information System (INIS)

    1995-09-01

    The monitoring of radioactive substances in the vicinity of nuclear sites in the United Kingdom by Her Majesty's Inspectorate of Pollution, acts as an independent check on the operator's returns, on the environmental impact of radioactive waste disposal at authorised sites and on radiation doses to critical groups of the public. In 1994 the programme included the analysis of 160 effluent samples, the analysis of low-level solid radioactive waste destined for the British Nuclear Fuels site at Drigg, and the analysis of a total of 290 environmental samples and direct monitoring at over 150 locations. The materials monitored are those that might result in exposure of the public to radiation by non-food pathways and complements monitoring by the Ministry of Agriculture, Food and Fisheries. Radiation exposures by these pathways which may have been incurred in 1994 are similar to those in previous years and, in all cases, fall substantially below the International Commission on Radiological Protection's recommended principal dose limit of 1mSv per year. (UK)

  2. Radioactive standards and calibration methods for contamination monitoring instruments

    Energy Technology Data Exchange (ETDEWEB)

    Yoshida, Makoto [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    1997-06-01

    Contamination monitoring in the facilities for handling unsealed radioactive materials is one of the most important procedures for radiation protection as well as radiation dose monitoring. For implementation of the proper contamination monitoring, radiation measuring instruments should not only be suitable to the purpose of monitoring, but also be well calibrated for the objective qualities of measurement. In the calibration of contamination monitoring instruments, quality reference activities need to be used. They are supplied in different such as extended sources, radioactive solutions or radioactive gases. These reference activities must be traceable to the national standards or equivalent standards. On the other hand, the appropriate calibration methods must be applied for each type of contamination monitoring instruments. In this paper, the concepts of calibration for contamination monitoring instruments, reference sources, determination methods of reference quantities and practical calibration methods of contamination monitoring instruments, including the procedures carried out in Japan Atomic Energy Research Institute and some relevant experimental data. (G.K.)

  3. Monitoring of radioactivity in the marine environment

    International Nuclear Information System (INIS)

    Bologa, A.S.

    1992-01-01

    The necessity of radioactivity monitoring in the marine environment was imposed by the increasing development of nuclear power and its world-wide use in many different segments of economic and social life. Both natural and artificial radioactivity play an important role in marine ecology and human health. In this respect three major facts continue to prevail in Romania. The fallout, the presence of the Danube river and the expectations for future energy production. Spatial and temporal monitoring of marine radioactivity along the Romanian Black Sea shore has been systematically performed in the Romanian Marine Research Institute in close co-operation with the Institute of Meteorology and Hydrology since 1981. Marine emerged and submerged sediments, coastal and offshore sea water, macroalgae, in vertebrates and fish off the Danube mouths and/or along the coast are monitored for natural and artificial radioactivity by means of beta gross measurements and gamma spectrometry. Concentrations of radionuclides as K-40, Cs-134, Cs-137 in abiotic and biotic samples, environmental distributions coefficients and concentrations factors (CF), as well as experimentally-derived CFs in marine biota as radioecological bioindicators are assessed and stored for a national data base. (author) 3 tabs., 18 refs

  4. Sampling method of environmental radioactivity monitoring

    International Nuclear Information System (INIS)

    1984-01-01

    This manual provides sampling methods of environmental samples of airborne dust, precipitated dust, precipitated water (rain or snow), fresh water, soil, river sediment or lake sediment, discharged water from a nuclear facility, grains, tea, milk, pasture grass, limnetic organisms, daily diet, index organisms, sea water, marine sediment, marine organisms, and that for tritium and radioiodine determination for radiation monitoring from radioactive fallout or radioactivity release by nuclear facilities. This manual aims at the presentation of standard sampling procedures for environmental radioactivity monitoring regardless of monitoring objectives, and shows preservation method of environmental samples acquired at the samplingpoint for radiation counting for those except human body. Sampling techniques adopted in this manual is decided by the criteria that they are suitable for routine monitoring and any special skillfulness is not necessary. Based on the above-mentioned principle, this manual presents outline and aims of sampling, sampling position or object, sampling quantity, apparatus, equipment or vessel for sampling, sampling location, sampling procedures, pretreatment and preparation procedures of a sample for radiation counting, necessary recording items for sampling and sample transportation procedures. Special attention is described in the chapter of tritium and radioiodine because these radionuclides might be lost by the above-mentioned sample preservation method for radiation counting of less volatile radionuclides than tritium or radioiodine. (Takagi, S.)

  5. HMIP Monitoring Programme radioactive substances report for 1990

    International Nuclear Information System (INIS)

    1992-03-01

    The programme of environmental monitoring of radioactive substances in England and Wales during 1990, was completed satisfactorily under the auspices of Her Majesty's Inspectorate of Pollution. The programme concentrates on monitoring activity levels in environmental materials which might result in radiation exposure of the public from non-food pathways. The programme acts as a check on site operator's returns and provides independent data on the environmental impact of authorised disposals of radioactive wastes and on radiation doses to critical groups of the public. This report presents the data from this continuing monitoring programme. The monitoring was carried out at installations controlled by British Nuclear Fuels PLC, Nuclear Electric the United Kingdom Atomic Energy Authority, Amersham International PLC, the Ministry of Defence, at two non-nuclear sites which use tritium, the works of Capper Pass Ltd who carry out lead smelting and at several landfill sites where controlled buried of low-level radioactive wastes is carried out. (Author)

  6. Design of automatic control and measurement software for radioactive aerosol continuity monitor

    International Nuclear Information System (INIS)

    Mao Yong; Li Aiwu

    1997-01-01

    The radioactive aerosol continuity measurement is very important for the development of nuclear industry, and it is the major method to measure and find out the leakage of radioactive material. Radioactive aerosol continuity monitor is the advanced method for the radioactive aerosol continuity measurement. With the development of nuclear industry and nuclear power station, it is necessary to design and automatic continuity measurement device. Because of this reason, the authors developed the first unit of radioactive aerosol continuity monitor and adopted the ministry appraisal. The design idea and method of automatic control and measurement for radioactive aerosol continuity monitor are discussed

  7. Survey monitoring of environmental radioactivity in Daegu area

    International Nuclear Information System (INIS)

    Kang, Hee Dong; Lee, Hae Young; Yang, Chan Sun

    2001-12-01

    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. In this report, we summarized a gamma exposure rates, a gross beta and gamma radionuclide activities for the environmental samples of airborned-dust. precipitation, fallout and tap water collected in Taegu radioactivity monitoring center, and a gamma radionuclide activities for the 28 grocery samples, such as tea, nut and mushroom, rice, chinese cabbage, wormwood and pine needles, soil and drinking water which were obtained from Taegu and Kyungpook region to establish the basic data base for estimating the internal exposure. In conclusion, it didn't appear any evidence for newly pollution of artificial radioactivity in Taegu and Kyungpook region

  8. Radioactivity Monitoring of the Irish Environment 2003-2005

    International Nuclear Information System (INIS)

    Ryan, R.W.; Dowdall, A; Fegan, M.F.; Hayden, E.; Kelleher, K.; Long, S.; McEvoy, I.; McKittrick, L.; McMahon, C.A.; Murray, M.; Smith, K.; Sequeira, S.; Wong, J.; Pollard, D.

    2007-05-01

    This report presents the results of the environmental radioactivity monitoring programme carried out by the Radiological Protection Institute of Ireland (RPII) between 2003 and 2005. This programme aims to assess the exposure of the Irish population to anthropogenic radioactivity in the environment, to review the temporal and geographical distribution of contaminating radionuclides and to maintain systems and procedures which would allow a rapid assessment of environmental contamination to be made in the event of a radiological emergency. Radioactivity is present in the environment due to natural processes, the testing of nuclear weapons in the atmosphere, past nuclear accidents such as that at Chernobyl and the routine licensed discharge of radionuclides from nuclear installations. Liquid discharges from the British Nuclear Group reprocessing plant at Sellafield in Cumbria in the North-West of England continue to be the dominant source of anthropogenic radioactivity in the Irish marine environment. The key elements of the monitoring programme implemented by the RPII during the reporting period include; assessment of ambient radioactivity based on measurements of radioactivity in air and external gamma dose rate at permanent monitoring stations located throughout the country; assessment of levels of radioactivity in drinking water; assessment of levels of radioactivity in foodstuffs based on measurements of total diet, milk and miscellaneous ingredients; assessment of levels of radioactivity in the marine environment based on sampling and measurements of seawater, sediment, seaweed, fish and shellfish. The RPII monitored airborne radioactivity at eleven stations located throughout the country. One station is equipped with a high volume sampler, which allows global fallout concentrations to be measured, and one is equipped to detect the presence of the gas krypton-85. Krypton-85 is released into the environment primarily as a result of the reprocessing of nuclear

  9. Environmental monitoring of low-level radioactive materials

    International Nuclear Information System (INIS)

    Jester, W.A.; Yu, C.

    1985-01-01

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

  10. Monitoring radioactivity in the environment: context, objectives, challenges and prospects

    International Nuclear Information System (INIS)

    Collet, J.; Jaunet, P.

    2010-01-01

    The aims of environmental radioactivity monitoring are multiples: protection of human health and environment, knowledge of the radiological status of the environment, early detection of radiological events, public information. This monitoring is ensured by several stakeholders (licensees, IRSN, ASN, state and local authorities, associations...) and in all environment compartments (air, water, soil, fauna and flora...). Within a European regulatory context, the Nuclear Transparency and Security Act 2006-686 of 13 June 2006 (TSN Act) reinforces the importance attached to consideration of safety, radiation protection and the environment. Other developments in the scope of environmental radioactivity must be noted: new stakeholders, lower background radiation, deployment of the French National Network of Environmental Radioactivity Monitoring (RNM), evolution of the ICPR thoughts to take better account of environmental protection, post-accident management doctrine, new concerns about environmental behaviour of some radionuclides. In order to maintain a quality policy in the field of environmental radioactivity measurements and to ensure the transparency of information, ASN will make sure that the strategy of environmental radioactivity monitoring will take into account these concerns. (author)

  11. Environmental monitoring for radioactivity in Scotland: 1981 to 1985

    Energy Technology Data Exchange (ETDEWEB)

    Anon.

    1987-01-01

    A bulletin, prepared by Her Majesty's Industrial Pollution Inspectorate (HMIPI) of the Scottish Development Department (SDD), contains a summary of the environmental monitoring for radioactivity carried out in Scotland as part of the statutory procedure for ensuring the safety of radioactive waste disposals from nuclear facilities. The monitoring results for discharges to both the atmosphere and the sea over the period 1981 to 1985 are presented for BNFL's Chapelcross and Sellafield Works, UKAEA Dounreay Nuclear Power Development Establishment, SSEB Hunterston Power Station and MOD Naval Installations. It is concluded that public radiation exposure in Scotland from environmental radioactivity arising from radioactive waste disposal has been well within the internationally recommended limits.

  12. Radioactivity monitor for high-performance liquid chromatography

    International Nuclear Information System (INIS)

    Reeve, D.R.; Crozier, A.

    1977-01-01

    The coupling of a homogeneous radioactivity monitor to a liquid chromatograph involves compromises between the sensitivity of the monitor and the resolution and speed of analysis of the chromatograph. The theoretical relationships between these parameters are considered and expressions derived which make it possible to calculate suitable monitor operating conditions for most types of high-performance liquid chromatography

  13. Monitoring programme. Radioactive substances report for 1994

    International Nuclear Information System (INIS)

    1995-09-01

    In the United Kingdom, Her Majesty's Inspectorate of Pollution commissions independent monitoring of radioactive discharges to the environment. This report presents the results of such monitoring for 1994. It covers nuclear sites, two non-nuclear sites which use large amounts of tritium and several landfill sites which receive low-level radioactive waste for controlled burial. The monitoring programme concentrates on activity levels in environmental materials that might result in exposure of the public to radiation from non-food pathways. The results show that exposures from these pathways in 1994 remain similar to those in previous years and in all cases are estimated to have been substantially lower than the International Commission on Radiological Protection's recommended dose limit of 1mSv per year. (6 figures; 20 tables; 29 references) (UK)

  14. Radioactivity monitoring status in French Polynesia in 2008. Results from IRSN's monitoring network

    International Nuclear Information System (INIS)

    2009-01-01

    Radiological monitoring of the French environment is one of IRSN's permanent tasks as part of public policy on nuclear safety and radiological protection. It is helping to guarantee the best possible protection of the population. The task addresses two objectives: - To monitor the levels of artificial radioactivity in all sectors of the environment and in major foodstuffs; - To estimate the exposure of the Polynesian population to this artificial radioactivity. The IRSN has monitored radioactivity levels in French Polynesia, excluding the Mururoa and Fangataufa nuclear experimentation centres, since 1962. This task is realized by the IRSN's Environmental Study and Monitoring Laboratory located in Tahiti (Vairao) This monitoring was instigated at the time when atmospheric nuclear weapons testing was being performed by the major powers (the United States, the Soviet Union, the United Kingdom, France and China), causing fallout of artificial radionuclides, over several years, on a planetary scale. In French Polynesia, the IRSN is most particularly interested in fallout resulting from the 41 tests carried out by France in this region of the globe between 1966 and 1974, and in its consequent effects on the population. Today, just as in metropolitan France, the IRSN carries out monitoring as part of its mission to constantly monitor radiological protection factors. The monitoring takes place on seven islands (Tahiti, Maupiti, Hao, Rangiroa, Hiva Oa, Mangareva and Tubuai) representing the five archipelagoes and consists of taking monthly samples of various kinds from the different environmental compartments (air, water, soil, food...) with which the population may be in contact. For more than 40 years, the IRSN takes part in the evaluation of the dosimetric consequences of these atmospheric depositions in French Polynesia. This laboratory is established in Tahiti. The ingestion component of this dosimetric evaluation requires to collect the most representative samples of

  15. Terrestrial radioactivity monitoring programme (TRAMP) report for 1986

    International Nuclear Information System (INIS)

    1988-01-01

    The Ministry of Agriculture, Fisheries and Food (MAFF) undertakes a comprehensive independent monitoring programme for radioactivity in terrestrial foodstuffs in England and Wales, this report presents the results from the first full year of operation of this programme and complements the data published annually by the Ministry's Directorate of Fisheries Research in respect of the aquatic environment. This work is undertaken in Wales on behalf of the Secretary of State. The Terrestrial Radioactivity Monitoring Programme (TRAMP) concentrates on samples of agricultural produce (milk, crops, meat) collected from the vicinity of the major nuclear sites in England and Wales and is independent of monitoring undertaken for various purposes by site operators. (author)

  16. Monitoring of the release of gaseous and aerosol-bound radioactive materials. Pt. 2

    International Nuclear Information System (INIS)

    1992-01-01

    KTA 1503 contains requirements on technical installations and supplementary organizational measures considered necessary in order to monitor the release of gaseous and aerosol-bound radioactive materials. It consists of part 1: Monitoring of the release of radioactive materials together with stack gas during normal operation; part 2: Monitoring of the release of radioactive materials together with stack gas in the event of incidents; part 3: Monitoring of radioactive materials not released together with stack gas. The concept on which this rule is based is to ensure that in the case of incidents during which the result of effluent monitoring remains meaningful, such monitoring can be reliably performed. (orig./HSCH) [de

  17. Ionization chamber for monitoring radioactive gas

    International Nuclear Information System (INIS)

    Kotrappa, P.; Dempsey, J.

    1992-01-01

    This present invention provides simple, effective and accurate cumulative measurement of radioactive gas over a time period. Measurements of radioactive gas are important for many purposes. Tritium concentrations in potentially exposed workers are measured, for example, with periodic urine specimens. Carbon-14 serves as a useful research tool for monitoring the progress of many chemical and biological reactions and interactions. For example, many microorganisms break down carbon-14 containing compounds in sugar to produce carbon-14 dioxide gas which can be collected and measured to determine various characteristics of the microorganisms. Both tritium and carbon-14 dioxide produce low energy radiation which cannot be easily measured by conventional radioactivity detectors. (author). 4 figs

  18. Ionization chamber for monitoring radioactive gas

    Energy Technology Data Exchange (ETDEWEB)

    Kotrappa, P; Dempsey, J

    1992-09-22

    This present invention provides simple, effective and accurate cumulative measurement of radioactive gas over a time period. Measurements of radioactive gas are important for many purposes. Tritium concentrations in potentially exposed workers are measured, for example, with periodic urine specimens. Carbon-14 serves as a useful research tool for monitoring the progress of many chemical and biological reactions and interactions. For example, many microorganisms break down carbon-14 containing compounds in sugar to produce carbon-14 dioxide gas which can be collected and measured to determine various characteristics of the microorganisms. Both tritium and carbon-14 dioxide produce low energy radiation which cannot be easily measured by conventional radioactivity detectors. (author). 4 figs.

  19. Environmental radioactivity monitoring in Greece

    International Nuclear Information System (INIS)

    Maltezos, A.; Potiriadis, C.; Aravantinos, A.

    1997-01-01

    Greek Atomic Energy Commission (GAEC) is the national organization responsible for the environmental radioactivity measurements in Greece. In order to monitor the radioactivity, 12 stations were placed all over Greece. Each station is equipped with NaI detector, measuring daily the total gamma dose rates. After the Chernobyl experience many countries have installed dense automatic networks, for measuring environmental radioactivity and serving as an early warning systems. In Greece a small telemetric network of two stations was installed in Athens area as a pilot project. Each station consists of two GM detectors (for low and high dose rate respectively). Data are collected for every ten minutes sampling time. Regration time of one hour is obtained. In case of level one and level two alarm states, the sampling time intervals are ten and one minutes respectively. The measurements are obtained by the above stations using the lines of the telephone network, and stored in the central station. Financial support to upgrade the existing telemetric system was assured by the addition of 25 new telemetric stations which will cover madly the northern part bordering to other states with nuclear power plants.In order to complete the network, we plan to add more stations to measure the gamma dose rates spread all over Greece, and also monitor river water. (authors)

  20. Monitoring dissolved radioactive cesium in Abukuma River in Fukushima Prefecture

    International Nuclear Information System (INIS)

    Yasutaka, Tetsuo; Kawabe, Yoshishige; Kurosawa, Akihiko; Komai, Takeshi

    2013-01-01

    Radioactive materials were released into the atmosphere and deposited over wide areas of farmland, forests, and cities; elevated levels of "1"3"1I, "1"3"4Cs, and "1"3"7Cs have been detected in these areas due to the accident at the Tokyo Power Fukushima Daiichi Nuclear Power Plant caused by the April 2011 earthquake and tsunami in eastern Japan. Radioactive Cs deposited on farmland and forests gradually leaches into water bodies such as mountain streams and rivers adsorbed onto particles or in a dissolved state. It is important to calrify the level of dissolved and total radioactive Cs in environmental water for forecasting the of discharge of radioactive Cs from forest and watersheds, assessing on the effect of dissolved and total radioactive Cs on not only irrigation water but also rice and other crops, and evaluating the transport of radioactive Cs from rivers to costal areas. Therefore, it is important to monitor their levels in Fukushima Prefecture over time. In this research, we monitored the levels of dissolved and total radioactive Cs in Abukuma River using a conventional evaporative concentration method. By monitoring the river waters since September 2012, it was estimated that the levels of dissolved radioactive Cs were less than 0.128 Bq/L and those of total radioactive Cs were less than 0.274 Bq/L in the main stream and branches of Abukuma River in the low suspended solid condition. (author)

  1. Comparison of monitoring technologies for CO2 storage and radioactive waste disposal

    International Nuclear Information System (INIS)

    Ryu, Jihun; Koh, Yongkwon; Choi, Jongwon; Lee, Jongyoul

    2013-01-01

    The monitoring techniques used in radioactive waste disposal have fundamentals of geology, hydrogeology, geochemistry etc, which could be applied to CO 2 sequestration. Large and diverse tools are available to monitoring methods for radioactive waste and CO 2 storage. They have fundamentals on geophysical and geochemical principles. Many techniques are well established while others are both novel and at an early stage of development. Reliable and cost-effective monitoring will be an important part of making geologic sequestration a safe, effective and acceptable method for radioactive waste disposal and CO 2 storage. In study, we discuss the monitoring techniques and the role of these techniques in providing insight in the risks of radioactive waste disposal and CO 2 sequestration

  2. Monitoring of radioactivity in 1979

    International Nuclear Information System (INIS)

    Data are given on the monitoring of radioactive contamination of air and some food stuffe at world locations throughout Western South America, South Pacific and Africa during 1979. Data are included on the total β and γ activity and radionuclide content in air, milk and other environmental samples ( 131 I, 90 Sr, 137 Cs) [fr

  3. Storage of radioactive material - accidents - precipitation - personnel monitoring

    International Nuclear Information System (INIS)

    Matijasic, A.; Gacinovic, O.

    1961-12-01

    This volume covers the reports on four routine tasks concerned with safe handling of radioactive material and influence of nuclear facilities on the environment. The tasks performed were as follows: Storage of solid and liquid radioactive material; actions in case of accidents; radiation monitoring of the fallout, water and ground; personnel dosimetry

  4. Radioactivity monitoring of fallout, water and ground

    International Nuclear Information System (INIS)

    Radosavljevic, R.

    1961-01-01

    During 1961, the radioactivity monitoring of the Boris Kidric Institute site covered monitoring of the total β activity of the fallout and water on the site. Activity of the fallout was monitored by measuring the activity of the rain and collected sedimented dust form the atmosphere. Water monitored was the water from Danube and river Mlaka, technical and drinking water. Plants and soil activity were not measured although sample were taken and the total β activity will be measured and analysed later

  5. Monitoring of radioactivity in 1973

    International Nuclear Information System (INIS)

    Data are presented on the monitoring of radioactive contamination of air and some foodstuffs at world (locations throughout Western South America, South Pacific, Africa during 1973. Data are included on the total β and γ activity and content of radionuclides found in fallout in air, milk and other environmental samples ( 131 I, 90 Sr, 137 Cs) [fr

  6. Fifty years of atmospheric radioactivity monitoring by the German Meteorological Service

    International Nuclear Information System (INIS)

    2006-01-01

    At a commemorative event at the Langen Training and Congress Center on 8 and 9 June 2005 it was brought to the attention of the audience that the German Meteorological Service has been charged with the sovereign task of monitoring atmospheric radioactivity since 8 August 1955. The purpose of this commission at the time was to measure traces of radioactivity in the atmosphere and precipitation and make forecasts on the movement of radioactive air masses. This was motivated by the above-ground nuclear tests carried out by the USA and the Soviet Union and the resulting measurable increase in atmospheric radioactivity levels. Equipped as it was with the necessary infrastructure the German Meteorological Service offered to take on this monitoring task. The importance of being able to assess the meteorological situation and provide data on radioactivity levels in the atmosphere and precipitation became apparent in 1986 after the reactor disaster of Chernobyl. When the Law on Preventive Radiation Protection was enacted in 1986 it was therefore only logical for the German Meteorological Service's commission to monitor atmospheric radioactivity levels to be renewed

  7. Studies on radioactivity monitoring proceedure for marine organisms

    International Nuclear Information System (INIS)

    Koyanagi, Taku; Hirano, Shigeki

    1978-01-01

    Suitability of several species of mollusca and seaweeds as indicator organisms for radioactivity monitoring of marine environment was examined by radioisotope tracer experiments or stable elements analyses from the standpoints of the affinities for radionuclides, the sampling procedures, and the distribution of radioactive and stable elements in the body of these organisms. Extremely high concentration factor of 54 Mn was shown by kidney of scallop suggesting the suitability for the efficient monitoring of the nuclide though the contribution of kidney to the weight of scallop was very small. Higher concentration of 54 Mn in midgut gland rather than kidney was observed in the case of other species of shellfishes but distribution of the nuclide among organs or tissues of the organisms varied during the period of intake and excretion. Ununiform distribution of radioactive and stable elements among the species of seaweeds and in the body of seaweeds observed by the tracer experiments and stable element analyses suggested the necessity of careful selection of the samples for monitoring of these nuclides. From the results of tracer experiments carried out in order to elucidate the relation between existing state of radionuclides in seawater and uptake by marine organisms, it was supposed that the complexed forms with inorganic or organic ligands in seawater were predominant species of radioactive cerium in seawater. (author)

  8. Environmental monitoring for radioactivity in Scotland, 1983 to 1987

    International Nuclear Information System (INIS)

    1989-01-01

    This bulletin, which has been prepared by Her Majesty's Industrial Pollution Inspectorate (HMIPI) of the Scottish Development Department (SDD), contains a summary of the environmental monitoring for radioactivity carried out in Scotland as part of the statutory procedure for ensuring the safety of radioactive waste disposals from nuclear facilities. The results presented cover the period 1983 to 1987. The first section of the bulletin draws together the results of the monitoring and presents the principal conclusions; the second section summarises the procedures underlying the monitoring; and the remaining sections present detailed monitoring results. The principal conclusions of this bulletin are that: public radiation exposure in Scotland from environmental radioactivity arising from radioactive waste disposal has been well within the internationally recommended limits including the ICRP's recommended principal limit of 1 millisievert per year; the levels of radiation exposure have been consistent with the recommendation of the NRPB that procedures leading to exposure of the public should be controlled so that the life-time effective dose equivalent does not exceed 70 millisieverts; any doses received have been small and correspond to negligible levels of risk to individuals; and the effects of waste disposals have been limited in accordance with the national standards of radiological safety, which are designed to protect the population from the harmful effects of radiation. (author)

  9. Radioactivity Monitoring of the Irish Environment 2010-2011

    International Nuclear Information System (INIS)

    McGinnity, P.; Currivan, L.; Dowdall, A.; Hanley, O.; Kelleher, K.; McKittrick, L.; Pollard, D.; Somerville, S.; Wong, J.; McMahon, C.

    2012-11-01

    This report presents the results of the environmental radioactivity monitoring programme carried out by the Radiological Protection Institute of Ireland RPII during 2010 and 2011. The RPII has routinely monitored levels of radioactivity in the Irish environment since 1982 and this is the latest in the RPII's series of environmental monitoring reports. The RPII reviews and updates its environmental programme annually to ensure it remains relevant and continues to focus on the most important sources of radioactivity in the environment. The data presented in this report confirm that while the levels of artificial radioactivity in the Irish environment are detectable, they are low. They do not pose a significant risk to the human health of the Irish population. Trace amounts of radioactive isotopes consistent with the Fukushima nuclear accident were detected in air, rainwater and milk samples during the period March to May 2011. These increases in levels of radioactivity were not of concern from a public health point of view. For the remainder of the reporting period, activity concentrations of radionuclides in airborne particles were low and consistent with measurements made in recent years. Radioactivity levels in milk, mixed diet and a wide range of foodstuffs were low and, for the majority of samples, below the detection limits. All drinking waters tested were found to be in compliance with the total indicative dose defined in national and EU legislation. The doses incurred by the Irish public in 2010 and 2011 as a result of artificial radioactivity in the marine environment are small when compared to dose limits or to natural radiation doses received by the Irish public. The doses to the most exposed individuals, members of the oyster and mussel farmers critical group, were approximately 0.02 per cent and 0.05 per cent of the annual dose limit of 1000 microsieverts for members of the public from practices involving controllable sources of radiation in 2010 and

  10. Occupational monitoring at radioactive waste deposit

    Energy Technology Data Exchange (ETDEWEB)

    Pereira, Wagner S.; Cunha, Franklin S. [Indústrias Nucleares do Brasil (COMAP.N/FCN/INB), Resende, RJ (Brazil). Fábrica de Combustível Nuclear. Coordenação de Meio Ambiente e Proteção Radiológica Ambiental; Kelecom, Alphonse [Universidade Federal Fluminense (LARARA-PLS/UFF), Niterói, RJ (Brazil). Lab. de Radiobiologia e Radiometria Pedro Lopes dos Santos; Silva, Ademir X., E-mail: pereiraws@gmail.com, E-mail: wspereira@inb.gov.br, E-mail: franklincunha@inb.gov.br, E-mail: lararapls@hotmail.com, E-mail: Ademir@nuclear.ufrj.br [Coordenacao de Pos-Graduacao e Pesquisa de Engenharia (PEN/COPPE/UFRJ), Rio de Janeiro, RJ (Brazil). Programa de Engenharia Nuclear

    2017-07-01

    The Initial Deposit of Low Activity Radioactive Waste - DIRBA is an ancillary facility to the Nuclear Fuel Factory - FCN for the initial storage of low activity radioactive waste generated in the nuclear fuel cycle under the responsibility of the FCN. Currently approximately 460 200-liter drums containing Class 2.3 waste are stored: Waste containing Natural Radionuclides (RBMN-RN). As part of the nuclear licensing of the facility, an area radiological monitoring program was developed with monthly monitoring of 17 exposure points, 3 direct long-distance air sampling points with CAM alpha-7 monitors, monitored in January and 9 points where smears of alpha long half-life emitters were monitored in January. The mean exposure rate between points was 0.5 μSv∙h{sup -1}, with a maximum of 1.27 μSv∙h{sup -1} varying, on average, between 0.98 μSv∙h{sup -1} at point P1 to 0.23 μSv∙h{sup -1} at P11. The monthly average was the same, 0.50 μSv∙h-1, ranging from 0.46 μSv∙h{sup -1} (November) to 0.57 μSv∙h{sup -1} (August). The half-life long-lived alpha sampling were all below the MDA as well as the 9 smears. Regarding the requirements of monitored areas, the deposit must be considered as supervised area, from the point of view of radioprotection. The possibility of tipping the drums or other accidents with spillage of material contained into them caused, in a proactive way, the area to be considered a controlled area. (author)

  11. 30 years of monitoring environmental radioactivity in the Federal Republic of Germany

    International Nuclear Information System (INIS)

    1985-01-01

    The individual sections of the report describe the development of monitoring functions and of the contamination of the atmosphere and the biosphere by radioactive substances. After environmental radioactivity due to the fallout of nuclear explosions reached a peak level in 1963, its contribution to radiation exposure today is insignificant in comparison with natural radioactivity. Moreover, monitoring by authorities of the emissions and the environmental impact of nuclear installations has been extended during the past 20 years in such a way that the existing network of measuring stations takes full account of the increased number of nuclear installations. The monitoring results show that nuclear installations do not make any considerable contribution to environmental radioactivity. (orig./PW) [de

  12. Evaluation of environmental radioactivity monitoring data around the Kartini Reactor area

    International Nuclear Information System (INIS)

    Yazid, M; Sutrisno; Sukarman-Aminjoyo; Zaenal-Abidin

    1996-01-01

    Evaluation of environmental radioactivity monitoring data around the Kartini Reactor area has been done. The aim of this investigation is for tracing the possibility of radioactivity released in the environment during the operation of Kartini reactor. The data was evaluated were monthly monitored data taken from 1986 to 1994 period. The method of analysis was done by comparing the environmental radioactivity data before and after reactor commissioning, off side the reactor up to a radius of 5.000 meters and more than 5.000 meters from Kartini reactor and also compared to the maximum permissible radioactivity according to the current regulation. This evaluation showed that there was no indication of radioactivity release to the environment during this period of reactor operation

  13. Radioactive contamination in monitors received for calibration

    International Nuclear Information System (INIS)

    Dias, Paulo S.; Santos, Gilvan C. dos; Brunelo, Maria Antonieta G.; Paula, Tiago C. de; Pires, Marina A.; Borges, Jose C.

    2013-01-01

    The Calibration Laboratory - LABCAL, from the Research Center for Metrology and Testing - METROBRAS, MRA Comercio de Instrumentos Eletronicos Ltda., began activities in October 2008 and, in August 2009, decided to establish a procedure for monitoring tests, external and internal, of all packages received from customers, containing instruments for calibration. The aim was to investigate possible contamination radioactive on these instruments. On July 2011, this procedure was extended to packagings of personal thermoluminescent dosemeters - TLD, received by the newly created Laboratory Laboratorio de Dosimetria Pessoal - LDP . In the monitoring procedure were used monitors with external probe, type pancake, MRA brand, models GP - 500 and MIR 7028. During the 37 months in which this investigation was conducted, were detected 42 cases of radioactive contamination, with the following characteristics: 1) just one case was personal dosimeter, TLD type; 2) just one case was not from a packing from nuclear medicine service - was from a mining company; 3) contamination occurred on packs and instruments, located and/or widespread; 4) contamination values ranged from slightly above the level of background radiation to about a thousand fold. Although METROBRAS has facilities for decontamination, in most cases, especially those of higher contamination, the procedure followed was to store the contaminated material in a room used for storage of radioactive sources. Periodically, each package and/or instrument was monitored, being released when the radiation level matched the background radiation. Every contamination detected, the client and/or owner of the instrument was informed. The Brazilian National Energy Commission - CNEN, was informed, during your public consultation for reviewing the standard for nuclear medicine services, held in mid-2012, having received from METROBRAS the statistical data available at the time. The high frequency of contamination detected and the high

  14. Monitoring of radioactivity in the environment 201

    International Nuclear Information System (INIS)

    Moeller, B.; Dyve, J.E.; Tazmini, K.

    2013-01-01

    The Report summarizes the data from Norwegian Radiation Protection Authority and The Norwegian Civil Defence monitoring programs for radioactivity in the environment in 2011. A short description of the systems is also presented.(Author)

  15. Roshydromet system of environment radioactive contamination monitoring in the Arctic region of Russia

    International Nuclear Information System (INIS)

    Chelukanov, V.

    1995-01-01

    159 arctic hydrometerological stations take measurements of gamma radiation. 51 stations monitor the density of atmospheric radioactive fallout and 12 stations monitor the concentration of aerosols. 13 hydrological stations sited in the mouths of main Arctic Ocean rivers take water samples. Regional laboratories carry out isotop analysis of samples. Information on high levels of a radioactivity measured at the monitoring stations, as well as information on abnormal radioactivity from regional laboratories are transmitted to the Information Centers on the monitoring system (Moscow and Obnisk) by cable. 2 figs., 1 tab

  16. Survey monitoring of environmental radioactivity in Chuncheon area

    Energy Technology Data Exchange (ETDEWEB)

    Cha, Moon Hoe.; Hwang, Sang Gyu [Chuncheon Regional Radioactivity Monitoring Station, Chuncheon (Korea, Republic of)

    2002-12-15

    Gross beta radioactivities in airborne dust, fallout, precipitation and tap water, and gamma exposure rates have been monitored periodically in 2002 at Chunchon Regional Radioactivity Monitoring Station. The concentrations of radioactive nuclide of {sup 7}Be and {sup 137}Cs on airborne dust, and {sup 7}Be, {sup 40}K and {sup 137}Cs on fallout, precipitation have been analyzed monthly. The {sup 7}Be, {sup 40}K, {sup 137}Cs etc. concentrations in the 19 foodstuffs(peanut, chestnut, walnut, pine nut acorn, oak mushroom, western mushroom, winter mushroom, oyster mushroom, coffee, green tea, ginseng tea, soils, cereals, vegetable, indicator plant) and 5 tap water sampled in Youngseo area of Kangwon-do have also been measured. No significant changes from the previous years have been found in gross beta radioactivities in environmental samples and gamma exposure rates. The concentrations of {sup 7}Be, {sup 40}K, and {sup 137}Cs nuclide in the foodstuffs sampled in Youngseo area are less(or slightly higher in some cases) than the MDA values, except {sup 40}K nuclide. All the concentrations of {sup 137}Cs nuclides in the water are less than the MDA values.

  17. Survey monitoring of environmental radioactivity in Chuncheon area

    Energy Technology Data Exchange (ETDEWEB)

    Cha, Moon Hoe.; Hwang, Sang Gyu [Chuncheon Regional Radioactivity Monitoring Station, Chuncheon (Korea, Republic of)

    2003-12-15

    Gross beta radioactivities in airborne dust, fallout, precipitation and tap water, and gamma exposure rates have been monitored periodically in 2003 at Chunchon Regional Radioactivity Monitoring Station. The concentrations of radioactive nuclide of {sup 7}Be and {sup 137} Cs on airborne dust, and {sup 7}Be, {sup 40}K and {sup 137}Cs on fallout, precipitation have been analyzed monthly. The {sup 7}Be, {sup 40}K, {sup 137}Cs etc. concentrations in the 22 foodstuffs(peanut, chestnut, walnut, pine nut acorn, oak mushroom, western mushroom, winter mushroom, oyster mushroom, coffee, green tea, ginseng tea, soils, cereals, vegetable, indicator plant) and 10 tap water sampled in Youngseo area of Kangwon-do have also been measured. No significant changes from the previous years have been found in gross beta radioactivities in environmental samples and gamma exposure rates. The concentrations of {sup 7}Be, {sup 40}K, and {sup 137}Cs nuclide in the foodstuffs sampled in Youngseo area are less(or slightly higher in some cases) than the MDA values, except {sup 40}K nuclide. All the concentrations of {sup 137}Cs nuclides in the water are less than the MDA values.

  18. Survey monitoring of environmental radioactivity in Chuncheon area

    International Nuclear Information System (INIS)

    Lee, Byung Ki.; Hwang, Sang Kyu

    2001-12-01

    Gross beta radioactivities in airborne dust, fallout, precipitation and tap water, and gamma exposure rates have been monitored periodically in 2001 at Chunchon Regional Radioactivity Monitoring Station. The concentrations of radioactive nuclide of 7 Be and 137 Cs on airborne dust, and 7 Be, 40 K and 137 Cs on fallout, precipitation have been analyzed monthly. The 7 Be, 40 K, 137 Cs and 226 Ra etc. concentrations in the 23 foodstuffs(potato, sweet potato, bean sprout, onion, pumpkin, spinach, welsh onion, radish leaves, red pepper, garlic, lettuce, apple, persimmon, orange, pear, grape, mackerel, Alaska pollack, hairtail, squid oyster, baby clam, mussel) and 5 tap water sampled in Youngseo area of Kangwon-do have also been measured. No significant changes from the previous years have been found in gross beta radioactivities in environmental samples and gamma exposure rates. The concentrations of 7 Be, 40 K, and 137 Cs nuclide in the foodstuffs sampled in Youngseo area are less(or slightly higher in some cases) than the MDA values, except 40 K nuclide. All the concentrations of 137 Cs and 226 Ra nuclides in the water are less than the MDA values

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

    International Nuclear Information System (INIS)

    2010-01-01

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

  20. Status of 2009 radioactivity monitoring in French Polynesia. Results of IRSN's monitoring network

    International Nuclear Information System (INIS)

    2010-01-01

    Radiological monitoring of the French environment is one of IRSN's permanent tasks as part of public policy on nuclear safety and radiological protection. It is helping to guarantee the best possible protection of the population. Exercised in Polynesia since 1962, this monitoring, which takes place on seven islands (Tahiti, Maupiti, Hao, Rangiroa, Hiva Oa, Mangareva and Tubuai) representing the five archipelagoes, consists in regularly collecting samples of various kinds from the different environmental compartments (air, water, soil, food...) with which the population may be in contact. Regarding food, the samples analyzed are representative of the diet of Polynesians living in the five archipelagoes of that territory. They come from the marine environment of the open sea, from the marine lagoon environment and from the terrestrial environment. Almost all samples are measured at the IRSN Laboratory for the Environment Study and Monitoring, based in Vairao, Tahiti Island. The 239 samples collected in 2009 were measured by Hp-Ge low background gamma spectrometry in order to be able to characterize lowest possible radioactivity levels. The levels of activity of Pu isotopes have also been determined for 17 selected samples and tritium activities for 15 water samples. The results for the year 2009 are in the continuity of a regular reduction of the levels of radioactivity since the stop, in 1974, of the French atmospheric tests. This residual radioactivity relates to primarily the 137 Cs. In term of additional dose, this artificial and residual radioactivity is lower than 5 μSv.y -1 (5 micro Sieverts per year). This value corresponds to less than 0, 5 % of exposure due to natural radioactivity in Polynesia (approximately 1000 μSv.y -1 ). (authors)

  1. Investigation on supervising and monitoring of major radioactive pollution source

    International Nuclear Information System (INIS)

    Zeng Yibing; Zhang Zongrang; Men Meng; Zhang Peng

    2005-01-01

    Objective: In order to optimize the supervisory monitoring proposal of the major radioactive enterprises. Methods: The authors have worked out the public doses within the range of 0-1 km as well as 1-2 km through monitoring analysis of the radioactive pollutant enterprises on the samples of its surrounding air, water, soil and organism. Results: Generally the pollutant range of the enterprises runs from 0 to 1.5 km. Conclusion: Unnecessary working hours can be shortened as long as we keep the routine supervisory monitor of pollutant enterprises within the range of 2 km. (authors)

  2. Survey monitoring of environmental radioactivity in Busan area

    Energy Technology Data Exchange (ETDEWEB)

    Yang, Han Soeb; Jang, Young A. [Busan Regional Monitoring Station, Busan (Korea, Republic of)

    2003-12-15

    At Regional Radioactivity Monitoring Station in Pusan have been measured periodically in 2003 gross beta activities in the airborne dust, fallout, precipitation and tap water and gamma exposure rates. Gamma nuclides in airborne dust, fallout and precipitation have also been monitored at the station. As a part of environmental radiation/radioactivity distribution survey around Busan foodstuffs, dust, drinking water (total 24ea) samples were taken from sampling sites which were selected by KINS. We analysis gamma nuclide for all. No significant changes from the previous survey have been found in both beta activities and gamma exposure rates. As the results of analyzing an gamma nuclide concentration in environmental samples in Pusan are fee of radiological contaminants.

  3. Survey monitoring of environmental radioactivity in Busan area

    International Nuclear Information System (INIS)

    Yang, Han Soeb; Jang, Young A.

    2003-12-01

    At Regional Radioactivity Monitoring Station in Pusan have been measured periodically in 2003 gross beta activities in the airborne dust, fallout, precipitation and tap water and gamma exposure rates. Gamma nuclides in airborne dust, fallout and precipitation have also been monitored at the station. As a part of environmental radiation/radioactivity distribution survey around Busan foodstuffs, dust, drinking water (total 24ea) samples were taken from sampling sites which were selected by KINS. We analysis gamma nuclide for all. No significant changes from the previous survey have been found in both beta activities and gamma exposure rates. As the results of analyzing an gamma nuclide concentration in environmental samples in Pusan are fee of radiological contaminants

  4. Radioactivity, radiation protection and monitoring during dismantling of light-water reactors

    International Nuclear Information System (INIS)

    Hummel, L.; Zech, J.B.

    2005-01-01

    Based on the radioactivity inventory in the systems and components of light-water reactors observed during operation, the impact of actions during plant emptying after the conclusion of power operation and possible subsequent long-term safe enclosure concerning the composition of the nuclide inventory of the plant to be dismantled will be described. Derived from this will be the effects on radioactivity monitoring in the plant, physical radiation protection monitoring, and the measured characterization of the residual materials resulting from the dismantling. The impact of long-term interim storage will also be addressed in the discussion. The talk should provide an overview of the interrelationships between source terms, decay times and the radioactivity monitoring requirements of the various dismantling concepts for commercial light-water reactors. (orig.)

  5. Environmental radioactive monitoring in Itu, Sao Paulo, Brazil

    International Nuclear Information System (INIS)

    1990-01-01

    The results of the environmental monitoring of a region near to a radioactive materials deposit in Sao Paulo State, Brazil, are presented. The radioactive materials are uranium and thorium hydroxides from monazite processing. The temporal variation of 226 Ra was determined in the superficial and underground water, showing no increase for the former and a maximum concentration of 0,306 Bq/L for the latter. 21 figs., 17 tabs

  6. Survey monitoring of environmental radioactivity in Chuncheon area

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Byung Ki.; Hwang, Sang Kyu [Chuncheon Regional Radioactivity Monitoring Station, Chuncheon (Korea, Republic of)

    2001-12-15

    Gross beta radioactivities in airborne dust, fallout, precipitation and tap water, and gamma exposure rates have been monitored periodically in 2001 at Chunchon Regional Radioactivity Monitoring Station. The concentrations of radioactive nuclide of {sup 7}Be and {sup 137}Cs on airborne dust, and {sup 7}Be, {sup 40}K and {sup 137}Cs on fallout, precipitation have been analyzed monthly. The {sup 7}Be, {sup 40}K, {sup 137}Cs and {sup 226}Ra etc. concentrations in the 23 foodstuffs(potato, sweet potato, bean sprout, onion, pumpkin, spinach, welsh onion, radish leaves, red pepper, garlic, lettuce, apple, persimmon, orange, pear, grape, mackerel, Alaska pollack, hairtail, squid oyster, baby clam, mussel) and 5 tap water sampled in Youngseo area of Kangwon-do have also been measured. No significant changes from the previous years have been found in gross beta radioactivities in environmental samples and gamma exposure rates. The concentrations of {sup 7}Be, {sup 40}K, and {sup 137}Cs nuclide in the foodstuffs sampled in Youngseo area are less(or slightly higher in some cases) than the MDA values, except {sup 40}K nuclide. All the concentrations of {sup 137}Cs and {sup 226}Ra nuclides in the water are less than the MDA values.

  7. Survey monitoring of environmental radioactivity in Chuncheon area

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Byung Ki.; Hwang, Sang Kyu [Chuncheon Regional Radioactivity Monitoring Station, Chuncheon (Korea, Republic of)

    2000-12-15

    Gross beta radioactivities in airborne dust, fallout, precipitation and tap water, and gamma exposure rates have been monitored periodically in 2000 at Chunchon Regional Radioactivity Monitoring Station. The concentrations of radioactive nuclide of {sup 7}Be and {sup 137}Cs on airborne dust, and {sup 7}Be, {sup 40}K and {sup 137}Cs on fallout, precipitation have been analyzed monthly. The {sup 7}Be, {sup 40}K, {sup 137}Cs and {sup 226}Ra etc. concentrations in the 23 foodstuffs(potato, sweet potato, bean sprout, onion, pumpkin, spinach, welsh onion, radish leaves, red pepper, garlic, lettuce, apple, persimmon, orange, pear, grape, mackerel, Alaska pollack, hairtail, squid oyster, baby clam, mussed) and 5 tap water sampled in Youngsoe area of Kangwon-do have also been measured. No significant changes from the previous years have been found in gross beta radioactivities in environmental samples and gamma exposure rates. The concentrations of {sup 7}Be, {sup 40}K, and {sup 137}Cs nuclide in the foodstuffs sampled in Youngseo area are less(or slightly higher in some cases) than the MDA value, except {sup 40}K nuclide. The concentrations of {sup 137}Cs and {sup 226}Ra nuclide in tap water are less(or is slightly higher in one sample) than the MDA value.

  8. Ambient radioactivity monitoring V: Marine environment, fish and marine organisms

    International Nuclear Information System (INIS)

    Wedekind, C.; Kanisch, G.

    1996-01-01

    The sea, originally thought to have an almost unlimited capacity of uptake of pollutants due to its water volumes available for dilution, was shown by growing insight into the physical, chemical and ecologic interdependencies to be a sensitive ecosystem. Its limits to cope with growing pollution are increasingly becoming clear, and this is a particular reason to perform radioactivity monitoring of the sea water, as radioactivity is transferred to the marine organisms. Organisms selected for monitoring are fish and crustaceans. (orig.) [de

  9. Annual report on radioactive discharges and monitoring of the environment 1992. V. 1

    International Nuclear Information System (INIS)

    1993-01-01

    This Annual Report supplements the Company's Health and Safety Annual Report by providing more detailed information on radioactive discharges, monitoring of the environment and critical group doses. BNFL has published Annual Reports on Radioactive Discharges and Monitoring of the Environment, covering the period from 1977 to the present. For 1990 this report has been sub-divided into two complementary parts. Volume I includes annual data for each of the Company sites on radioactive discharges into the environment and the associated environmental monitoring programmes. Volume II reproduces the Certificates of Authorisation under which the Company operates and the statutory environmental monitoring programmes which relate to them. (author)

  10. Annual report on radioactive discharges and monitoring of the environment 1990. V. 1

    International Nuclear Information System (INIS)

    1991-01-01

    This Annual Report supplements the Company's Health and Safety Annual Report by providing more detailed information on radioactive discharges, monitoring of the environment and critical group doses. BNFL has published Annual Reports on Radioactive Discharges and Monitoring of the Environment, covering the period from 1977 to the present. For 1990 this report has been sub-divided into two complementary parts. Volume I includes annual data for each of the Company sites on radioactive discharges into the environment and the associated environmental monitoring programmes. Volume II reproduces the Certificates of Authorisation under which the Company operates and the statutory environmental monitoring programmes which relate to them. (author)

  11. Annual report on radioactive discharges and monitoring of the environment 1990. V. 2

    International Nuclear Information System (INIS)

    1991-01-01

    This Annual Report supplements the Company's Health and Safety Annual Report by providing more detailed information on radioactive discharges, monitoring of the environment and critical group doses. BNFL has published Annual Reports on Radioactive Discharges and Monitoring of the Environment, covering the period from 1977 to the present. For 1990 this report has been sub-divided into two complementary parts. Volume I includes annual data for each of the Company sites on radioactive discharges into the environment and the associated environmental monitoring programmes. Volume II reproduces the Certificates of Authorisation under which the Company operates and the statutory environmental monitoring programmes which relate to them. (author)

  12. Biological sampling for marine radioactivity monitoring

    International Nuclear Information System (INIS)

    Fowler, S.W.

    1997-01-01

    Strategies and methodologies for using marine organisms to monitor radioactivity in marine waters are presented. When the criteria for monitoring radioactivity is to determine routes of radionuclide transfer to man, the ''critical pathway'' approach is often applied. Alternatively, where information on ambient radionuclide levels and distributions is sought, the approach of selecting marine organisms as ''bioindicators'' of radioactivity is generally used. Whichever approach is applied, a great deal of knowledge is required about the physiology and ecology of the specific organism chosen. In addition, several criteria for qualifying as a bioindicator species are discussed; e.g., it must be a sedentary species which reflects the ambient radionuclide concentration at a given site, sufficiently long-lived to allow long-term temporal sampling, widely distributed to allow spatial comparisons, able to bioconcentrate the radionuclide to a relatively high degree, while showing a simple correlation between radionuclide content in its tissues with that in the surrounding waters. Useful hints on the appropriate species to use and the best way to collect and prepare organisms for radioanalysis are also given. It is concluded that benthic algae and bivalve molluscs generally offer the greatest potential for use as a ''bioindicator'' species in radionuclide biomonitoring programmes. Where knowledge on contribution to radiological dose is required, specific edible marine species should be the organisms of choice; however, both purposes can be served when the edible species chosen through critical pathway analysis is also an excellent bioaccumulator of the radionuclide of interest. (author)

  13. Survey monitoring of environmental radioactivity in Gunsan area

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Byoung Ho; Ro, Jeong Suk [Kunsan Regional Radioactivity Monitoring Station, Gunsan (Korea, Republic of)

    2001-01-15

    At Regional Radioactivity Monitoring Station in Kunsan have been measured priodically in 2000 gross beta activities in the airborne dust, fallout, precipitation and tap water and gamma exposure rates. Artificial radionuclide of {sup 137}Cs in airborne dust, fallout and precipitation have also been monitored at the station. As a part of environmental radiation/radioactivity distribution survey around Jeon-buk, vegetables, fishes, shellfishes, drinking water (total 33ea) samples were taken from sampling sites which were selected by KINS. We analysis gamma isotope for all. No significant Changes from the previous survey have been found in both beta activities and gamma exposure rates. As the results of analyzig an artificial nuclide concentration in living environmental sample in Jeon-buk are I fee of radiological contaminants.

  14. Survey monitoring of environmental radioactivity in Gunsan area

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Byoung Ho; Ro, Jeong Suk [Kunsan Regional Radioactivity Monitoring Station, Gunsan (Korea, Republic of)

    2002-12-15

    At Regional Radioactivity Monitoring Station in Kunsan have been measured priodically in 2002 gross beta activities in the airborne dust, fallout, precipitation and tap water and gamma exposure rates. Artificial radionuclide of {sup 137}Cs in airborne dust, fallout and precipitation have also been monitored at the station. As a part of environmental radiation/radioactivity distribution survey around Jeon-buk, vegetables, fishes, shellfishes, drinking water (total 33ea) samples were taken from sampling sites which were selected by KINS. We analysis gamma isotope for all. No significant changes from the previous survey have been found in both beta activities and gamma exposure rates. As the results of analyzig an artificial nuclide concentration in living environmental sample in Jeon-buk are fee of radiological contaminants.

  15. Survey monitoring of environmental radioactivity in Gunsan area

    International Nuclear Information System (INIS)

    Kim, Byoung Ho; Ro, Jeong Suk

    2002-12-01

    At Regional Radioactivity Monitoring Station in Kunsan have been measured priodically in 2002 gross beta activities in the airborne dust, fallout, precipitation and tap water and gamma exposure rates. Artificial radionuclide of 137 Cs in airborne dust, fallout and precipitation have also been monitored at the station. As a part of environmental radiation/radioactivity distribution survey around Jeon-buk, vegetables, fishes, shellfishes, drinking water (total 33ea) samples were taken from sampling sites which were selected by KINS. We analysis gamma isotope for all. No significant changes from the previous survey have been found in both beta activities and gamma exposure rates. As the results of analyzig an artificial nuclide concentration in living environmental sample in Jeon-buk are fee of radiological contaminants

  16. Radioactive gases monitor system: tritium, radon, noble gases

    International Nuclear Information System (INIS)

    Egey, J.Z.; Matatagui, E.

    2015-01-01

    A system for monitoring the radioactive gases tritium, radon and noble gases is described. We present the description of the sensor and the associated electronics that have been developed to monitor the presence of radioactive gases in air or other gaseous effluents. The system has a high sensitivity and a wide range of operation. The sensor is an ionization chamber, featuring the internal circulation of the gas to monitor and the associated electronics has a resolution better than 10 E-15A (fA). It allows the detection of the individual pulses that are produced during the alpha decay of radon and its daughter elements. The measurement system is made up of a commercial data acquisition system connected to a computer. The acquired data is presented on a graphical display and it is stored for later processing and analysis. We have a system that is of simple construction and versatile. Here we present the experimental results. (authors) [es

  17. Annual report on radioactive discharges and monitoring of the environment 1986

    International Nuclear Information System (INIS)

    1987-01-01

    British Nuclear Fuels plc (BNFL) provides a comprehensive range of nuclear fuel cycle services, ie the purification and processing of uranium ore concentrates, the enrichment of uranium, the manufacture of uranium and plutonium based fuels, the reprocessing of irradiated fuel, and the conditioning and storage of nuclear materials and radioactive wastes. Some of these activities give rise to discharges of radioactive isotopes to the environment. This annual report follows the pattern established in 1977 in that it gives information on radioactive discharges, through authorised and scheduled outlets, and on environmental monitoring for all of the Company's Works and sites, ie Sellafield Site and the Drigg Storage and Disposal Site; Chapelcross Works; Springfield Works and the Ulnes Walton Disposal Site; and Capenhurst Works. Where a site also encompasses laboratories of the United Kingdom Atomic Energy Authority (UKAEA) reference is made to the significance of the discharges from the latter. It also includes assessment of radiation doses to representative members of the most highly exposed group of the general population (the critical group) for the most important environmental pathways in the vicinity of each site. Information for the period 1971-76 inclusive has also been published by BNFL and prior to 1971, the year in which BNFL was formed, information was published by the UKAEA. An appendix contains certificates of Authorisation granted by the DOE, MAFF and Scottish Office imposing limits and conditions relating to methods of disposal and quantities to be discharged. (author)

  18. Radioactivity monitoring in Ireland of air, deposition and water 1982-1987

    International Nuclear Information System (INIS)

    Sequeira, S.; McRandall, M.; Hayden, E.; Cunningham, J.D.

    1989-02-01

    The Nuclear Energy Board in conjunction with the Meteorological Service undertakes an environmental radioactivity monitoring programme with the objective of determining levels of artificially produced radioactivity in the Irish environment. The levels of radioactivity in airbourne dust, total fallout samples, precipitation and drinking water are presented for 1982, 1983, 1984, 1985, 1986 and 1987

  19. Bulk monitoring and segregation of radioactive wastes

    Energy Technology Data Exchange (ETDEWEB)

    Beddow, H.; Adsley, I.; Pearman, I.; Sweeney, A.; Davies, M., E-mail: helen.beddow@nuvia.co.uk [Nuvia Limited, Harwell Oxford, Didcot, Oxfordshire (United Kingdom)

    2014-07-01

    Several sites in the UK are contaminated by radioactive legacy wastes. These include; radium luminising sites and more recently the oil, and (potentially) fracking industries; sites contaminated from thorium gas mantle factories; old nuclear research sites; nuclear power sites, and the Sellafield reprocessing site. Nuvia has developed a suite of technologies to map the location of and to recover and process wastes during remedial operations. The main method for delineating contaminated areas in-situ is by use of the Groundhog system, whilst bulk monitoring methods employ the Gamma Excavation Monitor, the High Resolution Assay Monitor, and the Conveyor Active Particle System. (author)

  20. Bulk monitoring and segregation of radioactive wastes

    International Nuclear Information System (INIS)

    Beddow, H.; Adsley, I.; Pearman, I.; Sweeney, A.; Davies, M.

