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

Radiological monitoring of food in Cuba

International Nuclear Information System (INIS)

Jerez V, S.F.

1996-01-01

The appearing of the problem for protecting the environment from radioactive contamination is not an accidental matter. The introduction into the earth crust of radioactive material coming from nuclear weapons, accidents, wastes, etc, has caused, as a consequence, the contamination of the biosphere. The extensive trade of food in our country has made necessary the establishment of radiological monitoring in food, which was organized by the Department of Public Health. The structure, functions, characteristics and aspects related to radiological monitoring of food in Cuba are shown in the present paper. The organization and resources for performing the monitoring program, both for normal conditions and for nuclear and/or radiological emergency cases, are detailed. (author). 12 refs., 2 figs

Routine Radiological Environmental Monitoring Plan. Volume 1

Energy Technology Data Exchange (ETDEWEB)

Bechtel Nevada

1999-12-31

The U.S. Department of Energy manages the Nevada Test Site in a manner that meets evolving DOE Missions and responds to the concerns of affected and interested individuals and agencies. This Routine Radiological Monitoring Plan addressess complicance with DOE Orders 5400.1 and 5400.5 and other drivers requiring routine effluent monitoring and environmental surveillance on the Nevada Test Site. This monitoring plan, prepared in 1998, addresses the activities conducted onsite NTS under the Final Environmental Impact Statement and Record of Decision. This radiological monitoring plan, prepared on behalf of the Nevada Test Site Landlord, brings together sitewide environmental surveillance; site-specific effluent monitoring; and operational monitoring conducted by various missions, programs, and projects on the NTS. The plan provides an approach to identifying and conducting routine radiological monitoring at the NTS, based on integrated technical, scientific, and regulatory complicance data needs.

Hyperion technology enables unified meteorological and radiological monitoring

International Nuclear Information System (INIS)

Zigic, A.; Saponjic, D.; Arandjelovic, V.; Zunic, Z. . E-mail address of corresponding author: alex@vin.bg.ac.yu; Zigic, A.)

2005-01-01

The present state of meteorological and radiological measurement and monitoring are quite localized to smaller areas which implies the difficulties in knowing the measurement results in the wider region instantly. The need for establishing a distributed, flexible, modular and centralized measurement system for both meteorological and radiological parameters of environment is arising. The measurement and monitoring of radiological parameters of environment are not sufficient since there is a strong correlation between radiological and meteorological parameters which implies a unified distributed automatic monitoring system. The unified monitoring system makes it possible to transfer, process and store measured data in local and central databases. Central database gives a possibility of easy access to all measured data for authorized personnel and institutions. Stored measured data in central database gives a new opportunity to create a base for meteorological and radiological modelling and studies. (author)

Radiological monitoring. Controlling surface water pollution

International Nuclear Information System (INIS)

Morin, Maxime

2018-01-01

Throughout France, surface waters (from rivers to brooks) located at the vicinity of nuclear or industrial sites, are subject to regular radiological monitoring. An example is given with the radiological monitoring of a small river near La Hague Areva's plant, where contaminations have been detected with the help of the French IRSN nuclear safety research organization. The sampling method and various measurement types are described

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)

Measurement and instrumentation techniques for monitoring plutonium and uranium particulates released from nuclear facilities

International Nuclear Information System (INIS)

Nero, A.V. Jr.

1976-08-01

The purpose of this work has been an analysis and evaluation of the state-of-the-art of measurement and instrumentation techniques for monitoring plutonium and uranium particulates released from nuclear facilities. The occurrence of plutonium and uranium in the nuclear fuel cycle, the corresponding potential for releases, associated radiological protection standards and monitoring objectives are discussed. Techniques for monitoring via decay radiation from plutonium and uranium isotopes are presented in detail, emphasizing air monitoring, but also including soil sampling and survey methods. Additionally, activation and mass measurement techniques are discussed. The availability and prevalence of these various techniques are summarized. Finally, possible improvements in monitoring capabilities due to alterations in instrumentation, data analysis, or programs are presented

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

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

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.

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)

Instrument evaluation no. 11. ESI nuclear model 271 C contamination monitor

International Nuclear Information System (INIS)

Burgess, P.H.; Iles, W.J.

1978-06-01

The various radiations encountered in radiological protection cover a wide range of energies and radiation measurements have to he carried out under an equally broad spectrum of environmental conditions. This report is one of a series intended to give information on the performance characteristics of radiological protection instruments, to assist in the selection of appropriate instruments for a given purpose, to interpret the results obtained with such instruments, and, in particular, to know the likely sources and magnitude of errors that might be associated with measurements in the field. The radiation, electrical and environmental characteristics of radiation protection instruments are considered together with those aspects of the construction which make an instrument convenient for routine use. To provide consistent criteria for instrument performance, the range of tests performed on any particular class of instrument, the test methods and the criteria of acceptable performance are based broadly on the appropriate Recommendations of the International Electrotechnical Commission. The radiations in the tests are, in general, selected from the range of reference radiations for instrument calibration being drawn up by the International Standards Organisation. Normally, each report deals with the capabilities and limitations of one model of instrument and no direct comparison with other instruments intended for similar purposes is made, since the significance of particular performance characteristics largely depends on the radiations and environmental conditions in which the instrument is to be used. The results quoted here have all been obtained from tests on instruments in routine production, with the appropriate measurements being made by the NRPB. This report deals with the ESI Nuclear Model 271 C; a general purpose contamination monitor, comprising a GM tube connected by a coiled extensible cable to a ratemeter

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)

Technological considerations in emergency instrumentation preparedness. Phase II-D. Evaluation testing and calibration methodology for emergency radiological instrumentation

International Nuclear Information System (INIS)

Bramson, P.E.; Andersen, B.V.; Fleming, D.M.; Kathren, R.L.; Mulhern, O.R.; Newton, C.E.; Oscarson, E.E.; Selby, J.M.

1976-09-01

In response to recommendations from the Advisory Committee on Reactor Safeguards, the Division of Operational Safety, U.S. ERDA has contracted with Battelle, Pacific Northwest Laboratories to survey the adequacy of existing instrumentation at nuclear fuel cycle facilities to meet emergency requirements and to develop technical criteria for instrumentation systems to be used in assessment of environmental conditions following plant emergencies. This report, the fifth in a series, provides: (1) calibration methods to assure the quality of radiological measurements and (2) testing procedures for determining whether an emergency radiological instrument meets the performance specifications. Three previous reports in this series identified the emergency instrumentation needs for power reactors, mixed oxide fuel plants, and fuel reprocessing facilities. Each of these three reports contains a Section VI, which sets forth applicable radiological instrument performance criteria and calibration requirements. Testing and calibration procedures in this report have been formatted in two parts: IV and V, each divided into three subsections: (1) Power Reactors, (2) Mixed Oxide Fuel Plants, and (3) Fuel Reprocessing Facilities. The three performance criteria subsections directly coincide with the performance criteria sections of the previous reports. These performance criteria sections have been reproduced in this report as Part III with references of ''required action'' added

Federal Radiological Monitoring and Assessment Center Overview of FRMAC Operations

International Nuclear Information System (INIS)

1998-01-01

In the event of a major radiological emergency, 17 federal agencies with various statutory responsibilities have agreed to coordinate their efforts at the emergency scene under the umbrella of the Federal Radiological Emergency Response Plan. This cooperative effort will ensure that all federal radiological assistance fully supports their efforts to protect the public. the mandated federal cooperation ensures that each agency can obtain the data critical to its specific responsibilities. This Overview of Federal Radiological Monitoring and Assessment Center (FRMAC) describes the FRMAC response activities to a major radiological emergency. It also describes the federal assets and subsequent operational activities which provide federal radiological monitoring and assessment of the off-site areas

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

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

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

Federal Radiological Monitoring and Assessment Center Monitoring Manual Volume 1, Operations

Energy Technology Data Exchange (ETDEWEB)

NSTec Aerial Measurement Systems

2012-07-31

The Monitoring division is primarily responsible for the coordination and direction of: Aerial measurements to delineate the footprint of radioactive contaminants that have been released into the environment. Monitoring of radiation levels in the environment; Sampling to determine the extent of contaminant deposition in soil, water, air and on vegetation; Preliminary field analyses to quantify soil concentrations or depositions; and Environmental and personal dosimetry for FRMAC field personnel, during a Consequence Management Response Team (CMRT) and Federal Radiological Monitoring and Assessment Center (FRMAC) response. Monitoring and sampling techniques used during CM/FRMAC operations are specifically selected for use during radiological emergencies where large numbers of measurements and samples must be acquired, analyzed, and interpreted in the shortest amount of time possible. In addition, techniques and procedures are flexible so that they can be used during a variety of different scenarios; e.g., accidents involving releases from nuclear reactors, contamination by nuclear waste, nuclear weapon accidents, space vehicle reentries, or contamination from a radiological dispersal device. The Monitoring division also provides technicians to support specific Health and Safety Division activities including: The operation of the Hotline; FRMAC facility surveys; Assistance with Health and Safety at Check Points; and Assistance at population assembly areas which require support from the FRMAC. This volume covers deployment activities, initial FRMAC activities, development and implementation of the monitoring and assessment plan, the briefing of field teams, and the transfer of FRMAC to the EPA.

Identification and monitoring of non-radiological carcinogens

Energy Technology Data Exchange (ETDEWEB)

Chuaqui, C A; Petkau, A; Greenstock, C L; Brown, C P [Atomic Energy of Canada Ltd., Pinawa, MB (Canada). Whiteshell Labs.

1995-09-01

This study examines the feasibility of identifying and monitoring occupational exposures to non-radiological carcinogens in the workplace at Canadian nuclear establishments (Whiteshell Laboratories, Pickering Nuclear Generating Station, Cameco Limited and Canadian General Electric Company Limited). Recent epidemiological studies recommended that potential confounding factors of a non-radiological nature be identified and analyzed, particularly non-radiological carcinogens that may be present in the workplace at nuclear facilities. The feasibility of identifying and measuring occupational exposures to non-radiological carcinogens in Canadian nuclear facilities is examined. Also, the report describes the problem of chemical carcinogens and the mechanisms involved in chemical carcinogenesis; the epidemiology related to the problem, followed by a description of the analytical aspects of detection, monitoring and analysis of carcinogens, as well as a discussion on the regulatory aspects and the regulations in place; and the findings, recommendations and concluding remarks of this study. Several problem areas became apparent as the study proceeded. For example, the classification of a chemical as a human carcinogen is a difficult problem, as is its adequate monitoring and analysis. This situation reflects, in turn, the regulatory aspects in the workplace. A list of chemical carcinogens used industrially at the four Canadian nuclear facilities has been identified. The list includes arsenic, asbestos, benzene, cadmium, beryllium, nickel, polychlorinated biphenyls, lead and trichloroethylene. Several recommendations are made in relation to the need for practical and efficient monitoring methods for chemical carcinogens, the definition of radiation and chemical dose equivalencies, and the classification of human chemical carcinogens, as well as their disposal. (author). 122 refs., 8 tabs., 6 figs.

Identification and monitoring of non-radiological carcinogens

International Nuclear Information System (INIS)

Chuaqui, C.A.; Petkau, A.; Greenstock, C.L.; Brown, C.P.

1995-09-01

This study examines the feasibility of identifying and monitoring occupational exposures to non-radiological carcinogens in the workplace at Canadian nuclear establishments (Whiteshell Laboratories, Pickering Nuclear Generating Station, Cameco Limited and Canadian General Electric Company Limited). Recent epidemiological studies recommended that potential confounding factors of a non-radiological nature be identified and analyzed, particularly non-radiological carcinogens that may be present in the workplace at nuclear facilities. The feasibility of identifying and measuring occupational exposures to non-radiological carcinogens in Canadian nuclear facilities is examined. Also, the report describes the problem of chemical carcinogens and the mechanisms involved in chemical carcinogenesis; the epidemiology related to the problem, followed by a description of the analytical aspects of detection, monitoring and analysis of carcinogens, as well as a discussion on the regulatory aspects and the regulations in place; and the findings, recommendations and concluding remarks of this study. Several problem areas became apparent as the study proceeded. For example, the classification of a chemical as a human carcinogen is a difficult problem, as is its adequate monitoring and analysis. This situation reflects, in turn, the regulatory aspects in the workplace. A list of chemical carcinogens used industrially at the four Canadian nuclear facilities has been identified. The list includes arsenic, asbestos, benzene, cadmium, beryllium, nickel, polychlorinated biphenyls, lead and trichloroethylene. Several recommendations are made in relation to the need for practical and efficient monitoring methods for chemical carcinogens, the definition of radiation and chemical dose equivalencies, and the classification of human chemical carcinogens, as well as their disposal. (author). 122 refs., 8 tabs., 6 figs

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

Soil monitoring instrumentation

International Nuclear Information System (INIS)

Umbarger, C.J.

