Role of the Federal Radiological Monitoring and Assessment Center (FRMAC) following a radiological accident

International Nuclear Information System (INIS)

Doyle, J.F. III.

1986-01-01

The Federal Radiological Emergency Response Plan (FRERP) calls for the Department of Energy to establish a Federal Radiological Monitoring and Assessment Center (FRMAC) immediately following a major radiological accident to coordinate all federal off-site monitoring efforts in support of the State and the Cognizant Federal Agency (CFA) for the facility or material involved in the accident. Some accidents are potentailly very complex and may require hundreds of radiation specialists to ensure immediate protection of the public and workers in the area, and to identify priorities for the Environmental Protection Agency (EPA) long-term efforts once the immediate protective actions have been carried out. The FRMAC provides a working environment with today's high technology tools (i.e., communication, computers, management procedures, etc.) to assure that the State and CFA decision makers have the best possible information in a timely manner on which to act. The FRMAC planners also recognize an underlying responsibility to continuously document such operations in order to provide the State, the CFA, and the EPA the technical information they will require for long term assessments. In addition, it is fully recognized that information collected and actions taken by the FRMAC will be subjected to the same scrutiny as other parts of the accident and the overall response

Federal Radiological Monitoring and Assessment Center Phased Response Operations

International Nuclear Information System (INIS)

Riland, C.A.; Bowman, D.R.

1999-01-01

A Federal Radiological Monitoring and Assessment Center (FRMAC) is established in response to the Lead Federal Agency (LFA) or state request when a major radiological emergency is anticipated of has occurred. The FRMAC becomes a coalition of federal off-site monitoring and assessment activities to assist the LFA, state(s), local, and tribal authorities. State, local, and tribal authorities are invited to co-locate and prioritize monitoring and assessment efforts in the FRMAC. The Department of Energy is tasked by the Federal Radiological Emergency Response Plan to coordinate the FRMAC

Technical Basis Document for PFP Area Monitoring Dosimetry Program

CERN Document Server

Cooper, J R

2000-01-01

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

Technical Basis Document for PFP Area Monitoring Dosimetry Program

International Nuclear Information System (INIS)

COOPER, J.R.

2000-01-01

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

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

Energy Technology Data Exchange (ETDEWEB)

NSTec Aerial Measurement Systems

2012-07-31

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

Monitoring techniques for the impact assessment during nuclear and radiological emergencies: current status and the challenges

International Nuclear Information System (INIS)

Pradeepkumar, K.S.; Sharma, D.N.

2003-01-01

Preparedness and response capability for Nuclear and Radiological emergencies, existing world over, are mainly based on the requirement of responding to radiation emergency caused by nuclear or radiological accidents. Cosmos satellite accident, plutonium contamination at Polaris, nuclear accidents like Kystium, Windscale, TMI and Chernobyl, radiological accidents at Goiania etc have demonstrated the requirement of improved radiation monitoring techniques. For quick decision making, state of the art monitoring methodology which can support quantitative and qualitative impact assessment is essential. Evaluation of radiological mapping of the area suspected to be contaminated needs ground based as well as aerial based monitoring systems to predict the level of radioactive contamination on ground. This will help in delineating the area and deciding the required countermeasures, based on the quantity and type of radionuclides responsible for it. The response can be successful with the effective use of i) Early Warning System ii) Mobile Monitoring System and iii) Aerial Gamma Spectrometric System. Selection of the monitoring methodology and survey parameters and assessment of situation using available resources etc. are to be optimized depending on the accident scenario. Recently, many countries and agencies like IAEA have expressed the requirement for responding to other types of nuclear/radiological emergencies i.e, man made radiation emergency situations aimed at harming public at large that can also lead to environmental contamination and significant exposure to public. Reports of lost / misplaced / stolen radioactive sources from many countries are alarming as safety and security of these radioactive sources are under challenge. The monitoring methodology has to take into account of the increase in such demands and more periodic monitoring in suspected locations is to be carried out. Detection of orphan sources possible amidst large heap of metallic scraps may pose

Area Monitoring Dosimeter Program for the Pacific Northwest National Laboratory: Results for CY 2000

International Nuclear Information System (INIS)

Bivins, Steven R; Stoetzel, Gregory A

2001-01-01

Pacific Northwest National Laboratory (PNNL) established an area monitoring dosimeter program in accordance with Article 514 of the Department of Energy (DOE) Radiological Control Manual (RCM) in January 1993. This program is to minimize the number of areas requiring issuance of personnel dosimeters and to demonstrate that doses outside Radiological Buffer Areas are negligible. In accordance with 10 CFR Part 835.402 (a) (1)-(4) and Article 511.1 of the DOE Standard Radiological Control, personnel dosimetry shall be provided to (1) radiological workers who are likely to receive at least 100 mrem annually, and (2) declared pregnant workers, minors, and members of the public who are likely to receive at least 50 mrem annually. Program results for calendar years 1993-2000 confirm that personnel dosimetry is not needed for individuals located in areas monitored by the program

Technical Basis Document for PFP Area Monitoring Dosimetry Program

Energy Technology Data Exchange (ETDEWEB)

COOPER, J.R.

2000-04-17

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

Radiological aerial monitoring in a nuclear emergency

International Nuclear Information System (INIS)

Shin, Hyeongki; Kim, Juyoul; Jung, Gunhyo

2008-01-01

Since North Korea announced the underground nuclear test on last October 9th, 2006, many countries around the world have worried about the atmospheric dispersion and pollution of radioactive materials crossing the border by the clandestine nuclear test. After that time, verifying the existence of nuclear test by detecting radioactive materials such as xenon, I-131, and Cs-134 at the early stage of radiological emergency, locating the position of test site by backward trajectory analysis, and chasing the moving path of airborne radionuclide have been heavily issued. And collection of airborne radioactivity and gamma radiation monitoring technology using an aircraft have been recently examined by an authority concerned in South Korea. Although various techniques of radiological aerial monitoring have been developed and operated around the world, the relevant technical development or research is still required. In order to decide potential measuring location and time within the framework of radiological monitoring system, we use HYSPLIT (Hybrid Single Particle Lagrangian Integrated Trajectory) model developed by National Oceanic and Atmospheric Administration (NOAA) of U.S. Department of Commerce. The model is validated and assessed against North Korea's nuclear test. Calculation results of radionuclide trajectory show a good agreement with measured values. Backward trajectory analysis is useful to track the radiological source term, possible time and place of nuclear accidents and/or activities. Nationwide early warning system using aircraft and atmospheric dispersion model can help a nearly real-time forecasting and warning in preparation for radiological emergencies. (author)

Federal Radiological Monitoring and Assessment Center (FRMAC): Overview of FRMAC operations

International Nuclear Information System (INIS)

1993-09-01

The purpose of this Management Overview of the Federal Radiological Monitoring and Assessment Center (FRMAC) is to explain the federal preparation for a radiological accident and to describe the subsequent response activities which provide radiological monitoring and assessment outside the boundaries of the monitoring which support the radiological accident site. In the event of a radiological accident, federal agencies with various statutory responsibilities have agreed to coordinate their efforts at the accident scene under the umbrella of the Federal Radiological Emergency Response Plan (FRERP). This cooperative effort will assure the state(s) and the Lead Federal Agency (LFA) that all federal technical assistance is fully supporting their efforts to protect the public and will provide these monitoring results in a working data center for immediate use by the state(s) and LFA decision makers. The federal agencies do not relinquish their statutory responsibilities. However, the mandated federal cooperation ensures that each agency can obtain the data critical to its specific responsibility

Federal Radiological Monitoring and Assessment Center: Phase I Response

International Nuclear Information System (INIS)

Riland, C.; Bowman, D.R.; Lambert, R.; Tighe, R.

1999-01-01

A Federal Radiological Monitoring and Assessment Center (FRMAC) is established in response to a Lead Federal Agency (LFA) or State request when a radiological emergency is anticipated or has occurred. The FRMAC coordinates the off-site monitoring, assessment, and analysis activities during such an emergency. The FRMAC response is divided into three phases. FRMAC Phase 1 is a rapid, initial-response capability that can interface with Federal or State officials and is designed for a quick response time and rapid radiological data collection and assessment. FRMAC Phase 1 products provide an initial characterization of the radiological situation and information on early health effects to officials responsible for making and implementing protective action decisions

Area monitoring dosimeter program for the Pacific Northwest National Laboratory: Results for CY 1997

International Nuclear Information System (INIS)

Bivins, S.R.; Stoetzel, G.A.

1998-07-01

In January 1993, Pacific Northwest National Laboratory (PNNL) established an area monitoring dosimeter program in accordance with Article 514 of the US Department of Energy (DOE) Radiological Control Manual (RCM). The purpose of the program was to minimize the number of areas requiring issuance of personnel dosimeters and to demonstrate that doses outside Radiological Buffer Areas are negligible. In accordance with 10 CFR Part 835.402 (a) (1)--(3) and Article 511.1 of the RCM, personnel dosimetry shall be provided to (1) radiological workers who are likely to receive at least 100 mrem annually, and (2) declared pregnant workers, minors, and members of the public who are likely to receive at least 50 mrem annually. Program results for calendar years (CY) 1993--1996 confirmed that personnel dosimetry was not needed for individuals located in areas monitored by the program. A total of 93 area thermoluminescent dosimeters (TLDs) were placed in PNNL facilities during CY 1997. The TLDs were exchanged and analyzed quarterly. All routine area monitoring TLD results were less than 50 mrem annually after correcting for worker occupancy. The results support the conclusions that personnel dosimeters are not necessary for staff, declared pregnant workers, minors, or members of the public in these monitored areas

Area Monitoring Dosimeter Program for the Pacific Northwest National Laboratory: Results for CY 1998

International Nuclear Information System (INIS)

GA Stoetzel; SR Bivins

1999-01-01

In January 1993, Pacific Northwest National Laboratory (PNNL) established an area monitoring dosimeter program in accordance with Article 514 of the Department of Energy (DOE) Radiological Control Manual (RCM). The purpose of the program was to minimize the number of areas requiring issuance of personnel dosimeters and to demonstrate that doses outside Radiological Buffer Areas are negligible. In accordance with 10 CFR Part 835.402 (a)(1)-(4) and Article 511.1 of the RCM, personnel dosimetry shall be provided to (1) radiological workers who are likely to receive at least 100 mrem annually and (2) declared pregnant workers, minors, and members of the public who are likely to receive at least 50 mrem annually. Program results for calendar years 1993-1997 confirmed that personnel dosimetry was not needed for individuals located in areas monitored by the program. A total of 97 area thermoluminescent dosimeters (TLDs) were placed in PNNL facilities during calendar year 1998. The TLDs were exchanged and analyzed quarterly. All routine area monitoring TLD results were less than 50 mrem annually after correcting for worker occupancy. The results support the conclusion that personnel dosimeters are not necessary for staff, declared pregnant workers, minors, or members of the public in these monitored areas

Online remote radiological monitoring during operation of Advance Vitrification System (AVS), Tarapur

International Nuclear Information System (INIS)

Deokar, U.V.; Kulkarni, V.V.; Mathew, P.; Khot, A.R.; Singh, K.K.; Kamlesh; Deshpande, M.D.; Kulkarni, Y.

2010-01-01

Advanced Vitrification System (AVS) is commissioned for vitrification of high level waste (HLW) by using Joule heated ceramic melter first time in India. The HLW is generated in fuel reprocessing plant. For radiological surveillance of plant, Health Physics Unit (HPU) had installed 37 Area Gamma Monitors (AGM), 7 Continuous Air Monitors (CAM) and all types of personal contamination monitors. Exposure control is a major concern in operating plant. Therefore in addition to installed monitors, we have developed online remote radiation monitoring system to minimize exposures to the surveyor and operator. This also helped in volume reduction of secondary waste. The reliability and accuracy of the online monitoring system is confirmed by calibrating the system by comparing TLD and DRD readings and by theoretical analysis. In addition some modifications were carried in HP instruments to make them user friendly. This paper summarizes different kinds of remote radiological monitoring systems installed for online monitoring of Melter off Gas (MOG) filter, Hood filter, three exhaust filter banks, annulus air sampling and over pack monitoring in AVS. Our online remote monitoring system has helped the plant management to plan in advance for replacement of these filters, which resulted in considerable saving of collective dose. (author)

Quarterly environmental radiological survey summary: First quarter 1995 100, 200, 300, and 600 Areas

International Nuclear Information System (INIS)

McKinney, S.M.

1995-04-01

This report provides a summary of the radiological surveys performed in support of the operational environmental monitoring program at the Hanford Site. The surveys included in this program consist of inactive waste sites; outdoor radiological control areas; tank farm perimeters and associated diversion boxes, lift stations, and vent stations; perimeters of active or uncovered waste sites such as burial grounds, retention basins, ponds, process trenches, and ditches; and road and rail surfaces. This report provides a summary of the radiological surveys performed during the First Quarter of 1995. The status of corrective actions required from current and past reports are also discussed

Federal Radiological Monitoring and Assessment Center Analytical Response

International Nuclear Information System (INIS)

Nielsen, E.C.

2003-01-01

The Federal Radiological Monitoring and Assessment Center (FR-MAC) is authorized by the Federal Radiological Emergency Response Plan to coordinate all off-site radiological response assistance to state and local government s, in the event of a major radiological emergency in the United States. The FR-MAC is established by the U.S. Department of Energy, National Nuclear Security Administration, to coordinate all Federal assets involved in conducting a comprehensive program of radiological environmental monitoring, sampling, radioanalysis, quality assurance, and dose assessment. During an emergency response, the initial analytical data is provided by portable field instrumentation. As incident responders scale up their response based on the seriousness of the incident, local analytical assets and mobile laboratories add additional capability and capacity. During the intermediate phase of the response, data quality objectives and measurement quality objectives are more rigorous. These higher objectives will require the use of larger laboratories, with greater capacity and enhanced capabilities. These labs may be geographically distant FR-om the incident, which will increase sample management challenges. This paper addresses emergency radioanalytical capability and capacity and its utilization during FR-MAC operations

Environmental Radiological Impact of Nuclear Power. Monitoring and Control Programs

International Nuclear Information System (INIS)

Ramos, L. M.

2000-01-01

Radioactive contamination of the environment and public exposure to ionizing radiation may result from releases from programmed or accidental operations in regulated activities, or they may be due to preexisting situations such as contamination caused by past accidents, radioactive rain caused by nuclear tests, or increased natural radioactivity resulting from human activities. In many cases, both the emission sources and the environment should be monitored to determine the risk to the population and verify to what extent the limits and conditions established by competent authorities are being observed. Monitoring can be divided into three categories: monitoring of the emission source, of the receiving medium and of members of the public; individual monitoring of the population is extremely rare and would only be considered when estimated doses substantially exceed the annual public dose limit. In practices likely to produce significant radioactive releases, as is the case of nuclear fuel cycle facilities, the limits and conditions for monitoring and controlling them and the requirements for environmental radiological monitoring are established in the licensing process. Programs implemented during normal operation of the facilities form the basis for monitoring in the event of accidents. in addition to environmental radiological monitoring associated with facilities, different countries have monitoring programs outside the facilities zones of influence, in order to ascertain the nationwide radiological fund and determine possible increases in this fund. In Spain, the facilities that generate radioactive waste have effluent storage, treatment and removal systems and radiological monitoring programs based on site and discharge characteristics. The environmental radiological monitoring system is composed of the network implemented by the owners in the nuclear fuel cycle facilities zones of influence, and by nationwide monitoring networks managed by the Consejo de

Optimal layout of radiological environment monitoring based on TOPSIS method

International Nuclear Information System (INIS)

Li Sufen; Zhou Chunlin

2006-01-01

TOPSIS is a method for multi-objective-decision-making, which can be applied to comprehensive assessment of environmental quality. This paper adopts it to get the optimal layout of radiological environment monitoring, it is proved that this method is a correct, simple and convenient, practical one, and beneficial to supervision departments to scientifically and reasonably layout Radiological Environment monitoring sites. (authors)

Federal Radiological Monitoring and Assessment Center. The analytical response

International Nuclear Information System (INIS)

Nielsen, E.C.

2005-01-01

The Federal Radiological Monitoring and Assessment Center (FRMAC) is authorized by the Federal Radiological Emergency Response Plan to coordinate all off-site radiological response assistance to state and local governments, in the event of a major radiological emergency in the United States. The FRMAC is established by the U.S. Department of Energy, National Nuclear Security Administration, to coordinate all Federal assets involved in conducting a comprehensive program of radiological environmental monitoring, sampling, radioanalysis, quality assurance, and dose assessment. During an emergency response, the initial analytical data is provided by portable field instrumentation. As incident responders scale up their response based on the seriousness of the incident, local analytical assets and mobile laboratories add additional capability and capacity. During the intermediate phase of the response, data quality objectives and measurement quality objectives are more rigorous. These higher objectives will require the use of larger laboratories, with greater capacity and enhanced capabilities. These labs may be geographically distant from the incident, which will increase sample management challenges. Emergency radioanalytical capability and capacity and its utilization during FRMAC operations are discussed. (author)

Radiological monitoring of northern slopes of Mogoltau

International Nuclear Information System (INIS)

Murtazaev, Kh.; Boboev, B.D.; Bolibekov, Sh.; Akhmedov, M.Z.

2010-01-01

Present article is devoted to radiological monitoring of northern slopes of Mogoltau. The physicochemical properties of water of northern slopes of Mogoltau were studied. The radiation monitoring of northern slopes of Mogoltau was carried out during several years under various weather conditions. The exposure rate of human settlements of northern part of Mogoltau was defined.

Radiological monitoring related to the operation of PUSPATI's Triga Reactor

International Nuclear Information System (INIS)

Fatimah Mohamad Amin; Mohamad Yusof Mohamad Ali; Lau How Mooi; Idris Besar.

1983-01-01

Reactor operation is one of the main activities carried out at the Tun Ismail Atomic Research Centre (PUSPATI) which requires radiological monitoring. This paper describes the programme for radiological monitoring which is related to the operation of the 1 MW Triga MK II research reactor which was commissioned in July, 1982. This programme includes monitoring of the radiation and contamination levels of the reactor and its associated facilities and environmental monitoring of PUSPATI's site and its environs. The data presented in this paper covers the period between 1982 to 1983 which includes both the pre-operational and operational phases of the monitoring programme. (author)

The basis for a radiological protection program to the health area of the State University of Campinas (UNICAMP)

International Nuclear Information System (INIS)

Coelho, Rosangela Franco.

1994-01-01

There are some sectors in the Health Area of the State University of Campinas (UNICAMP) that present great potential risks from the viewpoint of radiation protection. The aim of this work is to establish the basis a radiological protection program applicable to these sectors. The Diagnostic Radiology Services and the Laboratory of Cardiac Catheterization of the Hospital de Clinicas have been analyzed, as well as the Radiotherapy Services of the Center for Integral Assistance to the Women Health (CAISM). This work was mainly supported by national and international regulations related to the operative and employment aspects of the equipment and radiation sources used in the health area. Regulations related to area and individual monitoring of workers were also used. Results show that the interior of the rooms where the equipment and radiation sources are located is classified as controlled area, whereas the neighborhoods of the rooms are mostly free areas. In order to improve the radiological protection conditions, only some of the operative and employment aspects need to be modified regarding equipment and radiation sources. In this way, routine personal monitoring would not be further required. Since all the workers have their annual mean equivalent doses below 3/10 of the primary limits of the applicable equivalent dose, routine individual monitoring could be exempted. (author). 23 refs., 51 figs., 83 tabs

Radiological safety system based on real-time tritium-in-air monitoring in room and effluents

Energy Technology Data Exchange (ETDEWEB)

Bidica, N.; Sofalca, N.; Balteanu, O.; Stefan, I. [National Institute of Cryogenics and Isotopes Technologies, Ramnicu Valcea (Romania)

2006-07-01

The conceptual design of the radiological safety system based on real time-in-air monitoring in room and effluents is intended to provide the maximum achievable safety level, basing no the ALARA concept. the capabilities of this system are not only to inform any time personnel about tritium in air concentration level, but it will be able to: initiate the shut down procedure and drain off the plant, as well to start the Air cleaning System when the tritium-in-air concentration exceed pre-established threshold; estimate tritium effective dose rate before starting an activity into the monitored area, or during this activity, or soon as the activity was finished; estimate tritium effective dose and instantly record and update individual effective doses, using a special computer application called 'dose record'; lock access into the radiological area for individuals when tritium dose rate in the monitoring area will exceed the pre-established thresholds, or when any individual dose data provided by 'dose records' application ask for, or for other protection consideration; calculate the total tritium activity released to the environment (per day, week, or month). (N.C.)

Radiological safety system based on real-time tritium-in-air monitoring in room and effluents

International Nuclear Information System (INIS)

Bidica, N.; Sofalca, N.; Balteanu, O.; Stefan, I.

2006-01-01

The conceptual design of the radiological safety system based on real time-in-air monitoring in room and effluents is intended to provide the maximum achievable safety level, basing no the ALARA concept. the capabilities of this system are not only to inform any time personnel about tritium in air concentration level, but it will be able to: initiate the shut down procedure and drain off the plant, as well to start the Air cleaning System when the tritium-in-air concentration exceed pre-established threshold; estimate tritium effective dose rate before starting an activity into the monitored area, or during this activity, or soon as the activity was finished; estimate tritium effective dose and instantly record and update individual effective doses, using a special computer application called 'dose record'; lock access into the radiological area for individuals when tritium dose rate in the monitoring area will exceed the pre-established thresholds, or when any individual dose data provided by 'dose records' application ask for, or for other protection consideration; calculate the total tritium activity released to the environment (per day, week, or month). (N.C.)

Uranium mining and milling sites in Argentina: environmental radiological monitoring (1980-1994)

International Nuclear Information System (INIS)

Bomben, A.M.; Gomez, J.C.; Oliveira, A.A.

1995-01-01

Environmental radiological monitoring in the vicinity of uranium mining and milling plants in Argentina is performed on a routine basis, in order to assess the possibility of significant environmental contamination due to uranium mill wastes and mill tailings of plants still operating or those where the exploitation have concluded. Dissolved natural uranium and 226 Ra concentrations in surface waters are measured in samples taken from rivers near the mills, according to a special monitoring plan set up for each facility. In addition, 222 Rn emanation rates from ore tailings are measured at times. In this paper the environmental radiological monitoring program results obtained for the 1980-1994 period are shown. From the data analyses it can be concluded that there are not significant differences for the concentrations of the radionuclides of interest, between the surface water samples taken from river location above and below the plants discharge points. Besides, no significant exposure results for the population living in the surrounding areas due to the uranium mining and milling plants operation or their wastes. (author). 2 refs., 5 figs

The Mobile Surface Contamination Monitor II environmental radiological characterization utilizing GPS/GIS technologies

International Nuclear Information System (INIS)

Wendling, M.A.

1993-05-01

Time, cost, and most importantly quality of data are the three factors to measure the success of field radiological characterizations. The application of coupling radiation detection instrumentation to a GPS receiver has dramatically increased the data quality achievable compared to traditional environmental radiological survey methods. Improvements in verifying adequate spatial coverage of an area while collecting data and at,the same time reducing field time requirements can be realized. Data acquired during the recent implementation of the Mobile Surface Contamination Monitor 11 (MSCM-11) will be presented to demonstrate the advantages of this system over traditional radiological survey methods. The comparison will include time and manpower requirements. Linking the complimentary GPS, GIS and radiation detection technologies on a mobile tractor based platform has provided a tool to provide radiological characterization data faster, cheaper, and better to assist in the Environmental Restoration Mission of the Hanford Site

Automated radiological monitoring at a Russian Ministry of Defence Naval Site

International Nuclear Information System (INIS)

Moskowitz, P.D.; Pomerville, J.; Gavrilov, S.; Kisselev, V.; Daniylan, V.; Belikov, A.; Egorkin, A.; Sokolovski, Y.; Endregard, M.; Krosshavn, M.; Sundling, C.V.; Yokstad, H.

2001-01-01

The Arctic Military Environmental Cooperation (AMEC) Program is a cooperative effort between the military establishments of the Kingdom of Norway, the Russian Federation, and the US. This paper discusses joint activities conducted over the past year among Norwegian, Russian, and US technical experts on a project to develop, demonstrate and implement automated radiological monitoring at Russian Navy facilities engaged in the dismantlement of nuclear-powered strategic ballistic missile launching submarines. Radiological monitoring is needed at these facilities to help protect workers engaged in the dismantlement program and the public living within the footprint of routine and accidental radiation exposure areas. By providing remote stand-alone monitoring, the Russian Navy will achieve added protection due to the defense-in-depth strategy afforded by local (at the site), regional (Kola) and national-level (Moscow) oversight. The system being implemented at the Polyaminsky Russian Naval Shipyard was developed from a working model tested at the Russian Institute for Nuclear Safety, Moscow, Russia. It includes Russian manufactured terrestrial and underwater gamma detectors, smart controllers for graded sampling, radio-modems for offsite transmission of the data, and a data fusion/display system: The data fusion/display system is derived from the Norwegian Picasso AMEC Environmental Monitoring software package. This computer package allows monitoring personnel to review the real-time and historical status of monitoring at specific sites and objects and to establish new monitoring protocols as required, for example, in an off-normal accident situation. Plans are being developed to implement the use of this system at most RF Naval sites handling spent nuclear fuel

The Department of Energy Nevada Test Site Remote Area Monitoring System

International Nuclear Information System (INIS)

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

1993-01-01

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

Legal provisions governing liquid effluents radiological monitoring

International Nuclear Information System (INIS)

Gans, I.; Ruehle, H.

1985-01-01

The KTA rule 1504 for radiological monitoring of liquid effluents from nuclear installations is explained. As there are no such rules published to date for establishments handling isotopes, some criteria are discussed which in the future ought to form part of a practical guide for liquid effluents monitoring in isotope handling installations. Monitoring measures described refer to liquid effluents from transfer containers, auxiliary cooling equipment, turbine buildings, main cooling installations, and waste air discharges from closed-circuit cooling systems. (DG) [de

Tonopah Test Range Air Monitoring. CY2014 Meteorological, Radiological, and Airborne Particulate Observations

Energy Technology Data Exchange (ETDEWEB)

Nikoloch, George [Desert Research Inst. (DRI), Las Vegas, NV (United States); Shadel, Craig [Desert Research Inst. (DRI), Las Vegas, NV (United States); Chapman, Jenny [Desert Research Inst. (DRI), Las Vegas, NV (United States); Mizell, Steve A. [Desert Research Inst. (DRI), Las Vegas, NV (United States); McCurdy, Greg [Desert Research Inst. (DRI), Las Vegas, NV (United States); Etyemezian, Vicken [Desert Research Inst. (DRI), Las Vegas, NV (United States); Miller, Julianne J. [Desert Research Inst. (DRI), Las Vegas, NV (United States)

2015-10-01

In 1963, the U.S. Department of Energy (DOE) (formerly the Atomic Energy Commission [AEC]), implemented Operation Roller Coaster on the Tonopah Test Range (TTR) and an adjacent area of the Nevada Test and Training Range (NTTR) (formerly the Nellis Air Force Range). This test resulted in radionuclide-contaminated soils at Clean Slate I, II, and III. This report documents observations made during ongoing monitoring of radiological, meteorological, and dust conditions at stations installed adjacent to Clean Slate I and Clean Slate III and at the TTR Range Operations Control center. The primary objective of the monitoring effort is to determine if winds blowing across the Clean Slate sites are transporting particles of radionuclide-contaminated soils beyond both the physical and administrative boundaries of the sites. Results for the calendar year (CY) 2014 monitoring are: (1) the gross alpha and gross beta values from the monitoring stations are approximately equivalent to the highest values observed during the CY2014 reporting at the surrounding Community Environmental Monitoring Program (CEMP) stations; (2) only naturally occurring radionuclides were identified in the gamma spectral analyses; (3) the ambient gamma radiation measurements indicate that the average annual gamma exposure is similar at all three monitoring stations and periodic intervals of increased gamma values appear to be associated with storm fronts passing through the area; and (4) the concentrations of both resuspended dust and saltated sand particles generally increase with increasing wind speed. Differences in the observed dust concentrations are likely the result of differences in the soil characteristics immediately adjacent to the monitoring stations. Neither the resuspended particulate radiological analyses nor the ambient gamma radiation measurements suggest wind transport of radionuclide-contaminated soils.

A Low-Cost, Real-Time Network for Radiological Monitoring Around Nuclear Facilities

International Nuclear Information System (INIS)

Bertoldo, N A

2004-01-01

A low-cost, real-time radiological sensor network for emergency response has been developed and deployed at the Lawrence Livermore National Laboratory (LLNL). The Real-Time Radiological Area Monitoring (RTRAM) network is comprised of 16 Geiger-Mueller (GM) sensors positioned on the site perimeter to continuously monitor radiological conditions as part of LLNL's comprehensive environment/safety/health protection program. The RTRAM network sensor locations coincide with wind sector directions to provide thorough coverage of the one square mile site. These low-power sensors transmit measurement data back to a central command center (CCC) computer through the LLNL telecommunications infrastructure. Alarm conditions are identified by comparing current data to predetermined threshold parameters and are validated by comparison with plausible dispersion modeling scenarios and prevailing meteorological conditions. Emergency response personnel are notified of alarm conditions by automatic radio- and computer- based notifications. A secure intranet provides emergency response personnel with current condition assessment data that enable them to direct field response efforts remotely. This system provides a low-cost real-time radiation monitoring solution that is easily converted to incorporate both a hard-wired interior perimeter with strategically positioned wireless secondary and tertiary concentric remote locations. These wireless stations would be configured with solar voltaic panels that provide current to recharge batteries and power the sensors and radio transceivers. These platforms would supply data transmission at a range of up to 95 km from a single transceiver location. As necessary, using radio transceivers in repeater mode can extend the transmission range. The RTRAM network as it is presently configured at LLNL has proven to be a reliable system since initial deployment in August 2001 and maintains stability during inclement weather conditions. With the proposed

Radiological monitoring of food on the French territory

Energy Technology Data Exchange (ETDEWEB)

Boissieux, T.; Leprieur, F.; Pierrard, O. [Institute for Radiological Protection and Nuclear Safety (France)

2014-07-01

Drink the milk of cows grazing near French nuclear power plants is it really safe in normal times? In case of a nuclear accident leading to release in the environment, what kind of foodstuff can we still eat? In his regulatory mission of environmental monitoring, the French Institute for Radiological Protection and Nuclear Safety (IRSN) tends to answer these questions by acquiring radioactivity data in the food chain. Food radiological monitoring program by IRSN is implemented with a three scale strategy. Locally, i.e. within the range 0 to 10 kilometers of nuclear installations, foodstuff locally produced and thus potentially exposed to radioactive sources are frequently sampled and analyzed. At the regional level, specific studies are carried out to establish an updated levels baseline of radioactivity in the environment, especially in agricultural productions characteristic of the area concerned. At the national level, monitoring food aims to map the average contamination observed all around the French territory. This work of vigilance is organized in partnerships with other French actors involved in food monitoring. In the event of a nuclear accident or small-scale incidents, it would allow having an efficient support network of samplers and measurers located on the whole French territory and quickly mobilized in short or medium terms. Since 2008, IRSN has developed a food monitoring program with the Directorate general for food (DGAL) and the Directorate general for competition policy, consumer affairs and fraud control (DGCCRF). These directions have a general mission of food safety control (animal and plant products) and animal feed-stuff, which requires the search for chemical, physical, biological and radioactive substances. Likewise, a sampling program of grain products is efficient since 1969 with the support of France Agrimer. In 2013, the food monitoring is based on multi-radionuclides analysis (cesium, iodine, tritium, alpha emitters...) in about 650

Tonopah Test Range Air Monitoring: CY2013 Meteorological, Radiological, and Airborne Particulate Observations

Energy Technology Data Exchange (ETDEWEB)

Mizell, Steve A [DRI; Nikolich, George [DRI; Shadel, Craig [DRI; McCurdy, Greg [DRI; Etyemezian, Vicken [DRI; Miller, Julianne J [DRI

2014-10-01

In 1963, the U.S. Department of Energy (DOE) (formerly the Atomic Energy Commission [AEC]), implemented Operation Roller Coaster on the Tonopah Test Range (TTR) and an adjacent area of the Nevada Test and Training Range (NTTR) (formerly the Nellis Air Force Range). This test resulted in radionuclide-contaminated soils at Clean Slate I, II, and III. This report documents observations made during on-going monitoring of radiological, meteorological, and dust conditions at stations installed adjacent to Clean Slate I and Clean Slate III and at the TTR Range Operations Control center. The primary objective of the monitoring effort is to determine if winds blowing across the Clean Slate sites are transporting particles of radionuclide-contaminated soils beyond both the physical and administrative boundaries of the sites. Results for the calendar year (CY) 2013 monitoring include: (1) the gross alpha and gross beta values from the monitoring stations are approximately equivalent to the highest values observed during the CY2012 reporting at the surrounding Community Environmental Monitoring Program (CEMP) stations (this was the latest documented data available at the time of this writing); (2) only naturally occurring radionuclides were identified in the gamma spectral analyses; (3) the ambient gamma radiation measurements indicate that the average annual gamma exposure is similar at all three monitoring stations and periodic intervals of increased gamma values appear to be associated with storm fronts passing through the area; and (4) the concentrations of both resuspended dust and saltated sand particles generally increase with increasing wind speed. However, differences in the observed dust concentrations are likely due to differences in the soil characteristics immediately adjacent to the monitoring stations. Neither the resuspended particulate radiological analyses nor the ambient gamma radiation measurements suggest wind transport of radionuclide-contaminated soils.

Quarterly environmental radiological survey summary - first quarter 1997 100, 200, 300, and 600 areas

International Nuclear Information System (INIS)

Mckinney, S.M.

1997-01-01

This report provides a summary of the radiological surveys performed in support of near-facility environmental monitoring at the Hanford Site. The First Quarter 1997 survey results and the status of actions required are summarized below: (1) All of the routine environmental radiological surveys scheduled during January, February, and March 1997, were performed as planned. (2) One hundred four environmental radiological surveys were performed during the first quarter 1997, twenty-nine at the active waste sites and seventy-five at the inactive waste sites. Contamination above background levels was found at eight of the active waste sites and seven of the inactive waste sites. Contamination levels as high as >1,000,000 disintegrations per minute (dpm) were reported. Of these contaminated surveys twelve were in Underground Radioactive Material (URM) areas and three were in contamination areas. The contamination found within ten of the URM areas was immediately cleaned up and no further action was required. In the remaining five sites the areas were posted and will require decontamination. Radiological Problem Reports (RPR's) were issued and the sites were turned over to the landlord for further action if required. (3) During the first quarter of 1997, 5.6 hectares (13.8 acres) were stabilized and radiologically down posted from Contamination Area (CA)/Soil Contamination (SC) to URM. (4) During the first quarter of 1997, the size of 216-A-25 Gable Mountain Pond was increased from 30.4 to 34.5 hectares (75.0 to 85.2 acres). This increase in size was due to the correction of the original boundary area by using the advanced technology of a global positioning system (GPS). An area, 1.6 hectares (4.0 acres), east of and adjacent to the 241-S/SX/SY tank farm complex was posted as a contamination/soil contamination area. (5) Five open Surveillance Compliance Inspection Reports (SCIRs) had not been resolved

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

International Nuclear Information System (INIS)

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

1983-07-01

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

Baseline radiological monitoring at proposed uranium prospecting site at Rohil Sikar, Rajasthan

International Nuclear Information System (INIS)

Kumar, Rajesh; Jha, V.N.; Sahoo, N.K.; Jha, S.K.; Tripathi, R.M.

2018-01-01

Once economically viable grades of uranium deposits are proposed for mining and processing by the industry radiological baseline studies are required for future comparison during operational phases. The information collected during such studies serve as connecting feature between regulatory compliance and technical information. Present paper summarizes the results of baseline monitoring of atmospheric 222 Rn and gamma level in the area at prospecting mining, milling and waste disposal sites of Rohil Rajasthan

Monitoring in radiological protection scheme; Pemonitoran dalam skim perlindungan radiologi

Energy Technology Data Exchange (ETDEWEB)

NONE

1988-12-31

The chapter briefly discussed the following subjects: function and responsibility of the monitoring, planning of monitoring programme i.e working area for external radiation, monitoring of workers for external radiation, monitoring of working area for surface contamination, monitoring of working area for air contamination, monitoring of workers for internal contamination, and the evaluation of monitoring results.

Nuclear radiation sensors and monitoring following a nuclear or radiological emergencies

International Nuclear Information System (INIS)

Bhatnagar, P.K.

2009-01-01

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

Nuclear radiation sensors and monitoring following a nuclear or radiological emergencies

Energy Technology Data Exchange (ETDEWEB)

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

2009-01-15

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

Quarterly Environmental Radiological Survey Summary Third Quarter 1998, 100, 200, 300, and 600 Areas; TOPICAL

International Nuclear Information System (INIS)

MCKINNEY, S.M.

1998-01-01

This report provides a summary of the radiological surveys performed in support of near-facility environmental monitoring at the Hanford Site. The Third Quarter 1998 survey results and the status of actions required are summarized: (1) All of the eighty-five environmental radiological surveys scheduled during July, August and September were performed as planned. Fifty-one of the surveys were conducted at Project Hanford Management Contractors (PHMC) sites and thirty-four at Environmental Restoration Contractor (ERC) sites. Contamination above background levels was found at seventeen of the PHMC waste sites and two of the ERC waste sites. Contamination levels as high and gt;1,000,000 disintegrations per minute (dpm) per 100 cm(sup 2) were reported. Of these contaminated surveys nine were in Underground Radioactive Material (URM) areas, three were in unposted areas and seven were in contamination areas. The contamination found within four of the URM and three of the CA areas was immediately cleaned up and no further action was required. The remaining five URM and two unposted sites were posted and along with the five CA sites will require remediation. Radiological Problem Reports (RPR's) were issued and the sites were turned over to the landlord for further action as required. (2) During the second quarter of 1998, 1.2 hectares (3.0 acres) were stabilized and radiologically down posted from Contamination Area (CA)/Soil Contamination (SC) to URM. (3) Four hectares (10 acres) located south and west of B-Plant were posted as a radiological buffer area as a result of a contamination spread. This off-normal occurrence is currently being investigated. (4) Four Surveillance Compliance Inspection Reports (SCIRs) remained open and had not been resolved. Tank Farms Operations has responsibility for the unresolved SCIRs

Dose monitoring in radiology departments. Status quo and future perspectives

International Nuclear Information System (INIS)

Boos, J.; Bethge, O.T.; Antoch, G.; Kroepil, P.

2016-01-01

The number of computed tomography examinations has continuously increased over the last decades and accounts for a major part of the collective radiation dose from medical investigations. For purposes of quality assurance in modern radiology a systematic monitoring and analysis of dose related data from radiological examinations is mandatory. Various ways of collecting dose data are available today, for example the Digital Imaging and Communication in Medicine - Structured Report (DICOM-SR), optical character recognition and DICOM-modality performed procedure steps (MPPS). The DICOM-SR is part of the DICOM-standard and provides the DICOM-Radiation Dose Structured Report, which is an easily applicable and comprehensive solution to collect radiation dose parameters. This standard simplifies the process of data collection and enables comprehensive dose monitoring. Various commercial dose monitoring software devices with varying characteristics are available today. In this article, we discuss legal obligations, various ways to monitor dose data, current dose monitoring software solutions and future perspectives in regard to the EU Council Directive 2013/59/EURATOM.

Legal provisions governing gaseous effluents radiological monitoring

International Nuclear Information System (INIS)

Winkelmann, I.

1985-01-01

This contribution explains the main provisions governing radiological monitoring of gaseous effluents from LWR type nuclear power plants. KTA rule 1503.1 defines the measuring methods and tasks to be fulfilled by reactor operators in order to safeguard due monitoring and accounting of radioactive substances in the plants' gaseous effluents. The routine measurements are checked by a supervisory programme by an independent expert. The routine controls include analysis of filter samples, comparative measurement of radioactive noble gases, interlaboratory comparisons, and comparative evaluation of measured values. (DG) [de

Radiation monitoring systems and methodologies for radiological impact assessment

International Nuclear Information System (INIS)

Chaudhury, Probal

2016-01-01

Radioactive sources of various strengths are used in large number of applications in industry, healthcare, agriculture and research. Though all the sources are transported and used under regulatory control, there is always a possibility of some of the sources getting into the hands of committed antisocial non state actors. In addition to this, there is a possible threat of radioactive material being illegally brought into a country. These gives rise to an increase in the global radiological threat and security experts world over are concerned about the possibility of malicious use of radiation in the public domain. Radiation detection systems are installed at various entry and exit ports of some of the countries to detect illicit trafficking of radioactive materials. IAEA has recommended that all States should have a national response plan for nuclear security events to provide for an appropriate and coordinated response. Considering the requirement of radiological emergency preparedness, various radiation monitoring systems and methodologies have been developed. A few aerial radiation monitoring systems developed at Bhabha Atomic Research Centre (BARC) for radiological impact assessment are described here

Generic procedures for monitoring in a nuclear or radiological emergency

International Nuclear Information System (INIS)

1999-06-01

One of the most important aspects of managing a radiological emergency is the ability to promptly and adequately assess the need for protective actions. Protective action accident management must make use of the key relevant information available. Decision-making and accident assessment will be an iterative and dynamic process aimed at refining the initial evaluation as more detailed and complete information becomes available. Emergency monitoring is one of the main sources for obtaining needed information. This publication is in the scope of the Convention on Assistance in the Case of a Nuclear Accident or Radiological Emergency (Legal Series No. 14) under which the IAEA is authorized to assist a State Party or a Member State among other matters in developing appropriate radiation monitoring programmes, procedures and standards (Article 5). The scope of this manual is restricted to practical guidance for environmental and source monitoring during a nuclear or other radiological emergency. It does not address emergency response preparedness, nor does it cover the emergency management aspects of accident assessment. This manual is organised into sections relating to measurements in order of priority of a major reactor accident, namely: ambient gamma/beta dose rates from plume, ground deposition or source; radionuclide concentrations in air; deposition maps for 131 I and 137 Cs and other important radionuclides; radionuclide mix in deposition and radionuclide concentrations in food, drinking water and other samples. The introductory section provides an overview of the design of emergency monitoring and sampling programmes, monitoring teams and their qualifications and training, monitoring equipment and instrumentation, protective actions for emergency monitoring teams and quality assurance and quality control checks

Offsite emergency radiological monitoring system and technology

International Nuclear Information System (INIS)

Mao Yongze

1994-01-01

The study and advance of the offsite radiological monitoring system and technology which is an important branch in the field of nuclear monitoring technology are described. The author suggests that the predicting and measuring system should be involved in the monitoring system. The measuring system can further be divided into four sub-systems, namely plume exposure pathway, emergency worker, ingestion exposure pathway and post accident recovery measuring sub-systems. The main facilities for the monitoring system are concluded as one station, one helicopter, one laboratory and two vehicles. The instrumentation for complement of the facilities and their good performance characteristics, up-to-date technology are also introduced in brief. The offsite emergency radiation monitoring system and technology are compared in detail with those recommended by FEMA U.S.A.. Finally the paper discusses some trends in development of emergency radiation monitoring system and technology in the developed countries

Radiological assessments, environmental monitoring, and study design

International Nuclear Information System (INIS)

Hansen, W.R.; Elle, D.R.