    2014-01-01

    Several sites in the UK are contaminated by radioactive legacy wastes. These include; radium luminising sites and more recently the oil, and (potentially) fracking industries; sites contaminated from thorium gas mantle factories; old nuclear research sites; nuclear power sites, and the Sellafield reprocessing site. Nuvia has developed a suite of technologies to map the location of and to recover and process wastes during remedial operations. The main method for delineating contaminated areas in-situ is by use of the Groundhog system, whilst bulk monitoring methods employ the Gamma Excavation Monitor, the High Resolution Assay Monitor, and the Conveyor Active Particle System. (author)

  1. Infrared thermography applied to monitoring of radioactive waste drums

    International Nuclear Information System (INIS)

    Kelmer, P.; Camarano, D.M.; Calado, F.; Phillip, B.; Viana, C.; Andrade, R.M.

    2013-01-01

    The use of thermography in the inspection of drums containing radioactive waste is being stimulated by the absence of physical contact. In Brazil the majority of radioactive wastes are compacted solids packed in metal drums stored temporarily for decades and requires special attention. These drums have only one qualitative indication of the radionuclides present. However, its structural condition is not followed systematically. The aim of this work is presents a methodology by applying thermography for monitoring the structural condition of drums containing radioactive waste in order to detect degraded regions of the drums. (author)

  2. Environmental radioactive monitoring, evaluation and protection in luminous workshops of a factory

    International Nuclear Information System (INIS)

    Dai Hanbin; Xiang Ming; Tan Jianzu

    2009-01-01

    Fluorescent technique is often used to display instrumental indicator in the dark environment. Luminous workshops of a factory smear and depict the glassware by means of fluorescent power with adulterated radioactive matter. Because of adulterated radioactive matters such as 226 Ra, 40 K emit alpha-ray,beta-ray and gamma-ray, while they decay spontaneously, and high dose or cumulative radiation can damage human body in different degrees. Therefore, any radioactive damage to human body caused by over-safety dose should be prevented strictly during the working. To ensure health and safety of working staff in luminous workshop and the public, it is necessary to regularly have radioactive monitoring and evaluation to luminous workshop and its surrounding environment. Through the environment radioactive monitoring, the authors analyze its environmental radioactive level,and try to find out the possible problems so as to propose some protective measures for personal health. (authors)

  3. Experience during the monitoring of inactive scrap for the detection of inadvertent presence of radioactivity

    International Nuclear Information System (INIS)

    Sharma, Ranjit; Kumar, Anoj; Vikas; Patra, R.P.; Kumar, Vikas; Singh, Rajvir; Pradeepkumar, K.S.

    2012-01-01

    The inspection and certification of scrap material from nuclear facilities is a regulatory requirement to ensure that radioactive material will not reach public domain. Around the world, cases involving radioactive contamination of metallic components have occurred due to radioactive sources/contaminated metal scrap reaching the public domain. Radiological monitoring of inactive scrap material is essential as it may get into various usages in public domain where controls cannot be implemented. The method of detection is measurement of gamma dose rates due to any loose/fixed radioactive contamination in the scrap or presence of any radioactive material/source. In addition prevention of any inadvertent/malicious act leading to radioactive material reaching the public domain through scrap being essential, this monitoring gains further importance. This paper describes the methodology and experience in detection of presence of radioactivity at inactive Scrap monitoring facility. Even though radioactive sources of high strength with potential for serious environmental hazard have not been detected, few cases of contaminated material (MS plate/equipments etc with extremely low level of 137 Cs and Uranium contamination) have been detected and identified using portable gamma spectrometer. If proper monitoring is not carried out the dispersal of radioactivity to the environment can be a matter of concern due to metal scrap reaching recycling industry resulting in huge cost of decontamination and waste disposal. These events may also have negative impact on the export from the country resulting in economic losses. The impact of such events can be ruled out by effective scrap monitoring techniques which ensure that even small quantity of radioactivity escaping into public domain can be prevented. The methodology followed for monitoring of inactive scrap is found to be effective even for detection of presence of very low level of radioactivity

  4. Annual report on radioactive discharges and monitoring of the environment 1991. V. 1

    International Nuclear Information System (INIS)

    1992-01-01

    This Annual Report supplements and updates British Nuclear Fuel plc's Health and Safety and the Environment Annual Report by providing more detailed information on radioactive discharges, monitoring of the environment and critical groups doses. BNFL has published Annual Reports on Radioactive Discharges and Monitoring of the Environment since 1977. This year the report is again sub-divided into two complementary volumes. Volume I includes, for each of the Company's sites, annual data on radioactive discharges into the environment and the associated environmental monitoring programmes. Critical groups doses for each site are presented in summary tables at the beginning of each chapter. (author)

  5. Experience during the monitoring of inactive scrap for the detection of inadvertent presence of radioactivity

    International Nuclear Information System (INIS)

    Sharma, Ranjit; Anoj Kumar; Vikas; Singh, Rajvir; Patra, R.P.; Vikas Kumar; Pradeepkumar, K.S.

    2012-01-01

    The paper describes about the experience gained during the radiation monitoring of inactive scrap generated at various nuclear facilities. This type surveillance is carried out to prevent the spread of radioactivity in public domain and also as requirement by regulatory authorities. The inspection and certification of scrap material from nuclear facilities is a regulatory requirement to ensure that no radioactive material reaches public domain. This paper describes the methodology and experience in detection of radioactivity at inactive Scrap monitoring facility. Inactive scraps (metallic and non metallic) generated from various nuclear facilities of BARC, Trombay is dispatched to Trombay Village Store (TVS) for temporary storage before auction to the public. The monitoring at the facility includes visual inspection and radiation measurement before loading the scrap in the truck. An online PC based monitoring system and portable monitoring instruments in the range (nSv/h-µSv/h) are used to carry out radiation monitoring of inactive scrap loaded in a vehicle. Radioactive source of high activity with potential for serious environmental hazard has not been detected, but few cases of presence of radioactive/contaminated material (MS plate/equipments with low level of 137 Cs contamination) have been detected and identified using portable gamma spectrometer. Implementation of strict regulatory measures and radiation monitoring at nuclear facilities can minimize the probability of radioactive material reaching the public domain. The methodology followed for monitoring of inactive scrap is found to be effective even for detection of presence of radioactivity in scrap if any. (author)

  6. MONITORING OF RADIOACTIVITY AT DNURT CAMPUS

    Directory of Open Access Journals (Sweden)

    L. F. Dolina

    2016-06-01

    Full Text Available Purpose. The research paper aims to determine radioactive contamination on the territory of campus of Dnipropetrovsk National University of Railway Transport named after Academician V. Lazaryan (DNURT. Methodology. The dosimeters measured the radioactive contamination in different places (points of DNURT campus, focusing on public places. The centres of measurements became dormitories, monuments, stops, main entrances of the new and the old buildings, classrooms, basements, a swimming pool, boiler room and others. Findings. The conducted radiation monitoring for the first time in the history of the University discovered the source of radioactive contamination on DNURT territory and campus. The highest radiation background is observed on three points, namely: the pedestal of the monument, the monument to students-soldiers, the main entrance of the new building (columns. This can be explained by granite materials, which the pedestals and the stairs are made of. Originality. The largest contribution to the total value of annual effective dose of human exposure is made by ionizing radiation sources (IRS of building materials (65 - 70%. The radioactivity level of building materials is determined by the content of natural radionuclides that are included in uranium-radium and thorium decay series (18 and 12 radionuclides as well as potassium-40. Radioactivity of building materials is evaluated by the content of dominant radionuclides radium-226, thorium-232 and potassium-40. Their dominant role is explained by the fact that these long-lived high-energy - emitters are the products of decay of radium-226 in uranium series of and radium-224 in thorium series, exposing radioactive gases (radon-222 and radon-220. Radioactive gases are accumulated in the basements of educational buildings; their decay is accompanied by 100% alpha radiation, which is the most dangerous. Practical value. It is necessary to set radioactivity signs near the objects with high

  7. Radiation protection instrumentation. Monitoring equipment. Atmospheric radioactive iodine in the environment

    International Nuclear Information System (INIS)

    1995-01-01

    This international standard applies to portable or installed equipment for the monitoring of radioactive iodine (such as I-131 or I-125) in air in the environment of nuclear installations during normal operation, during design basis events, and in emergency situations. The monitoring involves continuous sample trapping and, where adequate, automatic start of sampling. The document deals with radioactive iodine monitor design, testing procedures, and documentation. Appended tables refer to the reference and normal testing conditions, tests in normal testing conditions, tests during changes of the affecting quantities, and tests of changes in the air circuit. (P.A.)

  8. Use of Portal Monitors for Detection of Technogenic Radioactive Sources in Scrap Metal

    Science.gov (United States)

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

    2017-11-01

    The article considers the features of organization of scrap-metal primary radiation control on the specialized enterprises engaging in its deep processing and storage at using by primary technical equipment - radiation portal monitors. The issue of this direction relevance, validity of radiation control implementation with the use of radiation portal monitors, physical and organizational bases of radiation control are considered in detail. The emphasis is put on the considerable increase in the number of technogenic radioactive sources detected in scrap-metal that results in the entering into exploitation of radioactive metallic structures as different building wares. One of reasons of such increase of the number of technogenic radioactive sources getting for processing with scrap-metal is the absence of any recommendations on the radiation portal monitors exploitation. The practical division of the article offers to recommendation on tuning of the modes of work of radiation portal monitors depending on influence the weather factor thus allowing to considerably increase the percent of technogenic radioactive sources detection.

  9. Annual report on radioactive discharges and monitoring of the environment 1992. V. 1

    International Nuclear Information System (INIS)

    1993-01-01

    This Annual Report supplements and updates the Company's Environment Annual Report by providing more detailed information on radioactive discharges, monitoring of the environment and critical group doses. BNFL has published Annual Reports on Radioactive Discharges and Monitoring of the Environment since 1977. This year the report is again sub-divided into two complementary volumes. Volume I consists of site papers, one for each of the Company's sites and includes annual data on radioactive discharges into the environment and the associated environmental monitoring programmes. Critical group doses for each site are presented in summary tables at the beginning of each Site paper. Volume II reproduces the Certificates of Authorisation regulating the Company's discharges and the statutory environmental monitoring programmes which relate to them. (Author)

  10. Implementation vigenere algorithm using microcontroller for sending SMS in monitoring radioactive substances transport system

    International Nuclear Information System (INIS)

    Adi Abimanyu; Nurhidayat; Jumari

    2013-01-01

    Aspects of safety and security of radioactive substances from the sender to the receiver is to be secured for not to harm humans. In general, monitoring the transport of radioactive materials is done by communication with a telephone conversation to determine the location and rate of exposure radioactive substances. From the aspect of safety, communication through telephone conversations easily interpreted by others, in addition the possibility of human-error is quite high. SMS service is known for its ease in terms of use so that SMS can be used as a substitute for communication through telephone conversations to monitor the rate of radiation exposure and the position of radioactive substances in the transport of radioactive substances. The system monitors the transport of radioactive materials developed by implement vigenere algorithms using a microcontroller for sending SMS (Short Message Service) to communicate. Tests was conducted to testing encryption and description and computation time required. From the test results obtained they have been successfully implemented vigenere algorithm to encrypt and decrypt the messages on the transport of radioactive monitoring system and the computational time required to encrypt and decrypt the data is 13.05 ms for 36 characters and 13.61 for 37 characters. So for every single character require computing time 0.56 ms. (author)

  11. Proposed radioactive liquid effluent monitoring requirements at the Savannah River Site

    International Nuclear Information System (INIS)

    Jannik, G.T.; Carlton, W.H.; Blunt, B.C.

    1994-01-01

    Clear regulatory guidance exists for structuring a radiological air monitoring program, however, there is no parallel guidance for radiological liquid monitoring. For Department of Energy (DOE) facilities, there are no existing applicable federal regulations, DOE orders, or DOE guidance documents that specify at what levels continuous monitoring, continuous sampling, or periodic confirmatory measurements of radioactive liquid effluents must be made. In order to bridge this gap and to technically justify and document liquid effluent monitoring decisions at DOE's Savannah River Site, Westinghouse Savannah River Company has proposed that a graded, dose-based approach be established, in conjunction with limits on facility radionuclide inventories, to determine the monitoring and sampling criteria to be applied at each potential liquid radioactive effluent point. The graded approach would be similar to--and a conservative extension of--the existing, agreed-upon SRS/EPA-IV airborne effluent monitoring approach documented in WSRC's NESHAP Quality Assurance Project Plan. The limits on facility radionuclide inventories are based on--and are a conservative extension of--the 10 CFR 834, 10 CFR 20, and SCR 61-63 annual limits on discharges to sanitary sewers. Used in conjunction with each other, the recommended source category criteria levels and facility radionuclide inventories would allow for the best utilization of resources and provide consistent, technically justifiable determinations of radioactive liquid effluent monitoring requirements

  12. A monitoring system of radioactive tracers in hydroponic solution for research on plant physiology

    International Nuclear Information System (INIS)

    Suzui, N.; Kawachi, N.; Ishioka, N.; Fujimaki, S.; Yamaguchi, M.

    2009-01-01

    The mechanism of nutrient uptake in plants has received considerable attention in the field of plant science. Here we describe the development of a new monitoring system of radioactive tracers in hydroponic solution, which enables the noninvasive measurement of radioactive tracer uptake by an intact plant. In addition, we incorporated a weighing instrument into this system in order to simultaneously monitor water uptake by the same plant. For an evaluation of this monitoring system, we conducted a tracer experiment with a rice plant and a positron-emitting radioactive tracer, and successfully obtained continuous data for the amounts of radioactive tracer and water taken up by the intact plant over 36 h. (authors)

  13. A monitoring system of radioactive tracers in hydroponic solution for research on plant physiology

    Energy Technology Data Exchange (ETDEWEB)

    Suzui, N.; Kawachi, N.; Ishioka, N.; Fujimaki, S. [Quantum Beam Science Directorate, Japan Atomic Energy Agency, Takasaki, Gunma 370-1292 (Japan); Yamaguchi, M. [Takasaki Advanced Radiation Research Institute, Atomic Energy Agency, Takasaki, Gunma 370-1292 (Japan)

    2009-07-01

    The mechanism of nutrient uptake in plants has received considerable attention in the field of plant science. Here we describe the development of a new monitoring system of radioactive tracers in hydroponic solution, which enables the noninvasive measurement of radioactive tracer uptake by an intact plant. In addition, we incorporated a weighing instrument into this system in order to simultaneously monitor water uptake by the same plant. For an evaluation of this monitoring system, we conducted a tracer experiment with a rice plant and a positron-emitting radioactive tracer, and successfully obtained continuous data for the amounts of radioactive tracer and water taken up by the intact plant over 36 h. (authors)

  14. Radioactivity monitoring of the Irish marine environment 1987

    International Nuclear Information System (INIS)

    O'Grady, J.; Currivan, L.

    1990-06-01

    This report represents the results of the Board's monitoring of radioactivity levels in the Irish marine environment during 1987. The principal objective of the monitoring programme is to obtain estimates of radiation doses to the Irish public arising from caesium-137 and caesium 134, the main contaminating radionuclides. Estimates are presented of the radiation doses to the Irish public arising from the consumption of fish and shellfish contaminated with radiocaesium

  15. Survey monitoring of environmental radioactivity in Gangneung area

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Jae Hwa; An, Mi Jung [Gangnung Regional Radiation Monitoring Station, Gangneung (Korea, Republic of)

    2003-12-15

    The objectives of the project are to get a systematic data for the distribution of environmental radioactivity levels in Gangnung provinces, and use them as a baseline data for the health of the peoples. To monitor the environmental radiation/radioactivity, gross beta activities and gamma exposure rate in the airborne-dust, fallout, precipitation and tap water were measured in Gangnung province during the period of January 1 - December 31, 2003. Waters from drinking water reservoirs, agricultural and marine products were sampled and measured by the HPGe(High Purity Ge)detector for the analysis from some selected areas to make sure of the effect of the fallout due to the atmospheric weapons test. The radioactivity in Kangnung was all about the past data.

  16. Survey monitoring of environmental radioactivity in Gangneung area

    Energy Technology Data Exchange (ETDEWEB)

    An, Dong Wan; An, Mi Jeong [Gangnung Regional Radiation Monitoring Station, Gangneung (Korea, Republic of)

    2001-12-15

    The objectives of the project are to get a systematic data for the distribution of environmental radioactivity levels in Gangnung provinces, and use them as a baseline data for the health of the peoples. To monitor the environmental radiation/radioactivity, gross beta activities and gamma exposure rate in the airborne-dust, fallout, precipitation and tap water were measured in Kangnung province during the period of January 1- December 31, 2001. Waters from drinking water reservoirs, agricultural and marine products were sampled and measured by the HPGe(High Purity Ge)detector for the analysis from some selected areas to make sure of the effect of the fallout due to the atmospheric weapons test. The radioactivity in Kangnung was all about the past data.

  17. Survey monitoring of environmental radioactivity in Gangneung area

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Jae Hwa; An, Mi Jung [Gangnung Regional Radiation Monitoring Station, Gangneung (Korea, Republic of)

    2002-12-15

    The objectives of the project are to get a systematic data for the distribution of environmental radioactivity levels in Gangnung provinces, and use them as a baseline data for the health of the peoples. To monitor the environmental radiation/radioactivity, gross beta activities and gamma exposure rate in the airborne-dust, fallout, precipitation and tap water were measured in Kangnung province during the period of January 1- December 31, 2002. Waters from drinking water reservoirs, agricultural and marine products were sampled and measured by the HPGe(High Purity Ge)detector for the analysis from some selected areas to make sure of the effect of the fallout due to the atmospheric weapons test. The radioactivity in Kangnung was all about the past data.

  18. Real-time alpha monitoring of a radioactive liquid waste stream at Los Alamos National Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Johnson, J.D.; Whitley, C.R.; Rawool-Sullivan, M. [Los Alamos National Lab., NM (United States)

    1995-12-31

    This poster display concerns the development, installation, and testing of a real-time radioactive liquid waste monitor at Los Alamos National Laboratory (LANL). The detector system was designed for the LANL Radioactive Liquid Waste Treatment Facility so that influent to the plant could be monitored in real time. By knowing the activity of the influent, plant operators can better monitor treatment, better segregate waste (potentially), and monitor the regulatory compliance of users of the LANL Radioactive Liquid Waste Collection System. The detector system uses long-range alpha detection technology, which is a nonintrusive method of characterization that determines alpha activity on the liquid surface by measuring the ionization of ambient air. Extensive testing has been performed to ensure long-term use with a minimal amount of maintenance. The final design was a simple cost-effective alpha monitor that could be modified for monitoring influent waste streams at various points in the LANL Radioactive Liquid Waste Collection System.

  19. Evaluation of indigenously developed plastic scintillator sheet detector for surface radioactive contamination monitoring application

    International Nuclear Information System (INIS)

    Sahani, R.M.; Chaudhary, H.S.; Mahala, V.K.; Senwar, K.R.; Meena, J.P.

    2018-01-01

    Radioactive contamination may be caused by release of radioactivity in the environment due to accident at nuclear plant/reactor or spillage of loose radioactive materials in a laboratory. The protection of workers from potentially hazardous radiations emitted by the contaminants is a matter of prime concern. The detection of such radiations requires a monitoring system capable of measuring the level of radioactivity at the contaminated site. Plastic scintillators are widely used for large area radiation monitoring due to the ease of preparation in different shape and sizes. These detectors are sensitive to beta and gamma radiation therefore can be used for monitoring of beta and gamma contamination. In this paper, performance results of indigenously developed plastic scintillator sheet of area 800 cm 2 are reported

  20. Radioactivity Portal Monitor: An actual application and its unconventional detector

    International Nuclear Information System (INIS)

    Izraelevitch, F.; Matatagui, E.; Regueiro Veiga, J.L.

    2012-01-01

    A Radioactivity Portal Monitor is an instrument designed to be used at traffic check points to detect the presence of ionizing radiation in goods, vehicles, people, in critical places such as those at border road crossing, airports and seaports, the entrance at nuclear facilities etc. and alert the officer to the presence of radioactive and nuclear material. We have developed and built, and is in operation a Radioactivity Portal Monitor for gamma radiation. The detector and the associated electronics does not follow a conventional design concept and is based on a pressurized ionization chamber with a very large sensitive volume (60 liters) and a very large length (2 meters), and a very low level DC electronics (fAmp). The System is simple, and its operational characteristics are excellent. The reference radiation level is the background radiation, which is continuously measured, and compared with the radiation level measured when a subject (vehicle, person, good) goes trough the Monitor. The system automatically takes a decision, and alert the officer with an alarm signal if the detected radiation level is larger than the reference (dynamical) level. We will describe the designed system and some of its characterization results will be shown (author)

  1. 30 years of environmental radioactivity monitoring in Romania

    International Nuclear Information System (INIS)

    Sonoc, S.; Alexandrescu, M.; Dovlete, C.; Halasz, A.; Sonoc, N.

    1993-01-01

    A short history of environmental radioactivity monitoring in Romania is presented. Started in 1962 in a few number of sites this activity is performed now by the National Environmental Radioactivity Surveillance Network (NERSN) consisting in 44 local laboratories in each county of the country and a central laboratory, Environmental Radioactivity Laboratory (ERL). The measured values of fallout samples in six points of the network during the period 1962-1992 and the average values of the Cs-137 deposits on Romanian territory from 1977 to 1992 are also presented. The main scientific results of the staff of the central laboratory during the years are mentioned. All these results were possible only due to a persuasive work done during the years by all the staff of the local and central laboratories. (author). 7 figs., 14 refs

  2. Monitoring water for radioactive releases in the United States

    International Nuclear Information System (INIS)

    Porter, C.R.; Broadway, J.A.; Kahn, B.

    1990-01-01

    The major radiological environmental monitoring programs for water in the United States are described. The applications of these programs for monitoring radioactive fallout, routine discharges from nuclear facilities, and releases due to accidents at such facilities are discussed, and some examples of measurements are presented. The programs monitor rainfall, surface water, and water supplies. Samples are usually collected and analyzed on a monthly or quarterly schedule, but the frequency is increased in response to emergencies. (author)

  3. Development of alpha radioactivity monitor using ionized air transport technology

    International Nuclear Information System (INIS)

    Maekawa, Tatsuyuki

    2008-01-01

    A novel alpha radioactivity monitor using ionized air transport technology has been developed for future constitution of 'Clearance Level' for uranium and TRU radioactive waste. We carried out optimum design and realized two kinds of practical alpha activity monitor, combining with radiation detector technology, ionized air physics and computational fluid dynamics. The results will bring paradigm shift on the alpha-ray measurement such as converting 'closely contacting and scanning measurement' to 'remotely measurement in the block', and drastically improve the efficiency of measurement operation. We hope that this technology will be widely endorsed as the practical method for the alpha clearance measurement in future. (author)

  4. Suitability study of using a coincidence monitor for room air radioactivity monitoring in a PET center

    International Nuclear Information System (INIS)

    Roellig, D.; Reichelt, C.; Iwatschenko-Borho, M.

    2001-01-01

    The application of radioactive nuclides in medicine may cause as well radioactive exposure of personnel (Medical Technical Assistants). In the present case the exposure of personnel in the area of medical positron-emission tomography (PET) within the Research Center of Rossendorf due to exhalation of the injected activity by the patient shall be investigated. For this purpose it is necessary to measure the activity concentration of the room air. Conventional methods such as collecting samples on special filters are not suitable due to the short half-life time of the used nuclides. Standard type continuous monitors are hardly suitable as well, because the injected activity of the patient and various radioactive sources required for the calibration of the PET-Camera produce an increased gamma background. In order to eliminate these disturbing influences a monitor has been constructed which uses CCM (cobalt coincidence method) developed by the company Thermo Eberline ESM. This method is specially suitable because upon each radioactive decay of PET nuclides positrons are emitted which in turn annihilate via the simultaneous emission of two 511 keV gamma quanta under an angle of 180 . The air to be measured is sucked through a cavity with two scintillation detectors on opposite sides. The coincident pulses produced by annihilating positrons inside the cavity are counted by a suitable electronic. Gamma quanta from outside the cavity can produce a pulse only in one detector and are rejected. Therefore no heavy lead shielding is required. Besides the mechanical construction of the monitor optimization and calibration for different PET-nuclides had to be performed. Special attention was paid to the sampling system. The air intake had to be close to the breathing zone of the MTA. The hose to the monitor had to be as short as possible. The target of the work was to design a model for an industrial monitor. (orig.) [de

  5. Annual report on radioactive discharges and monitoring of the environment 1981

    International Nuclear Information System (INIS)

    1982-07-01

    A report is given on discharges and disposal of radioactive wastes through authorised outlets and on environmental monitoring for all of BNFL's Company Works and Sites during 1981. At no time during 1981 have discharges and disposals of radioactive wastes at any of the Works or Sites exceeded those laid down in any of the Authorisations. Similarly, environmental monitoring studies have shown that the radiation doses to the most highly exposed group of the general population were significantly lower than the dose limit recommended by the ICRP. (U.K.)

  6. Environmental radioactivity monitoring around Jeongeup ARTI in 2007

    International Nuclear Information System (INIS)

    Lee, Yun Jong; Kwon, Ho Je; Kang, Tai Jin

    2008-03-01

    Because Jeongeup ARTI was designed so that there was not a leakage possibility based on the use of radioactive material and has been operated after acquired an usage permission according to the relevant laws associated with making the use of radiation. It is judged that there may not be the radioactive influence on the surroundings of Jeongeup ARTI. However, an investigation on radioactivity distribution before radiation-use-facilities are installed was not performed, and there is also a possibility that those can be installed additionally. Therefore, it is judged that a preliminary investigation is required to prevents local dwellers from feeling anxious about radiation-use-facilities. The objective of this investigation is to guarantee the health and safety of local residences by detecting a possible radiological effect a prior due to an operation of Jeongeup ARTI, providing the basic data that can estimate environmental effect by radiation, and also to establish a stable research mood by acquiring confidence on analysis results from local dwellers through an scientific and a continuous inspection

  7. Environmental radioactivity monitoring around Jeongeup ARTI in 2007

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Yun Jong; Kwon, Ho Je; Kang, Tai Jin (and others)

    2008-03-15

    Because Jeongeup ARTI was designed so that there was not a leakage possibility based on the use of radioactive material and has been operated after acquired an usage permission according to the relevant laws associated with making the use of radiation. It is judged that there may not be the radioactive influence on the surroundings of Jeongeup ARTI. However, an investigation on radioactivity distribution before radiation-use-facilities are installed was not performed, and there is also a possibility that those can be installed additionally. Therefore, it is judged that a preliminary investigation is required to prevents local dwellers from feeling anxious about radiation-use-facilities. The objective of this investigation is to guarantee the health and safety of local residences by detecting a possible radiological effect a prior due to an operation of Jeongeup ARTI, providing the basic data that can estimate environmental effect by radiation, and also to establish a stable research mood by acquiring confidence on analysis results from local dwellers through an scientific and a continuous inspection.

  8. Radioactivity monitoring in Irish upland lakes 1988 - 1992

    International Nuclear Information System (INIS)

    O'Sullivan, M.; McGarry, A.T.; Lyons, S.; McEnri, C.; Cunningham, J.D.

    1995-04-01

    In 1988, monitoring of radioactivity in upland lakes was initiated in areas of Ireland which had been subjected to highest deposition following the Chernobyl accident. The monitoring programme was continued in 1989 and extended in 1990 to include 25 lakes in 13 counties. This survey provided a comprehensive national picture of the distribution of Chernobyl contamination in Irish freshwater lakes. In 1991 and 1992, the monitoring programme concentrated on those lakes which had shown highest levels in the 1990 survey. This report details the results of the freshwater lake monitoring programme for the years 1988 - 1992. As assessment of the radiation doses to those consumers who include relatively large amounts of freshwater fish in their diet is also made

  9. Radioactive aerosol detection station for near real-time atmospheric monitoring

    International Nuclear Information System (INIS)

    Mason, L.R.; Bohner, John D.

    1997-01-01

    A radionuclide aerosol detection station has been developed to measure radioactivity in the environment. The objective is to monitor the atmosphere for anthropogenic radioactivity that could be indicative of nuclear weapons tests to verify the Comprehensive Nuclear Test Ban Treaty. Eighty stations will form the backbone of the International Monitoring System in which stations are linked to a central analysis facility called the International Data Centre. Data are transmitted to this centre in near real-time to facilitate rapid detection. Principal process of the field measurement are collection, separation, and assay. Collection of airborne radioactivity is achieved through high-volume air sampling. Aerosols separation is accomplished by high-efficiency particulate filtration. Radionuclides assay is achieved by in-situ high resolution gamma spectrometry. These modules are integrated into a unit that provides power, control, and communication support subsystems. Station operation is semi-automatic requiring only minimal human interaction. (author). 6 refs., 3 figs., 3 tabs

  10. The Coordinating Laboratories for monitoring of environmental radioactivity. History, activities, perspectives

    International Nuclear Information System (INIS)

    Wiechen, A.; Bayer, A.

    2000-10-01

    The article reviews the development of the monitoring of environmental radioactivity in the former Federal Republic of Germany and from 1990 onwards in re-unified Germany. This monitoring originated in the need to investigate the radioactive fallout from the testing of atomic bombs in the atmosphere in the 1950's and 1960's. Monitoring was intensified and became increasingly regulated by law as a response to the large scale use of atomic power and in accordance with the Euratom Treaty of 1957. The necessity of evaluating the radiological effects in old mining regions in some of the new Laender was recognised in 1990. Since then legislation and official monitoring have been extended to include this source of radiation exposure. Also described is the way in which those institutions now termed Coordinating Laboratories were involved in all of the developments mentioned above. They tested and developed sampling, analysis and measurement techniques, carried out research projects on the various contamination pathways, reported regularly on environmental radioactivity and radiation exposure, organised and evaluated interlaboratory comparisons, assisted in the setting up of the Federal Integrated Measurement and Information System (IMIS), and advised the appropriate Federal and Laender Ministries. Some of the Coordinating Laboratories also manage Federal Monitoring Networks. The Precautionary Radiation Protection Act stipulates these tasks and names the institutions appointed as Coordinating Laboratories. (orig.) [de

  11. Monitoring of released radioactive gaseous and liquid effluent at Rokkasho Reprocessing Plant

    International Nuclear Information System (INIS)

    Oka, M.; Keta, S.; Nagai, S.; Kano, M.; Ishihara, N.; Moriyama, T.; Ogaki, K.; Noda, K.

    2009-01-01

    Rokkasho Reprocessing Plant (RRP) Rokkasho Reprocessing Plant started its active tests with spent fuel at the end of March 2006. When spent fuels are sheared and dissolved, radioactive gaseous effluent and radioactive liquid effluent such as krypton-85, tritium, etc. are released into the environment. In order to limit the public dose as low as reasonably achievable in an efficient way, RRP removes radioactive material by evaporation, rinsing, filtering, etc., and then releases it through the main stack and the sea discharge pipeline that allow to make dispersion and dilution very efficiently. Also, concerning the radioactive gaseous and liquid effluent to be released into the environment, the target values of annual release have been defined in the Safety Rule based on the estimated annual release evaluated at the safety review of RRP. By monitoring the radioactive material in gaseous exhaust and liquid effluent RRP controls it not to exceed the target values. RRP reprocessed 430 tUpr of spent fuel during Active Test (March 2006 to October 2008). In this report, we report about: The outline of gaseous and liquid effluent monitoring. The amount of radioactive gaseous and liquid effluent during the active test. The performance of removal of radioactive materials in gaseous and liquid effluents. The impact on the public from radioactive effluents during the active test. (author)

  12. Annual report on radioactive discharges and monitoring of the environment 1992. V. 2

    International Nuclear Information System (INIS)

    1993-01-01

    This Annual Report supplements British Nuclear Fuel plc's Health and Safety Annual Report by providing more detailed information on radioactive discharges, monitoring of the environmental and critical group doses. BNFL has published Annual Reports on Radioactive Discharges and Monitoring of the Environment, covering the period from 1977 to the present. For 1991 this report has been sub-divided into two complementary parts. Volume II reproduces the Certificates of Authorisation under which the Company operates and the statutory environmental monitoring programmes which relate to them. (author)

  13. Annual report on radioactive discharges and monitoring of the environment 1991. V. 2

    International Nuclear Information System (INIS)

    1992-01-01

    This Annual Report supplements British Nuclear Fuel plc's Health and Safety Annual Report by providing more detailed information on radioactive discharges, monitoring of the environmental and critical group doses. BNFL has published Annual Reports on Radioactive Discharges and Monitoring of the Environment, covering the period from 1977 to the present. For 1991 this report has been sub-divided into two complementary parts. Volume II reproduces the Certificates of Authorisation under which the Company operates and the statutory environmental monitoring programmes which relate to them. (author)

  14. Radioactivity monitoring programme of Krsko nuclear power plant

    International Nuclear Information System (INIS)

    Miklavzic, U.; Martincic, R.; Kanduc, M.; Lulic, S.; Kovac, J.; Breznik, B.

    1996-01-01

    As a successor to the preoperational surveillance programme, the regular offsite radioactivity monitoring programme (RMP) of the Krsko Nuclear Power Plant (NPP) was implemented in 1982, when the power plant formally commenced operating. Observations collected during the first years of its operation were later also the basis for setting up the official 'Regulatory guide on monitoring of nuclear installations', issued not earlier than in 1986. The basic criterion which governed the selection of measuring methods, sampling techniques and locations, was the extent to which the data obtained could serve for the realistic assessment of the committed dose to a member of the population, and later on to members of a representative (critical) group. To be able to differentiate the radioactivity released through the liquid and gaseous effluents of the NPP from other radiation sources (natural radioactivity, global contamination), and especially because of the varying radiotoxicity of different radionuclides, in principle monitoring in the environment, as at the source, had to provide activity data for each individual radionuclide appearing in the effluents. Therefore, as early as 1982 the programme attributed the main weight to high resolution gamma spectrometry, combined with specific radiochemical analytical methods (e.g. 90 Sr/ 89 Sr, 3 H, 14 C, alpha spectrometry of Pu isotopes) which together made feasible determination of individual specific activities of the most significant man-made and natural radionuclides. By weighting the specific activities of the radionuclides identified and measured in the media surveyed by dose factors for intake, the quantity 'B' - the so-called 'radiological burden', was calculated and introduced in the yearly-summary tables. Expressed in relative units, from which the committed dose could be readily calculated, the burden B very lucidly disclosed the relative importance of different artificial pollutants and natural radioactivity present in

  15. Design of an on-line monitoring system for radioactive wastewater

    International Nuclear Information System (INIS)

    Qin Guoxiu; Youning Xu; Lei Wang; Xuesong Zhang; Wenping Zhou; Weizhe Li

    2017-01-01

    An on-line monitoring system for radioactive wastewater was designed to discriminate the type and concentration of the radionuclides discharged from nuclear facilities. An HPGe semiconductor was used as the detector in the system for continuous monitoring by pumping wastewater. The minimum detectable activity for 137 Cs was 0.4 Bq L -1 after 10 min of measuring wastewater with the system. The system can detect excessive radioactivity in the wastewater and quickly and effectively alert personnel. Based on the experimental measurements and the Monte Carlo simulation, the detection efficiency of the system was calibrated, and an efficiency curve was determined for the energy range from 50 to 2754 keV. (author)

  16. Chernobyl radioactivity and high altitude air-particulate monitoring at Islamabad

    International Nuclear Information System (INIS)

    Bhatti, M.S.; Ihsanullah; Shafiq, M.; Perveen, N.; Orfi, S.D.

    1987-11-01

    High altitude sampling of air particulates for radioactivity monitoring was conducted at Islamabad after the CHERNOBYL accident. Smears from aeroplanes flying at varying altitudes were collected and analysed for fresh fission products mainly gamma emitters e.g. Ru-103 and Cs-137 etc. The maximum radioactivity observed was of the order of 15Bq/sample for Ru-103 and 9Bq/sample for Cs-137 respectively. The study was purely qualitative in nature indicated the presence of fresh fission radioactivity at high altitudes over Islamabad. For quantitative measurements at high altitudes sophisticated instrumentation/procedure needs to be adopted. (author)

  17. Annual report on radioactive discharges and monitoring of the environment 1990. V. 2

    International Nuclear Information System (INIS)

    1991-01-01

    This Annual Report supplements the Health and Safety Annual Report of British Nuclear Fuels plc by providing more detailed information on radioactive discharges, monitoring of the environment and critical group doses. This report has been sub-divided into two complementary parts. Volume I includes annual data for each of the Company sites on radioactive discharges into the environment and the associated environmental monitoring programmes. The sites involved are: Sellafield where the main activities are irradiated nuclear fuel reprocessing and the Calder Hall nuclear station; the Drigg radioactive waste storage and disposal site; the Chapelcross nuclear power station; Springfields Works which manufactures nuclear fuels; Capenhurst Works where uranium isotopic enrichment plants are operated. Volume II reproduces the Certificates of Authorisation under which the Company operates and the statutory environmental monitoring programmes which relate to them. (author)

  18. Annual report on radioactive discharges and monitoring of the environment 1990. V. 1

    International Nuclear Information System (INIS)

    1991-01-01

    This Annual Report supplements the Health and Safety Annual Report of British Nuclear Fuels plc by providing more detailed information on radioactive discharges, monitoring of the environment and critical group doses. This report has been sub-divided into two complementary parts. Volume I includes annual data for each of the Company sites on radioactive discharges into the environment and the associated environmental monitoring programmes. The sites involved are: Sellafield where the main activities are irradiated nuclear fuel reprocessing and the Calder Hall nuclear station; the Drigg radioactive waste storage and disposal site; the Chapelcross nuclear power station; Springfields Works which manufactures nuclear fuels; Capenhurst Works where uranium isotopic enrichment plants are operated. Volume II reproduces the Certificates of Authorisation under which the Company operates and the statutory environmental monitoring programmes which relate to them. (author)

  19. Annual report on radioactive discharges and monitoring of the environment 1980

    International Nuclear Information System (INIS)

    1981-07-01

    A report is given on radioactive discharges through authorised outlets and on environmental monitoring for all of British Nuclear Fuels Limited Works and Sites, i.e. the Windscale and Calder Works and the Drigg Storage and Disposal Site; Chapelcross Works; Springfields Works and the Ulnes Walton Disposal Site; and Capenhurst Works. The report includes information on liquid and airborne radioactive effluents and solid radioactive waste at each of the Company's Works and Sites. Assessments are made of maximum radiological exposures to individual members of the public expressed in terms of limits based on ICRP recommendations and in accordance with advice given by the NRPB. The report showed that at no time during 1980 did discharges and disposals of radioactive wastes through authorised outlets at any of the Works exceed those laid down in any of the Authorisations. Environmental monitoring studies also showed that the radiation exposure in 1980 of the most highly exposed groups of the general population was significantly lower than the Annual Limit recommended by the ICRP. (U.K.)

  20. 15. Experts' meeting on monitoring environmental radioactivity. Data - models - information. Proceedings

    International Nuclear Information System (INIS)

    2014-01-01

    The proceedings of the 15. Experts' meeting on monitoring environmental radioactivity include contributions o the following topics: environmental monitoring in Germany; developments in emergency protection and environmental monitoring; implementation of model and information systems; measuring programs during events and exercises; public information during local and global events; fast and (new) analytical methods; measures of the quality management systems; European and international environmental monitoring harmonization.

  1. Radiation protection instrumentation. Monitoring equipment. Radioactive aerosols in the environment

    International Nuclear Information System (INIS)

    1996-01-01

    This international standard applies to portable or installed equipment for continuous monitoring of radioactive aerosols in the environment in normal and emergency conditions. Monitoring involves continuous sampling and, where desirable, automatic start of sampling. The document applies particularly to the following assignments: (i) determination of the volume activity of radionuclides in the form of aerosols, either per time unit, along with its time changes, or in the integral form over a longer time period such as 24 h, and measurement of the volume sampled; (ii) triggering a warning alarm signal if the preset volume activity or time integral of the volume activity of aerosols has been exceeded. The document deals with radioactive aerosol monitor design, testing procedures, and documentation. Appended tables refer to the reference and normal testing conditions, tests in normal testing conditions, tests during changes of the affecting quantities, and tests of the air circuit. (P.A.)

  2. A radioactive waste transportation package monitoring system for normal transport and accident emergency response conditions

    International Nuclear Information System (INIS)

    Brown, G.S.; Cashwell, J.W.; Apple, M.L.

    1993-01-01

    This paper addresses spent fuel and high level waste transportation history and prospects, discusses accident histories of radioactive material transport, discusses emergency responder needs and provides a general description of the Transportation Intelligent Monitoring System (TRANSIMS) design. The key objectives of the monitoring system are twofold: (1) to facilitate effective emergency response to accidents involving a radioactive waste transportation package, while minimizing risk to the public and emergency first-response personnel, and (2) to allow remote monitoring of transportation vehicle and payload conditions to enable research into radioactive material transportation for normal and accident conditions. (J.P.N.)

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

    International Nuclear Information System (INIS)

    1990-01-01

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

  4. Terrestrial radioactivity monitoring programme (TRAMP) report for 1994. Radioactivity in food and agricultural products in England and Wales

    International Nuclear Information System (INIS)

    1995-01-01

    The Ministry of Agriculture and Fisheries monitoring programmes for radioactivity in the terrestrial environment of the United Kingdom during 1994 are described. The results of the analyses performed with a commentary are presented. Two complimentary programmes, TRAMP and FARM, are used to ensure that radiation doses received by the public from the consumption of foodstuffs are controlled ion accordance with national and international guidelines. TRAMP concentrates on the monitoring of agricultural produce from the vicinity of the 23 licensed nuclear sites in England and Wales. The focus of FARM is the safety of the general food supply through natural food monitoring; a representative selection of industrial and landfill sites which provide potential sources of radionuclide contamination of the food chain is also monitored. In addition, monitoring programmes are undertaken for airborne grass and soil contamination in the neighbourhood of 18 nuclear sites. The overall conclusion drawn from the results presented is that public exposure to anthropogenic radioactivity due to the consumption of milk and foodstuffs grown around licensed nuclear sites in 1994 was well within acceptable limits. (67 references; 97 tables). (UK)

  5. Annual report on radioactive discharges and monitoring of the environment, 1996. V. 1

    International Nuclear Information System (INIS)

    1997-01-01

    British Nuclear Fuels Limited (BNFL)'s 1996 report on radioactive discharges from its various sites and monitoring of the surrounding environments are described. For each of the Sellafield, Drigg, Chapelcross, Springfields and Capenhurst sites, details are given on normal operations, radioactive discharges in gaseous, liquid or solid forms, environmental monitoring routines and collective dose and critical group estimates. The second, linked, volume of this report covers certificates of authorisation issued to the company. (UK)

  6. Monitoring of radioactivity in the UK environment: an annotated bibliography of current programmes

    International Nuclear Information System (INIS)

    Cotter, A.J.R.; Hunt, G.J.

    1992-01-01

    In the UK, many organisations carry out regular radioactivity monitoring programmes, and summaries of these programmes have been published in 1983 and 1988. The number of organisations carrying out radioactivity monitoring has increased rapidly in recent years, particularly in the local authority sector. The present report updates the previous summarises in the form of an annotated bibliography, giving synopses of all regular UK programmes whose results are published in report form. (author)

  7. Radioactive contamination in monitors received for calibration; Contaminacao em monitores de radiacao recebidos para calibracao

    Energy Technology Data Exchange (ETDEWEB)

    Dias, Paulo S.; Santos, Gilvan C. dos; Brunelo, Maria Antonieta G.; Paula, Tiago C. de; Pires, Marina A.; Borges, Jose C. [MRA Comercio de Instrumentos Eletronicos Ltda., Jardinopolis, SP (Brazil). Centro de Ensaios e Pesquisas em Metrologia (METROBRAS)

    2013-10-01

    The Calibration Laboratory - LABCAL, from the Research Center for Metrology and Testing - METROBRAS, MRA Comercio de Instrumentos Eletronicos Ltda., began activities in October 2008 and, in August 2009, decided to establish a procedure for monitoring tests, external and internal, of all packages received from customers, containing instruments for calibration. The aim was to investigate possible contamination radioactive on these instruments. On July 2011, this procedure was extended to packagings of personal thermoluminescent dosemeters - TLD, received by the newly created Laboratory Laboratorio de Dosimetria Pessoal - LDP . In the monitoring procedure were used monitors with external probe, type pancake, MRA brand, models GP - 500 and MIR 7028. During the 37 months in which this investigation was conducted, were detected 42 cases of radioactive contamination, with the following characteristics: 1) just one case was personal dosimeter, TLD type; 2) just one case was not from a packing from nuclear medicine service - was from a mining company; 3) contamination occurred on packs and instruments, located and/or widespread; 4) contamination values ranged from slightly above the level of background radiation to about a thousand fold. Although METROBRAS has facilities for decontamination, in most cases, especially those of higher contamination, the procedure followed was to store the contaminated material in a room used for storage of radioactive sources. Periodically, each package and/or instrument was monitored, being released when the radiation level matched the background radiation. Every contamination detected, the client and/or owner of the instrument was informed. The Brazilian National Energy Commission - CNEN, was informed, during your public consultation for reviewing the standard for nuclear medicine services, held in mid-2012, having received from METROBRAS the statistical data available at the time. The high frequency of contamination detected and the high

  8. Radioactive contamination monitoring device for off-gas in ventilation system

    International Nuclear Information System (INIS)

    Osaki, Masahiko; Watabe, Atsushi; Kaneko, Itaru; Kubokoya, Takashi.

    1990-01-01

    In a conventional method of detecting leakage for primary coolants, radioactive iodine in off-gases was detected while going up the off-gas system. As an event resulting in abnormality to radioactive rare gas level, leakage of water, leakage in cleanup system-recycling system, leakage in main steams and leakage from wastes processing system are considered. An off-gas system to be measured is selectively sampled by a sample changer in order to measure radioactive rare gases in the off-gases, and sample gases are introduced to detect radioactivity. Detection signals are received for analysis and quantitative determination, the result of the analysis is diagnosed and the presence or absence of abnormality in an object to be measured is determined. Subsequently, an abnormality alarm and the result of the analysis are outputted. Since the radioactive rare gases are chemically inactive, they are neither combined with other materials nor deposited to wall surfaces. Abnormality can be easily detected by always monitoring a composition pattern and a radioactivity level. (N.H.)

  9. HMIP monitoring programme: radioactive substances report for 1990

    International Nuclear Information System (INIS)

    1992-03-01

    Discharges of radioactive wastes to the environment can only be made under authorisation from government bodies. The main potential sources of environmental contamination in England are nuclear sites (power stations, fuel fabrication and reprocessing plants), some industrial premises such as metal smelters, and landfill sites. As well as the environmental monitoring programmes undertaken by the operators of such sites various government bodies also undertake monitoring. In January 1988 Her Majesty's Inspectorate of Pollution (HMIP) initiated a programme to monitor exposure of the public from non-food pathways such as could occur from occupation of beaches, river banks etc. Radiation levels and radiochemical and gamma spectra of samples collected at specified locations near nuclear sites and industrial premises have been monitored every quarter since then. The results for 1990 are presented and discussed. (UK)

  10. Annual report on radioactive discharges from Winfrith and monitoring the environment 1987

    International Nuclear Information System (INIS)

    1988-04-01

    The 1987 Annual Report on radioactive discharges from Winfrith Atomic Energy Establishment and monitoring of the environment is given. The report covers waste discharges to the sea and the earth atmosphere and the associated environmental monitoring. (UK)

  11. USING STATISTICAL PROCESS CONTROL TO MONITOR RADIOACTIVE WASTE CHARACTERIZATION AT A RADIOACTIVE FACILITY

    International Nuclear Information System (INIS)

    WESTCOTT, J.L.

    2006-01-01

    Two facilities for storing spent nuclear fuel underwater at the Hanford site in southeastern Washington State being removed from service, decommissioned, and prepared for eventual demolition. The fuel-storage facilities consist of two separate basins called K East (KE) and K West (KW) that are large subsurface concrete pools filled with water, with a containment structure over each. The basins presently contain sludge, debris, and equipment that have accumulated over the years. The spent fuel has been removed from the basins. The process for removing the remaining sludge, equipment, and structure has been initiated for the basins. Ongoing removal operations generate solid waste that is being treated as required, and then disposed. The waste, equipment and building structures must be characterized to properly manage, ship, treat (if necessary), and dispose as radioactive waste. As the work progresses, it is expected that radiological conditions in each basin may change as radioactive materials are being moved within and between the basins. It is imperative that these changing conditions be monitored so that radioactive characterization of waste is adjusted as necessary

  12. USING STATISTICAL PROCESS CONTROL TO MONITOR RADIOACTIVE WASTE CHARACTERIZATION AT A RADIOACTIVE FACILITY

    International Nuclear Information System (INIS)

    WESTCOTT, J.L.; JOCHEN; PREVETTE

    2007-01-01

    Two facilities for storing spent nuclear fuel underwater at the Hanford site in southeastern Washington State are being removed from service, decommissioned, and prepared for eventual demolition. The fuel-storage facilities consist of two separate basins called K East (KE) and K West (KW) that are large subsurface concrete pools filled with water, with a containment structure over each. The basins presently contain sludge, debris, and equipment that have accumulated over the years. The spent fuel has been removed from the basins. The process for removing the remaining sludge, equipment, and structure has been initiated for the basins. Ongoing removal operations generate solid waste that is being treated as required, and then disposed. The waste, equipment and building structures must be characterized to properly manage, ship, treat (if necessary), and dispose as radioactive waste. As the work progresses, it is expected that radiological conditions in each basin may change as radioactive materials are being moved within and between the basins. It is imperative that these changing conditions be monitored so that radioactive characterization of waste is adjusted as necessary

  13. Radioactivity monitoring of Irish dairy produce

    International Nuclear Information System (INIS)

    Kelleher, K.

    2010-01-01

    Full text: The RPII has been carrying out monitoring of milk and dairy produce since 1986. Milk samples are routinely analysed for radiocaesium and strontium-90 as part of the RPII's environmental monitoring programme to determine the doses received to the Irish population from milk consumption. The method the RPII utilises for determining the Sr-90 activity in milk is by measuring the Cerenkov radiation produced by its daughter 90 Y isolated from interfering nuclides such as uranium, thorium, radium and their decay products as well as isotopes of caesium, potassium and strontium by extraction with 10% di-(2-ethylhexyl)phosphate (HDEHP) in toluene. The chemical yield of 90 Y is determined by the acidmetric titration of yttrium nitrate carrier with titriplex III. The levels of Sr-90 and dose to the Irish population from milk consumption have been negligible when compared to other radioactive sources in the Irish environment. Other dairy products are analysed for radiocaesium on a routine basis for commercial customers to ensure the levels of radioactivity in the dairy products fall within EC regulations governing the export/import of dairy produce. The export of milk and milk produce from Ireland is a very important industry, 80% of dairy products produced in Ireland are exported and these exports are worth Euro 2.2 billion annually to the Irish economy. The dairy products are analysed by gamma spectroscopy and include full and skim milk powders, butter, casein, cheese, cream, whey and lactose. The levels of radiocaesium in these products are typically below 5 Bk/kg and fall well within the limit of 370 Bq/kg laid down by the European Community in Council Regulation 737/90. Although the levels of these radionuclides are relatively low the RPII recognises the importance of analysing these samples for radioactivity to inform the public, ensure consumer confidence and, more importantly, to maintain a level of expertise in the RPII in these analytical techniques so that

  14. Radioactivity monitoring of Irish dairy produce

    Energy Technology Data Exchange (ETDEWEB)

    Kelleher, K. (Radiological Protection Institute of Ireland. Radiation Monitoring, Dublin (Ireland))

    2010-03-15

    Full text: The RPII has been carrying out monitoring of milk and dairy produce since 1986. Milk samples are routinely analysed for radiocaesium and strontium-90 as part of the RPII's environmental monitoring programme to determine the doses received to the Irish population from milk consumption. The method the RPII utilises for determining the Sr-90 activity in milk is by measuring the Cerenkov radiation produced by its daughter 90Y isolated from interfering nuclides such as uranium, thorium, radium and their decay products as well as isotopes of caesium, potassium and strontium by extraction with 10% di-(2-ethylhexyl)phosphate (HDEHP) in toluene. The chemical yield of 90Y is determined by the acidmetric titration of yttrium nitrate carrier with titriplex III. The levels of Sr-90 and dose to the Irish population from milk consumption have been negligible when compared to other radioactive sources in the Irish environment. Other dairy products are analysed for radiocaesium on a routine basis for commercial customers to ensure the levels of radioactivity in the dairy products fall within EC regulations governing the export/import of dairy produce. The export of milk and milk produce from Ireland is a very important industry, 80% of dairy products produced in Ireland are exported and these exports are worth Euro 2.2 billion annually to the Irish economy. The dairy products are analysed by gamma spectroscopy and include full and skim milk powders, butter, casein, cheese, cream, whey and lactose. The levels of radiocaesium in these products are typically below 5 Bk/kg and fall well within the limit of 370 Bq/kg laid down by the European Community in Council Regulation 737/90. Although the levels of these radionuclides are relatively low the RPII recognises the importance of analysing these samples for radioactivity to inform the public, ensure consumer confidence and, more importantly, to maintain a level of expertise in the RPII in these analytical techniques so

  15. Environmental monitoring and deep ocean disposal of packaged radioactive waste

    International Nuclear Information System (INIS)

    Mitchell, N.T.; Preston, A.

    1980-01-01

    The aims and objectives of environmental monitoring as laid down, for example by the ICRP and the IAEA include the assessment of actual or potential radiation exposure of man and the requirements of scientific investigations. The fulfillment of these aims is discussed in the context of the disposal of packaged radioactive waste in the deep Atlantic Ocean within the terms of the London Dumping Convention and within a regional agreement, the consultation/surveillance mechanism of the Nuclear Energy Agency. The paper discusses UK attitudes to such environmental monitoring, concentrates on the first of these ICRP objectives and shows how this is unlikely to be achieved by direct measurement in view of the small quantities of radioactive material involved relative to the scale of the receiving environment, and the timescale on which return to man can be conceived. Whilst meaningful environmental measurement is very unlikely to facilitate direct estimation of public radiation exposure by monitoring, it is still held that the basic objective of environmental monitoring can be met. A means by which this may be achieved is by oceanographic models. These procedures are discussed, illustrating the application of this philosophy in practice. (H.K.)

  16. Status of radioactivity monitoring in French Polynesia in 2012. Synthesis of IRSN's monitoring network results

    International Nuclear Information System (INIS)

    Bouisset, P.; Bernagout, S.; Leclerc, G.; Rua, J.; Delabbaye, P.; De Vismes, P.A.

    2013-01-01

    Exercised in Polynesia since 1962, the radiological monitoring of the French environment, which takes place on seven islands (Tahiti, Maupiti, Hao, Rangiroa, Hiva Oa, Mangareva and Tubuai) representing the five archipelagos, and consists of taking regular samples of various kinds from the different environmental compartments (air, water, soil, food...) with which the population may be in contact. Regarding food, the samples analyzed are representative of the diet of Polynesians living in the five archipelagos of that territory, and from the marine environment of the open sea, from the lagoon environment and from the terrestrial environment. Almost all the samples are measured at the Laboratory for the Study and Monitoring of the Environment (LESE) IRSN, based in Vairao on the island of Tahiti. During the year 2012, were stable and typical of the regular reduction of the levels of radioactivity since the stop, in 1974, of the French atmospheric tests. This residual radioactivity relates primarily to the 137 Cs. In term of additional dose, this artificial and residual radioactivity is lower than 5 μSv.y -1 (5 micro-sieverts per year). This value corresponds to less than 0,5 % of exposure due to natural radioactivity in Polynesia (approximately 1 000 μSv.y -1 ). Enhanced radiological monitoring of the environment set up in the wake of the Fukushima disaster, continued in 2012 in the marine field. The measurements carried out throughout the year confirm the lack of impact of the contamination of Japanese marine area in Polynesian waters. Samples of pelagic fish (tuna, swordfish, dolphin fish, wahoo...) were made in the vicinity of five Polynesian archipelagos: no increase of 137 Cs compared to previous years was observed and 134 Cs was never detected. (authors) [fr

  17. The MAFF dry cloth collector programme for monitoring airborne radioactivity

    International Nuclear Information System (INIS)

    McHugh, J.O.; Smith, B.D.; Hunt, G.J.; Thomas, R.E.G.