1980-01-01

The Los Alamos Scientific Laboratory (LASL) has an extensive program for the development of nondestructive assay instrumentation for the quantitative analysis of transuranic (TRU) materials found in bulk solid wastes generated by Department of Energy facilities and by the commercial nuclear power industry. Included are wastes generated in decontamination and decommissioning of outdated nuclear facilities as well as wastes from old waste burial ground exhumation programs. The assay instrumentation is designed to have detection limits below 10 nCi/g wherever practicable. Because of the topic of this workshop, only the assay instrumentation applied specifically to soil monitoring will be discussed here. Four types of soil monitors are described

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)

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

Calibration of radiation monitoring instruments

International Nuclear Information System (INIS)

1973-01-01

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

Calibration of radiation monitoring instruments

Energy Technology Data Exchange (ETDEWEB)

NONE

1974-12-31

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

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)

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.

Design principles for radiological protection instrumentation systems

International Nuclear Information System (INIS)

Wells, F.H.; Powell, R.G.

1981-02-01

This Code of Practice takes the form of recommendations intended for designers and installers of Radiological Protection Instrumentation, and should also be of value to the newcomer to the R.P.I. field. Topics are discussed under the following headings: outline of R.P.I. requirements, specifying the requirement, satisfying the requirements, (overall design, availability and reliability, information display, human factors, power supplies, manufacture, quality assurance, testing, and cost analysis), supply, location and operation of the equipment, importance of documentation. (U.K.)

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)

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

Federal Radiological Monitoring and Assessment Center (FRMAC) overview of FRMAC operations

International Nuclear Information System (INIS)

1996-02-01

In the event of a major radiological emergency, 17 federal agencies with various statutory responsibilities have agreed to coordinate their efforts at the emergency scene under the umbrella of the Federal Radiological Emergency Response plan (FRERP). This cooperative effort will assure the designated Lead Federal Agency (LFA) and the state(s) that all federal radiological assistance fully supports their efforts to protect the public. The mandated federal cooperation ensures that each agency can obtain the data critical to its specific responsibilities. This Overview of the Federal Radiological Monitoring and Assessment Center (FRMAC) Operations describes the FRMAC response activities to a major radiological emergency. It also describes the federal assets and subsequent operational activities which provide federal radiological monitoring and assessment of the off-site areas. These off-site areas may include one or more affected states

Instrumentation requirements for radiological defense of the U.S. population in community shelters. Final report

International Nuclear Information System (INIS)

Haaland, C.M.; Gant, K.S.

1978-08-01

Estimates are made of requirements for instruments for radiological defense of the U.S. population in the event of a nuclear attack. A detailed Community Shelter Plan posture is developed for each of 42,000 Standard Location Areas. Travel distance from residence to shelter in urban areas is limited to approximately 1 mile. Sixty percent of the U.S. population is sheltered in home basements, thirty-one percent in National Shelter Survey shelters, and nine percent is in neither. Three minimum allocations of instruments are developed. Allocation A, one radiological defense set per shelter, is essentially the same as the current civil defense allocations but is found to be inadequate for about 100,000 shelters having more than 100 occupants. Allocation B requires 3.4 million new dosimeters based on estimated shelter occupancy and provides a minimum instrumentation for radiological defense but not enough instruments to maintain individual dose records. Allocation C would require 18.1 million new dosimeters and would provide adequate instrumentation to maintain dose records for all shelter occupants

Nuclear radiation monitoring instruments for personnel in nuclear disaster for defence needs

International Nuclear Information System (INIS)

Bhatnagar, P.K.; Vaijapurkar, S.G.; Yadav, Ashok

2005-01-01

Ever since the tragedy of nuclear device exploding over Japan by USA in 1945 awareness exists amongst the armed forces personnel all over the world that a requirement of implementing radiological protection is imminent. Towards this adoption of radiological safety programme is a criterion. In a nuclear war disaster scenario, one encounters initial nuclear radiation (gamma and neutron radiations), gamma radiations from fallout, heat and blast. At certain distances Tanks/ armoured vehicles will survive and 4 R/s radiation level sensing to actuate relays for closing the ports of vehicles is essential, leading to reduction in inhalation, ingestion of fallout radioactivity and reduction in radiation dose received by occupants of the vehicle. Towards this sturdy radiation monitors to indicate gamma dose rate of the order of 1000 R/h, gamma and neutron dosimeters of the order of 1000 cGy with reading instruments are to be developed. These must work in harsh environment and sustain JSS 55555 conditions of army. Defence Laboratory, Jodhpur over past one decade has been involved in developing personnel, area and field monitoring instruments like dosimeters, survey meters, which are useful, acceptable to army personnel, armoured and personnel carrier vehicles, field structures/shelters. Technology transfer after satisfaction of armed forces, product ionisation and supply, maintenance, training has been the endeavor of the DRDO. Herein it is proposed to highlight the techno electronics nuclear radiation monitoring sensors and associated electronics systems developed first time in the country and productionised in bulk for Services for implementing personnel protection. The sensors developed and described are - Radiophotoluminescent Glass (RPLG) for gamma radiation dosimetry , neutron sensitive PIN diode for fast neutron dosimetry, gamma radiation sensitive PIN diode, superheated liquid neutron and gamma sensors. The dosimeter, dose rate meter and field/area instruments are

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

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

Characterization of different qualities in X-rays, for instruments calibration in radiological protection

International Nuclear Information System (INIS)

Cejudo A, J.; Tovar M, V. M.; Vergara M, F.

2010-09-01

In the Secondary Laboratory of Dosimetric Calibration in Mexico was realized the qualities characterization of the series X-rays RQR reported in the International Code of Practices in Dosimetry and Diagnostic Radiology No. 457, using attenuator filters of high purity aluminum and ionizing radiation equipment of inherent filtration of 4 mm Be with and emergent X-radiation beam of 40 grades. For the attenuation was used a geometric arrangement with three beam limiters and a monitor camera prepared on the established form in the mentioned technical report, and a spherical ionization chamber with collection volume of 3.6 cm 3 , aligning its geometric center with the focus of X-rays tube to get that the incident radiation direction will be perpendicular to the ionization chamber. From the perspective of the radiological protection is important to know the X-radiation quality for the application dedicated to the instruments calibration and can to give to these the traceability to a reference laboratory, this way the quality combination and reference chamber can give as a result a procedure for the evaluation of the entrance in surface dose to estimate the dose orientate levels, specified in the basic standards of safety. (Author)

Soil monitoring instrumentation

International Nuclear Information System (INIS)

Umbarger, C.J.

1981-01-01

The Los Alamos Scientific Laboratory (LASL) has an extensive program for the development of nondestructive assay instrumentation for the quantitative analysis of transuranic (TRU) materials found in bulk solid wastes generated by Department of Energy facilities and by the commercial nuclear power industry. Included are wastes generated in decontamination and decommissioning of outdated nuclear facilities, as well as from old waste-burial-ground exhumation programs. The assay instrumentation is designed to have detection limits below 10 nCi/g wherever practicable. The assay instrumentation that is applied specifically to soil monitoring is discussed

The application of geographic information system to radiological and nuclear emergency monitoring

International Nuclear Information System (INIS)

Sadaniowski, I.V.; Rodriguez, M.; Rojas, C.A.; Jordan, O.D.

2010-01-01

The Geographic Information System (GIS) implementation for the preparation and response in case of to radiological and nuclear emergencies is being developed in the Emergency Control Center of the Argentina Nuclear Regulatory Authority, since many years ago. Additionals features have been incorporated such as integration with the results of radiological monitoring, improving and expanding its benefits both in the preparation stage and during the work of emergency response. This paper shows the specific application of GIS to radiological monitoring in case of emergency situations such as during the search of orphan sources and the characterization of geographic context around nuclear power plants and atomic centers. The GIS provides essential data cartographic for the monitoring with sophisticated detectors, to integrate with the information received with infrastructure, urban and rural population maps, physical features of the place, satellite images, etc. The monitoring results are analyzed and compared with relevant information for decision making during the response, like evacuation routes, affected population, security forces in the area, radiological characterization, application of protective actions, hospitals, schools, etc. These two integrated tools improve preparedness and response system in case of radiological or nuclear emergency. (authors) [es

Instrument evaluation no. 11. ESI nuclear model 271 C contamination monitor

CERN Document Server

Burgess, P H

1978-01-01

The various radiations encountered in radiological protection cover a wide range of energies and radiation measurements have to he carried out under an equally broad spectrum of environmental conditions. This report is one of a series intended to give information on the performance characteristics of radiological protection instruments, to assist in the selection of appropriate instruments for a given purpose, to interpret the results obtained with such instruments, and, in particular, to know the likely sources and magnitude of errors that might be associated with measurements in the field. The radiation, electrical and environmental characteristics of radiation protection instruments are considered together with those aspects of the construction which make an instrument convenient for routine use. To provide consistent criteria for instrument performance, the range of tests performed on any particular class of instrument, the test methods and the criteria of acceptable performance are based broadly on the a...

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)

Airborne systems for emergency radiological monitoring

International Nuclear Information System (INIS)

Jupiter, C.; Boyns, P.

1976-01-01

A variety of aerial radiological monitoring systems are available to respond to a radiological accident or incident affecting large areas. These are operated by EG and G, Inc. for ERDA's Division of Operational Safety. A survey system can be airborne within approximately two hours after notification. Both airborne and terrestrial radioactivity can be measured and mapped. Special analysis procedures allow discrimination between radioactivity from most man-made radioelements and naturally occurring radioelements. A position accuracy of +-54 feet can be maintained over a large area survey. Detection sensitivity for gamma sources employing NaI detector arrays on board an airplane flying at 500 feet altitude is better than 2 μR/hr for surface planar contaminants and approximately 10 mCi for a point gamma source

Instruments for Water Quality Monitoring

Science.gov (United States)

Ballinger, Dwight G.

1972-01-01

Presents information regarding available instruments for industries and agencies who must monitor numerous aquatic parameters. Charts denote examples of parameters sampled, testing methods, range and accuracy of test methods, cost analysis, and reliability of instruments. (BL)

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

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.

Instrumentation for environmental monitoring: biomedical

International Nuclear Information System (INIS)

1979-05-01

An update is presented to Volume four of the six-volume series devoted to a survey of instruments useful for measurements in biomedicine related to environmental research and monitoring. Results of the survey are given as descriptions of the physical and operating characteristics of available instruments, critical comparisons among instrumentation methods, and recommendations of promising methodology and development of new instrumentation. Methods of detection and analysis of gaseous organic pollutants and metals, including Ni and As are presented. Instrument techniques and notes are included on atomic spectrometry and uv and visible absorption instrumentation

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

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

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

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

Report on a visit to Canada to discuss tritium instrumentation and radiological protection

International Nuclear Information System (INIS)

Gibson, J.A.B.

1984-10-01

A report is presented of a visit to Canada on behalf of the CEC DG II/Fusion between the 8th to 13th April 1984. Discussions were arranged by the Canadian Fusion-Fuels Technology Project near Toronto and covered all aspects of tritium technology but especially radiological protection. Visits included the CFFTP Centre, Pickering Nuclear Generating Section, Ontario Hydro's Head Office, Safety Services Department and Research Division, Scintrex Ltd (tritium instrument manufacturers) and the Atomic Energy of Canada (AECL) Chalk River Nuclear laboratories (CRNL). There are clearly many areas for the use of Canadian Technology in Europe, particularly with CRNL and Scintrex on the development of 3 H 2 / 3 H 2 O discriminating monitors. There is some doubt whether these development will be in time for applications at the JET laboratory and the JRC at ISPRA but this collaboration will be pursued. (author)

SMART instruments for radiological surveillance at the back end of nuclear fuel cycle

International Nuclear Information System (INIS)

Pendharkar, K.A.; Jauhri, G.S.; Ganesh, G.; Kulkarni, V.V.