1980-01-01

Studies of the behavior of transuranic elements in the environment form the basic data for applied programs in radiological assessment, environmental monitoring, derivation of radiation-protection standards, and environmental impact statements. This chapter introduces some of the major information requirements of these applications of transuranic research data. Characteristics of the source terms from nuclear activities usually are needed for an analysis of environmental pathways or deployment of monitoring systems. Major inhalation and ingestion pathways are considered in assessments of hazards from transuranics and are discussed from the viewpoint of research needed

Radiological Control Technician: Phase 1, Site academic training study guides

International Nuclear Information System (INIS)

1992-10-01

This volume is a study guide for training Radiological Control Technicians. Provided herein are support materials for learning radiological documentation, communication systems, counting errors and statistics, dosimetry, contamination control, airborne sampling program methods, respiratory protection, radiological source control, environmental monitoring, access control and work area setup, radiological work coverage, shipment and receipt for radioactive material, radiological incidents and emergencies, personnel decontamination, first aid, radiation survey instrumentation, contamination monitoring, air sampling, and counting room equipment

White paper on radiological monitoring of workers exposures

International Nuclear Information System (INIS)

Shettle, Jennifer

2016-01-01

This article comments the content of a white paper which aimed at proposing new regulatory bases to update the French Code of Labour and other legal texts related to the radiation protection of workers. The author briefly comments the objectives of this white paper (to put the initial regulatory basis into question again), briefly describes the adopted approach, the new definition of risk related to ionizing radiations within the frame of a global approach to the prevention of occupational risks. She notices and comments the removal of a reference to an exposure limit for the public as input criterion in the system of radiological monitoring of workers exposures. She also comments the introduction of some concepts: the concept of a worker submitted to a risk related to ionizing radiation, and the concept of exposure value entailing a strengthened preventive action. She indicates the different modalities adopted for exposure monitoring (radiological monitoring and dose follow-up), addresses the issue of communication of dosimetry data and the access to all dosimetry information for the person in charge of radiation protection, and finally briefly evokes the idea of publishing guides for each specific sectors

Annual radiological environmental monitoring report: Watts Bar Nuclear Plant, 1991

International Nuclear Information System (INIS)

1992-04-01

This report describes the preoperational environmental radiological monitoring program conducted by TVA in the vicinity of the Watts Bar Nuclear Plant (WBN) in 1991. The program includes the collection of samples from the environment and the determination of the concentrations of radioactive materials in the samples. Samples are taken from stations in the general area of the plant and from areas that will not be influenced by plant operations. Material sampled includes air, water, milk, foods, vegetation, soil, fish, sediment, and direct radiation levels. During plant operations, results from stations near the plant will be compared with concentrations from control stations and with preoperational measurements to determine potential impacts to the public. Exposures calculated from environmental samples were contributed by naturally occurring radioactive materials, from materials commonly found in the environment a a result of atmospheric fallout, or from the operation of other nuclear facilities in the area. Since WBN has not operated, there has been no contribution of radioactivity from the plant to the environment

Annual radiological environmental monitoring report: Watts Bar Nuclear Plant, 1992

International Nuclear Information System (INIS)

1993-04-01

This report describes the preoperational environmental radiological monitoring program conducted by TVA in the vicinity of the Watts Bar Nuclear Plant (WBN) in 1992. The program includes the collection of samples from the environment and the determination of the concentrations of radioactive materials in the samples. Samples are taken from stations in the general area of the plant and from areas that will not be influenced by plant operations. Material sampled includes air, water, milk, foods, vegetation, soil, fish, sediment, and direct radiation levels. During plant operations, results from stations near the plant will be compared with concentrations from control stations and with preoperational measurements to determine potential impacts to the public. Exposures calculated from environmental samples were contributed by naturally occurring radioactive materials, from materials commonly found in the environment as a result of atmospheric fallout, or from the operation of other nuclear facilities in the area. Since WBN has not operated, there has been no contribution of radioactivity from the plant to the environment

Annual radiological environmental monitoring report, Watts Bar Nuclear Plant

International Nuclear Information System (INIS)

1988-05-01

This report describes the preoperational environmental radiological monitoring program conducted by TVA in the vicinity of the Watts Bar Nuclear Plant (WBN) in 1988. The program includes the collection of samples from the environment and the determination of the concentrations of radioactive materials in the samples. Samples are taken from stations in the general area of the plant and from areas that will not be influenced by plant operations. Station locations are selected after careful consideration of the weather patterns and projected radiation doses to the various areas around the plant. Material sampled includes air, water, milk, foods, vegetation, soil, fish, sediment, and direct radiation levels. During plant operations, results from stations near the plant will be compared with concentrations from control stations and with preoperational measurements to determine potential impacts to the public. The exposures calculated from environmental samples were contributed by naturally occurring radioactive materials, from materials commonly found in the environment as a result of atmospheric fallout, or from the operation of other nuclear facilities in the area. Since WBN has not operated, there has been no contribution of radioactivity from the plant to the environment. 4 refs., 2 figs., 1 tab

Monitoring activities review of the Radiological Environmental Surveillance Program

International Nuclear Information System (INIS)

Ritter, P.D.

1992-03-01

The 1992 Monitoring Activities Review (MAR) is directed at the Radiological Environment Surveillance Program (RESP) activities at the Radioactive Waste Management Complex (RWMC) of Idaho Engineering Laboratory (INEL). MAR panelists studied RESP documents and discussed their concerns with Environmental Monitoring Unit (EMU) staff and other panel members. These concerns were subsequently consolidated into a collection of recommendations with supporting discussions. Recommendations focus on specific monitoring activities, as well as the overall program. The MAR report also contains pertinent comments that should not require further action

Follow-up radiological surveillance, Marshall Islands

International Nuclear Information System (INIS)

Greenhouse, N.A.

1978-01-01

The political approvals have been given for the return of Bikini and Enewetak Atolls to their original inhabitants. These two regions, which comprised the Pacific Nuclear Testing Areas from 1946 to 1958, are now being repopulated by their original inhabitants and their families. Recent assessments of internal and external exposure pathways at Bikini and Enewetak have indicated that doses and dose commitments in excess of current radiation protection guidelines are possible or even likely for persons living in these areas. Rongelap and Utirik Atolls, which were downwind of the 1954 Bravo event, also received significant fallout; potential radiological problems exist in these areas as well. In view of this prospect, follow-up environmental monitoring and personnel monitoring programs are being established to maintain our cognizance of radiological conditions, and to make corrective action where necessary. The unexpected finding of detectable amounts (above background) of plutonium in the urine of individuals at Bikini and Rongelap Atolls also raises the possibility of radiological problems in the long term from environmentally-derived plutonium via pathways which are not completely understood. This finding adds further impetus to the surveillance programs for an area where real radiological concerns for the general public are already known to exist. The continuing environmental and personnel monitoring programs which this paper describes are a necessary part of the BNL radiological safety program in the Marshall Islands, which is designed to do the following: (1) elucidate the internal exposure pathways; (2) define the external radiation environment; (3) assess the doses and dose commitments from radioactivity in the environment; (4) provide the feedback necessary to improve existing predictive modelling of radiological trends; and (5) suggest actions which will minimize doses via the more significant pathways. (author)

Monitoring of the radiological environmental impact of the AREVA site of Tricastin

International Nuclear Information System (INIS)

Mercat, C.; Brun, F.; Florens, P.; Petit, J.; Garnier, F.; Devin, P.

2010-01-01

Set up at the beginning of the site's operations, in 1962, the monitoring of the radiological environmental impact of the AREVA site of Tricastin has evolved over time to meet more specifically the multiple objectives of environmental monitoring: to prove the respect of the commitments required by the authorities, to be able to detect a dysfunction in the observed levels, to enable the assessment of impacts of industrial activities, to ensure the balance between environmental quality and the use made by the local population and to inform the public of the radiological state of the environment. Thousands of data were acquired on the radioactivity of all environmental compartments as well as on the functioning of local ecosystems. Today, the Network of Environmental Monitoring of AREVA Tricastin goes beyond the requirements of routine monitoring to provide innovative solutions for monitoring the radioactivity (especially for uranium) in the environment. (author)

Data Quality Objectives Supporting Radiological Air Emissions Monitoring for the PNNL Richland Campus

Energy Technology Data Exchange (ETDEWEB)

Snyder, Sandra F. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Moleta, Donna Grace L. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Meier, Kirsten M. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Barnett, John M. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

2017-12-31

This is the second revision of the DQO Supporting Radiological Air Emissions Monitoring for the Pacific Northwest National Laboratory Richland Campus. In January 2017, the PNNL Richland Campus expanded to the north by 0.35 km² (85.6 acres). Under the requirements of Washington State Department of Health Radioactive Air Emissions License (RAEL)-005, the PNNL Campus operates and maintains a radiological air monitoring program. This revision documents and evaluates the newly acquired acreage while also removing recreational land at the southwest, and also re-examines all active radioactive emission units on the PNNL Campus. No buildings are located on this new Campus land, which was transferred from the U.S. DOE Hanford Site. Additionally, this revision includes information regarding the background monitoring station PNL-5 in Benton City, Washington, which became active in October 2016. The key purpose of this revision is to determine the adequacy of the existing environmental surveillance stations to monitor radiological air emissions in light of this northern boundary change.

Public monitoring during the radiological accident in Goiania

International Nuclear Information System (INIS)

Ferreira, W.M.

2000-01-01

During the radiological accident with Cs 137 occurred at Goiania, Brazil, many people were contaminated. To identify the people with possible contamination a large place in the center of the city was selected for screening people with a possibility of contamination. This paper describes the work involved monitoring about 112.800 persons in a period of three month. (author)

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.

Federal Radiological Monitoring and Assessment Center (FRMAC), US response to major radiological accidents

International Nuclear Information System (INIS)

Mueller, P.G.

2000-01-01

radiological materials from: Nuclear Fuel Cycle Facilities, Space Craft Launches, Weapon (Department of Defence or DOE) Transportation, Weapon Production Facilities, Spacecraft Re-entry (domestic or foreign), Terrorist Incidents, High-Level Waste Transportation, Nuclear Power Plants. Key to the FRERP would be the establishment of the Federal Radiological Monitoring and Assessment Center (FRMAC). Development and implementation was assigned to DOE as the agency most capable of providing sufficient resources, assets, and support. In 1987, DOE subsequently assigned programmatic responsibility, with limited funding, to the Nevada Operations Office in Las Vegas, Nevada. (author)

Analgosedation and monitoring in interventional radiology

International Nuclear Information System (INIS)

Girolami, Guido; Steinbrich, Roman; Jacob, Augustinus Ludwig

2010-01-01

This article deals with the change of treatment in interventional radiology during the last decade adding a wider margin of safety through automated monitoring and better patient comfort through a combination of sedation and analgetics. In this regard it is very important to ensure adherence to standard procedures that are as simple as possible, to provide adequate training of staff members and to keep a succinct procedure protocol to ensure a high quality of care. Guidelines and checklists for the safe performance of this 'comfort-therapy' are given. (orig.)

Results of the radiological environmental monitoring network in the Central Eastern region of Cuba

International Nuclear Information System (INIS)

Montalvan Estrada, O.; Brigido Flores, R.; Rosa Suarez, R.; Barreras Caballero, A.; Damera Martinez, A.

1998-01-01

The radiological environmental monitoring laboratory of Camaguey is a member of the Cuban radiological environmental network and it has been carried out a series of measures about radioactivity in the atmosphere: gamma-dose rate, gross-beta activities in fallout and in aerosols. The results show that this region has a low radiological background and it has been exposure contamination

Summary of radiological monitoring of Columbia River water along the Hanford Reach, 1980 through 1989

International Nuclear Information System (INIS)

Dirkes, R.L.

1994-02-01

The Surface Environmental Surveillance Project (SESP) is conducted by the Pacific Northwest Laboratory (PNL) for the US Department of Energy (DOE) at the Hanford Site in southeastern Washington State. The Columbia River monitoring program, conducted as part of the SESP, provides a historical record of contaminant concentrations in the river attributable to natural causes, worldwide fallout, and operations conducted at the Hanford Site. In addition to ongoing monitoring, special studies are conducted periodically to enhance the understanding of the transport and fate of contaminants in the river. The Columbia River monitoring program includes sampling of river water, river sediment, river-bank springs entering the river, and various types of aquatic biota found in or along the river. These samples are analyzed for radiological constituents and a wide range of chemical parameters. This report describes the water sampling component of the overall Columbia River monitoring program conducted during the years 1980 through 1989 and summarizes the radiological results generated through the program during this time period. The only radionuclides found in the river that were consistently influenced by Hanford were tritium and iodine-129. Strontium-90 and uranium, also attributable to Hanford operations, were present in localized areas within the river near ground-water discharge points; however, these contaminants are quickly dispersed within the river to concentrations similar to background

Data Quality Objectives Supporting Radiological Air Emissions Monitoring for the PNNL Site

Energy Technology Data Exchange (ETDEWEB)

Barnett, J. Matthew; Meier, Kirsten M.; Snyder, Sandra F.; Fritz, Brad G.; Poston, Ted M.; Rhoads, Kathleen

2010-05-25

This document of Data Quality Objectives (DQOs) was prepared based on the U.S. Environmental Protection Agency (EPA) Guidance on Systematic Planning Using the Data Quality Objectives Process, EPA, QA/G4, 2/2006 (EPA 2006) as well as several other published DQOs. Pacific Northwest National Laboratory (PNNL) is in the process of developing a radiological air monitoring program for the PNNL Site that is distinct from that of the nearby Hanford Site. Radiological emissions at the PNNL Site result from Physical Sciences Facility (PSF) major emissions units. A team was established to determine how the PNNL Site would meet federal regulations and address guidelines developed to monitor and estimate offsite air emissions of radioactive materials. The result is a program that monitors the impact to the public from the PNNL Site.

Radiological monitoring plan for the Oak Ridge Y-12 Plant: Surface Water

International Nuclear Information System (INIS)

1997-10-01

The Y-12 Plant conducts a surface water monitoring program in response to DOE Orders and state of Tennessee requirements under the National Pollutant Discharge Elimination System (NPDES). The anticipated codification of DOE Order 5400.5 for radiation protection of the public and the environment (10 CFR Part 834) will require an environmental radiation protection plan (ERPP). The NPDES permit issued by the state of Tennessee requires a radiological monitoring plan (RMP) for Y-12 Plant surface waters. In a May 4, 1995 memo, the state of Tennessee, Division of Water Pollution Control, stated their desired needs and goals regarding the content of RMPs, associated documentation, and data resulting from the RMPs required under the NPDES permitting system (L. Bunting, General Discussion, Radiological Monitoring Plans, Tennessee Division of Water Pollution Control, May 4,1995). Appendix A provides an overview of how the Y-12 Plant will begin to address these needs and goals. It provides a more complete, documented basis for the current Y-12 Plant surface water monitoring program and is intended to supplement documentation provided in the Annual Site Environmental Reports (ASERs), NPDES reports, Groundwater Quality Assessment Reports, and studies conducted under the Y-12 Plant Environmental Restoration (ER) Program. The purpose of this update to the Y-12 Plant RMP is to satisfy the requirements of the current NPDES permit, DOE Order 5400.5, and 10 CFR Part 834, as current proposed, by defining the radiological monitoring plan for surface water for the Y-12 Plant. This plan includes initial storm water monitoring and data analysis. Related activities such as sanitary sewer and sediment monitoring are also summarized. The plan discusses monitoring goals necessary to determine background concentrations of radionuclides, to quantify releases, determine trends, satisfy regulatory requirements, support consequence assessments, and meet requirements that releases be ''as low as

Annual evaluation of routine radiological survey/monitoring frequencies for the High Ranking Facilities Deactivating Project at Oak Ridge, Tennessee

International Nuclear Information System (INIS)

1998-12-01

The Bethel Valley Watershed at the Oak Ridge National Laboratory (ORNL) has several Environmental Management (EM) facilities that are designated for deactivation and subsequent decontamination and decommissioning (D and D). The Surplus Facilities Program at ORNL provides surveillance and maintenance support for these facilities as deactivation objectives are completed to reduce the risks associated with radioactive material inventories, etc. The Bechtel Jacobs Company LLC Radiological Control (RADCON) Program has established requirements for radiological monitoring and surveying radiological conditions in these facilities. These requirements include an annual evaluation of routine radiation survey and monitoring frequencies. Radiological survey/monitoring frequencies were evaluated for two High Ranking Facilities Deactivation Project facilities, the Bulk Shielding Facility and Tower Shielding Facility. Considerable progress has been made toward accomplishing deactivation objectives, thus the routine radiological survey/monitoring frequencies are being reduced for 1999. This report identifies the survey/monitoring frequency adjustments and provides justification that the applicable RADCON Program requirements are also satisfied

Geoinformation dataware for radiological monitoring of territories

Science.gov (United States)

Zatserkovnyi, V. I.; Kozachenko, E. V.; Shishenko, O. I.

2015-10-01

The paper provides a study, during which the fully accessible and open information from the literature and thematic maps is processed and systemized, reflecting the state of the problem of the radiological monitoring of the territories using the geoinformation technology. The stated ArcGIS technologies is used in the Web ecological Chernihiv region atlas for the map binding of sites and zones of the radioactive and chemical contamination of the territories as well as filling the atlas data with ecological and economical resources of the region.

Generic procedures for monitoring in a nuclear or radiological emergency

International Nuclear Information System (INIS)

2005-03-01

This book is a Japanese version of the International Atomic Energy Agency (IAEA) publication (Report No., IAEA-TECDOC-1092, published in Vienna, 1999) of the same title. The translation of the original English into Japanese was done by the Department of Dose Assessment, Research Center for Radiation Emergency Medicine, National Institute of Radiological Sciences (NIRS). Since the Department was organized in addition to the Emergency Medicine Dept. in the Center in 2003 to establish a system for rapid and accurate dose assessment at emergent radiation exposure, the translation is thus a result of the department works, and is published with permission by IAEA as one of a series of NIRS Report (NIRS-M--179) for use in the country. The book is essentially a manual for providing technical requirements and procedures for radiation monitoring, environmental sampling and laboratory analyses for a nuclear or other radiological emergency. The contents are: Introduction, Outline of monitoring, Monitoring of outdoor radiation and contamination, Outdoor sampling, Gross alpha/beta measurement, Gamma spectrometry, Activation analyses, Basic data assessment, Work-sheets, Check-list for measuring equipments, Appendices, References, and others. (S.I.)

Present state and problems of radiological protection monitoring for high energy electron accelerator facilities in SPring-8

International Nuclear Information System (INIS)

Miyamoto, Yukihiro; Harada, Yasunori; Ueda, Hisao

1998-09-01

The present state and problems of the radiological protection monitoring for the high-energy electron accelerator are summarized. In the radiological protection monitoring for SPring-8, a third generation synchrotron radiation facility, there are many problems specific to the high-energy electron accelerator. This report describes the monitoring technique of pulsed radiation, high-energy radiation and low-energy radiation, and their problems. The management of induced radioactivity and the effects of electro-magnetic noise to monitoring instruments are also discussed. (author)

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

International Nuclear Information System (INIS)

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

1987-05-01

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

The radiological monitoring protocol for metallic products and cleared scrap management

International Nuclear Information System (INIS)

Gil Lopez, E.

2003-01-01

Event though the use of nuclear and radiological techniques is subject to strict controls in most countries, the presence of radioactive material in batches of metallic scrap has been detected with relative frequency in the last few years. This circumstance has motivated the implementation of a series of national and international initiatives aimed at detecting and preventing this type of events, whether they be intentional or involuntary. The Spanish iron and steel industry is one of the country's most important industrial sectors, and to a great extent it depends on the importation of a very significant amount of metallic scrap that it uses as raw material. Experience has shown that countries that import large amounts of scrap, apart from supporting the mentioned international initiatives, should complement them with other national initiatives to reduce the risks resulting from the presence of radioactive material in scrap. In this context, the Spanish authorities, together with trade unions and entrepreneurial associations in the metal reclamations and smelting sectors and ENRESA, have signed a voluntary Protocol that defines and implements a national radiological monitoring and control system for scrap materials and their byproducts. The Protocol defines the obligations and rights of the signatories, and it describes the monitoring and control system and its legal bases, the operation of both specific and other general-purpose radiological monitoring equipment that existed prior to this initiative, the development of radiological training and dissemination plans for professionals in the metal reclamation and smelting sectors, the establishment of effective systems for the safe management of any radioactive materials detected, and the general improvement of the national response system in the event of radiological emergencies. Since the Protocol took effect in November 1999, more than 100 enterprises from the metallurgical (steel, copper, lead and aluminum

New method for presenting offsite radiological monitoring data during emergency preparedness exercises

International Nuclear Information System (INIS)

Moeller, M.P.; Martin, G.F.; Hickey, E.E.; Jamison, J.D.

1986-09-01

As scenarios for exercises become more complicated and flexible to challenge emergency response personnel, improved means of presenting data must be developed. To provide maximum realism and free play during an exercise, staff at the Pacific Northwest Laboratory (PNL) have recently devised a simple method of presenting realistic radiological field monitoring information for a range of possible releases. The method uses only two pieces of paper. The first is a map of the offsite area showing the shape of the plume for the duration of the exercise. The second is a semilog graph containing curves that relate exposure rate and iodine concentration to downwind distance and time. Several techniques are used to maximize the information on the graph

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

Energy Technology Data Exchange (ETDEWEB)

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

2006-04-15

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

Tonopah Test Range Air Monitoring: CY2016 Meteorological, Radiological, and Wind Transported Particulate Observations

Energy Technology Data Exchange (ETDEWEB)

Chapman, Jenny [Desert Research Inst. (DRI), Las Vegas, NV (United States); Nikolich, George [Desert Research Inst. (DRI), Las Vegas, NV (United States); Shadel, Craig [Desert Research Inst. (DRI), Las Vegas, NV (United States); McCurdy, Greg [Desert Research Inst. (DRI), Las Vegas, NV (United States); Etyemezian, Vicken [Desert Research Inst. (DRI), Las Vegas, NV (United States); Miller, Julianne J [Desert Research Inst. (DRI), Las Vegas, NV (United States); Mizell, Steve [Desert Research Inst. (DRI), Las Vegas, NV (United States)

2017-10-01

In 1963, the U.S. Department of Energy (DOE) (formerly the Atomic Energy Commission [AEC]), implemented Operation Roller Coaster on the Tonopah Test Range (TTR) and an adjacent area of the Nevada Test and Training Range (NTTR) (formerly the Nellis Air Force Range). This operation resulted in radionuclide-contaminated soils at the Clean Slate I, II, and III sites. This report documents observations made during ongoing monitoring of radiological, meteorological, and dust conditions at stations installed adjacent to Clean Slate I and Clean Slate III, and at the TTR Sandia National Laboratories (SNL) Range Operations Control (ROC) center. The primary objective of the monitoring effort is to determine if wind blowing across the Clean Slate sites is transporting particles of radionuclide-contaminated soil beyond the physical and administrative boundaries of the sites.

Technological and operational structure of the National Automatic Network for Environmental Radiological Monitoring (RENAMORA)

International Nuclear Information System (INIS)

Martinez G, E.; Lopez G, M.; Aguirre G, J.; Fabian O, R.; Hernandez A, Y.

2015-09-01

The Comision Nacional de Seguridad Nuclear y Salvaguardias (CNSNS) in Mexico is a decentralized body, under the Secretaria de Energia whose main mission is to ensure that activities involving nuclear and radioactive materials as well as ionizing radiation sources are carried out with maximum security, considering the current technological developments. In order to monitor the levels of environmental radiation to which the population is exposed, the CNSNS has established a series of radiological monitoring programs that allow characterize the environmental radiation levels in each zone or region in the country; to identify the occurrence of natural or artificial radiological events, such as nuclear tests and accidents in radioactive or nuclear facilities. The National Automatic Network for Environmental Radiological Monitoring (RENAMORA) project was initiated with the support of the IAEA through MEX9/049 project and its purpose is to have a network of instruments that automatically and in real time, transmit information of the gamma radiological environmental status of the national territory and changes occurring in it. This network provides data such as the speed of ambient dose equivalent, temperature and humidity in different regions of the country. The network is composed of 92 stations that are distributed throughout the national territory. The structure of the stations has evolved since its inception, now allowing detection tasks, data transmission and managing them remotely from the main server, which is located in the CNSNS, which is performed a statistical dose for each monitoring station. Each monitoring station is formed in its current structure by a probe detection of gamma radiation, a communication module and associated electronics, a mini Web server DataGATE, a cellular modem and an interface converter. (Author)

Endoscopy versus radiology in post-procedural monitoring after peroral endoscopic myotomy (POEM).

Science.gov (United States)

Nast, Jan Friso; Berliner, Christoph; Rösch, Thomas; von Renteln, Daniel; Noder, Tania; Schachschal, Guido; Groth, Stefan; Ittrich, Harald; Kersten, Jan F; Adam, Gerhard; Werner, Yuki B

2018-03-15

The newly developed technique of peroral endoscopic myotomy (POEM) has been shown to be effective in several short- and mid-term studies. Limited information is available about the adequacy of immediate post-POEM monitoring tests. POEM was performed under general anesthesia in 228 patients (59.6% male, mean age 45.6 ± 15.5 years). Post-procedural checks comprised clinical and laboratory examination, and, during post-procedure days 1-5, endoscopy and-in the first 114 cases-radiologic examination using water-soluble contrast (1st group); the remaining patients underwent post-procedure controls without radiology (2nd group). Main outcome was value of endoscopic compared to radiologic control for recognition of early adverse events. In the first group, routine fluoroscopic contrast swallow suggested minor leakages at the mucosal entry site in two cases which was confirmed endoscopically in only one. Endoscopy revealed two minor entry site leakages and, in six additional cases, dislocated clips without leakage (overall 5.3%). All eight patients underwent reclipping and healed without clinical sequelae. In the 2nd group, endoscopy showed 5 clip dislocations (all reclipped) and one ischemic cardiac perforation in a patient with clinical deterioration on post-POEM day 1 who had to undergo surgery after confirmation of leakage by CT. Radiologic monitoring (contrast swallow) after POEM is not useful and can be omitted. Even routine endoscopic monitoring for detection and closure of minor defects of the mucosal entry site yields limited information with regards to final outcome; major complications are very rare and probably associated with clinical deterioration. Clinical Trials Gov Registration number of the main study: NCT01405417.

Radiological safety and control

Energy Technology Data Exchange (ETDEWEB)

Chang, Sea Young; Yoo, Y S; Lee, J C; Lee, T Y; Lee, J L; Kim, B W; Lee, B J; Chung, K K; Chung, R I; Kim, J S; Lee, H S; Han, Y D; Lee, J I; Lee, K C; Yoon, J H; Sul, C W; Kim, C K; Yoon, K S; Seo, K W; Yoon, Y C [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

1996-01-01

This report describes the annual results of radiological safety and control program of 1995. This program consists of working area monitoring including HANARO, personnel radiation monitoring, education for radiation protection. As a result, the objectives of radiation protection have been achieved satisfactorily through the activities mentioned above. Also, the calibration services were provided to insure accurate radiation measurement in the radiation working places. 21 figs., 39 tabs., 5 refs. (Author) .new.

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

International Nuclear Information System (INIS)

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

2008-01-01

radiation. Through the sea route (Radiation monitoring of Mumbai coast) the average of the dose rates recorded was 35±05 nGy.h -1 . Handheld monitors were used for detail monitoring of the locations like scrap yards, shopping mall, temples etc to rule out the presence of any orphan sources. Elevated radiation levels ranging from 140 - 160 nGy.h -1 were observed at few locations within the Mumbai city. The laboratory based spectrometry analysis of soil/rock samples collected from such locations confirmed the presence of higher concentration of K 40 in these areas up to 1450 Bq.kg -1 compared to Mumbai average of 291.7±14.9 Bq.kg -1 and 394 ± 14.8 Bq.kg -1 for soil and rock respectively. This paper gives the details of the monitoring methodology and systems used along with the results arrived after the radiological mapping of Mumbai city. (author)

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

International Nuclear Information System (INIS)

Lahtinen, J.

2006-04-01

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

Model for the elaboration of program of environmental radiological monitoring reports

International Nuclear Information System (INIS)

2005-11-01

This Regulation refers to the requirements of the Regulation CNEN-NN.3.01 'Basic Guidelines for Radiation Protection', expressed in the section 5.14, and its application related to the emission of reports of Environmental Radiological Monitoring Program to be submitted to CNEN evaluation

Nevada Test Site Area 25. Radiological survey and cleanup project, 1974-1983. Final report

International Nuclear Information System (INIS)

McKnight, R.K.; Rosenberry, C.E.; Orcutt, J.A.

1984-01-01

This report describes radiological survey, decontamination and decommissioning of the Nevada Test Site (NTS) Area 25 facilities and land areas incorporated in the Nuclear Rocket Development Station (NRDS). Buildings, facilities and support systems used after 1959 for nuclear reactor and engine testing were surveyed for the presence of radioactive contamination. The cleanup was part of the Surplus Facilities Management Program funded by the Department of Energy's Richland Operations Office. The radiological survey portion of the project encompassed portable instrument surveys and removable contamination surveys (swipe) for alpha and beta plus gamma radiation contamination of facilities, equipment and land areas. Soil sampling was also accomplished. The majority of Area 25 facilities and land areas have been returned to unrestricted use. Remaining radiologically contaminated areas are posted with warning signs and barricades. 12 figures

Systematic Layout Planning of a Radiology Reporting Area to Optimize Radiologists' Performance.

Science.gov (United States)

Benitez, Guilherme Brittes; Fogliatto, Flavio Sanson; Cardoso, Ricardo Bertoglio; Torres, Felipe Soares; Faccin, Carlo Sasso; Dora, José Miguel

2018-04-01

Optimizing radiologists' performance is a major priority for managers of health services/systems, since the radiologists' reporting activity imposes a severe constraint on radiology productivity. Despite that, methods to optimize radiologists' reporting workplace layout are scarce in the literature. This study was performed in the Radiology Division (RD) of an 850-bed University-based general hospital. The analysis of the reporting workplace layout was carried out using the systematic layout planning (SLP) method, in association with cluster analysis as a complementary tool in early stages of SLP. Radiologists, architects, and hospital managers were the stakeholders consulted for the completion of different stages of the layout planning process. A step-by-step description of the proposed methodology to plan an RD reporting layout is presented. Clusters of radiologists were defined using types of exams reported and their frequency of occurrence as clustering variables. Sectors with high degree of interaction were placed in proximity in the new RD layout, with separation of noisy and quiet areas. Four reporting cells were positioned in the quiet area, grouping radiologists by subspecialty, as follows: cluster 1-abdomen; cluster 2-musculoskeletal; cluster 3-neurological, vascular and head & neck; cluster 4-thoracic and cardiac. The creation of reporting cells has the potential to limit unplanned interruptions and enhance the exchange of knowledge and information within cells, joining radiologists with the same expertise. That should lead to improvements in productivity, allowing managers to more easily monitor radiologists' performance.

Radiation area monitoring by wireless-communicating area monitor with surveillance camera

International Nuclear Information System (INIS)

Shimura, Mitsuo; Kobayashi, Hiromitsu; Kitahara, Hideki; Kobayashi, Hironobu; Okamoto, Shinji

2004-01-01

Aiming at a dose reduction and a work efficiency improvement for nuclear power plants that have high dose regions, we have developed our system of wireless-communicating Area Monitor with Surveillance Camera, and have performed an on-site test. Now we are implementing this Area Monitor with Surveillance Camera for a use as a TV camera in the controlled-area, which enables a personal computer to simultaneously display two or more dose values and site live images on the screen. For the radiation detector of this Area Monitor System, our wireless-communicating dosimeter is utilized. Image data are transmitted via a wireless Local Area Network (LAN). As a test result, image transmission of a maximum of 20 frames per second has been realized, which shows that this concept is a practical application. Remote-site monitoring also has been realized from an office desk located within the non-controlled area, adopting a Japan's wireless phone system, PHS (Personal Handy Phone) for the transmission interface. (author)

Quality control of the interpretation monitors of digital radiological images

International Nuclear Information System (INIS)

Favero, Mariana S.; Goulart, Adriano Oliveira S.

2016-01-01

The performance monitors has great importance in image quality of digital radiographic systems. In environments without films, it became necessary to implement acceptance testing and quality control monitors used for interpretation of medical images. The monitors dedicated to radiodiagnostic should provide information that represent slight differences in x-ray attenuation or minor differences in some anatomical region of interest. This should also result in small differences in luminance of an image represented. Factors affecting the quality of medical imaging are contrast, noise, resolution, artifacts and distortions. Therefore, a monitor must have specific characteristics, making it possible for the observer to carry out an assessment that leads to better diagnosis. Based on the need to evaluate diagnostic monitors in various radiological applications, this paper presents a summary for implementation and standardization of tests that are recommended by the publication AAPM Report 03. (author)

Individual radiological monitoring for exposed personnel of Nuclear Fuel Plant at Pitesti

International Nuclear Information System (INIS)

Ivana, T.; Epure, Gh.

2010-01-01

In the activity of nuclear fuel fabrication of CANDU type, based on natural and depleted uranium, individual radiological monitoring of the personnel exposed to ionizing radiation is very carefully approached. For Nuclear Fuel Plant (NFP) facility, where uranium appears in bulk and itemized form, measures for individual radiological monitoring are established by Radiological Safety Manual (MSR) in accordance with national and international legislation. All NFP employees are classified in either category A or category B of exposure to ionizing radiation. The classification is a function of type of activity and magnitude of exposure. All the exposed personnel are monitored for external doses (from gamma radiation) by measuring the equivalent dose H p (10) with monthly frequency. The system used for external individual dosimetric monitoring is based on the thermoluminescent dosimeter (TLD) of PANASONIC type UD813AS14. The NFP incorporates an in-house dosimetric laboratory notified by Romanian regulatory body CNCAN (National Commission for Control of Nuclear Activities). The workers handling nuclear materials are exposed to internal intake of uranium, mainly by inhalation. For internal doses monitoring is included part of exposed employees working directly with radioactive open sources (pulverulent or liquid nuclear materials), UO 2 sinterable powder, green pellets, sintered pellets, scrap and radioactive effluents. The estimation of internal exposure is made quarterly using the results from radioactive airborne monitors operating in the working places. The internal dose of each person exposed to open sources is calculated taking into account the rate of breathing, the time spent at the work place and the dose-activity coefficient (variable function of uranium absorption rate). The total effective individual dose is obtained by summing the external dose and internal dose (E=E ext +E int ). For conformity, the total effective individual dose (E) is compared with dose

RadSTraM: Radiological Source Tracking and Monitoring, Phase II Final Report

Energy Technology Data Exchange (ETDEWEB)

Warren, Tracy A [ORNL; Walker, Randy M [ORNL; Hill, David E [ORNL; Gross, Ian G [ORNL; Smith, Cyrus M [ORNL; Abercrombie, Robert K [ORNL

2008-12-01

This report focuses on the technical information gained from the Radiological Source Tracking and Monitoring (RadSTraM) Phase II investigation and its implications. The intent of the RadSTraM project was to determine the feasibility of tracking radioactive materials in commerce, particularly International Atomic Energy Agency (IAEA) Category 3 and 4 materials. Specifically, Phase II of the project addressed tracking radiological medical isotopes in commerce. These categories of materials are susceptible to loss or theft but the problem is not being addressed by other agencies.

RadSTraM: Radiological Source Tracking and Monitoring, Phase II Final Report

International Nuclear Information System (INIS)

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

2008-01-01

This report focuses on the technical information gained from the Radiological Source Tracking and Monitoring (RadSTraM) Phase II investigation and its implications. The intent of the RadSTraM project was to determine the feasibility of tracking radioactive materials in commerce, particularly International Atomic Energy Agency (IAEA) Category 3 and 4 materials. Specifically, Phase II of the project addressed tracking radiological medical isotopes in commerce. These categories of materials are susceptible to loss or theft but the problem is not being addressed by other agencies

84-KILOMETER RADIOLOGICAL MONITORING GRID

International Nuclear Information System (INIS)

L. Roe

2000-01-01

The purpose of this calculation is to document the development of a radial grid that is suitable for evaluating the pathways and potential impacts of a release of radioactive materials to the environment within a distance of 84 kilometers (km). The center of the grid represents an approximate location from which a potential release of radioactive materials could originate. The center is located on Nevada State Plane coordinates Northing 765621.5, and Easting 570433.6, which is on the eastern side of Exile Hill at the Yucca Mountain site. The North Portal Pad is located over this point. The grid resulting from this calculation is intended for use primarily in the Radiological Monitoring Program (RadMP). This grid also is suitable for use in Biosphere Modeling and other Yucca Mountain Site Characteristic Project (YMP) activities that require the evaluation of data referenced by spatial or geographic coordinates

Radiological Worker Training: Radiological Worker 2 study guides

International Nuclear Information System (INIS)

1992-10-01

Upon completion of this training course, the participant will have the knowledge to work safely in areas controlled for radiological purposes using proper radiological practices. Radiological Worker H Training, for the worker whose job assignment involves entry into Radiological Buffer Areas and all types of Radiation Contamination and Airborne Radioactivity Areas. This course is designed to prepare the worker to work safely in and around radiological areas and present methods to use to ensure individual radiation exposure is maintained As Low As Reasonably Achievable

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.).

Release protocol to address DOE moratorium on shipments of waste generated in radiologically controlled areas

International Nuclear Information System (INIS)

Rathbun, L.A.; Boothe, G.F.

1992-10-01

On May 17, 1991 the US DOE Office of Waste Operations issued a moratorium on the shipment of hazardous waste from radiologically contaminated or potentially contaminated areas on DOE sites to offsite facilities not licensed for radiological material. This document describes a release protocol generated by Westinghouse Hanford submitted for US DOE approval. Topics considered include designating Radiological Materials Management Areas (RMMAs), classification of wastes, handling of mixed wastes, detection limits

Development of web monitoring radiation area monitor

International Nuclear Information System (INIS)

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

2005-01-01

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

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

International Nuclear Information System (INIS)

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

2008-01-01

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

Tonopah Test Range Air Monitoring: CY2015 Meteorological, Radiological, and Airborne Particulate Observations

International Nuclear Information System (INIS)

Nikolich, George; Shadel, Craig; Chapman, Jenny; McCurdy, Greg; Etyemezian, Vicken; Miller, Julianne J.; Mizell, Steve

2016-01-01

In 1963, the U.S. Department of Energy (DOE) (formerly the Atomic Energy Commission [AEC]), implemented Operation Roller Coaster on the Tonopah Test Range (TTR) and an adjacent area of the Nevada Test and Training Range (NTTR) (formerly the Nellis Air Force Range). The operation resulted in radionuclide-contaminated soils at the Clean Slate I, II, and III sites. This report documents observations made during ongoing monitoring of radiological, meteorological, and dust conditions at stations installed adjacent to Clean Slate I and Clean Slate III, and at the TTR Sandia National Laboratories (SNL) Range Operations Control (ROC) center. The primary objective of the monitoring effort is to determine if winds blowing across the Clean Slate sites are transporting particles of radionuclide-contaminated soil beyond the physical and administrative boundaries of the sites. Radionuclide assessment of airborne particulates in 2015 found the gross alpha and gross beta values of dust collected from the filters at the monitoring stations are consistent with background conditions. The meteorological and particle monitoring indicate that conditions for wind-borne contaminant movement exist at the Clean Slate sites and that, although the transport of radionuclide-contaminated soil by suspension has not been detected, movement by saltation is occurring.

Tonopah Test Range Air Monitoring: CY2015 Meteorological, Radiological, and Airborne Particulate Observations

Energy Technology Data Exchange (ETDEWEB)

Nikolich, George [Nevada University, Reno, NV (United States). Desert Research Inst.; Shadel, Craig [Nevada University, Reno, NV (United States). Desert Research Inst.; Chapman, Jenny [Nevada University, Reno, NV (United States). Desert Research Inst.; McCurdy, Greg [Nevada University, Reno, NV (United States). Desert Research Inst.; Etyemezian, Vicken [Nevada University, Reno, NV (United States). Desert Research Inst.; Miller, Julianne J. [Nevada University, Reno, NV (United States). Desert Research Inst.; Mizell, Steve [Nevada University, Reno, NV (United States). Desert Research Inst.

2016-09-01

In 1963, the U.S. Department of Energy (DOE) (formerly the Atomic Energy Commission [AEC]), implemented Operation Roller Coaster on the Tonopah Test Range (TTR) and an adjacent area of the Nevada Test and Training Range (NTTR) (formerly the Nellis Air Force Range). The operation resulted in radionuclide-contaminated soils at the Clean Slate I, II, and III sites. This report documents observations made during ongoing monitoring of radiological, meteorological, and dust conditions at stations installed adjacent to Clean Slate I and Clean Slate III, and at the TTR Sandia National Laboratories (SNL) Range Operations Control (ROC) center. The primary objective of the monitoring effort is to determine if winds blowing across the Clean Slate sites are transporting particles of radionuclide-contaminated soil beyond the physical and administrative boundaries of the sites. Radionuclide assessment of airborne particulates in 2015 found the gross alpha and gross beta values of dust collected from the filters at the monitoring stations are consistent with background conditions. The meteorological and particle monitoring indicate that conditions for wind-borne contaminant movement exist at the Clean Slate sites and that, although the transport of radionuclide-contaminated soil by suspension has not been detected, movement by saltation is occurring.

Registration and monitoring of radiation exposure from radiological imaging

International Nuclear Information System (INIS)

Jungmann, F.; Pinto dos Santos, D.; Hempel, J.; Dueber, C.; Mildenberger, P.

2013-01-01

Strategies for reducing radiation exposure are an important part of optimizing medical imaging and therefore a relevant quality factor in radiology. Regarding the medical radiation exposure, computed tomography has a special relevance. The use of the integrating the healthcare enterprise (IHE) radiation exposure monitoring (REM) profile is the upcoming standard for organizing and collecting exposure data in radiology. Currently most installed base devices do not support this profile generating the required digital imaging and communication in medicine (DICOM) dose structured reporting (SR). For this reason different solutions had been developed to register dose exposure measurements without having the dose SR object. Registration and analysis of dose-related parameters is required for constantly optimizing examination protocols, especially computed tomography (CT) examinations based on the latest research results in order to minimize the individual radiation dose exposure from medical imaging according to the principle as low as reasonably achievable (ALARA). (orig.) [de

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

International Nuclear Information System (INIS)

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

1999-01-01

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

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

Energy Technology Data Exchange (ETDEWEB)

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

1999-01-01

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

Anesthesia for interventional radiology

International Nuclear Information System (INIS)

van Sonnenberg, E.; Casola, G.; Varney, R.R.; D'Agostino, H.B.; Zornow, M.; Mazzie, W.

1989-01-01

We recognized that the complexity and surgical nature of many interventional radiology procedures dictate essential radiologic involvement into traditional anesthesiologic areas. They reviewed our experience with a variety of interventional procedures to document complications and problems related to anesthetic use (or misuse) and compile recommendations for rational monitoring and control for these procedures. In particular, the authors have studied complications of drug therapies and the treatment of these complications; use of complex anesthesia procedures (e.g., epidural anesthesia, succinylcholine blockage); reasons for choice of drugs (e.g., fentanyl vs meperidine vs morphine); and medico-legal aspects of radiologist performing traditional anesthesiology-type procedures

New method for presenting off-site radiological monitoring data during emergency preparedness exercises

International Nuclear Information System (INIS)

Moeller, M.P.; Martin, G.F.; Hickey, E.E.; Jamison, J.D.

1987-01-01

As scenarios for exercises become more complicated and flexible to challenge emergency response personnel, improved means of presenting data must be developed to meet this need. To provide maximum realism and free play during an exercise, staff at the Pacific Northwest Laboratory (PNL) have recently devised a simple method of presenting realistic radiological field monitoring information for a range of possible releases. The method utilizes only two pieces of paper. The first is a map of the offsite area showing the shape of the plume for the duration of the exercise. The second is a semi-log graph containing curves relating exposure rate and iodine concentration to downwind distance and time. Several techniques are used to maximize the information on the graph

Environment radiological monitoring by JNC related to the JCO criticality accident

International Nuclear Information System (INIS)

Watanabe, Hitoshi

2001-01-01

Concerning the criticality accident at JCO Co., Ltd. (JCO) which occurred at 10:35 on 30th Sep. 1999, Japan Nuclear Cycle Development Institute (JNC) established ''JNC's task force'' at 12:35 on the same data in conjunction with Head Office and Tokai Works. JNC's task force had collaborated on environmental radiological monitoring with the government of Japan and the local governments. This report compiles the results of the environmental monitoring performed by JNC's task force based on the request from the government of Japan and the local governments. (author)

Radiological investigation in the outside area of expedition's room during radiopharmaceuticals' expedition

International Nuclear Information System (INIS)

Reina, Luiz C.; Monteiro, Ilka H.T.S.; Silva, Joao Carlos P. da; Teixeira, Danilo L.; Pedro, C.R.; Santos, J. Regis dos

2013-01-01

Radiopharmaceuticals produced in IEN - Instituto de Engenharia Nuclear of the Brazilian Nuclear Energy Commission, are issued by the radiation protection team, which is responsible for preparing and issuing the packaged documentation required for movement in modal transportation. The documents are: Invoice , Shipper's Declaration of Radioactive Material , Shipper's Declaration of Dangerous Goods - (form IATA ) , Emergency Sheet, sketch of packed. All this documentation is inserted in an envelope of emergency. The Department of Radiological Protection is responsible for issuing such documents except the invoice that is issued by the Commercial Sector (Setcom). A employee of this sector is responsible for delivering it to the shipment sector. The preparation of packaged and documentation is performed in a room located in the building of Radiopharmaceutical Division. The vehicles which are used in the transport are parked outside this building, where are monitored after commissioning of packaged. The present study aims to evaluate potential and occupational radiation risks of people in transit or remain in the area where radioactive material circulates due to the shipment of radiopharmaceuticals for the classification of the area during the operation of dispatch

Assessment of radiological environment around coal mining area of Dhanbad, Jharkhand

International Nuclear Information System (INIS)

Patnaik, R.L.; Thakur, V.K.; Jha, V.N.; Sethy, N.K.; Srivastava, V.S.; Kumar, Rajesh; Tripathi, R.M.; Puranik, V.D.