    1986-01-01

    The history of the MAFF airborne radioactivity monitoring programme and its current operation using dry cloth collectors are described. The detection system has become well established as a sensitive indicator of airborne radioactivity. Details of collector materials, deployment around the major UK nuclear establishments and procedures for radiometric analysis of cloths are given. Typical results for the period 1980-82 show that at most sites only nuclear weapons fallout was detected. The systems's usefulness is exemplified by its response to the release of I-131 from Sellafield in 1981; this release was of negligible radiological significance but was easily detected. The response of dry cloths to various sources of atmospheric radioactivity and factors affecting collection efficiency are discussed. (author)

  18. Effluent monitoring Quality Assurance Project Plan for radioactive airborne emissions data. Revision 2

    International Nuclear Information System (INIS)

    Frazier, T.P.

    1995-12-01

    This Quality Assurance Project Plan addresses the quality assurance requirements for compiling Hanford Site radioactive airborne emissions data. These data will be reported to the U.S. Environmental Protection Agency, the US Department of Energy, and the Washington State Department of Health. Effluent Monitoring performs compliance assessments on radioactive airborne sampling and monitoring systems. This Quality Assurance Project Plan is prepared in compliance with interim guidelines and specifications. Topics include: project description; project organization and management; quality assurance objectives; sampling procedures; sample custody; calibration procedures; analytical procedures; monitoring and reporting criteria; data reduction, verification, and reporting; internal quality control; performance and system audits; corrective actions; and quality assurance reports

  19. Radioactivity in drinking water: regulations, monitoring results and radiation protection issues

    Directory of Open Access Journals (Sweden)

    Cristina Nuccetelli

    2012-12-01

    Full Text Available INTRODUCTION: Drinking waters usually contain several natural radionuclides: tritium, radon, radium, uranium isotopes, etc. Their concentrations vary widely since they depend on the nature of the aquifer, namely, the prevailing lithology and whether there is air in it or not. AIMS: In this work a broad overview of the radioactivity in drinking water is presented: national and international regulations, for limiting the presence of radioactivity in waters intended for human consumption; results of extensive campaigns for monitoring radioactivity in drinking waters, including mineral bottled waters, carried out throughout the world in recent years; a draft of guidelines for the planning of campaigns to measure radioactivity in drinking water proposed by the Environmental Protection Agency (ARPA of Lombardia.

  20. Monitoring of radioactive ferrous scarp and products, current practices and regulatory problems in North-Eastern Italy

    International Nuclear Information System (INIS)

    Barbina, V.; Bianco, L.

    1997-01-01

    Radioactive scrap metal is a major source of concern among the steel industries of northeastern Italy, since most of the scrap supply comes from east-European countries and may originate from dismantled nuclear installations or dismissed radioactive devices. In this respect reliable monitoring procedures and consistent regulations are essential to face the many economic, legal and safety problems involved in the control and management of radioactive scrap and products. The authors describe the monitoring methods developed in more than two years practice at the steel works Ferriere Nord, Osoppo UD, Italy, as a realistic compromise between reliability, radiation protection and cost. They also discuss the drawbacks sometimes due to the lack of coherent monitoring protocols and exemption levels in Italian regulations, which leave some ways out for the uncontrolled recycling of radioactive metal scrap. (author)

  1. Development of monitor for multiple beta-ray nuclides in liquid radioactive waste (IV)

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Chang Kyu; Nam, Uk Won; Seon, K. I.; Kong, K. N.; Son, J. D.; Chin, H.; Park, J. H.; Yuk, I. S.; Han, W. Y. [Korea Astronomy and Space Science Institute, Daejeon (Korea, Republic of)

    2004-02-15

    In the 4{sup th} fiscal year, the performance of the system developed in previous year have been stablilized. An automatic mixer system to mix the liquid radioactive waste with the liquid scintillator was designed and manufactured to make continuous monitoring possible. Mechanical systems for the automatic transfer, injection of radioactive samples, and for sealing sample bottle and its attachment on detector system have been designed and developed for completely integrated system, The experimental has been performed for the radioactive analysis by using the system. The measured data are transferred to central computer, which controls the monitoring system, through the RS-232 communication protocol. A software for host personal computer was developed for the control and analysis of the integrated system.

  2. 2011 report on radioactivity monitoring in French Polynesia. Summary of results from the IRSN monitoring network

    International Nuclear Information System (INIS)

    Bouisset, P.; Bernagout, S.; Leclerc, G.; Rua, J.; Delabbaye, P.; Cagnat, X.; Jonhson, I.; Taputu, G.; Paeamara, H.; Tamarii, R.; Temarohirani, T.; Flores, T.

    2013-01-01

    Radiological monitoring of the French environment is one of IRSN's permanent tasks as part of public policy on nuclear safety and radiological protection. It helps to guarantee the best possible protection for the population. Carried out in Polynesia since 1962, this monitoring focuses on seven islands (Tahiti, Maupiti, Hao, Rangiroa, Hiva Oa, Mangareva and Tubuai) which are representative of the five archipelagoes. It consists in taking monthly samples of various kinds from the different environmental compartments (air, water, soil, food, etc.) with which the population may be in contact. Regarding food, the samples analyzed are representative of the diet of Polynesians living in the five archipelagoes of the region and are taken from the marine environment of the open sea, the lagoon environment and the terrestrial environment. Almost all samples are measured at the IRSN Laboratory for the Study and Monitoring of the Environment, based in Vairao on the island of Tahiti, plus a few samples at the IRSN Orsay Laboratory. The year 2011 was marked by the Fukushima nuclear accident, which occurred on March 11. Within this context, IRSN stepped up its monitoring activities in French Polynesia and was able to confirm the absence of radiological impact in New Caledonia and Polynesia. As the results of these analyses were published in the previous annual report (report DEI/SESURE 2011-40), this report does not include all the data and results relating to the accident, but provides a summary for the year 2011. As in recent years, levels of radioactivity, which fell steadily as of 1974 when French atmospheric nuclear weapons testing came to an end, were stable and very low in 2011. The residual radioactivity is mainly due to 137 Cs. In terms of additional dose, this artificial and residual radioactivity is lower than 5 μSv.yr -1 (5 micro-sieverts per year). This corresponds to less than 0.5% of exposure due to natural radioactivity in Polynesia (approximately 1000

  3. Monitoring of geological repositories for high level radioactive waste

    International Nuclear Information System (INIS)

    2001-04-01

    Geological repositories for disposal of high level radioactive waste are designed to provide isolation of the waste from human environment for many thousands of years. This report discusses the possible purposes for monitoring geological repositories at the different stages of a repository programme, the use that may be made of the information obtained and the techniques that might be applied. This report focuses on the different objectives that monitoring might have at various stages of a programme, from the initiation of work on a candidate site, to the period after repository closure. Each objective may require somewhat different types of information, or may use the same information in different ways. Having evaluated monitoring requirements, the report concludes with a brief evaluation of available monitoring techniques

  4. Monitoring for radioactive materials releasing to environment in M310 reformatived nuclear power plant

    International Nuclear Information System (INIS)

    Yin Zhenyu; Yang Guangli; Xu Guang

    2012-01-01

    Airborne radioactive materials of nuclear power plant (NPP) releases to the environment from the stack of NPP. Radioactive liquid waste releases of the ocean, the fluvial and the lake through the liquid waste letdyke of NPP. Further more, a few radioactive waste may be taken out of the NPP by vehicle or personnel. For the purpose of strict management and control above-mentioned waste, we use detect equipment monitoring radioactive waste of NPP. Management and control for the releasing of radioactive material to the environment in M310 reformatived NPP is strict and safety. (authors)

  5. Radioactivity monitoring and import regulation of the contaminated foodstuffs in Japan following the Chernobyl nuclear power plant accident

    International Nuclear Information System (INIS)

    Izumo, Yoshiro

    1997-01-01

    Radioactivity monitoring and import regulation of the contaminated foodstuffs executed by Minstry of Health and Welfare following the Chernobyl nuclear plant accident were reviewed as follows; 1) background of socio-psychological effects and environmental radioactivity leading to the regulation (to may 3, 1986); 2) intial intervention for imported foodstuffs in Japan (may 8, '86), and 3) in european countries (to may 31, '86), immediately after the Accident, respectively; 4) determination of the interim driven intervention level for radionuclides in imported foodstuffs (( 134 Cs + 137 Cs): 370 Bq/Kg) and activation of the monitoring, 5) outline of the monitoring with elapsed time, number of foodstuffs monitored, number of foodstuffs exceeded radioactivity of the intervention level and re-exported; 6) guideline in international trade of radioactive contaminated foodstuffs adopted by CODEX Alimentarius Commission (FAO/WHO) and the intervention level recommended by ICRP following the Accident; 7) discussion for problems and scopes in future based on the results of monitoring. As the results, a number of imported foodstuffs (about 75,000 samples at present) has been monitored, 55 samples exceeding the interim intervention level were re-exported to each export's country, and socio-psychological doubts for radioactive contamination of imported foodstuffs have been dispersed. In addition, problems for several factors based on calculation of the interim intervention level, radioactivity level of foodstuffs exceeding about 50 Bq/Kg as radiocesiums and necessity of monitoring for the other radionuclides in foods except radiocesiums were also discussed. (author)

  6. Radioactivity monitoring and import regulation of the contaminated foodstuffs in Japan following the Chernobyl nuclear power plant accident

    Energy Technology Data Exchange (ETDEWEB)

    Izumo, Yoshiro [Institute of Public Health, Tokyo (Japan)

    1997-03-01

    Radioactivity monitoring and import regulation of the contaminated foodstuffs executed by Minstry of Health and Welfare following the Chernobyl nuclear plant accident were reviewed as follows; (1) background of socio-psychological effects and environmental radioactivity leading to the regulation (to may 3, 1986); (2) intial intervention for imported foodstuffs in Japan (may 8, `86), and (3) in european countries (to may 31, `86), immediately after the Accident, respectively; (4) determination of the interim driven intervention level for radionuclides in imported foodstuffs (({sup 134}Cs + {sup 137}Cs): 370 Bq/Kg) and activation of the monitoring, (5) outline of the monitoring with elapsed time, number of foodstuffs monitored, number of foodstuffs exceeded radioactivity of the intervention level and re-exported; (6) guideline in international trade of radioactive contaminated foodstuffs adopted by CODEX Alimentarius Commission (FAO/WHO) and the intervention level recommended by ICRP following the Accident; (7) discussion for problems and scopes in future based on the results of monitoring. As the results, a number of imported foodstuffs (about 75,000 samples at present) has been monitored, 55 samples exceeding the interim intervention level were re-exported to each export`s country, and socio-psychological doubts for radioactive contamination of imported foodstuffs have been dispersed. In addition, problems for several factors based on calculation of the interim intervention level, radioactivity level of foodstuffs exceeding about 50 Bq/Kg as radiocesiums and necessity of monitoring for the other radionuclides in foods except radiocesiums were also discussed. (author)

  7. The Chernobyl nuclear accident: environmental radioactivity monitoring at the LENA site

    International Nuclear Information System (INIS)

    Genova, N.; Meloni, S.; Rosti, G.; Caramella Crespi, V.

    1986-01-01

    Air pumping and filtration stations nearby the LENA site, routinely active for air radioactivity monitoring, were alerted on April 28, 1986 to look for fission products coming from U.S.S.R. after the Chernobyl accident according to weather forecast. Air filters were submitted to direct gamma ray spectrometry and fission products detected. After May 1st 1986, when the maximum radionuclide concentration in air was observed, an environmental radioactivity monitoring program was started. Several matrices such as milk, soil, grass, vegetables, tap and rain water, were systematically analyzed. At the moment the program is still active but only air, milk, vegetables and meat are periodically analyzed by gamma ray spectrometry. Results, distributions and correlations are presented and discussed. (author)

  8. Real Time Radioactivity Monitoring and its Interface with predictive atmospheric transport modelling

    International Nuclear Information System (INIS)

    Raes, F.

    1990-01-01

    After the Chernobyl accident, a programme was initiated at the Joint Research Centre of the Commission of the European Communities named 'Radioactivity Environmental Monitoring' (REM). The main aspects considered in REM are: data handling, atmospheric modelling and data quality control related to radioactivity in the environment. The first REM workshop was held in December 1987: 'Aerosol Measurements and Nuclear Accidents: A Reconsideration'. (CEC EUR 11755 EN). These are the proceedings of the second REM workshop, held in December 1989, dealing with real-time radioactivity monitoring and its interface with predictive atmospheric models. Atmospheric transport models, in applications extending over time scales of the order of a day or more become progressively less reliable to the extent that an interface with real-time radiological field data becomes highly desirable. Through international arrangements for early exchange of information in the event of a nuclear accident (European Community, IAEA) such data might become available on a quasi real-time basis. The question is how best to use such information to improve our predictive capabilities. During the workshop the present status of on-line monitoring networks for airborne radioactivity in the EC Member States has been reviewed. Possibilities were discussed to use data from such networks as soon as they become available, in order to update predictions made with long range transport models. This publication gives the full text of 13 presentations and a report of the Round Table Discussion held afterwards

  9. Preliminary tests of an infrared process monitor for polyethylene encapsulation of radioactive waste

    International Nuclear Information System (INIS)

    Wright, S.L.; Jones, R.W.; McClelland, J.F.; Kalb, P.D.

    1996-01-01

    Polyethylene encapsulation is a process that is being investigated for the solidification of radioactive nitrate salts at Brookhaven National Laboratory and Rocky Flats Plant. In the encapsulation process, radioactive-salt waste is mixed with polyethylene pellets, heated, and extruded as a molten stream. Upon cooling, the mixture solidifies to a monolithic waste form with excellent properties for long-term waste storage. This paper describes a novel method to monitor the composition of the salt/polymer stream as it exits the extruder. The monitor is based on a technique known as transient infrared spectroscopy (TIRS). The TIRS monitor is able to capture the real-time mid-infrared spectrum of the processed waste stream as it exits the extruder. The wealth of chemical information contained in a mid-infrared spectrum makes this technique very appealing for on-line monitoring and process control. Data from the monitor can be used to guide processing, minimize waste volume, and certify the composition of the final waste form

  10. TLD system for the monitoring of the environmental radioactivity

    International Nuclear Information System (INIS)

    Stochioiu, Ana; Sahagia, Maria; Tudor, Ion

    2008-01-01

    The paper presents a high sensitivity TLD system, designed for the survey of the environmental radioactivity. It is based on the use of TL detectors type LiF:Mg, Cu, P, commercially known as GR-200A. The dosimeter designed in our Institute, contains 3 detectors, and the measurement value is calculated as the arithmetic mean. A very sensitive, TL Reader, READER ANALYSER RA'94 was chosen and an optimal thermal cycle was designed, such as to enhance the measurement performances. For each placement, a set of 3 dosemeters is used, and survey intervals from 1 to 100 days, depending on the radioactivity level and reporting requirements, are selected. The technical characteristics of the system were determined by exposing the dosimeters in reference X and gamma radiation fields, such as required by the IEC standard 61066:iun.2006 'Thermoluminescence dosimetry systems for personal and environmental monitoring'. The main technical parameters are of highest quality and recommend it for use in the survey of the environmental radioactivity, at the level of ambient dose equivalent rate, due to normal natural radioactivity, in open areas. The paper describes the method of characterisation and measurement results, as well as their relevance. (author)

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

    International Nuclear Information System (INIS)

    Sukiman Sarmani

    2002-01-01

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

  12. Demolition and removal of radioactively contaminated concrete soil: Aerosol control and monitoring

    Energy Technology Data Exchange (ETDEWEB)

    Newton, G.J.; Hoover, M.D.; Grace, A.C. III

    1995-12-01

    From 1963 to 1985, two concrete-lined ponds were used to reduce the volume of radioactive liquids from the Institute`s research programs. Following withdrawal of the {open_quotes}hot ponds{close_quotes} from active use, the residual sludges and plastic liners of the ponds were removed and shipped to a radioactive waste disposal site. From 1987 to 1994, the concrete structures remained undisturbed pending environmental restoration on the site. Restoration began in 1994 and was completed in 1995. Restoration involved mechanical breakup and removal of the concrete structures and removal of areas of contaminated soils from the site. This report describes the design and results of the aerosol control and monitoring program that was conducted to ensure protection of workers and the environment during the restoration process. The aerosol control and monitoring strategy developed for remediation of the ITRI hot ponds was successful both in preventing dispersion of radioactive dusts and in demonstrating that exposures of workers and offsite releases were within statutory limits.

  13. Status of radioactivity monitoring in French Polynesia in 2011. Synthesis of the results from the IRSN's monitoring network

    International Nuclear Information System (INIS)

    Bouisset, P.; Bernagout, S.; Leclerc, G.; Rua, J.; Delabbaye, P.; Cagnat, X.

    2012-11-01

    Radiological monitoring of the French environment is one of IRSN's permanent tasks as part of public policy on nuclear safety and radiological protection. It is helping to guarantee the best possible protection of the population. Exercised in Polynesia since 1962, this monitoring, which takes place on seven islands (Tahiti, Maupiti, Hao, Rangiroa, HivaOa, Mangareva and Tubuai) representing the five archipelagos, and consists of taking regular samples of various kinds from the different environmental compartments (air, water, soil, food...) with which the population may be in contact. Regarding food, the samples analyzed are representative of the diet of Polynesians living in the five archipelagos of that territory, and from the marine environment of the open sea, from the lagoon environment and from the terrestrial environment. Almost all samples are measured at the Laboratory for the Study and Monitoring of the Environment IRSN, based in Vairao on the island of Tahiti. The year 2011 was marked by the Fukushima nuclear accident, which occurred on March 11. In this context, IRSN conducted a strengthened monitoring of French Polynesia, thus confirming the absence of radiological impact in Caledonia and Polynesia. The results of analyzes have been published in the previous annual report (report DEI/SESURE 2011-40), this report does not include all data and results for the year 2011, but establishes a synthesis for this year. During the year 2011, results fall under the continuity of a regular reduction of the levels of radioactivity since the stop, in 1974, of the French atmospheric tests. This residual radioactivity relates to primarily the 137 Cs. In term of additional dose, this artificial and residual radioactivity is lower than 5 μSv.y -1 (5 micro-sieverts per year). This value corresponds to less than 0,5 % of exposure due to natural radioactivity in Polynesia (approximately 1 000 μSv.y -1 ). (authors)

  14. Report on radioactivity monitoring during the visits of nuclear powered ships

    International Nuclear Information System (INIS)

    1977-01-01

    The National Radiation Laboratory of the Department of Health is required under NZAEC Report 500 'New Zealand Code for Nuclear Powered Shipping' (June 1976) to monitor for release of radioactivity during the stay of such a ship in a New Zealand port and to provide technical assistance to Civil Defence organisations charged with dealing with any emergency arising from an accidental release of radioactive materials. This report outlines the activities undertaken for the two visits which took place in 1976

  15. Survey monitoring of environmental radioactivity in Busan area

    Energy Technology Data Exchange (ETDEWEB)

    Yang, H. S.; Lee, J. [Busan Regional Monitoring Station, Busan (Korea, Republic of)

    2000-12-15

    At Pusan Regional Monitoring Station in Busan have been measured periodically in 2000 gross beta activities in the airborne dust, fallout, precipitation and tap water and gamma exposure rates. Gamma nuclides in airborne dust, fallout and precipitation have also been monitored at the station. As a part of environmental radiation/radioactivity distribution survey around Pusan, vegetables, fishes, shellfish, drinking water (total 23ea) samples were taken from sampling sites which were selected by KlNS. We analysis gamma nuclide for all. No significant changes from the previous survey have been found in both beta activities and gamma exposure rates. As the results of analyzing an gamma nuclide concentration in environmental samples in Pusan are fee of radiological contaminants.

  16. A Low Level Radioactivity Monitor for Aqueous Waste

    International Nuclear Information System (INIS)

    Quirk, E.J.M.

    1968-04-01

    A system is described for continuous monitoring of very low levels of radioactivity in waste water containing typically 3.5 g/l dissolved solids. Spray evaporation of the water enables the dissolved solids to be recovered in the form of an aerosol and collected on a filter tape where the radioactivity is measured by a radiation detector. The advantage of this method compared with a direct measurement is that the attenuating effect of the water is removed and thus greater sensitivity is obtained. Compensation for background and any contamination is achieved by feeding distilled water to the aerosol generator every alternate sampling period and recording the count difference between two successive sampling periods . A printed record of the totalised count difference is obtained once per hour during the integration time of one month. For β radioactivity the minimum values of specific activity measurable extend from 1 x 10 -6 Ci/m 3 to 6 x 10 -8 Ci/m depending on the B end-point energy in the range 167 KeV to 2.26 MeV. The estimated minimum measurable specific activity is 6 x 10 -8 Ci/m 3

  17. A Low Level Radioactivity Monitor for Aqueous Waste

    Energy Technology Data Exchange (ETDEWEB)

    Quirk, E J.M.

    1968-04-15

    A system is described for continuous monitoring of very low levels of radioactivity in waste water containing typically 3.5 g/l dissolved solids. Spray evaporation of the water enables the dissolved solids to be recovered in the form of an aerosol and collected on a filter tape where the radioactivity is measured by a radiation detector. The advantage of this method compared with a direct measurement is that the attenuating effect of the water is removed and thus greater sensitivity is obtained. Compensation for background and any contamination is achieved by feeding distilled water to the aerosol generator every alternate sampling period and recording the count difference between two successive sampling periods . A printed record of the totalised count difference is obtained once per hour during the integration time of one month. For {beta} radioactivity the minimum values of specific activity measurable extend from 1 x 10{sup -6} Ci/m{sup 3} to 6 x 10{sup -8} Ci/m depending on the B end-point energy in the range 167 KeV to 2.26 MeV. The estimated minimum measurable specific activity is 6 x 10{sup -8} Ci/m{sup 3}.

  18. Radioactivity Monitoring System for TRIGA 2000 Reactor Water Tank with On-Line Gamma Spectrometer

    International Nuclear Information System (INIS)

    Prasetyo Basuki; Sudjatmi KA

    2009-01-01

    One of the requirements in radiological safety in the operating condition of research reactor are the absence of radionuclide from fission product released to reactor cooling water and environment. Early detection of fission product that released from fuel element can be done by monitoring radioactivity level on primary cooling water.Reactor cooling water can be used as an important indicator in detecting radioactivity level of material fission product, when the leakage occurs. Therefore, it needs to build a monitoring system for measuring radioactivity level of cooling water directly and simple. The idea of this system is counting radioactivity water flow from reactor tank to the marinelli cube that attached to the HPGe detector on gamma spectrometer. Cooling water from tank aimed on plastic pipe to the marinelli cube. Water flows in gravitational driven to the marinelli cube, with volume flow rate 5.1 liters/minute in the inlet and 2.2 liters/minute in output. (author)

  19. Radioactivity in the environment. A summary and radiological assessment of the Environment Agency's monitoring programmes; report for 1997

    International Nuclear Information System (INIS)

    1997-01-01

    The Radioactive Substances Act 1993 provides for controls to be exercised over the keeping and use of radioactive materials and, in particular, on the accumulation and disposal of radioactive wastes. The Environment Agency is responsible for administration and enforcement of the Act in England and Wales. In support of these regulatory functions and as part of the UK Government's arrangements for providing information to the European Commission under the Euratom Treaty, the Agency commissions independent monitoring of radioactive waste disposals and their impact on the environment, and monitoring of radioactivity in air, rainwater and drinking water sources. This report presents the data from these monitoring programmes and provides a commentary on their radiological significance. It includes assessments of radiation exposure of members of the public for compliance with the annual dose limit recommended by the International Commission on Radiological Protection. Concentrations of radioactivity in water are also assessed in relation to the guidelines on drinking water quality recommended by the World Health Organisation. This report for 1997 is one of an annual series published by the Agency. It is being distributed to local authorities as part of the arrangements under the Radioactive Substances Act 1993 for provision of access to environmental information. The monitoring programmes and preparation of this report are managed by the Agency's National Compliance Assessment Service. (author)

  20. Radiation monitoring in the mining and milling of radioactive ores

    International Nuclear Information System (INIS)

    1989-01-01

    The present Guide is a revision of IAEA Safety Series No. 43. It explains the recommendations on administrative requirements for the organization of radiation protection in the mining and milling of radioactive ores, and the monitoring requirements, including methods, techniques, instrumentation and strategy. 146 refs, 9 figs, 14 tabs

  1. Radioactivity monitoring network of slovak hydrometeorological institute and its activity within the framework of nuclear emergency information system

    Energy Technology Data Exchange (ETDEWEB)

    Prochazkova, A; Trcka, T [Slovak Hydrometeorological Institute, Bratsislava (Slovakia)

    1996-12-31

    Slovak hydrometeorological institute (SHMI) radioactivity monitoring network is a part of nuclear radiation early warning system. This paper describes the aim and the structure of the monitoring system. Paper presents a short description of radioactivity monitoring network of SHMI and its connection with Austrian and German systems. It provides national means for the monitoring of the radiological effects of nuclear accident and for informing government departments and the public.(J.K.) 2 figs.

  2. Radioactivity monitoring network of slovak hydrometeorological institute and its activity within the framework of nuclear emergency information system

    International Nuclear Information System (INIS)

    Prochazkova, A.; Trcka, T.

    1995-01-01

    Slovak hydrometeorological institute (SHMI) radioactivity monitoring network is a part of nuclear radiation early warning system. This paper describes the aim and the structure of the monitoring system. Paper presents a short description of radioactivity monitoring network of SHMI and its connection with Austrian and German systems. It provides national means for the monitoring of the radiological effects of nuclear accident and for informing government departments and the public.(J.K.) 2 figs

  3. Monitoring of radioactivity in drinking water; Control de la radiactividad en las aguas de consumo humano

    Energy Technology Data Exchange (ETDEWEB)

    Legarda, F.; Herranz, M.; Letessier, P.

    2008-07-01

    Radioactivity is a physical phenomenon whose presence in water is monitored due to its potential capability to induce deleterious effects on human health. In this article the effects that can be caused by radioactivity as well as the way in which regulations establish how to perform a monitorization of water that enables us to ascertain that the radiological quality of water is in agreement with the accepted standard of quality of life are analyzed. Finally the means available to know the content of radioactivity in water together with some clues on how to remove it from water are described. (Author) 5 refs.

  4. Airborne anthropogenic radioactivity measurements from an international radionuclide monitoring system

    International Nuclear Information System (INIS)

    Mason, L.R.; Bohner, J.D.; Williams, D.L.

    1998-01-01

    Anthropogenic radioactivity is being measured in near-real time by an international monitoring system designed to verify the Comprehensive Nuclear Test Ban Treaty. Airborne radioactivity measurements are conducted in-situ by stations that are linked to a central data processing and analysis facility. Aerosols are separated by high-volume air sampling with high-efficiency particulate filters. Radio-xenon is separated from other gases through cryogenic methods. Gamma-spectrometry is performed by high purity germanium detectors and the raw spectral data is immediately transmitted to the central facility via Internet, satellite, or modem. These highly sensitive sensors, combined with the automated data processing at the central facility, result in a system capable of measuring environmental radioactivity on the microbecquerel scale where the data is available to scientists within minutes of the field measurement. During the past year, anthropogenic radioactivity has been measured at approximately half of the stations in the current network. Sources of these measured radionuclides include nuclear power plant emissions, Chernobyl resuspension, and isotope production facilities. The ability to thoroughly characterize site-specific radionuclides, which contribute to the radioactivity of the ambient environment, will be necessary to reduce the number of false positive events. This is especially true of anthropogenic radionuclides that could lead to ambiguous analysis. (author)

  5. Radioactive waste disposal by UKAEA establishments during 1980 and associated environmental monitoring results

    International Nuclear Information System (INIS)

    Flew, E.M.

    1981-09-01

    This report gives details of the amounts of solid and liquid radioactive waste disposed of by the principal establishments of the UKAEA during 1980. Waste arising at the UKAEA Nuclear Power Development Laboratories at Windscale and Springfields, which are both situated on British Nuclear Fuels Ltd. (BNFL)-sites, is disposed of by BNFL and included in their authorisations. Discharges to atmosphere of airborne radioactive waste are also included in the report. A summary of the results of the environmental monitoring programmes carried out in connection with the radioactive waste discharges is given. (author)

  6. Radioactive waste disposal by UKAEA establishments during 1978 and associated environmental monitoring results

    International Nuclear Information System (INIS)

    Flew, E.M.

    1979-05-01

    This report gives details of the amounts of solid and liquid radioactive waste disposed of by the principal establishments of the UKAEA during 1978. Waste arising at the UKAEA Nuclear Power Development Laboratories at Windscale and Springfields, which are both situated on British Nuclear Fuels Ltd. (BNFL) sites, is disposed of by BNFL and included in their authorisations. Discharges to atmosphere of airborne radioactive waste are also included in the report. A summary of the results of the environmental monitoring programmes carried out in connection with the radioactive waste discharges is given. (author)

  7. Monitoring the radioactivity in the secondary systems of a nuclear power plant

    International Nuclear Information System (INIS)

    Labno, L.

    1979-01-01

    The direct water/steam circuit and the waste water and exhaust air systems of a nuclear power plant with boiling water reactor are slightly contaminated with radioactive nuclides during normal operation. In addition some auxiliary and subsidiary systems may show evidence of radioactivity as a result of leakages between the systems. These radioactive substances and those which are discharged to the environment in exhaust air or waste water - although present in quantities far below the admissible limits - still require supervision by a comprehensive activity monitoring system. The article sets out the concept and the technical solution adopted for the activity monitoring system for the secondary section of a nuclear power station. The system is so designed that it provides the information and performs the safety functions important for highly reliable plant operation. Particular importance has been attached to the reliability and dependability of the system, so that incorrect interpretations or reports, such as have been experienced, for example, in the nuclear power plants 'Brunsbuettel' (Federal Republic of Germany) and 'Three Mile Island', near Harrisburg (USA), will not be repeated. (Auth.)

  8. Radioactivity in the environment. A summary and radiological assessment of the Environment Ageny's monitoring programmes. Report for 1996

    International Nuclear Information System (INIS)

    1996-01-01

    This report presents the results from the Environment Agency's monitoring of radioactivity in the environment during 1996. Monitoring programmes were carried out in support of the Agency's regulatory functions under the Radioactive Substances Act 1993 and as part of the UK Government's obligations under the Euratom Treaty. The programmes included: effluent monitoring; the quality checking of solid waste disposals; environmental monitoring; the monitoring of radioactivity in air and rainwater; the monitoring of radioactivity in drinking water sources. A total of 160 effluent samples were analysed for nearly 900 determinants, two consignments of solid radioactive waste destined for disposal at British Nuclear Fuels' site at Drigg were checked, direct instrumental monitoring was carried out at ISO locations within the vicinity of nuclear sites, and 532 environmental samples were analysed for over 2,000 determinants. Effluent monitoring: The Agency requires operators of certain sites to provide samples of their liquid effluents for independent analysis. The results are compared with reports submitted by site operators. The majority of results showed satisfactory agreement; operators' values were frequently higher than the Agency's measurements indicating that they were not under-reporting. However, some discrepancies were found and are being investigated. Quality checking of solid waste disposals: Consignments of solid low level radioactive waste are seized by inspectors for examination at the Agency's Waste Quality Checking Laboratory. Sophisticated non-destructive and destructive analytical techniques are used at the laboratory to check the radioactive content and description of the wastes. Consignments of waste from the Atomic Weapons Establishment at Aldermaston and Amersham International at Amersham were examined. In both cases the operators reported higher activity than the Agency's laboratory. The consignments also conformed with the operators' disposal

  9. Spotting Radioactive Sources Buried Underground Using an Airborne Radiation Monitoring System

    International Nuclear Information System (INIS)

    Sheinfeld, M.; Wengrowicz, U.; Beck, A.; Marcus, E.; Tirosh, D.

    2002-01-01

    This article provides theoretical background concerning the capability of the Airborne Radiation Monitoring System [1]to detect fission products buried at 1-meter depth under the ground surface,at a flight altitude of 100 meters above ground.The 137 Cs source was used as a typical fission product. The System monitors radioactive contamination in the air or on the ground using two 2 inch NaI(Tl) scintillation detectors and computerized accessories for analysis purposes

  10. Monitoring technologies for ocean disposal of radioactive waste

    Science.gov (United States)

    Triplett, M. B.; Solomon, K. A.; Bishop, C. B.; Tyce, R. C.

    1982-01-01

    The feasibility of using carefully selected subseabed locations to permanently isolate high level radioactive wastes at ocean depths greater than 4000 meters is discussed. Disposal at several candidate subseabed areas is being studied because of the long term geologic stability of the sediments, remoteness from human activity, and lack of useful natural resources. While the deep sea environment is remote, it also poses some significant challenges for the technology required to survey and monitor these sites, to identify and pinpoint container leakage should it occur, and to provide the environmental information and data base essential to determining the probable impacts of any such occurrence. Objectives and technical approaches to aid in the selective development of advanced technologies for the future monitoring of nuclear low level and high level waste disposal in the deep seabed are presented. Detailed recommendations for measurement and sampling technology development needed for deep seabed nuclear waste monitoring are also presented.

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

    International Nuclear Information System (INIS)

    Mitic, D.

    2003-01-01

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

  12. Radioactivity monitoring of the Irish marine environment 1991 and 1992

    International Nuclear Information System (INIS)

    McGarry, A.; Lyons, S.; McEnri, C.; Ryan, T.; O'Colmain, M.; Cunningham, J.D.

    1994-05-01

    This report presents the results of the Radiological Protection Institute's programme of monitoring of radioactivity in the seas around Ireland during 1991 and 1992. The principal objective of the monitoring programme is to review the risks to human health arising from the Sellafield discharges. Secondary objectives include studies of the distribution of the significant contaminating radionuclides in the marie environment and the identification of trends with a view to assessing possible future effects. Estimates of the radiation doses to the Irish public are also presented in this report. 23 refs. 24 tabs. 9 figs

  13. Thermoexoemission detectors for monitoring radioactive contamination of industrial waste waters

    International Nuclear Information System (INIS)

    Obukhov, V.T.; Sobolev, I.A.; Khomchik, L.M.

    1987-01-01

    Detectors on base of BeO(Na) monocrystals with thermoemission to be used for monitoring radioactive contamination of industrial waste waters are suggested. The detectors advantages are sensitivity to α and low-ehergy β radiations, high mechanical strength and wide range of measurements. The main disadvantage is the necessity of working in red light

  14. Environmental monitoring and deep ocean disposal of packaged radioactive waste

    International Nuclear Information System (INIS)

    Mitchell, N.T.; Preston, A.

    1980-01-01

    Environmental monitoring in the context of the dumping of packaged radioactive waste in the deep ocean is discussed in detail. The principles and objectives laid down by the IAEA and the ICRP are reviewed. Monitoring and its relationships to radiation exposure, research, control measures and public information are described. Finally, the actual practice in the UK of environmental monitoring is detailed for the measurable case of liquid wastes in coastal waters and also for package waste in deep oceans which has to be calculated. It is concluded that better mathematical models are needed to predict the dose to man and that more research into oceanographic and biological transfer processes should be carried out. (UK)

  15. Methods of surveying and monitoring marine radioactivity. Report of an ad hoc panel of experts

    International Nuclear Information System (INIS)

    1965-01-01

    An effective control of the radioactive pollution of the sea depends partly on the availability of adequate technical methods for surveying and monitoring the sea and marine products with regard to the presence of radioactive substances. The purpose of this manual is to offer such methods.

  16. Radioactivity monitoring of the Irish marine environment 1993 to 1995

    International Nuclear Information System (INIS)

    Pollard, D.; Long, S.; Hayden, E.; Smith, V.; Ryan, T.P.; Dowdall, A.; McGarry, A.; Cunningham, J.D.

    1996-10-01

    This report presents the results of the marine radioactivity monitoring programme carried out by the Radiological Protection Institute of Ireland during the period 1993 to 1995. The principal objective of this programme is to assess the exposure to the Irish population arising from radioactive contamination in the Irish marine environment and to estimate the risks to human health arising from such exposure. In addition, the programme aims to assess the distribution of the significant contaminating radionuclides in the marine environment and to identify tends with a view to assessing possible future effects. The results show that by 1995 the mean concentration of caesium-137 in fish landed at north-east ports had fallen to 1.6 Bq/kg, from a figure of 68 Bq/kg in 1979-82 and 3.0 Bq/kg in 1993. A similar decline is evident for seawater, sediment and seaweed. In addition, the Irish Sea data show the progressive dilution of artificial radioactivity with increasing distance from Sellafield

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

    International Nuclear Information System (INIS)

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

    1992-01-01

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

  18. An integrate system for radioactivity monitoring

    International Nuclear Information System (INIS)

    Rusu, Al.; Bartos, D.; Constantin, F.; Stanga, D.; Giolu, Gh.; Calin, R.; Guta, T.; Stochioiu, A.; Lupu, A.

    2003-01-01

    This is one of the projects included in IFIN-HH nucleus programme 'Nuclear Physics Advanced Researches and Applied Nuclear Techniques'. A new instrument generation for measuring or monitoring the environmental radioactivity is to be developed, based on nowadays components, technology and data processing methods. The additional results should be: - the instrument and related procedures to certify the national standard for neutron dosimetry; - the operational simplicity and higher confidence in the new portable instruments for radioprotection; - the instruments and methods for gas absolute volume activity measuring laboratory; - transportable stand to measure the efficiency of the aerosol filtering systems; - PC based technique to reconstruct the radiometric map of an area supervised by an intelligent gamma probe array. The lecture is a review of the activities to be done. (authors)

  19. Radioactive waste disposal by UKAEA establishments during 1979 and associated environmental monitoring results

    International Nuclear Information System (INIS)

    Flew, E.M.

    1980-07-01

    This report gives details of the amounts of solid and liquid radioactive waste disposed of by the principal establishments of the UKAEA during 1979. Waste arising at the UKAEA Nuclear Power Development Laboratories at Windscale and Springfields, which are both situated on British Nuclear Fuels Ltd. (BNFL) sites, is disposed of by BNFL and included in their authorisations. Discharges to atmosphere of airborne radioactive waste are also included in the report. A summary of the results of the environmental monitoring programmes carried out in connection with the radioactive waste discharges is given. To facilitate an appreciation of the standard of safety achieved, the discharges are, where appropriate, shown as a percentage of those authorised. In the case of atmospheric discharges no quantitative limits are yet specified in the authorisations, but the results and estimates of discharges from stacks are compared with Derived Working Limits (DWL's) (i.e. a limit derived from the dose limits recommended by The International Commission on Radiological Protection in such a way that compliance with it implies virtual certainty of compliance with the relevant dose limits). Environmental monitoring results are also compared with appropriate DWL's. The principles underlying the control of the discharge of radioactive waste to the environment are summarised in an Appendix to the report. (author)

  20. Annual report on radioactive discharges and monitoring of the environment 1993. V. 2: Certificates of authorisation and environmental monitoring programmes

    International Nuclear Information System (INIS)

    1994-01-01

    British Nuclear Fuels plc's Certificates of Authorisation, under which it operates, are reproduced in the second volume of the 1993 Annual Report on Radioactive Discharges and Monitoring of the Environment. The report also includes environmental monitoring programmes relating to discharge authorisation for each of the Sellafield, Drigg, Chapelcross, Springfields and Capenhurst sites. (UK)

  1. Evil radioactivity. Subjective perception of radioactivity in patients with thyroid disease prior to treatment with radioiodine

    International Nuclear Information System (INIS)

    Freudenberg, L.S.; Beyer, T.; Mueller, S.P.; Goerges, R.; Bockisch, A.

    2006-01-01

    Aim: We assess the perspective of patients with thyroid disease towards radiation and radioactivity by means of a cultural-anthropological approach based on qualitative measures and quantitative scores. From the interviews with the patients we evaluate as to how much radioactivity is accepted as an abstract term or as a benefit within the medical context. Patients, methods: 68 patients with autonomously functioning thyroid lesions (35 women, 33 men, 32-81 years) were included in this study. All patients were interviewed in an open dialogue with the principal investigator. Patients were asked to describe their attitude towards radioactivity in general and towards radioiodine therapy in particular. Patients were asked to use a scoring system (1=positive, 5=negative) to quantify their attitudes. Results: The responses of all patients towards radioactivity in general were heterogeneous with most responses reflecting a negative perception. Many patients expressed their associated fears about atomic energy, malignant diseases and radioactive contamination. The scoring system reflected a mostly negative opinion base. However, patients became more positive once they assumed an immediate benefit of radioactivity for the treatment of their own disease (p=0.01). Conclusions: Knowing about significant differences in patient's perception about radioactivity in general or in the clinical context may help to optimise and tailor the initial, pre-therapeutical interview towards the patient. (orig.)

  2. Evil radioactivity. Subjective perception of radioactivity in patients with thyroid disease prior to treatment with radioiodine

    Energy Technology Data Exchange (ETDEWEB)

    Freudenberg, L.S. [Universitaetsklinikum Essen (Germany). Klinik fuer Nuklearmedizin; Radiologisch-Nuklearmedizinische Gemeinschaftspraxis, Grevenbroich (Germany); Beyer, T.; Mueller, S.P.; Goerges, R.; Bockisch, A. [Universitaetsklinikum Essen (Germany). Klinik fuer Nuklearmedizin; Hopfenbach, A. [Radiologisch-Nuklearmedizinische Gemeinschaftspraxis, Grevenbroich (Germany)

    2006-07-01

    Aim: We assess the perspective of patients with thyroid disease towards radiation and radioactivity by means of a cultural-anthropological approach based on qualitative measures and quantitative scores. From the interviews with the patients we evaluate as to how much radioactivity is accepted as an abstract term or as a benefit within the medical context. Patients, methods: 68 patients with autonomously functioning thyroid lesions (35 women, 33 men, 32-81 years) were included in this study. All patients were interviewed in an open dialogue with the principal investigator. Patients were asked to describe their attitude towards radioactivity in general and towards radioiodine therapy in particular. Patients were asked to use a scoring system (1=positive, 5=negative) to quantify their attitudes. Results: The responses of all patients towards radioactivity in general were heterogeneous with most responses reflecting a negative perception. Many patients expressed their associated fears about atomic energy, malignant diseases and radioactive contamination. The scoring system reflected a mostly negative opinion base. However, patients became more positive once they assumed an immediate benefit of radioactivity for the treatment of their own disease (p=0.01). Conclusions: Knowing about significant differences in patient's perception about radioactivity in general or in the clinical context may help to optimise and tailor the initial, pre-therapeutical interview towards the patient. (orig.)

  3. Report on radioactive discharges and environmental monitoring at nuclear power stations during 1991

    International Nuclear Information System (INIS)

    Hurst, M.J.; Thomas, D.W.

    1992-09-01

    This report presents the details for 1991 of radioactive discharges and environmental monitoring at Nuclear Electric sites. In addition to the main section which summarises the discharges and monitoring at the Company's nuclear sites as a whole, appendices are presented covering the data in detail for individual sites. In each case the radiological impact on the general public has been estimated. Discharges generally were not substantially different from those of recent years. All radioactive effluent discharges from power stations were within authorised limits. Radiation doses to members of the public resulting from these discharges, and from direct radiation from the Stations, were in all cases less than the limit of 1 mSv per year which has been recommended by ICRP since 1985. (Author)

  4. Environmental radioactivity monitoring around Jeongeup ARTI in 2009

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Yun Jong; Kwon, Ho Je; Kang, Tai Jin [KAERI, Daejeon (Korea, Republic of)

    2010-08-15

    In Advanced Radiation Technology Institute (ARTI), the environmental radioactivity monitoring programme has been enforced since 2007. This study has been done to guarantee the local residence radiation safety by detecting in early stage a possible radiological effect due to the operation of the ARTI facilities. For the radioactivity measurement, fourteen selected samples were gathered not only monthly, quarterly, half-yearly but also in the harvesting season. Measurement and analysis were done on the samples collected in and around the ARTI. The gamma exposure rates measured in and around ARTI was in the range of 0.05{approx}0.3 {mu}Sv/h. The range of gross-beta-radioactivity analyzed for the water samples except waste water was from <3.451 to 288 mBq/L. The range of 3H concentration detected in the rain sample collected in the ARTI site was 0.951{approx}2.34 Bq/L. 90Sr was not detected from all the samples of soil and honey, pine needles. The above results confirmed that there has been no influence due to operation of the ARTI facilities.. The analysis result reveals that there is no radiological influence due to operation of the ARTI facilities. Also, it is judged that the samples analyzed for the first time in 2009 have to be continuously evaluated afterward

  5. Monitoring of radioactivity in the UK environment. An annotated bibliography of current programmes

    International Nuclear Information System (INIS)

    2001-01-01

    With the continuing use of radioactive materials in industry, research and medicine, the public's awareness about the potential impact on human health and safety of any enhanced levels of radiation in the environment has heightened. All those involved recognise this concern and there has developed over the years a network of comprehensive monitoring systems designed to determine the levels of radiation to which members of the public are exposed. In the UK, many organisations carry out regular radioactivity monitoring programmes, and summaries of these programmes have been published in 1983, 1988 and 1992. The number of organisations carrying out monitoring, particularly in the local authority sector, increased rapidly following the Chernobyl incident in 1986 and later levelled off. This report updates those previous summaries, giving synopses of regular UK programmes whose results are published in report form, and of which the Department of the Environment, Transport and the Regions is currently aware

  6. Radioactivity in the scrap recycling process: Radiation protection aspects and experimental monitoring problems

    International Nuclear Information System (INIS)

    Sacco, D.; Ruggeri, F.; Bindi, G.; Bonanni, A.; Casciardi, S.; Delia, R.; Loppa, A.; Rossi, P.; Venturini, L.

    1996-01-01

    The steel scrap recycling by steel mill is increasing moved by profits and by purpose of protection of environmental resources. Besides the use of radioactive sources in several fields (medical, industrial and in scientific researches) on one hand, and the disposal of made radioactive materials from nuclear reactors on the other one, makes the likelihood no more negligible that some radionuclides could be found, accidental y or fraudulently, in steel recycling scrap. Radiation protection problems for surveillance both employees in the production cycle and of people and environment in general arose. First of all, we characterize different type of radioactive materials that can found in scraps, pointing out the potential hazards from exposure of workers and people and from environmental contamination, related to physical and chemical specifications of the involved radionuclides. Some suitable monitoring equipment for scrap recycling facilities are discussed, related to the different step of production cycle (transport, storage, manipulation and melting). At last experimental data, taken in some periods of the monitoring campaign made at the Italian border on imported scraps, are presented. (author)

  7. Storage of radioactive material - accidents - precipitation - personnel monitoring; Stokiranje radioaktivnih materijala - akcidenti - padavine - kontrola osoblja

    Energy Technology Data Exchange (ETDEWEB)

    Matijasic, A; Gacinovic, O [Institute of Nuclear Sciences Boris Kidric, Radioloska zastita, Vinca, Beograd (Serbia and Montenegro)

    1961-12-15

    This volume covers the reports on four routine tasks concerned with safe handling of radioactive material and influence of nuclear facilities on the environment. The tasks performed were as follows: Storage of solid and liquid radioactive material; actions in case of accidents; radiation monitoring of the fallout, water and ground; personnel dosimetry.

  8. Examination of the new index creatures for environmental radioactivity monitoring

    International Nuclear Information System (INIS)

    Yamaguchi, Y.; Saito, T.

    2001-01-01

    The purpose of the environmental radioactivity monitoring is to watch over the radiation hazard to the human body, fallout resting from the nuclear test and the environmental pollution around the nuclear facilities and so forth. The measurement of the environmental radioactivity is done using samples like the atmosphere, land water, land soil, bottom soil of the sea and lake, drainage, food, marine samples, index creatures, etc. The index creatures in the land are pine needle, cryptomeria leaf, mugwort and so on. However, in recent years, they are decreasing at the city. Therefore, Kin-mokusei and Pothos are examined using the microwave heating distillation system developed by Radioisotope Research Center of Osaka University, it was proved that they had possibility of the new index creature. (author)

  9. A radioactive aerosols in air monitoring system - 'ASIA'

    International Nuclear Information System (INIS)

    Belaish, I.; Levinson, S.; Pelled, O.; German, U.; Laichter, Y.; Gonen, E.; Wengrowicz, U.; Tirosh, D.; Barak, D.

    1997-01-01

    A continuous air monitoring system called 'ASIA' (Aerosols Sampler In Air) was developed at the NRCN for monitoring and measuring the concentration of airborne alpha emitting radionuclides such as Radon or natural Uranium. The 'ASIA' is a stationary multi-channel analyzer based system. The air passes through a 2.5 cm diameter filter and the radioactivity accumulated on it is monitored by a Silicon solid state detector. The sampling unit can be separated from the display and control unit to enable environment sampling close to the workers. The ASIA uses modern hardware and software in order to improve noise and background reduction and to allow friendly and flexible use. Remote communication is also available. The spectrum and additional data are displayed on line. The system was checked according to ANSI N42.17B -1989. The linearity and efficiency were evaluated by using various alpha sources. The Minimum Detectable Activity (MDA) and Decision Limit (Lc) were calculated according to ANSI N13.30. Long time stability measurements were performed using a natural Uranium source. (authors)

  10. Annual report on radioactive discharges and monitoring of the environment 1982

    International Nuclear Information System (INIS)

    1983-08-01

    A report is given on the liquid, airborne and solid radioactive discharges through authorised outlets and on environmental monitoring for all of BNFL's Works and sites for 1982, i.e. Sellafield Site and the Drigg Storage and Disposal Site; Chapelcross Works; Springfields Works and the Ulnes Walton Disposal Site; and Capenhurst Works. The report includes assessment of radiation doses to representative members of the most highly exposed group of the general population for the most important environmental pathways. At no time during 1982 have discharges and disposals of radioactive wastes through authorised outlets at any of the above Works exceeded those laid down in any of the Authorisations. (U.K.)

  11. 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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1992-01-01

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

  13. Activities and Issues in Monitoring Scrap Metal Against Radioactive Sources

    Energy Technology Data Exchange (ETDEWEB)

    Chen, S.Y., E-mail: sychen@anl.gov [Argonne National Laboratory, Argonne, IL (United States)

    2011-07-15

    Over the past few decades, the global scrap metal industry has grown increasingly vigilant regarding radioactive contamination. Accidental melts of radioactive sources in some smelting facilities, in particular, have caused considerable damage and required recovery efforts costing tens of millions of dollars. In response, the industry has developed and deployed countermeasures. Increasingly expensive and sophisticated radiation monitoring devices have been implemented at key scrap entry points - ports and scrapyards. Recognition of the importance of such endeavors has led to a series of activities aimed at establishing organized and coordinated efforts among the interested parties. Recent concerns over the potential use of radioactive sources for radiological devices in terrorist acts have substantially heightened the need for national and international authorities to further control, intercept, and secure the sources that have escaped the regulatory domain. Enhanced collaboration by the government and industry could substantially improve the effectiveness of efforts at control; the 'Spanish Protocol' as developed by the Spanish metal industry and government regulators is a good example of such collaboration. (author)

  14. A fuzzy logic based method to monitor organizational resilience: application in a brazilian radioactive facility

    International Nuclear Information System (INIS)

    Grecco, Claudio H.S.; Santos, Isaac J.A.L.; Carvalho, Paulo V.R.; Vidal, Mario C.R.; Cosenza, Carlos A.N.

    2013-01-01

    Resilience is the intrinsic ability of a system to adjust its functioning prior to, during, or following changes and disturbances, so that it can sustain required operations under expected and unexpected conditions. This definition focuses on the ability to function, rather than on being impervious to failure, and thereby overcomes the traditional conflict between productivity and safety. Resilience engineering (RE) has fast become recognized as a valuable complement to the established approaches to safety of complex socio-technical systems and methods to monitor organizational resilience are needed. However, few, if any, comprehensive and systematic research studies focus on developing an objective, reliable and practical assessment model for monitoring organizational resilience. Most methods cannot fully solve the subjectivity of resilience evaluation. In order to remedy this deficiency, the aim of this research is to adopt a Fuzzy Set Theory (FST) approach to establish a method for resilience assessment in organizations based on leading safety performance indicators, defined according to the resilience engineering principles. The method uses FST concepts and properties to model the indicators and to assess the results of their application. To exemplify the method we performed an exploratory case study at the process of radiopharmaceuticals dispatch package of a Brazilian radioactive facility. (author)

  15. A fuzzy logic based method to monitor organizational resilience: application in a brazilian radioactive facility

    Energy Technology Data Exchange (ETDEWEB)

    Grecco, Claudio H.S.; Santos, Isaac J.A.L.; Carvalho, Paulo V.R., E-mail: grecco@ien.gov.br, E-mail: luquetti@ien.gov.br, E-mail: paulov@ien.gov.br [Instituto de Engenharia Nuclear (IEN/CNEN-RJ), Rio de Janeiro, RJ (Brazil). Divisao de Instrumentacao e Confiabilidade Humana; Vidal, Mario C.R.; Cosenza, Carlos A.N., E-mail: mvidal@ergonomia.ufrj.br, E-mail: cosenza@pep.ufrj.br [Coordenacao dos Programas de Pos-Graduacao em Engenharia (PEP/COPPE/UFRJ), Rio de Janeiro, RJ (Brazil). Programa de Engenharia de Producao

    2013-07-01

    Resilience is the intrinsic ability of a system to adjust its functioning prior to, during, or following changes and disturbances, so that it can sustain required operations under expected and unexpected conditions. This definition focuses on the ability to function, rather than on being impervious to failure, and thereby overcomes the traditional conflict between productivity and safety. Resilience engineering (RE) has fast become recognized as a valuable complement to the established approaches to safety of complex socio-technical systems and methods to monitor organizational resilience are needed. However, few, if any, comprehensive and systematic research studies focus on developing an objective, reliable and practical assessment model for monitoring organizational resilience. Most methods cannot fully solve the subjectivity of resilience evaluation. In order to remedy this deficiency, the aim of this research is to adopt a Fuzzy Set Theory (FST) approach to establish a method for resilience assessment in organizations based on leading safety performance indicators, defined according to the resilience engineering principles. The method uses FST concepts and properties to model the indicators and to assess the results of their application. To exemplify the method we performed an exploratory case study at the process of radiopharmaceuticals dispatch package of a Brazilian radioactive facility. (author)

  16. Remote monitoring of radioactive sources based on i.MX27 platform

    International Nuclear Information System (INIS)

    Li Defeng; Wang Renbo; Lin Gangyong; Ding Yufei

    2012-01-01

    It based on the ASIC solutions, has chosen Freescale's i.MX27 development system as a platform for designing video capture and transmission system. The article uses the latest H.264 video compression standard and complete the entire system of hardware and software design, which is successfully applied to remote monitoring of radioactive sources. (authors)

  17. Situation of radioactivity monitoring in French Polynesia in 2014. Synthesis of results from the IRSN's monitoring network

    International Nuclear Information System (INIS)

    Bouisset, P.; Nohl, M.; Leclerc, G.; Rua, J.; Bernagout, S.; Delabbaye, P.; Vismes, A. de

    2015-01-01

    Exercised in Polynesia since 1962, the radiological monitoring of the environment, which takes place on seven islands (Tahiti, Maupiti, Hao, Rangiroa, Hiva Oa, Mangareva and Tubuai) representing the five archipelagos, and consists in taking regular samples of various kinds from the different environmental compartments (air, water, soil) with which the population may be in contact and foods. For the first time in 2014, IRSN have participating to the TURBO DGA and CEA program, in charge of the military atoll radiological monitoring, and have collecting ocean samples at Moruroa. Regarding food, the samples analysed are representative of the diet of Polynesians living in the five archipelagos of that territory, and from the marine environment of the open sea, from the lagoon environment and from the terrestrial environment. Almost all samples are measured at the Laboratory for the Study and Monitoring of the Environment IRSN, based in Vairao on the island of Tahiti. After a steady fall in radioactivity levels since the French atmospheric tests come to an end in 1974, the radiological level observed in 2014 has been stable in the recent year and is now very low. This residual radioactivity relates primarily to the 137 Cs. In term of additional dose, this artificial and residual radioactivity is lower than 5 μSv.y -1 (5 micro-sieverts per year). This value corresponds to less than 0.5 % of exposure due to natural radioactivity in Polynesia (approximately 1,000 μSv.y -1 ). From 2010, monitoring of natural radioactivity was performed in several islands. Dose rates are very low, below 1,000 μSv.y -1 . However, highest results were observed when soils come from volcanoes rocks, like on the 'marae'. The highest value, 6,000 μSv.y -1 , was detected on the Taiata mount at Tubuai. In 2014, these maps concerned Tahiti, Moorea, Hao and Gambier islands. Enhanced radiological monitoring of the environment set up in the wake of the Fukushima disaster, continued in 2014

  18. Environmental radioactivity monitoring at Rirang and Eko Remaja area Kalan West Kalimantan period 1997/1998

    International Nuclear Information System (INIS)

    Achmad-Sorot-Soediro; Eep-Dedi

    2000-01-01

    The research has been done for the purpose of monitoring radioactivity's level in the environment at Rirang and Eko Remaja Kalan, West Kalimantan, which will be exposed the impact of radioactivity environment at Rirang and Eko Remaja Kalan. The method which was applied in the field is direct measurement and samples collecting from water, stream sediment and soil sample were taken to site at environment Rirang, Remaja tunnel and uranium processing at Lemajung. The samples were analysed using spectrophotometer and Scintillation Alpha Counter SAC - R5 Eberline at Environment and Safety laboratory. Radiation exposure level monitoring applied at 18 location point at Eko Remaja Kalan and 12 location point at Rirang by Scintillation SPP 2 NF which had been calibrated. The experiment data showed that radioactivity of U, Th, Ra-226 and radiation exposure at Eko Remaja Kalan and Rirang were below threshold of limit value

  19. Proposal of a monitoring program of occupational exposure by incorporation of radioactive material for nuclear medicine services in the Caja Costarricense del Seguro Social

    International Nuclear Information System (INIS)

    Badilla Segura, Mirta

    2013-01-01

    A monitoring program of the occupational exposure by incorporation of radioactive material is proposed. Nuclear medicine services of the Caja Costarricense del Seguro Social (CCSS) are evaluated. The monitoring program is based on the provisions of the International Atomic Energy Agency and of study of nuclear medicine services of the CCSS. Radionuclides are determined for monitoring of the occupational exposure, according to the radioactive material that is worked in nuclear medicine services of the CCSS. The appropriate and alternative techniques are established for the monitoring of the occupational exposure by incorporation of radioactive material, depending on the type of radionuclide that is worked in nuclear medicine services. The worker occupationally exposed (TOE) should be subject of monitoring and how often should be realized the monitoring of the occupational exposure. The monitoring of the radiation by radioactive material must be applied to personnel working in radiopharmacies and the worker has carried out therapeutic procedures for handling of significant amounts of 13 1 I. The calculation of the committed effective dose is proposed by incorporation of radioactive material with the TOE [es

  20. New Monitoring System to Detect a Radioactive Material in Motion

    International Nuclear Information System (INIS)

    Boudergui, Karim; Kondrasovs, Vladimir; Coulon, Romain; Corre, Gwenole; Normand, Stephane

    2013-06-01

    Illegal radioactive material transportation detection, by terrorist for example, is problematic in urban public transportation. Academics and industrials systems include Radiation Portal Monitor (RPM) to detect radioactive matters transported in vehicles or carried by pedestrians. However, today's RPMs are not able to efficiently detect a radioactive material in movement. Due to count statistic and gamma background, false alarms may be triggered or at the contrary a radioactive material not detected. The statistical false alarm rate has to be as low as possible in order to limit useless intervention especially in urban mass transportation. The real-time approach depicted in this paper consists in using a time correlated detection technique in association with a sensor network. It is based on several low-cost and large area plastic scintillators and a digital signal processing designed for signal reconstruction from the sensor network. The number of sensors used in the network can be adapted to fit with applications requirements or cost. The reconstructed signal is improved by comparing other approaches. This allows us to increase the device speed that has to be scanned while decreasing the risk of false alarm. In the framework of a project called SECUR-ED Secured Urban Transportation - European Demonstration, this prototype system will be used during an experiment in the Milan urban mass transportation. (authors)

  1. Monitoring of radioactive contamination in food and the environment 1986-1998

    International Nuclear Information System (INIS)

    Liland, Astrid; Skuterud, Lavrans; Bergan, Tone; Forseth, Torbjoern; Gaare, Eldar; Hellstroem, Turid

    2001-01-01

    The results from the national monitoring of radioactive contamination in food and the environment 1986-1998 are presented. The average 137Cs concentration is decreasing in cow's and goat's milk, sheep, reindeer and fresh water fish. Pasture and fungi are, on the contrary, not showing a general decreasing trend. The radioactivity in food and humans has been decreasing since 1987. The effective dose from intake is estimated to 0.02 mSv for an average Norwegian in 1998. Vulnerable groups may have received doses up to 0.4 mSv. One cannot rule out the possibility that some individuals in these groups have received doses superior to 1 mSv/year. (Author)

  2. Radioactivity leakage monitoring system

    International Nuclear Information System (INIS)

    Nakajima, Takuichiro; Noguchi, Noboru.