2001-01-01

The back end of Nuclear Fuel Cycle mainly consists of Fuel Reprocessing Plant and Waste Management Plant for treatment of different types of wastes generated during processing of spent fuel. A fuel reprocessing plant handles annually several million curies of fission product activity and few hundred kg of plutonium. A Waste Management Facility associated with a reprocessing plant also handles several million curies of fission product activity. In both the plants several types of radiological measurements have to be carried out to ensure that the individual doses are well below regulatory limits and release of radioactivity to environment (through stack and through liquid effluent) is below the limit stipulated in technical specifications of the plant. The measurements comprise individual external dose, measurement of radiation level in different areas of the plant, assessment of air-borne activity due to plutonium and fission products in different areas of the plant, radioactivity release to environment through liquid effluents and through stack. In order to carry out the above mentioned measurements large number of different types of instruments are required. The existing instruments are analog instruments. These instruments have served well. However they have certain limitations with respect to flexibility and extra functionality. In this respect the 'SMART' instruments have distinct advantages. The advantages, that are offered by the 'SMART' instrument in making the radiological surveillance programme more effective, are brought out in the paper. (author)

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

Radioactive standards and calibration methods for contamination monitoring instruments

Energy Technology Data Exchange (ETDEWEB)

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

1997-06-01

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

Development of a calibration methodology for instruments used to interventional radiology quality control

International Nuclear Information System (INIS)

Miranda, Jurema Aparecida de

2009-01-01

Interventional radiology is the technique where X radiation images are used as a tool in the conduction of diagnostic or/and therapeutic procedures. The exposition times are long for both procedures, diagnostic and therapeutic, may cause serious injuries in the patient, and also contribute to the dose of the clinical staff. In Brazil there are not yet well established rules to determine the doses and to make the dosimetry in fluoroscopic beams. There is great interest in this study, in relation to the beam quality, the half-value-layer, and others parameters. In this work a Medicor Neo Diagnomax clinical X ray generator, fluoroscopy mode, was used to develop a calibration methodology for instruments used in interventional radiology quality control. One plane parallel ionization chamber PTW was used as monitor. The ionization chambers recommended for fluoroscopy measurements had been evaluated and calibrated in relation to the IPEN Calibration Laboratory reference ionization chamber. The RQR3, RQR5 and RQR7 radiation qualities and the specific ones for fluoroscopy, RQC3, RQC5 and RQC7, were established following the norm IEC 61267. All beams characteristics were determined. Ionization chambers positioning system and the acrylic phantoms to the entrance and exit doses determination were developed and constructed. The results obtained show air kerma rates of 4.5x10 -3 , 1.2x10 -2 and 1.9x10 -2 Gy/min for RQC3, RQC5 and RQC7 respectively. Tests with and without the collimation just after the monitor chamber, were carried out and the results showed a difference of +5.5%, +0.6% e + 0.8%, confirming the importance of the collimation use in these interventionist procedures. (author)

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

Standard audit procedure for continuous emission monitors and ambient air monitoring instruments

Energy Technology Data Exchange (ETDEWEB)

NONE

2009-06-15

The instruments were published in an operational policy manual in 2009. This policy aims to introduce standard audit criteria that can be used to determine if continuous emission monitors and ambient air monitoring devices are operating within acceptable parameters. Before delivering upscale points of the instrument to be audited, each one of the audit equipment used in the field is required to be at normal operating conditions. Before the beginning of the audit, each one of the meteorological and flow measurement equipment is required to be conditioned to current conditions. If the audit fails, the instrument will have to be audited quarterly. The establishment of specific procedures based on instrument manufacturer or certifying body operational standards is required in the case of non-continuous monitoring instruments presenting operational principles outside of the audit procedures listed in the document.

Radiological emergencies the first response

International Nuclear Information System (INIS)

2011-11-01

This national training course about radiological emergencies first answer include: Targets and preparation for emergency response in case of a nuclear or radiological accident. Operations center, action guide for fire fighting, medical coverage, forensic test, first aid, basic instrumentation for radiation, safety equipment, monitoring radiation, gamma rays, personnel exposed protection , radiation exposure rate, injury and illness for radiation, cancer risk, contamination, decontamination and treatment, markers, personnel dosimetry, training, medical and equipment transportation, shielded and tools. Psychological, physical (health and illness), economical (agriculture and industry) and environment impacts. Terrorist attacks, security belts. Support and international agreements (IAEA)

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

International Nuclear Information System (INIS)

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

2008-01-01

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

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)

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)

The ozone monitoring instrument

NARCIS (Netherlands)

Levelt, P.F.; Oord, G.H.J. van den; Dobber, M.R.; Mälkki, A.; Visser, H.; Vries, J. de; Stammes, P.; Lundell, J.O.V.; Saari, H.

2006-01-01

The Ozone Monitoring Instrument (OMI) flies on the National Aeronautics and Space Adminsitration's Earth Observing System Aura satellite launched in July 2004. OMI is a ultraviolet/visible (UV/VIS) nadir solar backscatter spectrometer, which provides nearly global coverage in one day with a spatial

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.)

Instrumentation for chemical and radiochemical monitoring in nuclear power plants

International Nuclear Information System (INIS)

Nordmann, F.; Ballard, G.

2009-01-01

This article details the instrumentation implemented in French nuclear power plants for the monitoring of chemical and radiochemical effluents with the aim of limiting their environmental impact. It describes the controls performed with chemical automata for the search for drifts, anomalies or pollution in a given circuit. The operation principles of the different types of chemical automata are explained as well as the manual controls performed on samples manually collected. Content: 1 - general considerations; 2 - objectives of the chemical monitoring: usefulness of continuous monitoring with automata, transmission to control rooms and related actions, redundancy of automata; 3 - instrumentation and explanations for the main circuits: principle of chemical automata monitoring, instrumentation of the main primary circuit, instrumentation of the main secondary circuit, instrumentation of the tertiary circuit, preparation of water makeup (demineralized water), other loops, instrumentation for effluents and environment monitoring, measurement principles of chemical automata, control and maintenance of chemical automata; 4 - manual controls after sampling; 5 - radiochemical monitoring: automatized radiochemical measurements, manual radiochemical measurements; 6 - conclusion

Onboard calibration and monitoring for the SWIFT instrument

International Nuclear Information System (INIS)

Rahnama, P; McDade, I; Shepherd, G; Gault, W

2012-01-01

The SWIFT (Stratospheric Wind Interferometer for Transport studies) instrument is a proposed space-based field-widened Doppler Michelson interferometer designed to measure stratospheric winds and ozone densities using a passive optical technique called Doppler Michelson imaging interferometry. The onboard calibration and monitoring procedures for the SWIFT instrument are described in this paper. Sample results of the simulations of onboard calibration measurements are presented and discussed. This paper also discusses the results of the derivation of the calibrations and monitoring requirements for the SWIFT instrument. SWIFT's measurement technique and viewing geometry are briefly described. The reference phase calibration and filter monitoring for the SWIFT instrument are two of the main critical design issues. In this paper it is shown that in order to meet SWIFT's science requirements, Michelson interferometer optical path difference monitoring corresponding to a phase calibration accuracy of ∼10 −3 radians, filter passband monitoring corresponding to phase accuracy of ∼5 × 10 −3 radians and a thermal stability of 10 −3 K s −1 are required. (paper)

Radioactive check sources for alpha and beta sensitive radiological instrumentation

International Nuclear Information System (INIS)

Barnett, J.M.; Kane, J.E. II.

1994-06-01

Since 1991, the Westinghouse Hanford Company has examined the construction and use of alpha and beta radioactive check sources for calibrating instruments and for performing response checks of instruments used for operational and environmental radiation detection. The purpose of using a radioactive check source is to characterize the response of a radiation monitoring instrument in the presence of radioactivity. To accurately calibrate the instrument and check its response, the check source used must emulate as closely as possible the actual physical and isotopic conditions being monitored. The isotope employed and the physical methods used to fabricate the check source (among other factors) determine instrument response. Although information from applicable national and international standards, journal articles, books, and government documents was considered, empirical data collected is most valuable when considering the type of source to use for a particular application. This paper presents source construction methods, use considerations, and standard recommendations. The results of a Hanford Site evaluation of several types of alpha and beta sources are also given

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

Development and implantation of a control and data acquisition program for the calibration of instruments for diagnostic radiology

International Nuclear Information System (INIS)

Betti, Flavio

2007-01-01

Design techniques of an automatic control system implementing corrected kerma determination and shutter command in the calibration laboratory at IPEN are shown, as well as the periodic calibration program developed for a monitor chamber for several X-ray beam qualities used for diagnostic radiology and radiation protection instruments. Two reference electrometers, a multichannel secondary standard thermometer, and an absolute pressure barometer were connected to the Rs-232 interface from a PC computer equipped with a National Instruments multi function analog and digital I/O card. LabVIEW MR was chosen as programming tool, which allowed for the development of a suite of programs for both controlling the shutter timing cycles and the calibration of the monitor chamber against a reference standard. A detailed description of the methods used for troubleshooting, fine tuning of parameters and evaluation of program results is followed by an analysis showing that considerable advantages regarding reduction of time and precision improvements during the calibrations could be achieved by the use of the developed programs, particularly under adverse conditions like those found during short expositions, or instead during long irradiation intervals where fluctuation of parameters like kerma rate or room conditions (temperature or pressure) can be found. (author)

Instrumentation for Air Pollution Monitoring

Science.gov (United States)

Hollowell, Craig D.; McLaughlin, Ralph D.

1973-01-01

Describes the techniques which form the basis of current commercial instrumentation for monitoring five major gaseous atmospheric pollutants (sulfur dioxide, oxides of nitrogen, oxidants, carbon monoxide, and hydrocarbons). (JR)

CLOUDCLOUD : general-purpose instrument monitoring and data managing software

Science.gov (United States)

Dias, António; Amorim, António; Tomé, António

2016-04-01

An effective experiment is dependent on the ability to store and deliver data and information to all participant parties regardless of their degree of involvement in the specific parts that make the experiment a whole. Having fast, efficient and ubiquitous access to data will increase visibility and discussion, such that the outcome will have already been reviewed several times, strengthening the conclusions. The CLOUD project aims at providing users with a general purpose data acquisition, management and instrument monitoring platform that is fast, easy to use, lightweight and accessible to all participants of an experiment. This work is now implemented in the CLOUD experiment at CERN and will be fully integrated with the experiment as of 2016. Despite being used in an experiment of the scale of CLOUD, this software can also be used in any size of experiment or monitoring station, from single computers to large networks of computers to monitor any sort of instrument output without influencing the individual instrument's DAQ. Instrument data and meta data is stored and accessed via a specially designed database architecture and any type of instrument output is accepted using our continuously growing parsing application. Multiple databases can be used to separate different data taking periods or a single database can be used if for instance an experiment is continuous. A simple web-based application gives the user total control over the monitored instruments and their data, allowing data visualization and download, upload of processed data and the ability to edit existing instruments or add new instruments to the experiment. When in a network, new computers are immediately recognized and added to the system and are able to monitor instruments connected to them. Automatic computer integration is achieved by a locally running python-based parsing agent that communicates with a main server application guaranteeing that all instruments assigned to that computer are

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

Instrument failure monitoring in nuclear power systems

International Nuclear Information System (INIS)

Tylee, J.L.

1982-01-01

Methods of monitoring dynamic systems for instrument failures were developed and evaluated. In particular, application of these methods to nuclear power plant components is addressed. For a linear system, statistical tests on the innovations sequence of a Kalman filter driven by all system measurements provides a failure detection decision and identifies any failed sensor. This sequence (in an unfailed system) is zero-mean with calculable covariance; hence, any major deviation from these properties is assumed to be due to an instrument failure. Once a failure is identified, the failed instrument is replaced with an optimal estimate of the measured parameter. This failure accommodation is accomplished using optimally combined data from a bank of accommodation Kalman filters (one for each sensor), each driven by a single measurement. Using such a sensor replacement allows continued system operation under failed conditions and provides a system operator with information otherwise unavailable. To demonstrate monitor performance, a liner failure monitor was developed for the pressurizer in the Loss-of-Fluid Test (LOFT) reactor plant. LOFT is a small-scale pressurized water reactor (PWR) research facility located at the Idaho National Engineering Laboratory. A linear, third-order model of the pressurizer dynamics was developed from first principles and validated. Using data from the LOFT L6 test series, numerous actual and simulated water level, pressure, and temperature sensor failures were employed to illustrate monitor capabilities. Failure monitor design was applied to nonlinear dynamic systems by replacing all monitor linear Kalman filters with extended Kalman filters. A nonlinear failure monitor was derived for LOFT reactor instrumentation. A sixth-order reactor model, including descriptions of reactor kinetics, fuel rod heat transfer, and core coolant dynamics, was obtained and verified with test data

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

Instrumentation for Power System Disturbance Monitoring, Data ...