2012-01-01

Naturally occurring radionuclides present in the earth crust is a significant source of human exposure. Variation in natural background radiation is expected in different geological formations. Anthropogenic activities in geological formation of elevated radionuclide level may enhance the area background. In areas of coal mining industries investigation of radiological environment is required as the residues contains significant amount of uranium and thorium series radionuclides (Van Hook, 1 979, Balogun, 2003). Radon and its short-lived progeny present in the environment contributes maximum natural background radiation dose due to inhalation. Apart from this radionuclide content in key environmental matrices may also contribute to inhalation and ingestion exposure for members of public. Present investigation was carried out in coal mining areas of Dhanbad, Jharkhand to assess the existing radiological status. A detailed investigation is required to evaluate the environmental impact of coal handling activities in the area. The contribution of 222 Rn progeny towards outdoor inhalation dose compares with global average reported by UNSCEAR (2006)

Cursory radiological assessment: Battelle Columbus Laboratory Decommissioning and Decontamination Project

International Nuclear Information System (INIS)

Smith, W.H.; Munyon, W.J.; Mosho, G.D.; Robinet, M.J.; Wynveen, R.A.

1988-10-01

This document reports on the results obtained from a cursory radiological assessment of various properties at the Battelle Columbus Laboratory, Columbia, Ohio. The cursory radiological assessment is part of a preliminary investigation for the Battelle Columbus Laboratory Decommissioning and Decontamination Project. The radiological assessment of Battelle Columbus Laboratory's two sites included conducting interior and exterior building surveys and collecting and analyzing air, sewer system, and soil samples. Direct radiological surveys were made of floor, wall, and overhead areas. Smear surveys were made on various interior building surfaces as well as the exterior building vents. Air samples were collected in select areas to determine concentrations of Rn-222, Rn-220, and Rn-219 daughters, in addition to any long-lived radioactive particulates. Radon-222 concentrations were continuously monitored over a 24-hr period at several building locations using a radon gas monitoring system. The sanitary sewer systems at King Avenue, West Jefferson-North, and West Jefferson-South were each sampled at select locations. All samples were submitted to the Argonne Analytical Chemistry Laboratory for various radiological and chemical analyses. Environmental soil corings were taken at both the King Avenue and West Jefferson sites to investigate the potential for soil contamination within the first 12-inches below grade. Further subsurface investigations at the West Jefferson-North and West Jefferson-South areas were conducted using soil boring techniques. 4 refs., 10 figs., 10 tabs

Assessment of the radiological control at the IPEN radioisotope production facility

International Nuclear Information System (INIS)

Carneiro, Janete C.G.G.; Sanches, Matias P.; Rodrigues, Demerval L.; Campos, Daniela; Nogueira, Paulo R.; Damato, Sandra R.; Pecequilo, Brigitte R.

2014-01-01

The main objective of this work is to evaluate the 2013 annual radiological control results in the radiopharmaceuticals areas of the Instituto de Pesquisas Energeticas e Nucleares, IPEN/SP, and the environmental radiological impact, resulting from the practices there performed. The current evaluation was performed through the analysis of the results obtained from occupational and environmental monitoring with air samplers and TL dosimeters. All monitoring results were compared with the limits established by national standards. The radionuclides detected by air sampling (in charcoal and paper filters) at the workplace during radioisotope production were 131 I, 99m Tc and 99 Mo, with activities concentrations values below the annual limits values. For the radioactive gaseous releases (Bq/m 3 ), the activities concentrations also remained below the maximum permissible values, excepting to 125 I release due to an unusual event occurred in a researcher laboratory, but the radiological impact to environmental was no significant. The occupational monitoring assessment was confirmed by the Environmental Radiological Monitoring Program results with air samplers and TL dosimeters. The mean annual background radiation at IPEN in 2013, according to the Environmental Radiological Monitoring Program results was 1.06 mSv. y -1 , below the ICRP 103 recommended limit of 20 mSv.y -1 for workers. (author)

National automatic network of environmental radiological monitoring (RENAMORA)

International Nuclear Information System (INIS)

Gonzalez M, J.L.; Sanchez H, L.

2003-01-01

Inside the programs of Environmental Radiological Surveillance that it carries out the National Commission of Nuclear Security and Safeguards (CNSNS), it develops an National Automatic Network of Environmental Radiological Monitoring (RENAMORA), where it is carried out a registration of speed of environmental dose in continuous and simultaneous forms with the same moment of the measurement. This net allows to account with the meticulous and opportune information that will help to characterize, in dynamics form, the radiological conditions of diverse geographical zones of the country, including the sites that by normative require bigger surveillance, like its are the Laguna Verde Nuclear power station (CNLV), the Nuclear Center of Mexico (ININ) and the Radioactive waste storage center (CADER). This net is in its first development stage; three points inside the state of Veracruz, in the surroundings of the CNLV, already its are operating; the obtained data of rapidity of environmental dose are being stored in a database inside a primary data center located in the facilities of the CNSNS in Mexico city and its will be analyzed according to the project advances. At the moment, its are installing the first ten teams corresponding to the first phase of the RENAMORA (three stages); its are carried out operation tests, transmission, reception and administration of data. The obtained data will be interpreted, analyzed and inter compared to evaluate the risk levels to that it would be hold the population and to determine thresholds that allow to integrate the alarm systems that its had considered for emergency situations. (Author)

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

Energy Technology Data Exchange (ETDEWEB)

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

2013-10-15

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

Radiological protection aspects regarding to assistance of the cesium-137 radiation accident victims in Goiania

International Nuclear Information System (INIS)

Hunt, John Graham; Oliveira Filho, Denizart Silveira de; Rabelo, Paulo Ney Pamplona

1997-01-01

The radiological protection measures taken in the general hospital of Goiania (HGG/INAMPS) and in the FEBEM institution, due to the accident involving Cesium-137 are described, as well as the work of the IRD personnel in the areas of: radiological protection of the medical and auxiliary staff, contamination control of the ward, radiological monitoring of the patients, waste management, personnel and area decontamination and patient transportation. (author)

Planning for exercises of the Federal Radiological Monitoring and Assessment Plan

International Nuclear Information System (INIS)

Adler, M.V.

1985-11-01

This report is to be used in planning radiological emergency exercises to test the Federal Radiological Monitoring and Assessment Plan (FRMAP). Although developed for this specific purpose, the document also contains material that may be useful for planning other types of exercises. This report describes the types of exercises that might be used, the steps in planning and conducting the exercises, and the special considerations required for exercises to test the FRMAP. FRMAP exercises typically involve several federal and state agencies. General and specific objectives that could guide these exercises, as well as the possible activities of all the participants - players, controllers, and evaluators - are discussed. The resources that each participating federal agency might provide during an exercise are listed

Physicochemical and radiological studies on some egyptian aquatic areas

International Nuclear Information System (INIS)

Youssef, S.K.; Abdel Malik, W.E.Y.; Seifin, S.M.; Abou-zeid, H.M.

2005-01-01

For the purpose of estimating the radiological health and safety to the Egyptian population arises from the natural background involved with coastal areas, it is necessary to make a comprehensive study to investigate the natural radionuclides activities in this environmental ecology. The locations of such areas were chosen from those in which people spend some time (e.g. the Mediterranean and Red Sea beaches, Suez Canal in addition to the River Nile Ismailia Canal and Quaroun Lake). Water and soil samples were brought from these locations and subjected to intensive physical, chemical analysis and radiological investigations. The densities of the collected soil samples were found to fall in the region of clay densities (2.30 - 2.70 g/cm 3 ). The particle size distribution analysis, of these soil samples showed values ranging from 128 Μ m to 1303 Μ according to sample site. The collected samples are mainly silicates with variable amounts of the major cations; Ca + +, Mg + +, Na + , K + with some other trace elements. For the radiological investigations 238 U , 226 R a, 232 T h and 40 K activity concentrations were resolved by spectroscopy technique. The majority of samples examined in this work showed variable activities of the naturally occurring radionuclides with fairly low levels compared with literature values reported in other countries. The analysis and discussions of the obtained data are thoroughly performed with the use of equations to estimate the radiation doses

Development of a real-time extremity dose monitor for personnel in interventional radiology

International Nuclear Information System (INIS)

Ban, Nobuhiko; Kusama, Tomoko; Adachi, Akiko

2000-01-01

Protection of personnel in interventional radiology is one of the most important issues of radiological protection in medicine. Fluoroscopically guided interventional procedures require the operation near X-ray beam, which brings a considerable hand exposure to the operators. For the purpose of effectual control of their extremity doses, we have developed a real-time extremity dose monitor which is worn on a strap around the wrist. The monitor consists of a silicon semiconductor detector, thin lithium battery and a waterproof frame with a four-digit LED display. Experiment was carried out to examine a response of the monitor to diagnostic X-rays. A practical test was also performed to evaluate usability in the actual interventional procedures. In the experiment, the extremity dose monitor was placed on an arm phantom and exposed to diagnostic X-rays. Readings of the monitor were compared to those of Capintec PS-033 shallow chamber. The monitor was highly sensitive to diagnostic X-rays. It showed a linear response down to doses of a few tens of microsieverts. For high dose-rate exposure, however, a slight decrease in the response was observed, about 10% of counting loss for 80 kV, 40 mA X-ray at one meter from the focus. With regard to energy dependence, variation was within 20% for 60 to 100 kV X-rays. The monitor showed a good angular response in general, except lateral geometry facing the far side from a detector center. In the practical test, hand exposures of medical staff were measured with the extremity dose monitor. They were also asked to fill in a questionnaire regarding size and weight of the monitor, clarity of the display and usefulness. The subjects consisted of physicians, technicians and nurses who engaged in angiography, PTCD, CT-biopsy, barium enema and so on. The readings of the monitor were less than 1 mSv in most cases while 93 mSv was recorded in an extreme case due to direct-beam exposure. In some cases, TLD rings were used together with the

Development of a real-time extremity dose monitor for personnel in interventional radiology

Energy Technology Data Exchange (ETDEWEB)

Ban, Nobuhiko; Kusama, Tomoko [Oita University of Nursing and Health Sciences, Oita (Japan); Adachi, Akiko [Oita Medical University, Oita (JP)] [and others

2000-05-01

Protection of personnel in interventional radiology is one of the most important issues of radiological protection in medicine. Fluoroscopically guided interventional procedures require the operation near X-ray beam, which brings a considerable hand exposure to the operators. For the purpose of effectual control of their extremity doses, we have developed a real-time extremity dose monitor which is worn on a strap around the wrist. The monitor consists of a silicon semiconductor detector, thin lithium battery and a waterproof frame with a four-digit LED display. Experiment was carried out to examine a response of the monitor to diagnostic X-rays. A practical test was also performed to evaluate usability in the actual interventional procedures. In the experiment, the extremity dose monitor was placed on an arm phantom and exposed to diagnostic X-rays. Readings of the monitor were compared to those of Capintec PS-033 shallow chamber. The monitor was highly sensitive to diagnostic X-rays. It showed a linear response down to doses of a few tens of microsieverts. For high dose-rate exposure, however, a slight decrease in the response was observed, about 10% of counting loss for 80 kV, 40 mA X-ray at one meter from the focus. With regard to energy dependence, variation was within 20% for 60 to 100 kV X-rays. The monitor showed a good angular response in general, except lateral geometry facing the far side from a detector center. In the practical test, hand exposures of medical staff were measured with the extremity dose monitor. They were also asked to fill in a questionnaire regarding size and weight of the monitor, clarity of the display and usefulness. The subjects consisted of physicians, technicians and nurses who engaged in angiography, PTCD, CT-biopsy, barium enema and so on. The readings of the monitor were less than 1 mSv in most cases while 93 mSv was recorded in an extreme case due to direct-beam exposure. In some cases, TLD rings were used together with the

Radiation monitoring strategy in nuclear or radiological emergencies

International Nuclear Information System (INIS)

Lahtinen, J.

2003-01-01

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

Findings of the first comprehensive radiological monitoring program of the Republic of the Marshall Islands

International Nuclear Information System (INIS)

Simon, S.L.; Graham, J.C.

1997-01-01

The Marshall Islands was the primary site of the United States atomic weapons testing program in the Pacific. From 1946 through 1958, 66 atomic weapons were detonated in the island country. For several decades, monitoring was conducted by the U.S. Department of Energy (or its predecessor agencies) on the test site atolls and neighboring atolls. However, 70% of the land area of the over 1,200 islands in the Marshall Islands was never systematically monitored prior to 1990. For the 5-y period from 1990 through 1994, the Government of the Republic of the Marshall Islands undertook an independent program to assess the radiological conditions throughout its 29 atolls. The scientific work was performed under the auspices of the Section 177 Agreement of the Compact of Free Association, U.S. public law 99-239, signed in 1986 by President Ronald Reagan. Although the total land area of the nations is a scant 180 km 2 , the islands are distributed over 6 X 10 5 km 2 of ocean. Consequently, logistics and instrumentation were main considerations, in addition to cultural and language issues. The objective of this paper is to report findings for all atolls of the Marshall Islands on the 137 Cs areal inventory (Bq m -2 ) and the external effective dose-rate (mSv y -1 ), the projected internal effective dose-rate (mSv y -1 ) from an assumed diet model, and surface soil concentrations of 239,240 Pu (Bq kg -1 ) for selected northern atolls. Interpretation is also provided on the degree of contamination above global fallout levels. This report provides the first comprehensive summary of the radiological conditions throughout the Marshall Islands. 37 refs., 25 figs., 1 tab

Chemical and radiological vulnerability assessment in urban areas

Directory of Open Access Journals (Sweden)

Stojanović Božidar

2006-01-01

Full Text Available Cities and towns are faced with various types of threat from the extraordinary events involving chemical and radiological materials as exemplified by major chemical accidents, radiological incidents, fires, explosions, traffic accidents, terrorist attacks, etc. On the other hand, many sensitive or vulnerable assets exist within cities, such as: settlements, infrastructures, hospitals, schools, churches, businesses, government, and others. Besides emergency planning, the land use planning also represents an important tool for prevention or reduction of damages on people and other assets due to unwanted events. This paper considers development of method for inclusion vulnerability assessment in land use planning with objective to assess and limit the consequences in cities of likely accidents involving hazardous materials. We made preliminary assessment of criticality and vulnerability of the assets within Belgrade city area in respect to chemical sites and transportation roads that can be exposed to chemical accidents, or terrorist attacks.

Radiological environmental monitoring around the mining sites in Argentina

International Nuclear Information System (INIS)

Quintana, Eduardo E.; Gomez, Juan C.; Palacios, Miguel A.

2004-01-01

The uranium mining industry began its development in Argentina in the fifties. Since then, several installations have operated as uranium underground mining until late seventies, when that mines were closed. Since then, open pit exploitation has been used. Milling facilities were installed in the mining areas or close to them. The environmental radiological surveillance and the impact assessment presented in this work are referred to the uranium ore mining and milling plants Tonco, in Salta province; Pichinan, in Chubut province; San Rafael and Malargue, in Mendoza province; Los Gigantes, in Cordoba province; La Estela, in San Luis province and Los Colorados in La Rioja province. The environmental radiological surveillance programme results carried out from the beginning of the operations are presented and include uranium and radium concentrations in surface waters and sediments. The results obtained in waters upstream and downstream the uranium mining complexes are compared and no significant differences were observed. Moreover, taking into consideration the critical exposition pathways of the population living in the area, no significant levels of exposition were observed. (author)

A review of radiology staff doses and dose monitoring requirements

International Nuclear Information System (INIS)

Martin, C. J.

2009-01-01

Studies of radiation doses received during X-ray procedures by radiology, cardiology and other clinical staff have been reviewed. Data for effective dose (E), and doses to the eyes, thyroid, hands and legs have been analysed. These data have been supplemented with local measurements to determine the most exposed part of the hand for monitoring purposes. There are ranges of 60-100 in doses to individual tissues reported in the literature for similar procedures at different centres. While ranges in the doses per unit dose-area product (DAP) are between 10 and 25, large variations in dose result from differences in the sensitivity of the X-ray equipment, the type of procedure and the operator technique, but protection factors are important in maintaining dose levels as low as possible. The influence of shielding devices is significant for determining the dose to the eyes and thyroid, and the position of the operator, which depends on the procedure, is the most significant factor determining doses to the hands. A second body dosemeter worn at the level of the collar is recommended for operators with high workloads for use in assessment of effective dose and the dose to the eye. It is proposed that the third quartile values from the distributions of dose per unit DAP identified in the review might be employed in predicting the orders of magnitude of doses to the eye, thyroid and hands, based on interventional operator workloads. Such dose estimates could be employed in risk assessments when reviewing protection and monitoring requirements. A dosemeter worn on the little finger of the hand nearest to the X-ray tube is recommended for monitoring the hand. (authors)

Aspects of radiation protection to attend the victims of radiological accident with cesium 137 in Goiania

International Nuclear Information System (INIS)

Hunt, J.G.; Oliveira Filho, D.S. de; Rabello, P.N.P.

1988-01-01

The radiological protection measures taken in the general hospital of Goiania (HGG/INAMPS) and in the FEBEM institution, due do the accident involving cesium 137 are described, as well the work of the NUCLEI personnel in the areas of: radiological protection of the medical and auxiliary staff, contamination control of the ward, radiological monitoring of the patients, waste management, personnel and area decontamination and patient transportation. (author) [pt

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

International Nuclear Information System (INIS)

Meyer, H.; Mueller-Lyda, I.

1993-01-01

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

Assessment of the radiological control at the IPEN radioisotope production facility

Energy Technology Data Exchange (ETDEWEB)

Carneiro, J.C.G.G.; Sanches, M.P.; Rodrigues, D.L.; Campos, D.; Nogueira, P.R.; Damatto, S.R.; Pecequilo, B.R.S. [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

2015-07-01

The main objective of this work is to evaluate the 2013 annual radiological control results in the radiopharmaceuticals areas of the Nuclear and Energy Research Institute, IPEN/SP, Brazil and the environmental radiological impact, resulting from the practices there performed. The current evaluation was performed through the analysis of the results obtained from occupational and environmental monitoring with air samplers and TL dosimeters. All monitoring results were compared with the limits established by national standards. The radionuclides detected by air sampling (in activated carbon cartridges and filter paper) at the workplace during radioisotope production were {sup 131}I, {sup 99m}Tc and {sup 99}Mo, with activities concentrations values below the annual limits values. For the radioactive gaseous releases (Bq/m{sup 3} ), the activities concentrations also remained below the maximum admissible values, excepting to {sup 125}I release due to an unusual event occurred in a researcher laboratory, but the radiological impact to environmental was no significant. The occupational monitoring assessment was confirmed by the Environmental Radiological Monitoring Program results with air samplers and TL dosimeters. The mean annual background radiation at IPEN in 2013, according to the Environmental Radiological Monitoring Program results was 1.06 mSv. y{sup -1} , below the ICRP 103 recommended limit of 20 mSv.y{sup -1} for workers. (author)

Federal Radiological Monitoring and Assessment Center advanced part phase response actions

International Nuclear Information System (INIS)

Hurley, B.

1997-01-01

Federal Radiological Monitoring and Assessment Center (FRMAC) response actions are carried out in Advance Party and Main Party phases of deployment. Response activities are initiated by a FRMAC Home Team prior to and during Advance Party deployment, with Home Team support continuing until the FRMAC Main Party is fully deployed. Upon arrival at the incident scene, the Advance Party establishes communications with other federal, state, and local response organizations, Following an Advance Party Meeting with these response organizations, FRMAC begins formulation of an initial monitoring and sampling plan, in coordination with the jurisdictional state and the Lead Federal Agency, and initiates detailed logistical arrangements for Main Party deployment and operations

Program of radiological monitoring environmental a nuclear facility in latency

International Nuclear Information System (INIS)

Blas, A. de; Riego, A.; Batalla, E.; Tapia, C.; Garcia, R.; Sanchez, J.; Toral, J.

2013-01-01

This paper presents the Radiological Environmental Monitoring program of the Vandellos I nuclear power plant in the latency period. This facility was dismantled to level 2, as defined by the International Atomic Energy Agency. The program is an adaptation of the implanted one during the dismantling, taking into account the isotopes that may be present, as well as the main transfer routes. Along with the description of the program the results obtained in the latent period from 2005 until 2012 are presented.

Android Based Area Web Monitoring

Science.gov (United States)

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

2014-03-01

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

Android Based Area Web Monitoring

Directory of Open Access Journals (Sweden)

Kanigoro Bayu

2014-03-01

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

Automated System of Area Radiation Measurement (ASARM)

International Nuclear Information System (INIS)

Hernandez G, J.

2013-10-01

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

Quarterly environmental radiological survey summary: Second Quarter 1995 100, 200, 300, and 600 Areas

International Nuclear Information System (INIS)

McKinney, S.M.

1995-01-01

This report provides a summary of the radiological surveys performed in support of the operational environmental monitoring program at the Hanford Site. The Second Quarter 1995 survey results and the status of actions required from current and past reports are summarized

Quarterly environmental radiological survey summary. Fourth quarter, 1995 100, 200, 300, and 600 Areas

International Nuclear Information System (INIS)

McKinney, S.M.; Markes, B.M.

1996-01-01

This report provides a summary of the radiological surveys performed in support of the operational environmental monitoring program at the Hanford Site. The Fourth Quarter 1995 survey results and the status of actions required from current and past reports are described

Survey monitoring of environmental radioactivity in Jeju area

Energy Technology Data Exchange (ETDEWEB)

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

2003-12-15

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

Survey monitoring of environmental radioactivity in Jeju area

Energy Technology Data Exchange (ETDEWEB)

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

1998-01-15

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

Survey monitoring of environmental radioactivity in Jeju area

Energy Technology Data Exchange (ETDEWEB)

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

2002-12-15

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

An aerial radiological survey of the southwest drainage basin area of the Savannah River Site

International Nuclear Information System (INIS)

Feimster, E.L.

1994-04-01

An aerial radiological survey was conducted over a 106-square-mile area of the Savannah River Site (SRS), formerly the Savannah River Plant. The survey was conducted from August 24 through September 8, 1988, to collect baseline radiological data over the area. Both natural and man-made gamma emitting radionuclides were detected in the area. The detected man-made sources were confined to creeks, branches, and SRS facilities in the surveyed area and were a result of SRS operations. Naturally-occurring radiation levels were consistent with those levels detected in adjacent areas during previous surveys. The annual dose levels were within the range of levels found throughout the United States

Nevada Test Site Area 25, Radiological Survey and Cleanup Project, 1974-1983 (a revised final report). Revision 1

International Nuclear Information System (INIS)

Miller, M.G.

1984-12-01

This report describes the radiological survey, decontamination and decommissioning (D and D) of the Nevada Test Site (NTS) Area 25 facilities and land areas incorporated in the Nuclear Rocket Development Station (NRDS). Buildings, facilities and support systems used after 1959 for nuclear reactor and engine testing were surveyed for the presence of radioactive contamination. The radiological survey portion of the project encompassed portable instrument surveys and removable contamination surveys (swipe) for beta plus gamma and alpha radioactive contamination of facilities, equipment and land areas. Soil sampling was also accomplished. The majority of Area 25 facilities and land areas have been returned to unrestricted use. Remaining radiologically contaminated areas are posted with warning signs and barricades. 9 references, 23 figures

Calibration of instrument and personnel monitoring in radiological protection

International Nuclear Information System (INIS)

Abdul Aziz Mohamad Ramli; Wan Saffiey Wan Abdullah

1987-01-01

It is difficult to choose radioprotection equipments that are not too expensive and suit the purpose. Some of the dosimetric characteristics of good dosemeters outlined by ISO 4071-1978 (E) namely scale linearity, energy dependence, radiation quality dependence and angular dependence for some of the commercially available dosemeters are discussed. The calibration procedures practised at the National Secondary Standard Dosimetry Laboratory (SSDL), of the Nuclear Energy Unit (NEU) is also explained. The radiological equipments for personnel monitoring such as film badge and TLD are widely used to estimate the radiation dose delivered to the whole or partial body of a personnel. Both of the personnel monitoring procedures have been established at the NEU. The objective, use and maintenance of the devices are also discussed in detail. The evaluation of the monthly dose received by a personnel from various establishments in the country are also presented. (author). 17 figs

New software tool for dynamic radiological characterisation and monitoring in nuclear sites

International Nuclear Information System (INIS)

Szoeke, Istvan; Louka, Michael N.; Mark, Niels K.; Bryntesen, Tom R.; Bratteli, Joachim; Edvardsen, Svein T.; Gustavsen, Morten A.; Toppe, Aleksander L.; Johnsen, Terje; Rindahl, Grete

2012-01-01

The Halden Reactor Project (HRP) is a jointly sponsored international cooperation, under the aegis of the Organisation for Economic Co-operation and Development - Nuclear Energy Agency. Extensive and valuable guidance and tools, connected to safe and reliable operation of nuclear facilities, has been elaborated throughout the years within the frame of this programme. The HRP has particularly high level results in virtual-reality based tools for real-time areal and personal monitoring. The techniques, developed earlier, are now being supplemented to enhance the planning and monitoring capabilities, and support general radiological characterisation connected to nuclear sites and facilities. Due to the complexity and abundance of the input information required, software tools, dedicated to the radiological characterization of contaminated materials, buildings, land and groundwater, are applied to review, evaluate and visualize the data. Characterisation of the radiation situation in a realistic environment can be very complex, and efficient visualisation of the data to the user is not straight forward. The monitoring and planning tools elaborated in the frame of the HRP feature very sophisticated three-dimensional (3D) high definition visualisation and user interfaces to promote easy interpretation of the input data. The visualisation tools permit dynamic visualisation of radiation fields in virtual or augmented reality by various techniques and real-time personal monitoring of humanoid models. In addition new techniques are being elaborated to visualise the 3D distribution of activities in structures and materials. The dosimetric algorithms, feeding information to the visualisation and user interface of these planning tools, include deterministic radiation transport techniques suitable for fast photon dose estimates, in case physical and radio- and spectrometric characteristics of the gamma sources are known. The basic deterministic model, implemented in earlier

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

Science.gov (United States)

Cournane, S; Sheehy, N; Cooke, J

2014-06-01

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

200-UP-2 operable unit radiological surveys

International Nuclear Information System (INIS)

Wendling, M.A.

1994-01-01

This report summarizes and documents the results of the radiological surveys conducted from August 17 through December 16, 1993 over a partial area of the 200-UP-2 Operable Unit, 200-W Area, Hanford Site, Richland, Washington. In addition, this report explains the survey methodology of the Mobile Surface Contamination Monitor 11 (MSCM-II) and the Ultra Sonic Ranging And Data System (USRADS). The radiological survey of the 200-UP-2 Operable Unit was conducted by the Site Investigative Surveys/Environmental Restoration Health Physics Organization of the Westinghouse Hanford Company. The survey methodology for the majority of area was based on utilization of the MSCM-II or the USRADS for automated recording of the gross beta/gamma radiation levels at or near six (6) inches from the surface soil

Radiological protection principles concerning the safeguard, use or release of contaminated materials, buildings, areas or dumps from uranium mining. Recommendations of the Commission on Radiological Protection with explanations

International Nuclear Information System (INIS)

Mueller-Neumann, M.

1992-01-01

The volume presents the full texts of the SSK Recommendations addressing the aspects and problems involved, and which can be separately retrieved from the database: 1) Radiological protection principles concerning the release of scrap from the shut-down of uranium mining plants; 2) Radiological protection principles concerning the release for industrial use of areas contaminated from uranium mining; 3) Radiological protection principles concerning the use for forest and agricultural purposes and as public gardens (parks) and residential areas of areas contaminated from uranium mining; 4) Radiological protection principles concerning the safeguard and use of mine dumps; 5) Radiological protection principles concerning the release for further commercial or industrial use of buildings used for commercial or industrial purposes and the disposal of building debris from uranium mining and milling; 6) Radiological protection principles concerning the release for general use of reusable equipment and installations from uranium mining. The following appendices round up the material: 1) Radiation exposure from mining in Saxony and Thuringia and its evaluation (Summary of the results of consultations during the 1990 closed meeting); 2) Radiological protection principles for the limitation of the radiation exposure of the public to radon and its daughters; 3) Epidemiological studies on the health state of the inhabitants of the mining region and the miners in Saxony and Thuringia. (orig.) [de

Quarterly environmental radiological survey summary - second quarter 1997 100, 200, 300, and 600 areas

International Nuclear Information System (INIS)

McKinney, S.M.; Marks, B.M.

1997-01-01

This report provides a summary of the radiological surveys performed in support of near-facility environmental monitoring at the Hanford Site. The Second Quarter 1997 survey results and the status of actions required are summarized below: All of the routine environmental radiological surveys scheduled during April, May, and June 1997, were performed as planned with the exception of UN-216-E-9. This site was not surveyed as stabilization activities were in progress. The sites scheduled for the Environmental Restorations Contractor (ERC) team were switched with those identified for the third quarter as there was a conflict with vegetation management activities

Development of a Data acquisition node for the environmental radiological monitoring network

International Nuclear Information System (INIS)

Benitez S, R.

2000-01-01

This work consists in the development of a data acquisition system related to the radiation levels of each one of the laboratories or installations of the ININ, setting up an interconnection of the existing radiological monitoring system (RMS-II), with a personal computer through the use and programming of a data acquisition card (PC-LPM-16). This system works in real time, presenting on the PC screen the measurement of each one of the connected detectors, the alarm signals that are being had been when the allowed levels have been exceeded and the registry of these alarm levels; for their later processing in rapidity graphs of exposure against time. Also aspects such as : brief history of the ionizing radiations and their nature, their interaction with matter and the method which were discovered are treated as well as how it is possible to detect and to measure them. The radiological protection and the standards on which that is based. The RMSII radiation monitoring system and its calibration as well as the obtention of performance curves are treated too. Finally, it is described the performance of the Data acquisition circuit, the based programming in virtual instrumentation and its importance. (Author)

An Aerial Radiological Survey of the Nevada Test Site - Area 10 Corrective Action Unit 367

International Nuclear Information System (INIS)

Lyons, Craig

2010-01-01

A series of aerial radiological surveys were conducted over the Sedan, Uncle, and Ess ground zero areas in Area 10. The surveys were performed in November 2009 utilizing a large array of helicopter mounted sodium iodide detectors. The purpose of the survey was to update the previous radiological survey levels of the environment and surrounding areas of the ground zeros. Gross Counts, inferred exposure rates, man-made activity, and Americium-241 activity, as calculated from the aerial data are presented in the form of isopleth maps superimposed on imagery of the surveyed areas. In addition, spectral products are included that identify Cesium-137, Americium-241 and Cobalt-60 as the primary radionuclides present within the survey area.

Environmental monitoring program for radiological emergencies at the Almirante Alvaro Alberto Nuclear Power Plant, Angra dos Reis, Rio de Janeiro, Brazil

Energy Technology Data Exchange (ETDEWEB)

Ferreira, Lilia M.J. Belem; Ramos Junior, Anthenor C.; Gomes, Carlos A.; Carvalho, Zenildo L.; Gouveia, Vandir; Estrada, Julio; Ney, Cezar [Instituto de Radioprotecao e Dosimetria (IRD), Rio de Janeiro, RJ (Brazil)

1997-12-31

In order to respond to a major radiological emergency at the Almirante Alvaro Alberto Nuclear Power Plant, located in Angra do Reis, Rio de Janeiro, the Emergency Response Team of the Institute of Radiation Protection and Dosimetry (IRD/CNEN) established a program of environmental monitoring. A monitoring trend to assess the off-site radiological conditions and give support to decision making for implementing protective measure in case of a radiological accident is presented. For the selection of the monitoring points, the program takes into account atmospheric diffusion, population conglomerates and their habits, water and land use; it includes the entire Emergency Planning Zone of 15 km radius. The program has been organized in the form of a handbook to facilitate handling by field teams 2 refs., 1 fig.; e-mail: lilia at ird.gov.br

Dose monitoring in radiology departments. Status quo and future perspectives; Dosismonitoring in der Radiologie. Status quo und Zukunftsperspektiven

Energy Technology Data Exchange (ETDEWEB)

Boos, J. [Harvard Medical School, Boston, MA (United States). Dept. of Radiology; Duesseldorf Univ. (Germany). Inst. fuer Diagnostische und Interventionelle Radiologie; Meineke, A. [Cerner Healthcare Services, Idstein (Germany); Bethge, O.T.; Antoch, G.; Kroepil, P. [Duesseldorf Univ. (Germany). Inst. fuer Diagnostische und Interventionelle Radiologie

2016-05-15

The number of computed tomography examinations has continuously increased over the last decades and accounts for a major part of the collective radiation dose from medical investigations. For purposes of quality assurance in modern radiology a systematic monitoring and analysis of dose related data from radiological examinations is mandatory. Various ways of collecting dose data are available today, for example the Digital Imaging and Communication in Medicine - Structured Report (DICOM-SR), optical character recognition and DICOM-modality performed procedure steps (MPPS). The DICOM-SR is part of the DICOM-standard and provides the DICOM-Radiation Dose Structured Report, which is an easily applicable and comprehensive solution to collect radiation dose parameters. This standard simplifies the process of data collection and enables comprehensive dose monitoring. Various commercial dose monitoring software devices with varying characteristics are available today. In this article, we discuss legal obligations, various ways to monitor dose data, current dose monitoring software solutions and future perspectives in regard to the EU Council Directive 2013/59/EURATOM.

Status of radiation protection in interventional radiology. Assessment of inspections in 2009 by the ASN

International Nuclear Information System (INIS)

2011-01-01

This report first describes the organization of inspections performed in health institutions, indicates the inspected establishments, the types of fixed installations in interventional radiology, the use of imagery in the operating theatre, and discusses the regulatory arrangements applicable to interventional radiology (in the Public Health Code, in the Labour Code). Then, the report discusses the results of inspections regarding radiation protection in interventional radiology: application of public health code arrangements (justification, patient training in radiation protection, radiological procedures and protocols, patient dosimetry monitoring), application of Labour Code arrangements (designation of the person with expertise in radiation protection, risk assessment and delimitation of monitored and controlled areas, workstation analysis, workers' training in radiation protection, individual protection equipment, workers' dosimetric monitoring, workers' medical monitoring, radiation protection technical controls), significant events, radiation protection in operating theatre. Propositions are stated regarding the differences noticed within or between the health establishments, the methodological and organisational difficulties faced by persons with expertise in radiation protection (PCR), the need of an interdisciplinary team

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

International Nuclear Information System (INIS)

1986-09-01

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

Bacteriological Monitoring of Radiology Room Apparatus in the Department of Radiological Technology and Contamination on Hands of Radiological Technologists

International Nuclear Information System (INIS)

Kim, Seon Chil

2008-01-01

Distribution of microorganisms were examined for the bucky tables in the radiology rooms of the department of radiological technology, the aprons, handles of various apparatus, handles of mobile radiological apparatus, and hands of the radiological technologists. As a result, relatively larger amounts of bacteria were found on the handles of the mobile radiological apparatus and the aprons. Among the isolated bacteria, Acinetobacter baumanni (7.3%), Klebsiella pneumoniae (6.7%), Staphylococcus aureus (3.9%), Serratia liquefaciens (1.7%), Enterobacter cloaceae (0.6%), Providenica rettgeri (0.6%) are known as the cause of nosocomial infection (hospital acquired infection). In addition, similar colonies were also found on the hands of the radiological technologists such as microorganisms of Klebsiella pneumoniae (8.4%), Staphylococcus aureus (6.6%), Yersinia enterocolotica (5.4%), Acinetobacter baumanni (4.2%), Enterobacter cloaceae (2.4%), Serratia liquefaciens (1.8%), Yersinia pseuotuberculosis (18%), Enterobacter sakazakii (1.2%), and Escherichia coli (0.6%). In particular, this result indicates clinical significance since Staphylococcus aureus and Escherichia coli show strong pathogenicity. Therefore, a continuous education is essential for the radiological technologists to prevent the nosocomial infection.

Bacteriological Monitoring of Radiology Room Apparatus in the Department of Radiological Technology and Contamination on Hands of Radiological Technologists

Energy Technology Data Exchange (ETDEWEB)

Kim, Seon Chil [Dept. of Radiologic Technology, Daegu Health College, Daegu (Korea, Republic of)

2008-12-15

Distribution of microorganisms were examined for the bucky tables in the radiology rooms of the department of radiological technology, the aprons, handles of various apparatus, handles of mobile radiological apparatus, and hands of the radiological technologists. As a result, relatively larger amounts of bacteria were found on the handles of the mobile radiological apparatus and the aprons. Among the isolated bacteria, Acinetobacter baumanni (7.3%), Klebsiella pneumoniae (6.7%), Staphylococcus aureus (3.9%), Serratia liquefaciens (1.7%), Enterobacter cloaceae (0.6%), Providenica rettgeri (0.6%) are known as the cause of nosocomial infection (hospital acquired infection). In addition, similar colonies were also found on the hands of the radiological technologists such as microorganisms of Klebsiella pneumoniae (8.4%), Staphylococcus aureus (6.6%), Yersinia enterocolotica (5.4%), Acinetobacter baumanni (4.2%), Enterobacter cloaceae (2.4%), Serratia liquefaciens (1.8%), Yersinia pseuotuberculosis (18%), Enterobacter sakazakii (1.2%), and Escherichia coli (0.6%). In particular, this result indicates clinical significance since Staphylococcus aureus and Escherichia coli show strong pathogenicity. Therefore, a continuous education is essential for the radiological technologists to prevent the nosocomial infection.

Area monitoring intelligent system - SIMA

International Nuclear Information System (INIS)

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

1990-01-01

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

Radiological Conditions in Selected Areas of Southern Iraq with Residues of Depleted Uranium. Report by an International Group of Experts

International Nuclear Information System (INIS)

2010-01-01

This publication describes the methods, assumptions and parameters used by the IAEA during the assessment of the post-conflict radiological conditions of the environment and populations in relation to the residues of depleted uranium munitions from 2003 that exist at four selected areas in southern Iraq. The studies conducted by the IAEA used the results of measurements provided by UNEP from the 2006-2007 environmental monitoring campaigns performed by the Iraqi Ministry for the Environment. It presents the data used, the results of the assessment, and the findings and conclusions in connection therewith.

A comparison of four aerial radiological surveys of Par Pond and the surrounding area, Savannah River Site, Aiken, South Carolina

International Nuclear Information System (INIS)

Feimster, E.L.

1993-09-01

A series of gamma radiation surveys was conducted over Par Pond at the Savannah River Site (SRS) in August 1993, October 1991, and August 1992 as part of an effort to monitor the radiological changes around Par Pond as its water level was lowered. The results of an April 1989 survey, which was about one-half the area of those surveys listed above, were used as baseline data for the comparison. Gamma energy spectrum analysis revealed that the only man-made gamma ray emitter detected during the four surveys in the Par Pond area was cesium-137. The comparisons revealed that: (1) significant change in the radiological environment occurred along the Par Pond shoreline as the water levels were lowered, (2) the activity in Lower Three Runs Creek varied slightly as the level/flow rate changed during the pumping process, (3) minor changes occurred in areas adjacent to the Par Pond, and (4) little or no change occurred between surveys in the spatial distribution or kind of sources detected. All changes were directly related to the moisture variations (Par Pond water lowering, rainfall, waterway flow rates) between the survey periods. The distribution, kind, and activity of sources detected beyond the pond bed were consistent between surveys. 60 figs., 14 tabs

Vehicle tracking based technique for radiation monitoring during nuclear or radiological emergency

International Nuclear Information System (INIS)

Saindane, Shashank S.; Otari, Anil D.; Suri, M.M.K.; Patil, S.S.; Pradeepkumar, K.S.; Sharma, D.N.

2010-01-01

Radiation Safety Systems Division, BARC has developed an advanced online radiation measurement cum vehicle tracking system for use. For the preparedness for response to any nuclear/radiological emergency scenario which may occur anywhere, the system designed is a Global System for Mobile (GSM) based Radiation Monitoring System (GRaMS) along with a Global Positioning System (GPS). It uses an energy compensated GM detector for radiation monitoring and is attached with commercially available Global Positioning System (GPS) for online acquisition of positional coordinates with time, and GSM modem for online data transfer to a remote control centre. The equipment can be operated continuously while the vehicle is moving

Overview of environmental radiological monitoring program of Institute of Radiation Protection And Dosimetry - IRD

Energy Technology Data Exchange (ETDEWEB)

Gomes, Sarah Barreto Oliveira de Christo; Peres, Sueli da Silva, E-mail: suelip@ird.gov.br, E-mail: sarah.barreto1@gmail.com [Instituto de Radioproteção e Dosimetria (IRD/CNEN-RJ), Rio de Janeiro, RJ (Brazil). Div. de Radioproteção

2017-07-01

As a branch of the Brazilian Nuclear Energy Commission (CNEN), the Institute of Radiation Protection and Dosimetry (IRD) performs extensive activities in the fields of radiation protection, metrology, and dosimetry, as well as specific education, onto a wide operational scope that includes the technical support to national regulatory authorities in the licensing process for nationwide nuclear and radioactive facilities. IRD has several laboratories where are performed radiometric and radiochemical analyses and others radioactivity evaluation procedures in different types of samples obtained in the inspection activities, production of radioactivity metrological standards and reference material by National Laboratory of Metrology of Ionizing Radiation (LMNRI), besides others research activities. In this laboratories can be used sealed or unsealed radioactive sources and radiation-producing devices and are classified with radioactive installations in accordance to national regulations. This way, radioactive liquid effluents can be eventually produced and released into the environment in the course of such activities and an effluent monitoring program to control and reduce the releases to environment is carried out. Additionally, IRD maintains the Radioactive Waste Management Program and Environmental Radiological Monitoring Program (ERMP) in accordance to national regulations requirements. The primary focus of ERMP comprises the validation of the dose prognostics for the public members due to effluents discharge and the provision of consistent projections of the radiation levels at the monitoring sites. In this study, a long term ERMP data survey is discussed, spanning the last thirteen years of activities. On the basis of such discussions and prognostics, it could be observed that the radiological environmental radiological impact due to operation of IRD installations is negligible. (author)

Overview of environmental radiological monitoring program of Institute of Radiation Protection And Dosimetry - IRD

International Nuclear Information System (INIS)

Gomes, Sarah Barreto Oliveira de Christo; Peres, Sueli da Silva

2017-01-01

As a branch of the Brazilian Nuclear Energy Commission (CNEN), the Institute of Radiation Protection and Dosimetry (IRD) performs extensive activities in the fields of radiation protection, metrology, and dosimetry, as well as specific education, onto a wide operational scope that includes the technical support to national regulatory authorities in the licensing process for nationwide nuclear and radioactive facilities. IRD has several laboratories where are performed radiometric and radiochemical analyses and others radioactivity evaluation procedures in different types of samples obtained in the inspection activities, production of radioactivity metrological standards and reference material by National Laboratory of Metrology of Ionizing Radiation (LMNRI), besides others research activities. In this laboratories can be used sealed or unsealed radioactive sources and radiation-producing devices and are classified with radioactive installations in accordance to national regulations. This way, radioactive liquid effluents can be eventually produced and released into the environment in the course of such activities and an effluent monitoring program to control and reduce the releases to environment is carried out. Additionally, IRD maintains the Radioactive Waste Management Program and Environmental Radiological Monitoring Program (ERMP) in accordance to national regulations requirements. The primary focus of ERMP comprises the validation of the dose prognostics for the public members due to effluents discharge and the provision of consistent projections of the radiation levels at the monitoring sites. In this study, a long term ERMP data survey is discussed, spanning the last thirteen years of activities. On the basis of such discussions and prognostics, it could be observed that the radiological environmental radiological impact due to operation of IRD installations is negligible. (author)

MARSAME Radiological Release Report for Archaeological Artifacts Excavated from Area L

Energy Technology Data Exchange (ETDEWEB)

Ruedig, Elizabeth [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Whicker, Jeffrey Jay [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Gillis, Jessica Mcdonnel [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2016-06-03

In 1991 Los Alamos National Laboratory’s (LANL’s) cultural resources team excavated archaeological site LA 4618 located at Technical Area 54, within Material Disposal Area L (MDA L). MDA L received non-radioactive chemical waste from the early 1960s until 1985. Further development of the MDA required excavation of several cultural sites under National Historic Preservation Act requirements; artifacts from these sites have been subsequently stored at LANL. The LANL cultural resources group would now like to release these artifacts to the Museum of Indian Arts and Culture in Santa Fe for curation. The history of disposal at Area L suggests that the artifact pool is unlikely to be chemically contaminated and LANL staff washed each artifact at least once following excavation. Thus, it is unlikely that the artifacts present a chemical hazard. LANL’s Environmental Stewardship group (EPC-ES) has evaluated the radiological survey results for the Area L artifact pool and found that the items described in this report meet the criteria for unrestricted radiological release under Department of Energy (DOE) Order 458.1 Radiation Protection of the Public and the Environment and are candidates for release without restriction from LANL control. This conclusion is based on the known history of MDA L and on radiation survey data.