    1982-01-01

    Purpose: To obtain a device for detecting the leakage ratio of a primary coolant by utilizing the variation in the radioactivity concentration in a reactor container when the coolant is leaked. Constitution: A measurement signal is produced from a radioactivity measuring instrument, and is continuously input to a malfunction discriminator. The discriminator inputs a measurement signal to a concentration variation discriminator when the malfunction is recognized and simultaneously inputs a measurement starting time from the inputting time to a concentration measuring instrument. On the other hand, reactor water radioactivity concentration data obtained by sampling the primary coolant is input to a concentration variation computing device. A comparator obtains the ratio of the measurement signal from the measuring instrument and the computed data signal from the computing device at the same time and hence the leakage rate, indicates the average leakage rate by averaging the leakage rate signals and also indicates the total leakage amount. (Yoshihara, H.)

  3. Research on design method of main control room intake air radioactive monitoring

    International Nuclear Information System (INIS)

    Li Lei; Sun Yu; Wang Jiaoya; Liu Hongtao

    2014-01-01

    According to the design of the main control room intake gamma radiation dose rate monitoring channels in CPR1000 project and the study of relevant regulations and standards, a design method of main control room air inlet radioactive monitoring was presented. The measured object, equipment layout and chain operation were described. The threshold setting was explored using a calculation model established by MCNP software. The advantages, disadvantages and improvement ideas of this design were presented on the basis of calculation results. (authors)

  4. Radioactivity on the surfaces of computer monitors and television screens due to progeny palatal

    International Nuclear Information System (INIS)

    Abdel-Nady, A.; Morsy, A.A.

    2002-01-01

    Computer monitors and television screens can collect radon progeny. Radon decay forming meta-stable progeny, namely, Po-218, Po-214, and Po-210, which are found mostly in positively, charged aerosol particles. These particles are attract by the large negative field of a video display terminals (VDT) leading to buildup of radioactivity on the VDT screen. The charged aerosol particles might drift in the electric field between the VDT and the operator and be accelerated into the operator's face. The aim of this work is to measure these phenomena set of ultra-sensitive TASTRAK detectors used to measure the plate out of positively charged radioactive radon progeny. The track detectors were fixed on the outer monitor screen. For an occupational computer worker spending 200 days per year for 6 hours a day. It was found that the mean dose equivalent was 1.77 mSv, 0.25 mSv/year for normal CRT and LCD monitors respectively

  5. Kalman filtration of radiation monitoring data from atmospheric dispersion of radioactive materials

    DEFF Research Database (Denmark)

    Drews, M.; Lauritzen, B.; Madsen, H.

    2004-01-01

    A Kalman filter method using off-site radiation monitoring data is proposed as a tool for on-line estimation of the source term for short-range atmospheric dispersion of radioactive materials. The method is based on the Gaussian plume model, in which the plume parameters including the source term...

  6. Use of aquatic bryophytes as bio monitors for radioactive studies

    International Nuclear Information System (INIS)

    Damianova, A.; Penev, I.; Drenska, M.

    2006-01-01

    As a widespread water moss Fontinalis antipyretics is frequently used as a biomonitor for trace elements pollution in lakes and running waters. The purpose of this study is to use Fontinalis antipyretics as a tool for monitoring of radioactivity in waters from different rivers (Musalenska Bistriza, Iskar, Maritza, etc.) in Rila Mountain. The radioactivity of aquatic moss, water samples and sediments were measured using HPG detector with the parameters FWHM 2 kev at 6 0Co efficiency 35% with low background. The dose rate measurements (μR/h) show different values according to the place of sampling and reflect the present ecological status of the river ecosystems. The ongoing measurements will allowed the absolute value of 1 37Cs in bryophytes to be determined and eventually some seasonal variations to be observed. A special interest is whether the measured activity is accidental or is as a consequence of a long time accumulation in the bryophytes. In this case they could probably be used for water purification. On that basis the bryophytes could be used for controlling radioactivity of river ecosystems even in high-mountain difficult accessible places replacing the transportation of large volumes of water

  7. Test what you eat. Monitoring of radioactivity in the food chain

    International Nuclear Information System (INIS)

    2014-01-01

    Since 2013, the total beta activity in animal feed products being exported to Belarus shall be lower than 600 Becquerel per kilogram. The Belgian Nuclear Research Center SCK-CEN carries out these checks on behalf of the professional association of compound feed manufacturers in Belgium. The article discusses work conducted by SCK-CEN relating to the monitoring of radioactivity in the food chain.

  8. Palisades Nuclear Plant. Radioactive effluents and environmental monitoring sections to second annual operating report

    International Nuclear Information System (INIS)

    1977-01-01

    A total of 0.435 Ci of radioactive liquid effluent less tritium was released with 19.63 Ci of tritium. Both liquid and gaseous releases were within permissible limits. There were 8 Ci of solid wastes stored on the site as of 12/31/76. Data clearly shows there was no detectable increase in radioactivity levels in the environmental media that can be attributed to plant effluents. Monitoring reports are presented concerning fish, meteorology, noise, and cooling tower drift

  9. Final annual report of the Partial monitoring system 'Radioactivity of the environment' 2015

    International Nuclear Information System (INIS)

    Melicherova, T.; Cabanekova, H.; Bodorova, J.

    2016-05-01

    The present report evaluates activities of radiation monitoring of Slovak Hydrometeorological Institute (SHMI) in 2015. Analytical part focuses on detailed statistical analysis of monitored data. Detailed knowledge of the course of time series during uneventful period enables early detect and analyze potential increase of radioactivity levels in the environment originating from domestic or foreign sources. SHMI is responsible for international data exchange with the European Commission and with partners in Austria and Hungary.

  10. Final annual report of the Partial monitoring system 'Radioactivity of the environment' 2016

    International Nuclear Information System (INIS)

    Melicherova, T.; Cabanekova, H.; Bodorova, J.

    2017-05-01

    The present report evaluates activities of radiation monitoring of Slovak Hydrometeorological Institute (SHMI) in 2016. Analytical part focuses on detailed statistical analysis of monitored data. Detailed knowledge of the course of time series during uneventful period enables early detect and analyze potential increase of radioactivity levels in the environment originating from domestic or foreign sources. SHMI is responsible for international data exchange with the European Commission and with partners in Austria and Hungary.

  11. Survey monitoring of environmental radioactivity in Gwangju area

    Energy Technology Data Exchange (ETDEWEB)

    Woo, Jeong Ju; Na, Jeong Yeun [Chonnam National Univ., Gwangju (Korea, Republic of)

    2001-12-15

    The objectives of this project are to detect radiation abnormalities In its early stage, to survey the regional environmental radiation/radioactivity levels and me variations of the levels, to prepare the capability of managing the radiological emergencies, and finally to extabish the protective and defence systems against the radiological hazards for the general publics. This report presents the levels of the external gamma dose rates, the gross {beta} - activities in the natural samples, such as airborne dust, fallout, precipitation, and tap water, which were continuously monitored at the environmental research institute at CNU during 2001, and also the levels of the {gamma} - activities in food samples and drinking water which were measured to collect the basic data of the regional environmental radioactivity levels around the Kwangju city and Chonnam province. The levels of the {gamma} - and gross {beta} - activities in the natural samples didn't any significant abnormality during 2001 and were similar to the results obtained in the past 5 years. The {gamma} - activities in almost all food samples, except for a few samples, and drinking water samples were measured to be below the MDA values.

  12. Survey monitoring of environmental radioactivity in Gwangju area

    Energy Technology Data Exchange (ETDEWEB)

    Woo, Jeong Ju; Na, Jeong Yeun [Chonnam National Univ., Gwangju (Korea, Republic of)

    2003-12-15

    The objectives of this project are to detect radiation abnormalities in its early stage, to survey the regional environmental radiation/radioactivity levels and the variations of the levels, to prepare the capability of managing the radiological emergencies, and finally to extabish the protective and defence systems against the radiological hazards for the general publics. This report presents the levels of the external gamma dose rates, the gross {beta} - activities in the natural samples, such as airborne dust, fallout, precipitation, and tap water, which were continuously monitored at the environmental research institute at CNU during 2003, and also the levels of the {gamma} - activities in food samples and drinking water which were measured to collect the basic data of the regional environmental radioactivity levels around the Gwangju city and Chonnam province. The levels of the {gamma} - and gross {beta} - activities in the natural samples didn't any significant abnormality during 2003 and were similar to the results obtained in the past 5 years. The {gamma} - activities in almost all food samples, except for a few samples, and drinking water samples were measured to be below the MDA values.

  13. Survey monitoring of environmental radioactivity in Gwangju area

    International Nuclear Information System (INIS)

    Woo, Jeong Ju; Na, Jeong Yeun

    2001-12-01

    The objectives of this project are to detect radiation abnormalities In its early stage, to survey the regional environmental radiation/radioactivity levels and me variations of the levels, to prepare the capability of managing the radiological emergencies, and finally to extabish the protective and defence systems against the radiological hazards for the general publics. This report presents the levels of the external gamma dose rates, the gross β - activities in the natural samples, such as airborne dust, fallout, precipitation, and tap water, which were continuously monitored at the environmental research institute at CNU during 2001, and also the levels of the γ - activities in food samples and drinking water which were measured to collect the basic data of the regional environmental radioactivity levels around the Kwangju city and Chonnam province. The levels of the γ - and gross β - activities in the natural samples didn't any significant abnormality during 2001 and were similar to the results obtained in the past 5 years. The γ - activities in almost all food samples, except for a few samples, and drinking water samples were measured to be below the MDA values

  14. Facility effluent monitoring plan for the 300 Area Fuels Fabrication Facility

    International Nuclear Information System (INIS)

    Nickels, J.M.; Brendel, D.F.

    1991-11-01

    A facility effluent monitoring plan is required by the US Department of Energy in DOE Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. This document is prepared using the specific guidelines identified in A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP- 0438. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements. This facility effluent monitoring plan is the first annual report. It shall ensure long-range integrity of the effluent monitoring system by requiring an update whenever a new process or operation introduces new hazardous materials or significant radioactive materials. This document must be reviewed annually even if there are no operational changes, and it must be updated as a minimum every three years. The Fuel Fabrication Facility in the Hanford 300 Area supported the production reactors from the 1940's until they were shut down in 1987. Prior to 1987 the Fuel Fabrication Facility released both airborne and liquid radioactive effluents. In January 1987 the emission of airborne radioactive effluents ceased with the shutdown of the fuels facility. The release of liquid radioactive effluents have continued although decreasing significantly from 1987 to 1990

  15. Functions of PTB in monitoring of environmental radioactivity; Die Aufgaben der PTB bei der Ueberwachung der Umweltradioaktivitaet

    Energy Technology Data Exchange (ETDEWEB)

    Wershofen, H. [Physikalisch-Technische Bundesanstalt, Berlin (Germany). Arbeitsgruppe Umweltradioaktivitaet; Arnold, D. [Physikalisch-Technische Bundesanstalt, Berlin (Germany). FB Radioaktivitaet

    2006-12-15

    After the Chernobyl accident, the IMIS measuring system for monitoring of environmental radioactivity and of emissions from nuclear power stations was founded in Germany, with the intention of preventing nuclear accidents or disasters and for early measuring and evaluation of their radiological effects. It works on behalf of the BMU (Federal Minister of the Environment, Conservation and Reactor Safety), on the basis of the 1986 StrVG (Act for preventive radiation protection). IMIS is an extensive national measuring system for monitoring or radioactivity throughout Germany and in all relevant environmental media. (orig.)

  16. Active waste disposal monitoring at the Radioactive Waste Management Complex, Idaho National Engineering Laboratory

    International Nuclear Information System (INIS)

    Hubbell, J.M.

    1990-10-01

    This report describes an active waste disposal monitoring system proposed to be installed beneath the low-level radioactive disposal site at the Radioactive Waste Management Complex (RWMC), Idaho National Engineering Laboratory, Idaho. The monitoring instruments will be installed while the waste is being disposed. Instruments will be located adjacent to and immediately beneath the disposal area within the unsaturated zone to provide early warning of contaminant movement before contaminants reach the Snake River Plain Aquifer. This study determined the optimum sampling techniques using existing monitoring equipment. Monitoring devices were chosen that provide long-term data for moisture content, movement of gamma-emitting nuclides, and gas concentrations in the waste. The devices will allow leachate collection, pore-water collection, collection of gasses, and access for drilling through and beneath the waste at a later time. The optimum monitoring design includes gas sampling devices above, within, and below the waste. Samples will be collected for methane, tritium, carbon dioxide, oxygen, and volatile organic compounds. Access tubes will be utilized to define the redistribution of radionuclides within, above, and below the waste over time and to define moisture content changes within the waste using spectral and neutron logging, respectively. Tracers will be placed within the cover material and within waste containers to estimate transport times by conservative chemical tracers. Monitoring the vadose zone below, within, and adjacent to waste while it is being buried is a viable monitoring option. 12 refs., 16 figs., 1 tab

  17. Processing methods for operation test data of radioactive aerosols monitor based on accumulation techniques

    International Nuclear Information System (INIS)

    Fu Cuiming; Xi Pingping; Ma Yinghao; Tan Linglong; Shen Fu

    2011-01-01

    This article introduces a radioactive aerosol continuous monitor based on accumulation sampling and measuring and three methods for processing the operation data. The monitoring results are processed by the 3 methods which are applied both under the conditions of natural background and at workplaces of a nuclear facility. How the monitoring results are assessed and how to calculate the detection limit when using the 3 different methods are explained. Moreover, the advantages and disadvantages of the 3 methods are discussed. (authors)

  18. Progress in the domain of emissions tracking and environment radioactivity monitoring - Proceedings of the technical days organised by the SFRP Environment Section

    International Nuclear Information System (INIS)

    Calmet, Dominique; Calvez, Marianne; Rivasseau, Corinne Cea; Monfort, Marguerite; Manificat, Guillaume; Pierrard, Olivier; Couvez, Celine; Masson, Olivier; Bruno, Valerie; Renaud, Philippe; Genova, Zhana; Reynal, Nathalie; Le Coz, Eric; Tchilian, Nathalie; Diana, Jean-Jacques; Beguinel, Philippe; Cortes, Pierre; Puydarrieux, Stephane; Brun, Thierry; Devin, Patrick; Clavel, Benoit; Hemidy, Pierre-Yves; Gontier, Gilles; Delloye, Thierry; Mailliat, Alain; Ferreri, Giovanni; LECLERC, Elisabeth

    2015-11-01

    The Environment Section of the French Society of Radiation Protection (SFRP) organized a technical meeting on the progress made in the domain of emissions tracking and environment radioactivity monitoring. This document brings together the abstracts and the presentations (slides) of the different talks given at the meeting: 1 - Environment monitoring at the global, national and local scale: historical overview (Dominique CALMET, CEA); 2 - Evolution of radioactivity monitoring in the environment from 1960 to the present day (Guillaume MANIFICAT, IRSN); 3 - Euratom's legal framework (Zhana GENOVA, CTE); 4 - Main regulatory changes during the last decade (Nathalie REYNAL, ASN); 5 - Progress of standardization works on radioactive effluent emissions control and environment monitoring (Philippe BEGUINEL, BNEN); 6 - From operators' self-monitoring to ASN's inspections: a many components control system (Eric LE COZ, ASN); 7 - Control of effluents and emissions management at CEA Centres (Marianne CALVEZ, CEA); 8 - Liquid and gaseous effluents of ITER experimental facility: description and impacts (Pierre CORTES, IO); 9 - Effluents and emissions management strategy at AREVA NC La Hague facility (Stephane PUYDARRIEUX, AREVA); 10 - Radioactive effluents from nuclear facilities ongoing deconstruction: from dimensioning to real effluents (Benoit CLAVEL, EDF); 11 - Radionuclides decontamination process for liquid effluents using micro-algae at the laboratory scale (Corinne RIVASSEAU, CEA); 12 - Radioactive effluents from nuclear medicine services: management, monitoring and impact measurement methods (Nathalie TCHILIAN, ASN); 13 - Evolution history of effluents management and environment monitoring at the Solvay La Rochelle site (Thierry DELLOYE, SOLVAY); 14 - Different international approaches in effluents management and monitoring: example of French and German gaseous effluents - regulation, analyses, accounting rules (Jean-Jacques DIANA, ASN); 15 - Environment

  19. Monitoring radioactivity in food and actions of the Ministry in charge of food

    International Nuclear Information System (INIS)

    Grastilleur, Ch.

    2010-01-01

    French ministry of food, agriculture and fisheries (general directorate for food) is involved in all aspects of food safety and food controls As such, MAAP guarantees both the quality and safety of food products radioactivity controls in food participate to this global aim. Since 1987 and following the accident on Tchernobyl nuclear plant, regulations and monitoring-control programmes have been implemented by MAPP, mainly based on Cs 134 and 137 and Sr 90 researches in raw products such as game, milk and dairy products and honey A new monitoring and control programme has been implemented as from 2009, with the help of IRSN and thanks to the work on management during post-accidental phases initiated in 2005 by ASN. Mainly the activity of Cs is determined but also other parameters are measured such as Ca, K and l 131 activities in the samples analysed by IRSN. In 2009, 812 samples were programmed and all of them have proven to be conform. During the year 2010, 725 samples will be collected, Global exposure to radioactivity in France is estimated at 4000 μSv per year, food and water contributing to 6% (that is about 250 μSv) mainly due to K and Ca (natural radioactive components of the regime). (author)

  20. On-line monitoring of water amount in fresh concrete by radioactive-wave method

    International Nuclear Information System (INIS)

    Kemi, T.; Arai, M.; Enomoto, S.; Suzki, K.; Kumahara, Y.

    2003-01-01

    The committee on nondestructive inspection for steel reinforced concrete structures in the Federation of Construction Materials Industries, Japan has published a proposed standard for on-line monitoring of water amount in fresh concrete by the radioactive wave method. By applying a neutron technique, water amount in fresh concrete is estimated continuously from the energy consumption of neutron due to hydrogen. A standard is discussed along with results of verification tests. Thus, on-line monitoring for water amount is proposed

  1. Situation of radioactivity monitoring in French Polynesia in 2015. Synthesis of results from the IRSN's monitoring network. 2016 mission report

    International Nuclear Information System (INIS)

    2016-12-01

    The radiological monitoring of the environment conducted in Polynesia by the Laboratory for the Study and Monitoring of the Environment (LESE lab), consists in regularly collecting and measuring radioactivity in samples from different environmental natures such as air, water, soil but also foodstuff etc, with which the inhabitants may come in contact. This regular monitoring has been carried out since 1962 on seven islands namely Tahiti, Maupiti, Hao, Rangiroa, Iva Oa, Mangareva and Tubuai representative for the five archipelagos. In 2015, the scope of this monitoring was enlarged by including specific a radiological study, consisting in analyzing local foodstuff in the Raivavae atoll, so as to assess the additional man-made radioactivity through the food chain, and soil samples so as to review the residual amount of "1"3"7Cs and Pu isotopes. A few additional measurements, complementary to the ones already made in 2012, were carried out to develop a map of external exposure all over this Austral atoll. For the second year in a row, the LESE lab took part in the Turbo program leaded by DGA and CEA, organizations in charge of radiological monitoring of the military atolls, by analyzing three ocean samples collected on an atoll shore and offshore from the island Moruroa. Almost all samples were processed and evaluated by the LESE laboratory, located on the Tahiti main land, in Vairao; some of the samples were analyzed in one of IRSN's other laboratories based in a suburb from Paris called Orsay in France. A steady decrease in radioactivity level has been observed since the end of the French atmospheric nuclear tests in 1974; the latest observations (2015) show a stable radiological situation, identical throughout the previous years of observation, and measured at a very low level. This residual radioactivity level comes, for the main part, from the "1"3"7Cs. The efficient annual dose, i.e. the additional man-made radioactivity, is below 5 μSv.y"-"1 (5 micro

  2. Monitoring artificial radioactivity in the Nordic countries. BER-2 final report

    International Nuclear Information System (INIS)

    Bennerstedt, T.; Rantanen, H.; Mortensen, B.N.

    1994-05-01

    This final report of the Nordic Nuclear Safety Research Project BER-2 gives detailed information on the monitoring of artificial radioactivity in the Nordic countries (Denmark, Finland, Iceland, Norway and Sweden). A comparison shows that for early warning the Nordic countries use a mix of stations measuring external gamma radiation and stations measuring airborne radioactivity. There is a trade-off between fast alarms and the sensitivity threshold. Total gamma measuring stations cannot detect increases smaller than the variations of normal background. Some stations, notably all Danish stations, are equipped with sodium iodide (NaI) type detectors, and operated in such a way that stray peaks due to an increase in the natural radon background can be subtracted. A Nordic Radiation Data Exchange System has been set up and tested on a trial basis. This system focuses on dose rate data from the automatic gamma monitoring stations. An important goal achieved in the project was to determine which data is essential, and to specify a common format for the data exchange. Various telecommunication methods have been tested, and the actual transfer of monitoring results between the Nordic countries was started. It is recommended as a future approach that every country appoint one organization with the responsibility of operating a national information data base, which can be commonly accessed from all the Nordic countries. A procedure for establishing a system of this type has been outlined

  3. The regulatory system of monitoring workers in Germany for intakes of radioactivity

    International Nuclear Information System (INIS)

    Dalheimer, A.; Henrichs, K.

    1996-01-01

    In Germany, the working group 'Incorporation Monitoring' of the German-Swiss Radiation Protection Association defined a new standard for the monitoring of workers occupationally exposed to radioactive material. During the last two years this draft has been accepted by the German government in the form of three guidelines. The purpose of the approach was the installation of a consistent state-of-the-art system: defining clear criteria for the necessity of routine and special monitoring programs, giving guidelines for monitoring programs ensuring that dose assessments are as reliable as necessary with the lowest possible expenses, standardizing as far as possible the procedures of dose assessments, and guaranteeing the necessary quality standards. The scientific basis of this regulatory system are the publications 30 and 54 of lCRP. (author)

  4. Radioactive waste discharges from UKAEA establishments during 1996 and associated monitoring results

    International Nuclear Information System (INIS)

    Morton, A.K.M.; Forbes, S.A.; Hughes, B.; Richardson, E.

    1997-08-01

    This annual report is published by the Safety Directorate of the United Kingdom Atomic Energy Authority (UKAEA) and provides information on radioactive discharges from its sites. The Culcheth site was closed and then redeveloped during the end of 1993 and the Springfields site became part of BNFL in October 1994. No operations involving the need to discharge radioactivity are undertaken at the Risley site. After discussions with the Authorising Departments at that time, the discharge authorisations were revoked on 1 July 1994. These sites are therefore no longer included in this report. UKAEA has published annual radioactive waste discharges and associated monitoring results since 1963. This report is intended to give a relatively short factual overview of UKAEA waste discharge and disposal, and its impact on the environment. Additional information may be found in annual discharge reports published by the individual UKAEA establishments and the UKAEA Report on Safety and the Environment 1996-97 due to be issued at the end of September 1997. (UK)

  5. Radioactivity in the vicinity of Sizewell nuclear power station: marine environmental monitoring, 1983

    International Nuclear Information System (INIS)

    Hunt, G.J.

    1984-01-01

    Regular monitoring of radioactivity in the aquatic environment of the British Isles has continued. A report presents the results of this program in relation to the Sizewell nuclear power station for 1983, so as to supplement the most recently available full report which is for 1982. (author)

  6. 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

  7. Monitoring system for detection of radioactive materials in trucks at Commissariat a l'Energie Atomique (CEA-France)

    International Nuclear Information System (INIS)

    Levelut, M.N.

    1998-01-01

    Radiation Monitoring to control the radioactivity in vehicles and trucks are in use inside the sites of Commissariat a l'Energie Atomique. The first function of these monitoring systems in the detection of radioactive source or contaminated materials inside all loads of vehicles, before going out the nuclear site for the discharge of their materials either in a proper waste disposal or in an industrial site for material recycling. Other radioactive controls are conducted for nuclear materials and radioactive wastes. The radiation monitoring system use 4 to 6 plastic scintillators mounted vertically on each side of the roadway near the truck and horizontally, above or below the vehicle. The functional components also include a microprocessor for processing the signals and algorithms for interpreting the data transmitted to the control unit. This system functions in a dynamic mode; radiation is detected while the truck is in motion taking a series of incremental observations based on a differential count rate with the respect to the background. Vehicle scan information is printed out on a ticket specifying the result of the control. In case of unexpected radiation, an alarm is emitted. The vehicle is submitted to further investigations to find the source with a hand held instrument, analyse the radionuclides by spectrometry and find its origin in order to manage the corrective actions. The paper describes the system named > (Controle de la Radioactivite des Chargements de Vehicules), its sensitivity and the results of routine monitoring for several years. Few examples of radiation alarm are developed. (author)

  8. Approval of radioactive consumer goods

    International Nuclear Information System (INIS)

    Paynter, R.A.

    1992-01-01

    The 1980 Euratom Directive obliges the UK to draw up a system of prior authorization for the use of radioactive substances in a range of consumer products, and the Government intends to make regulations to fulfil the requirements of the Directive. These regulations will empower NRPB to approve such products prior to their supply to the public. In this brief article, the NRPB reviews the criteria against which to consider any proposed use of radioactive substances, considers radiological production standards for products and discusses the questions of the labelling of radioactive consumer goods. (UK)

  9. Environmental radioactivity 1996

    International Nuclear Information System (INIS)

    1997-01-01

    Environmental Radioactivity in New Zealand and Rarotonga : annual report 1996 was published in May this year. The 1996 environmental radioactivity monitoring programme included, as usual, measurements in New Zealand and the Cook Islands of atmospheric, deposited and dairy product radioactivity. The environment in the New Zealand and Cook Island regions has now virtually returned to the situation in the 'pre-nuclear' era. The contination of monitoring, although at a reduced level of intensity, is basically to ensure that any change from the present state, due to any source of radioactivity does not go undetected or unquestioned. (author)

  10. Improving evaluation criteria for monitoring networks of weak radioactive plumes after nuclear emergencies

    DEFF Research Database (Denmark)

    Urso, L.; Astrup, Poul; Helle, K.B.

    2012-01-01

    Networks of monitoring stations have been set up in many European countries to detect the passage of a radioactive cloud in the event of a large-scale nuclear emergency. The layout and spatial density of these networks differs according to the needs and criteria defined by national authorities...

  11. Survey monitoring of environmental radioactivity in Gwangju area

    Energy Technology Data Exchange (ETDEWEB)

    Woo, Jeong Ju; Na, Jeong Yeun [Chonnam National Univ., Gwangju (Korea, Republic of)

    2000-12-15

    The objectives of this project are to detect radiation abnormalities in its early stage, to survey the regional environmental radiation/radioactivity levels and the variations of the levels, to prepare the capability of managing the radiological emergencies, and finally to extabish the protective and defence systems against the radiological hazards for the general publics. This report presents the levels of the external gamma dose rates, the gross {beta} - activities in the natural samples, such as airborne dust, fallout, precipitation, and tap water, which were continuously monitored at the environmental research institute at CNU in 2000, and also the levels of the {gamma} - activities in food samples and drinking water which were measured to collect the basic data of the regional environmental radioactivity levels around the Kwangju city and Chonnam province. The levels of the {gamma} - and gross {beta} - activities in the natural samples didn't any significant abnormality in 2000 and were similar to the results obtained in the past years. Also levels of the {gamma} - activities of Cs-137 in those samples were below the MDA values. The {gamma} - activities in almost all food samples, except for a few food samples, and drinking water samples were measured to be below the MDA values.

  12. Treating radioactive effluent

    International Nuclear Information System (INIS)

    Kirkham, I.A.

    1981-01-01

    In the treatment of radioactive effluent it is known to produce a floc being a suspension of precipitates carrying radioactive species in a mother liquor containing dissolved non-radioactive salts. It is also known and accepted practice to encapsulate the floc in a solid matrix by treatment with bitumen, cement and the like. In the present invention the floc is washed with water prior to encapsulation in the solid matrix whereby to displace the mother liquor containing the dissolved non-radioactive salts. This serves to reduce the final amount of solidified radioactive waste with consequent advantages in the storage and disposal thereof. (author)

  13. Environmental radioactive monitoring in Itu, Sao Paulo, Brazil; Monitoramento de radioatividade ambiental no municipio de Itu

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1990-01-01

    The results of the environmental monitoring of a region near to a radioactive materials deposit in Sao Paulo State, Brazil, are presented. The radioactive materials are uranium and thorium hydroxides from monazite processing. The temporal variation of {sup 226} Ra was determined in the superficial and underground water, showing no increase for the former and a maximum concentration of 0,306 Bq/L for the latter. 21 figs., 17 tabs.

  14. Annual report on radioactive discharges and monitoring of the environment 1984

    International Nuclear Information System (INIS)

    1985-01-01

    Information is given on the liquid, airborne, and solid radioactive discharges through authorised outlets, and on environmental monitoring for all of BNFL's works and sites for 1984; ie Sellafield site and Drigg storage and disposal site; Chapelcross works; Springfields works and Ulnes Walton disposal site; Capenhurst works. Included is assessment of radiation doses to representative members of the most highly exposed group of the general population for the most important environmental pathways. (author)

  15. The monitoring of radioactive substances in biological food chains by the veterinary service in Czechoslovakia

    Energy Technology Data Exchange (ETDEWEB)

    Pawel, O [Central State Veterinary Institute, Prague, Czechoslovakia (Czech Republic)

    1986-07-01

    Czechoslovakia has established an environmental monitoring system to protect the hygienic conditions of the environment from the radiation hazard. The control authorities of the Ministry of Agriculture and Food take part in this system in order to collect information on the contamination with radioactive substances of soil, plants, game, food animals, foodstuffs and raw materials, i.e. information on all links of the food chain which extends from animals to man. A radioactive substances detection programme has been launched by the appropriate authorities in agriculture, animal husbandry and veterinary service. The programme includes a two-stage laboratory analysis of radioactive substances. The majority of laboratories covering the programme are already in operation.

  16. The monitoring of radioactive substances in biological food chains by the veterinary service in Czechoslovakia

    International Nuclear Information System (INIS)

    Pawel, O.

    1986-01-01

    Czechoslovakia has established an environmental monitoring system to protect the hygienic conditions of the environment from the radiation hazard. The control authorities of the Ministry of Agriculture and Food take part in this system in order to collect information on the contamination with radioactive substances of soil, plants, game, food animals, foodstuffs and raw materials, i.e. information on all links of the food chain which extends from animals to man. A radioactive substances detection programme has been launched by the appropriate authorities in agriculture, animal husbandry and veterinary service. The programme includes a two-stage laboratory analysis of radioactive substances. The majority of laboratories covering the programme are already in operation

  17. Perspectives on radioactive waste repository monitoring. Confirmation, compliance, confidence building, and societal vigilance

    Energy Technology Data Exchange (ETDEWEB)

    Bergmans, Anne [Antwerp Univ. (Belgium). Research Group Society and Environment; Elam, Mark [Gothenburg Univ. (Sweden); Simmons, Peter [East Anglia Univ., Norwich (United Kingdom); Sundqvist, Goeran [Oslo Univ. (Norway)

    2012-12-15

    Monitoring is now widely seen as a necessary part of programmes for the geological disposal of radioactive waste. However, we find different perspectives on the nature and role of monitoring. Among technical experts it is viewed firstly as a matter of performance confirmation, a tool for validating the safety case underlying repository construction. Among concerned citizens we find a view of monitoring as enabling the critical scrutiny of safety, an instrument for acknowledging uncertainties and detecting emergent problems in a repository. After outlining differing views on questions of whether, why, what, where and for how long to monitor we discuss monitoring in light of constant vigilance as a technical and moral principle of nuclear safety. We suggest that ''how much monitoring'' and ''how should it be organised'' are societal questions and as such need to be broadly discussed.

  18. Radioactivity monitoring in French Polynesia and other countries and territories year 1998

    International Nuclear Information System (INIS)

    1999-07-01

    This report presents the results of measures made in 1998 to provide the radioactivity monitoring in environment and food chains in french Polynesia. It does not concern the Fangataufa and Mururoa sites. The only radionuclides detected in the air, land and sea sampling of the French Polynesia are long life elements (Sr 90 included). The results of measurements are often under the detection limit, and when they are significant they stay very low. The efficient year dose coming from radioactivity for the Tahiti island is inferior or equal to 4 micro sievert for 1998. The annual radiation doses estimated in relation with exposure to artificial radionuclides are for the adults between 2 and 6 micro sievert and for children between 2 and five micro sievert. (N.C.)

  19. Radioactivity monitoring in French Polynesia and others countries and territories year 1999

    International Nuclear Information System (INIS)

    2000-08-01

    This report presents the results of measures made in 1999 to provide the radioactivity monitoring in environment and food chains in french Polynesia. It does not concern the Fangataufa and Mururoa sites. The only radionuclides detected in the air, land and sea sampling of the French Polynesia are long life elements (Sr 90 included). The results of measurements are often under the detection limit, and when they are significant they stay very low. The efficient year dose coming from radioactivity for the Tahiti island is inferior or equal to 4 micro sievert for 1999. The annual radiation doses estimated in relation with exposure to artificial radionuclides are for the adults between 2 and 6 micro sievert and for children between 2 and five micro sievert. (N.C.)

  20. Radioactive effluent monitoring at the Idaho National Engineering Laboratory

    International Nuclear Information System (INIS)

    Simpson, O.D.

    1975-01-01

    The Effluent and Radiation Measurements Laboratory at the Idaho National Engineering Laboratory (INEL) has recently upgraded capabilities in the field of monitoring and analysis of radioactive airborne and liquid effluents using the techniques of gamma-ray spectrometry. The techniques and equipment used include remotely-operated, computer-based Ge(Li) spectrometers which obtain data on a real-time basis. Permanent record files are maintained of both the effluent release values and the gamma-ray data from which the release values are calculated. Should values for release levels ever be challenged, the gamma-ray spectral information for any measurement can be recalled and analyzed as needed. Daily effluent release reports are provided to operating personnel which contributes to prompt correction of any operational problems. Monthly, quarterly, and annual reports are compiled which provide inventories of the radionuclides released. A description of the effluent monitoring, reporting and records system developed at INEL for this application will be presented

  1. Measurement of exposures to radioactivity and monitoring of effects on health

    International Nuclear Information System (INIS)

    Spira, Alfred; Boutou, Odile

    1999-01-01

    On the request of the French ministries of Health and of the Environment, the author reports thoughts and proposals regarding epidemiological problems related to natural and artificial radioactive emissions. He first reports an analysis of the present context (assessment of health risks, ionizing radiation in France, radiation protection, nuclear operators, relationship between ionizing radiation and health, epidemiology) and knowledge (about nuclear and health, available results, current investigations). He outlines the benefits of an epidemiological monitoring and its requirements, and identifies the various components of this monitoring. While presenting current works, biological and epidemiological studies performed in the northern Cotentin area, he makes some specific proposals for this area and notably for the workers of La Hague. He proposes the implementation of a national arrangement comprising a measurement of exposures, an epidemiological monitoring, and a sociological survey. He discusses the associated administrative organisation and needs

  2. A multifunction radioactive waste monitoring system

    International Nuclear Information System (INIS)

    Edeline, J.C.; Libs, G.

    1991-01-01

    The monitoring of unknown radioactive transuranic wastes mixed with fission products (FP) needs several measuring technics: passive and active neutron methods, gamma rays spectrometry and, sometimes, emission tomography to localize the hot points in the waste packages. The goal is to achieve a whole system from the most up-dated electronics sub-assemblies to provide these characterization measurement at the lowest cost and in the simplest manner. The control of the different measurements is made by only one micro-processor and an unusual way of using the gamma spectrometry A.D.C. and multichannel analyser makes possible to control the neutron analogic electronics: neutron counter high-voltage supplies, amplifiers and discriminators; many of the gamma spectrometry sub-assemblies are also used for the gamma emission tomography. The different measurements are automated and different programs offer the possibility to choice the proper measurement methods for each item. The waste package handling apparatus is not included in the system but the control of such handling might be performed by the micro-computer. We describe the main parts and features of the system [fr

  3. Low-level radioactive gas monitor for natural gas operations

    International Nuclear Information System (INIS)

    Armstrong, F.E.

    1969-11-01

    A portable radioactivity detection system for monitoring the tritium content of natural gas under field conditions has been developed. The sensing device employed is a complex proportional counting assembly operated without the use of massive shielding previously employed with such low-level radiation detectors. The practical limit of detection for the system is a tritium content of 10 -9 microcurie per cc of natural gas. All components of the system are packaged in three waterproof cases weighing slightly less than 30 kg each. Power requirement is 500 watts of 120 volt, 60 Hz current. Operation is fully automatic with a printed record produced at predetermined time intervals

  4. Monitoring of environmental radioactivity in the European Communities inventory of methods and development of data quality objectives

    International Nuclear Information System (INIS)

    Raes, F.

    1991-01-01

    A review is given of the procedures for environmental monitoring in the 12 Member States of the European Community. Detailed information of sampling and measuring methods for radioactivity in air, deposition, water, milk and for ambient gamma dose rate are presented in tables and figures. Some sample results of environmental radioactivity monitoring indicate problems with intercomparability of data reported by different EC countries. A review is given of international and national programmes and proposals for Quality Assurance and Control. There is a large but rather uncoordinated activity in this field; only a few countries within the EC have a well structured and comprehensive approach to QA and regularly join international programmes. Data Quality Objectives (DQOs) are developed for environmental radioactivity monitoring. They include the definition of the accuracy and repeatability of the measurements, and the definition of recording and detection levels. The recording levels, are based on a de minimis annual dose of 0.005 mSv. Based on these DQO's, the current problems with intercomparability are put into perspective, and proposals for future integration of national data into an overall European picture made. There is a need to improve quality of environmental monitoring in order to arrive at a meaningful and transparent picture of the overall radiological situation in the EC. Proposals are made for CEC initiatives in the field of QA/QC. The three most important deal with: - reporting of national data in a European context, - intercomparisons of analytical techniques among the 12 EC countries, - organization of a European network for monitoring levels actually prevailing in the environment

  5. The monitoring of radioactive contamination and radiation exposure in the environment in Germany- tasks, techniques, realizations

    International Nuclear Information System (INIS)

    Bayer, A.

    1998-01-01

    A brief historical account of the development of the monitoring of radioactivity in the environment in Germany is given. The aims of monitoring and the tasks, classified according to the possible sources of release, are presented and the methods required are described. The monitoring systems, set up on the basis of different legal principles, are presented and the technical realization of these including their current state of development, is described. Finally, an account is given of the coordination of the national monitoring systems which is at present in progress, as well as of the integration of these monitoring systems into international monitoring and information networks. (author)

  6. Monitoring System for the Inspection of Vehicle Loads for Radioactivity

    International Nuclear Information System (INIS)

    Krishnamarchri, G.; Chaudhury, P.; Jain, A.; Kale, M. S.; Pradeepkumar, K. S.; Sharma, D. N.; Venkat Raj, V.

    2004-01-01

    From the nuclear facilities, inactive scrap may have to be sent periodically for disposal. The scrap is to be monitored to ensure that it is free from inadvertent mix up of contaminated material, which has got the potential of unwanted exposure to people as well as costly and time consuming clean up operations. Earlier the scrap carrying vehicles were monitored manually using portable radiation survey monitors by health physicists. A PC based monitoring system for the inspection of vehicle loads for radioactivity is developed and is in use which requires minimum manual interaction. The advantage of the system is that it can automatically screen all outgoing vehicles from the establishment. The PC based system consists of two detector boxes, each having three Plastic Scintillation detectors of 50 mm dia x 500 mm long. The processing unit is built around a PC addon card. Using the calibration factor (i.e., nGy/h per cps), the dose rate is computed and 'allow' / 'disallow' visual signal is generated in the PC located in a control room. The graphical user interface provides ON / OFF button for controlling the counting process and counting time interval can be set by the user as desired. All the six counters are synchronized for the process of counting. The acquired counts are displayed on the PC screen in the form of a count rate vs. time graph. At the completion of scanning of a vehicle, the counting is continued to acquire background radiation level till the next vehicle arrives. The processing unit estimates the radiation dose rate from these recorded counts by using already established calibration factor and displays the data on the monitor screen of the computer. If the determined dose rate exceeds the pre determined limit, an audio alarm is initiated and the alarm information is displayed on the monitor of the computer. The system has provision to enter information like vehicle registration number, type of the vehicle, origin of the load, destination etc. These

  7. Environmental radioactivity survey in Suwon

    Energy Technology Data Exchange (ETDEWEB)

    Park, Won Keun; Park, Jong Mi [Kyunghee Univ., Suwon (Korea, Republic of)

    2003-12-15

    The project is carried out to monitor the change of environmental radioactivity in Suwon, 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 Suwon regional monitoring station m 2003. Also it contains the data of natural radioactivity levels of environmental samples such as soil, drinking water, indicator plant(mugwort, pine-needle), agricultural and forest products, and processed food(tea)

  8. Survey monitoring of environmental radioactivity in Seoul area

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Jai Ki; Chung, Ok Sun; Kim, Hong Suk [Seoul Monitoring Station, Seoul (Korea, Republic of)

    2002-12-15

    The following results were obtained through the environmental radiation monitoring in 2002 at the Seoul Monitoring Station: gamma exposure rate : 10.8 - 13.3 {mu}R/h, mean gross beta activity in airborne dust : 84.1 {+-} 46.2 mBq/m{sup 3}, mean gross beta activity in fallout dust : 11.9 {+-} 5.6 MBq/km{sup 2} - 30 days, meab gross beta activity in precipitation : 317 {+-} 465 mBq/L, mean gross beta activity in tap water : 71.2 {+-} 23.0 mBq/L. All the monitored variables remained in the corresponding normal ranges, which implies that there were no abnormal situations of environmental radiation in the Seoul-Gyunggi districts in 2002. Radioactivity contents in foodstuffs consumed in Seoul and Gyunggi districts were analyzed for use in assessment of population doses via dietary intakes. Samples include 16 foodstuffs (peanut, walnut, pine seeds, chessnut, acorn, sesame, perilla seeds, oak mushroom, meadow mushroom, velvet foot, oyster mushroom, instant coffee, green tea leaves, ginseng tea, rice and Chinese cabbage). Two indicator samples, pine needle and mug wort, were also included. Relatively higher concentrations of {sup 137}Cs, a man-made nuclide, were found in coffee and oak mushroom(0.554 and 0.480 Bq/kg, respectively). A few hundreds Bq/kg of {sup 40}K were found in most of the foodstuffs with higher concentrations in coffee and green tea leaves(786 and 574 Bq/kg, respectively)

  9. Final annual report of the Partial monitoring system 'Radioactivity of the environment' 2014

    International Nuclear Information System (INIS)

    Melicherova, T.; Cabanekova, H.; Bodorova, J.

    2015-01-01

    The present report evaluates activities of radiation monitoring of Slovak Hydrometeorological Institute (SHMI) in 2014. Analytical part focuses on detailed statistical analysis of monitored data. Detailed knowledge of the course of time series during uneventful period enables early detect and analyze potential increase of radioactivity levels in the environment originating from domestic or foreign sources. SHMI is responsible for international data exchange with the European Commission and with partners in Austria and Hungary.

  10. Research of reducing the shielding effect caused by vehicles passing the radioactivity monitor system

    International Nuclear Information System (INIS)

    Deng Xianqi; Li Jianmin; Wang Xiaobing

    2008-01-01

    A kind of Radioactivity Monitor System with Vehicle Contour Acquisition Module based on Optical Screen is developed. The system can reduce the shielding effect caused by the passing vehicles, so that the alarming sensitivity is improved. This paper introduces the work situation of the system and preliminary experimental results. (authors)

  11. Monitoring Programme of Radionuclide Migration Through Food Chains at Low and Intermediate Level Radioactive Waste Repository in Trgoska Gora Mountain

    International Nuclear Information System (INIS)

    Schaller, A.; Lokner, V.; Kucar Dragicevic, S.; Subasic, D.; Barisic, D.

    2001-01-01

    Full text: Basic objective of the paper is to prepare a comprehensive programme of monitoring at the preferred site for low and intermediate level radioactive waste repository in the region of Trgovska Gora mountain. The programme is based on available information regarding hydrogeology, lithostratigraphy, tectonics, seismotectonics, geomorphology, meteorology, bioecology, demography and other site relevant disciplines. It is supposed to ensure (1) identification of the zero state at the broader region of the Trgovska gora mountain, and (2) to underline activities needed for monitoring of concentrations of expected radionuclides throughout possible pathways (particularly through food chains) that would migrate to the biosphere in the period after start of radioactive waste repository operation. Inventory of radionuclides contained in the radioactive waste to be disposed of at the site is naturally an important element of the programme structure. There should be identified those radionuclides which concentrations require to be monitored. Concentration measuring methods are proposed in the article. In addition, relevant aquatic and terrestrial organisms, serving as bioindicators, are identified. Types, quantities, frequency and methodology of sampling present an important part of the monitoring programme. Determination of monitoring sites for undertaking particular types of sampling (e.g. stream waters, stream sediment, detritus, ichtiofauna, groundwater, terrestrial organisms, honey, etc.), presenting an important aspect of a well-organised monitoring programme, is also included into this presentation. (author)

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

    International Nuclear Information System (INIS)

    1990-05-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    1990-05-01

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

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

    International Nuclear Information System (INIS)

    Egorov, Yu.A.

    1987-01-01

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

  15. Tracking and Monitoring of Radioactive Materials in the Commercial Hazardous Materials Supply Chain

    International Nuclear Information System (INIS)

    Walker, Randy M.; Kopsick, Deborah A; Warren, Tracy A; Abercrombie, Robert K.; Sheldon, Frederick T; Hill, David E.; Gross, Ian G; Smith, Cyrus M.

    2007-01-01

    One of the main components of the Environmental Protection Agency's (EPA) Clean Materials Program is to prevent the loss of radioactive materials through the use of tracking technologies. If a source is inadvertently lost or purposely abandoned or stolen, it is critical that the source be recovered before harm to the public or the environment occurs. Radio frequency identification (RFID) tagging on radioactive sources is a technology that can be operated in the active or passive mode, has a variety of frequencies available allowing for flexibility in use, is able to transmit detailed data and is discreet. The purpose of the joint DOE and EPA Radiological Source Tracking and Monitoring (RadSTraM) project is to evaluate the viability, effectiveness and scalability of RFID technology under a variety of transportation scenarios. The goal of the Phase II was to continue testing integrated RFID tag systems from various vendors for feasibility in tracking radioactive sealed sources which included the following performance objectives: 1. Validate the performance of RFID intelligent systems to monitor express air shipments of medical radioisotopes in the nationwide supply chain, 2. Quantify the reliability of these tracking systems with regards to probability of tag detection and operational reliability, 3. Determine if the implementation of these systems improves manpower effectiveness, and 4. Demonstrate that RFID tracking and monitoring of radioactive materials is ready for large scale deployment at the National level. For purposes of analysis, the test scenario employed in this study utilized the real world commerce supply chain process for radioactive medical isotopes to validate the performance of intelligent RFID tags. Three different RFID systems were assessed from a shipping and packaging perspective, included varied environmental conditions, varied commodities on board vehicles, temporary staging in shipping terminals using various commodities and normal

  16. Method of monitoring volume activity of natural radioactive aerosol

    International Nuclear Information System (INIS)

    Dvorak, V.

    1980-01-01

    The method of monitoring radioactivity of a aerosol trapped, eg., with a filter is based on counting quasi-coincidences of the RaC-RaC' and ThC-ThC' decay. The first electronic unit counts quasi-coincidences at a time interval proportional to the ThC' half-life while the second electronic unit counts quasi-coincidences at a time interval proportional to the RaC' half-life, reduced by the time interval of the first electronic unit. The quasi-coincidences are evaluated of the RaC-RaC' decay independently of the ThC-ThC' quasi-coincidences and the decay products of the trapped radon and thoron gases are thus offset separately. (J.P.)

  17. Spectrum correction algorithm for detectors in airborne radioactivity monitoring equipment NH-UAV based on a ratio processing method

    International Nuclear Information System (INIS)

    Cao, Ye; Tang, Xiao-Bin; Wang, Peng; Meng, Jia; Huang, Xi; Wen, Liang-Sheng; Chen, Da

    2015-01-01

    The unmanned aerial vehicle (UAV) radiation monitoring method plays an important role in nuclear accidents emergency. In this research, a spectrum correction algorithm about the UAV airborne radioactivity monitoring equipment NH-UAV was studied to measure the radioactive nuclides within a small area in real time and in a fixed place. The simulation spectra of the high-purity germanium (HPGe) detector and the lanthanum bromide (LaBr 3 ) detector in the equipment were obtained using the Monte Carlo technique. Spectrum correction coefficients were calculated after performing ratio processing techniques about the net peak areas between the double detectors on the detection spectrum of the LaBr 3 detector according to the accuracy of the detection spectrum of the HPGe detector. The relationship between the spectrum correction coefficient and the size of the source term was also investigated. A good linear relation exists between the spectrum correction coefficient and the corresponding energy (R 2 =0.9765). The maximum relative deviation from the real condition reduced from 1.65 to 0.035. The spectrum correction method was verified as feasible. - Highlights: • An airborne radioactivity monitoring equipment NH-UAV was developed to measure radionuclide after a nuclear accident. • A spectrum correction algorithm was proposed to obtain precise information on the detected radioactivity within a small area. • The spectrum correction method was verified as feasible. • The corresponding spectrum correction coefficients increase first and then stay constant

  18. Spectrum correction algorithm for detectors in airborne radioactivity monitoring equipment NH-UAV based on a ratio processing method

    Energy Technology Data Exchange (ETDEWEB)

    Cao, Ye [Department of Nuclear Science and Engineering, Nanjing University of Aeronautics and Astronautics, Nanjing 210016 (China); Tang, Xiao-Bin, E-mail: tangxiaobin@nuaa.edu.cn [Department of Nuclear Science and Engineering, Nanjing University of Aeronautics and Astronautics, Nanjing 210016 (China); Jiangsu Key Laboratory of Nuclear Energy Equipment Materials Engineering, Nanjing University of Aeronautics and Astronautics, Nanjing 210016 (China); Wang, Peng; Meng, Jia; Huang, Xi; Wen, Liang-Sheng [Department of Nuclear Science and Engineering, Nanjing University of Aeronautics and Astronautics, Nanjing 210016 (China); Chen, Da [Department of Nuclear Science and Engineering, Nanjing University of Aeronautics and Astronautics, Nanjing 210016 (China); Jiangsu Key Laboratory of Nuclear Energy Equipment Materials Engineering, Nanjing University of Aeronautics and Astronautics, Nanjing 210016 (China)

    2015-10-11

    The unmanned aerial vehicle (UAV) radiation monitoring method plays an important role in nuclear accidents emergency. In this research, a spectrum correction algorithm about the UAV airborne radioactivity monitoring equipment NH-UAV was studied to measure the radioactive nuclides within a small area in real time and in a fixed place. The simulation spectra of the high-purity germanium (HPGe) detector and the lanthanum bromide (LaBr{sub 3}) detector in the equipment were obtained using the Monte Carlo technique. Spectrum correction coefficients were calculated after performing ratio processing techniques about the net peak areas between the double detectors on the detection spectrum of the LaBr{sub 3} detector according to the accuracy of the detection spectrum of the HPGe detector. The relationship between the spectrum correction coefficient and the size of the source term was also investigated. A good linear relation exists between the spectrum correction coefficient and the corresponding energy (R{sup 2}=0.9765). The maximum relative deviation from the real condition reduced from 1.65 to 0.035. The spectrum correction method was verified as feasible. - Highlights: • An airborne radioactivity monitoring equipment NH-UAV was developed to measure radionuclide after a nuclear accident. • A spectrum correction algorithm was proposed to obtain precise information on the detected radioactivity within a small area. • The spectrum correction method was verified as feasible. • The corresponding spectrum correction coefficients increase first and then stay constant.