African Journals Online (AJOL)

In this paper, the level of instrumentation for power system disturbance monitoring, data acquisition and control in Nigerian Electric Power System; National Electric Power Authority (NEPA) is presented. The need for accurate power system disturbance monitoring is highlighted. A feature of an adequate monitoring, data ...

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

INSTRUMENTATION FOR ENVIRONMENTAL MONITORING--Radiation--Vol3Pt1

Energy Technology Data Exchange (ETDEWEB)

Authors, Various

1972-01-02

A comprehensive survey of instrumentation for environmental monitoring is being carried out by the Lawrence Berkeley Laboratory originally under a grant from the National Science Foundation and now by the Office of Health and Environmental Research of the Department of Energy. Instruments being investigated are those useful for measurements in Air Quality, Water Quality, Radiation, and Biomedicine related to environmental research and monitoring. Consideration is given to instruments and techniques presently in use and to those developed for other purposes but having possible applications to this work. The results of the survey are given as (a) descriptions of the physical and operating characteristics of available instruments, (b) critical comparisons among instrumentation methods, and (c) recommendations of promising methodology and development of new instrumentation. Information is also given regarding the pollutants to be monitored: their characteristics and forms, their sources and pathways, their effects on the ecosystem, and the means of controlling them through process and regulatory controls.

Volcano-Monitoring Instrumentation in the United States, 2008

Science.gov (United States)

Guffanti, Marianne; Diefenbach, Angela K.; Ewert, John W.; Ramsey, David W.; Cervelli, Peter F.; Schilling, Steven P.

2010-01-01

The United States is one of the most volcanically active countries in the world. According to the global volcanism database of the Smithsonian Institution, the United States (including its Commonwealth of the Northern Mariana Islands) is home to about 170 volcanoes that are in an eruptive phase, have erupted in historical time, or have not erupted recently but are young enough (eruptions within the past 10,000 years) to be capable of reawakening. From 1980 through 2008, 30 of these volcanoes erupted, several repeatedly. Volcano monitoring in the United States is carried out by the U.S. Geological Survey (USGS) Volcano Hazards Program, which operates a system of five volcano observatories-Alaska Volcano Observatory (AVO), Cascades Volcano Observatory (CVO), Hawaiian Volcano Observatory (HVO), Long Valley Observatory (LVO), and Yellowstone Volcano Observatory (YVO). The observatories issue public alerts about conditions and hazards at U.S. volcanoes in support of the USGS mandate under P.L. 93-288 (Stafford Act) to provide timely warnings of potential volcanic disasters to the affected populace and civil authorities. To make efficient use of the Nation's scientific resources, the volcano observatories operate in partnership with universities and other governmental agencies through various formal agreements. The Consortium of U.S. Volcano Observatories (CUSVO) was established in 2001 to promote scientific cooperation among the Federal, academic, and State agencies involved in observatory operations. Other groups also contribute to volcano monitoring by sponsoring long-term installation of geophysical instruments at some volcanoes for specific research projects. This report describes a database of information about permanently installed ground-based instruments used by the U.S. volcano observatories to monitor volcanic activity (unrest and eruptions). The purposes of this Volcano-Monitoring Instrumentation Database (VMID) are to (1) document the Nation's existing

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.

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

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.)

Offsite dose calculation manual guidance: Standard radiological effluent controls for boiling water reactors

International Nuclear Information System (INIS)

Meinke, W.W.; Essig, T.H.

1991-04-01

This report contains guidance which may be voluntarily used by licensees who choose to implement the provision of Generic Letter 89-- 01, which allows Radiological Effluent Technical Specifications (RETS) to be removed from the main body of the Technical Specifications and placed in the Offsite Dose Calculation Manual (ODCM). Guidance is provided for Standard Effluent Controls definitions, Controls for effluent monitoring instrumentation, Controls for effluent releases, Controls for radiological environmental monitoring, and the basis for Controls. Guidance on the formulation of RETS has been available in draft form for a number of years; the current effort simply recasts those RETS into Standard Radiological Effluent Controls for application to the ODCM. 11 tabs

Offsite dose calculation manual guidance: Standard radiological effluent controls for pressurized water reactors

International Nuclear Information System (INIS)

Meinke, W.W.; Essig, T.H.

1991-04-01

This report contains guidance which may be voluntarily used by licensees who choose to implement the provision of Generic Letter 89-01, which allows Radiological Effect Technical Specifications (RETS) to be removed from the main body of the Technical Specifications and placed in the Offsite Dose Calculation Manual (ODCM). Guidance is provided for Standard Effluent Controls definitions, Controls for effluent monitoring instrumentation, Controls for effluent releases, Controls for radiological environmental monitoring, and the basis for Controls. Guidance on the formulation of RETS has been available in draft from (NUREG-0471 and -0473) for a number of years; the current effort simply recasts those RETS into Standard Radiological Effluent Controls for application to the ODCM. Also included for completeness are: (1) radiological environmental monitoring program guidance previously which had been available as a Branch Technical Position (Rev. 1, November 1979); (2) existing ODCM guidance; and (3) a reproduction of generic Letter 89-01

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

Hanford Radiological Protection Support Services Annual Report for 2000

Energy Technology Data Exchange (ETDEWEB)

Lynch, Timothy P.; Bihl, Donald E.; Johnson, Michelle L.; Maclellan, Jay A.; Piper, Roman K.

2001-05-07

During calendar year 2000, the Pacific Northwest National Laboratory performed its customary radiological protection support services in support of the U.S. Department of Energy Richland Operations Office and the Hanford contractors. These services included: 1) external dosimetry, 2) internal dosimetry, 3) in vivo monitoring, 4) radiological records, 5) instrument calibration and evaluation, and 6) calibration of radiation sources traceable to the National Institute of Standards and Technology. Each program summary describes the routine operations, program changes and improvements, program assessments, supporting technical studies, and professional activities.

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)

Proceedings of the 3. Regional Meeting on Radiological and Nuclear Safety. Radiological protection in Latin America and the Caribbean. Vol. 1,2; Actas del 3. Congreso Regional sobre Seguridad Radiologica y Nuclear. Proteccion Radiologica en America Latina y el Caribe. Vol. 1,2

Energy Technology Data Exchange (ETDEWEB)

NONE

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 mapping of Mumbai-Arakkonam rail route

International Nuclear Information System (INIS)

Chavan, R.V.; Patil, S.S.; Solase, S.; Saindane, S.S.; Murali, S.

2018-01-01

Presently usage of sources of radiation in various fields of application has increased significantly. If such radiation sources get misplaced, lost from administrative control mechanism or smuggled out, it is advisable to have the countrywide baseline data on radiological aspects. As a part of emergency preparedness programme, it had been planned to generate the radiological baseline data for various road routes and cities in India. The radiological mapping is useful for updates on the trend of the radiation level at various locations/routes. The radiation mapping of Mumbai-Arakkonam rail route was carried out by using various state of the art monitoring systems/instruments. The radiological data at every railway stations were analyzed thoroughly. The overall increase in radiation level was found mainly due to the presence of higher concentration of naturally occurring radionuclide's in the environment mainly 40 K and 232 Th

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.

Post-accident monitoring systems in Prototype Fast Breeder Reactor

International Nuclear Information System (INIS)

Suriya Murthy, N.; Sivasailanathan, Vidhya; Ananth, Allu; Roy, Kallol

2018-01-01

PFBR is a 500 MW(e) MOX fueled and sodium cooled fast reactor (SFR) under advanced stage of commissioning at Kalpakkam. Currently, the main vessel is preheated and sodium has been charged into two secondary loops that are operated in recirculation mode. In order to characterize the radiation field and contamination, the workplace monitoring is undertaken using installed monitors that are commissioned and made operational. This helps to ensure radiological protection during normal operating conditions. On the other hand, radiological monitoring in emergency conditions is quite different. For undertaking the mitigative accident management, a set of specialized nuclear instruments called post-accident monitoring systems (PAMS) which include radiation monitors are stipulated. The Fukushima Daiichi accident emphasized the importance and need for reliable accident monitoring instrumentation to indicate the safety functions during the progression and aftermath of accident in NPP. In PFBR, the PAMS are integrated with other monitoring systems in design stage itself to manage the measurements and indicating the safety functions for implementing EOP and SAMG

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

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)

Development of an instrument to measure the clinical learning environment in diagnostic radiology

International Nuclear Information System (INIS)

Bloomfield, L.; Subramaniam, R.

2008-01-01

A clinical learning environment survey instrument was developed that provided insights into diagnostic radiology trainees' perceptions of the culture and context of the hospital-based training programme. The survey was completed by trainees allocated to 37 important training hospitals in Australia, New Zealand and Singapore in 2006. The main findings were that most obvious strengths of the diagnostic radiology programme are the wide variety of work-based learning opportunities and the social atmosphere. These were well regarded in all training sites. Work overload was seen as a significant problem in most hospitals and will probably remain a challenge. The areas that are most likely to repay efforts to bring about change are supervision and feedback. The study provides baseline data against which the influence of changes to the training programme may be evaluated.

Survey of instrumentation for environmental monitoring: major update. Volume 3. Radiation

Energy Technology Data Exchange (ETDEWEB)

1979-09-01

This is the third volume of a four-volume (seven-part) series, the culmination of a comprehensive survey of instrumentation for environmental monitoring. Consideration is given to instruments and techniques presently in use and to those developed for other purposes but having possible applications to radiation monitoring. The results of the survey are given as descriptions of the physical and operating characteristics of available instruments, critical comparisons among instrumentation methods, and recommendations of promising methodology and development of new instrumentation. Information is also given regarding the pollutants to be monitored, their characteristics and forms, their sources and pathways, their effects on the ecosystem, and the means of controlling them through process and regulatory controls. The discussion is presented under sections entitled radiation sources; instrumentation: by type of radiation or instrument type; and, instrumentation for specific radionuclides. (JGB)

Survey of instrumentation for environmental monitoring: major update. Volume 3. Radiation

International Nuclear Information System (INIS)

1979-09-01

This is the third volume of a four-volume (seven-part) series, the culmination of a comprehensive survey of instrumentation for environmental monitoring. Consideration is given to instruments and techniques presently in use and to those developed for other purposes but having possible applications to radiation monitoring. The results of the survey are given as descriptions of the physical and operating characteristics of available instruments, critical comparisons among instrumentation methods, and recommendations of promising methodology and development of new instrumentation. Information is also given regarding the pollutants to be monitored, their characteristics and forms, their sources and pathways, their effects on the ecosystem, and the means of controlling them through process and regulatory controls. The discussion is presented under sections entitled radiation sources; instrumentation: by type of radiation or instrument type; and, instrumentation for specific radionuclides

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

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

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

An instrument to perform automated quality assurance and patient dosimetry in diagnostic radiology

International Nuclear Information System (INIS)

Chapple, C.-L.; Faulkner, K.

1992-01-01

A computerised method of automatically monitoring tube and generator parameters to perform on-line quality assurance and patient dosimetry has been developed. A microcomputer has been interfaced to a microprocessor controlled X ray generator and dose-area product meter. The instrument prompts the operator to enter details of the examination and projection before an examination is made. The field size and dose-area product are monitored by the instrument. These data, together with information on the tube potential are used to deduce the patient entrance dose and energy imparted. Organ doses are estimated using normalised organ dose data. The accuracy and reproducibility of the instrument were investigated. Doses measured in a Rando phantom were compared with calculations made by the instrument. The instrument will compare various measured quality assurance parameters against their nominal values. The implications of this instrument for both patient dosimetry studies and effective continuous quality assurance are discussed. (author)

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

Radiological mapping of Bhubaneswar city

International Nuclear Information System (INIS)

Patil, S.S.; Patra, R.P.; Murali, S.; Singh, Rajvir; Pradeepkumar, K.S.; Vidya Sagar, D; Patra, P.