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.

GSM based real time remote radiation monitoring and mapping system

International Nuclear Information System (INIS)

Dodiya, Kamal; Gupta, Ashutosh; Padmanabhan, N.; Chaudhury, Probal; Pradeepkumar, K.S.

2014-01-01

Mobile Radiological Impact Assessment Laboratory (M-RIAL) has been developed in Radiation Safety Systems Division, Bhabha Atomic Research Centre for carrying out assessment of radioactive contamination following a nuclear or radiological emergency in a nuclear facility or in public domain. During such situations a large area is to be monitored for radiological impact assessment and availability of the monitored data in real-time to a control centre is a great advantage for the decision makers. Development and application of such a system has been described in this paper. The system can transmit real-time radiological data, acquired by the universal counting system of M-RIAL and tagged with positional information, wirelessly to an Emergency Response Centre (ERC) using Global System for Mobile (GSM) communication. The radiological profile of the affected area is then superimposed on Geographical Information System (GIS) at the ERC and which can be used for the generation of radiological impact maps for use as decision support

Development of environmental monitoring robot against nuclear hazard and establishment of its wide-area transportation method using a cargo plane

International Nuclear Information System (INIS)

Magara, Shigenori; Kimura, Norio; Onishi, Ryoichi; Yamasaki, Hitoshi; Kimura, Toshimasa; Sugisaki, Norihiko; Maeyama, Hiroshi

2008-01-01

In case of nuclear hazard, collecting images and radiological information around the epicenter are strongly anticipated for making evacuation plans and securing residents' safety. In order to meet with this requirement, Nuclear Safety Technology Center has developed the two types of environmental monitoring robots; MONIROBO-A and -B, which work for gathering the images and monitoring the radiation doses in hazardous area through the remote-control by the operator in distant secured area. MONIROBO-A collects the images of hazard center using laser scanner and infrared camera, while MONIROBO-B monitors the atmospheric condition using neutron measurement device, flammable gas detector and dust sampler. Also the both types have gamma ray measurement instruments and manipulators. They are sized almost 1.5 m in length and height, and weighed 600kg in mass. (author)

Data Quality Objectives Supporting Radiological Air Emissions Monitoring for the PNNL Site

Energy Technology Data Exchange (ETDEWEB)

Barnett, J. Matthew; Meier, Kirsten M.; Snyder, Sandra F.; Fritz, Brad G.; Poston, Theodore M.; Antonio, Ernest J.

2012-11-12

Pacific Northwest National Laboratory (PNNL) is in the process of developing a radiological air monitoring program for the PNNL Site that is distinct from that of the nearby Hanford Site. The original DQO (PNNL-19427) considered radiological emissions at the PNNL Site from Physical Sciences Facility (PSF) major emissions units. This first revision considers PNNL Site changes subsequent to the implementation of the original DQO. A team was established to determine how the PNNL Site changes would continue to meet federal regulations and address guidelines developed to monitor air emissions and estimate offsite impacts of radioactive material operations. The result is an updated program to monitor the impact to the public from the PNNL Site. The team used the emission unit operation parameters and local meteorological data as well as information from the PSF Potential-to-Emit documentation and Notices of Construction submitted to the Washington State Department of Health (WDOH). The locations where environmental monitoring stations would most successfully characterize the maximum offsite impacts of PNNL Site emissions from the three PSF buildings with major emission units were determined from these data. Three monitoring station locations were determined during the original revision of this document. This first revision considers expanded Department of Energy operations south of the PNNL Site and relocation of the two offsite, northern monitoring stations to sites near the PNNL Site fenceline. Inclusion of the southern facilities resulted in the proposal for a fourth monitoring station in the southern region. The southern expansion added two minor emission unit facilities and one diffuse emission unit facility. Relocation of the two northern stations was possible due to the use of solar power, rather than the previous limitation of the need for access to AC power, at these more remote locations. Addendum A contains all the changes brought about by the revision 1

Specific radiological monitoring experiences and the challenges at offshore

International Nuclear Information System (INIS)

Mod Omar Hassan

2005-01-01

Lately, EASELAB / PROJEK KHAS has performed Specific Radiological Monitoring job at offshore rigs off Terengganu for Syarikat Petronas Carigali [M] Sdn Bhd. In order to perform the job, every worker must attend a Basic Offshore Safety and Emergency Training Course and pass the theory and practical test. Before a license or safety passport is issued, the worker must undergo Medical Checkup and certified physically and mentally fit. The passport is recognized by most of international oil companies. During performing the jobs, MINT staff has faced some difficulties such as weather conditions, to suit with the working environment and life at the oil platform. There were a few staff has withdrew (resigned) from performing the jobs. (Author)

An Aerial Radiological Survey of the Nevada Test Site - Areas 18 and 20 Corrective Action Unit 372

International Nuclear Information System (INIS)

Lyons, Craig

2010-01-01

A series of aerial radiological surveys were conducted over the Little Feller I and II ground zero areas in Area 18 and the Palanquin and Cabriolet ground zero areas in Area 20. The surveys were performed in October and November 2009 utilizing a large array of helicopter mounted sodium iodide detectors. The purpose of the survey was to update the previous radiological survey levels of the environment and surrounding areas of the ground zeros. Gross Counts, inferred exposure rates, man-made activity, and Americium-241 activity, as calculated from the aerial data are presented in the form of isopleth maps superimposed on imagery of the surveyed areas.

Occupational radiological protection in diagnostic radiology

International Nuclear Information System (INIS)

Mota, H.C.

1983-01-01

The following topics are discussed: occupational expossure (the ALARA principle, dose-equivalent limit, ICRP justification); radiological protection planning (general aspects, barrier estimation) and determination of the occupational expossures (individual monitoring). (M.A.) [pt

Radiological monitoring plan for the Oak Ridge Y-12 Plant: Surface water

International Nuclear Information System (INIS)

1995-01-01

National Pollutant Discharge Elimination System (NPDES) Permit TN0002968, issued April 28, 1995, requires that the Y-12 Plant Radiological Monitoring Plan for surface water be modified (Part 111-H). These modifications shall consist of expanding the plan to include storm water monitoring and an assessment of alpha, beta, and gamma emitters. In addition, a meeting was held with personnel from the Tennessee Department of Environment and Conservation (TDEC) on May 4, 1995. In this meeting, TDEC personnel provided guidance to Y-12 Plant personnel in regard to the contents of the modified plan. This report contains a revised plan incorporating the permit requirements and guidance provided by TDEC personnel. In addition, modifications were made to address future requirements of the new regulation for radiation protection of the public and the environment in regards to surface water monitoring

The development of web monitoring digital area monitor

International Nuclear Information System (INIS)

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

2005-01-01

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

The development of web monitoring digital area monitor

Energy Technology Data Exchange (ETDEWEB)

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

2005-11-15

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

Radiological assessment of an area with uranium residual material

International Nuclear Information System (INIS)

Perez-Sanchez, Danyl; Cancio, David; Alvarez, Alicia

2008-01-01

As a result of a pilot project developed at the old Spanish 'Junta de Energia Nuclear' to extract uranium from ores, tailings materials were generated. Most of these residual materials were sent back to different uranium mines, but a small amount of it was mixed with conventional building materials and deposited near the old plant until the surrounding ground was flattened. The affected land is included in an area under institutional control and used as recreational area. At the time of processing, uranium isotopes were separated but other radionuclides of the uranium decays series as 230 Th, 226 Ra and daughters remain in the residue. Recently, the analyses of samples taken at different ground's depths confirm their presence. This paper presents the methodology used to calculate the derived concentration level to ensure the reference dose level of 0.1 mSv y-1 used as radiological criteria. In this study, a radiological impact assessment was performed modelling the area as recreational scenario. The modelization study was carried out with the code RESRAD considering as exposure pathways, external irradiation, inadvertent ingestion of soil, inhalation of resuspended particles, and inhalation of outdoor radon ( 222 Rn). As result was concluded that, if the concentration of 226 Ra in the first 15 cm of soil is lower than, 0.34 Bq g-1 , the dose would not exceed the reference dose. Applying this value as a derived concentration level and comparing with the results of measurements on the ground, some areas with a concentration of activity slightly higher than latter were found. In these zones the remediation proposal has been to cover with a layer of 15 cm of clean material. This action represents a reduction of 85% of the dose and ensures compliance with the reference dose. (author)

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.

Creation and clinical application of real-time dose monitor using dose area product meter

International Nuclear Information System (INIS)

Matsubara, Kosuke; Uoyama, Yoshinori; Iida, Hiroji; Mizushima, Takashi

2004-01-01

The management of patient dose has become more of an issue in recent years. Dose can be determined non-invasively and in real time through the use of a dose area product meter, but it is the area dose value that is obtained. Therefore, we created a program that estimates entrance skin dose (ESD) in real time from area dose values obtained during procedures. We used Microsoft Visual C++ 6.0 (Standard Edition) for the programming language and C language for the programming environment. The value was a maximum 285.4 mGy at ileus tube insertion when measuring ESD for radiography of the digestive organ and non-vascular type interventional radiology (IVR) using the created program and seeking the average according to the procedures. The program that we created can be considered valid for monitoring ESD correctly and in real time. (author)

Tonopah Test Range Air Monitoring: CY2012 Meteorological, Radiological, and Airborne Particulate Observations

Energy Technology Data Exchange (ETDEWEB)

Mizell, Steve A; Nikolich, George; Shadel, Craig; McCurdy, Greg; Miller, Julianne J

2013-07-01

In 1963, the Atomic Energy Commission (AEC), predecessor to the US Department of Energy (DOE), implemented Operation Roller Coaster on the Tonopah Test Range (TTR) and an adjacent area of the Nevada Test and Training Range (NTTR) (formerly the Nellis Air Force Range (NAFR)). Operation Roller Coaster consisted of four tests in which chemical explosions were detonated in the presence of nuclear devices to assess the dispersal of radionuclides and evaluate the effectiveness of storage structures to contain the ejected radionuclides. These tests resulted in dispersal of plutonium over the ground surface downwind of the test ground zero. Three tests, Clean Slate 1, 2, and 3, were conducted on the TTR in Cactus Flat; the fourth, Double Tracks, was conducted in Stonewall Flat on the NTTR. DOE is working to clean up and close all four sites. Substantial cleaned up has been accomplished at Double Tracks and Clean Slate 1. Cleanup of Clean Slate 2 and 3 is on the DOE planning horizon for some time in the next several years. The Desert Research Institute installed two monitoring stations, number 400 at the Sandia National Laboratories Range Operations Center and number 401 at Clean Slate 3, in 2008 and a third monitoring station, number 402 at Clean Slate 1, in 2011 to measure radiological, meteorological, and dust conditions. The primary objectives of the data collection and analysis effort are to (1) monitor the concentration of radiological parameters in dust particles suspended in air, (2) determine whether winds are re-distributing radionuclides or contaminated soil material, (3) evaluate the controlling meteorological conditions if wind transport is occurring, and (4) measure ancillary radiological, meteorological, and environmental parameters that might provide insight to the above assessments. The following observations are based on data collected during CY2012. The mean annual concentration of gross alpha and gross beta is highest at Station 400 and lowest at Station

Implementation of the National Incident Management System (NIMS)/Incident Command System (ICS) in the Federal Radiological Monitoring and Assessment Center(FRMAC) - Emergency Phase

International Nuclear Information System (INIS)

NSTec Environmental Restoration

2007-01-01

Homeland Security Presidential Directive HSPD-5 requires all federal departments and agencies to adopt a National Incident Management System (NIMS)/Incident Command System (ICS) and use it in their individual domestic incident management and emergency prevention, preparedness, response, recovery, and mitigation programs and activities, as well as in support of those actions taken to assist state and local entities. This system provides a consistent nationwide template to enable federal, state, local, and tribal governments, private-sector, and nongovernmental organizations to work together effectively and efficiently to prepare for, prevent, respond to, and recover from domestic incidents, regardless of cause, size, or complexity, including acts of catastrophic terrorism. This document identifies the operational concepts of the Federal Radiological Monitoring and Assessment Center's (FRMAC) implementation of the NIMS/ICS response structure under the National Response Plan (NRP). The construct identified here defines the basic response template to be tailored to the incident-specific response requirements. FRMAC's mission to facilitate interagency environmental data management, monitoring, sampling, analysis, and assessment and link this information to the planning and decision staff clearly places the FRMAC in the Planning Section. FRMAC is not a mitigating resource for radiological contamination but is present to conduct radiological impact assessment for public dose avoidance. Field monitoring is a fact-finding mission to support this effort directly. Decisions based on the assessed data will drive public protection and operational requirements. This organizational structure under NIMS is focused by the mission responsibilities and interface requirements following the premise to provide emergency responders with a flexible yet standardized structure for incident response activities. The coordination responsibilities outlined in the NRP are based on the NIMS

Medical preparedness and response in nuclear accidents. The health team's experience in joint work with the radiological protection area

International Nuclear Information System (INIS)

Maurmo, Alexandre Mesquita

2007-01-01

The interaction between the health and the radiological protection areas has proved fundamental, in our work experience, for the quality of response to victims of accidents, involving ionizing radiation. The conceptions and basic needs comprehension of the adequate response, on these two areas, have brought changes to the essential behavior related to the victim's care, the protection response, the environment and waste production. The joint task of health professionals and radiological protection staff, as first responders, demonstrates that it is possible to adjust practices and procedures. The training of professionals of the radiological protection area by health workers, has qualified them on the basic notions of pre-hospital attendance, entitling the immediate response to the victim prior to the health team arrival, as well as the discussion on the basic concepts of radiological protection with the health professionals, along with the understanding of the health area with its specific needs on the quick response to imminent death risk, or even the necessary procedures of decontamination. (author)

Radiological safety system based on real-time tritium-in-air monitoring indoors and in effluents

International Nuclear Information System (INIS)

Bidica, N.; Sofalca, N; Balteanu, O.; Srefan, I.

2006-01-01

Exposure to tritium is an important health hazard in any tritium processing facility so that implementing a real-time tritium monitoring system is necessary for its operation in safety conditions. The tritium processing facility operators need to be informed at any time about the in-air tritium concentration indoors or in the stack effluents, in order to detect immediately any leaks in tritium containments, or any releases inside the buildings or to the environment. This information is very important for adopting if necessary protection measures and correcting actions as quickly as possible. In this paper we describe an improved real-time tritium monitoring system designed for the Heavy Water Detritiation Pilot Plant of National Institute for Cryogenics and Isotopes Separation, Rm. Valcea, Romania. The design of the Radiological Safety System implemented for the ICIT Water Detritiation Pilot Plant is intended to provide the maximum safety level based on the ALARA concept. The main functions of tritium monitoring system are: - monitoring the working areas and gaseous effluents by determination of the tritium-in-air activity concentration; - local and remote data display; - assessing of environment dose equivalent rates and dose equivalents in the working environment (for personnel exposure control and work planning); - assessing the total tritium activity released to the environment through ventilation exhaust stack; - safety functions, i.e., local and remote, locking/unlocking personnel access, process shut-down in emergency conditions and start of the air cleaning systems. With all these features our tritium monitoring system is really a safety system adequate for personnel and environmental protection. (authors)

A new means of communication with the populations: the Extremadura Regional Government Radiological Monitoring alert WEB Page

International Nuclear Information System (INIS)

Baeza, A.; Vasco, J.; Miralles, Y.; Torrado, L.; Gil, J. M.

2003-01-01

In 1990, the Junta (Regional government) of Extremadura encharged the University of Extremadura with the desogm and phased implementation of the Radiological Warning Network of Extremadura, initially limited to the proximity of the Almaraz Nuclear Power Plant. Since then, its structure and objectives have been steadily broadened, but always with priority given to the correct operation of the existing infrastructure. The network currently consists of the following installations. Around the cited nuclear plant, there are seven gamma dosimetry stations, two stations of continuous monitoring of radio iodines and radio particles, two automated meteorology stations, and two stations of continuous monitoring of radiation levels in the water of the River Tagas. Outside this zone, there are three gamma dosimetry stations and two for the continuous monitoring of radiosonde and radio particles. There is also a mobile laboratory equipped with an aerosol trap, a gamma dose rate monitor, and a portable germanium detector, with which it is possible in a minimally reasonable time to reach any location where it is necessary to determine the radiological status. All the information generated by the cited stations and the mobile laboratory are transmitted to the logistic centre located in the Physics Department of the Veterinary Faculty of Caceres, and to the network's strategic centre in the General Directorate for the Environment of the Agriculture and Environment council of the Junta of Extremadura. From the beginning of its operation, particular attention was paid to finding different means of providing the population with basic, truthful, and accessible periodic information on the radiological status of the zones covered by the network. Therefore, as well as sending to the Assembly (Parliament) of Extremadura summaries of the reports that are periodically presented to the Junta, an initial attempt was made to inform the population directly by including in the journal Extremadura

Request for information about radiological risks in the health area. A cross-cultural study

International Nuclear Information System (INIS)

Prades, A.; Martinez-Arias, R.; Arranz, L.; Macias, M.T.

2000-01-01

This paper will present some of the key findings of a comparative Latin-American study on radiological risk perception in the health area. The project used a survey method to examine the social demands for information about radiological risks with regard to diagnostic and therapeutic applications. The following topics will be analysed: 1) The role of information as a means for feeling safe; 2) who should inform the public on radiological risks; and 3) what type of information the public would like to receive. A questionnaire was distributed to outpatient samples from ten countries: Argentine, Brazil, Colombia, Cuba, Ecuador, Mexico, Panama, Peru, Uruguay, and Spain, thanks to the collaboration of the different National Radioprotection Societies of the above mentionned countries, and of other concerned professionals (in case they didn't had any association at the time). Correspondence analysis and other techniques of optimal scaling will be used. The paper will discuss the main cross-cultural differences with regard to social demand for information about radiological risks. Our findings may have relevant implications for radiological risks communication programs. (author)

Request for information about radiological risks in the health area. A cross-cultural study

Energy Technology Data Exchange (ETDEWEB)

Prades, A. [Ciemat, Madrid (Spain); Martinez-Arias, R. [Universidad Complutense, Madrid (Spain); Arranz, L. [Hospital Ramon y Cajal, Madrid (Spain); Macias, M.T. [CSIC, Madrid (Spain)

2000-05-01

This paper will present some of the key findings of a comparative Latin-American study on radiological risk perception in the health area. The project used a survey method to examine the social demands for information about radiological risks with regard to diagnostic and therapeutic applications. The following topics will be analysed: 1) The role of information as a means for feeling safe; 2) who should inform the public on radiological risks; and 3) what type of information the public would like to receive. A questionnaire was distributed to outpatient samples from ten countries: Argentine, Brazil, Colombia, Cuba, Ecuador, Mexico, Panama, Peru, Uruguay, and Spain, thanks to the collaboration of the different National Radioprotection Societies of the above mentionned countries, and of other concerned professionals (in case they didn't had any association at the time). Correspondence analysis and other techniques of optimal scaling will be used. The paper will discuss the main cross-cultural differences with regard to social demand for information about radiological risks. Our findings may have relevant implications for radiological risks communication programs. (author)

Technical basis for removal of 221-T tunnel from airborne radiological area status

International Nuclear Information System (INIS)

Geuther, W.J.

1996-01-01

This document provides the technical basis for removal of the 221-T Tunnel from airborne radiological control. T Plant Radiological Control has evaluated air sampling data and engineering controls, and determined the necessary administrative controls to make this transition. With these administrative controls (specified within document) in place, the tunnel can be removed from Airborne Radioactive Area status. The removal of the tunnel from airborne status will allow work to be performed within the tunnel under controlled conditions, as outlined in this technical basis, without the use of respiratory protection equipment

Radiological mapping of emergency planning zone of Narora Atomic Power Station

International Nuclear Information System (INIS)

Pujari, R.N.; Saindane, Shashank; Narsaiah, M.V.R.; Solase, S.S.; Chaudbury, Probal; Kumar, Deepak; Gautam, Y.P.; Sharma, A.K.; Kumar, Avinash

2016-01-01

As a part of emergency preparedness programme, environmental radiation monitoring of Emergency Planning Zone (EPZ) (16 km radius) of Nuclear Power Plants (NPPs) is being carried out periodically. An environmental radiation monitoring of EPZ of Narora Atomic Power Station (NAPS) was carried out by installing various state-of-the-art mobile radiation monitoring systems in a vehicle and soil samples were collected from 40 locations. Around 200 important villages within EPZ were monitored and the radiological mapping of the monitored area is shown. The average dose rate recorded was 125 ± 28.8 nGy h -1 . Analysis of the collected dose rate data and the soil samples indicate normal background radiation level in the area

Operational aspects of the radiological control in a radioisotopes plant production

International Nuclear Information System (INIS)

Corahua, A.

1996-01-01

The purpose of this paper is to inform about the results obtained in the control operations carried out by the radioprotection area of the radioisotopes plant production during 1994 and then were compared with the limits established by the regulations of radiological radioprotection. In the general inter-texture of the activities that are developed in the radioisotopes plant production, the carried out controls are: area monitoring, air monitoring, personnel monitoring, monitoring in the expedition of radioactive material and monitoring and control in the evacuation of solid and liquid wastes. The result obtained in the present paper states that the doses received by the exposed occupationally staff are below the allowed limits. (author). 3 refs

Assessment of radiological profile of Mumbai - Kota rail route using mobile monitoring methodology

International Nuclear Information System (INIS)

Saindane, Shashank S.; Anoj Kumar; Narsaiah, M.V.R.; Mishra, A.K.; Solase, Sachin; Murali, S.; Pradeepkumar, K.S.

2014-01-01

Radiological mapping is useful for updates on the trend of the radiation level at various locations/routes. As a part of this, the radiation mapping of Mumbai - Kota rail route (∼ 1230 km) was carried out by using various state of the art monitoring systems/instruments to record the radiation level both on online and offline modes. The state of the art monitoring systems/instruments such as Compact Radiation monitoring system, Gamma Tracer, Field Spec and portable spectrometer equipped with Global Positioning System were installed inside the train compartment. The dose rate data were noted manually also at various stations using highly sensitive portable instruments like Micro R (μR) survey meter, Field spec, Personal Radiation Detector (PRD) etc. With the help of portable spectrometer, spectral data were continuously collected along the route

A unique radiation area monitoring system

International Nuclear Information System (INIS)

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

1978-01-01

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

Radiological survey of Goiania by a mobile monitoring unit

International Nuclear Information System (INIS)

Moreira, M.C.F.

1989-01-01

After the initial response to the radiological accident in Goiania, a radiological survey throughout the city was performed using a mobile unit. This unit was equipped with two Geiger Muller detectors outsise the vehicle and one 4' x 4' NaI(Tl) detector connected to a dual recorder. All three detectors were placed 1 m above the ground. The survey system covers a wide range of exposure rate, since environmental levels up to 10 R h -1 . Eighty percent of the Goiania urban area was covered by this survey and except for some specific locations the contamination was restricted to the main foci surroundings ocurring in a non homogenous pattern. The highest value observed in the city after the main foci decontamination was of 0.7 mR h -1 in the 57 th street - where the source was opened. Results of the main foci and some other locations are apresented in the paper. The system designed to perform the survey in the city played a fundamental role during the decontamination process (author) [pt

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

Radiological effects

International Nuclear Information System (INIS)

Anon.

1978-01-01

Environmental monitoring in the vicinity of the Calvert Cliffs Nuclear Power Plant has been shown the radiation dose to the public from plant operation to be quite small. Calculations from the reported release rates yield 0.2 mrem whole body dose and 0.6 mrem skin dose for the calendar quarter of maximum release. Radioactivity discharges to the Chesapeake Bay have resulted in detectable concentrations of /sup 110m/Ag, 58 Co, and 60 Co in sediments and shellfish. The area yielding samples with detectable concentrations of plant effluents extends for roughly six miles up and down the western shore, with maximum values found at the plant discharge area. The radiation dose to an individual eating 29 doz oysters and 15 doz crabs (5 kg of each) taken from the plant discharge area would be about 4/1000 mrem whole body dose and 0.2 mrem gastrointestinal tract dose (about 0.007% and 0.5% of the applicable guidelines, respectively.) Comparison of these power plant-induced doses with the fluctuations in natural radiation dose already experienced by the public indicates that the power plant effects are insignificant. The natural variations are tens of times greater than the maximum doses resulting from Calvert Cliffs Power Plant. Although operations to date provide an insufficient basis to predict radiological impact of the Calvert Cliffs Plant over its operational lifetime, available data indicate that the plant should continue to operate with insignificant radiological impact, well within all applicable guidelines

The effects on health of radiological and chemical toxicity

International Nuclear Information System (INIS)

Toledano, M.; Flury-Herard, A.

2003-01-01

Future trends in the protection against the effects on health of radiological and/or chemical toxicity will certainly be based on improved knowledge of specific biological mechanisms and individual sensitivity. Progress in these areas will most likely be made at the interfaces between research, health care and biomedical monitoring. (authors)

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.

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.

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

An aerial radiological survey of the Savannah River Site TNX facility and surrounding area, Aiken, South Carolina

International Nuclear Information System (INIS)

1991-06-01

An aerial radiological survey was conducted over a 3.8-square-kilometer (1.5-square-mile) area, centered on the Savannah River Site (SRS) TNX facility. The survey was flown on July 25, 1986, prior to the Steel Creek Corridor survey. Radiological measurements were used to determine the extent of man-made radionuclides in the TNX area. This survey area had been covered during previous site surveys of the Savannah River Floodplain. Higher than typical levels of thorium-232 daughters were detected in the survey area just west of the TNX facility. The natural terrestrial radiation levels were consistent with those measured during prior surveys of this and other SRS areas. 5 refs., 12 figs., 2 tabs

Radiological terrorism and Australia's response

International Nuclear Information System (INIS)

Patterson, D.

2003-01-01

A terrorist attack in Australia involving dispersal of radioactive material is different from conventional terrorist attacks involving explosives. The trauma experienced by victims during an explosive incident includes cuts, broken limbs, burns and shock. When an explosive device involving radioactive materials is involved, there are a number of additional characteristics including the contamination of victims and the surrounding area and the potential requirement for ongoing monitoring and decontamination. Response actions may require additional complex emergency response measures including immediate protective actions to protect those potentially exposed to contamination, mass casualty care, and public and mental health. There are concerns that terrorist organizations are showing increasing interest in acquiring radiological material that could be used with explosive. A dirty bomb or technically known as a radiological dispersal device (RDD) is a device designed to spread radioactive contamination over a wide area and pose a health and safety threat to those within the contaminated area. The radioactive material could be in the form of a large chunk of material, fine powder, a liquid mist, or a gas. The material may also be spread in other ways, such as by simply emptying a container over the desired area. As RDD's do not require large amounts of explosives, there is unlikely to be a large numbers of casualties, however the areas contaminated by the radiological material may cause immediate and long term health risks to those exposed. An RDD is a weapon of Mass Disruption rather than destruction. While the likelihood of RDD's being employed by terrorist in Australia is still considered remote, Australia's emergency response organizations are developing plans to ensure a rapid and comprehensive response occurs should such an event occur in this country, The presentation will outline Australia's response arrangements at the local/state level and the type of federal

Radiological risk assessment for an urban area: Focusing on a drinking water contamination

International Nuclear Information System (INIS)

Jeong, Hyo-Joon; Hwang, Won-Tae; Kim, Eun-Han; Han, Moon-Hee

2009-01-01

This paper specifically discusses a water quality modeling and health risk assessment for cesium-137 to assess the potential and actual effects on human health from drinking water contaminated by a radiological terrorist attack in the Seoul metropolitan area, Korea. With respect to the source term caused by a terrorist attack, it was assumed that 50 TBq of cesium-137 was introduced into the Paldang Lake which is a single water resource for the Seoul metropolitan area. EFDC (Environmental Fluid Dynamics Code) model was used to calculate the hydrodynamic and water quality for the model domain, Paldang Lake. Mortality risk and morbid risk coefficients caused by the ingestion of tap water were used to assess a human health risk due to cesium-137. The transport of cesium-137 in the Paldang water system was mainly dependent on the flow streamlines and the effect of the dilution from the other branches. The mortality and morbidity risks due to the drinking water contamination by cesium-137 were 4.77 x 10 -7 and 6.92 x 10 -7 , respectively. Accordingly, it is very important to take appropriate countermeasures when radiological terrorist attacks have occurred at water resources to prevent radiological risks by radionuclides.

Individual monitoring of medical staff working in interventional radiology in Switzerland using double dosimetry

International Nuclear Information System (INIS)

Damet, J.; Bailat, C.; Bize, P.; Buchillier, Th.; Tosic, M.; Verdun, F.R.; Baechler, S.

2011-01-01

Physicians who frequently perform fluoroscopic examinations are exposed to high intensity radiation fields. The exposure monitoring is performed with a regular personal dosimeter under the apron in order to estimate the effective dose. However, large parts of the body are not protected by the apron (e.g. arms, head). Therefore, it is recommended to wear a supplemental dosimeter over the apron to obtain a better representative estimate of the effective dose. The over-apron dosimeter can also be used to estimate the eye lens dose. The goal of this study was to investigate the relevance of double dosimetry in interventional radiology. First the calibration procedure of the dosimeters placed over the apron was tested. Then, results of double dosimetry during the last five years were analyzed. We found that the personal dose equivalent measured over a lead apron was underestimated by ∼20% to ∼40% for X-ray beam qualities used in radiology. Measurements made over five-year period confirm that the use of a single under-apron dosimeter is inadequate for personnel monitoring. Relatively high skin dose (>10 mSv/month) would have remained undetected without a second dosimeter placed on the apron.

Estimating Radiological Doses to Predators Foraging in a Low-Level Radioactive Waste Management Area

International Nuclear Information System (INIS)

L.Soholt; G.Gonzales; P.Fresquez; K.Bennett; E.Lopez

2003-01-01

Since 1957, Los Alamos National Laboratory has operated Area G as its low-level, solid radioactive waste management and disposal area. Although the waste management area is developed, plants, small mammals, and avian and mammalian predators still occupy the less disturbed and revegetated portions of the land. For almost a decade, we have monitored the concentrations of selected radionuclides in soils, plants, and small mammals at Area G. The radionuclides tritium, plutonium-238, and plutonium-239 are regularly found at levels above regional background in all three media. Based on radionuclide concentrations in mice collected from 1994 to 1999, we calculated doses to higher trophic levels (owl, hawk, kestrel, and coyote) that forage on the waste management area. These predators play important functions in the regional ecosystems and are an important part of local Native American traditional tales that identify the uniqueness of their culture. The estimated doses are compared to Department of Energy's interim limit of 0.1 rad/day for the protection of terrestrial wildlife. We used exposure parameters that were derived from the literature for each receptor, including Environmental Protection Agency's exposure factors handbook. Estimated doses to predators ranged from 9E-06 to 2E-04 rad/day, assuming that they forage entirely on the waste management area. These doses are greater than those calculated for predators foraging exclusively in reference areas, but are still well below the interim dose limit. We believe that these calculated doses represent upper-bound estimates of exposure for local predators because the larger predators forage over areas that are much greater than the 63-acre waste management area. Based on these results, we concluded that predators foraging on this area do not face a hazard from radiological exposure under current site conditions

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

International Nuclear Information System (INIS)

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

1982-03-01

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

Guidelines for a radiology department

International Nuclear Information System (INIS)

1981-05-01

This manual presents guidelines for hospitals on a radiology quality assurance and dose measurement audit program and a system of planned actions that monitor and record the performance and effectiveness of the radiological service

Mobile radiological monitoring around Nuclear Power Plant site at Tarapur

International Nuclear Information System (INIS)

Patil, S.S.; Saindane, S.S.; Sharma, R.; Suri, M.M.K.; Pradeepkumar, K.S.; Sharma, D.N.; Rao, D.D.

2008-01-01

Real time mobile radiological monitoring around nuclear facilities is required for establishing background radiation dose rate data and to detect any increase in the radiation level which is attributable to the atmospheric releases from Nuclear facilities. Mobile radiation survey using mobile monitoring systems was carried out in the Emergency Planning Zone around Tarapur Atomic Power station during plant operation, taking the wind direction also into consideration. For identifying the potential difficulties during an emergency scenario and to understand the variation of the measured values several systems/instruments were used simultaneously for mapping the dose rates. As demonstrated during this monitoring programme, 40mm x 40mm NaI(Tl) detector based Portable Mobile Gamma Spectrometry System (PMGSS) which is attached with a GPS can acquire and store large amount of gamma spectra tagged with positional coordinates and can enhance the capacity of decision makers during any accidental situation. The average of dose rates measured from various locations around Tarapur Atomic Power Station is 70 - 80 nGy.h -1 . The higher dose rate in the range of 110-125 nGy.h -1 measured at one of the location is due to higher concentration of natural radioactivity mainly by 40 K which was confirmed by the gamma spectrometric measurement. (author)

Radiological manifestations of pulmonary tuberculosis

Energy Technology Data Exchange (ETDEWEB)

Andreu, J. E-mail: andreuj@hg.vhebron.es; Caceres, J.; Pallisa, E.; Martinez-Rodriguez, M

2004-08-01

Pulmonary tuberculosis (TB) is a common worldwide lung infection. The radiological features show considerable variation, but in most cases they are characteristic enough to suggest the diagnosis. Classically, tuberculosis is divided into primary, common in childhood, and postprimary, usually presenting in adults. The most characteristic radiological feature in primary tuberculosis is lymphadenopathy. On enhanced CT, hilar and mediastinal nodes with a central hypodense area suggest the diagnosis. Cavitation is the hallmark of postprimary tuberculosis and appears in around half of patients. Patchy, poorly defined consolidation in the apical and posterior segments of the upper lobes, and in the superior segment of the lower lobe is also commonly observed. Several complications are associated with tuberculous infection, such as hematogenous dissemination (miliary tuberculosis) or extension to the pleura, resulting in pleural effusion. Late complications of tuberculosis comprise a heterogeneous group of processes including tuberculoma, bronchial stenosis bronchiectasis, broncholithiasis, aspergilloma, bronchoesophageal fistula and fibrosing mediastinitis. Radiology provides essential information for the management and follow up of these patients and is extremely valuable for monitoring complications.

Implementation of an occupational monitoring program in diagnostic radiology at the 'Hospital Universitario Clementino Fraga Filho'

International Nuclear Information System (INIS)

Oliveira, Sergio Ricardo de; Carvalho, Antonio Carlos Pires; Azevedo, Ana Cecilia Pedrosa de

2003-01-01

An occupational monitoring program in diagnostic radiology was implemented at the Hospital Clementino Fraga Filho of the Rio de Janeiro Federal University (UFRJ), Brazil, in accordance with the Brazilian legislation. Previously, a survey of all personnel involved with ionizing radiation was performed. Many problems were observed: the great majority of the workers were not properly monitored; only three departments of the hospital kept an independent survey of the occupational doses; there was not a follow-up control of the high doses. With the implementation of the program, a new laboratory was chosen to read the dosemeters and this initiative resulted in reduction of the hospital costs. The inclusion of seven more departments in the program represented an increase of 60% in the number of monitored workers. The program also provided a system to control the high doses, especially in the Hemodynamics department, which presented the highest mean dose value (0.32 mSv/month). An area survey program was performed during different periods in places considered of high risk for the workers and for the public as well. At the same time, a software was used to build a database with the aim of controlling all personnel data. The implementation of the program provided all personnel involved a better knowledge of the risks associated with ionizing radiation and of radioprotection, and also awareness of the need of correct use of the personal dose monitors. (author)

Data Management and Tools for the Access to the Radiological Areas at CERN

CERN Document Server

Sanchez-Corral Mena, E; Dorsival, A; Dumont, G; Foraz, K; Hakulinen, T; Havart, F; Kepinski, M P; Mallon Amerigo, S; Martel, P; Ninin, P; Nunes, R; Valentini, F; Vollaire, J

2014-01-01

As part of the refurbishment of the PS accelerator complex Personnel Protection System, the Radiation Protection (RP) checkpoints and buffer zones, for the radiological controls of equipment removed from the beam areas, have been incorporated into the design of the new access points.

An Aerial Radiological Survey of Selected Areas of Area 18 - Nevada Test Site

International Nuclear Information System (INIS)

Lyons, Craig

2009-01-01

As part of the proficiency training for the Radiological Mapping mission of the Aerial Measuring System (AMS), a survey team from the Remote Sensing Laboratory-Nellis (RSL-Nellis) conducted an aerial radiological survey of selected areas of Area 18 of the Nevada Test Site (NTS) for the purpose of mapping man-made radiation deposited as a result of the Johnnie Boy and Little Feller I tests. The survey area centered over the Johnnie Boy ground zero but also included the ground zero and deposition area of the Little Feller I test, approximately 7,000 feet (2133 meters) southeast of the Johnnie Boy site. The survey was conducted in one flight. The completed survey covered a total of 4.0 square miles. The flight lines (with the turns) over the surveyed areas are presented in Figure 1. One 2.5-hour-long flight was performed at an altitude of 100 ft above ground level (AGL) with 200 foot flight-line spacing. A test-line flight was conducted near the Desert Rock Airstrip to ensure quality control of the data. The test line is not shown in Figure 1. However, Figure 1 does include the flight lines for a ''perimeter'' flight. The path traced by the helicopter flying over distinct roads within the survey area can be used to overlay the survey data on a base map or image. The flight survey lines were flown in an east-west orientation perpendicular to the deposition patterns for both sites. This technique provides better spatial resolution when contouring the data. The data were collected by the AMS data acquisition system (REDAR V) using an array of twelve 2-inch x 4-inch x 16-inch sodium iodide (NaI) detectors flown on-board a twin-engine Bell 412 helicopter. Data, in the form of gamma energy spectra, were collected every second over the course of the survey and were geo-referenced using a differential Global Positioning System. Spectral data allows the system to distinguish between ordinary fluctuations in natural background radiation levels and the signature produced by man

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.

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.

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

Emergency Management and Radiation Monitoring in Nuclear and Radiological Accidents. Summary Report on the NKS Project EMARAD

International Nuclear Information System (INIS)

Lahtinen, J.

2006-04-01

In order to manage various nuclear or radiological emergencies the authorities must have pre-prepared plans. The purpose of the NKS project EMARAD (Emergency Management and Radiation Monitoring in Nuclear and Radiological Accidents) was to produce and gather various data and information that could be useful in drawing up emergency plans and radiation monitoring strategies. One of the specific objectives of the project was to establish a www site that would contain various radiation-threat and radiation-monitoring related data and documents and that could be accessed by all Nordic countries. Other important objectives were discussing various factors affecting measurements in an emergency, efficient use of communication technology and disseminating relevant information on such topics as urban dispersion and illicit use of radiation. The web server is hosted by the Radiation and Nuclear Safety Authority (STUK) of Finland. The data stored include pre-calculated consequence data for nuclear power plant accidents as well as documents and presentations describing e.g. general features of monitoring strategies, the testing of the British urban dispersion model UDM and the scenarios and aspects related to malicious use of radiation sources and radioactive material. As regards the last item mentioned, a special workshop dealing with the subject was arranged in Sweden in 2005 within the framework of the project. (au)

Patient dosimetry in interventional radiology

International Nuclear Information System (INIS)

Silva, Mauro Wilson O. da; Canevaro, Lucia V.; Rodrigues, Barbara Beatriz D.

2009-01-01

Mapping skin doses in interventional radiology is useful to determine the probability of a possible injury, to detect areas of overlapping field and to obtain a permanent register of the most exposed skin areas. A method for the evaluation of patient doses in interventional radiology procedures is the slow film, Kodak EDR2 (Extended Dose Range). Kodak EDR 2 film was calibrated in the range of 50 kVp to 120 kVp beam qualities. Its dose-response curve was plotted up to the saturation point of 1000 mGy. Dose responses are a function of facility dependent factors including processing conditions the density sampling, and exposure monitoring equipment. The distribution and the form of all the irradiation fields have been registered in the Kodak EDR 2 films. The Dosimetric analysis was performed in a sample of 37 patients submitted the procedures coronariography and angioplasty. The film has a threshold of saturation around 1 Gy, the applied methodology is efficient to quantify the doses and to identify the distribution of the fields. (author)

Evaluation and assessment methodology, standards, and procedures manual of the United States Federal Radiological Monitoring and Assessment Center

International Nuclear Information System (INIS)

Kerns, K.C.; Burson, Z.G.; Smith, J.M.; Blanchard, R.L.

2000-01-01

In the event of a major radiological emergency, the U.S. Federal Radiological Emergency Response Plan authorises the creation of the Federal Radiological Monitoring and Assessment Center (FRMAC). The FRMAC is established to co-ordinate the Federal off-site monitoring and assessment activities, and is comprised of representatives from several Federal agencies and Department of Energy contractors who provide assistance to the state(s) and Lead Federal Agency. The Evaluation and Assessment (E and A) Division of the FRMAC is responsible for receiving, storing, and interpreting environmental surveillance data to estimate the potential health consequences to the population in the vicinity of the accident site. The E and A Division has commissioned the preparation of a methodology and procedures manual which will result in a consistent approach by Division members in carrying out their duties. The first edition of this manual is nearing completion. In this paper, a brief review of the structure of the FRMAC is presented, with emphasis on the E and A Division. The contents of the E and A manual are briefly described, as are future plans for its expansion. (author)

Annual Radiological Environmental Monitoring Program Report for the Three Mile Island, Unit 2, Independent Spent Fuel Storage Installation

International Nuclear Information System (INIS)

Hall, Gregory Graham

2002-01-01

This report presents the results of the 2001 Radiological Environmental Monitoring Program conducted in accordance with 10 CFR 72.44 for the Three Mile Island, Unit 2, Independent Spent Fuel Storage Installation. A description of the facility and the monitoring program is provided. The results of monitoring the two predominant radiation exposure pathways, potential airborne radioactivity releases and direct radiation exposure, indicate the facility operation has not contributed to any increase in the estimated maximum potential dose commitment to the general public.

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

Evaluation of the radiological safety of the working area in the installation of experimental fuel elements in 2010

International Nuclear Information System (INIS)

Nudia Barenzani

2011-01-01

Evaluations of radiological safety in working areas in IEBE during 2010 have been conducted. The purpose of this evaluation was to determine that the working area in IEBE is safe for workers to conducting research and development of nuclear fuel. The evaluation is done by analyzing the results of routine monitoring in the laboratory of IEBE during the year 2010, such as gamma exposure, alpha radioactivity in air and surface contamination. The result is the highest gamma exposure (3.213 ± 0.121) µSv/h at the desk-work-B in HR-05, alpha Radioactivity in air at (4.980 ± 0.444) Bq/m 3 and the average surface contamination (0.090 ± 0.008) Bq/cm 2 . The result is still above Permissible Maximum Concentration (MPC) and in the Lower Dose Limit Value established by the Regulatory Body. So it can be concluded that IEBE laboratory is safe for workers in conducting research and development nuclear fuel. (author)

Radiological emergency preparedness (REP) program

International Nuclear Information System (INIS)

Kwiatkowski, D.H.