  19. Monitoring of persons with injuries with incorporated radioactive material

    International Nuclear Information System (INIS)

    Lopes, A.G.; Tauhata, L.

    2017-01-01

    The monitoring of victims with injuries with incorporated radioactive material can be performed with portable detectors in initial evaluations, with unshielded measurements, collimation, often with the ignorance of the radionuclide, and also, in the posterior medical follow-up with whole-body detectors and HPGe, in measurements of body or urine activity in periodic measurements. Dosimetry in these situations is done using appropriate models, which surpass those of orthodox internal dosimetry, the biokinetic model described in the 2006 NCRP, such as the AIDE models, and the one developed by Deepesh for the 241 Am. Using tissue-equivalent material, measurements were made with portable detectors to obtain the values of the total attenuation coefficient for the 241 Am radiation and compared to the NIST tables. Measurements were also made with the fixed detectors for certification of the measurement procedure. The percentage deviations obtained in relation to the theoretical ones were: PRD (55%) and IdentiFINDER2 (72%). First-aid monitoring measurements may present great uncertainties and differences of accuracy, but are important data to guide the medical treatment of the victims of accidents

  20. Opportunities and challenges for structural health monitoring of radioactive waste systems and structures

    Energy Technology Data Exchange (ETDEWEB)

    Giurgiutiu, Victor [University of South Carolina, Columbia, SC 29208 (United States); Mendez Torres, Adrian E. [Savannah River National Laboratory, Aiken, SC 29808 (United States)

    2013-07-01

    Radioactive waste systems and structures (RWSS) are safety-critical facilities in need of monitoring over prolonged periods of time. Structural health monitoring (SHM) is an emerging technology that aims at monitoring the state of a structure through the use of networks of permanently mounted sensors. SHM technologies have been developed primarily within the aerospace and civil engineering communities. This paper addresses the issue of transitioning the SHM concept to the monitoring of RWSS and evaluates the opportunities and challenges associated with this process. Guided wave SHM technologies utilizing structurally-mounted piezoelectric wafer active sensors (PWAS) have a wide range of applications based on both propagating-wave and standing-wave methodologies. Hence, opportunities exist for transitioning these SHM technologies into RWSS monitoring. However, there exist certain special operational conditions specific to RWSS such as: radiation field, caustic environments, marine environments, and chemical, mechanical and thermal stressors. In order to address the high discharge of used nuclear fuel (UNF) and the limited space in the storage pools the U.S. the Department of Energy (DOE) has adopted a 'Strategy for the Management and Disposal of Used Nuclear Fuel and High-Level Radioactive Waste' (January 2013). This strategy endorses the key principles that underpin the Blue Ribbon Commission's on America's Nuclear Future recommendations to develop a sustainable program for deploying an integrated system capable of transporting, storing, and disposing of UNF and high-level radioactive waste from civilian nuclear power generation, defense, national security, and other activities. This will require research to develop monitoring, diagnosis, and prognosis tools that can aid to establish a strong technical basis for extended storage and transportation of UNF. Monitoring of such structures is critical for assuring the safety and security of the

  1. Environmental monitoring of low-level radioactive waste disposal facility

    International Nuclear Information System (INIS)

    Shum, E.Y.; Starmer, R.J.; Young, M.H.

    1989-12-01

    This branch technical position (BTP) paper on the environmental monitoring program for a low-level radioactive waste disposal facility provides general guidance on what is required by Section 61.53 of Title 10 of the Code of Federal Regulations (10 CFR) of applicants submitting a license application for such a facility. In general, the environmental monitoring program consists of three phases: preoperational, operational, and postoperational. Each phase of the monitoring program should be designed to fulfill the specific objectives defined in the BTP paper. During the preoperational phase, the objectives of the program are to provide site characterization information, to demonstrate site suitability and acceptability, to obtain background or baseline information, and to provide a record for public information. During the operational phase, the emphasis on measurement shifts. Monitoring data are obtained to provide early warning of releases and to document compliance with regulations, the dose limits of 10 CFR Part 61, or applicable standards of the US Environmental Protection Agency. Data are also used to update important pathway parameters to improve predictions of site performance and to provide a record of performance for public information. The postoperational environmental monitoring program emphasizes measurements to demonstrate compliance with the site-closure requirements and continued compliance with the performance objective in regard to the release of radionuclides to the environment. The data are used to support evaluation of long-term effects on the general public and for public information. Guidance is also provided in the BTP paper on the choice of which constituents to measure, setting action levels, relating measurements to appropriate actions in a corrective action plan, and quality assurance

  2. Long-term monitoring for closed special sites

    International Nuclear Information System (INIS)

    Golchert, N.W.; Sedlet, J.

    1987-01-01

    A methodology is presented for planning and implementing a long-term environmental monitoring program for closed special radioactive waste disposal sites. The steps in the method involve collection of the available background information on the site history, site and area characteristics, waste inventory, pathway analysis, prior monitoring programs, applicable standards, and the legal/regulatory requirements. This information is coupled with factors such as experience, half-life, radionuclide migration rates, and potential hazard to develop a monitoring program. As an example, a site-specific long-term monitoring program is described for the AMAX site using the available information. Sampling techniques and practices for the monitoring program are discussed and techniques and practices expected to be available in the future are considered. 7 references, 2 tables

  3. Immersed radioactive wastes

    International Nuclear Information System (INIS)

    2017-03-01

    This document presents a brief overview of immersed radioactive wastes worldwide: historical aspects, geographical localization, type of wastes (liquid, solid), radiological activity of immersed radioactive wastes in the NE Atlantic Ocean, immersion sites and monitoring

  4. Recommendations to the NRC for review criteria for alternative methods of low-level radioactive waste disposal: Environmental monitoring and surveillance programs

    International Nuclear Information System (INIS)

    Denham, D.H.; Stenner, R.D.; Eddy, P.A.; Jaquish, R.E.; Ramsdell, J.V. Jr.

    1988-07-01

    Licensing of a facility for low-level radioactive waste disposal requires the review of the environmental monitoring and surveillance programs. A set of review criteria is recommended for the US Nuclear Regulatory Commission (NRC) staff to use in each monitoring phase---preoperational, operational, and post operational---for evaluating radiological and selected nonradiological parameters in proposed environmental monitoring and surveillance programs at low-level waste disposal facilities. Applicable regulations, industry standards, and technical guidance on low-level radioactive waste are noted throughout the document. In the preoperational phase, the applicant must demonstrate that the environmental monitoring program identifies radiation levels and radionuclide concentrations at the site and also provides adequate basic data on the disposal site. Data recording and statistical analyses for this phase are addressed

  5. NRPA. Radioactivity in the marine environment 2008 and 2009. Results from the Norwegian national monitoring programme (RAME)

    International Nuclear Information System (INIS)

    Gaefvert, T.; Heldal, H. E.; Brungot, A. L.; Gwynn, J.; Svaeren, I.; Kolstad, A. K.; Moeller, B.; Straalberg, E.; Christensen, G. C.; Drefvelin, J.; Dowdall, M.; Lind, B.; Rudjord, A. L.

    2011-04-01

    The issue of present and potential radioactive contamination in the marine environment has received considerable attention in Norway. In the late 1980s several accidents and incidents involving nuclear-powered submarines,demonstrated that the risk of the release of radionuclides into the Barents Sea should be considered more carefully. In particular, it became evident that better documentation concerning the radioactivity levels in fish and other seafood was important for the seafood export industries. Furthermore, in the early 1990s, information concerning the dumping of nuclear waste emerged through bilateral environmental cooperation between Norway and Russia. In the years that followed, concern grew regarding the safety of military and civil nuclear installations in the northwest of Russia. This concern was associated not only with possible reactor accidents, but also with the prolonged or sudden release of radio-nuclides from radioactive waste facilities.In addition to the potential threats outlined above, radionuclides originating from nuclear weapons fallout, the Chernobyl accident and waste discharged from European reprocessing facilities have been detected in the Norwegian marine environment. In 1994 and 1995, the discharge of 99Tc from the reprocessing facility at Sellafield in the UK increased sharply, and although this discharge has been reduced, it continued at a high level up to 2003. There has been much public concern about the consequences of such kinds of release, as the radionuclides discharged to the Irish Sea are transported by ocean currents via the North Sea into the Norwegian coastal current and to the Barents Sea. In response to this concern, programmes for the monitoring of radioactivity in the marine environment have been established. Due to the economic importance of the fishing industry and its vulnerability to contamination, as well as any rumours of radioactive contamination, one of the main objectives of these programmes is to

  6. Survey monitoring of environmental radioactivity in Seoul area

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Jai Ki; Kim, Hong Suk [Seoul Monitoring Station, Seoul (Korea, Republic of)

    2003-12-15

    The following results were obtained through the environmental radiation monitoring in 2003 at the Seoul monitoring station : gamma exposure rate : 10.8 - 13.3 {mu}R/h, mean gross beta activity in airborne dust : 4.31 {+-} 2.01 mBq/m{sup 3} (after 48 hours), mean gross beta activity in fallout dust : 11.5 {+-} 4.3 MBq/km{sup 2} - 30 days, meab gross beta activity in precipitation : 230 {+-} 246 mBq/L, mean gross beta activity in tap water : 69.3 {+-} 15.7 mBq/L. All the monitored variables remained in the corresponding normal ranges, which implies that there were no abnormal situations of environmental radiation in the Seoul district in 2003. Radioactivity contents in foodstuffs consumed in Seoul and northern part of Gyunggi district were analyzed for use in assessment of population doses via dietary intakes. Samples include 16 foodstuffs(peanut, walnut, pine seeds, chessnut, acorn, sesame, perilla seeds, oak mushroom, meadow mushroom, velvet foot, oyster mushroom, instant coffee, green tea leaves, ginseng tea, rice and Chinese cabbage). Two indicator samples, pine needle and mugwort, were also included. Relatively higher concentrations of {sup l37}Cs, a man-made nuclide, were found in coffee and oak mushroom(0.733 and 0.339 Bq/kg{center_dot}fresh, respectively). A few hundreds Bq/kg{center_dot}fresh of {sup 40}K were found in most of the foodstuffs with higher concentrations in coffee and green tea leaves (1300 and 579 Bq/kg{center_dot}fresh, respectively)

  7. Environmental monitoring for low-level radioactive waste-disposal facilities

    International Nuclear Information System (INIS)

    Shum, E.Y.; Starmer, R.J.; Westbrook, K.; Young, M.H.

    1990-01-01

    The U.S. Nuclear Regulatory Commission prepared a Branch Technical Position (BTP) paper on environmental monitoring of a low-level radioactive waste-disposal facility. The BTP provides guidance on what is required in Section 61.53 of 10 CFR Part 61 for those submitting a license application. Guidance is also provided on choosing constituents to measure, setting action levels, relating measurements to appropriate actions in a corrective action plan, and quality assurance. The environmental monitoring program generally consists of three phases: preoperational, operational, and postoperational. Each phase should be designed to fulfill specific objectives defined in the BTP. During the preoperational phase, program objectives are to provide site characterization information, demonstrate site suitability and acceptability, and obtain background or baseline information. Emphasis during the operational phase is on measurement shifts. Monitoring data are obtained to demonstrate compliance with regulations, with dose limits of 10 CFR Part 61, or with applicable U.S. Environmental Protection Agency standards. Data are also used to update important pathway parameters to improve predictions of site performance and to provide a record of performance for public information. The postoperational phase emphasizes measurements to demonstrate compliance with site closure requirements and continued compliance with the performance objective for release. Data are used to support evaluation of long-term impacts to the general public and for public information

  8. Environmental radioactivity monitoring in surface water from an ecological point of view

    International Nuclear Information System (INIS)

    Huebel, K.

    1981-01-01

    For each bigger river section, ecological transition factors for the individual relevant media are to be determined. Because of the great biologic variability long-term investigations are necessary. For most of the nuclides, the deviations are more than two orders of magnitude; therefore, many values are necessary for guaranteeing the statistics. Here, the 'general environmental radioactivity monitoring' is offered. There are results (Bavaria) from 25 years which represent extensive material for the purposes of radio-ecology. (DG) [de

  9. Recent advances in nuclear techniques for environmental radioactivity monitoring

    International Nuclear Information System (INIS)

    Kumar, Ajay; Tripathi, R.M.

    2016-01-01

    The environmental radioactivity monitoring was first started in the late 1950s following the global fallout from testing of nuclear weapons in the atmosphere. Nuclear analytical techniques are generally classified into two categories: destructive and non-destructive. Destructive techniques are carried out through several analytical methods such as α-spectrometry, liquid Scintillation counting system, solid state nuclear track detector, spectrophotometry, fluorimetry, atomic absorption spectrometry (AAS), inductively coupled plasma mass spectrometry (ICP-MS), inductively coupled plasma optical emission spectrometry (ICP-OES), chromatography techniques, electro-analytical techniques etc. However, nondestructive methods include gamma spectrometry, X-Ray fluorescence (XRF) spectrometry, neutron activation analysis (NAA) etc. The development of radiochemical methods and measurement techniques using alpha and gamma spectrometry have been described in brief

  10. Radioactivity monitoring of the Irish marine environment 1985-86

    International Nuclear Information System (INIS)

    Cunningham, J.D.; O'Grady, J.; Rush, T.

    1988-01-01

    This report presents the results of the monitoring programme for the two-year period from January 1985 to December 1986. Information on the radioactive contamination of the marine environment is obtained from the analysis of environmental samples taken at a number of locations along the coastline and various sampling stations in the western Irish Sea. These usually include samples of surface seawater, sediment, seaweed, fish and shellfish. Estimates are presented of the individual and collective doses received by the Irish public from the consumption of fish and shellfish during the period 1985-1986. These doses are assessed in terms of the system of dose limitation recommended by the International Commission on Radiological Protection and embodied in the Basic Safety Standards Directive of the European Community

  11. Processing and monitoring liquid, radioactive effluents from the Wiederaufarbeitungsanlage Karlsruhe

    International Nuclear Information System (INIS)

    Hoehlein, G.; Huppert, K.L.; Winter, M.

    1977-01-01

    The Wiederaufarbeitungsanlage Karlsruhe (WAK) serves as a demonstration plant for the processing of highly-irradiated uranous oxide. The high active waste concentrates find interim storage at the WAK until they are solidified at a later stage. In contrast to this, the slightly- and the medium-active liquid wastes are transported to the decontamination facility of the Nuclear Research Centre Karlsruhe, where they are immediately processed. These liquid wastes contain about 1 per thousand of the activity inventary of the fuel elements processed. Monitoring of the radioactive waste water of the WAK is carried out by the Nuclear Research Centre's department radiation protection and safety. (orig.) [de

  12. Infrared thermography applied to monitoring of radioactive waste drums; Termografia infravermelha aplicada ao monitoramento de tambores de rejeitos radioativos

    Energy Technology Data Exchange (ETDEWEB)

    Kelmer, P.; Camarano, D.M. [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil); Calado, F.; Phillip, B.; Viana, C.; Andrade, R.M., E-mail: paulafuziki@yahoo.com.br, E-mail: flavio.arcalado@gmail.com, E-mail: bruno.phil@gmail.com, E-mail: criisviana@hotmail.com, E-mail: rma@ufmg.br, E-mail: dmc@cdtn.br [Universidade Federal de Minas Gerais (UFMG), Belo Horizonte, MG (Brazil). Departamento de Engenharia Eletrica

    2013-07-01

    The use of thermography in the inspection of drums containing radioactive waste is being stimulated by the absence of physical contact. In Brazil the majority of radioactive wastes are compacted solids packed in metal drums stored temporarily for decades and requires special attention. These drums have only one qualitative indication of the radionuclides present. However, its structural condition is not followed systematically. The aim of this work is presents a methodology by applying thermography for monitoring the structural condition of drums containing radioactive waste in order to detect degraded regions of the drums. (author)

  13. Evaluating the reproducibility of environmental radioactivity monitoring data through replicate sample analysis

    International Nuclear Information System (INIS)

    Lindeken, C.L.; White, J.H.; Silver, W.J.

    1978-01-01

    At the Lawrence Livermore Laboratory, about 10% of the sampling effort in the environmental monitoring program represents replicate sample collection. Replication of field samples was initiated as part of the quality assurance program for environmental monitoring to determine the reproducibility of environmental measurements. In the laboratory these replicates are processed along with routine samples. As all components of variance are included in analysis of such field samples, comparison of the analytical data from replicate analyses provides a basis for estimating the overall reproducibility of the measurements. The replication study indicates that the reproducibility of environmental radioactivity monitoring data is subject to considerably more variability than is indicated by the accompanying counting errors. The data are also compared with analyses of duplicate aliquots from a well mixed sample or with duplicate aliquots of samples with known radionuclide content. These comparisons show that most of the variability is associated with the collection and preparation of the sample rather than with the analytical procedures

  14. Handling of radioactive sources in Ecuador

    International Nuclear Information System (INIS)

    Benitez, Manuel

    2000-01-01

    This document describes the following aspects: sealed and unsealed radioactive sources, radiation detectors, personnel and area monitoring, surface pollution, radioactive wastes control and radioactive sources transferring. (The author)

  15. Mosses in Radioactive Monitoring

    International Nuclear Information System (INIS)

    Marovic, G.; Franic, Z.; Sencar, J.

    2008-01-01

    Mosses, lichens and perennial plants, all characterized by slow growth, are able to efficiently accumulate different radionuclides from their environment to a much higher degree than other vegetation. Consequently, they are sensitive bio indicators of radioactive contamination for various ecosystems. Results of systematic, long-term measurements of 137Cs activities in mosses for the period 1986-2007 are summarized. The study was conducted in the Radiation Protection Unit of the Institute for Medical Research and Occupational Health in Zagreb, as a part of an extensive monitoring program of the Croatian environment. In the overall observed period the highest activity concentration of 137Cs deposited by fallout has been recorded in 1986, which is the year of Chernobyl accident, causing peak 137Cs activity concentration in moss of 8800 Bqkg -1 in May 1986. Mean value for period 1986 - 1990 was 3423 Bqkg -1 . For comparison, in the same period mean 137Cs activity concentration in grass was 390 Bqkg -1 . In 1990s, ten year after Chernobyl accident, mean 137Cs activity concentration in moss was 1345 Bqkg -1 , with maximum value of 3940 Bqkg -1 (December 1994). In 2000s, mean 137Cs activity concentration in mosses was 172 Bqkg -1 with maximum value of 955 Bqkg -1 (July 2002). Fitting the measured 137Cs activity concentrations to the theoretical curve (1) the ecological half-life of 137Cs in moss was found to be about 978 days, while in grass was found to be about 126 days in the period 1986 - 1990. The ecological half-life of 137Cs in grass after 1991 was found to be about 2503 days. The ecological half-life of 137Cs in moss is about eight times higher than 137Cs ecological half-life observed in grass in the first period after the Chernobyl accident.(author)

  16. Design and development of food radioactivity contamination monitoring system

    International Nuclear Information System (INIS)

    Narayan, Pradeep; Vaijapurkar, S.G.; Bohra, Dinesh

    2014-01-01

    Radioactivity has been part and parcel of living being since the existence of the earth. It is available everywhere in our environment and being responsible for evolution of life on earth at some extent. However, the radioactivity in excess of the natural radioactive can have harmful effects on living being. The radiation exposure can be of external or internal origin or of both. The main route of internal radiation exposure is through the contaminated food chains. The concentration of natural radioactivity in food varies in range of 40-600 Bq/kg. 40 K being the single major radionuclide of food with typical radioactivity; 50 Bq/kg in milk, 420 Bq/kg in milk powder, 165 Bq/kg in potatoes, and 125 Bq/kg in beef is also the main contributor of natural radiation doses to human being. Measurement of radioactivity in food items and drinks is thus very important in controlling the internal exposure to human being especially in case of nuclear disaster. Though, the methods and techniques for food radioactivity measurement already existing, the need of portable instrument is warranted to measure the radioactivity in food items in raw form. Measurement of radioactivity may help in quick and mass screening of food items in case of nuclear emergencies. Any enhanced level of radioactivity in food items especially in case of nuclear emergency need to be evaluated for controlling its spread and restriction of consumption by the public. This way, it may help in managing internal radioactivity contamination to human being

  17. Integrated Closure and Monitoring Plan for the Area 3 and Area 5 Radioactive Waste Management Sites at the Nevada Test Site

    International Nuclear Information System (INIS)

    Bechtel Nevada

    2005-01-01

    This document is an integrated plan for closing and monitoring two low-level radioactive waste disposal sites at the Nevada Test Site. This document is an integrated plan for closing and monitoring two low-level radioactive waste disposal sites at the Nevada Test Site (NTS). The Area 3 and Area 5 Radioactive Waste Management Sites (RWMSs) are managed and operated by Bechtel Nevada (BN) for the U.S. Department of Energy's (DOE's) National Nuclear Security Administration Nevada Site Office (NNSA/NSO). The Integrated Closure and Monitoring Plan (ICMP) for these sites is based on guidance for developing closure plans issued by the DOE (DOE, 1999a). The plan does not closely follow the format suggested by the DOE guidance to better accommodate differences between the two RWMSs, especially in terms of operations and site characteristics. The modification reduces redundancy and provides a smoother progression of the discussion. Further, much of the information that would be included in the individual plans is the same, and integration provides efficient presentation. A cross-walk between the contents of the ICMP and the DOE guidance is given in Appendix A. Closure and monitoring were integrated because monitoring measures the degree to which the operational and closed disposal facilities are meeting performance objectives specified in the manual to DOE Order O 435.1. Department of Energy Order 435.1 governs management of radioactive waste, and associated with it are Manual DOE M 435.1-1 and Guidance DOE G 435.1-1. The performance objectives are intended to ensure protection of workers, the public, and the environment from radiological exposure associated with the RWMSs now and in the future

  18. Quality assurance for the measurements and monitoring of radioactivity in the environment

    International Nuclear Information System (INIS)

    Betti, Maria; Aldave de las Heras, Laura

    2004-01-01

    During the Fifth Framework Programme (FP5) of the European Commission--according to an institutional programme in support to the policy of the European Commission for the implementation of Art. 35 and 36 of the Euratom Treaty as well as in the framework of the OSPAR Convention for the protection of marine environment of the north-east Atlantic--at the Institute for Transuranium Elements (ITU-General Directorate Joint Research Centre-European Commission), a reference laboratory for the measurement of radioactivity in the environment (MaRE laboratory) has been set up. In this paper, the principles and philosophy in order to improve the quality and reliability of analytical data for the measurement and monitoring of radioactivity in the environment under a quality assurance (QA) programme are presented. Examples of how a QA programme at the MaRE laboratory is developed and applied are given. Internal and external quality control (QC) programmes are also discussed

  19. Monitoring of low-level radioactive liquid effluent in Tokai reprocessing plant

    International Nuclear Information System (INIS)

    Mizutani, Tomoko; Koarashi, Jun; Takeishi, Minoru

    2009-01-01

    The Tokai reprocessing plant (TRP), the first reprocessing plant in Japan, has discharged low-level liquid wastes to the Pacific Ocean since the start of its operation in 1977. We have performed liquid effluent monitoring to realize an appropriate radioactive discharge control. Comparing simple and rapid analytical methods with labor-intensive radiochemical analyses demonstrated that the gross-alpha and gross-beta activities agreed well with the total activities of plutonium isotopes ( 238 Pu and 239+240 Pu) and major beta emitters (e.g., 90 Sr and 137 Cs), respectively. The records of the radioactive liquid discharge from the TRP showed that the normalized discharges of all nuclides, except for 3 H, were three or four orders of magnitude lower than those from the Sellafield and La Hague reprocessing plants. This was probably due to the installation of multistage evaporators in the liquid waste treatment process in 1980. The annual public doses for a hypothetical person were estimated to be less than 0.2 μSv y -1 from the aquatic pathway. Plutonium radioactivity ratios ( 238 Pu/ 239+240 Pu) of liquid effluents were determined to be 1.3-3.7, while those of the seabed sediment samples collected around the discharge point were 0.003-0.059, indicating no remarkable accumulation of plutonium in the regional aquatic environment. Thus, we concluded that there were no significant radiological effects on the public and the aquatic environment during the past 30-year operation of the TRP. (author)

  20. New approach to airborne monitoring of radioactive pollution

    International Nuclear Information System (INIS)

    Hoeschl, V.; Jurza, P.; Pavlik, B.

    1997-01-01

    The use of remote sensing methods in the monitoring of an environment is increasing. The best results are obtained when various types of exploration methods are available. This paper presents the use of airborne gamma ray methods, which can be included in a wide scope of works related to environmental problems. It may concern uranium mining areas, areas surrounding various nuclear facilities or areas of Chernobyl fallout. Gamma ray spectrometry data can be combined with airborne magnetic, surface gravity and satellite imagery data to obtain maximum information in data output. Airborne geophysics is able to detect and delineate radioactive contamination and to find important geological trends defining the geological structure of the monitored area. Our company PICODAS Prague Ltd. introduces new sophisticated airborne instrumentation as well as up-to-date data processing and data presentation techniques. In the Czech Cretaceous, a long term project, ''The Structurally-tectonic Survey of the South-West Foreland of the Straz Deposit'' has been undertaken, concerning the ecological load on the environment, especially the pollution of the underground water level horizons due to uranium mining in that area. The major interest is the complicated tectonic structure which interferes heavily with the hydrogeological situation of the region. The paper presents the results of airborne surveys and the interpretation of other geophysical data from the surroundings of Straz pod Ralskem and from Karlovy Vary. (author)

  1. Monitoring of the radioactive liquid effluents discharged from IPEN-CNEN/SP. Optimization of the procedures adopted

    International Nuclear Information System (INIS)

    Seki, C.R.

    1990-01-01

    The main purpose of a radioactive liquid effluents monitoring of a nuclear installation is to determine the amount of radioactivity discharged to the environment, as well as, to verify if this activity is below the authorized discharge limits established by the competent authority. Although this control has been established on a routine basis since the beginning of operation of the nuclear installations available at IPEN, the growing of such facilities in the last years has implied in an increase in the number of samples to be analyzed. The aim of this work is, therefore, to optimize the procedures adopted in the Environmental Monitoring Division of IPEN-CNEN/SP for the activity measurement of the liquid effluents discharged to the environment. Since these effluents are discharged to Pinheiros river, which presents a high dilution factor, a study is also carried out in order to verify if the activity present can be measured by the equipment available. (author)

  2. Construction and calibration of a simple scintillation counter for monitoring radioactive gases in ducts

    International Nuclear Information System (INIS)

    Johnston, M.S.

    1984-07-01

    A report is given of the practical construction, laboratory calibration and simple-in-situ calibration check of scintillation detectors used for monitoring radioactive inert gases in gaseous effluents. The βγ-ray and γ-ray detectors are identical except for an absorber which is placed over the window of the γ-ray detector after calibration. The construction and calibration of both detectors is therefore identical. (author)

  3. Radioactivity monitoring of the P.P

    Energy Technology Data Exchange (ETDEWEB)

    Joksic, J.; Todorovic, D.; Radenkovic, M. [VINCA Institute of Nuclear Sciences, Radiation and Enviro nmental Protecti on Lab., Belgrade (Serbia and Montenegro)

    2006-07-01

    The radioactivity monitoring in the 'Nikola Tesla' thermo-electric power plant environment comprised the analysis of soil, waters, flying ash, slag and plants. Soil, plant and water samples were taken in the environment of the 'Tent A', 'Tent B', 'Kolubara' and 'Morava' power plants during the two years period 2003-2004 and analyzed b y standard radiometric methods. Naturally occurring radionuclides 226 Ra, 232 Th, 40 K, 235 U, 238 U, 210 Pb are determined by gamma spectrometry using H.P. Ge detector, relative efficiency of 23% and energy resolution of 1.8 keV (1332.5 keV). Ceied reference materials: soil matrix with 55 Na, 57 Co, 60 Co, 89 Y, 133 Ba and 137 Cs (MIX-OMHSZ, National Office of Measures) and grass with 134 Cs, 137 Cs, 40 K and 90 Sr (IAEA-373) were used for calibration. The gross alpha and gross beta activity measurements are carried out using low-level background alpha-beta proportional gas counter. Radiochemical analyzes of soil samples have shown the naturally occurring radionuclides: 226 Ra 35-60 Bq/kg, 232 Th 35-49 Bq/kg, 40 K 513-711 Bq/kg, 210 Pb 14-69 Bq/kg, 238 U 25-80 Bq/kg and 235 U 1.1-4.5 Bq/kg. The 137 Cs was found in concentration 10-57 Bq/kg. Radiochemical analyzes of plant samples have shown the naturally occurring radionuclides: 226 Ra 0.7-6.1 Bq/kg, 232 Th 1-4.8 Bq/kg, 40 K 392-1132 Bq/kg, 210 Pb 5.6-97 Bq/kg, 238 U 2.3-7.4 Bq/kg and 235 U 0.2-0.7 Bq/kg. The 137 Cs was found in concentration 0.13-2.8 Bq/kg. The water samples were within the range of recommended values for drinking waters in Serbia and Montenegro. Total alpha activity was below the lowest limit of detection and total beta activities were up to 0.35 Bq/l. The results of measured radionuclides in soil, plant and water samples do not show any significant radioactive environmental pollution. (authors)

  4. Radioactivity monitoring of the P.P

    International Nuclear Information System (INIS)

    Joksic, J.; Todorovic, D.; Radenkovic, M.

    2006-01-01

    The radioactivity monitoring in the 'Nikola Tesla' thermo-electric power plant environment comprised the analysis of soil, waters, flying ash, slag and plants. Soil, plant and water samples were taken in the environment of the 'Tent A', 'Tent B', 'Kolubara' and 'Morava' power plants during the two years period 2003-2004 and analyzed b y standard radiometric methods. Naturally occurring radionuclides 226 Ra, 232 Th, 40 K, 235 U, 238 U, 210 Pb are determined by gamma spectrometry using H.P. Ge detector, relative efficiency of 23% and energy resolution of 1.8 keV (1332.5 keV). Certified reference materials: soil matrix with 55 Na, 57 Co, 60 Co, 89 Y, 133 Ba and 137 Cs (MIX-OMHSZ, National Office of Measures) and grass with 134 Cs, 137 Cs, 40 K and 90 Sr (IAEA-373) were used for calibration. The gross alpha and gross beta activity measurements are carried out using low-level background alpha-beta proportional gas counter. Radiochemical analyzes of soil samples have shown the naturally occurring radionuclides: 226 Ra 35-60 Bq/kg, 232 Th 35-49 Bq/kg, 40 K 513-711 Bq/kg, 210 Pb 14-69 Bq/kg, 238 U 25-80 Bq/kg and 235 U 1.1-4.5 Bq/kg. The 137 Cs was found in concentration 10-57 Bq/kg. Radiochemical analyzes of plant samples have shown the naturally occurring radionuclides: 226 Ra 0.7-6.1 Bq/kg, 232 Th 1-4.8 Bq/kg, 40 K 392-1132 Bq/kg, 210 Pb 5.6-97 Bq/kg, 238 U 2.3-7.4 Bq/kg and 235 U 0.2-0.7 Bq/kg. The 137 Cs was found in concentration 0.13-2.8 Bq/kg. The water samples were within the range of recommended values for drinking waters in Serbia and Montenegro. Total alpha activity was below the lowest limit of detection and total beta activities were up to 0.35 Bq/l. The results of measured radionuclides in soil, plant and water samples do not show any significant radioactive environmental pollution. (authors)

  5. EPA's Radioactive Source Program

    International Nuclear Information System (INIS)

    Kopsick, D.

    2004-01-01

    The US EPA is the lead Federal agency for emergency responses to unknown radiological materials, not licensed, owned or operated by a Federal agency or an Agreement state (Federal Radiological Emergency Response Plan, 1996). The purpose of EPA's clean materials programme is to keep unwanted and unregulated radioactive material out of the public domain. This is achieved by finding and securing lost sources, maintaining control of existing sources and preventing future losses. The focus is on both, domestic and international fronts. The domestic program concentrates on securing lost sources, preventing future losses, alternative technologies like tagging of radioactive sources in commerce, pilot radioactive source roundup, training programs, scrap metal and metal processing facilities, the demolition industry, product stewardship and alternatives to radioactive devices (fewer radioactive source devices means fewer orphan sources). The international program consists of securing lost sources, preventing future losses, radiation monitoring of scrap metal at ports and the international scrap metal monitoring protocol

  6. Environmental radioactivity surveillance programme 1994-1996

    International Nuclear Information System (INIS)

    Pollard, D.; Smith, V.; Howett, D.; Hayden, E.; Fegan, M.; O'Colmain, M.; Cunningham, J.D.

    1997-12-01

    This report presents the results of the terrestrial monitoring programme implemented by the Radiological Protection Institute of Ireland during the period 1994 to 1996. This monitoring programme includes the routine sampling and testing for radioactivity of samples of air, rainwater, drinking water and milk. Atmospheric concentrations of krypton-85 continued to rise over the period. No abnormal readings were observed for gamma dose rate, radioactivity in airborne particulates or radioactivity in rainwater. Significant variation in the concentrations of natural radioactivity was observed between drinking water supplies.The levels of anthropogenic radioactivity recorded during this reporting period in air, rainwater, drinking water and milk continue to be insignificant from a radiological safety point of view

  7. The role of national regulatory authority in monitoring of radioactivity and in case of seizure of radioactive or nuclear material

    International Nuclear Information System (INIS)

    Morkunas, G.

    2002-01-01

    Full text: The Radiation Protection Centre is a regulatory authority in radiation protection in Lithuania. Its main tasks are licensing of practices, supervision, control and enforcement of radiation protection requirements, dosimetric, radiometric and spectrometric measurements, evaluation of exposure and its sources, expertise and advice on optimization of radiation protection. Its activities may be divided into two main parts -- regulatory and analytical ones. Food, drinking water, environmental, wipe and other samples are monitored, the appropriate evaluation of doses is done. The data on concentrations of artificial radionuclides in different bodies are available. The laboratory is to be accredited according to the ISO 17025 standard in the framework of Phare Twinning Project. In case of seized radioactive or nuclear material the Radiation Protection Centre has to identify the necessary radiation protection means for members of public and emergency workers, perform measurements of dose rate and radioactive contamination, and, if necessary, evaluate doses received due to the seized radioactive or nuclear material. Since the Radiation Protection Centre has its departments in the largest cities of Lithuania the above mentioned measures can be taken very urgently, especially the ones connected with primary evaluation of situation and identification of optimized radiation protection measures. The Radiation Protection Centre has its own possibilities of identification of radionuclides in the seized material. Such installations as HpGe spectrometers (Oxford and Canberra), equipment for radiochemical separation of U, Pu and actinides, alpha spectrometer, liquid scintillation spectrometer and neutron rem counter are available. There were a few cases when seized material had to be analyzed also. Different sources were found in different places of Lithuania, and it was necessary to define the activity and isotopic content of these sources. The following scheme is used in

  8. Radioactive sources and contaminated materials in scrap: monitoring, detection and remedial actions

    International Nuclear Information System (INIS)

    Gallini, R.; Berna, V.; Bonora, A.; Santini, M.

    1999-01-01

    The scrap recycling in steel and other metal mills represents one of the most relevant activities in the Province of Brescia (Lombardy, Italy). In our Province more than 20 million tonnes of metal scrap are recycled every year by a melting process. Since 1990, many accidents which took place were caused by the unwanted melting of radioactive sources, that were probably hidden in metal scrap. In 1993, the Italian Government stated directives to monitor metal scrap imported from non-EC countries because of the suspicion of the illegal traffic of radioactive materials. In 1996, a law imposed the control of all metal scrap, regardless of their origins. Since 1993, our staff have controlled thousands of railway wagons and trucks. Approximately a hundred steel mills and foundries of aluminium, cooper, brass, etc. have also been controlled and many samples have been collected (flue dust, slag, finished products). During these controls, contaminated areas have been brought to light in two warehouses (Cs 137), in 6 companies (Cs 137 and Am 241), in two landfills of industrial waste (Cs 137) and in a quarry (Cs 137). Up to now the contaminated areas have been cleaned, except for the last one. About 150 radioactive sources on contaminated materials have been found in metal scrap. We found radioactive sources of Co 60, Ra 226, Ir 192, Kr 85, Am 241, while the contamination of metals was mainly due to Ra 226. The situation described above justifies an accurate control of the amount of scrap to reduce the risk of contamination of the workers in the working areas, in the environment and in the general public. (author)

  9. Environmental Remediation and Radioactivity Monitoring of Uranium Mining Legacy in Portugal

    Energy Technology Data Exchange (ETDEWEB)

    Carvalho, F.P., E-mail: carvalho@itn.pt [Nuclear and Technological Institute, Sacavém (Portugal)

    2014-05-15

    The main legacy site of uranium mining and milling in Portugal, located near the town of Canas de Senhorim, contained around 15 million tones of solid waste in various mill tailings and spoil heaps. Approval of an environmental remediation plan for this area was followed by the start of engineering works, including the transportation of several wastes to the main tailings pile, re shaping and contouring the waste heap and placing a multi layer cap. These works were mostly performed in 2006 and 2007. During part of this period, monitoring of radioactivity was performed in the surface air, surface waters from the area including the monitoring of the small river that receives drainage from the mill tailings area, and agriculture products. This paper presents the results of measurements of the main alpha emitting radionuclides of uranium series in water and compares them with previous data for the region. Implications for the radiological protection of the population are discussed. (author)

  10. Monitoring of radioactivity in the environs of Finnish nuclear power stations in 1986

    International Nuclear Information System (INIS)

    Ilus, E.; Sjoeblom, K.L.; Aaltonen, H.; Klemola, S.; Arvela, H.

    1987-06-01

    Results of the environmental programmes monitoring radioactivity around the Finnish nuclear power stations in 1986 are reported. After the end of April the fallout nuclides from the Chernobyl accident predominated in all samples taken from the environs of the two power stations Loviisa and Olkiluoto. Radionuclides originating from the Finnish power stations were detected mainly in samples taken from the aquatic environment. The concentrations of the locally discharged nuclides were very low in comparison with the fallout nuclides and their impact on the radiation doses of the population was insignificant. Both nuclear power stations are situated in the main fallout area in Finland. The results of these large monitoring programmes give a good picture of the behaviour of the Chernobyl fallout in the specific areas in Finland

  11. Devising a groundwater monitoring strategy for a geologic repository for radioactive waste

    International Nuclear Information System (INIS)

    Leonhart, L.S.; DeLuca, F.A.; Sheahan, N.T.; West, L.M.

    1981-01-01

    This paper represents a topical treatment of the subject of groundwater monitoring as it relates to the particular needs of high-level nuclear waste disposal facilities using the Basalt Waste Isolation Project (BWIP) as a specific reference. While the involvement with management of high-level radioactive wastes and the design and operation of repository facilities is presently parochial to the federal government and certain prime contractors, it is believed that the technical aspects involved with this groundwater monitoring example provide an interesting comparison with those encountered at near-surface and underground-injection, hazardous waste disposal operations. In particular, the integration of several program facets ranging from baselining parameters to validation of predictive models into a comprehensive strategy may be of interest. It is hoped that this type of conceptual exchange will be beneficial to all concerned

  12. Environmental radioactivity in Canada 1988. Radiological monitoring annual report

    Energy Technology Data Exchange (ETDEWEB)

    1992-12-31

    The radiological surveillance program of the Department of National Health and Welfare is conducted for the purpose of determining levels of environmental radioactivity in Canada and assessing the resulting population exposures. Following major changes to the CAMECO Port Hope operations to reduce uranium emissions, a study was initiated to measure uranium levels in air in the community. Studies continued on lung cancer and domestic exposure to radon, and current levels of cesium-137 in caribou, a major source of food in northern communities. The movement of tritium on the Ottawa and St. Lawrence rivers was studied following an accidental release into the Ottawa River. Monitoring continued of fallout contamination from Chernobyl in imported foods. All measurements recorded during 1988 were below the limits recommended by the International Commission on Radiological Protection. (14 refs., 14 figs., 15 tabs.).

  13. Monitoring of radioactivity at the Russian nuclear submarine Kursk

    International Nuclear Information System (INIS)

    Amundsen, I.; Lind, B.

    2002-01-01

    In the morning of August 12th 2000, a Russian submarine accident occurred in international waters east of Rybatschi Peninsula in the Barents Sea about 250 km from Norway. The submarine, a Russian Oscar class II attack submarine, sunk to 116 meters depth at the position 69 deg. 36,99N, 37 deg. 34,50E. The submarine 'Kursk' is 154 meters long, equipped with two pressurised water reactors and the submerged displacement is 24000 tons. Each reactor has a thermal effect or 190 megawatt, or less than 10% of a typical nuclear power plant reactor. The submarines in Oscar-II class is one of the largest and most capable in the Russian Northern Fleet. No indications of leakage from the submarine have so far been observed during the monitoring expeditions. Elevated levels of radioactivity have note been detected in any dose-rate readings or at any of the measurements of environmental samples taken close to Kursk. Furthermore, no increased levels were measured on bits and pieces from the submarine or from water sampled inside the submarine. A more comprehensive report covering experience and monitoring results from the two expeditions term and impact assessments of possible future releases from Kursk. (LN)

  14. Radioactive and electron microscope analysis of effluent monitor sample lines

    International Nuclear Information System (INIS)

    Kowalski, J.F.

    1986-01-01

    Effluent air sampling at nuclear power plant often leads to the question ''How representative is the sample of the effluent stream?'' Samples from radiation monitors are typically obtained at great distances from the sample nozzle because of high background concerns under postulated accidents. Sample line plateout during normal effluent sampling becomes the major concern. A US Nuclear Regulatory Commission inspection raised a concern that monitors were not collecting representative samples per ANSI standard N13.1. A comprehensive 2-yr study at Beaver Valley was performed during normal effluent releases in two phases: 1) weekly charcoal and glass fiber filter samples were analyzed for radioactivity for 6 months, and 2) nuclepore membrane filter samples were analyzed by electron microscope for 4- and 6-h periods. A specially designed test nozzle was directly inserted into an effluent stream for comparison with the radiation monitor samples. Particle behavior characteristics can be determined during effluent releases using a simple test probe. While particle plateout was the major purpose of the study, other particle behavior characteristics were evident and equally as important. Particle travel through long sample lines can also lead to (a) agglomeration or the coagulation of smaller particles to form larger ones, (b) particle splitting or fracturing upon impact with the sample line interior walls, and (c) resuspension of large particles in sample lines

  15. General principles governing sampling and measurement techniques for monitoring radioactive effluents from nuclear facilities

    International Nuclear Information System (INIS)

    Fitoussi, L.

    1978-01-01

    An explanation is given of the need to monitor the release of radioactive gases and liquid effluents from nuclear facilities, with particular emphasis on the ICRP recommendations and on the interest in this problem shown by the larger international organizations. This is followed by a description of the classes of radionuclides that are normally monitored in this way. The characteristics of monitoring 'in line' and 'by sample taking' are described; the disadvantages of in line monitoring and the problem of sample representativity are discussed. There follows an account of the general principles for measuring gaseous and liquid effluents that are applied in the techniques normally employed at nuclear facilities. Standards relating to the specifications for monitoring instruments are at present being devised by the International Electrotechnical Commission, and there are still major differences in national practices, at least as far as measurement thresholds are concerned. In conclusion, it is shown that harmonization of practices and standardization of equipment would probably help to make international relations in the field more productive. (author)

  16. Measuring networks for environmental radioactivity monitoring in the European Community, - a pattern of diversity as varying as the peoples?

    International Nuclear Information System (INIS)

    Maushart, R.

    1991-01-01

    A new study entitled 'Monitoring of Environmental Radioactivity in the European Community', (RAES, 90), shows a survey of the methods currently applied in every country. The study compiles available quality assurance programs and makes suggestions for CEC initiatives. The study refers to the current practice of monitoring in European countries as 'enormous diversity of methods' in member countries. Further suggestions for standardization of the data measuring networks are put forward by a manufacturer of monitoring equipment. (orig./DG) [de

  17. Innovative concept for a major breakthrough in atmospheric radioactive xenon detection for nuclear explosion monitoring

    International Nuclear Information System (INIS)

    Le Petit, G.; Cagniant, A.; Gross, P.; Achim, P.; Douysset, G.; Taffary, T.; Moulin, C.; Morelle, M.

    2013-01-01

    The verification regime of the comprehensive test ban treaty (CTBT) is based on a network of three different waveform technologies together with global monitoring of aerosols and noble gas in order to detect, locate and identify a nuclear weapon explosion down to 1 kt TNT equivalent. In case of a low intensity underground or underwater nuclear explosion, it appears that only radioactive gases, especially the noble gas which are difficult to contain, will allow identification of weak yield nuclear tests. Four radioactive xenon isotopes, 131m Xe, 133m Xe, 133 Xe and 135 Xe, are sufficiently produced in fission reactions and exhibit suitable half-lives and radiation emissions to be detected in atmosphere at low level far away from the release site. Four different monitoring CTBT systems, ARIX, ARSA, SAUNA, and SPALAX TM have been developed in order to sample and to measure them with high sensitivity. The latest developed by the French Atomic Energy Commission (CEA) is likely to be drastically improved in detection sensitivity (especially for the metastable isotopes) through a higher sampling rate, when equipped with a new conversion electron (CE)/X-ray coincidence spectrometer. This new spectrometer is based on two combined detectors, both exhibiting very low radioactive background: a well-type NaI(Tl) detector for photon detection surrounding a gas cell equipped with two large passivated implanted planar silicon chips for electron detection. It is characterized by a low electron energy threshold and a much better energy resolution for the CE than those usually measured with the existing CTBT equipments. Furthermore, the compact geometry of the spectrometer provides high efficiency for X-ray and for CE associated to the decay modes of the four relevant radioxenons. The paper focus on the design of this new spectrometer and presents spectroscopic performances of a prototype based on recent results achieved from both radioactive xenon standards and air sample

  18. Marine environmental monitoring related to sea disposal of radioactive waste in the NE Atlantic Ocean

    International Nuclear Information System (INIS)

    Bettencourt, A.O.; Elias, M.D.T.; Ferrador, G.C.

    1988-01-01

    Reference is made to the sea disposal of packaged radioactive waste in the NE Atlantic and to the role of the OCDE Nuclear Energy Agency (NEA) since 1967, in the dumping operations. The objectives of marine environmental monitoring in relation to sea disposal of radioactive wastes are described as well as the coordinated research and environmental surveillance programme (CRESP) developed within NEA frame. The Portuguese on-going programme in this field is presented and the results concerning measurements of 239+240 Pu, 238 Pu, 241 Am and 137 Cs in samples of water, sediments and fish collected at Madeira and Continental Portuguese coasts, are discussed. It was observed that these radionuclides concentrations are lower for deep-sea fishes than for the shallow-water ones. The obtained results are compared with those found in the literature. From the observation of the large spectrum of results available, it can be concluded that no generalized contamination of the marine environment due to the sea dumping of radioactive wastes if observed at present. On the other hand, there is an interest in pursuing analyses of deep-sea fish with the aim of early detection of any possible modifications in the actual levels of radioactivity in the marine environment. (author) [pt

  19. Environmental radioactivity survey in Andong

    Energy Technology Data Exchange (ETDEWEB)

    Yoon, Zi Hong; Jo, Kum Ju [Andong Regional Radioactivity Monitoring Station, Andong National Univ., Andong (Korea, Republic of)

    2003-12-15

    The objectives of the project are to monitor an abnormal level in Andong area and to provide a base line data on environmental radiation/radioactivity levels in case of any radiological emergency situation. The project is important in view of protecting the public health from the potential hazards of radiation and keeping up the clean environment. This report simonizes and interprets environmental radiation/radioactivity monitoring samples : Gamma exposure rates, airborne dust, precipitation, fall out and drinking-water. Environmental samples 2 kinds of indicator plant, 4 kinds of mushroom, 7 kinds of nut and seeds, and drinking waters. Among the all 2003 radiological monitoring and environmental data in Andong area were not found the extraordinary data. And a nation-wide environmental radiation/radioactivity level survey results were all background levels attributed to terrestrial and cosmic radiation.

  20. Environmental radioactivity survey in Andong

    Energy Technology Data Exchange (ETDEWEB)

    Yoon, Zi Hong; Jo, Kum Ju [Andong Regional Radioactivity Monitoring Station, Andong National Univ., Andong (Korea, Republic of)

    2002-12-15

    The objectives of the project are to monitor an abnormal level in Andong area and to provide a base-line data on environmental radiation/radioactivity levels in case of any radiological emergency situation. The project is important in view of protecting the public health from the potential hazards of radiation and keeping up the clean environment. This report summarizes and interprets environmental radiation/radioactivity monitoring samples Gamma exposure rates, airborne dust, precipitation, fall-out and drinking-water. Environmental samples 2 kinds of indicator plant, 4 kinds of mushroom, 7 kinds of nut and seeds, and drinking waters. Among the all 2002 radiological monitoring and environmental data in Andong area were not found the extraordinary data. And a nation-wide environmental radiation/radioactivity level survey results were all background levels attributed to terrestrial and cosmic radiation.

  1. Environmental radioactive intercomparison program and radioactive standards program

    Energy Technology Data Exchange (ETDEWEB)

    Dilbeck, G. [Environmental Monitoring Systems Laboratory, Las Vegas, NV (United States)

    1993-12-31

    The Environmental Radioactivity Intercomparison Program described herein provides quality assurance support for laboratories involved in analyzing public drinking water under the Safe Drinking Water Act (SDWA) Regulations, and to the environmental radiation monitoring activities of various agencies. More than 300 federal and state nuclear facilities and private laboratories participate in some phase of the program. This presentation describes the Intercomparison Program studies and matrices involved, summarizes the precision and accuracy requirements of various radioactive analytes, and describes the traceability determinations involved with radioactive calibration standards distributed to the participants. A summary of program participants, sample and report distributions, and additional responsibilities of this program are discussed.

  2. National infrastructure for detecting, controlling and monitoring radioactive materials

    International Nuclear Information System (INIS)

    Othman, I.

    2001-01-01

    Full text: The Atomic Energy Commission of Syria (AECS) has the direct responsibility to assure proper safety for handling, accounting for and controlling of nuclear materials and radioactive sources which based on a solid regulatory infrastructure , its elements contains the following items: preventing, responding, training, exchanging of information. Based on the National Law for AECS's Establishment no. 12/1976, a Ministerial Decree for Radiation Safety no. 6514 dated 8.12.1997, issued by the Prime Minister. This Decree authorizes the Syrian Atomic Energy Commission to regulate all kinds of radiation sources. It fulfills the basic requirements of radiation protection and enforce the rules and regulations. The Radiation and Nuclear Regulatory Office (RNRO) is responsible for preparing all the draft regulations. In 1999 the General Regulations for Radiation Protection was issued by the Director General of the AECS, under Decision no. 112/99 dated 3.2.1999. It is based on an IAEA publication, Safety Series no. 115 (1996), and adopted to meet the national requirements. Syria has nine Boarding Centers seeking to prevent unauthorized movement of nuclear material and radioactive sources in and out side the country. They are related to the Atomic Energy Commission (AECS), and are located at the main entrances of the country. Each is provided with the practical tools and equipment in order to assist Radiation Protection Officers (RPO) in fulfilling their commitments, by promoting greater transparency in legal transfers of radioactive materials and devices. They apply complete procedures for the safe import, export and transit of radioactive sources. The RPOs provide authorizations by issuing an entry approval document, after making sure that each concerned shipments has an authorized license from the Syrian Regulatory Body (RNRO) before permitting shipments to leave, arrive or transit across their territory, enabling law enforcement to track the legal movement of

  3. Radioactive elements in Pennsylvania waters

    International Nuclear Information System (INIS)

    Rose, A.W.

    1990-01-01

    The first recognition of radioactive elements in natural waters dates back many years, but interest has accelerated in recent years with the advent of concern about the health effects of radioactivity. At the present time, extensive monitoring of public water supplies for radioactive substances is mandated by federal and state law, and monitoring near nuclear facilities is required by federal regulations, so that a great deal of information is accumulating on the amount and distribution of radioactivity in natural waters. These results reveal that small amounts of radioactive elements are universally present in natural waters, and that the concentration vary over an appreciable range as a result of natural processes and human activities. The purpose of this paper is to summarize the origin, behavior, abundance and hazard of the main radioactive species in Pennsylvania surface and ground waters. This treatment is intended to provide background to the interested reader in comprehending questions such as the hazard of radon in homes with private wells and pollution related to the nuclear power cycle

  4. Study of radioactivity among te Bulgarian Black Sea coastal zone - results from the NIMH monitoring program

    Energy Technology Data Exchange (ETDEWEB)

    Veleva, B.; Kolarova, M.; Mungov, G. [National Institute of Meteorology and Hydrology, Bulgarian Academy of Sciences, Sofia (Bulgaria)

    2011-07-01

    In the frame of the NIMH at BAS investigations of the Black sea radioactivity were initiated in 1978 with a development of a monitoring campaign. Samples of sea waters, sediments and algae were collected from several sampling sites along the coastal zone and measured by gamma-spectrometry. Results on gamma-emitting radio-nuclide's measurements in the Black sea coastal waters were published in the 80's. After the Chernobyl accident during the period between 1986-1989 seasonal-fields sampling campaigns were organised and radioactivity of algae and bottom sediments was estimated. Harmonized sampling strategies, analytical procedures and related data information exchange for radioactivity of seawater, sediment and biota in coastal areas of Black Sea countries were developed under the IAEA TCP Black Sea Project. The present work reports results of the monitoring programme of the NIMH of Bulgaria developed in the frame of the IAEA projects for the Black Sea basin. From 1993 to 2005 regular seasonal sampling was performed in 5 sampling sites along the Bulgarian Black Sea shore. Results of the dissolved '1'3'7Cs concentrations in sea water, sand, algae, and fish samples are discussed. The data for the different radio-isotopes measured in algae, fish and sea sediment samples are given in comparison with other investigations. A complex assessment of Cs-137 concentrations as important tracer and indicator of the marine processes is made on a long-term basis. (author)

  5. Study of radioactivity among te Bulgarian Black Sea coastal zone - results from the NIMH monitoring program

    International Nuclear Information System (INIS)

    Veleva, B.; Kolarova, M.; Mungov, G.

    2011-01-01

    In the frame of the NIMH at BAS investigations of the Black sea radioactivity were initiated in 1978 with a development of a monitoring campaign. Samples of sea waters, sediments and algae were collected from several sampling sites along the coastal zone and measured by gamma-spectrometry. Results on gamma-emitting radio-nuclide's measurements in the Black sea coastal waters were published in the 80's. After the Chernobyl accident during the period between 1986-1989 seasonal-fields sampling campaigns were organised and radioactivity of algae and bottom sediments was estimated. Harmonized sampling strategies, analytical procedures and related data information exchange for radioactivity of seawater, sediment and biota in coastal areas of Black Sea countries were developed under the IAEA TCP Black Sea Project. The present work reports results of the monitoring programme of the NIMH of Bulgaria developed in the frame of the IAEA projects for the Black Sea basin. From 1993 to 2005 regular seasonal sampling was performed in 5 sampling sites along the Bulgarian Black Sea shore. Results of the dissolved '1'3'7Cs concentrations in sea water, sand, algae, and fish samples are discussed. The data for the different radio-isotopes measured in algae, fish and sea sediment samples are given in comparison with other investigations. A complex assessment of Cs-137 concentrations as important tracer and indicator of the marine processes is made on a long-term basis. (author)

  6. Working safely with radioactive materials

    International Nuclear Information System (INIS)

    Davies, Wynne

    1993-01-01

    In common with exposure to many other laboratory chemicals, exposure to ionising radiations and to radioactive materials carries a small risk of causing harm. Because of this, there are legal limits to the amount of exposure to ionising radiations at work and special rules for working with radioactive materials. Although radiation protection is a complex subject it is possible to simplify to 10 basic things you should do -the Golden Rules. They are: 1) understand the nature of the hazard and get practical training; 2) plan ahead to minimise time spent handling radioactivity; 3) distance yourself appropriately from sources of radiation; 4) use appropriate shielding for the radiation; 5) contain radioactive materials in defined work areas; 6) wear appropriate protective clothing and dosimeters; 7) monitor the work area frequently for contamination control; 8) follow the local rules and safe ways of working; 9) minimise accumulation of waste and dispose of it by appropriate routes, and 10) after completion of work, monitor, wash, and monitor yourself again. These rules are expanded in this article. (author)

  7. Assessment of low levels of radioactive contamination

    International Nuclear Information System (INIS)

    Gray, P.W.