2015-01-01

The radiological mapping of Bhubaneswar city was carried as a part of emergency preparedness program intended to generate the countrywide radiation field baseline data for various routes and major cities. The study was effected using various state of art monitoring systems both Online and Offline dose rate data monitoring instruments such as Compact Aerial Radiation Monitoring System (CARMS), Gamma Tracer (GT), μR survey meter, Identi-finder. The instruments/systems were installed with special care to minimize the radiation shielding effect due to vehicle surfaces in light motor vehicle. During survey the dose rate along with GPS data were recorded and spectra were taken whenever elevated radiation level was observed. The data on dose rate using survey meter were recorded manually. The data on dose rate at important places is tabulated and it was observed that the dose rate in Bhubaneswar city ranged between 90-130 nSvh -1 . Detailed survey was carried out around Lingraj pond and the spectra were recorded. The results on analysis confirmed the presence of 232 Th, 226 Ra and 40 K attributed to elevated radiation levels. (author)

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

Instrumentation for status monitoring and protection of SST-1 superconducting magnets

Energy Technology Data Exchange (ETDEWEB)

Sharma, A.N., E-mail: aashoo.sharma@yahoo.com; Prasad, U.; Doshi, K.; Varmora, P.; Khristi, Y.; Patel, D.; Pradhan, S.

2016-11-15

Highlights: • Details of status monitoring instrumentation are presented. • Protection instrumentation details are presented. • Instrumentation installation details, signal conditioning and DAQ system details and the results during SST-1 operation are presented. - Abstract: Superconducting magnets of SST-1 are extensively instrumented to continuously monitor the health of magnets during machine cool-down, plasma experiments and also during the machine warm-up phase. These instrumentations include temperature sensors, flow meters, hall probes, strain gages, displacement sensors, pressure sensors and voltage taps. The number of sensors and their locations has been optimized to systematically monitor all important magnet parameters to ensure its safety. In-house developed modular signal conditioning cards have been developed for these instrumentations. The data is acquired on a Versa Module Europa bus based data acquisition system (VME DAQ). This paper gives an overview of selection, installation, laboratory scale validations, and distribution logics of these instrumentations. Results during plasma campaigns and the up-gradation aspects of these instrumentations are also discussed in this paper.

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.).

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

Nuclear reactor instrumentation power monitor

International Nuclear Information System (INIS)

Suzuki, Shigeru.

1989-01-01

The present invention concerns a nuclear reactor instrumentation power monitor that can be used in, for example, BWR type nuclear power plants. Signals from multi-channel detectors disposed on field units are converted respectively by LPRM signal circuits. Then, the converted signals are further converted by a multiplexer into digital signals and transmitted as serial data to a central monitor unit. The thus transmitted serial data are converted into parallel data in the signal processing section of the central monitor unit. Then, LPRM signals are taken out from each of channel detectors to conduct mathematical processing such as trip judgment or averaging. Accordingly, the field unit and the central monitor unit can be connected by way of only one data transmission cable thereby enabling to reduce the number of cables. Further, since the data are transmitted on digital form, it less undergoes effect of noises. (I.S.)

Hanford double shell tank corrosion monitoring instrument trees

International Nuclear Information System (INIS)

Nelson, J.L.

1995-03-01

High-level nuclear wastes at the Hanford site are stored underground in carbon steel double-shell and single-shell tanks - (DSTs and SSTS). Westinghouse Hanford Company is considering installation of a prototype corrosion monitoring instrument tree in at least one DST in the summer of 1995. The instrument tree will have the ability to detect and discriminate between uniform corrosion, stress corrosion cracking (SCC), and pitting. Additional instrument trees will follow in later years. Proof-of-technology testing is currently underway for the use of commercially available electric field pattern (EFP) analysis and electrochemical noise (EN) corrosion monitoring equipment. Creative use and combinations of other existing technologies is also being considered. Successful demonstration of these technologies will be followed by the development of a Hanford specific instrument tree. The first instrument tree will incorporate one of these technologies. Subsequent trees may include both technologies, as well as a more standard assembly of corrosion coupons. Successful development of these trees will allow their application to single shell tanks and the transfer of technology to other U.S. Department of Energy (DOE) sites

Development of network communication function for digitalized neutron flux monitoring instrument

International Nuclear Information System (INIS)

Li Kai; Zhang Liangju; Chen Xiaojun; Li Baoxiang

2002-01-01

It is essential for a digitalized Neutron Flux Monitoring Instrument to communicate with other parts of Instrumentation and Control System in a network environment, and it is fairly different from the case of traditional analogue nuclear instrumentation. How to satisfy all the requirements of different network structure and communication protocol, which might be adopted in different target nuclear power plant, is a key issue in the design and development of a digitalized neutron flux monitoring instrument. The author describes the overall communication scheme, mainly discusses the design idea and the requirements of the communication interfaces and the implementation of the RS-485 interface as an example of the digitalized neutron flux monitoring instrument, which is under development in the institute

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

The introduction of radiation monitor produced by several nuclear instrument factories

International Nuclear Information System (INIS)

Yu Liying

2005-01-01

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

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)

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

International Nuclear Information System (INIS)

Carny, P.; Cabanekova, H

2003-01-01

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

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

On-line Monitoring of Instrumentation in Research Reactors

International Nuclear Information System (INIS)

2017-12-01

This publication is the result of a benchmarking effort undertaken under the IAEA coordinated research project on improved instrumentation and control (I&C) maintenance techniques for research reactors. It lays the foundation for implementation of on-line monitoring (OLM) techniques and establishment of the validity of those for improved maintenance practices in research reactors for a number of applications such as change to condition based calibration, performance monitoring of process instrumentation systems, detection of process anomalies and to distinguish between process problems/effects and instrumentation/sensor issues. The techniques and guidance embodied in this publication will serve the research reactor community in providing the technical foundation for implementation of OLM techniques. It is intended to be used by Member States to implement I&C maintenance and to improve performance of research reactors.

Quality assurance of radiation protection monitoring instruments in India

International Nuclear Information System (INIS)

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

2008-01-01

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

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; 3. Congreso Regional sobre Seguridad Radiologica y Nuclear, Congreso Regional IRPA y 3. Congreso Peruano de Proteccion Radiologica. Libro de Resumenes

Energy Technology Data Exchange (ETDEWEB)

NONE

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.

Calibration through on-line monitoring of instruments channels

International Nuclear Information System (INIS)

James, R.W.

1996-01-01

Plant technical specifications require periodic calibration of instrument channels, and this has traditionally meant calibration at fixed time intervals for nearly all instruments. Experience has shown that unnecessarily frequent calibrations reduce channel availability and reliability, impact outage durations, and increase maintenance costs. An alternative approach to satisfying existing requirements for periodic calibration consists of on-line monitoring and quantitative comparison of instrument channels during operation to identify instrument degradation and failure. A Utility Working Group has been formed by EPRI to support the technical activities necessary to achieve generic NRC acceptance of on-line monitoring of redundant instrument channels as a basis for determining when to perform calibrations. A topical report proposing NRC acceptance of this approach was submitted in August 1995, and the Working Group is currently resolving NRC technical questions. This paper describes the proposed approach and the current status of the topical report with regard to NRC review. While these activities will not preclude utilities from continuing to use existing calibration approaches, successful acceptance of this performance-based approach will allow utilities to substantially reduce the number of calibrations which are performed. Concurrent benefits will include reduced I ampersand C impact on outage durations and improved sensitivity to instrument channel performance

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

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)

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)

Calibration of radiation protection area monitoring instruments in Sudan

International Nuclear Information System (INIS)

Suliman, I.I.; Youssif, B.E.; Beineen, A.A.; Hassan, M.

2010-01-01

This article presents results of measurements for the calibration of radiation protection area monitoring instruments carried out during the period 2006-2008 at Secondary Standard Dosimetry Laboratory of Sudan. The work performed included quality assurance measurements, measurements for the dosimeter calibrations and uncertainty analysis. Calibrations were performed using 137 Cs gamma ray sources produced by OB 85 and OB 34/1 gamma calibrators producing air kerma rate that ranged from 10 μGy/h to 50 mGy/h. Area monitoring instruments were calibrated in terms of ambient dose equivalent, H*(10) derived using air kerma to ambient dose equivalent conversion coefficients. Results are presented for 78 area monitoring instruments representing most commonly used types in Sudan. Radioactive check source measurements for the reference chamber showed deviation within 1% limit. The accuracy in the beam output measurements was within 5% internationally considered as acceptable. The results highlighted the importance of radiation protection calibrations. Regulations are further need to ensure safety aspect really meet the required international standards.

Assessing hospitals' clinical risk management: Development of a monitoring instrument

Directory of Open Access Journals (Sweden)

Pfeiffer Yvonne

2010-12-01

Full Text Available Abstract Background Clinical risk management (CRM plays a crucial role in enabling hospitals to identify, contain, and manage risks related to patient safety. So far, no instruments are available to measure and monitor the level of implementation of CRM. Therefore, our objective was to develop an instrument for assessing CRM in hospitals. Methods The instrument was developed based on a literature review, which identified key elements of CRM. These elements were then discussed with a panel of patient safety experts. A theoretical model was used to describe the level to which CRM elements have been implemented within the organization. Interviews with CRM practitioners and a pilot evaluation were conducted to revise the instrument. The first nationwide application of the instrument (138 participating Swiss hospitals was complemented by in-depth interviews with 25 CRM practitioners in selected hospitals, for validation purposes. Results The monitoring instrument consists of 28 main questions organized in three sections: 1 Implementation and organizational integration of CRM, 2 Strategic objectives and operational implementation of CRM at hospital level, and 3 Overview of CRM in different services. The instrument is available in four languages (English, German, French, and Italian. It allows hospitals to gather comprehensive and systematic data on their CRM practice and to identify areas for further improvement. Conclusions We have developed an instrument for assessing development stages of CRM in hospitals that should be feasible for a continuous monitoring of developments in this important area of patient safety.

Assessing hospitals' clinical risk management: Development of a monitoring instrument.

Science.gov (United States)

Briner, Matthias; Kessler, Oliver; Pfeiffer, Yvonne; Wehner, Theo; Manser, Tanja

2010-12-13

Clinical risk management (CRM) plays a crucial role in enabling hospitals to identify, contain, and manage risks related to patient safety. So far, no instruments are available to measure and monitor the level of implementation of CRM. Therefore, our objective was to develop an instrument for assessing CRM in hospitals. The instrument was developed based on a literature review, which identified key elements of CRM. These elements were then discussed with a panel of patient safety experts. A theoretical model was used to describe the level to which CRM elements have been implemented within the organization. Interviews with CRM practitioners and a pilot evaluation were conducted to revise the instrument. The first nationwide application of the instrument (138 participating Swiss hospitals) was complemented by in-depth interviews with 25 CRM practitioners in selected hospitals, for validation purposes. The monitoring instrument consists of 28 main questions organized in three sections: 1) Implementation and organizational integration of CRM, 2) Strategic objectives and operational implementation of CRM at hospital level, and 3) Overview of CRM in different services. The instrument is available in four languages (English, German, French, and Italian). It allows hospitals to gather comprehensive and systematic data on their CRM practice and to identify areas for further improvement. We have developed an instrument for assessing development stages of CRM in hospitals that should be feasible for a continuous monitoring of developments in this important area of patient safety.

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

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)

Environmental radiation monitoring of Vizag City

International Nuclear Information System (INIS)

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

2014-01-01

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

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

Division of Radiological Protection : progress report, 1989-1991

International Nuclear Information System (INIS)

Gupta, B.L.; Nagarajan, P.S.; Bhatt, B.C.; Seethapathy, A.; Pradhan, A.S.; Vishwakarma, R.R.