1995-01-01

This talk focuses on the accomplishments of Radiological Emergency Preparedness Program. Major topics include the following: strengthening the partnership between FEMA, the States, and the Industry; the Standard Exercise Report Format (SERF); Multi-year performance partnership agreement (MYPPA); new REP Program guidance; comprehensive exercise program; federal radiological emergency response plan (FRERP); international interest; REP user fee; implementation EPA PAGs and Dose Limits; Contamination monitoring standard for portal monitors; guidance documents and training

Radiological Survey Results for Areas A1 North, A5A, A6, and B2 at the Molycorp Washington Remediation Project, Washington, Pennsylvania

International Nuclear Information System (INIS)

W.C. Adams

2007-01-01

Perform radiological surveys of the Molycorp Washington Remediation Project (MWRP) facility in Washington, Pennsylvania. The U.S. Nuclear Regulatory Commission (NRC) requested the Oak Ridge Institute for Science and Education (ORISE) to provide limited training pertaining to ORISE radiological soil scanning and sampling procedures to the Pennsylvania Department of Environmental Protection (PADEP) personnel. In addition, the NRC also requested that ORISE perform radiological surveys of the Molycorp Washington Remediation Project (MWRP) facility in Washington, Pennsylvania (Figure 1). ORISE has and will continue to interface with PADEP personnel in a joint effort to perform confirmatory radiological surveys, consisting of gamma scans and soil sampling, at the MWRP facility. PADEP personnel will continue to submit soil samples that they collect to ORISE for analyses. PADEP sample results, along with ORISE results, will be provided to the NRC and PADEP so that decisions regarding the radiological status of the surveyed areas can be determined. ORISE performed radiological surveys during the period of November 28 and 29, 2006. The survey unit (SU) available for ORISE radiological survey activities was Area A1 North. The MWRP final status survey (FSS) results for Area A1 North were reviewed prior to these survey activities. Prior to ORISE's survey activities, PADEP personnel had performed radiological surveys and collected soil samples from SU Areas A5A and A6. These samples were provided to ORISE for analyses while on site. After the ORISE radiological surveys, PADEP personnel collected soil samples from SU Areas A2 and B2 and these samples were shipped to ORISE for analyses in January 2007. Figure 2 depicts the MWRP Areas A through D; ORISE and PADEP personnel performed survey activities in portions of Areas A and B. For interlaboratory comparison analyses with MWRP's site contractor, Malcolm Pirnie (MP), ORISE requested soil samples from the Area A1 soil stockpiles

Mechanical analysis of flying robot for nuclear safety and security control by radiological monitoring

International Nuclear Information System (INIS)

Cho, Hyo Sung; Woo, Tae Ho

2016-01-01

Highlights: • Radiological monitoring of the NPPs site is performed by the flying robot. • The mechanics of drone is investigated in the NPPs. • Yaw and Pitch motions are simulated for the robotic behaviors. • The flying robot is analyzed for the nuclear safety and security successfully. - Abstract: The flying robot is investigated for the nuclear accident and security treatment. Several mechanics are introduced for the movement of the drone. The optimized motion of the drone should cover all areas of Nuclear Power Plants (NPPs) over the site where the circular and surmounting motions are needed with traverse of zigzag shapes. There is the Yaw motion in the circular moving and the Pitch motion in the climbing and downing against reactor facility. The fallout is calculated from the radiation concentration in the breaking part of the NPPs where the radioactive material leaks from the containment, coolant loop, plant facility and so on. The dose equivalents are obtained where the values are changeable following the random values of the y value, average wind speed, and dispersed concentration in the detection position. The simulation of new positions of x, y, and z are normalized from 0.0 to 1.0. The mechanics of flying robot produces the multidisciplinary converged technology incorporated with the aerial radiation monitoring information.

Radiological performance assessment for the E-Area Vaults Disposal Facility

International Nuclear Information System (INIS)

Cook, J.R.

2000-01-01

This report is the first revision to ''Radiological Performance Assessment for the E-Area Vaults Disposal Facility, Revision 0'', which was issued in April 1994 and received conditional DOE approval in September 1994. The title of this report has been changed to conform to the current name of the facility. The revision incorporates improved groundwater modeling methodology, which includes a large data base of site specific geotechnical data, and special Analyses on disposal of cement-based wasteforms and naval wastes, issued after publication of Revision 0

Radiological aspects of Gaucher disease

International Nuclear Information System (INIS)

Katz, Robert; Booth, Tom; Hargunani, Rikin; Wylie, Peter; Holloway, Brian

2011-01-01

Advances in imaging and the development of commercially available enzyme therapy have significantly altered the traditional radiology of Gaucher disease. The cost of treatment and need for monitoring response to therapy have magnified the importance of imaging. There are no recent comprehensive reviews of the radiology of this relatively common lysosomal storage disease. This article describes the modern imaging, techniques and radiological manifestations of Gaucher disease. (orig.)

Radiological aspects of Gaucher disease

Energy Technology Data Exchange (ETDEWEB)

Katz, Robert; Booth, Tom; Hargunani, Rikin; Wylie, Peter; Holloway, Brian [Royal Free Hospital, Radiology Department, London (United Kingdom)

2011-12-15

Advances in imaging and the development of commercially available enzyme therapy have significantly altered the traditional radiology of Gaucher disease. The cost of treatment and need for monitoring response to therapy have magnified the importance of imaging. There are no recent comprehensive reviews of the radiology of this relatively common lysosomal storage disease. This article describes the modern imaging, techniques and radiological manifestations of Gaucher disease. (orig.)

Quality control of the interpretation monitors of digital radiological images; Controle de qualidade dos monitores de interpretacao de imagens radiologicas digitais: uma revisao

Energy Technology Data Exchange (ETDEWEB)

Favero, Mariana S.; Goulart, Adriano Oliveira S., E-mail: mariana@phymed.com.br [PhyMED - Consultores em Fisica Medica e Radioprotecao Ltda, Porto Alegre, RS (Brazil)

2016-07-01

The performance monitors has great importance in image quality of digital radiographic systems. In environments without films, it became necessary to implement acceptance testing and quality control monitors used for interpretation of medical images. The monitors dedicated to radiodiagnostic should provide information that represent slight differences in x-ray attenuation or minor differences in some anatomical region of interest. This should also result in small differences in luminance of an image represented. Factors affecting the quality of medical imaging are contrast, noise, resolution, artifacts and distortions. Therefore, a monitor must have specific characteristics, making it possible for the observer to carry out an assessment that leads to better diagnosis. Based on the need to evaluate diagnostic monitors in various radiological applications, this paper presents a summary for implementation and standardization of tests that are recommended by the publication AAPM Report 03. (author)

An Aerial Radiological Survey of the Las Vegas Strip and Adjacent Areas

International Nuclear Information System (INIS)

Thane Hendricks

2008-01-01

As proficiency training for the Radiological Mapping mission of the Aerial Measuring System (AMS), a survey team from the Remote Sensing Laboratory-Nellis (RSL-Nellis) conducted aerial radiological surveys of the Las Vegas Strip and adjacent areas on December 11, 2006, and December 26 and 31, 2007. The AMS operation and appropriate law enforcement agencies selected the area as an appropriate urban location to exercise AMS capability for mapping environmental radiation and searching for man-made radioactive sources. The surveys covered ∼11 square miles. Each survey required a 2.5-hour-long flight, performed at an altitude of 300 ft above ground level (AGL) at a line spacing of 600 ft. Water line and test line flights were conducted over the Lake Mead and Government Wash areas to determine the nonterrestrial background contributed by aircraft, radon, and cosmic activity, and to determine the altitude-dependent air mass correction. The data were collected by the AMS data acquisition system (REDAR V) using an array of twelve 2-inch x 4-inch x 16-inch sodium iodide (NaI) detectors flown on-board a twin-engine Bell 412 helicopter. Gamma energy spectral data were collected second-by-second over the survey area. This spectral data allows the system to distinguish between natural terrestrial background contributions and man-made radioisotope contributions. Spectral data can also be used to identify specific man-made radioactive isotopes. Data geo-locations were determined with a Real-Time Differential Global Positioning System (RDGPS)

Environmental radiological monitoring methods in TENORM facilities and its relevance

International Nuclear Information System (INIS)

Teng Iyu Lin; Ismail Bahari; Muhamad Samudi Yasir

2011-01-01

In Malaysia, mineral processing plant is one of the Naturally Occurring Radioactive Material (NORM) processing industries controlled by the Atomic Energy Licensing Board (AELB) through the enforcement of Atomic Energy Licensing Act 1984 (Act 304). The activities generated waste which is called as TENORM wastes. TENORM wastes are mainly found in thorium hydroxide from the processing of xenotime and monazite, and iron oxide and red gypsum from the processing of ilmenite. Other TENORM wastes are scales and sludge from the oil and gas industries, tin slag produced from the smelting of tin, and ilmenite, zircon, and monazite produced from the processing of tin tailing (amang). The environmental and radiological monitoring program is needed to ensure that the TENORM wastes did not caused any contamination to the environment. The wastes vary in the types of samples, parameters of analysis as well as the frequency of monitoring based on licenses conditions issued by the AELB. The main objective of this study is to assess the suitability of licenses condition and the monitoring program required in oil and gas, and mineral processing industries. Study was done by assessing the data submitted to the AELB in order to comply with the licensing requirement. This study had found out that there are a few of licenses conditions that need to be reviewed accordingly based on the processing activity. (Author)

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

authorisations except for the presence of aerosol canisters in waste from both sites and a small quantity of free liquid in the Amersham waste. Environment monitoring: Instrumental surveys of radiation levels and laboratory analyses of samples collected mainly within the vicinity of nuclear sites are carried out. The results are used to assess the exposure of members of the public to radiation from non-food pathways, such as might arise from the occupation of beaches, river banks and inter-tidal areas. (MAFF undertake monitoring of radioactivity in foodstuffs.) Radiological assessment of the results confirmed that exposures remained similar to those in previous years and in all cases were substantially less than the dose limit of 1 milliSievert per year. As in previous years elevated levels of tritium were observed in leachates from a number of landfill sites. Although higher than expected the elevated levels do not pose a radiological hazard. Radioactivity in air and rainwater: This routine monitoring programme has been carried out for many years to provide information on radioactivity in air and deposited in rainwater. Airborne dust and rainwater were sampled continuously at locations throughout the UK. The concentrations in air of beryllium-7, a naturally occurring radionuclide formed by cosmic rays in the upper atmosphere, caesium-137, plutonium 239+240 and americium-241 were very low and similar to results recorded since 1990. Caesium-137 was undetectable in rainwater, and the concentration of tritium, plutonium 239+240 and americium-241 were at low levels, as expected. Radioactivity in drinking water sources: This routine monitoring programme has also been carried out for many years. Samples of water were provided by the water companies from 32 sources comprising reservoirs, rivers and groundwater boreholes providing drinking water to over 10 million people. The results show that all the monitored sources are generally below the World Health Organisation's (WHO) guideline

OPTIMIZING RADIOLOGICAL MONITOR SITING OVER THE CONTINENTAL U.S

International Nuclear Information System (INIS)

Chen, K; Robert Buckley, R; Robert Kurzeja, R; Lance Osteen, L; Saleem Salaymeh, S

2007-01-01

The US Environmental Protection Agency (EPA) is installing a network of sensors in the US to monitor background radiation and elevated radiation levels expected from a possible nuclear incident. The network (RadNet) of 180 fixed sensors is intended to provide a basic estimate of the radiation level throughout the US and enhanced accuracy near population centers. This report discusses one of the objective methods for locating these monitors based on criteria outlined by the EPA. The analysis employs a representative climatology of incident scenarios that includes 50 release locations, four seasons and four times of the day. This climatology was calculated from 5,600 simulations generated with NOAA-ARL's HYSPLIT Lagrangian trajectory model. The method treats the release plumes as targets and monitors are located to maximize the number of plumes detected with the network. Weighting schemes based on detection only, dose-weighted detection and population-dose weighted detection were evaluated. The result shows that most of the monitors are located around the population centers, as expected. However, there are monitors quite uniformly distributed around the less populated areas. The monitors at the populated areas will provide early warning to protect the general public, and the monitors spread across the country will provide valuable data for modelers to estimate the extent and the transport of the radioactive contamination

Wide-area, real-time monitoring and visualization system

Science.gov (United States)

Budhraja, Vikram S.; Dyer, James D.; Martinez Morales, Carlos A.

2013-03-19

A real-time performance monitoring system for monitoring an electric power grid. The electric power grid has a plurality of grid portions, each grid portion corresponding to one of a plurality of control areas. The real-time performance monitoring system includes a monitor computer for monitoring at least one of reliability metrics, generation metrics, transmission metrics, suppliers metrics, grid infrastructure security metrics, and markets metrics for the electric power grid. The data for metrics being monitored by the monitor computer are stored in a data base, and a visualization of the metrics is displayed on at least one display computer having a monitor. The at least one display computer in one said control area enables an operator to monitor the grid portion corresponding to a different said control area.

Emergency Management and Radiation Moni-toring in Nuclear and Radiological Accidents. Summary Report on the NKS Project EMARAD

Energy Technology Data Exchange (ETDEWEB)

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

2006-04-15

In order to manage various nuclear or radiological emergencies the authorities must have pre-prepared plans. The purpose of the NKS project EMARAD (Emergency Management and Radiation Monitoring in Nuclear and Radiological Accidents) was to produce and gather various data and information that could be useful in drawing up emergency plans and radiation monitoring strategies. One of the specific objectives of the project was to establish a www site that would contain various radiation-threat and radiation-monitoring related data and documents and that could be accessed by all Nordic countries. Other important objectives were discussing various factors affecting measurements in an emergency, efficient use of communication technology and disseminating relevant information on such topics as urban dispersion and illicit use of radiation. The web server is hosted by the Radiation and Nuclear Safety Authority (STUK) of Finland. The data stored include pre-calculated consequence data for nuclear power plant accidents as well as documents and presentations describing e.g. general features of monitoring strategies, the testing of the British urban dispersion model UDM and the scenarios and aspects related to malicious use of radiation sources and radioactive material. As regards the last item mentioned, a special workshop dealing with the subject was arranged in Sweden in 2005 within the framework of the project. (au)

Efficacy of rock doves at the Hanford site, Washington, as radiological indicators

Energy Technology Data Exchange (ETDEWEB)

Houser, M.R.

1996-02-01

Site faithfulness and general movement patterns of five rock dove (Columba livia) flocks were estimated in order to evaluate their efficacy as radiological indicators on the Hanford Site. Of 367 individually marked birds, 311 were resighted or recaptured at least once during onsite and offsite monitoring. Average site faithfulness for all flocks from resightings was 87.1% and was not significantly different than a hypothesized 90% site faithful distribution. Average site faithfulness from pooled resightings and recaptures was 91.3%, which was also not significantly different than a 90% distribution. Since Hanford rock doves exhibit site faithfulness and can be easily monitored, I conclude that they can be used as radiological indicators. I found 107 birds at 21 different locations during offsite surveys in agricultural areas adjacent to the Hanford Site. Mean movement distances from capture areas to offsite locations for each of the five flocks were significantly different. Mean movement distances from capture areas to offsite locations for each flock were highly correlated with closest possible distances for each flock. Mean movement directions from capture areas to offsite locations for each flock were significantly different than random movement patterns for each flock.

Efficacy of rock doves at the Hanford site, Washington, as radiological indicators

International Nuclear Information System (INIS)

Houser, M.R.

1996-02-01

Site faithfulness and general movement patterns of five rock dove (Columba livia) flocks were estimated in order to evaluate their efficacy as radiological indicators on the Hanford Site. Of 367 individually marked birds, 311 were resighted or recaptured at least once during onsite and offsite monitoring. Average site faithfulness for all flocks from resightings was 87.1% and was not significantly different than a hypothesized 90% site faithful distribution. Average site faithfulness from pooled resightings and recaptures was 91.3%, which was also not significantly different than a 90% distribution. Since Hanford rock doves exhibit site faithfulness and can be easily monitored, I conclude that they can be used as radiological indicators. I found 107 birds at 21 different locations during offsite surveys in agricultural areas adjacent to the Hanford Site. Mean movement distances from capture areas to offsite locations for each of the five flocks were significantly different. Mean movement distances from capture areas to offsite locations for each flock were highly correlated with closest possible distances for each flock. Mean movement directions from capture areas to offsite locations for each flock were significantly different than random movement patterns for each flock

Radiology applications of financial accounting.

Science.gov (United States)

Leibenhaut, Mark H

2005-03-01

A basic knowledge of financial accounting can help radiologists analyze business opportunities and examine the potential impacts of new technology or predict the adverse consequences of new competitors entering their service area. The income statement, balance sheet, and cash flow statement are the three basic financial statements that document the current financial position of the radiology practice and allow managers to monitor the ongoing financial operations of the enterprise. Pro forma, or hypothetical, financial statements can be generated to predict the financial impact of specific business decisions or investments on the profitability of the practice. Sensitivity analysis, or what-if scenarios, can be performed to determine the potential impact of changing key revenue, investment, operating cost or financial assumptions. By viewing radiology as both a profession and a business, radiologists can optimize their use of scarce economic resources and maximize the return on their financial investments.

Product kerma air area and effective dose in dental radiology; Produto kerma no ar-area e dose efetiva em radiodiagnostico odontologico

Energy Technology Data Exchange (ETDEWEB)

Mauro, Rodrigo A.P.; Souza, M. Daiane M.; Costa, Alessandro M. [Universidade de Sao Paulo (USP), Ribeirao Preto (USP), SP (Brazil). Faculdade de Filosofia Ciencias e Letras

2016-07-01

The main purpose of patient dosimetry in diagnostic radiology is to determine dosimetric quantities for the establishment and use of reference levels and comparative risk assessment. The use of the air kerma-area product, P{sub KA}, has been suggested in dental radiology, as this quantity is more closely related to risk. The aim of this study was to perform a preliminary survey of P{sub KA} and effective dose in different types of dental examinations. The future perspective is a large-scale survey for the establishment and use of diagnostic reference levels in dentistry in Brazil. (author)

Product kerma air area and effective dose in dental radiology; Produto kerma no ar area e dose efetiva em radiodiagnostico odontologico

Energy Technology Data Exchange (ETDEWEB)

Mauro, Rodrigo A.P.; Souza, Daiane M.; Costa, Alessandro M., E-mail: rodrigomauro@usp.br [Universidade de Sao Paulo (USP), Ribeirao Preto, SP (Brazil). Faculdade de Filosofia Ciencias e Letras

2016-07-01

The main purpose of patient dosimetry in diagnostic radiology is to determine dosimetric quantities for the establishment and use of reference levels and comparative risk assessment. The use of the air kerma-area product, P{sub KA}, has been suggested in dental radiology, as this quantity is more closely related to risk. The aim of this study was to perform a preliminary survey of P{sub KA} and effective dose in different types of dental examinations. The future perspective is a large-scale survey for the establishment and use of diagnostic reference levels in dentistry in Brazil. (author)

How conservative is routine personal dosimetry monitoring in diagnostic radiology?

International Nuclear Information System (INIS)

Boetticher, H. von; Lachmund, J.; Hoffmann, W.

2007-01-01

Purpose: Dose values obtained by official personal radiation exposure monitoring are often considered equivalent to the effective dose of a person. This paper provides estimates of the extent of deviation between the two dose concepts under various conditions. Materials and Methods: Doses for patients and personnel were measured using thermoluminescence dosimeters for five different geometries at three work settings in a radiology department. Patients and personnel were simulated with anthropomorphic phantoms. Different types of protective clothing as well as permanent protection shields were considered in the calculations. Results: Dose values obtained by official personal dose monitoring are conservative only for specific radiation protection situations. With state-of-the-art personal protective equipment (wrap-around style lead apron with thyroid shield), the ratio between effective dose and personal dose varies between 0.6 and 1.25. Without thyroid protection the official personal dose systematically underestimates the effective dose: for protective clothing with 0.5 mm lead equivalent without thyroid shielding, the effective dose exceeds the personal dose by factors between 1.7 and 3.1. If protective clothing with lead equivalent 0.35 mm is used, this factor varies between 1.1 and 1.82. (orig.)

Radiological demonstration of gastroesophageal reflux. Diagnostic value of barium and bread studies compared with 24-hour pH monitoring

International Nuclear Information System (INIS)

Aksglaede, K.; Funch-Jensen, P.; Thommesen, P.

1999-01-01

To correlate gastroesophageal reflux (GER), demonstrated by a radiological method using food, with the reflux events, as determined by 24-h pH monitoring. One hundred and seventeen patients with a median age of 47 years (86 male and 31 female) were examined. In the supine left position, the patient consumed 360 ml of barium contrast. Fluoroscopy was performed with the patient in the supine right oblique position during mastication and swallowing a piece of rye bread with liver pate and barium. The test was positive if barium was observed >= 5 cm proximal to the gastroesophageal junction. An antimony pH-probe was placed 5 cm above the lower esophageal sphincter, previously determined by manometry. The position was controlled by radiography after positioning and before removal. The total time of esophageal pH<4 exceeding 5.0% was considered pathological. The radiological method had a specificity of 100% and a sensitivity of 52% compared to 24-h pH monitoring. The high specificity of this radiological method justify direct therapeutic consequence of a positive test. However, a negative test still renders the problem unsolved

Radiological demonstration of gastroesophageal reflux. Diagnostic value of barium and bread studies compared with 24-hour pH monitoring

International Nuclear Information System (INIS)

Aksglaede, K.; Thommesen, P.; Funch-Jensen, P.

1999-01-01

Purpose: To correlate gastroesophageal reflux (GER), demonstrated by a radiological method using food, with the reflux events, as determined by 24-h pH monitoring. Material and Methods: One hundred and seventeen patients with a median age of 47 years (86 male and 31 female) were examinated. In the supine left position, the patient consumed 360 ml of barium contrast. Fluoroscopy was performed with the patient in the supine right oblique position during mastication and swallowing a piece of rye bread with liver pate and barium. The test was positive if barium was observed ≥5 cm proximal to the gastroesophageal junction. An antimony pH-probe was placed 5 cm above the lower esophageal sphincter, previously determined by manometry. The position was controlled by radiography after positioning and before removal. The total time of esophageal pH<4 exceeding 5.0% was considered pathological. Results: The radiological method had a specificity of 100% and a sensitivity of 52% compared to 24-h pH monitoring. Conclusion: The high specificity of this radiological method justify direct therapeutic consequence of a positive test. However, a negative test still renders the problem unsolved. (orig.)

Radiological demonstration of gastroesophageal reflux. Diagnostic value of barium and bread studies compared with 24-hour pH monitoring

Energy Technology Data Exchange (ETDEWEB)

Aksglaede, K.; Thommesen, P. [Dept. of Diagnostic Radiology R, Aarhus Univ. Hospital, Aarhus (Denmark); Funch-Jensen, P. [Surgical Gastroenterology L, Aarhus Univ. Hospital, Aarhus (Denmark)

1999-11-01

Purpose: To correlate gastroesophageal reflux (GER), demonstrated by a radiological method using food, with the reflux events, as determined by 24-h pH monitoring. Material and Methods: One hundred and seventeen patients with a median age of 47 years (86 male and 31 female) were examinated. In the supine left position, the patient consumed 360 ml of barium contrast. Fluoroscopy was performed with the patient in the supine right oblique position during mastication and swallowing a piece of rye bread with liver pate and barium. The test was positive if barium was observed {>=}5 cm proximal to the gastroesophageal junction. An antimony pH-probe was placed 5 cm above the lower esophageal sphincter, previously determined by manometry. The position was controlled by radiography after positioning and before removal. The total time of esophageal pH<4 exceeding 5.0% was considered pathological. Results: The radiological method had a specificity of 100% and a sensitivity of 52% compared to 24-h pH monitoring. Conclusion: The high specificity of this radiological method justify direct therapeutic consequence of a positive test. However, a negative test still renders the problem unsolved. (orig.)

An aerial radiological survey of the Millstone Nuclear Power Station and surrounding area

International Nuclear Information System (INIS)

Vojtech, R.J.

1994-03-01

An aerial radiological survey was conducted during the period of September 10 to 18, 1990, over a 40-square-mile (104-square-kilometer) area surrounding the Millstone Nuclear Power Station (MNPS). The MNPS is located on the Long Island Sound shoreline, three kilometers south of Waterford, Connecticut. The purpose of the survey was to measure and document the terrestrial gamma ray environment of the plant and surrounding areas. A contour map showing radiation exposure rates at 1 meter above ground level was constructed from the aerial data and overlaid on an aerial photograph and a United States Geological Survey map of the area. The exposure rates within the survey region are quite uniform. The area is characterized by an exposure rate of 10-12 microroentgens per hour including an estimated cosmic ray contribution of 3.6 μR/h. This is typical of natural background. The only exception to the natural background readings is the Millstone station itself, which is characterized by an exposure rate consistent with the standard operation of the reactor units. Radionuclide assays of soil samples and pressurized-ion-chamber gamma ray measurements were obtained at five locations within the survey boundaries. These measurements were taken in support of, and are in agreement with, the aerial data. The radiological environment near the plant is consistent with normal plant operation

An aerial radiological survey of the Millstone Nuclear Power Station and surrounding area

Energy Technology Data Exchange (ETDEWEB)

Vojtech, R.J.

1994-03-01

An aerial radiological survey was conducted during the period of September 10 to 18, 1990, over a 40-square-mile (104-square-kilometer) area surrounding the Millstone Nuclear Power Station (MNPS). The MNPS is located on the Long Island Sound shoreline, three kilometers south of Waterford, Connecticut. The purpose of the survey was to measure and document the terrestrial gamma ray environment of the plant and surrounding areas. A contour map showing radiation exposure rates at 1 meter above ground level was constructed from the aerial data and overlaid on an aerial photograph and a United States Geological Survey map of the area. The exposure rates within the survey region are quite uniform. The area is characterized by an exposure rate of 10-12 microroentgens per hour including an estimated cosmic ray contribution of 3.6 {mu}R/h. This is typical of natural background. The only exception to the natural background readings is the Millstone station itself, which is characterized by an exposure rate consistent with the standard operation of the reactor units. Radionuclide assays of soil samples and pressurized-ion-chamber gamma ray measurements were obtained at five locations within the survey boundaries. These measurements were taken in support of, and are in agreement with, the aerial data. The radiological environment near the plant is consistent with normal plant operation.

Radiological protection and environmental monitoring in the area of the Asse mine. Annual report 1991

International Nuclear Information System (INIS)

Meyer, H.; Mueller-Lyda, I.

1992-05-01

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

Radiological protection and environmental monitoring in the area of the Asse mine. Annual report 1990

International Nuclear Information System (INIS)

Meyer, H.; Mueller-Lyda, I.

1991-07-01

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

Radiological response of ceramic and polymeric devices for breast brachytherapy

International Nuclear Information System (INIS)

Batista Nogueira, Luciana; Passos Ribeiro de Campos, Tarcisio

2012-01-01

In the present study, the radiological visibility of ceramic and polymeric devices implanted in breast phantom was investigated for future applications in brachytherapy. The main goal was to determine the radiological viability of ceramic and polymeric devices in vitro by performing simple radiological diagnostic methods such as conventional X-ray analysis and mammography due to its easy access to the population. The radiological response of ceramic and polymeric devices implanted in breast phantom was determined using conventional X-ray, mammography and CT analysis. - Highlights: ► Radiological visibility of ceramic and polymeric devices implanted in breast phantom. ► The barium incorporation in the seed improves the radiological contrast. ► Radiological monitoring shows the position, orientation and degradation of devices. ► Simple radiological methods such as X-ray and mammography were used for radiological monitoring.

Intercomparison Measurements Exercises of Mobile Radiological Laboratories (invited paper)

International Nuclear Information System (INIS)

Martincic, R.

2000-01-01

After the reactor accident in Chernobyl, the importance of mobile radiological laboratories became evident and in situ gamma spectrometry became a common method for the rapid detection of gamma emitters in the environment. Since then different institutions in European countries have organised periodic intercomparison exercises of mobile radiological laboratories to improve the measurement methods and the preparedness of emergency monitoring teams. The general objectives of these workshops are to promote the knowledge and to exchange the experiences of emergency monitoring teams that use mobile radiological laboratories, as well as to foster the international harmonisation of emergency monitoring procedures and cooperation among teams. Finally, the results of intercomparison measurements have shown that such exercises are mandatory for rapid, efficient and correct environmental monitoring in nuclear or radiological emergencies. An overview of these intercomparison measurements is given, results from the 1999 intercomparison workshop are presented and lessons learned are discussed. (author)

Specific radiological monitoring (SRM) in oil and gas production platforms

International Nuclear Information System (INIS)

Hairul Nizam Idris, Syed Asraf Fahlawi Wafa S.M Ghazi and Fadzley Izwan Abd Manaf

2007-01-01

Technologically enhanced naturally occurring radioactive materials (TENORM) are present in components of both oil and natural gas production facilities. TENORM can be associated with the presence of crude oil, produced water and natural gas. The radiation exposure pathways to the workers in oil and gas production are similar to those in the uranium and heavy mineral sand mining and processing industry. This paper work provides a short review on the Specific Radiological Monitoring (SRM) program were carried out at oil and gas platforms in the east cost of Peninsular Malaysia. The objective of this paper work is to observe the monitoring parameters levels and to evaluate whether these levels are exceeding the limits set by Atomic Energy Licensing Board (AELB). The monitoring results showed that the surface contamination, airborne contamination and concentration of radon and thoron are well below the set limit stipulated in LEM/TEK/30 SEM.2, except for external radiation and radioactivity concentration of sludge and scales. About 2 (2.35%) from the 85 external radiation measurements performed were found above the permissible limit. While about 11 (36.6%) and 7 (23.3%) of the 30 collected sludge and scales samples were found containing higher Ra-226 and Ra-228, respectively, than the mean concentrations in normal soils of Peninsular Malaysia. In general, it can be concluded that a few of oil and gas production platform are producing TENORM. (Author)

Radiological conditions in areas of Kuwait with residues of depleted uranium. Report by an international group of experts

International Nuclear Information System (INIS)

2003-01-01

receive doses from exposure to residues of DU have been identified, either by the authorities of Kuwait or in the IAEA's investigation. Annual radiation doses that could arise from exposure to DU residues would be very low and of little radiological concern. Annual radiation doses in the areas where residues do exist would be of the order of a few microsieverts, well below the annual doses received by the population of Kuwait from the natural sources of radiation in the environment and far below the reference level recommended by the IAEA as a criterion to help establish whether remedial actions are necessary. Complete DU penetrators or fragments can still be found at some locations where DU weapons were used during the Gulf War, such as at the oilfields at Manageesh. Prolonged skin contact with these DU residues is the only possible exposure pathway that could result in exposures of radiological significance. As long as access to the areas remains restricted, the likelihood that members of the public could pick up or otherwise come into contact with these residues is low. The authorities of Kuwait have the competence and equipment to carry out the necessary monitoring and survey activities in relation to DU. The analysis techniques used by the Radiation Protection Department of the Ministry of Health of Kuwait are sufficient to determine whether concentrations of uranium in environmental samples are of radiological concern

NCRP Program Area Committee 3: Nuclear and Radiological Security and Safety.

Science.gov (United States)

Taylor, Tammy P; Buddemeier, Brooke

2016-02-01

Program Area Committee (PAC) 3 provides guidance and recommendations for response to nuclear and radiological incidents of both an accidental and deliberate nature. Leadership of PAC 3 was transitioned in March 2015, and the newly composed PAC has been working to delineate and then prioritize the landscape of possible activities for PAC 3. The major activity of PAC 3 during the past year was the establishment of Scientific Committee 3-1 to begin producing a report on Guidance for Emergency Responder Dosimetry.

Dosimetry on the radiological risks prevention in radiotherapy

International Nuclear Information System (INIS)

Fornet R, O. M.; Perez G, F.

2014-08-01

Dosimetry in its various forms plays a determining role on the radiological risks prevention in radiotherapy. To prove this in this paper is shown an analysis based on the risk matrix method, how the dosimetry can influence in each stages of a radiotherapy service; installation and acceptance, operation, maintenance and calibration. For each one of these stages the role that can play is analyzed as either the initiating event of a radiological accident or limiting barrier of these events of the dosimetric processes used for the individual dosimetry, the area monitoring, fixed or portable, for radiation beam dosimetry and of the patients for a radiotherapy service with cobalt-therapy equipment. The result of the study shows that the application of a prospective approach in the role evaluation of dosimetry in the prevention and mitigation of the consequences of a radiological accident in radiotherapy is crucial and should be subject to permanent evaluation at each development stage of these services. (author)

Radiology – Changing Role in Healthcare

Directory of Open Access Journals (Sweden)

Md Khalilur Rahman

2014-01-01

Full Text Available In November 1895, X-rays were inadvertently discovered by the German physicist Wilhelm Conrad Roentgen. Roentgen provisionally named the new rays as X-rays using the mathematical label for something unidentified. Roentgen's initial manuscript, "On A New Kind of Rays" (άber eine neue Art von Strahlen, was published two months later and in 1901, he received the first ever Nobel Prize in Physics “in recognition of the extraordinary services he has rendered by the discovery of the remarkable rays" subsequently named after him. He himself refused to take out patents, intending to the free use of X-rays for the benefit of mankind. Today, Wilhelm Conrad Roentgen is honoured as the father of diagnostic radiology.1,2 Since the inadvertent discovery of X-rays, conventional radiography has developed greatly and mostly has been replaced by digital radiography equipments which convert X-ray images to electronic data that can be studied using a monitor and archived on a computer disk. Digital techniques permit the radiographs to be viewed instantaneously, additionally allow specific areas of the image to be enlarged, and the contrast of the images can be manipulated to provide greater visibility of the abnormality.1 The anatomical details and sensitivity of the newer modalities is now of a high order and the use of imaging for ultrastructural diagnostics nanotechnology, functional and quantitative diagnostics and molecular medicine is steadily increasing. Most recently the improved imaging clarity and tissue differentiation in a number of clinical situations has dramatically increased the spectrum of the diagnostic information and even in many cases revealing the pathology without the requirement of invasive tissue sampling.3 Eventually radiology is now the prime diagnostic aid for many diseases and also has a vital role in monitoring treatment and predicting outcome. Recent advancements in this field bring a number of imaging modalities which have

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

International Nuclear Information System (INIS)

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

2005-01-01

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

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)

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

Assessment of the radiological conditions in areas of Kuwait with residues of depleted uranium

International Nuclear Information System (INIS)

Cabianca, T.; Danesi, P.R.; Linsley, G.

2004-01-01

The 1991 Gulf War was the first conflict in which DU munitions were used extensively. After this conflict, questions arose regarding the possible link between exposure to ionizing radiation from DU and harmful biological effects. In view of these concerns, the Government of Kuwait, in February 2001, requested the IAEA to conduct an assessment to evaluate the possible radiological impact of residues of DU munitions from the 1991 Gulf War at 11 locations in Kuwait. For this purpose, the IAEA assembled a team of senior experts, who visited Kuwait in September 2001 to carry out a preliminary assessment of the sites and to evaluate the available information. In February 2002 scientists from the IAEA, the Spiez Laboratory (Switzerland), representing UNEP, and the Radiation Protection Department of the Ministry of Health of Kuwait, carried out a sampling campaign at these sites. Around 200 environmental samples, including soil, water and vegetation, were collected during the campaign and subsequently analysed. This study constitutes the first comprehensive radiological assessment of compliance with international radiation protection criteria and standards for areas with residues of DU munitions conducted under the auspices of the IAEA. The findings of this investigation indicate that DU does not pose a radiological hazard to the population of Kuwait. Annual radiation doses arising from exposure to DU residues would be of a few micro-sieverts, well below the annual doses from natural sources of radiation and far below the reference level recommended by the IAEA as a criterion to help establish whether remedial actions are necessary. DU penetrators can still be found at some of the locations visited. Prolonged skin contact with these residues is the only possible pathway that could result in exposures of radiological significance. As long as access to these areas remains restricted, the likelihood that members of the public could come into contact with these residues is low

Emerging Technologies and Techniques for Wide Area Radiological Survey and Remediation

Energy Technology Data Exchange (ETDEWEB)

Sutton, M. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Zhao, P. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

2016-03-24

Technologies to survey and decontaminate wide-area contamination and process the subsequent radioactive waste have been developed and implemented following the Chernobyl nuclear power plant release and the breach of a radiological source resulting in contamination in Goiania, Brazil. These civilian examples of radioactive material releases provided some of the first examples of urban radiological remediation. Many emerging technologies have recently been developed and demonstrated in Japan following the release of radioactive cesium isotopes (Cs-134 and Cs-137) from the Fukushima Dai-ichi nuclear power plant in 2011. Information on technologies reported by several Japanese government agencies, such as the Japan Atomic Energy Agency (JAEA), the Ministry of the Environment (MOE) and the National Institute for Environmental Science (NIES), together with academic institutions and industry are summarized and compared to recently developed, deployed and available technologies in the United States. The technologies and techniques presented in this report may be deployed in response to a wide area contamination event in the United States. In some cases, additional research and testing is needed to adequately validate the technology effectiveness over wide areas. Survey techniques can be deployed on the ground or from the air, allowing a range of coverage rates and sensitivities. Survey technologies also include those useful in measuring decontamination progress and mapping contamination. Decontamination technologies and techniques range from non-destructive (e.g., high pressure washing) and minimally destructive (plowing), to fully destructive (surface removal or demolition). Waste minimization techniques can greatly impact the long-term environmental consequences and cost following remediation efforts. Recommendations on technical improvements to address technology gaps are presented together with observations on remediation in Japan.

Monitoring System for ALICE Surface Areas

CERN Document Server

Demirbasci, Oguz

2016-01-01

I have been at CERN for 12 weeks within the scope of Summer Student Programme working on a monitoring system project for surface areas of the ALICE experiment during this period of time. The development and implementation of a monitoring system for environmental parameters in the accessible areas where a cheap hardware setup can be deployed were aim of this project. This report explains how it was developed by using Arduino, Raspberry PI, WinCC OA and DIM protocol.

Radiological assessment and optimization

International Nuclear Information System (INIS)

Zeevaert, T.; Sohier, A.

1998-01-01

The objectives of SCK-CEN's research in the field of radiological assessment and optimization are (1) to implement ALARA principles in activities with radiological consequences; (2) to develop methodologies for radiological optimization in decision-aiding; (3) to improve methods to assess in real time the radiological hazards in the environment in case of an accident; (4) to develop methods and programmes to assist decision-makers during a nuclear emergency; (5) to support the policy of radioactive waste management authorities in the field of radiation protection; (6) to investigate computer codes in the area of multi criteria analysis; (7) to organise courses on off-site emergency response to nuclear accidents. Main achievements in these areas for 1997 are summarised

Radiological and chemical characterization report for the planned Quarry Construction Staging Area and Water Treatment Plant: Revision 1

International Nuclear Information System (INIS)

1989-03-01

The Quarry Construction Staging Area and Water Treatment Plant (QCSA) will be used in the support of the bulk waste removal of the Weldon Spring Quarry. Radiological and chemical characterization was performed on a 12 acre site where the QCSA will be constructed. The characterization revealed approximately .5 acres of radiologically contaminated land. No chemical contamination was found. 8 refs., 5 figs., 7 tabs

Reevaluation of environmental monitoring program for radiological emergency at Almirante Alvaro Alberto Nuclear Power Plant, Angra dos Reis, Rio de Janeiro - Brazil

International Nuclear Information System (INIS)

Ferreira, Lilia M.J. Belem; Ramos Junior, Anthenor C.; Gomes, Carlos A.; Carvalho, Zenildo L.; Gouveia, Vandir; Estrada, Julio; Ney, Cezar

1996-01-01

In order to respond to a major radiological emergency at the Almirante Alvaro Alberto Nuclear Power Plant, located in Angra dos Reis, Rio de Janeiro, the Emergency Response Team of the Institute for Radiation Protection and Dosimetry (IRD/CNEN) established a program of environmental monitoring. The purpose of this program is to define a monitoring trend to assess the off-site radiological conditions and give support to decision making for implementing protective measures in case of a radiological accident, taking into account atmospheric diffusion, population conglomerates and their habits, water and land use, contemplating the entire Emergency Planning Zone of 15 km radius. This program has been reevaluated recently, aiming to optimize it and keep it up to date to assure adequacy of environmental surveillance data in support to a prompt response in case of an emergency situation in the nuclear power plant. It has been organized in the form of a handbook to facilitate handling by field teams. Future revisions will be necessary to incorporate additional pertinent information and keep the handbook up to date, since Angra dos Reis is a summer resort region, subject to constant changes. This paper discusses the structure of the environmental monitoring program and describes the content and preparation of this handbook. (author)

An aerial radiological survey of the West Valley Demonstration Project and surrounding area, West Valley, New York

International Nuclear Information System (INIS)

Berry, H.A.

1991-09-01

An aerial radiological survey of the West Valley Demonstration Project and the surrounding area was conducted from mid-August through early September 1984 by EG ampersand G Energy Measurements, Inc. for the United States Department of Energy. The radiological survey was part of the United States Department of Energy Comprehensive Integrated Remote Sensing (CIRS) program, which provides state-of-the-art remote sensing to support the needs of the various DOE facilities. The survey consisted of airborne measurements of both natural and man-made gamma radiation emanating from the terrestrial surface. These measurements allowed an estimate of the distribution of isotopic concentrations in the area surrounding the project site. Results are reported as isopleths superimposed on aerial photographs of the area. Gamma ray energy spectra are also presented for the net man-made radionuclides. 8 refs., 16 figs., 9 tabs

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.

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.

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

Radiation risk assessment in professionals working in dental radiology area using buccal micronucleus cytome assay.

Science.gov (United States)

Sadatullah, Syed; Dawasaz, Ali Azhar; Luqman, Master; Assiry, Ali A; Almeshari, Ahmed A; Togoo, Rafi Ahmad

2013-11-01

The aim of this study was to assess the incidence of micronuclei (MN) in buccal mucosal cells of professionals working in radiology area to determine the risk of stochastic effects of radiation. All the professionals and students working in King Khalid University - College of Dentistry radiology area were included in the Risk Group (RG = 27). The Control Group (CG = 27) comprised of healthy individual matching the gender and age of the RG. Buccal mucosal scraping from all the 54 subjects of RG and CG were stained with Papanicolaou stain and observed under oil immersion lens (×100) for the presence of micronuclei (MN) in the exfoliated epithelial cells. There was no significant difference between the incidence of MN in RG and CG (p = >0.05) using t-test. Routine radiation protection protocol does minimize the risk of radiation induced cytotoxicity, however, screening of professionals should be carried out at regular intervals.

Radiation protection study of radiology medical workers in radiodiagnosis area

International Nuclear Information System (INIS)

Gaona, E.; Canizal, C.; Garcia, M.A.; Orozco, M.; Rincon, A.; Padilla, Y.; Martinez, A.

1996-01-01

Aspects related to radiological safety and its organization in radiodiagnosis were evaluated by means of scanning carried out in 18 hospitals of Mexico City, divided in 11 public institutions and 7 private ones. The population being studied was: hospital personnel that works in radiodiagnosis. The survey was made with 31 dichotomic variables, being obtained 132 surveys. The personnel characteristics are 83% works in public institutions, 49% works in radiodiagnosis, 3% has an academic degree, 13% is member of a hospital professional association, 13% has updated information on radiological protection, 36% was trained, 45% works for more than 2 years, 52% uses personal dosemeter, less than the 20% knows about the fundamentals of the radiological protection and 24% states to suffer from biological radiation effects, due to the exposure to x-rays. As result of the study, it was found that the main problems that the radiological protection has, are: lack of training programs in radiological protection and supervision, medical surveillance and the few number of persons that takes part in clinical meetings and professional associations. (authors). 7 refs., 3 tabs

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

International Nuclear Information System (INIS)

Maurer, R.J.

1993-04-01

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

Suitability of monitoring methods for the optimisation of Radiological Protection in the case of internal exposure through inhalation

International Nuclear Information System (INIS)

Degrange, J.P.; Gibert, B.; Basire, D.

2000-01-01

The radiological protection system recommended by the International Commission for Radiological Protection (ICRP) for justified practices relied pn the limitation and optimisation principles. The monitoring of internal exposure is most often based on the periodic assessment of individual exposure in order to essentially insure the simple compliance with the annual dose limits. Optimisation of protection implies a realistic, sensitive and analytical assessment of individual and collective exposures in order to allow the indentification of the main sources of exposure (main sources of contamination, most exposed operators, work activities contributing the most to the exposure) and the selection of the optimal protection options. Therefore the monitoring methods must allow the realistic assessment of individual dose levels far lower than annual limits together with measurements as frequent as possible. The aim of this presentation is to discuss the ability of various monitoring methods (collective and individual air sampling, in vivo and in vitro bioassays) to fulfil those needs. This discussion is illustrated by the particular case of the internal exposure to natural uranium compounds through inhalation. Firstly, the sensitivity and the degree to which each monitoring method is realistic are quantified and discussed on the basis of the application of the new ICRP dosimetric model, and their analytical capability for the optimisation of radiological protection is then indicated. Secondly, a case study is presented which shows the capability of individual air sampling techniques to analyse the exposure of the workers and the inadequacy of static air sampling to accurately estimate the exposures when contamination varies significantly over time and space in the workstations. As far as exposure to natural uranium compounds through inhalation is concerned, the study for assessing the sensitivity, analytic ability and accuracy of the different measuring systems shows that

Ergonomics in radiology

Energy Technology Data Exchange (ETDEWEB)

Goyal, N. [Department of Radiology, University Hospital of Wales, Cardiff (United Kingdom)], E-mail: nimitgoyal@doctors.org.uk; Jain, N.; Rachapalli, V. [Department of Radiology, University Hospital of Wales, Cardiff (United Kingdom)

2009-02-15

The use of computers is increasing in every field of medicine, especially radiology. Filmless radiology departments, speech recognition software, electronic request forms and teleradiology are some of the recent developments that have substantially increased the amount of time a radiologist spends in front of a computer monitor. Computers are also needed for searching literature on the internet, communicating via e-mails, and preparing for lectures and presentations. It is well known that regular computer users can suffer musculoskeletal injuries due to repetitive stress. The role of ergonomics in radiology is to ensure that working conditions are optimized in order to avoid injury and fatigue. Adequate workplace ergonomics can go a long way in increasing productivity, efficiency, and job satisfaction. We review the current literature pertaining to the role of ergonomics in modern-day radiology especially with the development of picture archiving and communication systems (PACS) workstations.