    1988-01-01

    This report describes a general methodology for the verification and clearance of sites contaminated with radioactive materials; general expressions for the risk or health detriment are derived. Techniques are developed, using Bayesian decision theory, to optimize the resources allocated to a site monitoring procedure, and to construct the probability distribution of the spatial distribution of specific activity within a site. A technique is also developed to determine the probability that a localized source of specified characteristics will not be detected by the monitoring procedure employed. The application of these techniques is illustrated by means of simple examples. This report confirms that a very large number of measurements are needed if a source of localized activity is to be detected with a high probability, and demonstrates how prior information about past radiological practices might be used to increase the probability of detection. Proposals are made for a programme of research to determine whether or not representative sites can be verified using current measuring techniques. (author)

  8. Natural and artificial radioactivity in the area of the Mochovce regional radioactive waste store

    International Nuclear Information System (INIS)

    Bezak, J.; Daniel, J.; Moravek, J.

    2000-01-01

    The results of monitoring of natural and artificial radioactivity in the area of the Mochovce regional radioactive waste store before commission are presented. The concentrations of uranium, thorium, potassium, and cesium, as well as radon volume activity were measured

  9. An On-Line Water Monitor for Low Level {beta}-Radioactivity Measurements

    Energy Technology Data Exchange (ETDEWEB)

    Quirk, E J.M.

    1968-05-15

    A detection system is described for the continuous monitoring of {beta}-radioactivity in the secondary cooling water at the Studsvik R2 reactor. Radiation emanating from a water surface is measured by a large area gas proportional detector. To protect the detector from splash caused by bursting bubbles a protective film and heater assembly is interposed between the detector and the water surface. A special feature is the programmed 'exercise' sequence for the magnetic valves which eliminates a tendency for them to stick after prolonged periods of idleness. The extent to which contamination affects the background counting rate has been studied. It is shown that for the duration of the tests described the monitor remains free from the effects of contamination so long as the scaler live time is suitably chosen. Minimum measurable specific activities obtainable in practice extend from 4 x 10{sup -6} to 3.86 x 10{sup -8} Ci/m{sup 3} depending on the {beta} end-point energy in the range 167 keV - 2.26 MeV.

  10. Radioactivity in food and the environment, 1996

    International Nuclear Information System (INIS)

    1997-09-01

    This report continues the series which combines the results of the radioactivity monitoring programmes previously published by MAFF in two documents: the 'Terrestrial Radioactivity Monitoring Programme (TRAMP) Report: Radioactivity in food and agricultural products in England and Wales' and the 'Aquatic Environment Monitoring Report: Radioactivity in surface and coastal waters of the British Isles' (AEMR). For the first time the report includes the results of all environmental monitoring for radioactivity carried out on behalf of the regulatory authority in Scotland. These results were previously presented in the 'Statistical Bulletin: Environmental Monitoring for Radioactivity in Scotland' (e.g. The Scottish Office, (1996). Measurements in 1996 included the analysis of samples of food and other materials from the environment and detection of beta and gamma dose rates in the environment. The results show that radionuclide concentrations and radiation dose rates were generally similar to those in 1995. However, near Sellafield, despite the general downward trend in disposals from the site during 1996, there were some increases in concentrations of technetium-99 and carbon-14 in marine foodstuffs reflecting disposals from and operations on the site in previous years. These operations included processing of stored wastes and the operation of the Enhanced Actinide Removal Plant (EARP). The Thermal Oxide Reprocessing Plant (THORP) continued its commissioning phase in 1996 and its disposals had little effect on food and the marine environment. The results of the monitoring have been interpreted in terms of public radiation exposures using data on activity levels in food and local surveys to establish potential 'critical groups' of people likely to be most exposed. (author)

  11. Radioactivity in the environment. Report for 2001 : a summary and radiological assessment of the Environment Agency's monitoring programmes

    International Nuclear Information System (INIS)

    2003-01-01

    RSA 93 authorisations. Radiological monitoring programmes are carried out in support of the Agency's regulatory functions under RSA 93 and as part of the UK Government's obligations under the Euratom Treaty. This report presents the results of the Agency's regular monitoring of radioactivity in the environment during 2001 and an assessment of the radiological impact. The main findings of the regular monitoring programme during 2001 were as follows: The majority of operator declarations of the radioactive content of waste discharges and disposals had been assessed accurately or were over-estimate; Radiation dose rates above sediments and concentrations of radionuclides in water, sediment, soil and grass were generally consistent with those reported in previous years. Enhanced levels of artificial radionuclides continue to be found in coastal sediments in the vicinity of Sellafield, which decline with increasing distance from the site. Radioactivity levels around other major sites were mostly low or not detectable; As in previous years, concentrations of radionuclides in samples of airborne dust and rainwater from seven locations in the UK were very low or undetectable; Water from all 31 monitored sources of drinking water in England and Wales, except one in Derbyshire, were consistently below the World Health Organisation (WHO) drinking water screening levels. The enhanced level of uranium in the Derbyshire water is due to the natural levels of uranium in the local geology, and is insignificant from a radiological point of view. Assessments of doses that might be received by members of the public from drinking water and occupation of beaches, inter-tidal areas and river banks around nuclear and major non-nuclear sites were made. In all cases, doses were less than the annual dose limit for members of the public of 1000 microsieverts (1000 μSv). Houseboat dwellers on the Ribble Estuary in Lancashire received the highest total annual dose of 142 μSv. This is due to

  12. Simulated minimum detectable activity concentration (MDAC) for a real-time UAV airborne radioactivity monitoring system with HPGe and LaBr_3 detectors

    International Nuclear Information System (INIS)

    Tang, Xiao-Bin; Meng, Jia; Wang, Peng; Cao, Ye; Huang, Xi; Wen, Liang-Sheng; Chen, Da

    2016-01-01

    An automatic real-time UAV airborne radioactivity monitoring system with high-purity germanium (HPGe) and lanthanum bromide (LaBr_3) detectors (NH-UAV) was developed to precisely obtain small-scope nuclide information in major nuclear accidents. The specific minimum detectable activity concentration (MDAC) calculation method for NH-UAV in the atmospheric environment was deduced in this study for a priori evaluation and quantification of the suitability of NH-UAV in the Fukushima nuclear accident, where the MDAC values of this new equipment were calculated based on Monte Carlo simulation. The effects of radioactive source term size and activity concentration on the MDAC values were analyzed to assess the detection performance of NH-UAV in more realistic environments. Finally, the MDAC values were calculated at different shielding thicknesses of the HPGe detector to improve the detection capabilities of the HPGe detector, and the relationship between the MDAC and the acquisition time of the system was deduced. The MDAC calculation method and data results in this study may be used as a reference for in-situ radioactivity measurement of NH-UAV. - Highlights: • A real-time UAV airborne radioactivity monitoring system (NH-UAV) was developed. • The efficiency calculations and MDAC values are given. • NH-UAV is able to monitor major nuclear accidents, such as the Fukushima accident. • The source term size can influence the detection sensitivity of the system. • The HPGe detector possesses measurement thresholds on activity concentration.

  13. Radioactivity measurements and control solutions

    International Nuclear Information System (INIS)

    Bartos, D.; Ciobanu, M.; Constantin, F.; Petcu, M.; Rusu, Al.

    2003-01-01

    In our department, in the last years, a new line of production has been developed devoted to the radioactivity measurements (portal monitor, gamma source detector, neutron monitor). Instruments of different design (hand-held, portals or steady-state) are intended for detection and locating of radioactive sources. Monitors are intended to detect radioactive and special nuclear materials in vehicles, pedestrians, luggage, as well as for illegal traffic prevention of radioactive sources. Monitors provide audio and visual alarm signals when radioactive and/or special nuclear materials are detected. Neutron dosimeters are designed for the determination of dose equivalent rate around neutron generators or sources. All devices can be recommended for use to officers of customs, border guard and emergency services, civil defense, fire brigades, police and military departments, nuclear research or power facilities. Incorporating micro controllers and new design, our products span almost all the spectra of radioactivity detection (gamma, beta, X and neutrons). No special knowledge is needed to operate these instruments as all service functions are performed automatically (self-tests, background updating and threshold calculation). The Portal monitor is intended to be a checkpoint in contamination control or in unauthorized traffic of radioactive materials. The portal monitor can be installed both in open, unprotected to environmental conditions areas or in enclosed areas. It may be used at pedestrian cross border points, at check points of Nuclear Power Plants, enterprises of nuclear industry, weapons manufacturing and storage plants, nuclear waste disposal and storage sites, at the entrances to steel plants, the post-offices and airports, the governmental offices, banks, private companies etc. The monitor provides audio alarming signals when radioactive and/or special nuclear materials are detected. The monitor consists in a portal frame, which sustains 5 detectors. Each

  14. Recommendations for Additional Design Development of Components for the SpinTek Rotary Microfilter Prior to Radioactive Service

    International Nuclear Information System (INIS)

    Herman, D.T.

    2004-01-01

    The SpinTek rotary microfilter is being considered as an alternative to crossflow filtration. Prior testing evaluated the vendor's standard design for a 1-disk and 3-disk design. We noted several areas of improvement during the testing of the two filter systems that can be included in the 25-disk plant size unit.This report outlines several potential enhancements and improvements to the vendor's standard design which would extend the lifetime of the unit and increase the ability to perform maintenance for units deployed in radioactive service. The enhancements proposed in this report can be implemented to the current design with minimal impact to the cost and schedule of the purchase of the standard unit. An example of this is the replacement of the current mechanical seal with a bellows seal. The improvements proposed will require an extensive redesign of components found in the current system such as the filter chamber

  15. Radioactivity measurements

    International Nuclear Information System (INIS)

    Schwach, G.

    1986-01-01

    This is an overview of radioactivity monitoring work done in the Austrian Research Centre Seibersdorf in the wake of the Chernobyl accident. It consists of air, rainwater, food and personnel monitoring. Additional services to the public are: information and development of a database and a computer code for predicting future radionuclide concentration in air, soil, water and food. (G.Q.)

  16. 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.)

  17. Radioactivity monitoring of the Irish marine environment 1996 and 1997

    International Nuclear Information System (INIS)

    Long, S.; Pollard, D.; Hayden, E.; Smith, V.; Fegan, M.; Ryan, T.P.; Dowdall, A.; Cunningham, J.D.

    1998-07-01

    This report presents the results of the marine radioactivity monitoring programme carried out be the Radiological Protection Institute of Ireland (RPII) during 1996 and 1997. The primary objective of the programme is to assess the exposure to the Irish population resulting from radioactive contamination of the Irish marine environment and to estimate the risks to health from this exposure. Discharges from the British Nuclear Fuels (BNFL) reprocessing plant at Sellafield continue to be the principal source of this contamination. Approximately 300 samples of fish, shellfish, seaweed, seawater and sediment were collected each year. The samples were analysed for a range of contaminating radionuclides at the Institute's radioanalytical laboratory. The results show that the radionuclide of greatest dosimetric significance continues to be caesium-137. Since 1994 the commissioning and operation of new facilities at Sellafield have resulted in an increase in the discharges of technetium-99 to the Irish Sea. This has been reflected in an increase in the activity concentration of this radionuclide at all east coast sampling sites during the reporting period. The main pathway contributing to the exposure of the Irish public is the consumption of seafood. The committed effective dose to heavy consumers of seafood due to artificial radionuclides in 1996 was 1.6 μSv and in 1997 was 1.4 μSv. in 1996 was 1.6 μSv and in 1997 was 1.4 μSv

  18. Transporting radioactive rock

    International Nuclear Information System (INIS)

    Pearce, G.

    1990-01-01

    The case is made for exempting geological specimens from the IAEA Regulations for Safer Transport of Radioactive Materials. It is pointed out that many mineral collectors in Devon and Cornwall may be unwittingly infringing these regulations by taking naturally radioactive rocks and specimens containing uranium ores. Even if these collectors are aware that these rocks are radioactive, and many are not, few have the necessary equipment to monitor the activity levels. If the transport regulations were to be enforced alarm could be generated and the regulations devalued in case of an accident. The danger from a spill of rock specimens is negligible compared with an accident involving industrial or medical radioactive substances yet would require similar special treatment. (UK)

  19. Monitoring of radioactivity in foodstuffs: experience gained and recommendations

    International Nuclear Information System (INIS)

    Mamoon, A.M.; Abdulfattah, A.F.; Abulfaraj, W.H.; Abdul-Majid, S.; Al-Johani, M.; Abubakar, K.M.

    1988-01-01

    The Chernobyl reactor accident released large amounts of radioactivity that was carried by winds across international boundaries. Soils and surface waters as well as vegetation and grazing animals in neighbouring countries to the Soviet Union were subject to radioactive contamination in various degrees. Saudi Arabia imports much of its foodstuffs from European countries and about 75% of the imported foodstuffs come through western ports of the country. Hence the Government of Saudi Arabia took appropriate measures to ensure safety of imported foodstuffs. King Abdulaziz University (KAU) was directed by the government at about mid-June 1986, to carry out radioactivity inspections of food items reaching Jeddah, Yanbu and Jizan seaports as well as food arrivals at King Abdulaziz International Airport at Jeddah. Parallel responsibilities were assigned to other universities and King Abdulaziz City for Science and Technology, for radioactivity inspections of imported foodstuffs reaching ports or inlets in their respective areas. In applying the measures and controls enacted by the government against importation of radioactively contaminated foodstuffs, much management experience was acquired and some of it is rather unique to Saudi Arabia

  20. Environmental radioactivity survey in Andong area

    Energy Technology Data Exchange (ETDEWEB)

    Yoon, Zi Hong; Jo, Kum Ju [Andong Regional Radioactivity Monitoring Station, Andong National Univ., Andong (Korea, Republic of)

    2001-12-15

    The objectives of the project are to monitor an abnormal level in Andong area and to provide a base-line data on environmental radiation/radioactivity levels in case of any radiological emergency situation. The project is important in view of protecting the public health from the potential hazards of radiation and keeping up the clean environment. This report summarizes and interprets environmental radiation/radioactivity monitoring samples Gamma exposure rates, airborne dust, precipitation, fall-out and drinking-water. Environmental samples : vegetables, fishes/shellfishes, fruits, starch and starch roots and drinking waters. Among the all 2001 radiological monitoring and environmental data in Andong area were not found the extraordinary data. And a nation-wide environmental radiation/radioactivity level survey results were all background levels attributed to terrestrial and cosmic radiation.

  1. The new German regulatory system of monitoring workers for intakes of radioactivity with special reference to thorium

    International Nuclear Information System (INIS)

    Henrichs, K.

    1995-01-01

    In Germany, the Association for Radiation Protection (member of IRPA) defined a new standard for the monitoring of workers occupationally exposed to radioactive material. During the last two years this draft has been accepted by the German government in the form of three directives. The purpose of our approach was the installation of a system defining clear criteria for the necessity of regular and special monitoring programs, giving directives for monitoring programs ensuring that dose assessments are as reliable as necessary with the lowest possible expenses, standardizing as far as possible the procedures of dose assessments, and guaranteeing the necessary quality standards. The most important features of these regulations will be discussed in this contribution and their application will be exemplified for the specially difficult monitoring of thorium intakes. (author). 2 figs., 2 tabs

  2. Radioactivity in waters in SR Slovenia

    International Nuclear Information System (INIS)

    Kobal, I.; Mihailovic, M.; Shkofljanec, M.; Zhlebnik, L.; Drobne, F.

    1977-12-01

    The radioactivity of samples of rivers Brebovscica and Sava with its contributaries was monitored. The Brebovscica was found to have an enchanced radioactivity due to the geological and mining excavations in the uranium mine Zirovski vrh. This radioactivity is lowered by a dillution in the Poljanska Sora where the radioactive contamination has been hardly detected. The radioactivity in the Sava is relatively low though a few places with enchanced values were found may be due to radioactive pollutants from conventional industries. But this ought to be confirmed in the future

  3. Testing of In-Line Slurry Monitors and Pulsair Mixers with Radioactive Slurries

    Energy Technology Data Exchange (ETDEWEB)

    Hylton, T.D.; Bayne, C.K.

    1999-08-01

    Three in-line slurry monitoring instruments were demonstrated, tested, and evaluated for their capability to determine the transport properties of radioactive slurries. The instruments included the Endress + Hauser Promass 63M Coriolis meter for measuring density, the Lasentec M600P for measuring particle size distribution, and a prototype ultrasonic monitor that was developed by Argonne National Laboratory for measuring suspended solids concentration. In addition, the power consumption of the recirculation pump was monitored to determine whether this parameter could be used as a tool for in-line slurry monitoring. The Promass 63M and the M600P were also evaluated as potential indicators of suspended solids concentration. In order to use the Promass 63M as a suspended solids monitor, the densities of the fluid phase and the dry solid particle phase must be known. In addition, the fluid phase density and the dry solids density must remain constant, as any change will affect the correlation between the slurry density and the suspended solids concentration. For the M600P, the particle size distribution would need to remain relatively constant. These instruments were demonstrated and tested at the Gunite and Associated Tanks Remediation Project at the Oak Ridge National Laboratory. The testing of the instruments was conducted in parallel with the testing of a Pulsair mixing system, which was used to mix the contents of the selected tank. A total of six tests were performed. A submersible pump was positioned at two depths, while the Pulsair system was operated at three mixing rates.

  4. A case study on determining air monitoring requirements in a radioactive materials handling area

    International Nuclear Information System (INIS)

    Newton, G.J.; Bechtold, W.E.; Hoover, M.D.; Ghanbari, F.; Herring, P.S.; Jow, Hong-Nian

    1993-01-01

    A technical, defensible basis for the number and placement of air sampling instruments in a radioactive materials handling facility was developed. Historical air sampling data, process and physicochemical knowledge, qualitative smoke dispersion studies with video documentation, and quantitative trace gas dispersion studies were used to develop a strategy for number and placement of air samplers. These approaches can be used in other facilities to provide a basis for operational decisions. The requirements for retrospective sampling, personal sampling, and real-time monitoring are included. Other relevant operational decisions include selecting the numbers, placement, and appropriate sampling rates for instruments, identifying areas of stagnation or recirculation, and determining the adequacy and efficiency of any sampling transport lines. Justification is presented for using a graded approach to characterizing the workplace and determining air sampling and monitoring needs

  5. Generating acceptability of PNRI environmental radioactivity monitoring studies at the former ammunition dump area in Clark special economic zone

    International Nuclear Information System (INIS)

    Garcia, Teofilo Y.

    2002-11-01

    The rejection of the 1991 Treaty of Friendship and Cooperation, which sought to extend the military bases agreement (MBA), paved the way for the Americans to abandon Clark Air Base in Angeles, Pampanga, which had served as an American military base since 1947. The total and immediate pullout of the Americans left the base in an ''as is'' condition and without the benefits of restoration efforts. Various studies and reports have been conducted to determine the presence of hazardous wastes in the former Clark Air Base. The issue of hazardous wastes purportedly left there by the Americans is a continuing and a growing concern particularly of citizens living within its area. The Philippine Nuclear Research Institute (PNRI) In November of 1997 and in April of 1998, the Philippine Nuclear Research Institute PNRI, upon the request of Clark Development Corporation, conducted a thorough radiological monitoring in CSEZ in order to determine the presence of radioactive contamination. Radioactive materials such as cesium-137 and tritium are considered hazardous wastes. Results of monitoring showed that radiation levels in CSEZ were within allowable standards. This means that the workers and residents at the Clark Air Base ( t he base ) are free from dangers of exposure to radiation. Despite the findings, however, reports by the media and environmental NGOs on the presence of hazardous wastes, including radioactive wastes, in Clark have proliferated. This action plan and project (APP) intends to address the issue of environmental radioactivity contamination (if any) within the CSEZ. The APP results are geared towards dispelling the persistent fear of the public in general, and the base stakeholders especially its residents, in particular, regarding the presence of radioactive contamination which results in untoward health effects to those exposed to such contaminants. Thus, the sectoral concern of this APP is to heighten the level of social acceptability by the base

  6. Generating acceptability of PNRI environmental radioactivity monitoring studies at the former ammunition dump area in Clark special economic zone

    Energy Technology Data Exchange (ETDEWEB)

    Garcia, Teofilo Y

    2002-11-01

    The rejection of the 1991 Treaty of Friendship and Cooperation, which sought to extend the military bases agreement (MBA), paved the way for the Americans to abandon Clark Air Base in Angeles, Pampanga, which had served as an American military base since 1947. The total and immediate pullout of the Americans left the base in an ''as is'' condition and without the benefits of restoration efforts. Various studies and reports have been conducted to determine the presence of hazardous wastes in the former Clark Air Base. The issue of hazardous wastes purportedly left there by the Americans is a continuing and a growing concern particularly of citizens living within its area. The Philippine Nuclear Research Institute (PNRI) In November of 1997 and in April of 1998, the Philippine Nuclear Research Institute PNRI, upon the request of Clark Development Corporation, conducted a thorough radiological monitoring in CSEZ in order to determine the presence of radioactive contamination. Radioactive materials such as cesium-137 and tritium are considered hazardous wastes. Results of monitoring showed that radiation levels in CSEZ were within allowable standards. This means that the workers and residents at the Clark Air Base ({sup t}he base{sup )} are free from dangers of exposure to radiation. Despite the findings, however, reports by the media and environmental NGOs on the presence of hazardous wastes, including radioactive wastes, in Clark have proliferated. This action plan and project (APP) intends to address the issue of environmental radioactivity contamination (if any) within the CSEZ. The APP results are geared towards dispelling the persistent fear of the public in general, and the base stakeholders especially its residents, in particular, regarding the presence of radioactive contamination which results in untoward health effects to those exposed to such contaminants. Thus, the sectoral concern of this APP is to heighten the level of social acceptability by the base

  7. The Perennial Environment Observatory by A.N.D.R.A. (the French National Radioactive Waste Management Agency)

    International Nuclear Information System (INIS)

    Leclerc, E.

    2010-01-01

    The Perennial Environment Observatory [Observatoire Perenne de l'Environnement - OPE] is a unique approach and infrastructure developed and implemented by ANDRA, the French National Radioactive Waste Management Agency, as part of its overall project of deep geological disposal for radioactive waste. Its current mission is to assess the initial state of the rural (forest, pasture, open-field and aquatic) environment, prior to repository construction. This will be followed in 2017 (pending construction authorizations) and for a period exceeding a century, by monitoring of any impact the repository may have on the environment. In addition to serving its own industrial purpose of environmental monitoring, ANDRA also opens the OPE approach, infrastructure and acquired knowledge (database...) to the scientific community to support further research on long term evolution of the environment subjected to natural and anthropogenic stresses, and to contribute to a better understanding of the interaction between the various compartments of the environment. (author)

  8. The challenge and countermeasure for radioactivity monitor in ocean--the reflection derived from Fukushima nuclear power plant accident

    International Nuclear Information System (INIS)

    Liu Guangshan

    2014-01-01

    Environmental radioactivity monitor (ERM) follows with interest raising level, sink and transportation of radioactive materials in the environment. There are two kinds of challenges for marine radioactivity monitor (MRM), for which one concerned with facilities and methods that lead the very difficult measurement of MRM. Up to now, the bulk of sample must collected and prepared for most MRM by radiometry (counting method) and long acquisition period is needed. The long time from sampling to derived results postponed the time of the scientists and government officials learning contamination distribution information. Developing accelerator mass spectrometry (AMS) can overcome above difficulty because AMS method need one tenth of sample and one tenth measuring time needed by radiometric method. The second challenge is lack of the behavior research of radionuclide in the ocean. In the ocean, radionuclide behavior is constrained by physical and biogeochemical process, following that the radionuclides are transported from released sea area to where far from source area, from upper water to deep and bottom waters, and buried to sediment. There are some reports about radionuclide transportation with physical oceanographical process, but few paper about radionuclide biogeochemistry has been found. Lesser theory knowledge and lesser investigation data make scientists worked on MRM puzzling. The radionuclide behavior in the ocean can be studied by the method used in marine biogeochemistry. (author)

  9. Groundwater monitoring and modelling of the “Vector” site for near-surface radioactive waste disposal in the Chornobyl exclusion zone

    Directory of Open Access Journals (Sweden)

    D. Bugai

    2017-12-01

    Full Text Available Results of purposeful groundwater monitoring and modelling studies are presented, which were carried out in order to better understand groundwater flow patterns from the “Vector” site for near-surface radioactive waste disposal and storage in the Chornobyl exclusion zone towards river network. Both data of observations at local-scale monitoring well network at “Vector” site carried out in 2015 - 2016 and modelling analyses using the regional groundwater flow model of Chornobyl exclusion zone suggest that the groundwater discharge contour for water originating from “Vector” site is Sakhan River, which is the tributary to Pripyat River. The respective groundwater travel time is estimated at 210 - 340 years. The travel times in subsurface for 90Sr, 137Cs, and transuranium radionuclides (Pu isotopes, 241Am are estimated respectively at thousands, tenths of thousands, hundreds of thousands – million of years. These results, as well as presented data of analyses of lithological properties of the geological deposits of the unsaturated zone at “Vector” site, provide evidence for good protection of surface water resources from radioactivity sources (e.g., radioactive wastes to be disposed in the near-sursface facilities at “Vector” site.

  10. Classification of Radioactive Waste. General Safety Guide

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2009-11-15

    This publication is a revision of an earlier Safety Guide of the same title issued in 1994. It recommends revised waste management strategies that reflect changes in practices and approaches since then. It sets out a classification system for the management of waste prior to disposal and for disposal, driven by long term safety considerations. It includes a number of schemes for classifying radioactive waste that can be used to assist with planning overall national approaches to radioactive waste management and to assist with operational management at facilities. Contents: 1. Introduction; 2. The radioactive waste classification scheme; Appendix: The classification of radioactive waste; Annex I: Evolution of IAEA standards on radioactive waste classification; Annex II: Methods of classification; Annex III: Origin and types of radioactive waste.

  11. Classification of Radioactive Waste. General Safety Guide

    International Nuclear Information System (INIS)

    2009-01-01

    This publication is a revision of an earlier Safety Guide of the same title issued in 1994. It recommends revised waste management strategies that reflect changes in practices and approaches since then. It sets out a classification system for the management of waste prior to disposal and for disposal, driven by long term safety considerations. It includes a number of schemes for classifying radioactive waste that can be used to assist with planning overall national approaches to radioactive waste management and to assist with operational management at facilities. Contents: 1. Introduction; 2. The radioactive waste classification scheme; Appendix: The classification of radioactive waste; Annex I: Evolution of IAEA standards on radioactive waste classification; Annex II: Methods of classification; Annex III: Origin and types of radioactive waste

  12. The development of gate monitor for low level radioactive waste

    International Nuclear Information System (INIS)

    Fujisawa, Morio; Watanabe, Michito; Kato, Tatsuo

    1994-01-01

    Low-level radioactive waste (LLW) generated from nuclear power plants in Japan, have been deposited in the yard of each power plant. At present, it is stored in about 500,000 drum cans (200l each). These drum cans are carried to Mutsu-ogawara Port by special transport ships and then transferred to Rokkasho LLW transport trucks (special vehicles) for storage. The gate monitor is used to automatically measure the dose rate on the vehicles loaded with transport vessels from a remote location, to ensure the safe transportation from Mutsu-ogawara Port the Burying Center. It is a new system which has been developed for effective measurement of dose rate on a number of transport vessels in a short time. This system is the first in the world for measuring dose rate on vehicles. Such a system cannot be found in any country of the world. (author)

  13. Monitoring a repository for high-level radioactive waste in Germany. Possibilities and limits

    International Nuclear Information System (INIS)

    Jobmann, M.; Haverkamp, B.; Eilers, G.

    2011-01-01

    Pursuant to the new BMU safety requirements of September 2010 imposed upon the final storage of radioactive waste generating heat, the operator of a repository in Germany must establish a monitoring program which furnishes relevant measured information during the operations phase and for a defined period of time after closure of the repository. Within the framework of a feasibility study, an assessment basis was established to show in what format information about the status of a closed repository mine could be obtained technically without impairing the safety of barriers, for instance, by cable ducts. As a conceptual design basis, processes and measured quantities relevant to monitoring were attributed to the components of the current safety demonstration concept. For one model variant, monitoring possibilities of these processes were shown on the basis of monitoring modules. Some first experiments are being carried out in European underground laboratories about the use of wireless transmission systems in the repository area. On the basis of those activities, experiments could also be designed in the German exploratory mine of Gorleben in order to examine to what extent information obtained by monitoring could be transmitted in a wireless mode in rock salt formations. As far as the autonomous supply of electricity to measurement systems is concerned, which must be guaranteed on a long-term basis, there is now a possibility of using thermoelectric isotope generators or betavoltaic batteries. (orig.)

  14. Hyperthyroidism and radioactive iodine

    International Nuclear Information System (INIS)

    Corstens, F.H.M.

    1980-01-01

    The study details the results of treatment of patients with hyperthyroidism using a combination of fractionated low doses radioactive iodine and anthithyroid drug therapy. The patients studied were treated according to this regimen after August 1968 and all reached euthyroidism before March 1979. None of the patients had been treated with radioactive iodine prior to the start of the protocol. A subgroup of the patients had received an unsuccessfull course with antithyroid drug therapy and, or, surgical therapy before the start of the protocol. Patients who had never been treated for hyperthyroidism were given antithyroid drug therapy for at least 6 months in an attempt to reach euthryroidism without the use of 131 I therapy. Therefore, all patients had experienced a course of unsuccessfull therapy prior to the start of the treatment protocol using combined fractionated low doses of 131 I and antithyroid drug therapy. (Auth.)

  15. Apparatus and method for radioactive waste screening

    Science.gov (United States)

    Akers, Douglas W.; Roybal, Lyle G.; Salomon, Hopi; Williams, Charles Leroy

    2012-09-04

    An apparatus and method relating to screening radioactive waste are disclosed for ensuring that at least one calculated parameter for the measurement data of a sample falls within a range between an upper limit and a lower limit prior to the sample being packaged for disposal. The apparatus includes a radiation detector configured for detecting radioactivity and radionuclide content of the of the sample of radioactive waste and generating measurement data in response thereto, and a collimator including at least one aperture to direct a field of view of the radiation detector. The method includes measuring a radioactive content of a sample, and calculating one or more parameters from the radioactive content of the sample.

  16. Applicability of a generic monitoring program for radioactive waste burial grounds at Oak Ridge National Laboratory and Idaho National Engineering Laboratory

    International Nuclear Information System (INIS)

    1978-07-01

    Six burial grounds were evaluated at Oak Ridge to determine which would be most suitable for testing the generic monitoring approach, and two were selected. Burial Ground 4 was chosen because it is known to be leaking radioactivity and a monitoring program is desirable to determine the source, pattern and extent of the leakage. Burial Ground 6 was chosen because the most complete radiologic and geologic data is available and modern burial practices have been utilized at this site. At the Idaho National Engineering Laboratory (INEL) only one burial ground exists, the Radioactive Waste Management Complex (RWMC). The data available on the burial grounds are insufficient for an adequate understanding of radionuclide migration patterns and accordingly, inadequate for the design of reliable monitoring programs. It was decided, therefore, that preliminary monitoring programs should be designed in order to obtain additional data for a later implementation of reliable monitoring programs. The monitoring programs designed for ORNL consist primarily of the installation of surface water monitoring stations, the surveillance of trench sump wells, a test boring program to study subsurface geologic conditions, a ground water sampling program and the installation of instrumentation, specifically infiltrometers and evaporation pans, to develop data on site water balances. The program designed for the INEL burial ground includes installation of trench sumps, a ground water monitoring program, test borings to further define subsurface geohydrologic conditions and the installation of instrumentation to develop data on the site water balance. The estimated costs of implementing the recommended programs are about $420,820 for monitoring Burial Grounds 4 and 6 at Oak Ridge and $382,060 for monitoring the RWMC at INEL. 12 figures

  17. Monitoring program for evaluating radionuclide emissions from incineration of low-level radioactive waste

    International Nuclear Information System (INIS)

    Wittmer, S.C.; Solomon, H.F.

    1984-01-01

    The implementation of an incineration program for low-level radioactive waste is a complex task, especially in the area of obtaining environmental permits. To provide assurance to the appropriate regulatory agencies involved with environmental permitting and others that an incineration program is properly conducted, emissions monitoring to identify radionuclides and their fate may be needed. An electronic spreadsheet software program Lotus 1-2-3 (Lotus Development Corporation) on an IBM Personal Computer has been used to perform data reduction for test results from such a monitoring program and to present them graphically to facilitate interpretation. The sampling technique includes: (1) the use of an EPA Method 5 stack sampling train modified to exclude the dry-catch filtration assembly with ethanolamine used to scrub incinerator gas at depressed temperatures and (2) a continuous composite liquid sampler for incinerator wet scrubber discharge to the sanitary sewer. Radionuclides in the samples are assayed using scintillation spectrometry

  18. A simple method for the verification of clearance levels for non-radioactive solid waste

    International Nuclear Information System (INIS)

    Holland, B.

    1997-01-01

    ANSTO's radiopharmaceutical production laboratories generate 25 m 3 of solid waste per month. Most of this waste is not radioactive. Up until recently the non-radioactive waste was cleared from the controlled area and stored for 10 halflives prior to disposal as normal solid refuse. To eliminate the storage and ''double handling'' of the large quantities of non-radioactive waste a simple clearance method was devised to allow direct disposal. This paper describes how clearance levels were determined. Here the term ''clearance level'' is used as a general term for the release of material regardless of whether it was previously subject to regulatory control. This contrasts with the IAEA definition of a clearance level and highlights a potential problem with the implementation of exemption levels to keep material out of regulatory control and the use of clearance levels to allow removal of materials from regulatory control. Several common hand held contamination monitors were tested to determine their limits of detection and ability to meet these clearance levels. The clearance method includes waste segregation and size limitation features to ensure the waste is monitored in a consistent manner, compatible with the limits of detection. The clearance levels achieved were subsequently found to be compatible with some of the unconditional clearance levels in IAEA-TECDOC-855 and the measurement method also meets the required features of that document. The ANSTO non-radioactive waste clearance system has been in operation for more than 12 months and has proved simple and effective to operate. Approximately 12m 3 of the solid waste is now been treated directly as normal solid refuse. This paper describes the ANSTO clearance system, the contamination monitor tests and details practical problems associated with the direct monitoring of solid waste, including averaging of the activity in the package. The paper also briefly highlights the potential problem with the use of

  19. Radioactivity monitoring within the environment of the Loire basin. A partnership between the IRSN and the Dampierre-en-Burly and Saint-Laurent CLIs at the service of citizen vigilance

    International Nuclear Information System (INIS)

    2008-01-01

    The first part of this report presents the Loire basin and its environment, discusses the physical-chemical quality control of its waters and the main usages of the Loire waters. It also presents the nuclear installations present in the Loire basin (electricity production nuclear power stations and other installations), the actors involved in radioactivity measurement in the Loire basin environment (IRSN, EDF, AREVA, associations for the monitoring of water quality, public services), and the national network for radioactivity measurement in the environment. The second part describes and reports the radioactivity monitoring of the environment in the Loire basin, i.e. in the atmosphere, in rain waters and in continental waters, and in the food chain. Addressing this monitoring activity, a last part discusses the evolution of measurements, the importance of the plurality of actors involved in sampling and measurement (in order to guarantee the monitoring system transparency), the variety of sources, the assessment of health impact

  20. Monitoring of gross beta radioactivities on water sample environment in the surrounding of kartini reactor at 2011

    International Nuclear Information System (INIS)

    Siswanti; Munandar, A. Aris

    2013-01-01

    Measurement of gross beta radioactivities on water environment were done in the PTAPB BATAN has a goal for routine monitoring, with the result that fill RPL has been made and the result equivalented with quality standard were decided by BAPETEN. The water sample taken as much as 2 liter at 18 area were definited on radius 100 m to 5000 m in the surrounding of kartini reactor, vaporin on electric stove till the volume been ± 10 ml, and than pick out to the aluminium planset and drying on hot plate. Sample in the plancet were counted with a Low Background Counter (LBC) for 30 minutes and accounted of gross beta radioactivity water system. The result of gross beta radioactivity water environment at 2011 has a lowest 009, ± 0,06 Bq/I on Tambak Bayan area at june and in the Janti area highest 0,39 ± 0,08 Bq/ at December. The result still under of quality standard were decided by SK BAPETEN. No. 02/Ka- BAPETEN/V-99 is 0,4 Bq/I. (author)

  1. Nuclear reactor monitoring device

    International Nuclear Information System (INIS)

    Mihashi, Ishi; Honma, Hitoshi.

    1993-01-01

    The monitoring device of the present invention comprises a reactor core/reactor system data measuring and controlling device, a radioactivity concentration calculation device for activated coolants for calculating a radioactivity concentration of activated coolants in a main steam and reactor water by using an appropriate physical model, a radioactivity concentration correlation and comparison device for activated coolants for comparing correlationship with a radiation dose and an abnormality alarm device. Since radioactivity of activated primary coolants is monitored at each of positions in the reactor system and occurrence of leakage and the amount thereof from a primary circuit to a secondary circuit is monitored if the reactor has secondary circuit, integrity of the reactor system can be ensured and an abnormality can be detected rapidly. Further, radioactivity concentration of activated primary circuit coolants, represented by 16 N or 15 C, is always monitored at each of positions of PWR primary circuits. When a heat transfer pipe is ruptured in a steam generator, leakage of primary circuit coolants is detected rapidly, as well as the amount of the leakage can be informed. (N.H.)

  2. Application of the UNECE Recommendations on Monitoring and Response Procedures for Radioactive Scrap Metal: From Theory to Practice

    Energy Technology Data Exchange (ETDEWEB)

    Magold, M.; Mansourian-Stephenson, S., E-mail: stephanie.mansourian-stephenson@unece.org [United Nations Economic Council for Europe, Geneva (Switzerland)

    2011-07-15

    The work of the United Nations Economic Commission for Europe (UNECE) in addressing the issue of radioactive material appearing inadvertently in scrap metal is summarized. After hosting several meetings of national and international representatives of the scrap metal industry and radiation protection experts, the UNECE issued recommendations in 2006 on Monitoring and Response Procedures for Radioactive Scrap Metal. Since then, the UNECE has been exploring, with its Member States, the extent to which the Recommendations have been utilized - by means of a questionnaire. In this paper the results of the questionnaire are presented and, on the basis of the results of the questionnaire, conclusions are drawn and recommendations made for international action in this field for the future. (author)

  3. 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

  4. Data acquisition system and analysis programme for environmental radioactivity monitoring

    International Nuclear Information System (INIS)

    Rajaram, S.; Kannan, V.; Hegde, A.G.

    2003-01-01

    Full text: In every Environmental Survey Laboratory (ESL) many nuclear radiation detecting instruments such as low level Gas Flow Beta Counting Systems, Gross Alpha Counting Systems, Gamma Counting Systems (Single Channel Analyser) are in use to detect the environmental radiation level. These instruments give output in terms of number (total pulse event counts), which is further manually converted into activity concentration per unit weight of the environmental samples. There is considerable difficulty and delay in obtaining the data, since calculations are done manually and also it is very difficult to maintain database of these results for future reference. In order to overcome all this difficulties a Data Acquisition System and Analysing Software Programme has been designed and developed. This paper describes the design and development of the Data Acquisition System using PCL-830 Counter Timer add on card, for networking the environmental radioactivity monitoring equipment's, which is under routine operation at ESL Kalpakkam

  5. Innovative characterization, monitoring and sensor technologies for environmental radioactivity at USDOE sites

    International Nuclear Information System (INIS)

    Hutter, A.; Weeks, S.

    2001-01-01

    The mission of the U.S. Department of Energy Office of Environmental Management (EM) is to clean up its contaminated sites from the past production of nuclear weapons. Within EM, the Office of Science and Technology (OST) is responsible for providing a full range of science and technology resources needed to support resolution of EM cleanup and long-term environmental stewardship problems. This responsibility includes implementation of a technology development pathway from basic research to development, demonstration, and deployment of scientific and technological solutions needed by DOE sites. One OST Program is the Characterization, Monitoring, and Sensor Technology Crosscutting Program (CMST-CP), which aims to provide innovative technologies (i.e., faster, better, cheaper, and/or safer) for environmental characterization and monitoring. Several technologies are described that CMST-CP has supported for development with significant benefits realized or projected over the baseline characterization and monitoring practices. Examples of these technologies include mapping of subsurface radioactivity using Cone Penetrometer and drilling techniques; a Rapid Liquid Sampler for Sr, Ra, Tc, and Cs using 3M Empore TM Rad Disks; Long-Range Alpha Detectors; a Compact High Resolution Spectrometer; BetaScint TM for determination of Sr in soil; Laser-Induced Fluorescence Imaging techniques for mapping U on surfaces; the Environmental Measurements While Drilling System; and the Expedited Site Characterization methodology. (author)

  6. Status on contamination monitoring in China

    Energy Technology Data Exchange (ETDEWEB)

    Quanlu, Gou [China Institute for Radiation Protection, Taiyuan (China)

    1997-06-01

    The air contaminated by radioactive materials in nuclear enterprises and radioactive workplaces and forming radioactive aerosol and the leakage of radioactive materials in operation cause internal exposure damage in workers. It is necessary and important to monitor air and surface contaminations for the health of public and workers, and for protecting environment. At present, many institutes engage in the studies on surface contamination monitoring in China, and the government has formulated the control limits of surface contamination in the Regulations of Radiation Protection. The monitors for surface contamination monitoring are almost home-made. The methods being used often are smear test and placing surface sample test. Scintillation counters, semiconductor detectors and G-M counters have been used for detecting alpha surface contamination. Plastic scintillator meters and thin wall/window G-M counters are used for beta surface contamination. Special detectors have been designed for monitoring low energy nuclides. The status of airborne contamination monitoring in China is reported. As the studies for future, the development of the surface contamination monitor for low energy beta nuclides, especially H-3, the monitoring methods for the special shapes of surfaces, the technology of decontamination and the calibration method and device for on-line radioactive aerosol continuous monitors are taken up. (K.I.)

  7. Sellafield (release of radioactivity)

    Energy Technology Data Exchange (ETDEWEB)

    Cunningham, J; Goodlad, A; Morris, M

    1986-02-06

    A government statement is reported, about the release of plutonium nitrate at the Sellafield site of British Nuclear Fuels plc on 5 February 1986. Matters raised included: details of accident; personnel monitoring; whether radioactive material was released from the site; need for public acceptance of BNFL activities; whether plant should be closed; need to reduce level of radioactive effluent; number of incidents at the plant.

  8. Radioactivity in surface and coastal waters of the British Isles, 1986

    International Nuclear Information System (INIS)

    Hunt, G.J.

    1987-01-01

    The report presents the results of the environmental monitoring programme carried out during 1986 by staff of the Directorate of Fisheries Research, Lowestoft, United Kingdom. The programme was set up to verify the satisfactory control of liquid radioactive waste discharges to the aquatic environment, and to ensure that the resulting public radiation exposure is within nationally-accepted limits. The environmental programme includes monitoring the environmental consequences of discharges of liquid radioactive wastes from four British Nuclear Fuels plc sites - at Sellafield, Springfield, Capenhurst and Chapelcross, and monitoring the environment impact of liquid radioactive discharges from Winfrith and Dounraey. Monitoring is also carried out near nuclear power stations operated by the electricity boards, near Naval establishments, near Amersham International plc, and the marine environment of the Channel Islands States. Results are also presented on the monitoring of the freshwater environment for radioactivity from the Chernobyl reactor accident. (U.K.)

  9. Radioactive materials in recycled metals.

    Science.gov (United States)

    Lubenau, J O; Yusko, J G

    1995-04-01

    In recent years, the metal recycling industry has become increasingly aware of an unwanted component in metal scrap--radioactive material. Worldwide, there have been 35 instances where radioactive sources were unintentionally smelted in the course of recycling metal scrap. In some cases contaminated metal consumer products were distributed internationally. In at least one case, serious radiation exposures of workers and the public occurred. Radioactive material appearing in metal scrap includes sources subject to licensing under the Atomic Energy Act and also naturally occurring radioactive material. U.S. mills that have smelted a radioactive source face costs resulting from decontamination, waste disposal, and lost profits that range from 7 to 23 million U.S. dollars for each event. To solve the problem, industry and the government have jointly undertaken initiatives to increase awareness of the problem within the metal recycling industry. Radiation monitoring of recycled metal scrap is being performed increasingly by mills and, to a lesser extent, by scrap processors. The monitoring does not, however, provide 100% protection. Improvements in regulatory oversight by the government could stimulate improved accounting and control of licensed sources. However, additional government effort in this area must be reconciled with competing priorities in radiation safety and budgetary constraints. The threat of radioactive material in recycled metal scrap will continue for the foreseeable future and, thus, poses regulatory policy challenges for both developed and developing nations.

  10. Management and control of radioactive wastes in Ghana | Gbadago ...

    African Journals Online (AJOL)

    ... is responsible for monitoring and tracking all radioactive materials imported, stored or exported. The profile of radioactive sources in active use are also presented, in addition to spent radioactive sources currently in the custody of the NRWMC as part of the inventory for creating databases on radioactive wastes in Ghana.

  11. Nevada Test Site 2000 Annual Data Report: Groundwater Monitoring Program Area 5 Radioactive Waste Management Site

    Energy Technology Data Exchange (ETDEWEB)

    Y. E.Townsend

    2001-02-01

    This report is a compilation of the calendar year 2000 groundwater sampling results from the Area 5 Radioactive Waste Management Site (RWMS). Contamination indicator data are presented in control chart and tabular form with investigation levels (IL) indicated. Gross water chemistry data are presented in graphical and tabular form. Other information in the report includes, the Cumulative Chronology for Area 5 RWMS Groundwater Monitoring Program, a brief description of the site hydrogeology, and the groundwater sampling procedure.

  12. Nevada Test Site 2000 Annual Data Report: Groundwater Monitoring Program Area 5 Radioactive Waste Management Site

    International Nuclear Information System (INIS)

    Y. E.Townsend

    2001-01-01

    This report is a compilation of the calendar year 2000 groundwater sampling results from the Area 5 Radioactive Waste Management Site (RWMS). Contamination indicator data are presented in control chart and tabular form with investigation levels (IL) indicated. Gross water chemistry data are presented in graphical and tabular form. Other information in the report includes, the Cumulative Chronology for Area 5 RWMS Groundwater Monitoring Program, a brief description of the site hydrogeology, and the groundwater sampling procedure

  13. Analysis of stresses on the 1st phase support of the monitoring drifts of the radioactive waste repository

    Directory of Open Access Journals (Sweden)

    Hatala Jozef

    1999-09-01

    Full Text Available In the paper, the stability analysis of the radioactive waste repository monitoring drifts’ support by means of the numerical modelling - finite element method is described. The aim of this analysis was to judge to what extent the designed 1st phase support’s parameters correspond with the geomechanical conditions determined by the engineering-geological survey.

  14. Environmental monitoring of nuclear facilities

    International Nuclear Information System (INIS)

    Koelzer, W.

    1988-01-01

    Environmental monitoring of nuclear facilities is part of general monitoring for environmental radioactivity all over the territory of the Federal Republic of Germany. General principles of environmental monitoring were formulated by the ICRP in 1965. In 1974 guidelines for measures of monitoring the environment of NPP incorporating LWR were drafted, which helped to standardize environmental monitoring programs. Since 1958, data on environmental radioactivity from measurements by authorized laboratories have been published in reports. (DG)

  15. Radiation monitoring network in Poland

    International Nuclear Information System (INIS)

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

    2001-01-01

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

  16. Krypton-85 and other airborne radioactivity measurements throughout Ireland

    International Nuclear Information System (INIS)

    Smith, K.J.; Murray, M.; Wong, J.; Sequeira, S.; Long, S.C.; Rafferty, B.

    2004-01-01

    In compliance with articles 35 and 36 of the EURATOM Treaty, the Radiological Protection Institute of Ireland (RPII) undertakes a comprehensive programme of radioactivity monitoring in the Irish terrestrial environment. Radioactivity is present in the terrestrial environment due to natural processes, the testing of nuclear weapons in the atmosphere, accidents such as the Chernobyl accident and the routine discharge of radionuclides from nuclear installations. The RPII monitors airborne radioactivity concentrations at ten stations throughout Ireland, of which, nine are equipped with low volume particulate samplers and one, in Dublin, with a high volume particulate sampler. The low volume particulate samples are assessed for total beta activity and high volume samples for gamma emitting radionuclides such as caesium-137 and beryllium-7. In addition, air sampled at the RPII laboratory in Dublin, is monitored for krypton-85, a radioactive noble gas, released into the environment primarily as a result of the reprocessing of nuclear fuel at installations such as Sellafield in the UK and La Hague in France. Since the inception of the krypton measurements in 1993 a trend of increasing atmospheric concentrations has been observed. The results of the krypton-85 monitoring, as well as the airborne radioactivity concentration measurements, will be presented and discussed in this paper. (author)

  17. Development of plastic scintillator based food radioactivity contamination monitoring system

    International Nuclear Information System (INIS)

    Parihar, A.; Sahani, R.M.; Mahala, V.K.; Vaijapurkar, S.G.

    2016-01-01

    Radioactivity is naturally present in soil, water and food stuffs. Food can be contaminated after discharge of radioactivity into the environment from industries that concentrate natural radionuclide and from civil or military nuclear operations. The contamination can be in three ways; by direct deposition, through the food chain and induced radioactivity due to exposure of high neutron flux. The health effects on human depend on the type of radionuclide and the length of time people are exposed to it. The studies of fission product behaviour in the food chain have revealed radionuclide Strontium-90, Caesium 137 and Iodine-131 are of major concern. Plastic scintillator is already developed indigenously at Defence Laboratory, Jodhpur. Efforts has been made to develop a portable field instrument using plastic scintillator for assessment of beta ( 90 Sr) and gamma ( 137 Cs and 131 I) radioactivity in food

  18. Vadose zone monitoring at the radioactive waste management complex, Idaho National Engineering Laboratory

    International Nuclear Information System (INIS)

    McElroy, D.L.; Hubbell, J.M.

    1989-01-01

    A network of vadose zone instruments was installed in surficial sediments and sedimentary interbeds beneath the Radioactive Waste Management Complex (RWMC) of the Idaho National Engineering Laboratory. The network of instruments monitor moisture movement in a heterogeneous geologic system comprised of sediments which overlie and are intercalated with basalt flows. The general range of matric potentials in the surficial sediments (0 to 9.1 m) was from saturation to -3 bars. The basalt layer beneath the surficial sediments impedes downward water movement. The general range of matric potentials in the 9-, 34- and 73-m interbeds was from -0.3 to 1.7 bars. Preliminary results indicated downward moisture movement through the interbeds. 8 refs., 9 figs., 1 tab

  19. Monitoring of radioactivity in the environs of Finnish nuclear power stations in 1987

    International Nuclear Information System (INIS)

    Sjoeblom, K.-L.; Klemola, S.; Ilus, E.; Arvela, H.; Blomqvist, L.

    1989-06-01

    Results of the environmental programmes for monitoring radioactive contamination around Finnish nuclear power plants in 1987 are reported. Fallout from the Chernobyl accident, which took place in April 1986, was still dominating the artificial radiation situation in Finland. Thus, large amounts of 137 Cs and other long-lived fallout nuclides predominated in the environmental samples taken in the vicinity of nuclear power plants. The extremely small airborne releases from Finnish nuclear power plants were almost totally covered by fallout nuclides. The somewhat higher aquatic releases were easier to distinguish, and it was possible to follow their spread in the marine environment. The contribution of locally discharged nuclides to radiation doses of the population was insignificant

  20. Radiation monitoring system in medical facilities

    International Nuclear Information System (INIS)

    Matsuno, Kiyoshi

    1981-01-01

    (1) RI selective liquid effluent monitor is, in many cases, used at medical facilities to obtain data for density of radioactivity of six radionuclides. In comparison with the conventional gross measuring systems, over-evaluation is less, and the monitor is more practical. (2) Preventive monitor for loss of radium needle is a system which prevents missing of radium needle at a flush-toilet in radium treatment wards, and this monitor is capable of sensing a drop-off of radium needle of 0.5 mCi (minimum). (3) Short-lived positron gas measuring device belongs to a BABY CYCLOTRON installed in a hospital, and this device is used to measure density of radioactivity, radioactive impurity and chemical impurity of produced radioactive gas. (author)

  1. A survey of the environmental radioactivity in the east sea related to the Russian ocean dumping of the radioactive waste

    International Nuclear Information System (INIS)

    Kim, Kyehoon; Kim, Changkyu; Lee, Mosung

    1994-01-01

    From October 24 - December 30, 1993 a joint survey by the Office of Fisheries, Korea Institute of Nuclear Safety, Korea Ocean Research and Development Institute, and several other governmental institutes which was supervised by Ministry of Science and Technology was carried out to investigate present marine environmental radioactivity of the East Sea where former USSR and Russia had dumped radioactive waste since 1957. Exposure rate was measured and the radioactivity of seawater, both surface and deep water, bottom sediment, fish, and planktonic organisms from the areas around the dumping sites and the East Sae were analyzed. Results showed that the radioactivities of Cs-137 in the sea water from dumping sites were less than 0.0038 Bq/L, which was similar to the background level of the East Sea. The radioactivity level of fish and bottom sediment from dumping sites also did not increased. A detailed Ocean Environmental Monitoring Plan, however, should be established and the monitoring must be carried out continuously to protect people from potential radioactive hazards

  2. Testing and assessment of a large BGO detector for beach monitoring of radioactive particles

    International Nuclear Information System (INIS)

    Graaf, E.R. van der; Rigollet, C.; Maleka, P.P.; Jones, D.G.

    2007-01-01

    The Beach Monitoring Steering Group (BMSG) was set up by UKAEA to explore whether improved systems for beach monitoring of radioactive particles are available. The BMSG commissioned the British Geological Survey (BGS) and the Nuclear Geophysics Division of the Kernfysisch Versneller Instituut (KVI/NGD), and other companies, to test their most sensitive system. This paper presents the results of trials in a specially created test facility at UKAEA Harwell with a large BGO detector. The detector's size and weight mean that it would be suitable for vehicle deployment but would be too large and heavy to carry in areas that could not be accessed by a vehicle. However, it would be possible to use the same methodology that is described here with a smaller detector capable of being carried in a backpack, albeit with reduced sensitivity for particle detection. The approach that we present is also applicable, with modifications, to the detection of offshore particles using a towed seabed detector

  3. Subjective perception of radioactivity. No change post successful treatment with radioiodine

    International Nuclear Information System (INIS)

    Freudenberg, L.S.; Mueller, S.P.; Beyer, T.; Bockisch, A.

    2009-01-01

    We assess the attitude of patients with thyroid disease towards radiation and radioactivity before and after radioiodine therapy by means of a cultural-anthropological approach. We evaluate in patient interviews how their subjective attitude towards radioactivity as an abstract term and towards radioactivity in the medical context on the basis of their personal experiences with radionuclide therapy. 29 patients with autonomously functioning thyroid lesions (17 women, 12 men, 35-79 years) were included in this study. All patients were interviewed prior to and 22-27 month post radioiodine therapy in an open dialogue with the principal investigator. Patients were asked to describe their attitude towards radioactivity in general and towards radioiodine therapy in particular. Patients were asked to use a scoring system (1: positive, 5: negative) to quantify their perception of radioactivity. The personal perception of radioactivity as an abstract term does not change significantly (p = 0.15) before and after radioiodine therapy. This perception is linked to mostly negative impressions of radiactivity. However, patients become more positive when assessing the value of radioactivity as part of their therapy regimen. Thus, we observe a significant increase in percepted value of radioactivity post radioiodine therapy (p = 0.03). Patients continue to view radioactivity as something negative despite treatment success following radioiodine therapy. Our results provide useful information for patient information by the nuclear medicine physician prior to a radioiodine therapy. (orig.)

  4. Handbook of radioactivity measurements procedures. Second edition

    International Nuclear Information System (INIS)

    Anon.

    1985-01-01

    This report is concerned with the measurement of radioactivity in general, but specifically it deals with radioactive materials that have become available in the last three decades, from nuclear reactors and particle accelerators, for applications in medicine, scientific research, and industry. It is also concerned with low-level radioactivity measurements for the monitoring of radioactivity in environmental media, such as air and water, in connection with the control of radioactive effluents associated with the production of nuclear power or the use of radionuclides. Included in appendices are nuclear decay data for selected radionuclides and statistics of radioactive decay. An extensive bibliography is also included

  5. The monitoring network for radioactivity in air in Norway. Annual report 2000; Nettverket for overvaaking av radioaktivitet i luft i Norge

    Energy Technology Data Exchange (ETDEWEB)

    Berg, Thor Chr.