1992-01-01

This report describes the work of the Division of Radiological Protection during 1989-91, for implementation of radiation safety in all institutions in the country using radiation sources for medical, industrial and research applications. It gives information about personnel monitoring using photographic film and TLD badges, neutron monitoring badges, dosimetric techniques developed, calibration techniques for high-dose irradiators, design and fabrication of special radiation protection instruments, advisory and licensing services, regulation and transport of radioactive materials, periodic protection survey, education and training related to radiation safety programmes. About 164 publications by the staff of this Division are listed. (author). 1 index., 1 tab

40 CFR 63.1004 - Instrument and sensory monitoring for leaks.

Science.gov (United States)

2010-07-01

... to be measured in air. (5) Monitoring performance. Monitoring shall be performed when the equipment... devices in gas and vapor service) or § 63.1012(f) (compressors). (d) Sensory monitoring methods. Sensory... 40 Protection of Environment 10 2010-07-01 2010-07-01 false Instrument and sensory monitoring for...

Automated Calibration of Dosimeters for Diagnostic Radiology

International Nuclear Information System (INIS)

Romero Acosta, A.; Gutierrez Lores, S.

2015-01-01

Calibration of dosimeters for diagnostic radiology includes current and charge measurements, which are often repetitive. However, these measurements are usually done using modern electrometers, which are equipped with an RS-232 interface that enables instrument control from a computer. This paper presents an automated system aimed to the measurements for the calibration of dosimeters used in diagnostic radiology. A software application was developed, in order to achieve the acquisition of the electric charge readings, measured values of the monitor chamber, calculation of the calibration coefficient and issue of a calibration certificate. A primary data record file is filled and stored in the computer hard disk. The calibration method used was calibration by substitution. With this system, a better control over the calibration process is achieved and the need for human intervention is reduced. the automated system will be used in the calibration of dosimeters for diagnostic radiology at the Cuban Secondary Standard Dosimetry Laboratory of the Center for Radiation Protection and Hygiene. (Author)

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

Design of instrument for monitoring nuclear radiation and baneful gas

International Nuclear Information System (INIS)

Xiong Jianping; Chen Jun; Zhu Wenkai

2006-01-01

Counters and ionization chambers are applied to sensors, and microprocessor based on ARM IP is applied to center controller in the instrument. It is achieved to monitor nuclear radiation and baneful gas in an instrument. The instrument is capable of LCD displaying, menu operating and speech alarming. (authors)

Instrumentation for environmental monitoring in biological systems

International Nuclear Information System (INIS)

Amer, N.M.; Graven, R.M.; Budnitz, R.J.; Mack, D.A.

1975-01-01

A brief review of the status of instrumentation for monitoring environmental pollutants is given. Pollutants are divided into six broad categories: trace elements, pesticides and herbicides, ionizing radiation and radionuclides, asbestos and other microparticulates, and gaseous pollutants. (U.S.)

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

Monitoring instrumentation spent fuel management program. Final report

International Nuclear Information System (INIS)

1979-01-01

Preliminary monitoring system methodologies are identified as an input to the risk assessment of spent fuel management. Conceptual approaches to instrumentation for surveillance of canister position and orientation, vault deformation, spent fuel dissolution, temperature, and health physics conditions are presented. In future studies, the resolution, reliability, and uncertainty associated with these monitoring system methodologies will be evaluated

New portable hand-held radiation instruments for measurements and monitoring

International Nuclear Information System (INIS)

Fehlau, P.E.

1987-01-01

Hand-held radiation monitors are often used to search pedestrians and motor vehicles for special nuclear material (SNM) as part of a physical protection plan for nuclear materials. Recently, the Los Alamos Advanced Nuclear Technology group has commercialized an improved hand-held monitor that can be used for both physical-protection monitoring and verification measurements in nuclear material control and waste management. The new monitoring instruments are smaller and lighter; operate much longer on a battery charge; are available with NaI(Tl) or neutron and gamma-ray sensitive plastic scintillation detectors; and are less expensive than other comparable instruments. They also have a second operating mode for making precise measurements over counting times as long as 99 s. This mode permits making basic verification measurements that may be needed before transporting nuclear material or waste outside protected areas. Improved verification measurements can be made with a second new hand-held instrument that has a stabilized detector and three separate gamma-ray energy windows to obtain spectral information for SNM quantity, enrichment, or material-type verification

Post-accident radiation monitors

International Nuclear Information System (INIS)

Laughlin, G.J.; Kathren, R.L.

1982-01-01

Under contract to the Nuclear Safety Analysis Center of the Electric Power Research Institute, technical information and specifications were obtained for commercially available radiological monitoring instrumentation designed for use as post-accident monitors. The information was collated and published in the NSAC Handbook of Postaccident Instrumentation (Kathren and Laughlin 1981), and included such data as range, accuracy, precision, sensitivity, and energy dependence of the detector, environmental and seismic limitations of the equipment, the testing program performed to evaluate the equipment, a list of references where the instrumentation is currently installed, and a list of features and accessories available with the monitoring systems. The information presented in this section reveals that, even though a number of vendors claim to be able to meet the guidance of Regulatory Guide 1.97 (USNRC 1980), few have actually conducted tests to verify that their equipment does indeed satisfy the guidance of this Regulatory Guide, and that some of the guidance may in fact be unrealistic

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.

Monitoring Instrument Performance in Regional Broadband Seismic Network Using Ambient Seismic Noise

Science.gov (United States)

Ye, F.; Lyu, S.; Lin, J.

2017-12-01

In the past ten years, the number of seismic stations has increased significantly, and regional seismic networks with advanced technology have been gradually developed all over the world. The resulting broadband data help to improve the seismological research. It is important to monitor the performance of broadband instruments in a new network in a long period of time to ensure the accuracy of seismic records. Here, we propose a method that uses ambient noise data in the period range 5-25 s to monitor instrument performance and check data quality in situ. The method is based on an analysis of amplitude and phase index parameters calculated from pairwise cross-correlations of three stations, which provides multiple references for reliable error estimates. Index parameters calculated daily during a two-year observation period are evaluated to identify stations with instrument response errors in near real time. During data processing, initial instrument responses are used in place of available instrument responses to simulate instrument response errors, which are then used to verify our results. We also examine feasibility of the tailing noise using data from stations selected from USArray in different locations and analyze the possible instrumental errors resulting in time-shifts used to verify the method. Additionally, we show an application that effects of instrument response errors that experience pole-zeros variations on monitoring temporal variations in crustal properties appear statistically significant velocity perturbation larger than the standard deviation. The results indicate that monitoring seismic instrument performance helps eliminate data pollution before analysis begins.

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.

Concurrent Pilot Instrument Monitoring in the Automated Multi-Crew Airline Cockpit.

Science.gov (United States)

Jarvis, Stephen R

2017-12-01

Pilot instrument monitoring has been described as "inadequate," "ineffective," and "insufficient" after multicrew aircraft accidents. Regulators have called for improved instrument monitoring by flight crews, but scientific knowledge in the area is scarce. Research has tended to investigate the monitoring of individual pilots when in the pilot-flying role; very little research has looked at crew monitoring, or that of the "monitoring-pilot" role despite it being half of the apparent problem. Eye-tracking data were collected from 17 properly constituted and current Boeing 737 crews operating in a full motion simulator. Each crew flew four realistic flight segments, with pilots swapping between the pilot-flying and pilot-monitoring roles, with and without the autopilot engaged. Analysis was performed on the 375 maneuvering-segments prior to localizer intercept. Autopilot engagement led to significantly less visual dwell time on the attitude director indicator (mean 212.8-47.8 s for the flying pilot and 58.5-39.8 s for the monitoring-pilot) and an associated increase on the horizontal situation indicator (18-52.5 s and 36.4-50.5 s). The flying-pilots' withdrawal of attention from the primary flight reference and increased attention to the primary navigational reference was paralleled rather than complemented by the monitoring-pilot, suggesting that monitoring vulnerabilities can be duplicated in the flight deck. Therefore it is possible that accident causes identified as "inadequate" or "insufficient" monitoring, are in fact a result of parallel monitoring.Jarvis SR. Concurrent pilot instrument monitoring in the automated multi-crew airline cockpit. Aerosp Med Hum Perform. 2017; 88(12):1100-1106.

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

International Nuclear Information System (INIS)

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

2005-01-01

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

Single-chip microcomputer application in nuclear radiation monitoring instruments

International Nuclear Information System (INIS)

Zhang Songshou

1994-01-01

The single-chip microcomputer has advantage in many respects i.e. multiple function, small size, low-power consumption,reliability etc. It is widely used now in industry, instrumentation, communication and machinery. The author introduced usage of single-chip microcomputer in nuclear radiation monitoring instruments for control, linear compensation, calculation, changeable parameter presetting and military training

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

Science.gov (United States)

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

2012-10-01

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

Radiation monitoring instrumentation for nuclear power plants

International Nuclear Information System (INIS)

Bharath Kumar, M.

2013-01-01

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

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

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.

Evaluation of a draft standard on performance specifications for health physics instrumentation. Initial results for radiological tests

International Nuclear Information System (INIS)

Swinth, K.L.; Kenoyer, J.L.; Mileham, A.P.; Kathren, R.L.; Selby, J.M.

1983-06-01

The draft ANSI standard N42.17D2 on performance specifications for health physics instrumentation is currently being evaluated by the Pacific Northwest Laboratory. The primary objective of the project is the evaluation of the applicability and practicality of the proposed standard through testing of a cross-section of currently available commercial instruments to determine how well they conform to the standard. The standard is being tested against instruments such as ionization chambers, G.M. detectors, alpha survey meters, and neutron dose equivalent survey meters. This paper presents results of the preliminary radiological performance tests on ionization chambers and G.M. detectors. This includes both the data generated during the tests and a discussion of procedures developed to perform the testing. Results are reported for response time, accuracy, precision, radiation overloads, and angular dependence. In addition, results are reported for parameters that affect instrument performance including battery lifetime, geotropism and stability. Initial test indicates that some of the instruments will not meet the criteria specified in ANSI N42.17D2. Results cover approximately 40 instruments that have been obtained by direct purchase, by loan from instrument vendors or by loan from others including DOE licensees

Monitoring Instrument for X-Ray Box

CERN Document Server

Cifuentes Ospina, Alberto; Kuehn, Susanne; Schaepe, Steffen; CERN. Geneva. EP Department

2017-01-01

A humidity and temperature readout instrument has been designed and implemented in order to monitor the X-Ray Box used for testing the silicon detectors prototypes of the ITk. The sensors are connected to an Arduino Mega board equipped with 16 analog inputs and a serial port to a computer. A user-friendly software has been also designed in order to give an easy access to all measurements.

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.

Instrument calibration reduction through on-line monitoring in the USA. Annex IV

International Nuclear Information System (INIS)

Hashemian, H.M.

2008-01-01

Nuclear power plants are required to calibrate important instruments once every fuel cycle. This requirement dates back more than 30 years, when commercial nuclear power plants began to operate. Based on calibration data accumulated over this period, it has been determined that the calibration of some instruments, such as pressure transmitters, do not drift enough to warrant calibration as often as once every fuel cycle. This fact, combined with human resources limitations and reduced maintenance budgets, has provided the motivation for the nuclear industry to develop new technologies for identifying drifting instruments during plant operation. Implementing these technologies allows calibration efforts to be focused on the instruments that have drifted out of tolerance, as opposed to current practice, which calls for calibration verification of almost all instruments every fuel cycle. To date, an array of technologies, referred to collectively as 'on-line calibration monitoring', has been developed to meet this objective. These technologies are based on identifying outlier sensors using techniques that compare a particular sensor's output to a calculated estimate of the actual process the sensor is measuring. If on-line monitoring data are collected during plant startup and/or shutdown periods as well as normal operation, the on-line monitoring approach can help verify the calibration of instruments over their entire operating range. Although on-line calibration monitoring is applicable to most sensors and can cover an entire instrument channel, the main application of this approach in nuclear power plants is currently for pressure transmitters (including level and flow transmitters). (author)

The development of state/region owned goods management’s monitoring instrument design

Directory of Open Access Journals (Sweden)

Ikhwanto Yogy

2017-01-01

Full Text Available The problems in state/region owned goods in Indonesian state and local governments are suspected to occur because of weak monitoring programs, according to many studies. A tool or instrument in implementing this monitoring program is expected to address this problem. Such tool currently doesn’t exist yet. This research aims to fill that gap by developing a monitoring instrument design for state/region owned goods by using Daerah Istimewa Yogyakarta (DIY Local Government as a research context in order to take valuable inputs for the design. This research is using developmental research method. Government Regulation were used for normative reference and Friedman’s results-based accountability quadrat were used in developing good indicators for the instrument. This research is succeeded in formulating the indicators that made up the instrument. Indicators compiled are divided into compliance-based indicators and results-based indicators. Indicators are formulated based on the validation and inputs from employees of DIY’s Assets Management Agency and experts from academia. This instrument still has some limitations that need improvement through further research.