Ergonomics in radiology

International Nuclear Information System (INIS)

Goyal, N.; Jain, N.; Rachapalli, V.

2009-01-01

The use of computers is increasing in every field of medicine, especially radiology. Filmless radiology departments, speech recognition software, electronic request forms and teleradiology are some of the recent developments that have substantially increased the amount of time a radiologist spends in front of a computer monitor. Computers are also needed for searching literature on the internet, communicating via e-mails, and preparing for lectures and presentations. It is well known that regular computer users can suffer musculoskeletal injuries due to repetitive stress. The role of ergonomics in radiology is to ensure that working conditions are optimized in order to avoid injury and fatigue. Adequate workplace ergonomics can go a long way in increasing productivity, efficiency, and job satisfaction. We review the current literature pertaining to the role of ergonomics in modern-day radiology especially with the development of picture archiving and communication systems (PACS) workstations

X-ray area monitor

International Nuclear Information System (INIS)

Nintrakit, N.

1983-01-01

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

The Argonne Radiological Impact Program (ARIP). Part II. MONITOR: A Program and Data Base for Retrieval and Utilization of Pollutant Monitoring Data

Energy Technology Data Exchange (ETDEWEB)

Eckerman, Keith F.; Stowe, Ralph F.; Frigerio, Norman A.

1977-02-01

The Argonne Radiological Impact Program (ARIP) is an ongoing project of the Laboratory's Division of Environmental Impact Studies that aims at developing methodologies for assessing the carcinogenic hazards associated with nuclear power development. The project's first report (ANL/ES-26, Part I), published in September.l973, discussed models of radiation carcinogenesis and the contribution of U .. S. background radiation levels to hazardous dose rates. The current report (Part II) treats the storage and access of available data on radiation and radioactivity levels in the u. S. A compute-r code. (the MONITOR program) is prf!sented, which can serve as a ready-access data. bank for all monitoring data acquired over the past two decades. The MONITOR program currently stores data on monitoring locations, types of monitoring efforts, and types of monitoring data. reported in Radiation Data and Reports by the various state and federal ne-tworks; expansion of this data base to include nuclear power facilities in operation or on order is ongoing ·. The MONITOR code retrieves information within a search radius, or rectangl.e ,. circumscribed by parameters of latitude and longitude, and l:.ists or maps the data_as: requested. The code, with examples, is given in full in the report ..

Determination and evaluation of the radiological situation using mobile measurements during the ground phase

Energy Technology Data Exchange (ETDEWEB)

Obrecht, R.; Pohl, H.; Schneider, S.; Grimm, C. [Umweltministerium Baden-Wuerttemberg, Stuttgart (Germany); Neff, Ulrich; Coutinho, Paula; Mueller, Ulrich; Mandel, Carmen [Landesanstalt fuer Umweltschutz, Messungen und Naturschutz Baden-Wuerttemberg, Karlsruhe (Germany); Wilbois, Thomas; Ren, Yongxiang [T-Systems GEI GmbH, Ulm (Germany); Chaves, Fernando [Fraunhofer Inst. IITB, Karlsruhe (Germany)

2009-08-15

The nuclear reactor remote monitoring system of the state of Baden-Wuerttemberg (Kernreaktor-Fernueberwachung Baden-Wuerttemberg - KFUeBW) is implemented according to the recently renewed ''recommendations for remote monitoring of nuclear power plants''. In Baden-Wuerttemberg, the application area of the system covers both, the surveillance of internal procedures on one hand, and the handling of incidents or accidents on the other. The following paper shows the role of the KFUeregarding the determination and evaluation of the radiological situation in the range of off-site emergency response. Progress is reported on the measurement conception and the technical possibilities for the investigation of the radiological situation after the end of the deposition of radio nuclides (ground phase). (orig.)

Radiological Emergency Response Data

Data.gov (United States)

U.S. Environmental Protection Agency — Quality Data Asset includes all current and historical emergency radiological response event and incident of national significance data and surveillance, monitoring,...

Proceedings of the 3. Regional Meeting on Radiological and Nuclear Safety. Radiological protection in Latin America and the Caribbean. Vol. 1,2

International Nuclear Information System (INIS)

1996-08-01

Two volumes contain more than 183 complete papers presented during the Third Regional Meeting on Radiological Protection and Nuclear Safety held on 23-27 October, 1995 in Cusco-Peru. Latin american specialist talk about nuclear safety and radiological protection, radiation natural exposure, biological effect of radiation, radiotherapy and medical radiological safety, radiological safety in industry and research. Also we deal with subjects related to radiological safety of nuclear and radioactive facilities, radioactive waste management, radioactive material transport, environmental radiological monitoring program, radiological emergency and accidents, instruments and dosimetry, basic safety standards of protection against radiation

Radiological control of a microPET/CT laboratory

International Nuclear Information System (INIS)

Sarmento, Daniele M.; Sanches, Matias P.; Carneiro, Janete C.G.G.

2015-01-01

This paper presents the radiological control of a research laboratory in order to satisfy national standards and international recommendations. The microPET/CT laboratory in IPEN uses an Albira system for research purposes in small animals. This study focuses mainly to carry out an initial radiological evaluation and the exposure situation related with the task. The assessment of workplace conditions and individual exposures constitutes as integral part of the operational monitoring programme. Initially, the radiometric survey in laboratory has been carried out using an ionization chamber Radcal 9010 (10 x 5 - 1800). In addition, nine monitoring points with potential exposure were selected, where thermoluminescent dosimeters, TLDs, of CaSO 4 :Dy, were positioned. The occupationally exposed workers were monthly evaluated for external exposures using TL dosimeters, worn on the surface of the body. For internal exposure, the evaluated period was approximately one year starting on April 2014. The average effective dose of the occupationally exposed workers did not exceed 2.4 mSv in the year of 2014, which is equal to the recording level. The workplace, microPET/CT laboratory, is classified as supervised area and the monitoring results in the evaluated period, are within the dose limits established by national standard, as well as the values obtained in individual control. (author)

Radiological control of a microPET/CT laboratory

Energy Technology Data Exchange (ETDEWEB)

Sarmento, Daniele M.; Sanches, Matias P.; Carneiro, Janete C.G.G., E-mail: dms.danica@gmail.com.br, E-mail: msanches@ipen.br, E-mail: janetgc@ipen.br [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

2015-07-01

This paper presents the radiological control of a research laboratory in order to satisfy national standards and international recommendations. The microPET/CT laboratory in IPEN uses an Albira system for research purposes in small animals. This study focuses mainly to carry out an initial radiological evaluation and the exposure situation related with the task. The assessment of workplace conditions and individual exposures constitutes as integral part of the operational monitoring programme. Initially, the radiometric survey in laboratory has been carried out using an ionization chamber Radcal 9010 (10 x 5 - 1800). In addition, nine monitoring points with potential exposure were selected, where thermoluminescent dosimeters, TLDs, of CaSO{sub 4}:Dy, were positioned. The occupationally exposed workers were monthly evaluated for external exposures using TL dosimeters, worn on the surface of the body. For internal exposure, the evaluated period was approximately one year starting on April 2014. The average effective dose of the occupationally exposed workers did not exceed 2.4 mSv in the year of 2014, which is equal to the recording level. The workplace, microPET/CT laboratory, is classified as supervised area and the monitoring results in the evaluated period, are within the dose limits established by national standard, as well as the values obtained in individual control. (author)

An Aerial Radiological Survey of the Yucca Mountain Project Proposed Land Withdrawal and Adjacent Areas

International Nuclear Information System (INIS)

Craig Lyons, Thane Hendricks

2006-01-01

An aerial radiological survey of the Yucca Mountain Project (YMP) proposed land withdrawal was conducted from January to April 2006, and encompassed a total area of approximately 284 square miles (73,556 hectares). The aerial radiological survey was conducted to provide a sound technical basis and rigorous statistical approach for determining the potential presence of radiological contaminants in the Yucca Mountain proposed Land withdrawal area. The survey site included land areas currently managed by the Bureau of Land Management, the U.S. Air Force as part of the Nevada Test and Training Range or the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office (NNSA/NSO) as part of the Nevada Test Site (NTS). The survey was flown at an approximate ground speed of 70 knots (36 meters per second), at a nominal altitude of 150 ft (46 m) above ground level, along a set of parallel flight lines spaced 250 ft (76 m) apart. The flight lines were oriented in a north-south trajectory. The survey was conducted by the DOE NNSA/NSO Remote Sensing Laboratory-Nellis, which is located in Las Vegas, Nevada. The aerial survey was conducted at the request of the DOE Office of Civilian Radioactive Waste Management. The primary contaminant of concern was identified by YMP personnel as cesium-137 ( 137 Cs). Due to the proposed land withdrawal area's proximity to the historical Nuclear Rocket Development Station (NRDS) facilities located on the NTS, the aerial survey system required sufficient sensitivity to discriminate between dispersed but elevated 137 Cs levels from those normally encountered from worldwide fallout. As part of that process, the survey also measured and mapped the exposure-rate levels that currently existed within the survey area. The inferred aerial exposure rates of the natural terrestrial background radiation varied from less than 3 to 22 microroentgens per hour. This range of exposure rates was primarily due to the surface

A project: 'Radiological protection in radiology', IAEA - Universidad Central de Venezuela

International Nuclear Information System (INIS)

Diaz, A.R.; Salazar, G.; Fermin, R.; Gonzalez, M.

2001-01-01

For several years a reference center of the UCV has been working on the project VEN/9/007 on dose reduction in diagnostic radiology sponsored by the IAEA. The dose and quality image was evaluated for different types of radiological study (conventional radiology, CT, mammography, interventional radiology) in different facilities at Caracas and others regions of the Venezuela. TL dosimeters were used to assess dose and reduction in dose. Based on the recommendations given by CEC documents on diagnostic quality criteria, a quality control program in radiological protection of patients and staff has been developed, for example: Pilot study by using TLD in personnel radiation monitoring. Comparative study between high and low kVp in chest. Evaluation and dose reduction in chest pediatric. Reduction of radiation dose in studies of billiards via Quality Image and reduction of the dose in studies of colon by enema. Radiation dose of staff in fluoroscopy procedures. Evaluation and dose reduction in dental radiography in public Institutions. A mammography accreditation program for Venezuela, applied to public hospitals. (author)

Neutron area monitoring at storage bunkers of density/moisture gauges

Energy Technology Data Exchange (ETDEWEB)

Garcia-Fuste, M.J. [Grup de Fisica de les Radiacions. Universitat Autonoma de Barcelona (UAB), Edifici Cc, E-08193 Bellaterra (Spain); Amgarou, K., E-mail: khalil.amgarou@uab.ca [Grup de Fisica de les Radiacions. Universitat Autonoma de Barcelona (UAB), Edifici Cc, E-08193 Bellaterra (Spain); Garcia-Orellana, J.; Domingo, C. [Grup de Fisica de les Radiacions. Universitat Autonoma de Barcelona (UAB), Edifici Cc, E-08193 Bellaterra (Spain)

2010-12-15

Previous studies remarked the need of performing neutron personal dosimetry, together with gamma dosimetry, when using portable density/moisture gauges that are normally equipped with gamma and neutron sources. The convenience of our Poly-Allyl-Diglycol-Carbonate (PADC) based neutron dosimeter to perform long-term routine survey of all workers involved in the transport, maintenance and usage of these gauges was also corroborated in the past. This complete dosimetric control offers the possibility to quantify simultaneously individual neutron and gamma doses of workers operating such devices, especially in the most frequent cleaning and maintenance (shutter lubrication) operations of the gauges or in emergency situations that may lead to radiological risk of the persons involved. Another aspect to be considered, from the radioprotection point of view, is the optimization of the occupational and public exposure in the storage bunkers of the gauges. In this work, three storage bunkers, located at three different factories of the PAYMA Cotas S.A.U company, have been monitored for three months using several units of our PADC based neutron dosimeter. Special care has been taken to study also offices near the bunkers with high occupancy rates and passage zones, such as toilets and access areas. Results for all monitored points inside and around the three storage bunkers are presented. Neutron doses inside the bunkers could be relatively high depending on the specific conditions (geometry configuration, localization and shielding composition) of the considered bunker and the number of portable gauges stored.

Neutron area monitoring at storage bunkers of density/moisture gauges

International Nuclear Information System (INIS)

Garcia-Fuste, M.J.; Amgarou, K.; Garcia-Orellana, J.; Domingo, C.

2010-01-01

Previous studies remarked the need of performing neutron personal dosimetry, together with gamma dosimetry, when using portable density/moisture gauges that are normally equipped with gamma and neutron sources. The convenience of our Poly-Allyl-Diglycol-Carbonate (PADC) based neutron dosimeter to perform long-term routine survey of all workers involved in the transport, maintenance and usage of these gauges was also corroborated in the past. This complete dosimetric control offers the possibility to quantify simultaneously individual neutron and gamma doses of workers operating such devices, especially in the most frequent cleaning and maintenance (shutter lubrication) operations of the gauges or in emergency situations that may lead to radiological risk of the persons involved. Another aspect to be considered, from the radioprotection point of view, is the optimization of the occupational and public exposure in the storage bunkers of the gauges. In this work, three storage bunkers, located at three different factories of the PAYMA Cotas S.A.U company, have been monitored for three months using several units of our PADC based neutron dosimeter. Special care has been taken to study also offices near the bunkers with high occupancy rates and passage zones, such as toilets and access areas. Results for all monitored points inside and around the three storage bunkers are presented. Neutron doses inside the bunkers could be relatively high depending on the specific conditions (geometry configuration, localization and shielding composition) of the considered bunker and the number of portable gauges stored.

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

International Nuclear Information System (INIS)

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

1984-01-01

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

Survey of radiological contaminants in the near-shore environment at the Hanford Site 100-N Area reactor

International Nuclear Information System (INIS)

Van Verst, S.P.; Albin, C.L.; Patton, G.W.; Blanton, M.L.; Poston, T.M.; Cooper, A.T.; Antonio, E.J.

1998-09-01

Past operations at the Hanford Site 100-N Area reactor resulted in the release of radiological contaminants to the soil column, local groundwater, and ultimately to the near-shore environment of the Columbia River. In September 1997, the Washington State Department of Health (WDOH) and the Hanford Site Surface Environmental Surveillance Project (SESP) initiated a special study of the near-shore vicinity at the Hanford Site's retired 100-N Area reactor. Environmental samples were collected and analyzed for radiological contaminants ( 3 H, 90 Sr, and gamma/ emitters), with both the WDOH and SESP analyzing a portion of the samples. Samples of river water, sediment, riverbank springs, periphyton, milfoil, flying insects, clam shells, and reed canary grass were collected. External exposure rates were also measured for the near-shore environment in the vicinity of the 100-N Area. In addition, samples were collected at background locations above Vernita Bridge

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

International Nuclear Information System (INIS)

Meyer, H.; Stippler, R.

2001-01-01

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

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

International Nuclear Information System (INIS)

Meyer, H.; Stippler, R.

2000-01-01

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

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

International Nuclear Information System (INIS)

Meyer, H.; Stippler, R.

2002-01-01

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

Online dose rate monitoring: Better information by using the IRMA concept (Integral Radiological Multidetector Arrays)

International Nuclear Information System (INIS)

Genrich, V.

1989-01-01

A new GM detector system has been developed for online environmental monitoring. The approach is unorthodox, but simple: A) Take a set of radiological probes and feed all their information to an 'intelligent' front-end. B) Elaborate some algorithms, so that the system will give out just one gamma dose rate (running over more than nine decades). C) If necessary, associate some additional sensors, and the system will exhibit better discriminating qualities for the detection of artificial nuclides in the environment. (orig.)

Design of movable fixed area γ dose rate monitor

International Nuclear Information System (INIS)

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

2005-10-01

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

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

International Nuclear Information System (INIS)

1992-11-01

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

Monitoring of the radiological environmental impact of the AREVA site of Tricastin; Suivi de l'impact radiologique environnemental des activites du site AREVA du Tricastin

Energy Technology Data Exchange (ETDEWEB)

Mercat, C.; Brun, F.; Florens, P.; Petit, J. [AREVA NC Pierrelatte, Direction surete environnement du site du Tricastin, 26 (France); Garnier, F. [EURODIF Production, Direction qualite securite surete environnement, 26 (France); Devin, P. [AREVA NC Pierrelatte, Direction surete, sante, securite, environnement, 26 (France)

2010-06-15

Set up at the beginning of the site's operations, in 1962, the monitoring of the radiological environmental impact of the AREVA site of Tricastin has evolved over time to meet more specifically the multiple objectives of environmental monitoring: to prove the respect of the commitments required by the authorities, to be able to detect a dysfunction in the observed levels, to enable the assessment of impacts of industrial activities, to ensure the balance between environmental quality and the use made by the local population and to inform the public of the radiological state of the environment. Thousands of data were acquired on the radioactivity of all environmental compartments as well as on the functioning of local ecosystems. Today, the Network of Environmental Monitoring of AREVA Tricastin goes beyond the requirements of routine monitoring to provide innovative solutions for monitoring the radioactivity (especially for uranium) in the environment. (author)

Radiological protection of populations in contaminated areas: synthesis of tools, concepts and methods elaborated in the ETHOS project

International Nuclear Information System (INIS)

Lepicard, S.; Lochard, J.; Schneider, T.

2004-01-01

The ETHOS project has been implemented in Belarus from 1996 to 2001. This report addresses several issues concerning the monitoring of radioactivity of the environment and of persons, and its modalities: organization of measurement devices, restitution of measurements, formatting and exploitation of results by different actors in order to develop strategies adapted to a contaminated environment. Thus, the report discusses the methodological fundamentals, the common information base on a radiological situation, and modalities for information exchange, formatting and processing. Then, it addresses the articulation between individual and public actions in improvement strategies (monitoring of local product quality with example of milk, children health monitoring), and the issue of the management of radioactive wastes in household activities

Results of the radiological environmental monitoring network in Cantabria, Spain

International Nuclear Information System (INIS)

Soto, J.; Rodenas, C.; Gomez, J.; Quindos, L.S.; Fernandez, P.L.

1997-01-01

The Medical Physics Department in the University of Cantabria, Spain as member belonging to the radiological environmental Monitoring Network has been carried out a series of measures about radioactive elements in air, rain water and soil. This report shows the methodology used and the results obtained in the measurement of the gross-alpha and gross beta activities. 90S r and gamma spectrometry in atmospheric aerosols; the activity of 131I in air; the gross-beta activity 90 Sr and gamma spectrometry in rain water and dry deposition: and the activity of 90S r gamma spectrometer in soils. The average values of the gross-alpha and gross beta activities in air has been 4 x 10 -5 and 32 x10 -5B q/m 3, respectively. The concentration of 131I has been inferior to the limit of detection in the whole of measurements. Finally, has been found small concentrations of 90S r and the 137C s in soils samples

Clay as Thermoluminescence Dosemeter in diagnostic Radiology ...

African Journals Online (AJOL)

This paper reports the investigation of the basic thermoluminescence properties of clay at x-rays in the diagnostic radiology range, including dose monitoring in abdominal radiography. Clay sourced from Calabar, Nigeria, was tested for thermoluminescence response after irradiation at diagnostic radiology doses, including ...

Radiological Worker Training: Radiological Worker 2 lesson plans

International Nuclear Information System (INIS)

1992-10-01

Upon completion of this g course, the participant will have the knowledge to work safely in areas controlled for a radiological purposes using proper radiological practices. The participant will be able toidentify the fundamentals of radiation, radioactive material and radioactive contamination includes identify the three basic particles of an atom, define ionization, define ionizing radiation, radioactive material and radioactive contamination, distinguish between ionizing radiation and non-ionizing radiation, define radioactivity and radioactive half-life

Radiological protection aspects regarding to assistance of the cesium-137 radiation accident victims in Goiania; Aspectos de protecao radiologica no atendimento as vitimas do acidente radiologico com cesio-137 em Goiania

Energy Technology Data Exchange (ETDEWEB)

Hunt, John Graham; Oliveira Filho, Denizart Silveira de; Rabelo, Paulo Ney Pamplona [Instituto de Radioprotecao e Dosimetria (IRD), Rio de Janeiro, RJ (Brazil)

1997-12-31

The radiological protection measures taken in the general hospital of Goiania (HGG/INAMPS) and in the FEBEM institution, due to the accident involving Cesium-137 are described, as well as the work of the IRD personnel in the areas of: radiological protection of the medical and auxiliary staff, contamination control of the ward, radiological monitoring of the patients, waste management, personnel and area decontamination and patient transportation. (author) 4 refs., 11 figs.; e-mail: marcos at omega.lncc.br

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.

Model to predict radiological consequences of transportation accidents involving dispersal of radioactive material in urban areas

International Nuclear Information System (INIS)

Taylor, J.M.; Daniel, S.L.

1978-01-01

The analysis of accidental releases of radioactive material which may result from transportation accidents in high-density urban areas is influenced by several urban characteristics which make computer simulation the calculational method of choice. These urban features fall into four categories. Each of these categories contains time- and location-dependent parameters which must be coupled to the actual time and location of the release in the calculation of the anticipated radiological consequences. Due to the large number of dependent parameters a computer model, METRAN, has been developed to quantify these radiological consequences. Rather than attempt to describe an urban area as a single entity, a specific urban area is subdivided into a set of cells of fixed size to permit more detailed characterization. Initially, the study area is subdivided into a set of 2-dimensional cells. A uniform set of time-dependent physical characteristics which describe the land use, population distribution, traffic density, etc., within that cell are then computed from various data sources. The METRAN code incorporates several details of urban areas. A principal limitation of the analysis is the limited availability of accurate information to use as input data. Although the code was originally developed to analyze dispersal of radioactive material, it is currently being evaluated for use in analyzing the effects of dispersal of other hazardous materials in both urban and rural areas

Recommendations of the AIRP-SEFP-SFPR working group individual radiological monitoring document-dosimetric data base

International Nuclear Information System (INIS)

Litido, M.; Busuoli, G.; Pelliccioni, M.; Iniiguez Saez, J.; Dollo, R.

1996-01-01

On the initiative of the chairmen of the three radiation protection societies (Italian, French, Spanish), it has been decided to extend the study carried out at TAORMINA (Sicily, Italy) joint conference on the harmonization of radiation protection practices. In order to formulate proposals on this topic, a working group was created at the end of 1993 made up of representatives of each society, with the objective of harmonizing the individual radiological monitoring documents and methods of recording and managing dosimetric information in data banks. (author)

Radiological effluent and onsite area monitoring report for the Nevada Test Site (January 1985 through December 1985)

International Nuclear Information System (INIS)

Gonzalez, D.A.

1986-09-01

This report documents the environmental surveillance program at the Nevada Test Site as conducted by the Department of Energy (DOE) onsite radiological safety contractor from January 1985 through December 1985. The results and evaluations of measurements of radioactivity in air and water, and of direct gamma radiation exposure rates are presented. Relevancy to DOE concentration guides (CG'S) is established. This report was formerly titled ''Environmental Surveillance Report for the Nevada Test Site.''

Database for the registration of radiological surveillance in radioactive facilities of CIEMAT; Base de datos para el registro de vigilancias radiologicas en las instalaciones radiactivas del CIEMAT

Energy Technology Data Exchange (ETDEWEB)

Marquez Fernandez, J. L.; Carroza Garcia, J. A.; Perez-Cejuela, P.; Vico Ocon, A.; Alvarez Garcia, A.

2013-07-01

In the CIEMAT There are 21 Radiation Facilities in which according to the Radiation Protection Manual must considered radiation hazards and / or contamination. The Radiological Protection Service according to this risk It establishes the classification and marking of areas and a monitoring plan that includes the type and extent of radiological periodicity. The information derived from this monitoring be registered and properly stored. Therefore, it has been completed the design of an application that allows technical experts record their actions and also consult records radiation monitoring tasks performed. (Author)

H-Area Seepage Basins groundwater monitoring report

International Nuclear Information System (INIS)

Thompson, C.Y.

1992-06-01

During first quarter 1992, tritium, nitrate, nonvolatile beta, total alpha-emitting radium (radium-224 and radium-226), gross alpha, antimony, mercury, lead, tetrachloroethylene, arsenic, and cadmium exceeded the US Environmental Protection Agency Primary Drinking Water Standards (PDWS) in groundwater samples from monitoring wells at the H-Area Seepage Basins (HASB) at the Savannah River Site. This report presents and discusses the groundwater monitoring results in the H-Area for first quarter 1992

Radiation protection and monitoring

International Nuclear Information System (INIS)

Thomas, P.

1982-01-01

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

Occupational Exposure to Diagnostic Radiology in Workers without Training in Radiation Safety

International Nuclear Information System (INIS)

Gaona, Enrique; Enriquez, Jesus G. Franco

2004-01-01

The physicians, technicians, nurses, and others involved in radiation areas constitute the largest group of workers occupationally exposed to man-made sources of radiation. Personnel radiation exposure must be monitored for safety and regulatory considerations, this assessment may need to be made over a period of one month or several months. The purpose of this study was to carry out an exploratory survey of occupational exposures associated with diagnostic radiology. The personnel dosimeters used in this study were thermoluminescent dosimeters (TLDs). The reported number of monitored workers was 110 of different departments of radiology of the Mexican Republic without education in radiation safety, included general fluoscopic/radiographic imaging, computed tomography and mammography procedures. Physicians and X-ray technologist in diagnostic radiology receive an average annual effective dose of 2.9 mSv with range from 0.18 to 5.64 mSv. The average level of occupational exposures is generally similar to the global average level of natural radiation exposure. The annual global per capita effective dose due to natural radiation sources is 2.4 mSv (UNSCEAR 2000 Report). There is not significant difference between average occupational exposures and natural radiation exposure for p < 0.05

Community Radiation Monitoring Program

International Nuclear Information System (INIS)

Cooper, E.N.

1993-05-01

The Community Radiation Monitoring Program (CRMP) is a cooperative effort between the US Department of Energy (DOE); the US Environmental Protection Agency (EPA); the Desert Research Institute (DRI), a division of the University and Community College System of Nevada and the Nuclear Engineering Laboratory of the University of Utah (UNEL). The twelfth year of the program began in the fall of 1991, and the work continues as an integral part of the DOE-sponsored long-term offsite radiological monitoring effort that has been conducted by EPA and its predecessors since the inception of nuclear testing at the Nevada Test Site (NTS). The program began as an outgrowth of activities that occurred during the Three Mile Island incident in 1979. The local interest and public participation that took place there were thought to be transferrable to the situation at the NTS, so, with adaptations, that methodology was implemented for this program. The CRMP began by enhancing and centralizing environmental monitoring and sampling equipment at 15 communities in the existing EPA monitoring network, and has since expanded to 19 locations in Nevada, Utah and California. The primary objectives of this program are still to increase the understanding by the people who live in the area surrounding the NTS of the activities for which DOE is responsible, to enhance the performance of radiological sampling and monitoring, and to inform all concerned of the results of these efforts. One of the primary methods used to improve the communication link with people in the potentially impacted area has been the hiring and training of local citizens as station managers and program representatives in those selected communities in the offsite area. These managers, active science teachers wherever possible, have succeeded, through their training, experience, community standing, and effort, in becoming a very visible, able and valuable asset in this link

A study of professional competence for radiological technology department students in Taiwan area

International Nuclear Information System (INIS)

Cheng Kai-Yuan; Hsieh Bor-Tsung; Huang W.

2005-01-01

Recently, so many medical institutions established and the increasing use of the high technological medical imaging equipment, it makes radiological technology become the main instrument for the medical diagnostic and radiation therapy. However, the medical radiological technologies play the important role to operate all the related radiological machines. If they do not use the machines adequately, it will increase the patients' radiation absorbed dose. Then, the whole society health may be influenced. Therefore, constructing the professional competence of the medical radiological technologists is an important course. The purpose of this research are: (1) to construct the index of professional competence with radiological technology students, (2) to discuss the professional competence for the graduates from the department of radiological technology to be the reference for the Ministry of Examination for the license test of radiological technologists, (3) to provide the direction of the radiological technology department development. (author)

Radiological Control Technician: Phase 1, Site academic training lesson plans

International Nuclear Information System (INIS)

1992-10-01

This volume provides lesson plans for training radiological control technicians. Covered here is basic radiological documentation, counting errors, dosimetry, environmental monitoring, and radiation instruments

River Corridor Project Workplace Air Monitoring Technical Basis

International Nuclear Information System (INIS)

MANTOOTH, D.S.

2001-01-01

This document provides the technical basis by which the workplace air monitoring and sampling program is operated in the River Corridor Project (RCP). Revision 2 addresses and incorporates changes in the air monitoring program drivers and implementing documents which occurred after the previous revision was issued. This revision also includes an additional RCP project to make Revision 2 applicable to the entire RCP. These changes occurred in the following areas: (1) Changes resulting from the conversion of the Hanford Site Radiological Control Manual (HSRCM-1) into the Project Hanford Radiological Control Manual (F-5173). HNF-5173 is now the implementing document for 10CFR835. (2) Changes resulting from the issue of new and revised Hanford Site implementing procedures. (3) Changes resulting from the issue of new and revised, as well as the cancellation of RCP implementing procedures. (4) Addition of the 200 Area Accelerated Deactivation Project (ADP). (5) Modification of some air sampling/monitoring locations to better meet the needs of facility operations. (6) Changes resulting from the RCP reorganization

Response of a neutron monitor area with TLDs pairs

Energy Technology Data Exchange (ETDEWEB)

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

2011-10-15

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

Quarterly environmental radiological survey summary: Third quarter 1994--100, 200, 300, and 600 Areas

International Nuclear Information System (INIS)

McKinney, S.M.

1994-11-01

This report provides a summary of the radiological surveys performed on waste disposal sites located at the Hanford Site. The Third Quarter 1994 survey results and the status of actions required from current and past reports and are summarized below: (1) All the routine environmental radiological surveys scheduled during July, August, and September 1994 were completed except for the D Island vent riser area. The surveys for the 200-W railways, spurs, and sidings were completed during this period after being delayed by equipment problems during the second quarter. (2) No Compliance Assessment Reports (CARs) were issued for sites found out of compliance with standards identified in WHC-CM-7-5, Environmental Compliance. (3) Two Surveillance Compliance/Inspection Reports (SCIRs) were closed during the Third Quarter of 1994. (4) Eleven open SCIRs had not been resolved

Radiologic considerations

International Nuclear Information System (INIS)

Judge, L.O.

1987-01-01

An increasing variety of imaging modalities as well as refinements of interventional techniques have led to a resurgence of radiologic interest and participation in urolithiasis management. Judicious selection of the diagnostic examination, close monitoring during the procedure, consultation with urologic colleagues, and a careful regard for radiation safety guidelines define the role of the radiologist in renal stone disease

Neutron monitoring for radiological protection

International Nuclear Information System (INIS)

Gibson, J.A.B.

1985-01-01

Neutron monitoring is a subject of increasing general interest and considerable attention is being paid to the development of improved techniques and methods for neutron monitoring. The Agency, therefore, considered it important to prepare a guide on the subject of neutron monitoring for radiation protection purposes. The present Manual is intended for those persons or authorities in Member States, particularly developing countries, who are responsible for the organization of neutron monitoring programmes and practical neutron monitoring. This Manual consequently, deals with topics such as neutron dosimetry, sources of neutrons and neutron detection as well as field instruments and operational systems used in this context

Aerial Radiological Surveys of the Las Vegas Strip and Adjacent Areas

International Nuclear Information System (INIS)

Hendricks, Thane; Reed, Michael

2008-01-01

As proficiency training for the Remote Sensing Laboratory's (RSL) Aerial Measuring System (AMS) radiological mapping mission, a survey team from RSL-Nellis conducted aerial radiological surveys of the Las Vegas Strip and adjacent areas on four separate occasions. The dates of the surveys were: December 11, 2006; December 26, 2007; December 31, 2007; and July 1, 2008. The AMS operation and appropriate law enforcement agencies selected the survey area as an appropriate urban location in which to exercise the AMS capability for mapping environmental radiation and searching for man-made radioactive sources. The surveys covered approximately 11 square miles. Each survey required a 2.5 hour-long flight, performed at an altitude of 300 ft above ground level (AGL), at a line spacing of 600 ft. Water line and test line flights were conducted over the Lake Mead and Government Wash areas in order to quantify the non-terrestrial background contributed by the aircraft, radon, and cosmic activity, and in order to determine the altitude-dependent air mass correction. The gamma data was collected by the AMS data acquisition system (REDAR V) using an array of twelve 2-inch x 4-inch x 16-inch sodium iodide (NaI) detectors flown on-board a twin-engine Bell 412 helicopter. One second gamma-energy spectral data were recorded continuously while in flight. This spectral data allows the system to distinguish between natural terrestrial background contributions and man-made radioisotope contributions. Spectral data can also be used to identify specific man-made radioactive isotopes. Data geo-locations were determined with a Real-Time Differential Global Positioning System (RDGPS). For the surveys occurring on December 26, 2007, and December 31, 2007, a neutron detection system was also flown. The neutron system consists of an array of eight moderated helium tubes, each cylindrical in nature measuring 6-feet in length with a diameter of 2-inches

Radiological Protection and Environmental Monitoring in Bolivia

International Nuclear Information System (INIS)

MartInez Pacheco, J.

1979-01-01

The paper describes the main activities of the Department of Radiological Protection, Nuclear Energy Commission of Bolivia. The following topics are covered: organization, environmental control of air, water, milk and plants, personal dosimetry, instrumentation and calibration, protection in uranium mines. Standard setting and international cooperation aspects are also presented

Quality control in dental diagnostic radiology : anomalous in the use of radiological equipment

International Nuclear Information System (INIS)

Alcaraz, M.; Martinez-Beneyto, Y.; Jodar, S.; Velasco, E.; Garcia-Vera, M. C.

2004-01-01

7,176 official quality control reports on dental diagnostic radiology were studied, relating to dental clinics located in 37 Spanish provinces covering 16 different autonomous Regions. The reports were issued as a result of the entry into force of Royal Decree 2071/1995 on quality control in General Diagnostic Radiology facilities, this Royal Decree was replaced by R. D. 1976/1999. The reports were writen by the UTPR (Technical Unit of Radiological Protection) Agsigma S. A. L., a company approved by the Nuclear Safety Council, and they correspond with the official reports issued during 1996-2001. This meants that a 5-year period has been monitored in order to observe the impacts of the establlishment of this legislation on quality control in intraoral dental diagnostic radiology facilities. The results show that 72.79% of the reports checked in 2001 would comply with the European Union's official recommendation (70 kVp, 8 mA> 1.5 mm of Al and 20 cm collimator length). Significant alterations have detected in a third (30.59%) of the radiological equipment. (Author) 36 refs

Operational characteristics of pediatric radiology: Image display stations

International Nuclear Information System (INIS)

Taira, R.K.

1987-01-01

The display of diagnostic images is accomplished in the UCLA Pediatric Radiology Clinical Radiology Imaging System (CRIS) using 3 different types of digital viewing stations. These include a low resolution station with six 512 x 512 monitors, a high resolution station with three 1024 x 1024 monitors, and a very high resolution workstation with two 2048 x 2048 monitors. The display stations provide very basic image processing manipulations including zoom and scroll, contrast enhancement, and contrast reversal. The display stations are driven by a computer system which is dedicated for clinical use. During times when the clinical computer is unavailable (maintenance or system malfunction), the 512 x 512 workstation can be switched to operate from a research PACS system in the UCLA Image Processing Laboratory via a broadband communication network. Our initial clinical implementation involves digital viewing for pediatric radiology conferences. Presentation of inpatient cases use the six monitor 512 x 512 multiple viewing station. Later stages of the clinical implementation involve the use of higher resolution displays for the purpose of primary diagnosis from video displays

Aerial radiological survey of the area surrounding the Portsmouth Gaseous Diffusion Plant, Portsmouth, Ohio

International Nuclear Information System (INIS)

1979-09-01

An airborne radiological survey was conducted in July 1976. It was centered on the Portsmouth Gaseous Diffusion Plant. Two areas were surveyed: one 35 km 2 and the other 16 km 2 . Using Nal(Tl) scintillation detectors, measurements were made of the terrestrial gamma radiation over the areas with a series of north-south flight lines. The processed data indicated that on-site radioactivity was due to nuclear matterials currently or previously handled, processed, or stored. Off-site activities were found to be due wholly to the naturally occurring 40 K, the 238 U chain, and thorium chain gamma emitters

Yucca Mountain Site Characterization Project Summary of Socioeconomic Data Analysis Conducted in Support of the Radiological Monitoring Program, During FY 2001

International Nuclear Information System (INIS)

L.K. Roe

2001-01-01

This report is a summary of socioeconomic data analyses conducted in support of the Radiological Monitoring Program during fiscal year 2001. Socioeconomic data contained in this report include estimates for the years 2000 and 2001 of the resident population in the vicinity of Yucca Mountain. The estimates presented in this report are based on selected Census 2000 statistics, and housing and population data that were acquired and developed in accordance with LP-RS-00 1 Q-M and 0, Scientific Investigation of Economic, Demographic, and Agricultural Characteristics in the Vicinity of Yucca Mountain. The study area from which data were collected is delineated by a radial grid, consisting of 160 grid cells, that is suitable for evaluating the pathways and potential impacts of a release of radioactive materials to the environment within a distance of 84 kilometers from Yucca Mountain. Data are presented in a tabular format by the county, state, area, and grid cell in which housing units, households, and resident population are located. Also included is a visual representation of the distribution of the 2000 residential populations within the study area, showing Census 2000 geography, county boundaries, and taxing district boundaries for selected communities

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

SITE GENERATED RADIOLOGICAL WASTE HANDLING SYSTEM DESCRIPTION DOCUMENT

Energy Technology Data Exchange (ETDEWEB)

S. C. Khamankar

2000-06-20

The Site Generated Radiological Waste Handling System handles radioactive waste products that are generated at the geologic repository operations area. The waste is collected, treated if required, packaged for shipment, and shipped to a disposal site. Waste streams include low-level waste (LLW) in solid and liquid forms, as-well-as mixed waste that contains hazardous and radioactive constituents. Liquid LLW is segregated into two streams, non-recyclable and recyclable. The non-recyclable stream may contain detergents or other non-hazardous cleaning agents and is packaged for shipment. The recyclable stream is treated to recycle a large portion of the water while the remaining concentrated waste is packaged for shipment; this greatly reduces the volume of waste requiring disposal. There will be no liquid LLW discharge. Solid LLW consists of wet solids such as ion exchange resins and filter cartridges, as-well-as dry active waste such as tools, protective clothing, and poly bags. Solids will be sorted, volume reduced, and packaged for shipment. The generation of mixed waste at the Monitored Geologic Repository (MGR) is not planned; however, if it does come into existence, it will be collected and packaged for disposal at its point of occurrence, temporarily staged, then shipped to government-approved off-site facilities for disposal. The Site Generated Radiological Waste Handling System has equipment located in both the Waste Treatment Building (WTB) and in the Waste Handling Building (WHB). All types of liquid and solid LLW are processed in the WTB, while wet solid waste from the Pool Water Treatment and Cooling System is packaged where received in the WHB. There is no installed hardware for mixed waste. The Site Generated Radiological Waste Handling System receives waste from locations where water is used for decontamination functions. In most cases the water is piped back to the WTB for processing. The WTB and WHB provide staging areas for storing and shipping LLW

SITE GENERATED RADIOLOGICAL WASTE HANDLING SYSTEM DESCRIPTION DOCUMENT

International Nuclear Information System (INIS)

S. C. Khamankar

2000-01-01

The Site Generated Radiological Waste Handling System handles radioactive waste products that are generated at the geologic repository operations area. The waste is collected, treated if required, packaged for shipment, and shipped to a disposal site. Waste streams include low-level waste (LLW) in solid and liquid forms, as-well-as mixed waste that contains hazardous and radioactive constituents. Liquid LLW is segregated into two streams, non-recyclable and recyclable. The non-recyclable stream may contain detergents or other non-hazardous cleaning agents and is packaged for shipment. The recyclable stream is treated to recycle a large portion of the water while the remaining concentrated waste is packaged for shipment; this greatly reduces the volume of waste requiring disposal. There will be no liquid LLW discharge. Solid LLW consists of wet solids such as ion exchange resins and filter cartridges, as-well-as dry active waste such as tools, protective clothing, and poly bags. Solids will be sorted, volume reduced, and packaged for shipment. The generation of mixed waste at the Monitored Geologic Repository (MGR) is not planned; however, if it does come into existence, it will be collected and packaged for disposal at its point of occurrence, temporarily staged, then shipped to government-approved off-site facilities for disposal. The Site Generated Radiological Waste Handling System has equipment located in both the Waste Treatment Building (WTB) and in the Waste Handling Building (WHB). All types of liquid and solid LLW are processed in the WTB, while wet solid waste from the Pool Water Treatment and Cooling System is packaged where received in the WHB. There is no installed hardware for mixed waste. The Site Generated Radiological Waste Handling System receives waste from locations where water is used for decontamination functions. In most cases the water is piped back to the WTB for processing. The WTB and WHB provide staging areas for storing and shipping LLW

Moisture Monitoring at Area G, Technical Area 54, Los Alamos National Laboratory, 2016 Status Report

Energy Technology Data Exchange (ETDEWEB)

Levitt, Daniel Glenn [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Birdsell, Kay Hanson [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Jennings, Terry L. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); French, Sean B. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2017-01-17

Hydrological characterization and moisture monitoring activities provide data required for evaluating the transport of subsurface contaminants in the unsaturated and saturated zones beneath Area G, and for the Area G Performance Assessment and Composite Analysis. These activities have been ongoing at Area G, Technical Area 54 of the Los Alamos National Laboratory since waste disposal operations began in 1957. This report summarizes the hydrological characterization and moisture monitoring activities conducted at Area G. It includes moisture monitoring data collected from 1986 through 2016 from numerous boreholes and access tubes with neutron moisture meters, as well as data collected by automated dataloggers for water content measurement sensors installed in a waste disposal pit cover, and buried beneath the floor of a waste disposal pit. This report is an update of a nearly identical report by Levitt et al., (2015) that summarized data collected through early 2015; this report includes additional moisture monitoring data collected at Pit 31 and the Pit 38 extension through December, 2016. It also includes information from the Jennings and French (2009) moisture monitoring report and includes all data from Jennings and French (2009) and the Draft 2010 Addendum moisture monitoring report (Jennings and French, 2010). For the 2015 version of this report, all neutron logging data, including neutron probe calibrations, were investigated for quality and pedigree. Some data were recalculated using more defensible calibration data. Therefore, some water content profiles are different from those in the Jennings and French (2009) report. All of that information is repeated in this report for completeness. Monitoring and characterization data generally indicate that some areas of the Area G vadose zone are consistent with undisturbed conditions, with water contents of less than five percent by volume in the top two layers of the Bandelier tuff at Area G. These data also

Eye lens monitoring for interventional radiology personnel: dosemeters, calibration and practical aspects of Hp(3) monitoring. A 2015 review

International Nuclear Information System (INIS)

Carinou, Eleftheria; Ferrari, Paolo; Bjelac, Olivera Ciraj; Gingaume, Merce; Merce, Marta Sans; O’Connor, Una

2015-01-01

A thorough literature review about the current situation on the implementation of eye lens monitoring has been performed in order to provide recommendations regarding dosemeter types, calibration procedures and practical aspects of eye lens monitoring for interventional radiology personnel. Most relevant data and recommendations from about 100 papers have been analysed and classified in the following topics: challenges of today in eye lens monitoring; conversion coefficients, phantoms and calibration procedures for eye lens dose evaluation; correction factors and dosemeters for eye lens dose measurements; dosemeter position and influence of protective devices. The major findings of the review can be summarised as follows: the recommended operational quantity for the eye lens monitoring is H p (3). At present, several dosemeters are available for eye lens monitoring and calibration procedures are being developed. However, in practice, very often, alternative methods are used to assess the dose to the eye lens. A summary of correction factors found in the literature for the assessment of the eye lens dose is provided. These factors can give an estimation of the eye lens dose when alternative methods, such as the use of a whole body dosemeter, are used. A wide range of values is found, thus indicating the large uncertainty associated with these simplified methods. Reduction factors from most common protective devices obtained experimentally and using Monte Carlo calculations are presented. The paper concludes that the use of a dosemeter placed at collar level outside the lead apron can provide a useful first estimate of the eye lens exposure. However, for workplaces with estimated annual equivalent dose to the eye lens close to the dose limit, specific eye lens monitoring should be performed. Finally, training of the involved medical staff on the risks of ionising radiation for the eye lens and on the correct use of protective systems is strongly recommended. (review)

Guide for environmental radiological surveillance at ERDA installations

International Nuclear Information System (INIS)

Corley, J.P.; Denham, D.H.; Michels, D.E.; Olsen, A.R.; Waite, D.A.