    2002-06-01

    On the instruction of the Radiation Monitoring Authority (SSV), NILU has assumed responsibility for the operation of a monitoring network for radioactivity. This report describes this network. None of the 29 stations of the network detected radiation in 2000 that cannot be attributed to the natural variation of the radiation levels or to normal technical irregularities. However, much of the equipment was acquired in the years following the Chernobyl accident of 1986 and is in need of replacement.

  6. Experiences in monitoring airborne radioactive contamination in JAERI

    International Nuclear Information System (INIS)

    Ikezawa, Y.; Okamoto, T.; Yabe, A.

    1980-01-01

    The following results were obtained at the Japan Atomic Energy Research Institute (JAERI) from experience in air monitoring at the hot cells for handling highly radioactive materials, the glove box containing plutonium and the cell for producing 99 Mo. (1) The ratios of activities of airborne dust to those of whole dust were of the order of 10 -2 for the semi-volatile form of 125 Sb, and 10 -3 to 10 -4 for the particulate form of 137 Cs, 144 Ce and 144 Pr, when irradiated fuels were cut in the hot cells. (2) The activity median aerodynamic diameter (AMAD) of airborne particle size distributions varied from O.4 to 15 μm with changing geometric standard deviation (sigmasub(g)) 1.7 to 7, depending on types of metallurgical treatment of fuels and on kinds of work in the cells. (3) A resuspension factor (the ratio of the concentration of airborne contamination to the surface contamination) was found to be 4x10 -8 to approximately 2x10 -7 cm -1 for plutonium oxide deposited on the floor surface. (4) The collection efficiency of the charcoal-loaded filter paper for airborne radioiodine, consisting of 60% inorganic and 40% organic iodide, was over 95% under conditions of relative humidity 40 to approximately 80% and face velocity 50 cm/sec, during the production of 99 Mo. (H.K.)

  7. Applicability of monitored natural attenuation at radioactively contaminated sites

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-01-15

    The IAEA attaches great importance to the dissemination of information that can assist Member States with the development, implementation, maintenance and continuous improvement of systems, programmes and activities that support a sustainable nuclear fuel cycle and nuclear applications, including managing the legacy of past practices and accidents. Hence, the IAEA has initiated a comprehensive programme of work covering all aspects of environmental remediation including: - Technical and non-technical factors influencing decision making in environmental remediation; - Site characterization techniques and strategies; - Assessment of remediation technologies; - Assessment of technical options for cleanup of contaminated media; - Post-restoration compliance monitoring; - Assessment of the costs of remediation measures. It has been observed that many measures to remove or contain contamination are inefficient below certain concentrations, in general costly, and of a limited lifetime compared with the half-lives of the radionuclides concerned. Dispersed low level contamination poses a particular challenge to those charged with its remediation. Economic considerations in many Member States also result in constraints being placed on resources available to deal with such contamination. Experience has also shown that many techniques are not efficient below certain concentration thresholds or may entail impacts on certain environmental compartments in addition to those due to the contamination itself. This includes doses received by workers on the remediation project. As a result, the concept of relying on geological media to retain contaminants and/or to 'flatten out' concentration/dose peaks is increasingly being discussed in a remediation context. Technical Reports Series No. 424 (Remediation of Sites with Dispersed Radioactive Contamination) examined a variety of technological options for remediating dispersed contamination and concluded that the approaches can be broadly

  8. Applicability of monitored natural attenuation at radioactively contaminated sites

    International Nuclear Information System (INIS)

    2006-01-01

    The IAEA attaches great importance to the dissemination of information that can assist Member States with the development, implementation, maintenance and continuous improvement of systems, programmes and activities that support a sustainable nuclear fuel cycle and nuclear applications, including managing the legacy of past practices and accidents. Hence, the IAEA has initiated a comprehensive programme of work covering all aspects of environmental remediation including: - Technical and non-technical factors influencing decision making in environmental remediation; - Site characterization techniques and strategies; - Assessment of remediation technologies; - Assessment of technical options for cleanup of contaminated media; - Post-restoration compliance monitoring; - Assessment of the costs of remediation measures. It has been observed that many measures to remove or contain contamination are inefficient below certain concentrations, in general costly, and of a limited lifetime compared with the half-lives of the radionuclides concerned. Dispersed low level contamination poses a particular challenge to those charged with its remediation. Economic considerations in many Member States also result in constraints being placed on resources available to deal with such contamination. Experience has also shown that many techniques are not efficient below certain concentration thresholds or may entail impacts on certain environmental compartments in addition to those due to the contamination itself. This includes doses received by workers on the remediation project. As a result, the concept of relying on geological media to retain contaminants and/or to 'flatten out' concentration/dose peaks is increasingly being discussed in a remediation context. Technical Reports Series No. 424 (Remediation of Sites with Dispersed Radioactive Contamination) examined a variety of technological options for remediating dispersed contamination and concluded that the approaches can be broadly

  9. Environmental monitoring report for commercial low-level radioactive waste disposal sites (1960's through 1990's)

    International Nuclear Information System (INIS)

    1996-11-01

    During the time period covered in this report (1960's through early 1990's), six commercial low-level radioactive waste (LLRW) disposal facilities have been operated in the US. This report provides environmental monitoring data collected at each site. The report summarizes: (1) each site's general design, (2) each site's inventory, (3) the environmental monitoring program for each site and the data obtained as the program has evolved, and (4) what the program has indicated about releases to off-site areas, if any, including a statement of the actual health and safety significance of any release. A summary with conclusions is provided at the end of each site's chapter. The six commercial LLRW disposal sites discussed are located near: Sheffield, Illinois; Maxey Flats, Kentucky; Beatty, Nevada; West Valley, New York; Barnwell, South Carolina; Richland, Washington

  10. A waste characterization monitor for low-level radioactive waste management

    International Nuclear Information System (INIS)

    Davey, E.C.; Csullog, G.W.; Kupca, S.; Hippola, K.B.

    1985-06-01

    The exploitation of nuclear processes and technology for the benefit of Canadians results in the routine generation of approximately 12 000 m 3 of solid low-level radioactive waste annually. To protect the public and the environment, this waste must be isolated for the duration of its potential hazard. In Canada, current planning foresees the development and use of a range of storage and disposal facilities exhibiting differing containment capabilities. To demonstrate adequate isolation safety and to minimize overall costs, the radionuclide content of waste items must be quantified so that the radiological hazards of each waste item can be matched to the isolation capabilities of specific containment facilities. This paper describes a non-invasive, waste characterization monitor that is capable of quantifying the radionuclide content of low-level waste packages to the 9 Bq/g (250 pCi/g) level. The assay technique is based on passive gamma-ray spectroscopy where the concentration of gamma-ray emitting radionuclides in a waste item can be estimated from the analysis of the gamma-ray spectra of the item and calibrated standards

  11. Analysis of Precursors Prior to Rock Burst in Granite Tunnel Using Acoustic Emission and Far Infrared Monitoring

    OpenAIRE

    Liang, Zhengzhao; Liu, Xiangxin; Zhang, Yanbo; Tang, Chunan

    2013-01-01

    To understand the physical mechanism of the anomalous behaviors observed prior to rock burst, the acoustic emission (AE) and far infrared (FIR) techniques were applied to monitor the progressive failure of a rock tunnel model subjected to biaxial stresses. Images of fracturing process, temperature changes of the tunnel, and spatiotemporal serials of acoustic emission were simultaneously recorded during deformation of the model. The b-value derived from the amplitude distribution data of AE wa...

  12. Radiation and environmental radioactivity

    International Nuclear Information System (INIS)

    Muhamat Omar; Ismail Sulaiman; Zalina Laili

    2015-01-01

    This book is written based on 25 years authors experience especially in scientifc research of radiation and environmental radioactivity field at Malaysian Nuclear Agency (Nuklear Malaysia). Interestingly, from the authors experience in managing the services and consultancies for radiological environmental monitoring, it is also helpful in preparing the ideas for this book. Although this book focuses on Malaysian radiation information environmental radioactivity, but the data collected by the international bodies are also included in this book.

  13. Hybrid monitoring of environmental radioactivity as a perspective approach to rapid control and prediction of environmental contamination due to NPP wastes and effluents

    International Nuclear Information System (INIS)

    Eremeev, I.S.; Eremenko, V.A.; Zhernov, V.S.; Makarov, Yu.A.; Matveev, V.V.; Ryzhov, N.V.; Ryazanov, V.V.; Skatkin, V.M.

    1985-01-01

    Conseptucal model of the system of hybride monitoring of environmental radioactivity due to NPP wastes and effluents is proposed. The model a combination of measuring and simulating monitoring, provides correlation of methods and aims of simulation of environmental contamination spread methods and means of monitoring of its factual distribution in space, methods of separation of technogeneous signals from natural radiation background and provision of the given degree of reliability of results of information processing, in particular periodic coorection, model adaptation according to the factual measurement data

  14. Summarization of radioactive effluent monitoring in Daya Bay Nuclear Power Station 1994-2002

    International Nuclear Information System (INIS)

    Ouyang Junjie; Chen Yue

    2004-01-01

    This paper introduces the radioactive effluent monitoring systems, measurement and quality control methods used in Daya Bay Nuclear Power Station from its commercial operation in 1994. The main work and experiences for the management of effluent release are discussed and analyzed. The radwaste data appear declining trend and are far blow the annual limit approved by the national Environmental Protection Bureau since 1995. The normalized release (unit GBq/GWa) of 9 years is as follows: liquid nuclides (except tritium) 11.1, liquid tritium 1.91 x 10 4 , noble gas 2.03 x 10 4 , halogen 0.13, aerosol 7.57 x 10 -3 . For 110m Ag, the average release from 1998 to 2002 has been reduced to 1/7 of the quantity in 1997

  15. Conditioning of Radioactive Wastes Prior to disposal; Segregation and Repackaging

    Energy Technology Data Exchange (ETDEWEB)

    Kang, Il Sik; Kim, Ki Hong; Hong, Dae Seok; Lee, Bum Chul [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2014-05-15

    We stored several types of radioactive wastes at interim storage facility of KAERI ; the combustible wastes (cloths, decontamination paper and vinyls) from Hanaro multipurpose research reactor, nuclear fuel cycle facility, RI production facility and laboratories, and the non-combustible wastes (metals and glass) dismantled and discarded from the apparatus of laboratories which deteriorated, and also the miscellaneous wastes (spent air-filters). After a segregation of these wastes as the same type, they were treated by using a proper method in order to meet both the national regulation and the waste acceptance criteria of Kyung-ju disposal site. For a safe disposal of waste drums, the waste characterization system including a scaling factor which is hard to measure special radionuclides is established completely. All data of those repackaged drums were input into an ANSIM system so that we could manage them clearly and effectively such like an easy transparent traceability. Through a decontamination of empty drums generated in a repackaging process of the stored drums, these drums can be reused or compressed to reduce their volume reduction for disposal. As a result, the space to store radioactive waste drums are secured more than before, and also the interim storage facility are maintained in a good state. The combustible wastes, which stored at the interim storage facility of KAERI, are managed safely in compliance with the specifications of the national regulations and disposal site. Through the classification and repackage of them, the storage space of drums at RWTF was secured more than before, and the storage facility was kept in a good state, and also the disposal cost of all stored waste drums of KAERI will be reduced due to the reduction of waste volume. Base on the experiences, the non-combustible wastes will be treated soon.

  16. Device for monitoring radioactivity of cooling water in a nuclear reactor

    International Nuclear Information System (INIS)

    Osawa, Yasuo.

    1975-01-01

    Object: To provide means for monitoring the peak channel of γ-ray spectrum in cooling water and the time-wise attenuation value of the counts of the peak channels and capable of early detecting abnormal phenomenon with a constant reference. Structure: It is provided with a γ-ray detector, a multi-channel γ-ray spectrometer, peak determining means for determining the peak position of the spectrum from the count value of each channel of the γ-ray spectrum, a peak channel memory for memorizing the channel number of the peak channels, attenuation measurement means for measuring the attenuation value by repeatedly measuring the count value of the peak channel, an attenuation memory for memorizing the attenuation value and a variation detector for detecting the variation in radioactivity of the reactor cooling water from the count value of the peak channel and peak channel attenuation value. When a difference is detected by the variation detector, the measurement value is provided as defective value. (Kamimura, M.)

  17. Radioactivity in surface and coastal waters of the British Isles, 1987

    International Nuclear Information System (INIS)

    Hunt, G.J.

    1988-01-01

    This report presents the results of the environmental monitoring programme carried out during 1987 by staff of the Directorate of Fisheries Research, Lowestoft. The monitoring programme supports the Ministry's functions under the Radioactive Substances Act, 1960 (Great Britain-Parliament, 1960). The programme is set up to verify the satisfactory control of liquid radioactive waste discharges to the aquatic environment, and to ensure that the resulting public radiation exposure is within nationally-accepted limits. The monitoring is independent of similar programmes carried out by nuclear site operators as a condition of their authorisations to discharge radioactive wastes. This report also includes results of monitoring carried out on behalf of departments of the Scottish Office, the Welsh Office, the Department of the Environment for Northern Ireland [DOE (NI)] and the Channel Islands States. Where appropriate, the information presented is supplemented by results from our extensive programme of research into the behaviour of radioactivity in the aquatic environment. (author)

  18. Detector module for gas monitor

    International Nuclear Information System (INIS)

    1980-01-01

    The invention relates to radioactive source detector module for use in a gas monitor. It is adapted to contain the source and other detector components to allow sealed coupling of those components with other portions of the gas monitor. It is particularly concerned with the use of radioactive materials used as electron sources in gas monitors. The module is used to detect changes in electron flow caused by partial absorption of the electron capture gas flowing between two electrodes. The assembly includes a gas flow source, a gas receiver and an electronic assembly for receiving a signal from the detector. The radioactive source and electrodes are housed so that they are connected to the gas flow source so as to prevent accidental or undesired disconnection. It is designed so that the detector module may be removed or replaced into the gas monitor assemblies by untrained personnel so as to prevent exposure to the radioactive material. Full details are given. (U.K.)

  19. Radioactivity in the Marine Environment 1999

    Energy Technology Data Exchange (ETDEWEB)

    Rudjord, A.L.; Foeyn, L.; Brungot, A.L.; Kolstad, A.K.; Helldal, H.E.; Brown, J.; Iosjpe, M.; Christensen, G.

    2001-07-01

    A new, comprehensive national programme for monitoring of Radioactivity in the Marine Environment (RAME) was established in 1999. This program is based on a proposal developed by the Norwegian Radiation Protection Authority (NRPA), the Institute of Marine Research (IMR), the Directorate for Nature Conservation (DN) and the State pollution authorities (SFT) on behalf of the Ministry of Environment. NRPA, as the responsible authority on radiation protection, co-ordinates the programme whilst sampling at sea is conducted in close co-operation with IMR as part of the regular monitoring of the marine environment and its living resources. The principal objective of the programme is to document levels, distributions and trends of anthropogenic and naturally occurring radionuclides in the North Sea, the Norwegian Sea, the Barents Sea and along the Norwegian coast. The programme also collects updated information on both Norwegian and other sources of radioactive contamination, and carries out assessments of radiation exposures of humans and biota. This new national monitoring programme has been co-ordinated with existing programmes funded by the Ministry of Fisheries. The monitoring programme for Marine Fish and Seafood was established in 1994. In previous reports from the programme established in 1994, (Sickel et al, 1995; Brungot et al, 1997, 1999) information regarding radioactivity in sea water, sediments and seaweed was included. However, the main purpose of this program is to document levels of anthropogenic radionuclides in fish and other seafood caught in Norwegian waters. This information is then made available to the relevant authorities, fishing industries and the general public as documentation regarding the quality of the marine products. The work in this programme is performed as a co-operation between the NRPA and the Directorate of Fisheries. In addition, results from the monitoring program conducted by the National Food Control Authority are also included

  20. Radioactivity in the Marine Environment 1999

    International Nuclear Information System (INIS)

    Rudjord, A.L.; Foeyn, L.; Brungot, A.L.; Kolstad, A.K.; Helldal, H.E.; Brown, J.; Iosjpe, M.; Christensen, G.

    2001-01-01

    A new, comprehensive national programme for monitoring of Radioactivity in the Marine Environment (RAME) was established in 1999. This program is based on a proposal developed by the Norwegian Radiation Protection Authority (NRPA), the Institute of Marine Research (IMR), the Directorate for Nature Conservation (DN) and the State pollution authorities (SFT) on behalf of the Ministry of Environment. NRPA, as the responsible authority on radiation protection, co-ordinates the programme whilst sampling at sea is conducted in close co-operation with IMR as part of the regular monitoring of the marine environment and its living resources. The principal objective of the programme is to document levels, distributions and trends of anthropogenic and naturally occurring radionuclides in the North Sea, the Norwegian Sea, the Barents Sea and along the Norwegian coast. The programme also collects updated information on both Norwegian and other sources of radioactive contamination, and carries out assessments of radiation exposures of humans and biota. This new national monitoring programme has been co-ordinated with existing programmes funded by the Ministry of Fisheries. The monitoring programme for Marine Fish and Seafood was established in 1994. In previous reports from the programme established in 1994, (Sickel et al, 1995; Brungot et al, 1997, 1999) information regarding radioactivity in sea water, sediments and seaweed was included. However, the main purpose of this program is to document levels of anthropogenic radionuclides in fish and other seafood caught in Norwegian waters. This information is then made available to the relevant authorities, fishing industries and the general public as documentation regarding the quality of the marine products. The work in this programme is performed as a co-operation between the NRPA and the Directorate of Fisheries. In addition, results from the monitoring program conducted by the National Food Control Authority are also included

  1. Radioactivity analysis of sounai region by gamma spectrometry and radiation monitoring network

    International Nuclear Information System (INIS)

    El-Mongy, S.A.; Abd El-Aziz, N.; El-Tahawy, M.S.; Morsy, S.

    2000-01-01

    Levels of natural and man-made radioactivity in soil and plant of southern sinai region are investigated by using Gamma- spectrometric analysis. The found average concentrations of 2 26Ra ( 2 38U) series, 2 32Th series and 4 0K are 20.2, 17.0 and 378.8 Bq/Kg respectively. The fall out 1 37Cs is the only man-made radionuclide detected with concentrations not exceed 3 Bq/Kg (dry weight) in both soil and plant samples. The effective dose rate equivalent are 106, 129, 114 and 104 n Sv/h for El-Tour, Sharm El-Shaik, Nwuiba and Taba as detected by the corresponding stations of the national radiation monitoring network (NRMN) respectively. The radium equivalent (Req) and absorbed dose rate resulted due to the natural radionuclides in soil are also calculated and given

  2. Radioactivity in the environment. Report for 1999. A summary and radiological assessment of the Environment Ageny's monitoring programmes

    International Nuclear Information System (INIS)

    1999-01-01

    The Environment Agency has wide-ranging responsibilities and powers to protect and, where necessary, improve the environment in England and Wales. The Agency also has a duty to protect the environment in a way that works towards sustainable development. In 1998, the Oslo and Paris Commission (OSPAR) strategy for radioactive substances was agreed by Ministers at Sintra, Portugal, to prevent pollution of the North East Atlantic maritime area through progressive and substantial reductions in discharges, emissions and losses of radioactive substances. In June 2000, the UK Government published for consultation the draft UK Strategy for Radioactive Discharges 2001-2020 which sets out the UK's plans to implement the OSPAR strategy. The Government will be issuing statutory guidance to the Environment Agency which will provide the vehicle through which the UK Strategy will be implemented. Radiological monitoring programmes are carried out in support of the Agency's regulatory functions under RSA 93 and as part of the UK Government's obligations under the Euratom Treaty. This report presents the results of the Agency's regular monitoring of radioactivity in the environment during 1999 and an assessment of the radiological impact. The main findings of the regular monitoring programme during 1999 were as follows: (i) The majority of operator declarations of the radioactive content of wastes discharges and disposals had been assessed accurately or were over estimated. (ii) Radiation dose-rates above sediments and concentrations of radionuclides in water, sediment, soil and grass were generally consistent with those reported in previous years, with no clear trend over the last 10 years. Enhanced levels of artificial radionuclides continue to be found in coastal sediments in the vicinity of Sellafield, which decline with increasing distance from the site. Radioactivity levels around other major sites were mostly low or not detectable. (iii) As in previous years, concentrations of

  3. 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

  4. Over the border - the problems of uncontrolled radioactive materials crossing national borders

    Energy Technology Data Exchange (ETDEWEB)

    Duftschmid, K.E. E-mail: k.duftschmid@aon.at

    2002-03-01

    Cross-border movement of radioactive materials and contaminated items, in particular metallurgical scrap, has become a problem of increasing importance. Radioactive sources out of regulatory control, now often called 'orphan sources', have frequently caused serious, even deadly, radiation exposures and widespread contamination. The United States Nuclear Regulatory Commission reported over 2300 incidents of radioactive materials found in recycled metal scrap and more than 50 accidental smeltings of radioactive sources. A further potentially serious problem is illicit trafficking in nuclear and other radioactive materials. In 1995 the International Atomic Energy Agency (IAEA) started a programme to combat illicit trafficking in nuclear and other radioactive materials, which includes an international database on incidents of illicit trafficking, receiving reports from some 80 member states. For the period 1993-2000 the IAEA database includes 345 confirmed incidents. While from 1994-1996 the frequency declined significantly, this trend has been reversed since 1997, largely due to radioactive sources rather than nuclear material. This paper compares monitoring techniques for radioactive materials in scrap applied at steel plants and scrap yards with monitoring at borders, a completely different situation. It discusses the results of the 'Illicit Trafficking Radiation Detection Assessment Program', a large international pilot study, conducted in cooperation between the IAEA, the Austrian Government and the Austrian Research Centre Seibersdorf. The aim of this exercise was to derive realistic and internationally agreed requirements for border monitoring instrumentation. Finally the present extent of border monitoring installations is discussed. (author)

  5. Early-stage bioassay for monitoring radioactive contamination in living livestock.

    Science.gov (United States)

    Yamaguchi, Toshiro; Sawano, Kaita; Kishimoto, Miori; Furuhama, Kazuhisa; Yamada, Kazutaka

    2012-12-01

    Soil samples from the ground surface and feces and blood from a mixed-breed male pig were collected on April 10, 2011 at a farm within 20 km of the Fukushima Daiichi nuclear power plant. The radioactivity of each sample was measured using a Ge semiconductor detector. Despite the fact that the pig had been fed non-contaminated imported feed, (131)I, (134)Cs and (137)Cs were detected in the feces, and (134)Cs and (137)Cs were detected in the blood clots. Because it is considerably difficult to measure radioactive contamination in the edible muscle of living livestock, bioassays are an option for the screening of radioactive contamination in living livestock to ensure food safety.

  6. Low-level radioactive waste disposal facility closure

    International Nuclear Information System (INIS)

    White, G.J.; Ferns, T.W.; Otis, M.D.; Marts, S.T.; DeHaan, M.S.; Schwaller, R.G.; White, G.J.

    1990-11-01

    Part I of this report describes and evaluates potential impacts associated with changes in environmental conditions on a low-level radioactive waste disposal site over a long period of time. Ecological processes are discussed and baselines are established consistent with their potential for causing a significant impact to low-level radioactive waste facility. A variety of factors that might disrupt or act on long-term predictions are evaluated including biological, chemical, and physical phenomena of both natural and anthropogenic origin. These factors are then applied to six existing, yet very different, low-level radioactive waste sites. A summary and recommendations for future site characterization and monitoring activities is given for application to potential and existing sites. Part II of this report contains guidance on the design and implementation of a performance monitoring program for low-level radioactive waste disposal facilities. A monitoring programs is described that will assess whether engineered barriers surrounding the waste are effectively isolating the waste and will continue to isolate the waste by remaining structurally stable. Monitoring techniques and instruments are discussed relative to their ability to measure (a) parameters directly related to water movement though engineered barriers, (b) parameters directly related to the structural stability of engineered barriers, and (c) parameters that characterize external or internal conditions that may cause physical changes leading to enhanced water movement or compromises in stability. Data interpretation leading to decisions concerning facility closure is discussed. 120 refs., 12 figs., 17 tabs

  7. Low-level radioactive waste disposal facility closure

    Energy Technology Data Exchange (ETDEWEB)

    White, G.J.; Ferns, T.W.; Otis, M.D.; Marts, S.T.; DeHaan, M.S.; Schwaller, R.G.; White, G.J. (EG and G Idaho, Inc., Idaho Falls, ID (USA))

    1990-11-01

    Part I of this report describes and evaluates potential impacts associated with changes in environmental conditions on a low-level radioactive waste disposal site over a long period of time. Ecological processes are discussed and baselines are established consistent with their potential for causing a significant impact to low-level radioactive waste facility. A variety of factors that might disrupt or act on long-term predictions are evaluated including biological, chemical, and physical phenomena of both natural and anthropogenic origin. These factors are then applied to six existing, yet very different, low-level radioactive waste sites. A summary and recommendations for future site characterization and monitoring activities is given for application to potential and existing sites. Part II of this report contains guidance on the design and implementation of a performance monitoring program for low-level radioactive waste disposal facilities. A monitoring programs is described that will assess whether engineered barriers surrounding the waste are effectively isolating the waste and will continue to isolate the waste by remaining structurally stable. Monitoring techniques and instruments are discussed relative to their ability to measure (a) parameters directly related to water movement though engineered barriers, (b) parameters directly related to the structural stability of engineered barriers, and (c) parameters that characterize external or internal conditions that may cause physical changes leading to enhanced water movement or compromises in stability. Data interpretation leading to decisions concerning facility closure is discussed. 120 refs., 12 figs., 17 tabs.

  8. Real breakthrough in detection of radioactive sources by portal monitors with plastic detectors and New Advanced Source Identification Algorithm (ASIA-New)

    Energy Technology Data Exchange (ETDEWEB)

    Stavrov, Andrei; Yamamoto, Eugene [Rapiscan Systems, Inc., 14000 Mead Street, Longmont, CO, 80504 (United States)

    2015-07-01

    Radiation Portal Monitors (RPM) with plastic detectors represent the main instruments used for primary border (customs) radiation control. RPM are widely used because they are simple, reliable, relatively inexpensive and have a high sensitivity. However, experience using the RPM in various countries has revealed the systems have some grave shortcomings. There is a dramatic decrease of the probability of detection of radioactive sources under high suppression of the natural gamma background (radiation control of heavy cargoes, containers and, especially, trains). NORM (Naturally Occurring Radioactive Material) existing in objects under control trigger the so-called 'nuisance alarms', requiring a secondary inspection for source verification. At a number of sites, the rate of such alarms is so high it significantly complicates the work of customs and border officers. This paper presents a brief description of new variant of algorithm ASIA-New (New Advanced Source Identification Algorithm), which was developed by the Rapiscan company. It also demonstrates results of different tests and the capability of a new system to overcome the shortcomings stated above. New electronics and ASIA-New enables RPM to detect radioactive sources under a high background suppression (tested at 15-30%) and to verify the detected NORM (KCl) and the artificial isotopes (Co- 57, Ba-133 and other). New variant of ASIA is based on physical principles, a phenomenological approach and analysis of some important parameter changes during the vehicle passage through the monitor control area. Thanks to this capability main advantage of new system is that this system can be easily installed into any RPM with plastic detectors. Taking into account that more than 4000 RPM has been installed worldwide their upgrading by ASIA-New may significantly increase probability of detection and verification of radioactive sources even masked by NORM. This algorithm was tested for 1,395 passages of

  9. Analysis on the influence of forest soil characteristics on radioactive Cs infiltration and evaluation of residual radioactive Cs on surfaces.

    Science.gov (United States)

    Mori, Yoshitomo; Yoneda, Minoru; Shimada, Yoko; Fukutani, Satoshi; Ikegami, Maiko; Shimomura, Ryohei

    2018-03-29

    We investigated the depth profiles of radioactive Cs, ignition loss, and cation exchange capacity (CEC) in five types of forest soils sampled using scraper plates. We then simulated the monitored depth profiles in a compartment model, taking ignition loss as a parameter based on experimental results showing a positive correlation between ignition loss and the CEC. The calculated values were comparable with the monitored values, though some discrepancy was observed in the middle of the soil layer. Based on decontamination data on the surface dose rate and surface contamination concentration, we newly defined a surface residual index (SRI) to evaluate the residual radioactive Cs on surfaces. The SRI value tended to gradually decrease in forests and unpaved roads and was much smaller in forests and on unpaved roads than on paved roads. The radioactive Cs was assumed to have already infiltrated underground 18 months after the nuclear power plant accident, and the sinking was assumed to be ongoing. The SRI values measured on paved roads suggested that radioactive Cs remained on the surfaces, though a gradual infiltration was observed towards the end of the monitoring term. The SRI value is thought to be effective in grasping the rough condition of residual radioactive Cs quickly at sites of decontamination activity in the field. The SRI value may be serviceable for actual contamination works after further research is done to elucidate points such as the relation between the SRI and the infiltration of radioactive Cs in various types of objects.

  10. Method for radioactivity monitoring

    Science.gov (United States)

    Umbarger, C. John; Cowder, Leo R.

    1976-10-26

    The disclosure relates to a method for analyzing uranium and/or thorium contents of liquid effluents preferably utilizing a sample containing counting chamber. Basically, 185.7-keV gamma rays following .sup.235 U alpha decay to .sup.231 Th which indicate .sup.235 U content and a 63-keV gamma ray doublet found in the nucleus of .sup.234 Pa, a granddaughter of .sup.238 U, are monitored and the ratio thereof taken to derive uranium content and isotopic enrichment .sup.235 U/.sup.235 U + .sup.238 U) in the liquid effluent. Thorium content is determined by monitoring the intensity of 238-keV gamma rays from the nucleus of .sup.212 Bi in the decay chain of .sup.232 Th.

  11. Environmental monitoring report for commercial low-level radioactive waste disposal sites (1960`s through 1990`s)

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-11-01

    During the time period covered in this report (1960`s through early 1990`s), six commercial low-level radioactive waste (LLRW) disposal facilities have been operated in the US. This report provides environmental monitoring data collected at each site. The report summarizes: (1) each site`s general design, (2) each site`s inventory, (3) the environmental monitoring program for each site and the data obtained as the program has evolved, and (4) what the program has indicated about releases to off-site areas, if any, including a statement of the actual health and safety significance of any release. A summary with conclusions is provided at the end of each site`s chapter. The six commercial LLRW disposal sites discussed are located near: Sheffield, Illinois; Maxey Flats, Kentucky; Beatty, Nevada; West Valley, New York; Barnwell, South Carolina; Richland, Washington.

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

    International Nuclear Information System (INIS)

    Katoch, D.S.; Somasundaram, S.

    1979-01-01

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

  13. Radioactivity monitoring of the Irish marine environment 2000 and 2001

    International Nuclear Information System (INIS)

    Ryan, T.P.; McMahon, C.A.; Dowdall, A.

    2003-04-01

    This report presents the results of the marine radioactivity monitoring programme carried out by the Radiological Protection Institute of Ireland (RPII) during 2000 and 2001. The primary objective of the programme is to assess the exposure of the Irish population resulting from radioactive contamination of the Irish marine environment and to estimate the risks to health from this exposure. Discharged radioactive waste from the British Nuclear Fuels plc (BNFL) reprocessing plant at Sellafield in Cumbria in the North West of England continues to be the dominant source of this contamination. In particular, the remobilisation from sediments of historic discharges makes an important contribution to the levels of radioactivity in the seawater of the western Irish Sea. Approximately 300 samples of fish, shellfish, seaweed, seawater and sediment were collected in 2000 and again in 2001. Both the Marine Institute and the Department of Communications, Marine and Natural Resources assisted the Institute with this sampling. The samples were analysed for a range of radionuclides at the Institute's radio-analytical laboratory. The results show that the artificial radionuclide of greatest dosimetric significance continues to be caesium-137. The activity concentration of this radionuclide in the Irish marine environment has remained relatively stable since the mid 1990s but at a lower level than that observed during the previous two decades. Along the Irish coastline the highest activity concentrations observed are in the north-east. Since 1994 the commissioning and operation of new facilities at Sellafield have resulted in an increase in the discharges of technetium-99 to the Irish Sea. This has been reflected in an increase in the activity concentrations of this radionuclide at all east coast sampling sites. However, the low radiotoxicity of technetium-99 means that it is generally of lesser radiological significance than caesium-137. The main pathway contributing to the

  14. Method for monitoring the course of oxidation of iodide ion during radioactive iodination operation

    Energy Technology Data Exchange (ETDEWEB)

    Xuezhong, Luo

    1986-05-01

    A micro-iodine ion selective electrode is developed to follow and monitor the course of oxidation of iodide ion during radioactive iodination operation. The experimental results indicate that this method can quickly respond to the course of oxidation if the reacting liquid is greater than 30 micro liter in volume. Therefore it can be used for accurate controlling the amount of oxidzing reagent used for the reaction, for example, the amount of chloroamine T can be reduced to 1/40 of the amount ordinarily used for the preparation of angiotonin II and insulin. The effect of pH and concentration of phosphate of the reacting liquid to the oxidation reaction of I with chloroamine T is also studied.

  15. Radioactive waste management

    International Nuclear Information System (INIS)

    1984-07-01

    The purpose of this document is to set out the Government's current strategy for the long term in the management of radioactive wastes. It takes account of the latest developments, and will be subject to review in the light of future developments and studies. The subject is discussed under the headings: what are radioactive wastes; who is responsible; what monitoring takes place; disposal as the objective; low-level wastes; intermediate-level wastes; discharges from Sellafield; heat generating wastes; how will waste management systems and procedures be assessed; how much more waste is there going to be in future; conclusion. (U.K.)

  16. Natural radioactivity monitoring in selected areas of the planet Earth

    International Nuclear Information System (INIS)

    Hobst, L.

    2015-01-01

    Mankind lives with the natural radioactivity throughout its development. The effects of radiation may affect to some extent the evolutionary development of life on the Earth. It is therefore important to find out what values can achieve this natural radioactivity at different places of the world. In this presentation some results of dose rate measurement during transcontinental flyers are discussed.

  17. Radioactive Waste Repositories Administration - SURAO

    International Nuclear Information System (INIS)

    Kucerka, M.

    1998-01-01

    The Atomic Act specifies, among other things, responsibilities of the government in the field of safe disposal of radioactive wastes. To satisfy this responsibility, the Ministry of Industry and Trade has established the Radioactive Waste Repositories Administration (SURAO). SURAO's major responsibilities include: (a) the preparation, construction, commissioning, operation, and decommissioning of radioactive waste repositories and the monitoring of their environmental impacts; (b) radioactive waste management; (c) spent or irradiated nuclear fuel processing into a form suitable for storage/disposal or reuse; (d) record-keeping of received radioactive wastes and their producers; (e) administration of fund transfers as stipulated by the Atomic Act, Article 27; (f) development of proposals for specification of fees to be paid to the Nuclear Account; (g) responsibility for and coordination of research and development in the field of radioactive waste handling and management; (h) supervision of licensees' margin earmarked for the decommissioning of their facilities; (i) providing services in radioactive waste handling and management; (j) handling and management of radioactive wastes that have been transferred to the Czech Republic from abroad and cannot be sent back; (k) interim administration of radioactive wastes that have become state property. The Statute of the Administration is reproduced in full. (P.A.)

  18. Radioactivity in the Romanian Black Sea sector one decade after Chernobyl

    International Nuclear Information System (INIS)

    Bologa, A.S.; Patrascu, V.

    1997-01-01

    Radioactivity monitoring in the marine environment was imposed by the increasing development of nuclear energetics and its world-wide use in many different activities. Spatial and temporal monitoring of marine radioactivity along the Romanian Black Sea shore has been systematically performed by the Romanian Marine Research Institute (RMRI), in close co-operation with the Research Laboratory of Environmental Radioactivity (RLER) belonging to the Institute of Meteorology and Hydrology (until 1990) and to the Research Institute for Environmental Engineering (REIE) afterwards, since 1991

  19. Measurement of radioactivity in the atmosphere and pollution nearby an atomic centre

    International Nuclear Information System (INIS)

    Labeyrie, J.; Weill, J.

    1955-01-01

    The French Atomic Energy Commission (CEA) is particularly interested in studies on atmospheric radioactivity by reason of the necessity to control the atmosphere nearby nuclear plants as uranium mines, nuclear reactors and hot laboratories or radioactive materials treatment plants. Thus, the CEA developed different apparatus to control and monitor the atmosphere nearby its sites. These air monitors are essentially of two types: the first one, called 'Babar', monitors smokes, fogs and dusts, the second type is an ionization chamber and measures the concentration of radioactive gas in the air. The functioning and sensitivity of these two systems are discussed. (M.P.)

  20. Radioactivity monitoring by the official monitoring stations in North-Rhine Westphalia and the Juelich Nuclear Research Centre after the Chernobyl reactor accident

    International Nuclear Information System (INIS)

    1986-01-01

    This official report presents a governmental declaration of the prime minister of NRW, Mr. Rau, concerning the reactor accident at Chernobyl, and a joint declaration of ministers of NRW, concerning the impact of the accident on the Land NRW. These statements are completed by six official reports on radioactivity measurements carried out by the official monitoring stations of the Land and by the KFA Juelich. These reports inform about methods, scope, and results of the measuring campaigns accomplished by the Zentralstelle fuer Sicherheitstechnik (ZFS), the public materials testing office (MPA), the Chemisches Untersuchungsamt, the Landesamt fuer Wasser und Abfall, and the KFA Juelich. (DG) [de

  1. Sources, classification, and disposal of radioactive wastes: History and legal and regulatory requirements

    International Nuclear Information System (INIS)

    Kocher, D.C.

    1991-01-01

    This report discusses the following topics: (1) early definitions of different types (classes) of radioactive waste developed prior to definitions in laws and regulations; (2) sources of different classes of radioactive waste; (3) current laws and regulations addressing classification of radioactive wastes; and requirements for disposal of different waste classes. Relationship between waste classification and requirements for permanent disposal is emphasized; (4) federal and state responsibilities for radioactive wastes; and (5) distinctions between radioactive wastes produced in civilian and defense sectors

  2. A field strategy to monitor radioactivity associated with investigation derived wastes returned from deep drilling sites

    International Nuclear Information System (INIS)

    Rego, J.H.; Smith, D.K.; Friensehner, A.V.

    1995-01-01

    The U.S. Department of Energy, Nevada Operations Office, Underground Test Area Operable Unit (UGTA) is drilling deep (>1500m) monitoring wells that penetrate both unsaturated (vadose) and saturated zones potentially contaminated by sub-surface nuclear weapons testing at the Nevada Test Site, Nye County, Nevada. Drill site radiological monitoring returns data on drilling effluents to make informed management decisions concerning fluid management. Because of rapid turn-around required for on-site monitoring, a representative sample will be analyzed simultaneously for α, β and γ emitters by instrumentation deployed on-site. For the purposes of field survey, accurate and precise data is returned, in many cases, with minimal sample treatment. A 30% efficient high purity germanium detector and a discriminating liquid scintillation detector are being evaluated for γ and α/β monitoring respectively. Implementation of these detector systems complements a successful on-site tritium monitoring program. Residual radioactivity associated with underground nuclear tests include tritium, activation products, fission products and actinides. Pulse shape discrimination (PSD) is used in α/β liquid scintillation counting and is a function of the time distribution of photon emission. In particular, we hope to measure 241 Am produced from 241 Pu by β decay. Because 241 Pu is depleted in fissile bomb fuels, maximum PSD resolution will be required. The high purity germanium detector employs a multichannel analyzer to count gamma emitting radionuclides; we will designate specific window configurations to selectively monitor diagnostic fission product radionuclides (i.e., 137 Cs)

  3. Environmental monitoring programme

    International Nuclear Information System (INIS)

    1991-08-01

    During 1989 there were about 1000 premises in England and Wales authorised to discharge radioactive wastes. The majority of these premises consisted of hospitals, universities and industrial, research or manufacturing centres. Discharges from these premises when made in accordance with the strict conditions specified in their authorisations will have been of little radiological significance. In the case of nuclear sites authorisations or approvals are issued jointly by the DoE and the Ministry of Agriculture, Fisheries and Food (MAFF) known collectively as the Authorising Departments. In Wales these functions are undertaken by the Welsh Office with the support of HMIP and MAFF. The Authorising Departments specify numerical limits on the amounts of radioactivity which operators may discharge to the environment. In addition operators are required to demonstrate that the best practicable means (BPM) to minimise discharges is undertaken. Operators are also required to carry out appropriate environmental monitoring to demonstrate the effectiveness of BPM. As part of their regulatory functions the Authorising Departments undertake their own environmental monitoring programmes to act as both a check on site operator's returns and to provide independent data on the exposure of the public. HM Inspectorate of Pollution has monitored levels of radioactivity in drinking water sources for many years and published results annually. MAFF undertakes two programmes to monitor radioactivity in the aquatic environment and in terrestrial foodstuffs and publishes annual reports. Environmental monitoring programmes undertaken by both nuclear site operators and government departments are summarised. (author)

  4. Environmental radioactivity monitoring at Kakuma campus of Kanazawa University after the accident of Fukushima nuclear power plant

    International Nuclear Information System (INIS)

    Nakai, Miki; Kimura, Hajime; Yokoyama, Akihiko; Nagamura, Yuichiro; Nakanishi, Takashi; Uesugi, Masaki

    2011-01-01

    The Nuclear power plant accident at Fukushima caused by the earthquake and tsunami disaster in March, 2011 led the public to fear the considerable-range contamination with radioactivity. For the reason, we started environmental monitoring on radioactivity just outside of the RI facility in the Kakuma campus of Kanazawa Univ. A high-volume dust sampler (SHIBATA, HV-1000) was used to collect air dust onto a filter and rain water was collected in a plastic container placed on the rooftop of the facility as well. The samples were assayed by gamma-ray spectrometer with germanium detectors to obtain the concentrations of I-131, Cs-134, and Cs-137. The data were compared with those measured in the other areas in Japan to discuss how the activities diffused and migrated from the plant to many places in Japan. The peaking dates of the activities coincided with those by a trajectory calculation of air from Fukushima. The trend was confirmed for the other data in other areas. (author)

  5. An evaluation of in vivo sensitivity via public monitoring

    Energy Technology Data Exchange (ETDEWEB)

    Webb, J.L.; Kirchner, T.B

    2000-07-01

    Citizen volunteers from the Carlsbad, New Mexico area were monitored for internally deposited radionuclides through a project entitled 'Lie Down and Be Counted'. This project is provided as an outreach service to the public to support education about naturally occurring and man-made radioactivity present in people and the environment prior to the opening of the Waste Isolation Pilot Plant (WIPP). The bioassay measurements consisted of a lung and whole-body count. Prior to their bioassay, each subject completed a lifestyle questionnaire which included questions regarding their age, sex, weight, height, ethnicity, occupation, foreign travel, wild game consumption, smoking habit and any nuclear medicine procedures. Since a majority of these radionuclides were not detectable in local residents, a primary focus of the study was to evaluate the variability of human background and the implications with respect to measurement sensitivity. (author)

  6. Adaptation of a Data Acquisition System for Monitoring Air Quality and Radioactivity

    International Nuclear Information System (INIS)

    Ramadan, A.B.; Hefnawi, M.; Hefnaw, M.

    2006-01-01

    the main aim from this work is adapting the data acquisition system for monitoring air quality and radioactivity to save cost, time and effort. the adaptation processes are not only based on rectifying drawbacks but also modifying new features for both systems.these drawbacks are hardware problems and software problems for both systems which cause more operation cost, more operation time and more human effort these new features are modified to achieve the grown user requirements, better performance, more flexibility for customization and better user acceptance the adaptation method is implemented by determining: how exactly two systems work, components for each system and relationships between them, which components need adaptation, and finally suitable adaptation procedure for each component with maintaining the relationships between them the proposed systems overcome the above-mentioned drawbacks associated with the old systems and have new facilities to verify their main goals

  7. Integrated Closure and Monitoring Plan for the Area 3 and Area 5 Radioactive Waste Management Sites at the Nevada Test Site

    Energy Technology Data Exchange (ETDEWEB)

    S. E. Rawlinson

    2001-09-01

    Bechtel Nevada (BN) manages two low-level Radioactive Waste Management Sites (RWMSs) (one site is in Area 3 and the other is in Area 5) at the Nevada Test Site (NTS) for the U.S. Department of Energy's (DOE's) National Nuclear Security Administration Nevada Operations Office (NNSA/NV). The current DOE Order governing management of radioactive waste is 435.1. Associated with DOE Order 435.1 is a Manual (DOE M 435.1-1) and Guidance (DOE G 435.1-1). The Manual and Guidance specify that preliminary closure and monitoring plans for a low-level waste (LLW) management facility be developed and initially submitted with the Performance Assessment (PA) and Composite Analysis (CA) for that facility. The Manual and Guidance, and the Disposal Authorization Statement (DAS) issued for the Area 3 RWMS further specify that the preliminary closure and monitoring plans be updated within one year following issuance of a DAS. This Integrated Closure and Monitoring Plan (ICMP) fulfills both requirements. Additional updates will be conducted every third year hereafter. This document is an integrated plan for closing and monitoring both RWMSs, and is based on guidance issued in 1999 by the DOE for developing closure plans. The plan does not follow the format suggested by the DOE guidance in order to better accommodate differences between the two RWMSs, especially in terms of operations and site characteristics. The modification reduces redundancy and provides a smoother progression of the discussion. The closure and monitoring plans were integrated because much of the information that would be included in individual plans is the same, and integration provides efficient presentation and program management. The ICMP identifies the regulatory requirements, describes the disposal sites and the physical environment where they are located, and defines the approach and schedule for both closing and monitoring the sites.

  8. 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

  9. Radioactivity in foodstuffs 1988

    International Nuclear Information System (INIS)

    1989-01-01

    The average radioactivity dose level to which the Norwegian population was exposed through the ingestion of food in 1988 was between 0.10 and 0.15 mSv. This was about the same as in 1987. The radioactivity dose to which individuals with certain special dietary habits (large proportions of freshwater fish and reindeer meat in the diet) were exposed, was, however, up to three times higher in 1988 than in 1987. This was due firstly to the fact that reindeer meat which had been produced prior to the Chernobyl accident was no longer available, and secondly, to dietary advice not being followed as closely as before. The cost-benefit ratio of the measures introduced to reduce radioactivity levels in food, i.e. resources employed compared with the actual reduction in radioactivity levels achieved, has proved to be reasonably satisfactory, both in 1987 and 1988. Action levels and dietary advice remained unchanged in 1988. The present report summarizes results of analyses performed in 1988, and describes the measures introduced concerning various categorites of foods. Measures introduced were, as in 1987, primarily focused on the production of sheep meat (mutton/lamb) and on reindeer farming. 4 figs., 1 tab

  10. 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

  11. The fractal nature of the european network for airborne radioactivity monitoring and its implications for the detectability of radioactive clouds

    International Nuclear Information System (INIS)

    Raes, F.; Graziani, G.

    1990-01-01

    Both the European Communities (EC) and the International Atomic Energy Agency (IAEA) have agreed upon a rapid exchange of radiological data among their member states, in case of nuclear emergencies. This will happen through an information network operated by the Commission of the European Communities (CEC) and/or through the Global Telecommunications System of WMO. Data coming from nation wide on-line monitoring networks will be among the very first to be exchanged. They will constitute an important source of information for the real-time assessment of the situation after large accidents with national and international impact. In particular when data on airborne radioactivity are availably early after an accidental release, they might be used to update long range transport model predictions for the period to follow. It is therefore important to analyze the national networks in an international context, to see what information they can offer and what limitations exist

  12. Status of radioactivity monitoring in French Polynesia in 2010 and follow up of the Fukushima accident impact in French Polynesia and New Caledonia from March to May 2011

    International Nuclear Information System (INIS)

    Bouisset, P.; Bernagout, S.; Leclerc, G.; Rua, J.; Delabbaye, P.; CAGNAT, X.; Jonhson, I.; Taputu, G.; Paeamara, H.; Tamarii, R.; Temarohirani, T.; Flores, T.

    2012-01-01

    Radiological monitoring of the French environment is one of IRSN's permanent tasks as part of public policy on nuclear safety and radiological protection. It is helping to guarantee the best possible protection of the population. Exercised in Polynesia since 1962, this monitoring, which takes place on seven islands (Tahiti, Maupiti, Hao, Rangiroa, Hiva Oa, Mangareva and Tubuai) representing the five archipelagos, consists of taking regular samples of various kinds from the different environmental compartments (air, water, soil, food..) with which the population may be in contact. Regarding food, the samples analyzed are representative of the diet of Polynesians living in the five archipelagos of that territory, and from the marine environment of the open sea, marine and terrestrial lagoon. Almost all samples are measured at the Laboratory for the Study and Monitoring of the Environment IRSN, based in Vairao on the island of Tahiti. During the year 2010 results fall under the continuity of a regular reduction of the levels of radioactivity since the stop, in 1974, of the French atmospheric tests. This residual radioactivity relates to primarily the 137 Cs. In term of additional dose, this artificial and residual radioactivity is lower than 5 μSv.y -1 (5 micro-Sieverts per year). This value corresponds to less than 0,5 % of exposure due to natural radioactivity in Polynesia (approximately 1 000 μSv.y -1 ). This 2010 report also includes the special monitoring engaged during spring 2011 to evaluate a possible radiological impact in French Polynesia and New-Caledonia territories due to the nuclear accident of Fukushima that occurred on March 11, 2011 (see chapter 5). (authors)

  13. Monitoring of radioactivity in the environment 201; Overvaking av radioaktivitet i omgivnadene 2011. Resultat fraa Straalevernet sine Radnett- og luftfilterstasjonar og fraa Sivilforsvaret si radacmaaleteneste

    Energy Technology Data Exchange (ETDEWEB)

    Moeller, B.; Dyve, J.E.; Tazmini, K.

    2013-03-01

    The Report summarizes the data from Norwegian Radiation Protection Authority and The Norwegian Civil Defence monitoring programs for radioactivity in the environment in 2011. A short description of the systems is also presented.(Author)

  14. Regulations under the Radioactive Substances Act of 1958, No. 115, 1961

    International Nuclear Information System (INIS)

    1961-01-01

    These very detailed regulations lay down the licensing system for the use of radioactive materials. They provide for monitoring and control of radiation and radiation contamination, storage, labelling and transport of radioactive materials and also for the disposal of radioactive waste. (NEA) [fr

  15. α-amylase assay and action pattern determination using radioactive substrate, HPLC, and a radioactive flow detector

    International Nuclear Information System (INIS)

    Marsili, R.T.; Ostapenko, H.

    1987-01-01

    A new assay system is presented for the analysis of α-amylase. The disappearance of 14 C-labeled starch substrate and the appearance of its radioactive degradation products were monitored by HPLC and a radioactive flow detector/integrator. The hydrolysis of radioactive substrate was proportional to enzyme concentration when two commercially available α-amylase preparations of Bacillus subtilis origin were studied. The method demonstrated an average recovery of 101.7 +/- 6.5% when modified food starch was spiked with amylase and analyzed. In addition, the method was shown to be useful for predicting detailed action patterns of various types of amylases

  16. Scanning personnel for internal deposition of radioactive material with personnel contamination whole body friskers and portal monitors

    International Nuclear Information System (INIS)

    Lobdell, J.L.

    1996-01-01

    The potential for using personnel contamination devices such as whole body friskers and portal monitors for internal contamination monitoring was evaluated. Internally deposited radioactive material is typically determined with whole body counting systems. Whole body counts have traditionally been performed on personnel when they report for work, on a periodic basis (i.e., annually), when an uptake is suspected, and on termination. These counts incur significant expense. The monitored personnel pass through whole body friskers and portal monitors daily. This investigation was performed to determine if the external contamination monitors could provide an alternative to the more Costly whole body counting. The ability to detect 1% of a DAC for critical radioisotopes was applied as a detection criteria for this investigation. The results of whole body counts were used to identify the typical internal contamination radionuclides. From this list, the radioisotopes that would be the most difficult to measure were identified. From this review, 60 Co and 131 I were determined to be the critical radionuclides. One percent of a DAC for each isotope was placed, one at a time, in a humanoid phantom. The phantom was placed in the whole body frisker and open-quotes countedclose quotes. The phantom was carried through the portal monitor at a speed equivalent to a person walking through the monitor. Frequency of detection was derived for both systems. Practical aspects of integrating this screening system with traditional internal dosimetry programs are discussed

  17. Automatic checking system of radioactivity in motor-cars 'AKKORD'

    International Nuclear Information System (INIS)

    Kuechler, L.; Seidler, M.; Zierenberg, B.

    1994-01-01

    A monitoring device has been developed for an automated checking of all vehicles leaving or entering a nuclear installation against uncontrolled lost of radioactive material. This device is an excellent tool for radioactive material flow control. (orig.) [de

  18. Results of radioactivity surveys in Miyagi Prefecture

    International Nuclear Information System (INIS)

    1983-01-01

    The results of radioactivity surveys carried out in Miyagi Prefecture in fiscal 1981 (from April, 1981, to March, 1982), entrusted by the Science and Technology Agency, are presented in tables: total β radioactivity in rainwater, in rainwater and dust collected by large basins, in daily foods, in land water, in dairy products and vegetables, in marine products and in soil, 131 I nuclide in cow's milk, air γ-ray dose rate by survey meters, and air γ-ray counting, rate by a monitoring post were examined. The total β radioactivity was measured by a GM counting apparatus with an automatic sample changer, the nuclide analysis by a NaI(Tl) scintillation spectrometer, the air γ-ray dose rate by a NaI(Tl) scintillation survey meter, and the γ-ray counting rate by a NaI(Tl) scintillation type monitoring post. (Mori, K.)

  19. Summary of industrial impacts from recycled radioactive scrap metals

    International Nuclear Information System (INIS)

    Dehmel, J.-C.; Harrop, J.; MacKinney, J.A.

    1995-01-01

    During operation, decontamination, and dismantlement, nuclear facilities are generating significant quantities of radioactive scrap metal (RSM). Future decommissioning will generate even more RSM. The petroleum industry also generates RSM in the form of equipment contaminated with naturally occurring radioactivity. Finally, the accidental melting of radioactive sources in steel mills has generated smaller amounts of contaminated metals. Steel mills, smelters, and foundries could recycle these materials, which might then appear in finished products or as feedstocks used by other industries. If introduced in this manner, residual radioactivity can adversely affect the performance of certain products. Such products include computers and other devices that rely on integrated circuits. The most important effect of residual radioactivity on integrated circuits is a phenomenon known as 'single event upsets or soft errors.' Radioactivity can also adversely affect the performance of products such as photographic film and components designed to measure the presence of radioactivity. Radioactivity that raises background count-rates to higher levels could affect the performance of radiation monitoring systems and analytical equipment. Higher background count-rates would lead to reduced sensitivity and lower resolution in spectroscopic systems. The computer, photographic, and radiation measurement industries have taken steps to minimize the impact of residual radioactivity on their products. These steps include monitoring manufacturing processes, specifying material acceptance standards, and screening suppliers. As RSM is recycled, these steps may become more important and more costly. This paper characterizes potentially impacted industries and vulnerability and effects due to the presence of residual radioactivity. Finally, the paper describes practices used to limit the impact of residual radioactivity. (J.P.N.)

  20. Comparative testing of slurry monitors

    International Nuclear Information System (INIS)

    Hylton, T.D.; Bayne, C.K.; Anderson, M.S.; Van Essen, D.C.

    1998-05-01

    The US Department of Energy (DOE) has millions of gallons of radioactive liquid and sludge wastes that must be retrieved from underground storage tanks, transferred to treatment facilities, and processed to a final waste form. The wastes will be removed from the current storage tanks by mobilizing the sludge wastes and mixing them with the liquid wastes to create slurries. Each slurry would then be transferred by pipeline to the desired destination. To reduce the risk of plugging a pipeline, the transport properties (e.g., density, suspended solids concentration, viscosity, particle size range) of the slurry should be determined to be within acceptable limits prior to transfer. These properties should also be monitored and controlled within specified limits while the slurry transfer is in progress. The DOE issued a call for proposals for developing on-line instrumentation to measure the transport properties of slurries. In response to the call for proposals, several researchers submitted proposals and were funded to develop slurry monitoring instruments. These newly developed DOE instruments are currently in the prototype stage. Before the instruments were installed in a radioactive application, the DOE wanted to evaluate them under nonradioactive conditions to determine if they were accurate, reliable, and dependable. The goal of this project was to test the performance of the newly developed DOE instruments along with several commercially available instruments. The baseline method for comparison utilized the results from grab-sample analyses

  1. Radioactivity monitoring of life environment in the Republic of Croatia, Report for 2004 - IMI-CRZ-81

    International Nuclear Information System (INIS)

    2005-01-01

    The radioactivity measurement programme in the environment of Republic of Croatia for 2004 is continuation of measurements that have started in 1959. Sampling, radiochemical analyses and measurements were carried out by the Radiation Protection Unit, Institute for Medical Research and Occupational Health, Zagreb. The scope of the monitoring of contamination in the environmental samples according to the European Commission recommendations of 8 June 2000, was to collect samples of air, fallout, soil, water, alimentary products and fodder. The purpose of these investigations is to collect as many data as possible for the assessment of radiation risk to man. (author)

  2. Storing solid radioactive wastes at the Savannah River Plant

    International Nuclear Information System (INIS)

    Horton, J.H.; Corey, J.C.