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.

Division of Radiological Protection progress report 1982-1988

International Nuclear Information System (INIS)

Gupta, B.L.; Bhat, R.M.; Narayan, G.R.

1989-01-01

This report describes the work of the Division of Radiological Protection during 2-88, for implementation of radiation safety in all institutions in the country using radiation sources for medical, industrial and research applications. It gives information about personnel monitoring using photographic film and TLD badges, neutron monitoring badges, dosimetric techniques developed, calibration facilities and maintenance of national standards for radiation and radioactivity, design and fabrication of special radiation protection instruments, development of coloured indicators for indentification of radiation sterilized medical products, advisory and licencing services, regulation and transport of radioactive materials, periodic protection survey, education and training related to radiation safety programmes. About 500 publications by the staff of this Division are listed. (author). 46 figs

Safeguards instrument to monitor spent reactor fuel

International Nuclear Information System (INIS)

Nicholson, N.; Dowdy, E.J.; Holt, D.M.; Stump, C.

1981-01-01

A hand-held instrument for monitoring irradiated nuclear fuel inventories located in water-filled storage ponds has been developed. This instrument provides sufficient precise qualitative and quantitative information to be useful as a confirmatory technique to International Atomic Energy Agency inspectors, and is believed to be of potential use to nuclear fuel managers and to operators of spent-fuel storage facilities, both at reactor and away-from-reactor, and to operators of nuclear fuel reprocessing plants. Because the Cerenkov radiation glow can barely be seen by the unaided eye under darkened conditions, a night vision device is incorporated to aid the operator in locating the fuel assembly to be measured. Beam splitting optics placed in front of the image intensifier and a preset aperture select a predetermined portion of the observed scene for measurement of the light intensity using a photomultiplier (PM) tube and digital readout. The PM tube gain is adjusted by use of an internal optical reference source, providing long term repeatability and instrument-to-instrument cnsistency. Interchangeable lenses accommodate various viewing and measuring conditions

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

Basic requirements for personnel monitoring. 1980 ed

International Nuclear Information System (INIS)

1980-01-01

This Code of Practice sets forth the objectives of an adequate system of personnel monitoring for radiation workers. It covers individual dosimetry, including internal radiation monitoring, and area monitoring to the extent required for the assessment of individual radiation doses. The responsibilities of authorities for organizing monitoring of radiation workers are discussed, together with brief descriptions of monitoring methods and the rules governing their application. The general principles to be considered in selecting instrumentation and the appropriate monitoring techniques are described, as well as calibration techniques, methods of data handling and record keeping. Current concepts and recommendations of the International Commission on Radiological Protection, as presented in ICRP Publication No.26, have been incorporated. New developments in techniques and instruments have been reflected, and several sections such as calibration and record keeping have been elaborated. The bibliography has been updated and new annexes added.

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)

Instrument reliability for high-level nuclear-waste-repository applications

International Nuclear Information System (INIS)

Rogue, F.; Binnall, E.P.; Armantrout, G.A.

1983-01-01

Reliable instrumentation will be needed to evaluate the characteristics of proposed high-level nuclear-wasted-repository sites and to monitor the performance of selected sites during the operational period and into repository closure. A study has been done to assess the reliability of instruments used in Department of Energy (DOE) waste repository related experiments and in other similar geological applications. The study included experiences with geotechnical, hydrological, geochemical, environmental, and radiological instrumentation and associated data acquisition equipment. Though this paper includes some findings on the reliability of instruments in each of these categories, the emphasis is on experiences with geotechnical instrumentation in hostile repository-type environments. We review the failure modes, rates, and mechanisms, along with manufacturers modifications and design changes to enhance and improve instrument performance; and include recommendations on areas where further improvements are needed

On-Line Monitoring of Instrument Channel Performance in Nuclear Power Plant Using PEANO

International Nuclear Information System (INIS)

Fantoni, Paolo F.; Hoffmann, Mario; Shankar, Ramesh; Davis, Eddie L.

2002-01-01

On-Line monitoring evaluates instrument channel performance by assessing its consistency with other plant indications. Industry and EPRI experience at several plants has shown this overall approach to be very effective in identifying instrument channels that are exhibiting degrading or inconsistent performance characteristics. On-Line monitoring of instrument channels provides information about the condition of the monitored channels through accurate, more frequent monitoring of each channel's performance over time. This type of performance monitoring is a methodology that offers an alternate approach to traditional time-directed calibration. On-line monitoring of these channels can provide an assessment of instrument performance and provide a basis for determining when adjustments are necessary. Elimination or reduction of unnecessary field calibrations can reduce associated labor costs, reduce personnel radiation exposure and reduce the potential for miss-calibration. PEANO is a system for on-line calibration monitoring developed in the years 1995-2000 at the Institutt for energiteknikk (IFE), Norway, which makes use of Artificial Intelligence techniques for its purpose. The system has been tested successfully in Europe in off-line tests with EDF (France), Tecnatom (Spain) and ENEA (Italy). PEANO is currently installed and used for on-line monitoring at the HBWR reactor in Halden. This paper describes the results of performance tests on PEANO with real data from a US PWR plant, in the framework of a co-operation among IFE, EPRI and Edan Engineering, to evaluate the potentials of PEANO for future installations in US nuclear plants. (authors)

Radiological Control Technician: Phase 2, Core/site practical training

International Nuclear Information System (INIS)

1992-10-01

This volume provides a description of the guidelines, qualification in radiological instrumentation, qualification in radiological protection, and qualification in emergency preparedness for radiological control technicians

Radiological Assistance Program, DOE Region 6 response plan

International Nuclear Information System (INIS)

Jakubowski, F.M.

1993-02-01

This program plan meets all the requirements identified in DOE Order 5530.3, Radiological Assistance Program and supports those requirements leading to the establishment of a Federal Radiological Monitoring and Assessment Center (FRMAC) as required by DOE 5530-5. Requests for radiological assistance may come from other DOE facilities, Federal or state agencies, tribal officials, or from any private corporation or individual. Many of the requests will be handled by a telephone call, a conference or a letter, teletype or memorandum. Other requests for assistance may involve radioactive material in serious accidents, fire, personal injuries, contamination or possible hazards to the general public. Some occurrences may require the dispatch of trained personnel equipped with radiation monitoring instruments and related equipment necessary to evaluate, control and neutralize the hazard. The primary responsibility for incidents involving radioactive material always remains with the party having custody of the radioactive materials. In addition, the DOE recognizes that the assistance provided shall not in any way preempt state, tribal, or local authority and/or responsibility on state or tribal properties. Toward this end, DOE assistance for non-DOE radioactive materials, is limited to technical assistance, advice, measurement and other resources as deemed necessary by the local authorities but excludes DOE interface with the public media. This is a function handled by the local or state Incident Commander

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

Development of infrared communication in radiation protection and monitoring

International Nuclear Information System (INIS)

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

2003-01-01

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

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)

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

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

Process instrument monitoring for SNM solution surveillance

International Nuclear Information System (INIS)

Armatys, C.M.; Johnson, C.E.; Wagner, E.P.

1983-02-01

A process monitoring computer system at the Idaho Chemical Processing Plant (ICPP) is being used to evaluate nuclear fuel reprocessing plant data for Safeguards surveillance capabilities. The computer system was installed to collect data from the existing plant instruments and to evaluate what safeguards assurances can be provided to complement conventional accountability and physical protection measures. Movements of solutions containing special nuclear material (SNM) can be observed, activities associated with accountancy measurements (mixing, sampling, and bulk measurement) can be confirmed, and long-term storage of SNM solutions can be monitored to ensure containment. Special precautions must be taken, both in system design and operation to ensure adequate coverage of essential measured parameters and interpretation of process data, which can be comprised by instrument malfunctions or failures, unreliable data collection, or process activities that deviate from readily identified procedures. Experience at ICPP and prior evaluations at the Tokai reprocessing plant show that the use of process data can provide assurances that accountability measurement procedures are followed and SNM solutions are properly contained and can help confirm that SNM controls are in effect within a facility

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.)

Indigenous development and networking of online radon monitors in the underground uranium mine

International Nuclear Information System (INIS)

Gaware, J.J.; Sahoo, B.K.; Sapra, B.K.; Mayya, Y.S.

2011-01-01

There has been a long standing demand for online monitoring of radon level in various locations of underground Uranium mine for taking care of radiological protection to workers. Nowadays, radon ( 222 Rn) monitors, based on electrostatic collection of charged progeny and subsequent detection by semiconductor detector are increasingly employed for radon monitoring in environment. However, such instruments have some limitations such as (i) requirement of additional dryer since sensitivity is dependent on the humidity (ii) cannot be connected to a network and (iii) not cost effective etc. Hence use of such instruments in underground uranium mine (humidity level >90), may not be reliable. Towards this end, we have indigenously developed radon monitor based on electrostatic collection and scintillation technology for the online monitoring in uranium mine. This instrument overcomes the above mentioned limitation of commercial radon monitors and based on custom made features. Different tests and measurements were carried out and compared with commercial instruments. It was found to be in an excellent agreement with the commercial instruments. A few such instruments have been installed in different locations of uranium mine at Turamdih and connected to a network system for online monitoring and display. (author)

Environmental radiation monitoring technology: Capabilities and needs

International Nuclear Information System (INIS)

Hofstetter, K.J.

1994-01-01

Radiation monitoring in the Savannah River Site (SRS) environment is conducted by a combination of automated, remote sampling and/or analysis systems, and manual sampling operations. This program provides early detection of radionuclide releases, minimizes the consequences, and assesses the impact on the public. Instrumentation installed at the release points monitor the atmospheric and aqueous releases from SRS operations. Ground water and air monitoring stations are strategically located throughout the site for radionuclide migration studies. The environmental radiological monitoring program at SRS includes: fixed monitoring stations for atmospheric radionuclide concentrations, aqueous monitors for surface water measurements, mobile laboratory operations for real-time, in-field measurements, aerial scanning for wide area contamination surveillance, and hand-held instruments for radionuclide-specific measurements. Rigorous environmentnal sampling surveillance coupled with laboratory analyses provide confirmatory results for all in-field measurements. Gaps in the technologies and development projects at SRS to fill these deficiencies are discussed in the context of customer needs and regulatory requirements

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

Method and apparatus for continuous fluid leak monitoring and detection in analytical instruments and instrument systems

Science.gov (United States)

Weitz, Karl K [Pasco, WA; Moore, Ronald J [West Richland, WA

2010-07-13

A method and device are disclosed that provide for detection of fluid leaks in analytical instruments and instrument systems. The leak detection device includes a collection tube, a fluid absorbing material, and a circuit that electrically couples to an indicator device. When assembled, the leak detection device detects and monitors for fluid leaks, providing a preselected response in conjunction with the indicator device when contacted by a fluid.

[Design and implementation of real-time continuous glucose monitoring instrument].

Science.gov (United States)

Huang, Yonghong; Liu, Hongying; Tian, Senfu; Jia, Ziru; Wang, Zi; Pi, Xitian

2017-12-01

Real-time continuous glucose monitoring can help diabetics to control blood sugar levels within the normal range. However, in the process of practical monitoring, the output of real-time continuous glucose monitoring system is susceptible to glucose sensor and environment noise, which will influence the measurement accuracy of the system. Aiming at this problem, a dual-calibration algorithm for the moving-window double-layer filtering algorithm combined with real-time self-compensation calibration algorithm is proposed in this paper, which can realize the signal drift compensation for current data. And a real-time continuous glucose monitoring instrument based on this study was designed. This real-time continuous glucose monitoring instrument consisted of an adjustable excitation voltage module, a current-voltage converter module, a microprocessor and a wireless transceiver module. For portability, the size of the device was only 40 mm × 30 mm × 5 mm and its weight was only 30 g. In addition, a communication command code algorithm was designed to ensure the security and integrity of data transmission in this study. Results of experiments in vitro showed that current detection of the device worked effectively. A 5-hour monitoring of blood glucose level in vivo showed that the device could continuously monitor blood glucose in real time. The relative error of monitoring results of the designed device ranged from 2.22% to 7.17% when comparing to a portable blood meter.