1977-03-01

This Guide is intended to: Provide recommended methods, procedures, and performance criteria to bring greater comparability to ERDA environmental monitoring and reporting systems; provide ERDA management, particularly the Headquarters' Division of Safety, Standards, and Compliance (SSC) and field offices, with a broad review of accepted radiological surveillance practices for use in the evaluation of environmental surveillance programs at ERDA facilities; and delineate the capabilities and limitations of the various environmental monitoring systems for radioactivity currently used at ERDA sites, including technical areas where there is either an inadequate basis for procedural selection or where further developmental work may be warranted. The discussion of equipment, measurement techniques, and quality control procedures, although believed to represent current technology, is subject to continuing change as technological improvements become available

Technological and operational structure of the National Automatic Network for Environmental Radiological Monitoring (RENAMORA); Estructura tecnologica y operativa de la Red Nacional Automatica de Monitoreo Radiologico Ambiental RENAMORA

Energy Technology Data Exchange (ETDEWEB)

Martinez G, E.; Lopez G, M.; Aguirre G, J.; Fabian O, R.; Hernandez A, Y., E-mail: elias.martinez@cnsns.gob.mx [Comision Nacional de Seguridad Nuclear y Salvaguardias, Dr. Barragan 779, Col. Narvarte, 03020 Ciudad de Mexico (Mexico)

2015-09-15

The Comision Nacional de Seguridad Nuclear y Salvaguardias (CNSNS) in Mexico is a decentralized body, under the Secretaria de Energia whose main mission is to ensure that activities involving nuclear and radioactive materials as well as ionizing radiation sources are carried out with maximum security, considering the current technological developments. In order to monitor the levels of environmental radiation to which the population is exposed, the CNSNS has established a series of radiological monitoring programs that allow characterize the environmental radiation levels in each zone or region in the country; to identify the occurrence of natural or artificial radiological events, such as nuclear tests and accidents in radioactive or nuclear facilities. The National Automatic Network for Environmental Radiological Monitoring (RENAMORA) project was initiated with the support of the IAEA through MEX9/049 project and its purpose is to have a network of instruments that automatically and in real time, transmit information of the gamma radiological environmental status of the national territory and changes occurring in it. This network provides data such as the speed of ambient dose equivalent, temperature and humidity in different regions of the country. The network is composed of 92 stations that are distributed throughout the national territory. The structure of the stations has evolved since its inception, now allowing detection tasks, data transmission and managing them remotely from the main server, which is located in the CNSNS, which is performed a statistical dose for each monitoring station. Each monitoring station is formed in its current structure by a probe detection of gamma radiation, a communication module and associated electronics, a mini Web server DataGATE, a cellular modem and an interface converter. (Author)

Regional radiological observations of the environment

International Nuclear Information System (INIS)

2014-11-01

After having recalled the objective of regional radiological observations (establishment of an updated referential of radioactivity levels in some parts of the environment which are typical of the concerned territory), and indicated the three main steps of these observations (definition of a methodology which may differ from one territory to the other, sampling and analysis, assessment of the radiological status of the studied territory), this report presents a methodology which can be applied to big rivers and predominantly agricultural territories. The radiological observations of different areas are reported (Val de Loire, Rhone valley, areas of persistence like mountains, or mining areas). Maps indicate the sampling location and the analysed products (food, soil, plants) and report of the ground or aquatic environment analysis, or available data and sampling strategy are given. The New Caledonia radiological observation is also reported

Routine environmental monitoring schedule, calendar year 1997

Energy Technology Data Exchange (ETDEWEB)

Markes, B.M., Westinghouse Hanford

1996-12-10

This document provides the Environmental Restorations Contractor (ERC) and the Project Hanford Management Contractor.(PHMC) a schedule in accordance with the WHC-CM-7-5, Environmental Compliance` and BHI- EE-02, Environmental Requirements, of monitoring and sampling routines for the Near-Field Monitoring (NFM) program during calendar year (CY) 1997. Every attempt will be made to consistently follow this schedule; any deviation from this schedule will be documented by an internal memorandum (DSI) explaining the reason for the deviation. The DSI will be issued by the scheduled performing organization and directed to Near-Field Monitoring. The survey frequencies for particular sites are determined by the technical judgment of Near- Field Monitoring and may depend on the site history, radiological status, use, and general conditions. Additional surveys may be requested at irregular frequencies if conditions warrant. All radioactive wastes sites are scheduled to be surveyed at least annually. Any newly discovered wastes sites not documented by this schedule will be included in the revised schedule for CY 1998. The outside perimeter road surveys of 200 East and West Area and the rail survey from the 300 Area to Columbia Center will be performed in the year 2000 per agreement with Department of Energy. Richland Field Office. This schedule does not discuss staffing needs, nor does it list the monitoring equipment to be used in completing specific routines. Personnel performing routines to meet this schedule shall communicate any need for assistance in completing these routines to Radiological Control management and Near-Field Monitoring. After each routine survey is completed, a copy of the survey record, maps, and data sheets will be forwarded to Near-Field Monitoring. These routine surveys will not be considered complete until this documentation is received. At the end of each month, the ERC and PHMC radiological control organizations shall forward a copy of the Routine

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

Energy Technology Data Exchange (ETDEWEB)

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

2017-08-30

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

Groundwater Quality Sampling and Analysis Plan for Environmental Monitoring Waste Area Grouping 6 at Oak Ridge National Laboratory. Environmental Restoration Program

International Nuclear Information System (INIS)

1995-09-01

This Sampling and Analysis Plan addresses groundwater quality sampling and analysis activities that will be conducted in support of the Environmental Monitoring Plan for Waste Area Grouping (WAG) 6. WAG 6 is a shallow-burial land disposal facility for low-level radioactive waste at the Oak Ridge National Laboratory, a research facility owned by the US Department of Energy and managed by Martin Marietta Energy Systems, Inc. (Energy Systems). Groundwater sampling will be conducted by Energy Systems at 45 wells within WAG 6. The samples will be analyzed for various organic, inorganic, and radiological parameters. The information derived from the groundwater quality monitoring, sampling, and analysis will aid in evaluating relative risk associated with contaminants migrating off-WAG, and also will fulfill Resource Conservation and Recovery Act (RCRA) interim permit monitoring requirements. The sampling steps described in this plan are consistent with the steps that have previously been followed by Energy Systems when conducting RCRA sampling

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

Radiological Worker Training: Radiological Worker 1 lesson plans

International Nuclear Information System (INIS)

1992-10-01

Upon completion of this training course, the participant will have the knowledge to work safely in areas controlled for radiological purposes using proper radiological practices. Upon completion of this unit the participant will be able to identify the fundamentals of radiation, radioactive material and radioactive contamination. The participant will be able to select the correct response from a group of responses which verifies his/her ability to: Define ionizing radiation, radioactive material and radioactive contamination and identify the units used to measure radiation and radioactivity

Radiological protection and quality control for diagnostic radiology in China

International Nuclear Information System (INIS)

Baorong, Yue

2008-01-01

Full text: There are 43,000 diagnostic departments, nearly 70,000 X-ray diagnostic facilities, 7,000 CT, 250 million for the annual total numbers of X-ray examinations, 120,000 occupationally exposed workers in diagnostic radiology. 'Basic standards for protection against ionizing radiation and for the safety of radiation sources' is promulgated on October, 2002. This basic standard follows the BSS. 'Rule on the administration of radio-diagnosis and radiotherapy', as a order of the Ministry of Health No. 46, is promulgated by Minister of Health on January 24, 2006. It includes general provisions, requirements and practice, establishment and approval of radio-diagnosis and radiotherapy services, safeguards and quality assurance, and so on. There are a series of radiological protection standards and quality control standards in diagnostic radiology, including 'radiological protection standard for the examination in X-ray diagnosis', 'radiological health protection standards for X-ray examination of child-bearing age women and pregnant women', 'radiological protection standards for the children in X-ray diagnosis', 'standards for radiological protection in medical X-ray diagnosis', 'specification for radiological protection monitoring in medical X-ray diagnosis', 'guide for reasonable application of medical X-ray diagnosis', 'general aspects for quality assurance in medical X-ray image of diagnosis', 'specification of image quality control test for the medical X-ray diagnostic equipment', 'specification of image quality assurance test for X-ray equipment for computed tomography', 'specification for testing of quality control in computed radiography (CR)' and 'specification for testing of quality control in X-ray mammography'. With the X-ray diagnostic equipment, there are acceptant tests, status tests and routing tests in large hospitals. It is poor for routing test in middle and smaller hospitals. CT is used widely in diagnostic radiology, however most workers in CT

Proposed procedure and analysis of results to verify the indicator of the product dose-area in radiology equipment

International Nuclear Information System (INIS)

Garcia Marcos, R.; Gallego Franco, P.; Sierra Diaz, F.; Gonzalez Ruiz, C.; Rodriguez Checa, M.; Brasa Estevez, M.; Gomez Calvar, R.

2013-01-01

The aim of this work is to establish a procedure to verify the value of the product dose-area showing certain teams of Radiology, with an alternative to the use of external transmission cameras. (Author)

An aerial radiological survey of the Fermi National Accelerator Laboratory and surrounding area, Batavia, Illinois

International Nuclear Information System (INIS)

Fritzsche, A.E.

1990-11-01

An aerial radiological gamma survey was conducted over the Fermi National Accelerator Laboratory during 1 through 6 June 1989. Flight lines at 150-foot altitude and 250-foot line spacings assured nearly 100% coverage. The terrestrial exposure at about 6 μR/h was nearly the same as that measured by the previous survey of this area (May 1977). Ten anomalous areas, mostly Na-22 and Mn-54, were detected within buildings and laboratories in the area. Although these locations have changed somewhat from the 1977 survey, the aerial data shows good agreement with the ground-based ion chamber and soil sample data. 7 refs., 15 figs., 1 tab

Groundwater Monitoring Plan for the Z-Area Saltstone Facility

International Nuclear Information System (INIS)

Wells, D.

2002-01-01

Groundwater monitoring has been conducted at the Z-Area Saltstone Disposal Facility since 1987. At that time, groundwater monitoring was not required by the industrial landfill regulations, but a modest monitoring program was required by the operating permit. In 1996 SRS proposed a program based on direct push sampling. This program called for biennial direct push sampling within 25 feet of each waste-containing cell with additional samples being taken in areas where excessive cracking had been observed. The direct push proposal was accepted by The South Carolina Department of Health and Environmental Control (SCDHEC). The Industrial Solid Waste Landfill Regulations were revised in 1998 and now include requirements for groundwater monitoring. The major elements of those regulations and their application at Z-Area are discussed. These are a point of compliance, groundwater protection standards, the groundwater monitoring system, sampling and analysis, and data evaluation and reporting

1980 annual radiological environmental report. Volume 2

International Nuclear Information System (INIS)

1980-01-01

This report describes the Radiological Environmental Monitoring Program conducted during 1980 in the vicinity of the Beaver Valley Power Station and the Shippingport Atomic Power Station. The Radiological Environmental Program consists of on-site sampling of water and gaseous effluents and off-site monitoring of water, air, river sediments, soils, food pathway samples, and radiation levels in the vicinity of the site. This report discusses the results of this monitoring during 1980. The environmental program outlined in the Beaver Valley Power Station Technical Specifications was followed throughout 1980. There were no radioactive liquid effluents released from the Shippingport Atomic Power Station since radioactive liquids are processed and re-cycled within the plant systems. The results of this environmental monitoring program show that Shippingport Atomic Power Station and Beaver Valley Power Station operations have not adversely affected the surrounding environment

Survey monitoring of environmental radioactivity in Daejeon area

Energy Technology Data Exchange (ETDEWEB)

Jun, Jae Shik.; Noh, Hyung Ah [Taejon Radiation Monitoring Station, Daejeon (Korea, Republic of)

2000-12-15

Systematic understanding of the distribution of environmental radioactivity and radiation level in Taejon, including Chungchung area, in normal circumstance, and rapid detection of unusual variation of the radiation level in emergency situation thereby ensure public safety are the objectives of this project to be carried out. This report summarizes and interprets environmental radiation/radioactivity monitoring data obtained at Taejon Radiation Monitoring Station in 2000. In conclusion, the natural environmental radiation level in Taejon area has been preserved as usual and no significant artificial enhancement in environmental radioactivity was observed during the course of this survey and monitoring period.

Survey monitoring of environmental radioactivity in Daejeon area

Energy Technology Data Exchange (ETDEWEB)

Jun, Jae Sik; Noh, Hyung Ah [Daejon Radiation Monitoring Station, Daejeon (Korea, Republic of)

2001-12-15

Systematic understanding of the distribution of environmental radioactivity and radiation level in Daejeon, including Chungchung area, in normal circumstance, and rapid detection of unusual variation of the radiation level in emergency situation thereby ensure public safety are the objectives of this project to be carried out. This report summarizes and interprets environmental radiation/radioactivity monitoring data obtained at Daejeon Radiation Monitoring Station in 2001. In conclusion, the natural environmental radiation level in Daejeon area has been preserved as usual and no significant artificial enhancement in environmental radioactivity was observed during the course of this survey and monitoring period.

Survey monitoring of environmental radioactivity in Daejeon area

Energy Technology Data Exchange (ETDEWEB)

Jun, Jae Shik; Noh, Hyung Ah [Daejon Radiation Monitoring Station, Daejeon (Korea, Republic of)

2002-12-15

Systematic understanding of the distribution of environmental radioactivity and radiation level in Daejeon, including Chungchung area, in normal circumstance, and rapid detection of unusual variation of the radiation level in emergency situation thereby ensure public safety are the objectives of this project to be carried out. This report summarizes and interprets environmental radiation/radioactivity monitoring data obtained at Daejeon Radiation Monitoring Station in 2002. In conclusion, the natural environmental radiation level in Daejeon area has been preserved as usual and no significant artificial enhancement in environmental radioactivity was observed during the course of this survey and monitoring period.

Survey monitoring of environmental radioactivity in Daejeon area

Energy Technology Data Exchange (ETDEWEB)

Jun, Jae Shik; Noh, Hyung Ah [Daejon Radiation Monitoring Station, Daejeon (Korea, Republic of)

2003-12-15

Systematic understanding of the distribution of environmental radioactivity and radiation level in Daejeon, including Chungchung area, in normal circumstance, and rapid detection of unusual variation of the radiation level in emergency situation thereby ensure public safety are the objectives of this project to be carried out. This report summarizes and interprets environmental radiation/radioactivity monitoring data obtained at Daejeon Radiation Monitoring Station in 2002. In conclusion, the natural environmental radiation level in Daejeon area has been preserved as usual and no significant artificial enhancement in environmental radioactivity was observed during the course of this survey and monitoring period.

Survey monitoring of environmental radioactivity in Daejeon area

International Nuclear Information System (INIS)

Jun, J. S.; Kim, K. S.

1998-01-01

Systematic understanding of the distribution of environmental radioactivity and radiation level in Taejon, including Chungchung area, in normal circumstance, and rapid detection of unusual variation of the radiation level in emergency situation thereby ensure public safety are the objectives of this project to be carried out. This report summarizes and interprets environmental radiation/radioactivity monitoring data obtained at Taejon Radiation Monitoring Station in 1998. In conclusion, the natural environmental radiation level in Taejon area has been preserved as usual and no significant artificial enhancement in environmental radioactivity was observed during the course of this survey and monitoring period

Survey monitoring of environmental radioactivity in Daejeon area

International Nuclear Information System (INIS)

Jun, Jae Sik; Noh, Hyung Ah

2001-12-01

Systematic understanding of the distribution of environmental radioactivity and radiation level in Daejeon, including Chungchung area, in normal circumstance, and rapid detection of unusual variation of the radiation level in emergency situation thereby ensure public safety are the objectives of this project to be carried out. This report summarizes and interprets environmental radiation/radioactivity monitoring data obtained at Daejeon Radiation Monitoring Station in 2001. In conclusion, the natural environmental radiation level in Daejeon area has been preserved as usual and no significant artificial enhancement in environmental radioactivity was observed during the course of this survey and monitoring period

Assessment of radiological risk in vicinity of former uranium mining areas in Poland

Energy Technology Data Exchange (ETDEWEB)

Ciupek, K.; Krajewski, P.; Kardas, M.; Suplinska, M. [Central Laboratory for Radiological Protection (Poland)

2014-07-01

The work carried out under the project NCBiR - 'Technologies Supporting Development of Safe Nuclear Power Engineering'; Task 3: Meeting the Polish nuclear power engineering's demand for fuel - fundamental aspects. Human activities related to the use of ionizing radiation and radioactive substances might cause exposure of the population and the environment. However, radiological risk assessment is mainly conducted only to human as an estimation of the effective dose being the sum of external and internal exposure whereas environmental protection assessment is more complex studies. The increased interest in recent years in this aspect and the ability to perform computer simulations contributed the development of models enabling assessment of exposure to certain organisms and estimation the concentrations of radionuclides in the various components of the environment. These models define a possible transition path of radionuclide in the atmosphere or waterways through their physical parameterization. The estimation of the content of radionuclides in plants, animals and human is possible by applying an existing risk assessment methodology. Models assessing human and environmental exposure from natural and artificial radionuclides, such as CROM, RESRAD, IMPACT or ERICA, come to be useful tools not only for researchers but also for regulatory authorities. This case study focused on the uranium mining areas (inactive mines and waste dumps) in the Giant Mountains (Karkonosze Mountains) in the south-west of Poland. On the basis of activity concentrations in samples of soil and mineral material from mine shafts, water samples from ponds, streams and small rivers and vegetation samples, an assessment of radiological impact of the former uranium mining areas was performed. The doses for reference group of inhabitants and biota in the vicinity of the former uranium mine were evaluated using IMPACT (EcoMetrix Inc.) model and ERICA tool. The variability and

Autonomous mobile robot for radiologic surveys

International Nuclear Information System (INIS)

Dudar, A.M.; Wagner, D.G.; Teese, G.D.

1994-01-01

An apparatus is described for conducting radiologic surveys. The apparatus comprises in the main a robot capable of following a preprogrammed path through an area, a radiation monitor adapted to receive input from a radiation detector assembly, ultrasonic transducers for navigation and collision avoidance, and an on-board computer system including an integrator for interfacing the radiation monitor and the robot. Front and rear bumpers are attached to the robot by bumper mounts. The robot may be equipped with memory boards for the collection and storage of radiation survey information. The on-board computer system is connected to a remote host computer via a UHF radio link. The apparatus is powered by a rechargeable 24-volt DC battery, and is stored at a docking station when not in use and/or for recharging. A remote host computer contains a stored database defining paths between points in the area where the robot is to operate, including but not limited to the locations of walls, doors, stationary furniture and equipment, and sonic markers if used. When a program consisting of a series of paths is downloaded to the on-board computer system, the robot conducts a floor survey autonomously at any preselected rate. When the radiation monitor detects contamination, the robot resurveys the area at reduced speed and resumes its preprogrammed path if the contamination is not confirmed. If the contamination is confirmed, the robot stops and sounds an alarm. 5 figures

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

Wide area monitoring study

International Nuclear Information System (INIS)

Wogman, N.A.; Holdren, G.R. Jr.

1999-01-01

Environmental sampling can be used to complement the safeguarding of nuclear material, especially in the detection of undeclared nuclear activities. Routine monitoring of nuclear installations has provided valuable information about the fate of key signature materials within different environmental settings. The approach collates information regarding the generation of individual radiochemical signatures within different nuclear processes, the potential for release of these signatures to the environment and, the chemical form and mobility of the signatures in environmental media along which the material could migrate. Meteorological, geological and hydrological information is used to determine where to sample, what to sample, and how often to sample to provide the greatest likelihood for detection. Multiple strategies can be used to implement wide area monitoring for safeguards purposes. The most complex, and expensive of these, involves establishing extensive networks of fixed location sampling sites. The sites would be operated continuously, and would be instrumented with automated sampling, analysis, and communication equipment to relay information regarding potential anomalies to control centers in near-real time. Alternative strategies can be used to supplement fixed location monitoring equipment, especially in regions that cannot support (financially or logistically) the fixed stations. Through combinations of these various strategies, using a variety of environmental media to monitor a region, we believe that a competent network, one with a quantifiable probability for detecting undeclared nuclear activities, can be designed. While this approach cannot and should not replace other inspection and monitoring activities, it can potentially contribute valuable information to an international safeguards system. (author)

Radiological protection Program of CDTN

International Nuclear Information System (INIS)

1983-01-01

Radiological protection program of CDTN, its purposes and rules, responsabilities, physical control, monitoring, personnel radiation protection, radiation sources and radioactive wastes control, emergency and accidents and siting are described. (C.M.) [pt

Development and application of portable mobile gamma spectrometry system (PMGSS) for realtime online radiological assessment

International Nuclear Information System (INIS)

Patil, S.S.; Padmanabhan, N.; Sharma, R.; Singh, R.; Pradeepkumar, K.S.

2008-01-01

A state of art mobile monitoring system is a prime requirement to combat the challenging radiological situations. In the event of any radiological/nuclear Emergencies an effective, realistic methodology of radiological measurements is an asset. In this context, a highly sensitive real-time online mobile monitoring system having features and provision to display the important parameters will be an essential tool in the course of radiological impact assessment. This paper, describes the efforts that has been made towards providing a useful Portable Mobile Gamma Spectrometry System (PMGSS) and developing applications so as to enhance its usefulness in quick radiological impact assessment and to initiate the proper countermeasures during any Nuclear/Radiological emergency situation in public domain. The system uses a NaI(Tl) detector, a global positioning system (GPS) and a laptop PC for storage, analysis and graphical representation of the acquired data. PMGSS is a highly sensitive, portable and reliable radiation monitoring equipment with capability of qualitative and quick estimation of the radioisotopes. The system was used for the mobile radiological mapping of Bangalore and Mumbai city and demonstrated its capability for use in environmental radiation monitoring during any radiological emergency requirement the results of which are presented here. (abstract)

Areas for US-India civilian nuclear cooperation to prevent/mitigate radiological events.

Energy Technology Data Exchange (ETDEWEB)

Balachandran, Gopalan; Forden, Geoffrey Ethan

2013-01-01

Over the decades, India and the United States have had very little formal collaboration on nuclear issues. Partly this was because neither country needed collaboration to make progress in the nuclear field. But it was also due, in part, to the concerns both countries had about the others intentions. Now that the U.S.-India Deal on nuclear collaboration has been signed and the Hyde Act passed in the United States, it is possible to recognize that both countries can benefit from such nuclear collaboration, especially if it starts with issues important to both countries that do not touch on strategic systems. Fortunately, there are many noncontroversial areas for collaboration. This study, funded by the U.S. State Department, has identified a number of areas in the prevention of and response to radiological incidents where such collaboration could take place.

Information support for analysing the radiological impact of areas affected by the Chernobyl accident

Energy Technology Data Exchange (ETDEWEB)

Shershakov, V.M.; Baranov, A.Yu.; Borodin, R.V.; Golubenkov, A.V.; Godko, A.M.; Kosykh, V.S.; Korenev, A.I.; Meleshkin, M.A. [SPA `Typhoon`, Obninsk (Russian Federation)

1996-09-01

The organisation and management of data banks generated using data from monitoring the radiological situation after the Chernobyl accident is of key importance to health care and rehabilitation in the contaminated areas. Measures following the accident were based on large scale studies involving analysis and prediction of radioactive contamination. These studies included measurements of radioactivity in air, soil and water, modelling and prediction of radionuclides transport and transformation. This required the development of a computer system RECASS (RadioEcological Analysis Support System) which is currently being developed in SPA ``Typhoon``. The main tasks of RECASS are to integrate data on existing characteristics of the environment, and data on air, soil, water and biota-contamination with numerical models that account for radionuclide behaviour in all environmental media, and with radiation dose formations that are based on geographic information system (GIS) principles. The data bank of the system includes the following data bases: a data base with measurement of radioactive contamination levels in environmental media (soil, air, water); a meteorological data base; and a data base with administrative and demographic data. A set of models for radionuclide transfer in various environments incorporated in the chain permits short or long-term predictions to be made. The results of implementing RECASS to reconstruct the time and space picture of contamination in the first days after the Chernobyl accident are presented. (Author).

Informatics support for analysing the radiological impact of areas affected by the Chernobyl accident

International Nuclear Information System (INIS)

Shershakov, V.M.; Baranov, A.Yu.; Borodin, R.V.; Golubenkov, A.V.; Godko, A.M.; Kosykh, V.S.; Korenev, A.I.; Meleshkin, M.A.

1996-01-01

The organisation and management of data banks generated using data from monitoring the radiological situation after the Chernobyl accident is of key importance to health care and rehabilitation in the contaminated areas. Measures following the accident were based on large scale studies involving analysis and prediction of radioactive contamination. These studies included measurements of radioactivity in air, soil and water, modelling and prediction of radionuclides transport and transformation. This required the development of a computer system RECASS (RadioEcological Analysis Support System) which is currently being developed in SPA ''Typhoon''. The main tasks of RECASS are to integrate data on existing characteristics of the environment, and data on air, soil, water and biota-contamination with numerical models that account for radionuclide behaviour in all environmental media and with radiation dose formations that are based on geographic information system (GIS) principles. The data bank of the system includes the following databases: a data base with measurement of radioactive contamination levels in environmental media (soil, air, water); a meteorological data base; and a data base with administrative and demographic data. A set of models for radionuclide transfer in various environments incorporated in the chain permits short or long-term predictions to be made. The results of implementing RECASS to reconstruct the time and space picture of contamination in the first days after the Chernobyl accident are presented. (Author)

Information support for analysing the radiological impact of areas affected by the Chernobyl accident

International Nuclear Information System (INIS)

Shershakov, V.M.; Baranov, A.Yu.; Borodin, R.V.; Golubenkov, A.V.; Godko, A.M.; Kosykh, V.S.; Korenev, A.I.; Meleshkin, M.A.

1996-01-01

The organisation and management of data banks generated using data from monitoring the radiological situation after the Chernobyl accident is of key importance to health care and rehabilitation in the contaminated areas. Measures following the accident were based on large scale studies involving analysis and prediction of radioactive contamination. These studies included measurements of radioactivity in air, soil and water, modelling and prediction of radionuclides transport and transformation. This required the development of a computer system RECASS (RadioEcological Analysis Support System) which is currently being developed in SPA ''Typhoon''. The main tasks of RECASS are to integrate data on existing characteristics of the environment, and data on air, soil, water and biota-contamination with numerical models that account for radionuclide behaviour in all environmental media, and with radiation dose formations that are based on geographic information system (GIS) principles. The data bank of the system includes the following data bases: a data base with measurement of radioactive contamination levels in environmental media (soil, air, water); a meteorological data base; and a data base with administrative and demographic data. A set of models for radionuclide transfer in various environments incorporated in the chain permits short or long-term predictions to be made. The results of implementing RECASS to reconstruct the time and space picture of contamination in the first days after the Chernobyl accident are presented. (Author)

Application of classical versus bayesian statistical control charts to on-line radiological monitoring

International Nuclear Information System (INIS)

DeVol, T.A.; Gohres, A.A.; Williams, C.L.

2009-01-01

False positive and false negative incidence rates of radiological monitoring data from classical and Bayesian statistical process control chart techniques are compared. The on-line monitoring for illicit radioactive material with no false positives or false negatives is the goal of homeland security monitoring, but is unrealistic. However, statistical fluctuations in the detector signal, short detection times, large source to detector distances, and shielding effects make distinguishing between a radiation source and natural background particularly difficult. Experimental time series data were collected using a 1' x 1' LaCl 3 (Ce) based scintillation detector (Scionix, Orlando, FL) under various simulated conditions. Experimental parameters include radionuclide (gamma-ray) energy, activity, density thickness (source to detector distance and shielding), time, and temperature. All statistical algorithms were developed using MATLAB TM . The Shewhart (3-σ) control chart and the cumulative sum (CUSUM) control chart are the classical procedures adopted, while the Bayesian technique is the Shiryayev-Roberts (S-R) control chart. The Shiryayev-Roberts method was the best method for controlling the number of false positive detects, followed by the CUSUM method. However, The Shiryayev-Roberts method, used without modification, resulted in one of the highest false negative incidence rates independent of the signal strength. Modification of The Shiryayev-Roberts statistical analysis method reduced the number of false negatives, but resulted in an increase in the false positive incidence rate. (author)

Proceedings of the 3. Regional Meeting on Radiological and Nuclear Safety, Regional Meeting on International Radiation Protection Association (IRPA)and 3. Peruvian Meeting on Radiological Protection

International Nuclear Information System (INIS)

1995-10-01

There we show works of the Third Regional Meeting on Radiological and Nuclear Safety held on 23-27 October, 1995 in Cusco-Peru. Latin americans specialists talk about nuclear safety and radiological protection, radiation natural exposure, biological effect of radiation, radiotherapy and medical radiological safety, radiological safety in industry and research. Also we deal with subjects related to radiological safety of nuclear and radioactive facilities, radioactive waste management, radioactive material transport, environmental radiological monitoring program, radiological emergency and accidents, instruments and dosimetry, basic safety standards of protection against radiation. More than 225 works were presented on the meeting

Radiological effluents released from nuclear rocket and ramjet engine tests at the Nevada Test Site 1959 through 1969: Fact Book

Energy Technology Data Exchange (ETDEWEB)

Friesen, H.N.

1995-06-01

Nuclear rocket and ramjet engine tests were conducted on the Nevada Test Site (NTS) in Area 25 and Area 26, about 80 miles northwest of Las Vegas, Nevada, from July 1959 through September 1969. This document presents a brief history of the nuclear rocket engine tests, information on the off-site radiological monitoring, and descriptions of the tests.

International Cooperation of the Republic of Croatia in the Field of Radiological and Nuclear Safety

International Nuclear Information System (INIS)

Novosel, N.

2011-01-01

International cooperation of the Republic of Croatia in the field of radiological and nuclear safety can be divided in two parts - political part, for which the Ministry of Foreign Affairs and European Integration is responsible, and technical part, for which the State Office for Radiological and Nuclear Safety is responsible. According to the Radiological and Nuclear Safety Act (OG 28/10) the State Office for Radiological and Nuclear Safety: ''coordinates technical cooperation with the International Atomic Energy Agency for all participants from the Republic of Croatia''; ''fulfils the obligations which the Republic of Croatia has assumed through international conventions and bilateral agreements concerning protection against ionising radiation, nuclear safety and the application of protective measures aimed at the non-proliferation of nuclear weapons'' and ''cooperates with international and domestic organisations and associations in the area of protection against ionising radiation and nuclear safety, and appoints its own expert representatives to take part in the work of such organisations and associations or to monitor their work''. In this paper various aspects of the technical cooperation with the International Atomic Energy Agency, as well as international conventions and bilateral agreements in the field of radiological and nuclear safety, are presented. Also, cooperation with other international organizations and associations in the area of radiological and nuclear safety, such as Nuclear Suppliers Group, the Zangger Committee, the Wassenaar Arrangement, Comprehensive Nuclear-Test-Ban Treaty Organization, Euratom and certain civil expert groups of NATO, is described. (author)

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

Radiological investigation in the outside area of expedition's room during radiopharmaceuticals' expedition; Avaliacao radiologica na area externa da sala de expedicao durante a expedicao de radiofarmacos

Energy Technology Data Exchange (ETDEWEB)

Reina, Luiz C.; Monteiro, Ilka H.T.S.; Silva, Joao Carlos P. da; Teixeira, Danilo L.; Pedro, C.R.; Santos, J. Regis dos, E-mail: reina@ien.gov.br, E-mail: jcarlos@ien.gov.br [Instituto de Engenharia Nuclear (IEN/CNEN-RJ), Rio de janeiro, RJ (Brazil)

2013-07-01

Radiopharmaceuticals produced in IEN - Instituto de Engenharia Nuclear of the Brazilian Nuclear Energy Commission, are issued by the radiation protection team, which is responsible for preparing and issuing the packaged documentation required for movement in modal transportation. The documents are: Invoice , Shipper's Declaration of Radioactive Material , Shipper's Declaration of Dangerous Goods - (form IATA ) , Emergency Sheet, sketch of packed. All this documentation is inserted in an envelope of emergency. The Department of Radiological Protection is responsible for issuing such documents except the invoice that is issued by the Commercial Sector (Setcom). A employee of this sector is responsible for delivering it to the shipment sector. The preparation of packaged and documentation is performed in a room located in the building of Radiopharmaceutical Division. The vehicles which are used in the transport are parked outside this building, where are monitored after commissioning of packaged. The present study aims to evaluate potential and occupational radiation risks of people in transit or remain in the area where radioactive material circulates due to the shipment of radiopharmaceuticals for the classification of the area during the operation of dispatch.

Duquesne Light Company 1982 annual radiological environmental report. Volume 2

International Nuclear Information System (INIS)

1982-01-01

This report describes the Radiological Environmental Monitoring Program conducted during 1982 in the vicinity of the Beaver Valley Power Station and the Shippingport Atomic Power Station. The Radiological Environmental Program consists of on-site sampling of water and gaseous effluents and off-site monitoring of water, air, river sediments, soils, food pathway samples, and radiation levels in the vicinity of the site. This report discusses the results of this monitoring during 1982. The results show that Shippingport Atomic Power Station and Beaver Valley Power Station operations have not adversely affected the surrounding environment

Westinghouse Hanford Company operational environmental monitoring annual report, calendar year 1994

Energy Technology Data Exchange (ETDEWEB)

Schmidt, J.; Fassett, J.W.; Johnson, A.R.; Johnson, V.G.; Markes, B.M.; McKinney, S.M.; Moss, K.J.; Perkins, C.J.; Richterich, L.R.

1995-08-01

This document presents the results of the Westinghouse Hanford Company near-facility operational environmental monitoring for 1994 in the 100, 200/600, and 300/400 Areas of the Hanford Site, in south-central Washington State. Surveillance activities included sampling and analyses of ambient air surface water, groundwater, soil, sediments, and biota. Also, external radiation measurements and radiological surveys were taken at waste disposal sites, radiologically controlled areas, and roads. These activities were conducted to assess and control the effects of nuclear facilities and waste sites on the local environment. In addition, diffuse sources were monitored to determine compliance with Federal, State, and/or local regulations. In general, although effects from nuclear facilities are still seen on the Hanford Site and radiation levels are slightly elevated when compared to offsite locations, the differences are less than in previous years.

Westinghouse Hanford Company operational environmental monitoring annual report - calendar year 1995

Energy Technology Data Exchange (ETDEWEB)

Schmidt, J.W., Westinghouse Hanford

1996-07-30

This document summarizes the results of the Westinghouse Hanford Company (WHC) near-facility operational environmental monitoring for 1995 in the 100, 200/600, and 300/400 Areas of the Hanford Site, in south-central Washington State. Surveillance activities included sampling and analyses of ambient air, surface water,groundwater, soil, sediments, and biota. Also, external radiation measurements and radiological surveys were taken at waste disposal sites, radiologically controlled areas, and roads. These activities were conducted to assess and control the effects of nuclear facilities and waste sites on the local environment. In addition, diffuse sources were monitored to determine compliance with Federal, State, and/or local regulations. In general, although effects from nuclear facilities can still be observed on the Hanford Site and radiation levels are slightly elevated when compared to offsite locations, the differences are less than in previous years.

Groundwater quality sampling and analysis plan for environmental monitoring in Waste Area Grouping 6 at Oak Ridge National Laboratory, Oak Ridge, Tennessee

Energy Technology Data Exchange (ETDEWEB)

1994-03-01

This Sampling and Analysis Plan addresses groundwater quality sampling and analysis activities that will be conducted in support of the Environmental Monitoring Plan for Waste Area Grouping (WAG) 6. WAG 6 is a shallow-burial land disposal facility for low-level radioactive waste at the Oak Ridge National Laboratory, a research facility owned by the US Department of energy and managed by martin Marietta Energy Systems, Inc. (Energy Systems). Groundwater sampling will be conducted by Energy Systems at 45 wells within WAG 6. The samples will be analyzed for various organic, inorganic, and radiological parameters. The information derived from the groundwater quality monitoring, sampling, and analysis will aid in evaluating relative risk associated with contaminants migrating off-WAG, and also will fulfill Resource Conservation and Recovery Act (RCRA) interim permit monitoring requirements. The sampling steps described in this plan are consistent with the steps that have previously been followed by Energy Systems when conducting RCRA sampling.

Groundwater quality sampling and analysis plan for environmental monitoring in Waste Area Grouping 6 at Oak Ridge National Laboratory, Oak Ridge, Tennessee

International Nuclear Information System (INIS)

1994-03-01

This Sampling and Analysis Plan addresses groundwater quality sampling and analysis activities that will be conducted in support of the Environmental Monitoring Plan for Waste Area Grouping (WAG) 6. WAG 6 is a shallow-burial land disposal facility for low-level radioactive waste at the Oak Ridge National Laboratory, a research facility owned by the US Department of energy and managed by martin Marietta Energy Systems, Inc. (Energy Systems). Groundwater sampling will be conducted by Energy Systems at 45 wells within WAG 6. The samples will be analyzed for various organic, inorganic, and radiological parameters. The information derived from the groundwater quality monitoring, sampling, and analysis will aid in evaluating relative risk associated with contaminants migrating off-WAG, and also will fulfill Resource Conservation and Recovery Act (RCRA) interim permit monitoring requirements. The sampling steps described in this plan are consistent with the steps that have previously been followed by Energy Systems when conducting RCRA sampling

Measuring and improving productivity in general radiology.

Science.gov (United States)

Wilt, Michelle A; Miranda, Rafael; Johnson, C Daniel; Love, Peggy Sue

2010-10-01

The aim of this study was to determine a method of measuring productivity among general radiographers in a moderate-sized hospital and to improve and sustain productivity within that work area. The average times needed to perform the 13 most common examinations were measured. Performance of the various examinations was tracked and multiplied by the time allocated per procedure; this measure was divided by the length of the work shift to determine productivity. Productivity measures were shared among the work group, and decisions to improve productivity (eg, whether to fill open positions) were made by group members. Average time spent per examination type was calculated (range, 10 minutes to 1 hour 16 minutes). At baseline (February 2008), group productivity was 50%. Productivity increased during the first year of monitoring and was sustained through November 2009 (productivity range, 57%-63%). Yearly savings from not filling open positions were estimated to be $174,000. Productivity in a general radiology work area can be measured. Consensus among the work group helped increase productivity and assess progress. This methodology, if widely adopted, could be standardized and used to compare productivity across departments and institutions. Copyright © 2010 American College of Radiology. Published by Elsevier Inc. All rights reserved.

PARATI - a dynamic model for radiological assessments in urban areas. Pt. 1. Modelling of urban areas, their contamination and radiation fields

International Nuclear Information System (INIS)

Rochedo, E.R.R.; Conti, L.F.C.; Paretzke, H.G.

1996-01-01

The structure and mathematical model of PARATI, a detailed computer programme developed for the assessment of the radiological consequences of an accidental contamination of urban areas, is described with respect to the scenarios used for the estimation of exposure fields in a village or town, the models for the initial and secondary contamination with the radionuclide 137 Cs, the concepts for calculating the resulting radiation exposures and the changes with time of the contamination and radiation fields. Kerma rates at various locations in tropical urban areas are given, and the contribution of different contaminated surfaces to these rates after dry or wet deposition are discussed. (orig.). With 6 figs., 12 tabs

Yucca Mountain Biological Resources Monitoring Program

International Nuclear Information System (INIS)

1992-01-01

The US Department of Energy (DOE) is required by the Nuclear Waste Policy Act of 1982 (as amended in 1987) to study and characterize Yucca Mountain as a possible site for a geologic repository for high-level nuclear waste. During site characterization, the DOE will conduct a variety of geotechnical, geochemical, geological, and hydrological studies to determine the suitability of Yucca Mountain as a repository. To ensure that site characterization activities (SCA) do not adversely affect the Yucca Mountain area, an environmental program has been implemented to monitor and mitigate potential impacts and to ensure that activities comply with applicable environmental regulations. This report describes the activities and accomplishments during fiscal year 1991 (FY91) for six program areas within the Terrestrial Ecosystem component of the YMP environmental program. The six program areas are Site Characterization Activities Effects, Desert Tortoises, Habitat Reclamation, Monitoring and Mitigation, Radiological Monitoring, and Biological Support

Study on Korean Radiological Emergency System-Care System- and National Nuclear Emergency Preparedness System Development

International Nuclear Information System (INIS)

Akhmad Khusyairi; Yudi Pramono

2008-01-01

Care system; Radiological Emergency Supporting System. Environmental radiology level is the main aspect that should be concerned deal with the utilization of nuclear energy. The usage of informational technology in nuclear area gives significant contribution to anticipate and to protect human and environment. Since 1960, South Korea has developed environment monitoring system as the effort to protect the human and environment in the radiological emergency condition. Indonesia has possessed several nuclear installations and planned to build and operate nuclear power plants (PLTN) in the future. Therefore, Indonesia has to prepare the integrated system, technically enables to overcome the radiological emergency. Learning from the practice in South Korea, the system on the radiological emergency should be prepared and applied in Indonesia. However, the government regulation draft on National Radiological Emergency System, under construction, only touches the management aspect, not the technical matters. Consequently, when the regulation is implemented, it will need an additional regulation on technical aspect including the consideration on the system (TSS), the organization of operator and the preparation of human resources development of involved institution. For that purpose, BAPETEN should have a typical independence system in regulatory frame work. (author)

Aerial radiological survey of the Industrial Reactor Laboratory and surrounding area Plainsboro, New Jersey

International Nuclear Information System (INIS)

1980-12-01

An airborne radiological survey of a 6 km 2 area centered over the Industrial Reactor Laboratory was made 25-27 July 1979. Detected radioisotopes and their associated gamma ray exposure rates were consistent with that expected from normal background emitters, except at two locations described in this report. Count rates observed at 46 m altitude were converted to exposure rates at 1 m above the ground and are presented in the form of an isopleth map

Review Paper of Radionuclide Monitoring in Food Sample

International Nuclear Information System (INIS)

Noor Fadzilah Yusof; Abdul Kadir Ishak; Wo, Y.M.; Nurrul Assyikeen Mohd Jaffary

2011-01-01

The uncontrolled release of radionuclides into the atmospheric and aquatic environments may occur as the result of a nuclear or radiological accident. Monitoring of the accidental release at its source and especially direct monitoring of the environmental contamination with radionuclides is necessary for assessment and application of public protective actions and longer term countermeasures as well as emergency workers' protection. In areas historically contaminated with long lived radionuclides monitoring it is essential to protect the public and substantiation of any radiological incidents. Also, dietary pathways can be contaminated with radioactive materials resulting from natural occurrence or man-made applications especially during routine operation, accidents and migration of radionuclides from radioactive waste disposal repositories into the biosphere. Therefore, efforts should be made to determine the presence of radionuclides in a potentially high radiation area especially in operational nuclear facilities. This paper will review the strategies for food monitoring that has been adapted in most countries to obtain baseline data for future reference. Also, this study is discussing the type of food selection commonly collected as sample for radionuclide analysis in different countries over the years. Sampling procedure and analysis also included in this review for better understanding of the analysis. Stake holders' involvement is considered as an important asset in the establishment of monitoring strategies. As a conclusion, future plans for food monitoring programme in Malaysia are recommended as a preparation to embark on the Nuclear Power Plant programme. (author)

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

Planning new basic guideline to the radiological risk. Content, radiological criteria and implementation

International Nuclear Information System (INIS)

Calvin Cuartero, M.; Vega Riber, R. de la; Martin Calvarro, J. M.

2011-01-01

The most important aspects of the Basic Guideline focus on their area of planning, groups of potential radiological emergencies in the type of activity associated with the levels of response planning and responsible organizations, structure and functions for each level, radiological criteria, implementation and maintenance of the effectiveness of the level of response plans abroad.