    1976-06-01

    The facilities and the operation of solid radioactive waste storage at the Savannah River Plant (SRP) are discussed in the report. The procedures used to segregate and the methods used to store radioactive waste materials are described, and the monitoring results obtained from studies of the movement of radionuclides from buried wastes at SRP are summarized. The solid radioactive waste storage site, centrally located on the 192,000-acre SRP reservation, was established in 1952 to 1953, before any radioactivity was generated onsite. The site is used for storage and burial of solid radioactive waste, for storage of contaminated equipment, and for miscellaneous other operations. The solid radioactive waste storage site is divided into sections for burying waste materials of specified types and radioactivity levels, such as transuranium (TRU) alpha waste, low-level waste (primarily beta-gamma), and high-level waste (primarily beta-gamma). Detailed records are kept of the burial location of each shipment of waste. With the attention currently given to monitoring and controlling migration, the solid wastes can remain safely in their present location for as long as is necessary for a national policy to be established for their eventual disposal. Migration of transuranium, activation product, and fission product nuclides from the buried wastes has been negligible. However, monitoring data indicate that tritium is migrating from the solid waste emplacements. Because of the low movement rate of ground water, the dose-to-man projection is less than 0.02 man-rem for the inventory of tritium in the burial trenches. Limits are placed on the amounts of beta-gamma waste that can be stored so that the site will require minimum surveillance and control. The major portion (approximately 98 percent) of the transuranium alpha radioactivity in the waste is stored in durable containers, which are amenable to recovery for processing and restorage should national policy so dictate

  3. Estimation of global inventories of radioactive waste and other radioactive materials

    International Nuclear Information System (INIS)

    2008-06-01

    A variety of nuclear activities have been carried out in the second part of the twentieth century for different purposes. Initially the emphasis was on military applications, but with the passage of time the main focus of nuclear activities has shifted to peaceful uses of nuclear energy and to the use of radioactive material in industry, medicine and research. Regardless of the objectives, the nuclear activities generate radioactive waste. It was considered worthwhile to produce a set of worldwide data that could be assessed to evaluate the legacy of the nuclear activities performed up to the transition between the twentieth and the twenty first century. The assessment tries to cover the inventory of all the human produced radioactive material that can be considered to result from both military and civilian applications. This has caused remarkable difficulties since much of the data, particularly relating to military programmes, are not readily available. Consequently the data on the inventory of radioactive material should be considered as order-of-magnitude approximations. This report as a whole should be considered as a first iteration in a continuing process of updating and upgrading. The accumulations of radioactive materials can be considered a burden for human society, both at present and in the future, since they require continuing monitoring and control. Knowing the amounts and types of such radioactive inventories can help in the assessment of the relative burdens. Knowledge of the national or regional radioactive waste inventory is necessary for planning management operations, including the sizing and design of conditioning, storage and disposal facilities. A global inventory, either of radioactive waste or of other environmental accumulations of radioactive material, could be used to provide a perspective on the requirements and burdens associated with their management, by means of comparisons with the burdens caused by other types of waste or other

  4. A New Approach for the Determination of Dose Rate and Radioactivity for Detected Gamma Nuclides Using an Environmental Radiation Monitor Based on an NaI(Tl) Detector.

    Science.gov (United States)

    Ji, Young-Yong; Kim, Chang-Jong; Lim, Kyo-Sun; Lee, Wanno; Chang, Hyon-Sock; Chung, Kun Ho

    2017-10-01

    To expand the application of dose rate spectroscopy to the environment, the method using an environmental radiation monitor (ERM) based on a 3' × 3' NaI(Tl) detector was used to perform real-time monitoring of the dose rate and radioactivity for detected gamma nuclides in the ground around an ERM. Full-energy absorption peaks in the energy spectrum for dose rate were first identified to calculate the individual dose rates of Bi, Ac, Tl, and K distributed in the ground through interference correction because of the finite energy resolution of the NaI(Tl) detector used in an ERM. The radioactivity of the four natural radionuclides was then calculated from the in situ calibration factor-that is, the dose rate per unit curie-of the used ERM for the geometry of the ground in infinite half-space, which was theoretically estimated by Monte Carlo simulation. By an intercomparison using a portable HPGe and samples taken from the ground around an ERM, this method to calculate the dose rate and radioactivity of four nuclides using an ERM was experimentally verified and finally applied to remotely monitor them in real-time in the area in which the ERM had been installed.

  5. ANSTO's radioactive waste management policy. Preliminary environmental review

    International Nuclear Information System (INIS)

    Levins, D.M.; Airey, P.; Breadner, B.; Bull, P.; Camilleri, A.; Dimitrovski, L.; Gorman, T.; Harries, J.; Innes, R.; Jarquin, E.; Jay, G.; Ridal, A.; Smith, A.

    1996-05-01

    For over forty years, radioactive wastes have been generated by ANSTO (and its predecessor, the AAEC) from the operation of nuclear facilities, the production of radioisotopes for medical and industrial use, and from various research activities. the quantities and activities of radioactive waste currently at Lucas Heights are very small compared to many other nuclear facilities overseas, especially those in countries with nuclear power program. Nevertheless, in the absence of a repository for nuclear wastes in Australia and guidelines for waste conditioning, the waste inventory has been growing steadily. This report reviews the status of radioactive waste management at ANSTO, including spent fuel management, treatment of effluents and environmental monitoring. It gives details of: relevant legislative, regulatory and related requirements; sources and types of radioactive waste generated at ANSTO; waste quantities and activities (both cumulative and annual arisings); existing practices and procedures for waste management and environmental monitoring; recommended broad strategies for dealing with radioactive waste management issues. Detailed proposals on how the recommendations should be implemented is the subject of a companion internal document, the Radioactive Waste Management Action Plan 1996-2000 which provides details of the tasks to be undertaken, milestones and resource requirements. 44 refs., 2 tabs., 18 figs

  6. Measurement comparisons of radioactivity among European monitoring laboratories for the environment and food stuff

    International Nuclear Information System (INIS)

    Waetjen, U.; Spasova, Y.; Altzitzoglou, T.

    2008-01-01

    For more than 15 years, European Union (EU) laboratories monitoring environmental radioactivity have been obliged to participate in measurement comparisons organised by the European Commission. After a short review of comparisons conducted during the 1990s, the approach of IRMM organising these comparisons since 2003 is presented. It relies on the provision of comparison samples with reference values traceable to the International Reference System for radionuclides (SIR). The results of the most recent comparison, the determination of 40 K, 90 Sr and 137 Cs in milk powder, are presented. The influence of repetitive participation in measurement comparisons on laboratory performance is studied on the basis of data from more than 20 laboratories having participated in several exercises during the last 15 years

  7. Resuspension. Decadal monitoring time series of the anthropogenic radioactivity deposition in Japan

    International Nuclear Information System (INIS)

    Igarashi, Yasuhito; Aoyama, Michio; Hirose, Katsumi; Miyao, Takashi; Nemoto, Kazuhiro; Tomita, Masatoshi; Fujikawa, Takashi

    2003-01-01

    Monthly atmospheric depositions of 90 Sr and 137 Cs have been observed at the Meteorological Research Institute (MRI), Tsukuba, Japan. This study reports temporal trends and levels of 90 Sr and 137 Cs depositions in the 1990s. Although the current 90 Sr and 137 Cs concentrations declined dramatically, they have been found continuously in the deposition samples throughout the 1990s. During this period, the annual 90 Sr ( 137 Cs) deposits at MRI ranged from 70-180 (140-350) mBq/m 2 /year. With a sufficiently long time series, the decreasing trend of the deposition evidently differs from the past stratospheric fallout; it is far slower. Thus, reservoirs other than the stratosphere provide small amounts of 90 Sr and 137 Cs to the atmosphere. A simple calculation clearly refutes the significance of the ocean as a potential source of airborne anthropogenic radioactivity. We will demonstrate that these radionuclides in the deposited materials originate from resuspension processes (soil dust suspension processes). The temporal trends of the time series monitoring reveal differences from those in the United Nations Scientific Committee on the Effects of Atomic Radiation (UNSCEAR) Report 2000, which were predicted by a model that disregarded resuspension. The specific activity of 90 Sr ( 137 Cs) in the annual depositions exhibited a 10-year (20-year) half-life. Those data were comparable with values reported in the literature for the half-residence time (HRT) of 90 Sr and 137 Cs in Japanese surface soils. They were also comparable to those calculated from nationwide data of 90 Sr and 137 Cs concentrations in the surface soil (0-10 cm) obtained from the Ministry of Education, Culture, Sports, Science and Technology Environmental Radiation Database (the MEXT Database). Regarding the activity ratio of 137 Cs/ 90 Sr, the Japanese nationwide surface soil data collected during the 1990s in the MEXT Database (median: 5.3, n=584) did not accord with that in the deposition samples

  8. Development of monitoring technology for environmental radioactivity

    International Nuclear Information System (INIS)

    Lee, Chang Woo; Cho, Young Hyun; Lee, M. H.; Choi, K. S.; Hong, K. H.; Sin, H. S.; Kim, M. K.; Pak, J. H.

    2000-05-01

    The accurate and reliable determination techniques of the radioactive isotopes in environmental samples are very important to protect public health from the potential hazards of radiation. Isolation and purification of radiostrontium from environmental aqueous sample was performed by using strontium selectively binding resin (Sr-spec) and strontium selectively permeable liquid membrane. Radioactivity of radiostrontium was measured by liquid scintillation counter coupled with dual counting window and spectrum unfolding method. With combustion apparatus a new determination of Tc-99 in the environmental samples was developed for overcoming demerits of conventional TBP extraction method. An optimized method for determining beta-emitting 2 41Pu in the presence of alpha-emitting nuclides was developed using a liquid scintillation counting system. A method for measuring Rn-222 and Ra-226 in aqueous sample using liquid scintillation counting technique has studied. On-line measurement system coupled with ion chromatography and portable liquid scintillation detector was developed. U and Th measured by inductively coupled plasma mass spectrometry (ICP-MS). The mehtod of flow-injection preconcentration for the analysis of U and Th in seawater was developed. A new electrodeposition method for alpha spectrometry was developed

  9. Development of monitoring technology for environmental radioactivity

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Chang Woo; Cho, Young Hyun; Lee, M. H.; Choi, K. S.; Hong, K. H.; Sin, H. S.; Kim, M. K.; Pak, J. H

    2000-05-01

    The accurate and reliable determination techniques of the radioactive isotopes in environmental samples are very important to protect public health from the potential hazards of radiation. Isolation and purification of radiostrontium from environmental aqueous sample was performed by using strontium selectively binding resin (Sr-spec) and strontium selectively permeable liquid membrane. Radioactivity of radiostrontium was measured by liquid scintillation counter coupled with dual counting window and spectrum unfolding method. With combustion apparatus a new determination of Tc-99 in the environmental samples was developed for overcoming demerits of conventional TBP extraction method. An optimized method for determining beta-emitting {sup 2}41Pu in the presence of alpha-emitting nuclides was developed using a liquid scintillation counting system. A method for measuring Rn-222 and Ra-226 in aqueous sample using liquid scintillation counting technique has studied. On-line measurement system coupled with ion chromatography and portable liquid scintillation detector was developed. U and Th measured by inductively coupled plasma mass spectrometry (ICP-MS). The mehtod of flow-injection preconcentration for the analysis of U and Th in seawater was developed. A new electrodeposition method for alpha spectrometry was developed.

  10. A method of and apparatus for, monitoring the radioactivity of a plurality of samples incorporating lower energy beta-emitting isotopes

    International Nuclear Information System (INIS)

    Warner, G.T.; Potter, C.G.

    1981-01-01

    A method for monitoring the radioactivity of a number of samples incorporating low energy beta-emitting isotopes which allows the simultaneous precipitation of many samples with a minimum of sample handling, is described. The samples are placed on a support so that they are not overlapping, the support and sample are permeated with liquid or gel scintillant and the sample areas are scanned. (U.K.)

  11. Application of plastic scintillation detector in the construction of a monitoring system of radioactive contamination in water

    International Nuclear Information System (INIS)

    Morgado, Mario Monteiro; Moraes, Marco Antonio P.V. de; Madi Filho, Tufic

    1996-01-01

    Plastic scintillation detector system has been set up and used gamma ray radiation monitoring purpose in water. In order to determine its relative efficiency characteristics, several conventional solids gamma source has been used in the energy from 60 keV to 133 keV. The efficiency variation in this interval was from 31.8% to 13.2%, respectively and at 661.6 keV was 21.3 % +-0.86%. The sensibility of the system has been determined for use a 131 I radioactive solution as 41.25 kBq/m 3 . (author)

  12. 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

  13. Predisposal Management of Radioactive Waste. General Safety Requirements Pt. 5

    International Nuclear Information System (INIS)

    2010-01-01

    There are a large number of facilities and activities around the world in which radioactive material is produced, handled and stored. This Safety Requirements publication presents international consensus requirements for the management of radioactive waste prior to its disposal. It provides the safety imperatives on the basis of which facilities can be designed, operated and regulated. The publication is supported by a number of Safety Guides that provide up to date recommendations and guidance on best practices for management of particular types of radioactive waste, for storage of radioactive waste, for assuring safety by developing safety cases and supporting safety assessments, and for applying appropriate management systems. Contents: 1. Introduction; 2. Protection of human health and the environment; 3. Responsibilities associated with the predisposal management of radioactive waste; 4. Steps in the predisposal management of radioactive waste; 5. Development and operation of predisposal radioactive waste management facilities and activities; Annex: Predisposal management of radioactive waste and the fundamental safety principles.

  14. Predisposal Management of Radioactive Waste. General Safety Requirements Pt. 5

    International Nuclear Information System (INIS)

    2009-01-01

    There are a large number of facilities and activities around the world in which radioactive material is produced, handled and stored. This Safety Requirements publication presents international consensus requirements for the management of radioactive waste prior to its disposal. It provides the safety imperatives on the basis of which facilities can be designed, operated and regulated. The publication is supported by a number of Safety Guides that provide up to date recommendations and guidance on best practices for management of particular types of radioactive waste, for storage of radioactive waste, for assuring safety by developing safety cases and supporting safety assessments, and for applying appropriate management systems. Contents: 1. Introduction; 2. Protection of human health and the environment; 3. Responsibilities associated with the predisposal management of radioactive waste; 4. Steps in the predisposal management of radioactive waste; 5. Development and operation of predisposal radioactive waste management facilities and activities; Annex: Predisposal management of radioactive waste and the fundamental safety principles.

  15. The Radioactive Waste Management at Studsvik

    Energy Technology Data Exchange (ETDEWEB)

    Hedlund, R; Lindskog, A

    1966-04-15

    The report was originally prepared as a contribution to the discussions in an IAEA panel on economics of radioactive waste management held in Vienna from 13 - 17 December 1965. It contains the answers and comments to the questions of a questionnaire for the panel concerning the various operations associated with the management (collection, transport, treatment, discharge, storage, and operational monitoring) of: - radioactive liquid wastes, except high-level effluents from reactor fuel recovering operations; - solid wastes, except those produced from treatment of high level wastes; - gaseous wastes produced from treatment of the foregoing liquid and solid wastes; - equipment decontamination facilities and radioactive laundries.

  16. The Radioactive Waste Management at Studsvik

    International Nuclear Information System (INIS)

    Hedlund, R.; Lindskog, A.

    1966-04-01

    The report was originally prepared as a contribution to the discussions in an IAEA panel on economics of radioactive waste management held in Vienna from 13 - 17 December 1965. It contains the answers and comments to the questions of a questionnaire for the panel concerning the various operations associated with the management (collection, transport, treatment, discharge, storage, and operational monitoring) of: - radioactive liquid wastes, except high-level effluents from reactor fuel recovering operations; - solid wastes, except those produced from treatment of high level wastes; - gaseous wastes produced from treatment of the foregoing liquid and solid wastes; - equipment decontamination facilities and radioactive laundries

  17. Monitoring plan for routine organic air emissions at the Radioactive Waste Management Complex Waste Storage Facilities

    International Nuclear Information System (INIS)

    Galloway, K.J.; Jolley, J.G.

    1994-06-01

    This monitoring plan provides the information necessary to perform routine organic air emissions monitoring at the Waste Storage Facilities located at the Transuranic Storage Area of the Radioactive Waste Management Complex at the Idaho National Engineering Laboratory. The Waste Storage Facilities include both the Type I and II Waste Storage Modules. The plan implements a dual method approach where two dissimilar analytical methodologies, Open-Path Fourier Transform Infrared Spectroscopy (OP-FTIR) and ancillary SUMMA reg-sign canister sampling, following the US Environmental Protection Agency (EPA) analytical method TO-14, will be used to provide qualitative and quantitative volatile organic concentration data. The Open-Path Fourier Transform Infrared Spectroscopy will provide in situ, real time monitoring of volatile organic compound concentrations in the ambient air of the Waste Storage Facilities. To supplement the OP-FTIR data, air samples will be collected using SUMMA reg-sign, passivated, stainless steel canisters, following the EPA Method TO-14. These samples will be analyzed for volatile organic compounds with gas chromatograph/mass spectrometry analysis. The sampling strategy, procedures, and schedules are included in this monitoring plan. The development of this monitoring plan is driven by regulatory compliance to the Resource Conservation and Recovery Act, State of Idaho Toxic Air Pollutant increments, Occupational Safety and Health Administration. The various state and federal regulations address the characterization of the volatile organic compounds and the resultant ambient air emissions that may originate from facilities involved in industrial production and/or waste management activities

  18. Report of the consultants' meeting on ''fallout radioactivity monitoring in environment and food'' (MEF), French Nuclear Research Centre, Cadarache, France, 15-17 July 1987

    International Nuclear Information System (INIS)

    1989-01-01

    The purpose of the Consultants' Meeting was to get further advice on how the knowledge and experience gained from different activities since the last meeting could be beneficially implemented in the on-going Programme on ''Fallout Radioactivity Monitoring in Environment and Food''

  19. Final disposal of radioactive waste

    Directory of Open Access Journals (Sweden)

    Freiesleben H.

    2013-06-01

    Full Text Available In this paper the origin and properties of radioactive waste as well as its classification scheme (low-level waste – LLW, intermediate-level waste – ILW, high-level waste – HLW are presented. The various options for conditioning of waste of different levels of radioactivity are reviewed. The composition, radiotoxicity and reprocessing of spent fuel and their effect on storage and options for final disposal are discussed. The current situation of final waste disposal in a selected number of countries is mentioned. Also, the role of the International Atomic Energy Agency with regard to the development and monitoring of international safety standards for both spent nuclear fuel and radioactive waste management is described.

  20. Investigation of the environmental radioactivity around the mooring port

    International Nuclear Information System (INIS)

    Tanigawa, Yoshio

    1976-01-01

    Here are the main data for radioactivity examination performed in 1975 at Mutsu port, the mooring port of atomic energy vessel ''Mutsu''. No abnormality were observed in space γ ray dose ratio, and integrated doses measured by the thermofluorescence dosimeter at three monitoring posts in the port (G M tube) and three monitoring station in Mutsu City. A serial measurement of radioactivity concentration in sea water did not show any abnormality, either. Samples were taken from the surface soil of the ground, the bottom of the rivers, river water, drinking water, and milk and measured the total radioactivity by a gas flow counter. The measurement of the total β-radioactivity and radio nuclides analysis were carried out in sea water, the soil from the bottom of the sea and sea products. Abnormality considered to be caused by ''Mutsu'' did not observed at all. (Kobatake, H.)

  1. System for disposing of radioactive waste

    International Nuclear Information System (INIS)

    Gablin, K.A.; Hansen, L.J.

    1979-01-01

    A system is described for disposing of radioactive waste material from nuclear reactors by solidifying the liquid components to produce an encapsulated mass adapted for disposal by burial. The method contemplates mixing of radioactive waste materials, with or without contained solids, with a setting agent capable of solidifying the waste liquids into a free standing hardened mass, placing the resulting liquid mixture in a container with a proportionate amount of a curing agent to effect solidification under controlled conditions, and thereafter burying the container and contained solidified mixture. The setting agent is a water-extendable polymer consisting of a suspension of partially polymerized particles of urea formaldehyde in water, and the curing agent is sodium bisulfate. Methods are disclosed for dewatering slurry-like mixtures of liquid and particulate radioactive waste materials, such as spent ion exchange resin beads, and for effecting desired distribution of non-liquid radioactive materials in the central area of the container prior to solidification, so that the surrounding mass of lower specific radioactivity acts as a partial shield against higher radioactivity of the non-liquid radioactive materials. The methods also provide for addition of non-radioactive filler materials to dilute the mixture and lower the overall radioactivity of the hardened mixture to desired Lowest Specific Activity counts. An inhibiting agent is added to the liquid mixture to adjust the solidification time, and provision is made for adding additional amounts of setting agent and curing agent to take up any free water and further encapsulate the hardened material within the container. 30 claims

  2. System for disposing of radioactive waste

    International Nuclear Information System (INIS)

    Gablin, K.A.; Hansen, L.J.

    1977-01-01

    A system is described for disposing of radioactive waste material from nuclear reactors by solidifying the liquid components to produce an encapsulated mass adapted for disposal by burial. The method contemplates mixing of radioactive waste materials, with or without contained solids, with a setting agent capable of solidifying the waste liquids into a free standing hardened mass, placing the resulting liquid mixture in a container with a proportionate amount of a curing agent to effect solidification under controlled conditions, and thereafter burying the container and contained solidified mixture. The setting agent is a water-extendable polymer consisting of a suspension of partially polymerized particles of urea formaldehyde in water, and the curing agent is sodium bisulfate. Methods are disclosed for dewatering slurry-like mixtures of liquid and particulate radioactive waste materials, such as spent ion exchange resin beads, and for effecting desired distribution of non-liquid radioactive materials in the central area of the container prior to solidification, so that the surrounding mass of lower specific radioactivity acts as a partial shield against higher radioactivity of the non-liquid radioactive materials. The methods also provide for addition of non-radioactive filler materials to dilute the mixture and lower the overall radioactivity of the hardened mixture to desired Lowest Specific Activity counts. An inhibiting agent is added to the liquid mixture to adjust the solidification time, and provision is made for adding additional amounts of setting agent and curing agent to take up any free water and further encapsulate the hardened material within the container

  3. Radioactivities (dose rates) of rocks in Japan

    International Nuclear Information System (INIS)

    Matsuda, Hideharu; Minato, Susumu

    1995-01-01

    The radioactive distribution (radiation doses) of major rocks in Japan was monitored to clarify the factors influencing terrestrial gamma-ray absorbed dose rates. The rock samples were reduced to powder and analyzed by well-type NaI(Tl) scintillation detector and pulse height analyzer. Terrestrial gamma-ray dose rates were estimated in terms of gamma radiation dose rate 1 m above the ground. The radioactivity concentration was highest in acidic rock which contains much SiO 2 among igneous rock, followed by neutral rock, basic rock, and ultrabasic rock. The radioactive concentration was 30-40% lower in acidic and clastic rocks than those of the world average concentration. Higher radioactive concentration was observed in soils than the parent rocks of sedimentary rock and metamorphic rock. The gamma radiation dose rate was in proportion to the radioactive concentration of the rocks. To clarify the radioactive effect in the change course of rocks into soils, comparative measurement of outcrop and soil radioactive concentrations is important. (S.Y.)

  4. FFTF radioactive solid waste handling and transport

    International Nuclear Information System (INIS)

    Thomson, J.D.

    1982-01-01

    The equipment necessary for the disposal of radioactive solid waste from the Fast Flux Test Facility (FFTF) is scheduled to be available for operation in late 1982. The plan for disposal of radioactive waste from FFTF will utilize special waste containers, a reusable Solid Waste Cask (SWC) and a Disposable Solid Waste Cask (DSWC). The SWC will be used to transport the waste from the Reactor Containment Building to a concrete and steel DSWC. The DSWC will then be transported to a burial site on the Hanford Reservation near Richland, Washington. Radioactive solid waste generated during the operation of the FFTF consists of activated test assembly hardware, reflectors, in-core shim assemblies and control rods. This radioactive waste must be cleaned (sodium removed) prior to disposal. This paper provides a description of the solid waste disposal process, and the casks and equipment used for handling and transport

  5. DOE reassesses civilian radioactive waste management program

    International Nuclear Information System (INIS)

    Yates, M.

    1990-01-01

    This article reports on the announcement by the Department of Energy (DOE) that the opening of a high-level radioactive nuclear waste repository site will be delayed for seven years. The article discusses DOE's reassessment plan, the restructuring of the Office of Civilian Radioactive Waste Management, site access and evaluation, the Monitored Retrievable Storage Commission proposal, and the industry's response

  6. PROCESSING OF RADIOACTIVE WASTE

    Science.gov (United States)

    Johnson, B.M. Jr.; Barton, G.B.

    1961-11-14

    A process for treating radioactive waste solutions prior to disposal is described. A water-soluble phosphate, borate, and/or silicate is added. The solution is sprayed with steam into a space heated from 325 to 400 deg C whereby a powder is formed. The powder is melted and calcined at from 800 to 1000 deg C. Water vapor and gaseous products are separated from the glass formed. (AEC)

  7. Report of radioactivity survey research in fiscal year 1989

    International Nuclear Information System (INIS)

    1990-12-01

    In the National Institute of Radiological Sciences, as a part of the radioactivity survey and research of Science and Technology Agency, the survey of environmental radioactivity level due to the radioactive fallout accompanying nuclear explosion experiments and the radioactive substances released from nuclear facilities and others and the safety analysis of these have been carried out. The radioactivity and dose survey for environment, foods and human bodies, the survey of the level around nuclear facilities, the business of radioactivity data center, the basic investigation for the evaluation of the results of radioactivity survey, the training of environmental radiation monitoring technicians and the investigation and research of the measurement of emergency radiation exposure and countermeasures were carried out. Those results are summarized. (K.I.)

  8. 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

  9. Annual Report of Radioactive Waste Facilities Operation in 2015

    Institute of Scientific and Technical Information of China (English)

    DU; Hong-ming; GAO; Zhi-gang; DIAO; Lei; SHEN; Zheng; LI; Wen-ge

    2015-01-01

    301of the Department of Radiochemistry,is in charge of the management of radioactive waste and the safety of the relative facilities to meet the request of the scientific research production.There are 16radioactive waste facilities,including9facilities which are closed and monitored

  10. The dispersion of alpha and beta radioactivity to the environmental from spent fuel testing in RMI

    International Nuclear Information System (INIS)

    Yuwono, I.; Pudjadi, E.

    1996-01-01

    The destructive testing of 2 spent fuels in RMI and radioactivity air release monitoring to the environmental have been done. The monitoring equipment used alpha-beta particulate monitor, Berthold LB 150 D type. The calculations using the Gaussian plume model and distributions factor showed there were no radiological effect of alpha and beta radioactivity dispersion and contribution to the environmental. The maximum average construction of alpha and beta radioactivity are 0.002% and 0.05%. (author)

  11. Overview of food monitors

    International Nuclear Information System (INIS)

    Saito, I.

    2014-01-01

    May 11th 2011, nuclear accidents occurred by Tohoku Region Pacific Coast Earthquake made radioisotopes overflow in reactors and spread around the environments, and it caused risk of food contamination in these areas. And May 17th 2011, Ministry of Health, Labour and Welfare Japan announced provisional regulation values of radioactive materials in food in accordance with the food sanitation act. And they had notified the municipality to corresponding foods above the provisional regulation not had to be on sale. It causes massive needs for food monitoring in Japan. For reply to these massive needs, Hitachi Aloka Medical Ltd. commercialized food monitor: CAN-OSP-NAI in cooperation with CANBERRA Industries Inc. And after this, commercialized food screening system: FSS-101 for reply more expand food monitoring in Japan. This paper introduce Hitachi Aloka Medical Ltd. products which two types of food monitor product, provisional regulation values of radioactive materials in food in accordance with the food sanitation act and with comparing with past food monitoring, needs when accident happen. I wish this is going to be good report for help to radioactive and radiation detection in the future. (author)

  12. Public perceptions of aspects of radioactive waste management

    International Nuclear Information System (INIS)

    1985-04-01

    The paper concerns a study of peoples' attitude towards the siting of radioactive waste repositories, carried out by the University of Surrey, United Kingdom. The work has been commissioned by the Department of the Environment as part of its radioactive waste management research programme. The people taking part were asked to mark on a map of Great Britain places they felt radioactive waste repositories would be least objectionable. The degree to which people worried about the technology and the management of radioactive waste disposal was monitored. Questions were asked about storage, disposal and transportation aspects, and about present and future worries. (UK)

  13. Response to Illicit Trafficking of Radioactive Materials

    International Nuclear Information System (INIS)

    2010-01-01

    Two response paths are discussed in the presentation. Reactive response follows when an alarm of a border monitor goes off or a notification is received about an incident involving or suspected to involve radioactive materials. The response can also be the result of the finding of a discrepancy between a customs declaration form and the corresponding actual shipment. Proactive response is undertaken upon receipt of intelligence information suggesting the illicit trafficking of radioactive materials, notification about the discovery of non-compliance with transport regulations or if discrepancies are found in an inventory of radioactive materials.

  14. Monitoring system with integrated measuring sensors for radioactively contaminated iron and non-iron scrap metal (MerEN). Final report; Ueberwachungssystem mit integrierter Messsensorik fuer radioaktiv belastete Eisen- und Nichteisenschrotte (MerEN). Abschlussbericht

    Energy Technology Data Exchange (ETDEWEB)

    Celebic, Enis; Gentes, Sascha [Karlsruher Institut fuer Technologie (KIT), Karlsruhe (Germany). Inst. fuer Technologie und Management im Baubetrieb; Rutschmann, Michael; Goerisch, Uwe [Prof. Dr.-Ing. Uwe Goerisch GmbH Ingenieurbuero fuer Abfallwirtschaft, Karlsruhe (Germany); Wetzel, Ramona [Schrott Wetzel GmbH, Mannheim (Germany)

    2015-08-15

    Radioactive sources are used in the industry, in nuclear medicine, the military, as well as in research. Accidents and losses rarely occur, a proper and responsible handling of those sources provided. Radioactive sources represent a risk when divulged, moved, passed on without authorization or lost. Time and again, radioactive sources are found at scrap yards and metal processing facilities. The supervision of these radioactive materials is gaining importance in the light of the worldwide import and export of ferrous and non-ferrous scrap. The aim of the project was to develop a space monitoring system for radioactively contaminated ferrous and non-ferrous scrap, so it can be removed from the operating range and to protect staff. The monitoring system combines technical and application-specific requirements. As part of the research project, the system was designed based on the operational framework conditions, technical and economic possibilities, and the findings from the experimental phase. The prototype mainly consists of a mainframe computer, stationary and mobile detection units, and the data transfer technology. This has successfully been tested at a scrap yard. The effects of vibrations that occur on scrapyards were investigated. This was necessary to obtain functionality of the hardware. The experimental phase was carried out based on a pre-defined set-up. The aim was to test the individual scenarios, processing and logging of the date as well to interpret the test results. In the event of radioactive sources being found in discarded metal, a standard sequence of actions was designed to protect the yard's processes and its personnel against further radioactive damage. For the first time, active radiation monitoring was performed on scrap-processing machines and in the working range of mobile devices. With this, scrap yard operators will have the opportunity to detect radioactively contaminated material at an early stage and before radiation sources are

  15. Systematic monitoring of atmosphere radioactivity on the main French nuclear sites in 1961; Surveillance systematique de la radioactivite de l'atmosphere sur les principaux sites nucleaires francais en 1961

    Energy Technology Data Exchange (ETDEWEB)

    Doury, A.

    1963-07-01

    After having indicated the different stations, departments and bodies involved in the monitoring of radioactivity for radiation protection purposes (notably CEA, EDF, National Navy for their establishments in Saclay, Le Bouchet, Grenoble, Marcoule, Cadarache, Cherbourg, Chinon, Antony) and briefly described how this network operates, this report presents the measurement program which comprises measurements of global instantaneous radioactivity at the vicinity of the ground, measurements of long life radioactivity, the identification and dosing of long life radio-elements, and additional measurements. It presents sampling and measurement methods for these different measurements performed on different forms of radioactive elements (airborne dusts, gas, gamma and cosmic ambient radiation, precipitations). Results are discussed and presented under tabular and graphical forms.

  16. Guidebook of radioactive wastes removal. From collection to storage

    International Nuclear Information System (INIS)

    2014-06-01

    This document, more particularly devoted to radioactive waste producers (except electronuclear industry), defines the technical specifications relative to the taking over of their wastes by the ANDRA, the French national agency of radioactive wastes. Content: general conditions (producers liability and obligations), instructions manual of the taking over demand, non-electronuclear wastes collecting, wastes conditioning specifications, specifications for each category of waste, the lightning arresters case, specifications for particular removals with prior consent

  17. 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

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

    International Nuclear Information System (INIS)

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

    2012-01-01

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

  19. Effective Regulatory Control of Radioactive Sources in Taiwan

    International Nuclear Information System (INIS)

    Liu, W.; Yuan, C.; Fan, S.; Su, S.

    2004-01-01

    Since the incident of radioactively contaminated buildings first surfaced in Taiwan in 1992, efforts have been made by AEC (Atomic Energy Council) of Taiwan to prevent recurrence of similar incidents involving radioactive materials and to achieve effective regulatory control over radioactive sources. The most important milestone is when AEC began to enforce IRPA he Ionizing Radiation Protection Act with the promulgation of 18 relevant regulations on Feb. 1, 2003. In order to enhance accountability of radioactive material and equipment capable of producing ionizing radiation, AEC develops and begins implementing a RPCS Radiation Protection Control System which is a powerful tool in controlling radiation safety and security. In addition, AEC develops a monthly registration program via internet, an o n-line reporting system f or owners/operators of radioactive sources, to improve monitoring of sealed sources (in-use and not-in-use). The registration requirement applies to 469 licensees possessing about 3,000 sealed sources in Taiwan. Because of the threat of orphan sources, AEC has made great efforts in preventing their contamination of construction steel material by establishing and enforcing the RPMMPIRCB Regulation for Preventive Measures and Management Plans for Incident of Radioactively Contaminated Buildings. To comply with this regulation, all 19 of Taiwan's steel factories with melting furnace have installed portal-type radiation detection system to monitor incoming scrap metal. (Author)

  20. 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)

  1. Monitoring programme

    International Nuclear Information System (INIS)

    1994-06-01

    Her Majesty's Inspectorate of Pollution's 1992 report on its programme of monitoring radioactive substances is presented. Site operators' returns are verified and the report provides independent data on the environmental impact of authorized disposal of radioactive wastes. Radiation doses which may have been received by members of the public, fall well below the International Commission for Radiological Protection's (ICRP) recommended annual doses. (UK)

  2. An overview of application of bayesian classifier approach in radioactive tracer technology.case study

    International Nuclear Information System (INIS)

    El-Aseer, A.; Dawood, E.; Ben Ayad, S.; Alwerfalli, M.

    2015-01-01

    The usefulness of implementing a radioactive tracer techniques subjected to varied risk factors. Thus, the setup procedure for the application experimental techniques of radioactive tracer must be evaluated prior the decision action steps. One way of doing this, is to use Bay's theorem techniques. As there is a possibility of classifying the implemented parameters into certain catogries depending on their certainty to effect radioactive tracer technology. In this paper, the radioactive tracer experimental parameters classified accoring to Bayesian theory. Using this theory, one can study the proposed technical systems to determine the probabilities of the effectiveness of any selected parameter among the others. The classification of the applied experimental parameters into suitable or unsuitable in proposed theoretically. Ten parameters used in this experimental data were classified accordingly. The posterior is calculate from the prior and the likelihood previously determined by bayes rule.(author)

  3. 1985 environmental monitoring report

    Energy Technology Data Exchange (ETDEWEB)

    Day, L.E.; Miltenberger, R.P.; Naidu, J.R. (eds.)

    1986-04-01

    The environmental monitoring program is designed to determine that BNL facilities operate such that the applicable environmental standards and effluent control requirements have been met. The data were evaluated using the appropriate environmental regulatory criteria. The environmental levels of radioactivity and other pollutants found in the vicinity of BNL during 1985 are summarized in this report. Detailed data are not included in the main body of the report, but are tabulated and presented in Appendix D. The environmental data include external radiation levels; radioactive air particulates; tritium concentrations; the amounts and concentrations of radioactivity in and the water quality of the stream into which liquid effluents are released; the water quality of the potable supply wells; the concentrations of radioactivity in biota from the stream; the concentrations of radioactivity in and the water quality of ground waters underlying the Laboratoy; concentrations of radioactivity in milk samples obtained in the vicinity of the Laboratory; and the 1984 strontium-90 data which was not available for inclusion in the 1984 Environmental Monitoring Report. In 1985, the results of the surveillance program demonstraed that the Laboratory has operated within the applicable environmental standards.

  4. Environmental radioactivity survey data in Cheonju

    International Nuclear Information System (INIS)

    Lee, Mo Sung; Goo, Hyun Mi

    2003-12-01

    We surveyed the en environmental radiation and radioactivity in Chungcheongbuk-do in order to provide baseline data in the year of 2003. Data generated from the project will be the information base for making decisions necessary to ensure the protection of public health. This report contains the data of gamma exposure rates and radioactivities of airborne dust, fallout, precipitation and tap water which were analyzed periodically by Cheongju regional monitoring station In the year 2003. Also it contains the data of natural radioactivity levels of environmental samples such as soil, drinking water, indicator plant(mugwort, pine-needle), agricultural and forest products, and processed food(tea)

  5. Environmental radioactivity survey data in Cheonju

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Mo Sung; Goo, Hyun Mi [Cheongju Univ., Cheongju (Korea, Republic of)

    2003-12-15

    We surveyed the en environmental radiation and radioactivity in Chungcheongbuk-do in order to provide baseline data in the year of 2003. Data generated from the project will be the information base for making decisions necessary to ensure the protection of public health. This report contains the data of gamma exposure rates and radioactivities of airborne dust, fallout, precipitation and tap water which were analyzed periodically by Cheongju regional monitoring station In the year 2003. Also it contains the data of natural radioactivity levels of environmental samples such as soil, drinking water, indicator plant(mugwort, pine-needle), agricultural and forest products, and processed food(tea)

  6. Environmental radioactivity in Canada, 1987. Annual publication

    Energy Technology Data Exchange (ETDEWEB)

    1988-01-01

    The radiological surveillance program of the Department of National Health and Welfare is conducted to determine levels of environmental radioactivity in Canada and to assess the resulting population exposures. The report is prepared as a summary of work in progress and as a means of publishing the results of ongoing programs. Special studies reported on included the evaluation of the contamination by cesium-137 of caribou, a major source of food in northern communities; the development of methods for the determination of radon, carbon-14, polonium-210, radium-228 and isotopic uranium in samples; and monitoring of fallout contamination from Chernobyl of imported foods. Environmental monitoring programs conducted included external radiation exposure, tritium in water vapour, gross beta radioactivity, and monitoring of air, drinking water, precipitation and milk. A list of reports and presentations is also included.

  7. Measurement of radioactivity in Norway

    International Nuclear Information System (INIS)

    Berg, T.C.

    1990-08-01

    A nation-wide network of 11 monitoring stations for continous registration of radioactivity in the air has been established in Norway. Via the telecommunication network, collected data are dayly automatically transmitted to the Norwegian Institute for Air Research (NILU). High radiation levels trigger an alarm for immediate transmission. The monitoring system and experiences in connection with its operation are described. Results from measurements in 1989 are presented. 18 figs

  8. Radioactivity in the Romanian sector of the Black Sea

    International Nuclear Information System (INIS)

    Osvath, I.; Dovlete, C.; Bologa, A.

    2004-01-01

    The study of marine radioactivity in Romanian waters has been performed jointly by the Romanian marine research institute (RMRI) and the environmental radioactivity research laboratory of the Institute of meteorology and hydrology, presently the environmental radioactivity laboratory (ERL) of the Institute of environmental research and engineering, along two directions: 1. Marine radioactivity monitoring, 2. Studied on the distribution of radionuclides among the components of the marine environment and its time evolution. Assessment of distribution coefficients and concentration factors for radionuclides in the marine environment. Identification and study of the bioindicator species

  9. ANSTO`s radioactive waste management policy. Preliminary environmental review

    Energy Technology Data Exchange (ETDEWEB)

    Levins, D.M.; Airey, P.; Breadner, B.; Bull, P.; Camilleri, A.; Dimitrovski, L.; Gorman, T.; Harries, J.; Innes, R.; Jarquin, E.; Jay, G.; Ridal, A.; Smith, A.

    1996-05-01

    For over forty years, radioactive wastes have been generated by ANSTO (and its predecessor, the AAEC) from the operation of nuclear facilities, the production of radioisotopes for medical and industrial use, and from various research activities. the quantities and activities of radioactive waste currently at Lucas Heights are very small compared to many other nuclear facilities overseas, especially those in countries with nuclear power program. Nevertheless, in the absence of a repository for nuclear wastes in Australia and guidelines for waste conditioning, the waste inventory has been growing steadily. This report reviews the status of radioactive waste management at ANSTO, including spent fuel management, treatment of effluents and environmental monitoring. It gives details of: relevant legislative, regulatory and related requirements; sources and types of radioactive waste generated at ANSTO; waste quantities and activities (both cumulative and annual arisings); existing practices and procedures for waste management and environmental monitoring; recommended broad strategies for dealing with radioactive waste management issues. Detailed proposals on how the recommendations should be implemented is the subject of a companion internal document, the Radioactive Waste Management Action Plan 1996-2000 which provides details of the tasks to be undertaken, milestones and resource requirements. 44 refs., 2 tabs., 18 figs.

  10. Nuclide-specific monitoring of airborne radioactivity

    International Nuclear Information System (INIS)

    Aures, R.; Neu, A.

    1996-01-01

    Since the end of the seventies the Landesanstalt fuer Umweltschutz Baden-Wuerttemberg ist operating two radioaerosol monitoring stations at the border in the opposite of foreign nuclear power plants. Since the end of the eighties six similar monitoring stations were built up for measuring activity in breathing air in the common environment in Baden-Wuerttemberg. A special filtersystem allows measuring the activity concentration of up to 99 nuclides. The measuring system was optimized by advanced PC-technology, a multitasking operating system and a special software for users and gamma-spectroscopy. These increased the average availability of all monitoring stations to 96% in 1996. (orig.) [de

  11. Results of questionaire survey for the measurement of radioactivity in waste water

    International Nuclear Information System (INIS)

    1992-01-01

    A questionaire for radioactivity in waste water was sent to 388 facilities, including 158 medical facilities, and all (100%) answered. Information requested included: (1) kinds and annual usage of unsealed RI, (2) measuring method of radioactivity in waste water, (3) kinds of measuring instruments and the detection limits, (4) prior treatment of measurement materials, (5) level of radioactive waste exhausted during 3 months, (6) personnel and time per month required for radioactivity measurement, (7) problems and comments in waste water management, and (8) kinds of facilities. A total of 36 unsealed RI were used. The most commonly used RI was I-125 (n=240), followed by H-3 (n=189) and P-32 (n=179). Annual level of RI was 4 GBq or less in 90% of the facilities. The most common method for measuring radioactivity was sampling method (n=241). The most common instrument for measuring radioactivity was a gamma counter for I-125 (45% of the facilities), and a liquid scintillation counter for P-32 (80%) and for C-14 and H-3 (90%). The detection limits for I-125 exceeded the radioactivity limits in 24% of the facilities. The amount of sampler was 5 cc or less in 80% of the facilities. Prio treatment was not carried out in 62.7%. Prior treatment methods reported were enrichment, evaporation, pH adjustment, and sedimentation. Half of the facilities exhausted 10 cm 3 or less of waste water during 3 months. The number of persons engaging in radioactivity measurement per month was reported to be one in 282 facilities (87%). (N.K.)

  12. The radiation monitoring of environment around place of treatment and storage of radioactive wastes

    International Nuclear Information System (INIS)

    Vdovina, E.D.

    2001-01-01

    Full text: Large success was attained in the field of radiation protection of research nuclear center, but it is necessary to carry out works in this way around place of treatment and storage of radioactive wastes too. Moreover, for protection of environment it is necessary to control radiation condition of system (radioactive wastes of nuclear center - environment). There is large amount of natural and man-made radionuclides in environment and it is important to solve problem to control individual radionuclides, polluting natural environment. Also, it is necessary to control concentrations of specific radionuclides, which are marks of definite radioactive source. The radionuclides 137 Cs, 90 Sr, 60 Co, 141 Ce, 144 Ce, 95 Zr, 95 Nb, 131 I and natural radionuclides of uranium, thorium and their products of decay are basic radionuclides. The 57 Co, 35 S, 32 P are considered also basic radionuclides taking into consideration specialization of our Institute. The basic problems of control of environment are following: observation of radioactive pollution level of environment objects; estimation of radioactive pollution level with the purpose of warning of possible negative consequences; investigation of dynamics of radioactivity and prognosis of radioactive pollution of environment objects; influence on sources of radioactive pollution. There is large volume information, characterizing radiation condition of environment around research nuclear center and around place of treatment and storage of radioactive wastes. The bank of environment object analysis result date was build for investigation of information. The system of protection around location of treatment and storage of radioactive wastes and around nuclear center consists of control of radioactive wastes, superficial and underground water, soil, plants, atmospheric precipitation. There are analysis of total β- activity, α-activity and γ-spectrometry. This control includes estimation of throw down values

  13. Radiation protection - Monitoring of workers occupationally exposed to a risk of internal contamination with radioactive material

    International Nuclear Information System (INIS)

    2006-01-01

    In the course of employment, individuals might work with radioactive materials that, under certain circumstances, could be taken into the body. Protecting workers against risks of incorporated radionuclides requires the monitoring of potential intakes and/or the quantification of actual intakes and exposures. The selection of measures and programmes for this purpose requires decisions concerning methods, techniques, frequencies etc. for measurements and dose assessment. The criteria permitting the evaluation of the necessity of such a monitoring programme or for the selection of methods and frequencies of monitoring usually depend upon the legislation, the purpose of the radiation protection programme, the probabilities of potential radionuclide intakes, and the characteristics of the materials handled. This International Standard offers guidance for the decision whether a monitoring programme is required and how it should be designed. Its intention is to optimise the efforts for such a monitoring programme consistent with legal requirements and with the purpose of the radiation protection programme. Recommendations of international expert bodies and international experience with the practical application of these recommendations in radiation protection programmes have been considered in the development of this International Standard. Its application facilitates the exchanges of information between authorities, supervisory institutions and employers. The International Standard is not a substitute for legal requirements. In the International Standard, the word 'shall' is used to denote a requirement and no deviation is allowed. The word 'should' is used to denote a recommendation from which justified deviations are allowed. The word 'may' is used to denote permission

  14. Natural Radioactivity Accumulated in the Arctic from Long-range Atmospheric Transport - Observations in Canadian Monitoring Stations

    Energy Technology Data Exchange (ETDEWEB)

    Chen, Jing; Zhang, Weihua [Radiation Protection Bureau, Health Canada, 775 Brookfield Road, Ottawa K1A 1C1 (Canada)

    2014-07-01

    In the environment, the main sources of naturally occurring radionuclides come from radionuclides in the uranium decay series. Activity concentrations of uranium decay series radionuclides may vary considerably from place to place depending on the geological characteristics at the location. Their releases to the atmosphere are mainly through radon ({sup 222}Rn), a radioactive noble gas occurring naturally as an indirect decay product of uranium in soils and rocks. Due to the abundance of uranium, radon continuously emanates from continental land masses. With radon as the main source of naturally occurring radioactivity in the environment, one would think that the Arctic should be an area of low background radiation, because a considerable area of the Arctic is covered by glaciers and permafrost, and radon emanation rate has been reported to be negligible from those glacier and permafrost areas. However, available data have shown the opposite. The elevated level of naturally occurring radioactivity in the Arctic is due to natural sources outside of the Arctic, mainly through long-range atmospheric transport of radon and radon progeny. In some cases, natural radioactivity can accumulate to relatively high levels and become a health concern or a limiting factor of country food consumption. By definition, contaminants are undesirable substances which can cause harm to the environment, the biota, and humans. We can call these naturally accumulating radiological burdens to the Arctic 'natural contaminants' to distinguish them from the traditional meaning of contamination, the 'artificial contaminants' which are attributable to industrial or man-made sources. This paper reviews information available in the literature, analyses long-term atmospheric monitoring data in the Canadian high Arctic, sub-Arctic and mid-latitude sites, and provides discussion on research needed to address questions, such as how heavily the Arctic has been impacted by the

  15. Mineral water and radioactivity. Technical report n. 15

    International Nuclear Information System (INIS)

    2000-07-01

    This technical report aims at giving to people taking charge of mineral water analysis, information needed to the interpretation of radioactivity monitoring results. It provides bulk notions on the radioactivity (biological and environmental effects), regulations and reference texts of the WHO (World Health Organization). Examples of activities and absorbed doses calculation are also provided. (A.L.B.)

  16. Proceedings of the technical meetings 'Water, radioactivity and environment'

    International Nuclear Information System (INIS)

    Perceval, Olivier; Foulquier, Luc; Canneva, Guillem; Jedor, Beatrice; Genthon, Benedicte; Vicaud, Alain; Skrzypczak, Julien; Gibeaux, Audrey; Phrommavanh, Vannapha; Descostes, Michael; Tognelli, Antoine; Calmet, Dominique; Leprieur, Fabrice; Pignol, David; Thybaud, Eric; Feray, Christine; Leclerc, Elisabeth; Maitre, Melanie; Calmon, Philippe; Marang, Laura; Beaugelin-Seiller, Karine; Garnier-Laplace, Jacqueline; Leprieur, Fabrice; Philippot, Benoit; Hemidy, Pierre-Yves; Devin, Patrick; Perrier, Gilles; CALVEZ, Marianne; Descamps, E.; Preveral, S.; Brutesco, C.; Ginet, N.; Escofier, C.; Garcia, D.; Pignol, D.; Ansaldi, M.; Rodrigue, A.; Bazin, I.; Cholat, P.; Bailly-Du-Bois, Pascal; Fievet, Bruno; Godinot, Claire; Eyrolle-Boyer, Frederique; Antonelli, Christelle; Tournieux, Damien; Augeray, Celine; Galliez, Kevin; Baconet, I.; Cavaliere, N.; Dias Varela, D.; Foulon, L.; Laconici, C.; Lorand, H.; Mouton, M.; Siscard, N.; Tarlette, L.; Loyen, Jeanne; Gleizes, Marc; Vidal, R.; Borgia, Cecile; Hemidy, Pierre-Yves; Fouchet, Loic; Gontier, G.; Grignard, G.; Drozdzak, Jegodz; Leermakers, Martine; Brun, Frederic; Ameon, Roselyne; Gleizes, Marc; Maulard, Alain; Moine, Jerome; Tchilian, Nathalie; Paillard, Herve; Gaid, Abdelkader; Wittmann, Erich; Boucherie, Christophe; Devin, Patrick

    2014-12-01

    These technical days were organized by the 'Environment section' of the French Society of Radiation Protection (SFRP). Their aim was to review the current state of water use, management and monitoring, in particular in the nuclear industry, both on the radiological and chemical aspects. This document brings together the available presentations (slides) together with their corresponding abstracts (in French) and dealing with: 1 - Environmental issues linked to water and aquatic ecosystems contamination by micropollutants (O. Perceval); 2 - 50 years of radioecology in aquatic environments (L. Foulquier); 3 - Regulation and organisation of the French administration for water and aquatic ecosystems management (G. Canneva); 4 -European and French regulations about the radiological quality of drinking water (B. Jedor); 5 - Water samplings and liquid effluents from nuclear facilities: regulation, authorisations, prescriptions (B. Genthon); 6 - Water needs of a NPP (A. Vicaud); 7 - Water management at old uranium mining sites (A. Gibeaux); 8 - Mobile system for liquid effluents treatment (J. Skrzypczak); 9 - Water: an essential vector for the transfer of radioactive and chemical compounds in the underground (A. Tognelli); 10 - Environmental guide values for aquatic ecosystems protection (E. Thybaud); 11 - Prioritisation work for radioactive and chemical compounds to be monitored in aquatic environments in the framework of the environment perennial lab (E. Leclerc); 12 - Liquid radioactive effluents in continental aquatic environments: why and how estimating the impact? (K. Beaugelin-Seiller); 13 - Sustainable water management: standards, a compulsory tool (D. Calmet); 14 - Water sampling: from theory to practice (F. Leprieur, B. Philippot); 15 - Prototype for the detection of toxic compounds in the environment (D. Pignol); 16 - Nuclear metrology and water: new available and developing techniques (C. Augeray, K. Galliez); 17 - Measurement of the uranium and radium bio

  17. 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

  18. The radioactive environmental monitoring and its qualitative assessment at science city of Mianyang in 2001

    International Nuclear Information System (INIS)

    Ruan Guanglin; Xing Shixiong; Liao Xiaohua; Chang Zheng; Yang Fan

    2003-01-01

    The results of environmental monitoring shows that the radioactive level within main mediums (river water, air, soil and fallout etc.) have no significant differences from the background level before the start of operation of Science City of Mianyang. Through measurement and evaluation to emission of nuclear facilities, the data of sources terms are obtained. The distribution of doses in coordinate of reference are calculated by the principle of does fold to multi-chimney exhaust and air-diffuse model at the area. Quality assessments of radiological environment shows that maximum individual effective does is 4/10 5 of does limit, detriment is 2/10 7 of detriment constraint within 80 km. It is shown that environmental impact is little and receivable to the public. (authors)

  19. Method for monitoring drilling materials for gamma ray activity

    International Nuclear Information System (INIS)

    Smith, H.D. Jr.; Arnold, D.M.; Schultz, W.E.

    1985-01-01

    This invention relates to a method of verifying the radioactivity levels in raw barite prior to its use in drilling mud. Certain gamma ray measurements are taken of the raw barite and extrapolated to a well bore environment using the projected drilling mud weight made from this barite and the dimensions of the well bore. The natural radioactivity occurring in the formations in the vicinity of the well bore is then compared with the projected levels to enable a determination of whether or not the barite has sufficient radioactive trace elements to forbid its use in a well. Alternatively, the method indicates the ratios by which such additives containing radioactive trace elements must be diluted with non-radioactive additives before use in the drilling mud. A second use of the method involves mud testing at the well site for radioactivity from mud additives, including barite, potassium chloride, and well cuttings. Additional uses include testing other weight materials prior to or subsequent to addition to the mud, and methods for correcting observed gamma ray measurements for the mud-induced background

  20. Natural radioactivity product from coal burning in PLTU Pacitan

    International Nuclear Information System (INIS)

    Sukirno; Sri Murniasih; Rosidi; Sutanto WW

    2016-01-01

    Monitoring of radioactivity in the coal-fired power plant has been carried out in the CAST-NAA laboratory at 2015. Monitoring includes analysis of soil, water, fly ash, bottom ash and coal. The basic purpose of this work is the investigation of natural radionuclide contents in coal and the actual product samples in the Pacitan power plant as a first step to estimate the radioactive in the vicinity. This paper presents the results of the analysis of radioactivity in samples of coal, fly ash and bottom ash as well as environment samples of soil and water. Ra-226, Th-232, K-40, U-235, U-238, and Pb-210 Natural radionuclides are determined by gamma spectrometry with HPGe detector. Natural radionuclide in fine grain coal, bottom ash and fly ash have concentrations range (162.182 to 0.057) Bq/kg. Radioactivity contained in soil ranges (0.041 to 169.34) Bq/kg, whereas in water ranges (0.003 to 0.045) Bq/L. According Perka BAPETEN. No. 7 of 2013. On Boundary Value Environmental Radioactivity, the results of measurement analysis contained water around the power plant Pacitan still below the limit values allowed by BAPETEN. (author)