Radiological and Environmental Monitoring at the Clean Slate I and III Sites, Tonopah Test Range, Nevada, With Emphasis on the Implications for Off-site Transport

Energy Technology Data Exchange (ETDEWEB)

Mizell, Steve A [Desert Research Inst. (DRI), Las Vegas, NV (United States); Etyemezian, Vic [Desert Research Inst. (DRI), Las Vegas, NV (United States); McCurdy, Greg [Desert Research Inst. (DRI), Las Vegas, NV (United States); Nikolich, George [Desert Research Inst. (DRI), Las Vegas, NV (United States); Shadel, Craig [Desert Research Inst. (DRI), Las Vegas, NV (United States); Miller, Julianne J [Desert Research Inst. (DRI), Las Vegas, NV (United States)

2014-09-01

In 1963, the U.S. Department of Energy (DOE) (formerly the Atomic Energy Commission [AEC]) implemented Operation Roller Coaster on the Tonopah Test Range (TTR) and an adjacent area of the Nevada Test and Training Range (NTTR) (formerly the Nellis Air Force Range [NAFR]). Operation Roller Coaster consisted of four tests in which chemical explosions were detonated in the presence of nuclear devices to assess the dispersal of radionuclides and evaluate the effectiveness of storage structures to contain the ejected radionuclides. These tests resulted in the dispersal of plutonium over the ground surface downwind of the test ground zero (GZ). Three tests—Clean Slate I, II, and III—were conducted on the TTR in Cactus Flat. The fourth, Double Tracks, was conducted in Stonewall Flat on the NTTR. The Desert Research Institute (DRI) installed two monitoring stations in 2008, Station 400 at the Sandia National Laboratories (SNL) Range Operations Center (ROC) and Station 401 at Clean Slate III. Station 402 was installed at Clean Slate I in 2011 to measure radiological, meteorological, and dust conditions. The monitoring activity was implemented to determine if radionuclide contamination in the soil at the Clean Slate sites was being transported beyond the contamination area boundaries. Some of the data collected also permits comparison of radiological exposure at the TTR monitoring stations to conditions observed at Community Environmental Monitoring Program (CEMP) stations around the NTTR. Annual average gross alpha values from the TTR monitoring stations are higher than values from the surrounding CEMP stations. Annual average gross beta values from the TTR monitoring stations are generally lower than values observed for the surrounding CEMP stations. This may be due to use of sample filters with larger pore space because when glass-fiber filters began to be used at TTR Station 400, gross beta values increased. Gamma spectroscopy typically identified only naturally

Nuclear reactor effluent monitoring

International Nuclear Information System (INIS)

Minns, J.L.; Essig, T.H.

1993-01-01

Radiological environmental monitoring and effluent monitoring at nuclear power plants is important both for normal operations, as well as in the event of an accident. During normal operations, environmental monitoring verifies the effectiveness of in-plant measures for controlling the release of radioactive materials in the plant. Following an accident, it would be an additional mechanism for estimating doses to members of the general public. This paper identifies the U.S. Nuclear Regulatory Commission (NRC) regulatory basis for requiring radiological environmental and effluent monitoring, licensee conditions for effluent and environmental monitoring, NRC independent oversight activities, and NRC's program results

Nuclear reactor effluent monitoring

Energy Technology Data Exchange (ETDEWEB)

Minns, J.L.; Essig, T.H. [Nuclear Regulatory Commission, Washington, DC (United States)

1993-12-31

Radiological environmental monitoring and effluent monitoring at nuclear power plants is important both for normal operations, as well as in the event of an accident. During normal operations, environmental monitoring verifies the effectiveness of in-plant measures for controlling the release of radioactive materials in the plant. Following an accident, it would be an additional mechanism for estimating doses to members of the general public. This paper identifies the U.S. Nuclear Regulatory Commission (NRC) regulatory basis for requiring radiological environmental and effluent monitoring, licensee conditions for effluent and environmental monitoring, NRC independent oversight activities, and NRC`s program results.

Radiological and environmental surveillance in front-end fuel cycle facilities

International Nuclear Information System (INIS)

Khan, A.H.; Sahoo, S.K.; Tripathi, R.M.

2004-01-01

This paper describes the occupational and environmental radiological safety measures associated with the operations of front end nuclear fuel cycle. Radiological monitoring in the facilities is important to ensure safe working environment, protection of workers against exposure to radiation and comply with regulatory limits of exposure. The radiation exposure of workers in different units of the front end nuclear fuels cycle facilities operated by IREL, UCIL and NFC and environmental monitoring results are summarised

RaCon: a software tool serving to predict radiological consequences of various types of accident in support of emergency management and radiation monitoring management

International Nuclear Information System (INIS)

Svanda, J.; Hustakova, H.; Fiser, V.

2008-01-01

The RaCon software system, developed by the Nuclear Research Institute Rez, is described and its application when addressing various tasks in the domain of radiation accidents and nuclear safety (accidents at nuclear facilities, transport of radioactive material, terrorist attacks) are outlined. RaCon is intended for the prediction and evaluation of radiological consequences to population and rescue teams and for optimization of monitoring actions. The system provides support to emergency management when evaluating and devising actions to mitigate the consequences of radiation accidents. The deployment of RaCon within the system of radiation monitoring by mobile emergency teams or remote controlled UAV is an important application. Based on a prediction of the radiological situation, RaCon facilitates decision-making and control of the radiation monitoring system, and in turn, refines the prediction based on observed values. Furthermore, the system can perform simulations of evacuation patterns at the Dukovany NPP and at schools in the vicinity of the power plant and can provide support to emergency management should any such situation arise. (orig.)

Effective radiological contamination control and monitoring techniques in high alpha environments.

Science.gov (United States)

Funke, Kevin C

2003-02-01

In the decommissioning of a highly contaminated alpha environment, such as the one at Hanford's 233-S Plutonium Concentration Facility, one of the key elements of a successful radiological control program is an integrated safety approach. This approach begins with the job-planning phase where the scope of the work is described. This is followed by a brainstorming session involving engineering and craft to identify how to perform the work in a logical sequence of events. Once the brainstorming session is over, a Job Hazard Analysis is performed to identify any potential problems. Mockups are utilized to enable the craft to get hands on experience and provide feedback and ideas to make the job run smoother. Ideas and experience gained during mockups are incorporated into the task instruction. To assure appropriate data are used in planning and executing the job, our principal evaluation tools included lapel and workplace air sampling, plus continuous air monitors and frequent surveys to effectively monitor job progress. In this highly contaminated alpha environment, with contamination levels ranging from 0.3 Bq cm-2 to approximately 100,000 Bq cm-2 (2,000 dpm per 100 cm2 to approximately 600 million dpm per 100 cm2), with average working levels of 1,600-3,200 Bq cm-2 (10-20 million dpm per 100 cm2) without concomitant ambient radiation levels, control of the spread of contamination is key to keeping airborne levels As Low As Reasonably Achievable.

Radiological protection of the unborn child. Recommendation of the Commission on Radiological Protection and scientific grounds

International Nuclear Information System (INIS)

Sarenio, O.

2006-01-01

The Commission on Radiological Protection was asked to give advice on the practical implications of the absorption of the maximum possible activity values that, under the Radiological Protection Ordinance, may be incorporated in women of child-bearing age occupationally exposed to radiation with regard to incorporation monitoring and compliance with the dose limit for the protection of the unborn child. An unborn child's conceivable level of exposure to radiation in the least favourable case due to continuous and single incorporations of radionuclides in the mother was determined on a nuclide-specific basis by the Federal Office for Radiation Protection with the aid of the mathematical metabolic models provided in ICRP 88. At the proposal of the Commission on Radiological Protection, the Federal Office for Radiation Protection considered the following very conservative scenarios: - the mother's maximum possible exposure due to a continuous intake of activity over 10 years prior to the pregnancy and in the first 10 weeks postconception based on the limits set out in the Radiological Protection Ordinance; - the mother's maximum possible exposure due to a single intake at the most unfavourable time in the first 10 weeks postconception based on the limits set out in the Radiological Protection Ordinance. Examination of these scenarios found that, with a few exceptions, the dose to the unborn child attributable to the incorporation of radiation in the mother summed up over 70 years is less than that to the mother. The committed effective dose to the unborn child from certain radionuclides may exceed the value of 1 mSv when the dose to the mother reaches the maximum limit. The Commission on Radiological Protection was therefore asked 1. to examine whether compliance with the limit of 1 mSv effective dose is sufficient for the protection of the unborn child or whether any additional limitation is required for individual organs, 2. to discuss the implications for

Annual radiological environmental operating report: Sequoyah Nuclear Plant, 1987

International Nuclear Information System (INIS)

1988-04-01

This report describes the environmental radiological monitoring program conducted by TVA in the vicinity of the Sequoyah Nuclear Plant in 1987. The program includes the collection of samples from the environment and the determination of the concentrations of radioactive materials in the samples. Samples are taken from stations in the general area of the plant and from areas not influenced by plant operations. Station locations are selected after careful consideration of the weather patterns and projected radiation doses to the various areas around the plant. Material sampled includes air, water, milk, foods, vegetation, soil, fish, sediment, and direct radiation levels. Results from stations near the plant are compared with concentrations from control stations and with preoperational measurements to determine potential impacts of plant operations. 2 figs., 2 tabs

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

International Nuclear Information System (INIS)

Maurer, R.J.

1989-09-01

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

Hanford site near-facility environmental monitoring annual report, calendar year 1996

Energy Technology Data Exchange (ETDEWEB)

Perkins, C.J.

1997-08-05

This document summarizes the results of the near-facility environmental monitoring results for 1996 in the 100, 200/600, and 300/400 areas of the Hanford Site in south-central Washington State. Surveillance activities included sampling and analyses of ambient air, surface water, groundwater, soil, sediments, and biota. Also, external radiation measurements and radiological surveys were taken at waste disposal sites, radiologically controlled areas, and roads. These activities were conducted to assess and control the effects of nuclear facilities and waste sites on the local environment. The monitoring implements applicable portions of DOE Orders 5400.1 (DOE 1988a), 5400.5 (DOE 1990), and 5820.2A (DOE 1988b); Washington Administrative Code (WAC) 246-247; and Title 40 Code of Federal Regulations (CFR) Part 61, Subpart H (EPA 1989). In addition, diffuse sources were monitored to determine compliance with federal, state, and/or local regulations. In general, although effects from nuclear facilities can still be observed on the Hanford Site and radiation levels were slightly elevated when compared to offsite locations, the differences are less than in previous years.

Development of national level preparedness for response to nuclear and radiological emergencies

International Nuclear Information System (INIS)

Pradeepkumar, K.S.

2014-01-01

In India, DAE being the nodal agency for technical support for response to any radiation emergency nuclear disaster and various nuclear and radiological emergency scenarios and their impacts are identified. To reduce their consequences development of methodologies for detection and quick impact assessment, trained First Responders and Quick Response Teams (QRTs), twenty two DAE Emergency Response Centers, mobile and aerial radiation monitoring systems, aerial and ground based validation trials etc. are carried out. Study related to radiological threats and simulated RDD experiments conducted using stable isotopes indicates that radiation levels for distances more than 50 m will not be very high as hotspots may be restricted to nearby area. The biggest challenge from an RDD explosion will be handling of the radioactive contamination and 'fear factor' compared to radiation exposure to public or First Responders. Level and pattern of radioactive contamination on ground following releases during nuclear accidents and minimum strength of orphan radioactive sources to be detected are taken into account for optimizing systems and monitoring methodology required for emergency preparedness

Determination of Crack Area on Lead Apron used in Diagnostic Radiology

International Nuclear Information System (INIS)

Norriza Mohd Isa; Muhammad Jamal Muhammad Isa; Asmaliza Hashim

2014-01-01

The study was performed to determine crack area of lead aprons used by personnel as radiation protector from unnecessary radiation in diagnostic radiology. The experiment was done using general X-ray and Computed Radiography (CR) systems. Calibration curve was plotted for beam quality at 80 kVp and source to detector distance (SDD) is 100 cm by selecting manual exposure mode. Lead sheet with thickness from 0.1 to 1.0 mm were used for this purpose. It was used to relate the pixel value of lead sheet images with their thickness. A few sample of lead aprons with different thickness from a hospital and our laboratories were obtained and then undergoing the inspection at our laboratory through this procedure. The samples were divided with two groups based on how long they were used which are less 10 years and more than 10 years. The images data of the sample were obtained and analysis using our developed software. The reference object with known its area was also used in the experiment to ensure our output using the software is reliable and acceptable. The results shown that lead aprons used more than 10 years have depicted more crack areas compare with the lead apron used less than 10 years. (author)

Radiological protection report 2016

International Nuclear Information System (INIS)

2017-06-01

In the radiological protection report 2016, the Swiss Federal Nuclear Safety Inspectorate (ENSI) provides an overview of the radiological protection in its area of supervision. Part A of the report deals with protecting the staff of nuclear power plants from the dangers of ionising radiation. It also includes a list of the personal doses accumulated by the staff, broken down using various parameters. Applying the optimisation imperative, it has been proved possible to significantly reduce the annual collective doses in Switzerland's nuclear power plants since they came on stream thanks to major efforts by the operators. In 2016, a total of 6,153 people measured accumulated 2,877 person-mSv. The collective doses have reached a low level corresponding to the radiological condition of the plants and the scope of the work required to be performed in controlled zones (e.g. non-destructive materials testing). ENSI will continue to follow the trend for collective doses and assess the reasons for local variances as well as for measures initiated. The individual doses for people employed in ENSI's area of supervision in 2016 showed a maximum figure of 10 mSv and a mean value of 0.5 mSv which was significantly below the dose limit of 20 mSv for occupational radiation exposure. The discharge of radioactive substances with the exhaust air and waste water from nuclear power plants are dealt with in Part B of the report. In 2016, nuclear power plant operators again met the admissible release limits set by the authorities, in some cases by a considerable margin. The emissions of Swiss nuclear power plants led to a dose of less than 0.01 mSv per year in the direct neighbourhood. A comparison with the average annual radiation dose for the Swiss population of 5.5 mSv shows that the relevant contribution from nuclear power plants lies in the area of one percent of this figure. Effluents from Swiss nuclear power plants were also below the target of 1 GBq per year set by ENSI

Neutron area monitor with TLD pairs

International Nuclear Information System (INIS)

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

2011-11-01

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

RadNet Radiological Air Monitoring Network

International Nuclear Information System (INIS)

Scott Telofski, J.; Askren, D.R.; Petko, Ch.M.; Fraass, R.G.

2010-01-01

The United States Environmental Protection Agency operates a national environmental radiation monitoring program called RadNet. RadNet monitors airborne particulates, precipitation, milk, and drinking water for radiation levels. The primary purpose of the original program in the 1950's and 1960's was to collect and analyze samples in various media to assess the effects of radioactive fallout from above-ground nuclear weapon testing. As above-ground testing diminished in the 1970's, the program, especially the air network, became critical in evaluating effects of other types of nuclear incidents, such as the nuclear reactor accident at Chernobyl, as well as monitoring trends in environmental radioactive contamination. The value of rapid data collection subsequent to such incidents led to the consideration of developing air monitors with radiation detectors and telecommunication equipment for real-time radiation measurement. The strengthened United States homeland security posture after 2001 led to production and installation of the current real-time RadNet air monitors. There are now 118 stationary, continuously operating air monitoring stations and 40 mobile air monitors for site specific monitoring. The stationary air monitors include radiation detectors, meteorological sensors, a high-volume air sampler, and communication devices for hourly data transfers. When unusual levels are detected, scientists download a full sodium iodide detector spectrum for analysis. The real-time data collected by RadNet stationary systems permit rapid identification and quantification of airborne nuclides with sufficient sensitivity to provide critical information to help determine protective actions. The data also may help to rapidly refine long-range radioactive plume models and estimate exposure to the population. This paper provides an overview of the airborne particulate monitoring conducted during above-ground nuclear weapon testing, summarizes the uses of data from the program

Westinghouse Hanford Company Operational Environmental Monitoring. Annual report, CY 1993

International Nuclear Information System (INIS)

Schmidt, J.W.; Johnson, A.R.; Markes, B.M.; McKinney, S.M.; Perkins, C.J.

1994-07-01

This document presents the results of the Westinghouse Hanford Company near-facility operational environmental monitoring for 1993 in the 100, 200/600, and 300/400 Areas of the Hanford Site, in south-central Washington State. Surveillance activities included sampling and analyses of ambient air, surface water, groundwater, sediments, soil, and biota. Also, external radiation measurements and radiological surveys were taken at waste disposal sites, radiologically controlled areas, and roads. These activities were conducted to assess and control the effects of nuclear facilities and waste sites on the local environment. In addition, diffuse sources were monitored to determine compliance with Federal, State, and/or local regulations. In general, although effects from nuclear facilities are still seen on the Hanford Site and radiation levels are slightly elevated when compared to offsite conditions, the differences are less than in previous years. At certain locations on or directly adjacent to nuclear facilities and waste sites, levels can be several times higher than offsite conditions

Plan of routine environmental radiological monitoring in the vicinity of nuclear and radioactive facilities of the Country

International Nuclear Information System (INIS)

Czerniczyniec, M.A; Bonetto, J.P.; Giustina, Daniel

2009-01-01

The Nuclear Regulatory Authority (ARN) carries out the monitoring of the environment surrounding Argentina nuclear power plants, independently from the operators' own monitoring programmes. Recently, there has been a review of the criteria used for selecting target radionuclides, sampling matrix, sampling location, and sampling frequency. This revision was based on ARN objectives for an environmental radiological monitoring programme, which are: verification of discharge monitoring results and detection of unadverted/unauthorized emissions; verification of models assumptions and checking that doses to the critical groups are not exceeded; detection of radionuclides presence in the environment and trend analysis; and to provide information to the public. The criteria proposed for adoption implies the monitoring of the relevant radionuclides mentioned in the discharge authorization license, using specific analysis for those considered indicators and screening techniques for the others. The matrix to be sampled must be related with the different exposure pathways, from those related with direct exposure, which require higher sampling frequencies, to accumulating/concentrating matrices, which imply lower sampling frequencies. At least, three points should be sampled, related to both airborne and liquid emissions: a background location, the representative person location, and that where the concentration of a target radionuclide is expected to be maximum. Available modeling software was used for positioning the sampling points. (author)

Radiological surveys of properties in the Middlesex, New Jersey area. Final report

International Nuclear Information System (INIS)

Leggett, R.W.; Haywood, F.F.; Cottrell, W.D.

1981-03-01

Results of the radiological surveys conducted at three properties in the Middlesex, New Jersey area as well as one additional location downstream from the Middlesex Sampling Plant (Willow Lake), are presented. The survey revealed that the yard around the church rectory on Harris Avenue is contaminated with a 226 Ra-bearing material, probably pitchblende ore from the former Middlesex Sampling Plant. The elevated 226 Ra concentrations around and, to a lesser extent, underneath the rectory are leading to elevated 222 Rn concentrations in air in the rectory and elevated alpha contamination levels (from radon daughters) on surfaces inside the rectory. External gamma radiation levels in the rectory yard are well above background levels, and beta-gamma dose rates at many points in the yard are above federal guidelines for the release of property for unrestricted use. The radiological survey of a parking lot at the Union Carbide plant in Bound Brook, New Jersey revealed that a nearly circular region of 50-ft diam in the lot showed above-background external gamma radiation levels. Two isolated spots within this region showed concentrations of uranium in soil above the licensable level stated in 10 CFR 40. Soil samples taken in the area of elevated gamma radiation levels generally showed nearly equal activities of 226 Ra and 238 U. The survey at the residences on William Street in Piscataway, revealed that the front yeard is generally contaminated from near the surface to a depth of 1.5 to 2.5 ft with 226 Ra-bearing material, possibly pitchblende ore. The remainder of the yard shows scattered contaminaion. External gamma radiation levels inside the house are above the background level near some outside walls

Educational course in emergency radiology

International Nuclear Information System (INIS)

Velkova, K.; Stoeva, M.; Cvetkova, S.; Hilendarov, A.; Petrova, A.; Stefanov, P.; Simova, E.; Georgieva, V.; Sirakov, N.

2012-01-01

Emergency radiology is the part of radiology primarily focused on acute diagnosing conditions in ER patients. This advanced area of radiology improves the quality of care and treatment of patients and of the emergency medicine as a whole. The educational course in Emergency (ER) Radiology is available for medical students in their 8th and 9th semester. The main objective of the ER course is to obtain knowledge about the indications, possibilities and diagnostic value of the contemporary imaging methods in ER cases. Therapeutic methods under imaging control are also covered by the course. The curriculum of the course consists of 6 lectures and 12 practical classes. (authors)

An aerial radiological survey of the Superconducting Super Collider Laboratory and surrounding area, Waxahachie, Texas

International Nuclear Information System (INIS)

Fritzsche, A.E.

1993-02-01

An aerial radiological survey was conducted over the Superconducting Super Collider Laboratory (SSCL) site from July 22 through August 20,1991. Parallel lines were flown at intervals of 305 meters over a 1,036-square-kilometer (400-square-mile) area surrounding Waxahachie, Texas. The 70,000 terrestrial gamma energy spectra obtained were reduced to an exposure rate contour map overlaid on a United States Geological Survey (USGS) map of the area. The mean terrestrial exposure rate measured was 5.4 μR/h at 1 meter above ground level. Comparison to ground-based measurements shows good agreement. No anomalous or man-made isotopes were detected

Radiological characteristic of an area reclaimed by means of an ash-gravel power plant wastes

International Nuclear Information System (INIS)

Zak, A.; Biernacka, M.; Kusyk, M.; Mamont-Ciesla, K.; Florowska, K.

2002-01-01

A sand excavation after extraction of gravel and sand was filled with an ash-gravel mix. The mix was covered with shielding layers of clay and soil and grass was cultivated on it. Investigations of radiological characteristic such as: gamma radiation dose rate, radon concentration in soil air and radionuclide concentration in the ground were carried out in the both areas reclaimed one and in the vicinity of it. Radon exhalation coefficients were determined for uncovered ash-gravel mix layer, the shielding soil layer and for the ground in the vicinity. Analysis of the results revealed that the reclaimed area can be used for building development. (author)

A Business Analytics Software Tool for Monitoring and Predicting Radiology Throughput Performance.

Science.gov (United States)

Jones, Stephen; Cournane, Seán; Sheehy, Niall; Hederman, Lucy

2016-12-01

Business analytics (BA) is increasingly being utilised by radiology departments to analyse and present data. It encompasses statistical analysis, forecasting and predictive modelling and is used as an umbrella term for decision support and business intelligence systems. The primary aim of this study was to determine whether utilising BA technologies could contribute towards improved decision support and resource management within radiology departments. A set of information technology requirements were identified with key stakeholders, and a prototype BA software tool was designed, developed and implemented. A qualitative evaluation of the tool was carried out through a series of semi-structured interviews with key stakeholders. Feedback was collated, and emergent themes were identified. The results indicated that BA software applications can provide visibility of radiology performance data across all time horizons. The study demonstrated that the tool could potentially assist with improving operational efficiencies and management of radiology resources.

Wide area continuous offender monitoring

Energy Technology Data Exchange (ETDEWEB)

Hoshen, J. [Lucent Technologies (United States); Drake, G. [New Mexico Dept. of Corrections, Santa Fe, NM (United States); Spencer, D. [Sandia National Labs., Albuquerque, NM (United States)

1996-11-01

The corrections system in the U.S. is supervising over five million offenders. This number is rising fast and so are the direct and indirect costs to society. To improve supervision and reduce the cost of parole and probation, first generation home arrest systems were introduced in 1987. While these systems proved to be helpful to the corrections system, their scope is rather limited because they only cover an offender at a single location and provide only a partial time coverage. To correct the limitations of first-generation systems, second-generation wide area continuous electronic offender monitoring systems, designed to monitor the offender at all times and locations, are now on the drawing board. These systems use radio frequency location technology to track the position of offenders. The challenge for this technology is the development of reliable personal locator devices that are small, lightweight, with long operational battery life, and indoors/outdoors accuracy of 100 meters or less. At the center of a second-generation system is a database that specifies the offender`s home, workplace, commute, and time the offender should be found in each. The database could also define areas from which the offender is excluded. To test compliance, the system would compare the observed coordinates of the offender with the stored location for a given time interval. Database logfiles will also enable law enforcement to determine if a monitored offender was present at a crime scene and thus include or exclude the offender as a potential suspect.

Radiological environmental monitoring with LiF-700-H dosemeters

International Nuclear Information System (INIS)

Scarnichia, E.; Levanon, I.; Andres, P.; Miani, C.; Ramirez, S.

2011-10-01

Since 2008 a radiological environmental monitoring with LiF-700-H has been carried out as a result of increasing the Ra-6 research reactor core power. The information obtained is used to evaluate and to quantify analytically the air kerma rate, the fading and the associated uncertainty by developing software tools (deconvolution and uncertainty algorithms). LiF-700-H dosemeters were chosen because of their high sensitivity to low air kerma rates. They show a very good stability and a negligible fading for two-month working periods. The air kerma rate detection limit (based on the 3σ criterion) during these working periods is about 0.4 n Gy/h. Air kerma rates of about 70 n Gy/h are measured with this detection limit. Following the Nist guidelines, an algorithm was developed in order to find the associated uncertainty. It considers several aspects, such as the source activity decay, distance source-dosemeter during the calibration procedure, irradiation time, calibration factor, dosemeter readout, dosemeter sensitivity, TLD reader stability and fading. The associated uncertainty is found to be about 25% for a 95% confidence interval (k = 2.025), which can be considered acceptable when taking into account the very low air kerma rates estimated. The LiF-700-H response to different energies and its relationship with climate changes over the calendar year are planned as future tasks. (Author)

Development of a software for predicting the effects of nuclear and radiological terrorism events in city areas

International Nuclear Information System (INIS)

Luo Lijuan; Chen Bo; Zhuo Weihai; Lu Shuyu

2011-01-01

Objective: To develop a new software system that can directly display the predicted results on an electronic map, in order to get a directly perceived understanding of the affected areas of nuclear and radiological terrorism events in city areas. Methods: Three scenarios of events including spreading radioactive materials, dirty bomb attack, and explosion or arson attacks on the radiation facilities were assumed. Gaussian diffusion model was employed to predict the spread and deposition of radioactive pollutants, and both the internal and external doses were estimated for the representative person by using the corresponding dose conversion factors. Through integration of the computing system and Mapinfo geographic information system (GIS), the predicted results were visually displayed on the electronic maps of a city. Results: The new software system could visually display the predicted results on the electronic map of a city, and the predicted results were consistent with those calculated by the similar software Hotspot®. The deviation between this system and Hotspot was less than 0.2 km for predicted isoplethic curves of dose rate downwind. Conclusions: The newly developed software system is of the practical value in predicting the effects of nuclear and radiological terrorism events in city areas. (authors)

Surface water sampling and analysis plan for environmental monitoring in Waste Area Grouping 6 at Oak Ridge National Laboratory, Oak Ridge, Tennessee. Environmental Restoration Program

Energy Technology Data Exchange (ETDEWEB)

1994-06-01

This Sampling and Analysis Plan addresses surface water monitoring, sampling, and analysis activities that will be conducted in support of the Environmental Monitoring Plan for Waste Area Grouping (WAG) 6. WAG 6 is a shallow-burial land disposal facility for low-level radioactive waste at the Oak Ridge National Laboratory, a research facility owned by the US Department of Energy and managed by Martin Marietta Energy Systems, Inc. Surface water monitoring will be conducted at nine sites within WAG 6. Activities to be conducted will include the installation, inspection, and maintenance of automatic flow-monitoring and sampling equipment and manual collection of various water and sediment samples. The samples will be analyzed for various organic, inorganic, and radiological parameters. The information derived from the surface water monitoring, sampling, and analysis will aid in evaluating risk associated with contaminants migrating off-WAG, and will be used in calculations to establish relationships between contaminant concentration (C) and flow (Q). The C-Q relationship will be used in calculating the cumulative risk associated with the off-WAG migration of contaminants.

Surface water sampling and analysis plan for environmental monitoring in Waste Area Grouping 6 at Oak Ridge National Laboratory, Oak Ridge, Tennessee. Environmental Restoration Program

International Nuclear Information System (INIS)

1994-06-01

This Sampling and Analysis Plan addresses surface water monitoring, sampling, and analysis activities that will be conducted in support of the Environmental Monitoring Plan for Waste Area Grouping (WAG) 6. WAG 6 is a shallow-burial land disposal facility for low-level radioactive waste at the Oak Ridge National Laboratory, a research facility owned by the US Department of Energy and managed by Martin Marietta Energy Systems, Inc. Surface water monitoring will be conducted at nine sites within WAG 6. Activities to be conducted will include the installation, inspection, and maintenance of automatic flow-monitoring and sampling equipment and manual collection of various water and sediment samples. The samples will be analyzed for various organic, inorganic, and radiological parameters. The information derived from the surface water monitoring, sampling, and analysis will aid in evaluating risk associated with contaminants migrating off-WAG, and will be used in calculations to establish relationships between contaminant concentration (C) and flow (Q). The C-Q relationship will be used in calculating the cumulative risk associated with the off-WAG migration of contaminants

Development of a Real-time Hand Dose Monitor for Personnel in Interventional Radiology

Energy Technology Data Exchange (ETDEWEB)

Ban, N.; Nakaoka, H.; Haruta, R.; Murakami, Y.; Kubo, T.; Maeda, T.; Kusama, T

2001-07-01

Medical procedures denoted as interventional radiology require operation near an X ray beam, which brings high dose exposures to the operators' hands. For the effectual control of their extremity doses, a prototype of a real-time wrist dosemeter has been developed, hand dose monitor (HDM), based on a single silicon detector. Experiments were performed to test its response to diagnostic X rays. The HDM was highly sensitive and showed a linear response down to doses of a few tens of microsieverts. Though dose rate, energy and angular dependence of the response were observed in some extreme conditions, the HDM was proved to be of practical use if it was appropriately calibrated. Since an HDM enables personnel to check their hand doses on a real-time basis, it would enable medical staff to control the exposure themselves. (author)

Resources planning for radiological incidents management

Science.gov (United States)

Hamid, Amy Hamijah binti Ab.; Rozan, Mohd Zaidi Abd; Ibrahim, Roliana; Deris, Safaai; Yunus, Muhd. Noor Muhd.

2017-01-01

Disastrous radiation and nuclear meltdown require an intricate scale of emergency health and social care capacity planning framework. In Malaysia, multiple agencies are responsible for implementing radiological and nuclear safety and security. This research project focused on the Radiological Trauma Triage (RTT) System. This system applies patient's classification based on their injury and level of radiation sickness. This classification prioritizes on the diagnostic and treatment of the casualties which include resources estimation of the medical delivery system supply and demand. Also, this system consists of the leading rescue agency organization and disaster coordinator, as well as the technical support and radiological medical response teams. This research implemented and developed the resources planning simulator for radiological incidents management. The objective of the simulator is to assist the authorities in planning their resources while managing the radiological incidents within the Internal Treatment Area (ITA), Reception Area Treatment (RAT) and Hospital Care Treatment (HCT) phases. The majority (75%) of the stakeholders and experts, who had been interviewed, witnessed and accepted that the simulator would be effective to resolve various types of disaster and resources management issues.

National automatic network of environmental radiological monitoring (RENAMORA); Red Nacional automatica de monitoreo radiologico ambiental (RENAMORA)

Energy Technology Data Exchange (ETDEWEB)

Gonzalez M, J.L.; Sanchez H, L. [CNSNS, Dr. Barragan 779, Col. Narvarte, 03020 Mexico D.F. (Mexico)]. e-mail: jlgonzalez@cnsns.gob.mx

2003-07-01

Inside the programs of Environmental Radiological Surveillance that it carries out the National Commission of Nuclear Security and Safeguards (CNSNS), it develops an National Automatic Network of Environmental Radiological Monitoring (RENAMORA), where it is carried out a registration of speed of environmental dose in continuous and simultaneous forms with the same moment of the measurement. This net allows to account with the meticulous and opportune information that will help to characterize, in dynamics form, the radiological conditions of diverse geographical zones of the country, including the sites that by normative require bigger surveillance, like its are the Laguna Verde Nuclear power station (CNLV), the Nuclear Center of Mexico (ININ) and the Radioactive waste storage center (CADER). This net is in its first development stage; three points inside the state of Veracruz, in the surroundings of the CNLV, already its are operating; the obtained data of rapidity of environmental dose are being stored in a database inside a primary data center located in the facilities of the CNSNS in Mexico city and its will be analyzed according to the project advances. At the moment, its are installing the first ten teams corresponding to the first phase of the RENAMORA (three stages); its are carried out operation tests, transmission, reception and administration of data. The obtained data will be interpreted, analyzed and inter compared to evaluate the risk levels to that it would be hold the population and to determine thresholds that allow to integrate the alarm systems that its had considered for emergency situations. (Author)

Facility effluent monitoring plan determinations for the 400 Area facilities

International Nuclear Information System (INIS)

Nickels, J.M.

1991-09-01

This Facility Effluent Monitoring Plan determination resulted from an evaluation conducted for the Westinghouse Hanford Company 400 Area facilities on the Hanford Site. The Facility Effluent Monitoring Plan determinations have been prepared in accordance with A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans. Two major Westinghouse Hanford Company facilities in the 400 Area were evaluated: the Fast Flux Test Facility and the Fuels Manufacturing and examination Facility. The determinations were prepared by Westinghouse Hanford Company. Of these two facilities, only the Fast Flux Test Facility will require a Facility Effluent Monitoring Plan. 7 refs., 5 figs., 4 tabs

Evaluation of Radiological Impacts on the Operating Kartini Reactor and Natural Radioactivity of the Site Plan of Nuclear Power Plant Area

International Nuclear Information System (INIS)

Yazid, M; Sutresna, G; Sulistyono, A; Ngasifudin

1996-01-01

This radiological impacts evaluation covered of radioactivity in water, soil, grass, air samples and ambient gamma radiation that have been carried out in the Kartini reactor area and in the site plan of nuclear power plan are at Ujung Lemah Abang, Jepara, Central Java. The aim of this research was to determine that radiological impacts in the environment around the Kartini reactor compared to natural radioactivity for site plan of nuclear power plan area. The radioactivity in the water, soil and grass samples ware measured by low background beta counting system and were identified by low background gamma spectrometer. The radioactivity in the air samples was measured by beta portable counting system and the ambient gamma radiation was measured by portable high pressurized ionization chamber model RSS-112 Reuther-Stokes. The reactor data measurement was compared to the site plan of nuclear power plant area data for evaluation of radiological impacts on the operating reactor. From the evaluation and comparison can be concluded there are no indication of the radionuclide release from the reactor operation. The average radiactivity in the water, soil grass and air sample from the reactor area were between 0.17 - 0.61 Bq/1; 0,47 - 0,74 Bq/g; 4.43 - 4.60 Bq/g.ash and 49.53 - 70.90 x 10 Bq/cc. The average radioactivity of those sample from the nuclear power plant area were between 0.06-0.90 Bq/I; 0.02-0.86 Bq/g; 1.68-8.07 Bq/g.ash and 65.0-152.3 x 10 Bq/cc. The ambient gamma radiation were between 6.9-36.7 urad/h for the reactor area and 6.8-19.2 urad/h for the nuclear power plant area

Surface radiological investigations at the 0816 Site, Waste Area Grouping 13, Oak Ridge National Laboratory, Oak Ridge, Tennessee

International Nuclear Information System (INIS)

Tiner, P.F.; Uziel, M.S.

1994-12-01

A surface radiological investigation was conducted intermittently from July through September 1994 at the 0816 site, located within Waste Area Grouping (WAG) 13. The survey was performed by members of the Measurement Applications and Development Group, Health Sciences Research Division, Oak Ridge National Laboratory (ORNL) at the request of ORNL Site Environmental Restoration Program Facility Management. The purpose of the survey was to ascertain and document the surface radiological condition of the site subsequent to remedial action activities completed in May 1994. The survey was designed to determine whether any residual surface sod contamination in excess of 120 pCi/g 137 Cs (Specified by the Interim Record of Decision) remained at the site

Radiological emergency: Malaysian preparedness and response

International Nuclear Information System (INIS)

Yusof, M. A. W.; Ali, H. M.

2011-01-01

Planning and preparation in advance for radiological emergencies can help to minimise potential public health and environmental threats if and when an actual emergency occurs. During the planning process, emergency response organisations think through how they would respond to each type of incident and the resources that will be needed. In Malaysia, planning, preparation for and response to radiological emergencies involve many parties. In the event of a radiological emergency and if it is considered a disaster, the National Security Council, the Atomic Energy Licensing Board and the Malaysian Nuclear Agency (Nuclear Malaysia) will work together with other federal agencies, state and local governments, first responders and international organisations to monitor the situation, contain the release, and clean up the contaminated site. Throughout the response, these agencies use their protective action guidelines. This paper discusses Malaysian preparedness for, and response to, any potential radiological emergency. (authors)

NV/YMP radiological control manual, Revision 2

International Nuclear Information System (INIS)

Gile, A.L.

1996-11-01

The Nevada Test Site (NTS) and the adjacent Yucca Mountain Project (YMP) are located in Nye County, Nevada. The NTS has been the primary location for testing nuclear explosives in the continental US since 1951. Current activities include operating low-level radioactive and mixed waste disposal facilities for US defense-generated waste, assembly/disassembly of special experiments, surface cleanup and site characterization of contaminated land areas, and non-nuclear test operations such as controlled spills of hazardous materials at the hazardous Materials (HAZMAT) Spill Center (HSC). Currently, the major potential for occupational radiation exposure is associated with the burial of low-level nuclear waste and the handling of radioactive sources. Planned future remediation of contaminated land areas may also result in radiological exposures. The NV/YMP Radiological Control Manual, Revision 2, represents DOE-accepted guidelines and best practices for implementing Nevada Test Site and Yucca Mountain Project Radiation Protection Programs in accordance with the requirements of Title 10 Code of Federal Regulations Part 835, Occupational Radiation Protection. These programs provide protection for approximately 3,000 employees and visitors annually and include coverage for the on-site activities for both personnel and the environment. The personnel protection effort includes a DOE Laboratory Accreditation Program accredited dosimetry and personnel bioassay programs including in-vivo counting, routine workplace air sampling, personnel monitoring, and programmatic and job-specific As Low as Reasonably Achievable considerations

NV/YMP radiological control manual, Revision 2

Energy Technology Data Exchange (ETDEWEB)

Gile, A.L. [comp.

1996-11-01

The Nevada Test Site (NTS) and the adjacent Yucca Mountain Project (YMP) are located in Nye County, Nevada. The NTS has been the primary location for testing nuclear explosives in the continental US since 1951. Current activities include operating low-level radioactive and mixed waste disposal facilities for US defense-generated waste, assembly/disassembly of special experiments, surface cleanup and site characterization of contaminated land areas, and non-nuclear test operations such as controlled spills of hazardous materials at the hazardous Materials (HAZMAT) Spill Center (HSC). Currently, the major potential for occupational radiation exposure is associated with the burial of low-level nuclear waste and the handling of radioactive sources. Planned future remediation of contaminated land areas may also result in radiological exposures. The NV/YMP Radiological Control Manual, Revision 2, represents DOE-accepted guidelines and best practices for implementing Nevada Test Site and Yucca Mountain Project Radiation Protection Programs in accordance with the requirements of Title 10 Code of Federal Regulations Part 835, Occupational Radiation Protection. These programs provide protection for approximately 3,000 employees and visitors annually and include coverage for the on-site activities for both personnel and the environment. The personnel protection effort includes a DOE Laboratory Accreditation Program accredited dosimetry and personnel bioassay programs including in-vivo counting, routine workplace air sampling, personnel monitoring, and programmatic and job-specific As Low as Reasonably Achievable considerations.

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

International Nuclear Information System (INIS)

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

2008-01-01

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

Manual for environmental radiological surveillance

International Nuclear Information System (INIS)

Sumiya, Shuichi; Matsuura, Kenichi; Nakano, Masanao; Takeyasu, Masanori; Morisawa, Masato; Onuma, Toshimitsu; Fujita, Hiroki; Mizutani, Tomoko; Watanabe, Hajime; Sugai, Masamitsu

2010-03-01

Environmental radiation monitoring around the Tokai Reprocessing Plant has been conducted by the Nuclear Fuel Cycle Engineering Laboratories, based on 'Safety Regulations for the Reprocessing Plant of JAEA, Chapter IV - Environmental monitoring' and Environmental Radiation Monitoring Program decided by the Ibaraki prefectural government. The radiation monitoring installations and equipments were also prepared for emergency. This manual describes; (1) the installations of radiological measurement, (2) the installations of meteorological observation, and (3) environmental data processing system for executing the terrestrial environmental monitoring by Environmental Protection Section, Radiation Protection Department. The environmental monitoring has been operated through the manual published in 1993 (PNC TN8520 93-001). Then the whole articles were revised because the partially of installations and equipments having been updated in recent years. (author)

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

Recognition difference and improvement direction of the radiological technologists and patient against medical service in department radiology - Inchon area in the object

International Nuclear Information System (INIS)

An, Sung Min; Kim, Sung Chul

2006-01-01

Satisfaction of the patient against the medical service in department of radiology and it evaluated the different recognition of radiological technologist and patient, and investigates it's improvement direction. It sent the reply the above the which is a usual result in question result of the most that, the receipt process it was complicated in the portion which is insufficient. 'The receipt process is complication', 'waiting time is long' and ' don't radiation protection for patient and guardian'. Also these a facts was recognizing patients and radiological technologist all. And the effort of the radiological technologist is necessary with the method which reduces a recognition difference. The periodical medical service satisfaction investigates and must endeavor in reform measure preparation

Impact of the application of criteria of internal monitoring in radiological protection programmes in nuclear medicine services

International Nuclear Information System (INIS)

Dantas, B.M.; Dantas, A.L.A.; Juliao, L.Q.C.; Lourenco, M.C.; Melo, D.R.

2005-01-01

The manipulation of open sources in Nuclear Medicine services involves risks of external exposure and internal contamination. The radiological protection plan of facilities licensed by CNEN - Brazilian Nuclear Energy Commission - must include the evaluation of such risks and propose a programme of individual monitoring to control exposure and ensure the maintenance of conditions of radiation safety. The IAEA - International Atomic Energy Agency - recommendations presented in the Safety Guide RS-G-1.2 suggest that an internal worker monitoring program be implemented where there is a possibility of internal contamination lead to effective dose committed annual values equal to or greater than 1 mSv. This paper presents the application of such criteria to the radionuclides most frequently used in the field of Nuclear Medicine, taking into account the normal conditions of handling and the ranges of activity authorized by CNEN. It is concluded that iodine 131 manipulation for therapeutic purposes is the practice that presented the greatest risk of internal exposure of workers, requiring the adoption of a programme of internal monitoring of Nuclear Medicine services

Preliminary site characterization radiological monitoring plan for the Nevada Nuclear Waste Storage Investigations Project, Yucca Mountain Site

International Nuclear Information System (INIS)

1987-03-01

The activities described in this plan occur in the early phases of site characterization. This document presents the Preliminary Site Characterization Radiological Monitoring Plan (PSCRMP) for collecting and evaluating data in support of the NNWSI Project. The PSCRMP defines and identifies control procedures for the monitoring activities. The PSCRMP activity will utilize integrating radon monitoring devices, a continuous radon monitor, and a particulate air sampler. These instruments will be used to establish the baseline radioactivity and/or radioactivity released due to early site characterization activities. The sections that follow provide a general project description, the specifics of the monitoring program, and the practices that will be employed to ensure the validity of the collected data by integrating quality assurance into all activities. Section 2 of this document describes the regulatory base of this document. Section 3 describes the site characterization activities which may lead to release of radioactivity. Section 4 provides a description of the potential sources of radioactivity that site characterization could generate. Section 5 summarizes the sampling and monitoring methodology, which will be used to monitor the potential sources of radioactivity. The network of sampling and monitoring equipment is described in Section 6, and Section 7 summarizes the systems operation activities. The data reporting activities are described in Section 8. Finally, a description of the Quality Assurance (QA) and Quality Control (QC) activities is provided in Section 9. Appendix A contains a summary of the procedures to be used in this program, and Appendix B contains technical specification on equipment and services. 20 refs., 11 figs., 2 tabs

Radiology

International Nuclear Information System (INIS)

Meyers, M.A.

1989-01-01

This paper reports on disease processes originating within the alimentary tract, may extend through the extraperitoneal spaces, and abnormalities primarily arising within other extraperitoneal sites may significantly affect the bowel. Symptoms and signs may be obscure, delayed, or nonspecific, and the area is generally not accessible to auscultation, palpation, or percussion. Radiologic evaluation thus plays a critical role

Noise control of radiological monitoring equipment

International Nuclear Information System (INIS)

Rubick, R.D.; Stevens, W.W.; Burke, L.L.

1998-01-01

Although vacuum pumps on continuous air monitors (CAMs) do not produce noise levels above regulatory limits, engineering controls were used to establish a safer work environment. Operations performed in areas where CAMs are located are highly specialized and require precision work when handling nuclear materials, heavy metals, and inert gases. Traditional methods for controlling noise such as enclosing or isolating the source and the use of personal protection equipment were evaluated. An innovative solution was found by retrofitting CAMs with air powered multistage ejectors pumps. By allowing the air to expand in several chambers to create a vacuum, one can eliminate the noise hazard altogether. In facilities with adequate pressurized air, use of these improved ejector pumps may be a cost-effective replacement for noisy vacuum pumps. A workplace designed or engineered with noise levels as low as possible or as close to background adds to increased concentration, attention to detail, and increased production