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

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

Establishing a mobile automatic monitoring station for emergency response

International Nuclear Information System (INIS)

Fang, Hsin-Fa

2008-01-01

Full text: A radiological/nuclear emergency event may cause environmental contamination. The emergency response works always need to plan an environmental survey programme incorporating the assessment results to see what is happening. The places where are assessed to have the highest radioactive contamination/radiation dose will catch more concern and need continuous monitoring. It will cause unnecessary dangers and dose to command that personnel conduct surveying in such places when the radiological/nuclear accident become more severe. A mobile automatic monitoring station has been established for emergency response by INER (Institute of Nuclear Energy Research) to solve the problem practically. The monitoring station involves a HPIC to monitor radiation dose, an anemometer to monitor wind speed and direction, a GPS to get position data, a GPRS/3G communication module to send monitoring and positioning data to the monitoring centre where can show the monitoring result directly on a map shown on the computer. These instruments are integrated in a trailer easy to be towed to the place need to be monitored. The electric power of the station is supplied by s a solar power energy system. It can supply the station working at least 10 days without extra electric power supply designed based on the expected time length of a nuclear power plant event. The HPIC is very sensitive and stable that can discriminate a 10 nSv/hr increasing of dose rate with the monitoring time period every ten seconds. Where the radiological dispersion device events happened is not predictable, it is difficult to get suitable wind monitoring data to assess the result of radiological dispersion device events. The anemometer added on the station can provide the real time wind monitoring data to help assessment works. (author)

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

International Nuclear Information System (INIS)

1999-06-01

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

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

Energy Technology Data Exchange (ETDEWEB)

1999-06-01

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

Characterization of different qualities in X-rays, for instruments calibration in radiological protection; Caracterizacion de diferentes calidades en rayos X, para calibracion de instrumentos en proteccion radiologica

Energy Technology Data Exchange (ETDEWEB)

Cejudo A, J.; Tovar M, V. M.; Vergara M, F., E-mail: jesus.cejudo@inin.gob.m [ININ, Departamento de Metrologia de Radiaciones Ionizantes, Laboratorio Secundario de Calibracion Dosimetrica, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

2010-09-15

In the Secondary Laboratory of Dosimetric Calibration in Mexico was realized the qualities characterization of the series X-rays RQR reported in the International Code of Practices in Dosimetry and Diagnostic Radiology No. 457, using attenuator filters of high purity aluminum and ionizing radiation equipment of inherent filtration of 4 mm Be with and emergent X-radiation beam of 40 grades. For the attenuation was used a geometric arrangement with three beam limiters and a monitor camera prepared on the established form in the mentioned technical report, and a spherical ionization chamber with collection volume of 3.6 cm{sup 3}, aligning its geometric center with the focus of X-rays tube to get that the incident radiation direction will be perpendicular to the ionization chamber. From the perspective of the radiological protection is important to know the X-radiation quality for the application dedicated to the instruments calibration and can to give to these the traceability to a reference laboratory, this way the quality combination and reference chamber can give as a result a procedure for the evaluation of the entrance in surface dose to estimate the dose orientate levels, specified in the basic standards of safety. (Author)

Development of a Real-Time Radiological Area Monitoring Network for Emergency Response at Lawrence Livermore National Laboratory

International Nuclear Information System (INIS)

Bertoldo, N; Hunter, S; Fertig, R; Laguna, G; MacQueen, D

2004-01-01

A real-time radiological sensor network for emergency response was 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 LLNL Livermore site perimeter to continuously monitor for a radiological condition resulting from a terrorist threat to site security and the health and safety of LLNL personnel. The RTRAM network sensor locations coincide with wind sector directions to provide thorough coverage of the one square mile site. These loW--power sensors are supported by a central command center (CCC) and transmit measurement data back to the 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. The RTRAM network has proven to be a reliable system since initial deployment in August 2001 and maintains stability during inclement weather conditions

Instrumentation for Monitoring around Marine Renewable Energy Converters: Workshop Final Report

Energy Technology Data Exchange (ETDEWEB)

Polagye, B. L. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Copping, A. E. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Brown-Saracino, J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Suryan, R. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Kramer, S. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Smith, C. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

2014-01-14

To better understand the state of instrumentation and capabilities for monitoring around marine energy converters, the U.S. Department of Energy directed Pacific Northwest National Laboratory and the Northwest National Marine Renewable Energy Center at the University of Washington to convene an invitation-only workshop of experts from around the world to address instrumentation needs.

Environmental monitoring systems: a new type of mobile laboratory

International Nuclear Information System (INIS)

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

1999-01-01

Nuclear facilities are obligated to monitor the environmental radiation in their vicinity, which is often fulfilled by monitoring cars, combined with fixed monitoring stations. The MOLAR Mobile Laboratory for Environmental Radiation Monitoring as described here is being used under normal and accident conditions as a spot check monitoring system or to perform continuous measurements along a driving track. The mobile laboratories are continuously connected with the control centre's CRCS Central Radiological Computer System, where the RIS Radiological Information System provides corresponding evaluation functions. The mobile labs contain measuring and controlling units like γ-dose rate monitors, γ-spectrometer with a HpGe High Purity Germanium detector, a lead shielded measuring cell and MCA Multi-Channel Analyser, portable β-contamination monitor, α/β/γ multipurpose quick measuring unit, aerosol and iodine sampling units. The collected samples are safely stored for the transport to the environmental laboratory for being analysed later. The geographical location of the moving car is continuously determined by the satellite based GPS Global Positioning System and transferred in the on-board rack mounted computer system for being stored and locally displayed. Real-time data transmission via radio and mobile phone is continuously performed to supply the RIS Radiological Information System in the control centre via radio and mobile phone. The latter also serves for voice communication. Currently three MOLAR systems can be operated parallel and independent from the control centre. The system is ready to be extended to more mobile labs. This combination of mobile monitoring, sample analysis and radiological assessment of environmental data in combination with process occurrences has turned out to be a powerful instrument for emergency preparedness and environmental supervising. (orig.) [de

Traceability of a panoramic gamma irradiator using different TLD systems as transfer instruments

International Nuclear Information System (INIS)

Romero, A.M.; Saez, J.C.

1994-01-01

This work shows the calibration in terms of the new operational radiological quantities Hp(10) and H*(10) for different TLD systems (Harshaw TLD-100 and Panasonic UD-802) used in personal and environmental monitoring. The irradiations were performed in the Spanish Reference Laboratory in radiation protection levels, managed by the CIEMAT Metrology of ionizing radiations Unit. With these data, different calibrations of a panoramic gamma irradiator in terms of the radiological quantity for unit of time were established, providing the traceability of the irradiator to the Reference Laboratory using the corresponding TLD systems as transfer instruments. (Author) 9 refs

Traceability of a panoramic gamma irradiator using different TLD systems as transfer Instruments

International Nuclear Information System (INIS)

Romero, A. M.; Saez, J. C

1994-01-01

This work shows the calibration in terms of the new operational radiological quantities Hp (10) and H(10) for different TLD systems (Harshaw TLD-100 and Panasonic UD-002) used in personal and environmental monitoring. The irradiations were performed in the Spanish Reference Laboratory in radiation protection levels, managed by the CIEMAT Metrology of ionizing radiations Unit. With those data, different calibrations of a panoramic gamma irradiator in terms of the radiological quantity for unit of time were established, providing the traceability of the irradiator to the Reference Laboratory using the corresponding TLD systems as transfer instruments. (Author) 9 refs

Remote monitoring of instrumented structures using the Internet information superhighway

Science.gov (United States)

Fuhr, Peter L.; Huston, Dryver R.; Ambrose, Timothy P.

1994-09-01

The requirements of sensor monitoring associated with instrumented civil structures poses potential logistical constraints on manpower, training, and costs. The need for frequent or even continuous data monitoring places potentially severe constraints on overall system performance given real-world factors such as available manpower, geographic separation of the instrumented structures, and data archiving as well as the training and cost issues. While the pool of available low wage, moderate skill workers available to the authors is sizable (undergraduate engineering students), the level of performance of such workers is quite variable leading to data acquisition integrity and continuity issues - matters that are not acceptable in the practical field implementation of such developed systems. In the case of acquiring data from the numerous sensors within the civil structures which the authors have instrumented (e.g., a multistory building, roadway/railway bridges, and a hydroelectric dam), we have found that many of these concerns may be alleviated through the use of an automated data acquisition system which archives the acquired information in an electronic location remotely accessible through the Internet global computer network. It is therefore a possible for the data monitoring to be performed at a remote location with the only requirements for data acquisition being Internet accessibility. A description of the developed scheme is presented as well as guiding philosophies.

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.

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

Operation Praetorian onsite radiological safety report, October 1981-September 1982

International Nuclear Information System (INIS)

Mullen, O.W.; Eubank, B.F.

1983-09-01

PRAETORIAN was the name assigned to the series of underground nuclear experiments conducted at the Nevada Test Site from October 1, 1981 through September 30, 1982. Remote radiation measurements were taken during and after each nuclear experiment by a telemetry system. Monitors with portable radiation detection instruments surveyed reentry routes into ground zeros before other planned entries were made. Continuous surveillance was provided while personnel were in radiation areas and appropriate precautions were taken to protect persons from unnecessary exposure to radiation and toxic gases. Protective clothing and equipment were issued as needed. Complete radiological safety and industrial hygiene coverage was provided during drilling and mineback operations. Telemetered and portable radiation detector measurements are listed. Detection instrumentation used is described and specific operational procedures are defined

Operation QUICKSILVER. Onsite radiological safety report, October 1978-September 1979

International Nuclear Information System (INIS)

Mullen, O.W.; Eubank, B.F.

1980-02-01

QUICKSILVER was the name assigned to the series of underground nuclear experiments conducted at the Nevada Test Site from October 1, 1978 to September 30, 1979. Remote radiation measurements were taken during and after each nuclear experiment by a telemetry system. Monitors with portable radiation detection instruments surveyed reentry routes into ground zeroes before other planned entries were made. Continuous surveillance was provided while personnel were in radiation areas and appropriate precautions were taken to protect persons from unnecessary exposure to radiation and toxic gases. Protective clothing and equipment were issued as needed. Complete radiological safety and industrial hygiene coverage was provided during drilling and mineback operations. Telemetered and portable radiation detector measurements are listed. Detection instrumentation used is described and specific optional procedures are defined

Operation CRESSET: onsite radiological safety report, October 1977--September 1978

International Nuclear Information System (INIS)

Mullen, O.W.; Eubank, B.F.

1979-06-01

CRESSET was the name assigned to the series of underground nuclear experiments conducted at the Nevada Test Site from October 1, 1977 to September 30, 1978. Remote radiation measurements were taken during and after each nuclear experiment by a telemetry system. Monitors with portable radiation detection instruments surveyed reentry routes into ground zeroes before other planned entries were made. Continuous surveillance was provided while personnel were in radiation areas and appropriate precautions were taken to protect persons from unnecessary exposure to radiation and toxic gases. Protective clothing and equipment were issued as needed. Complete radiological safety and industrial hygiene coverage was provided during drilling and mineback operations. Telemetered and portable radiation detector measurements are listed. Detection instrumentation used is described and specific operational procedures are defined

Operation FULCRUM: onsite radiological safety report, October 1976--September 1977

International Nuclear Information System (INIS)

Mullen, O.W.; Eubank, B.F.

1978-03-01

FULCRUM was the name assigned to the series of underground nuclear experiments conducted at the Nevada Test Site from October 1, 1976 to September 30, 1977. Remote radiation measurements were taken during and after each nuclear experiment by a telemetry system. Monitors with portable radiation detection instruments surveyed reentry routes into ground zeroes before other planned entries were made. Continuous surveillance was provided while personnel were in radiation areas and appropriate precautions were taken to protect persons from unnecessary exposure to radiation and toxic gases. Protective clothing and equipment were issued as needed. Complete radiological safety and industrial hygiene coverage was provided during drilling and mineback operations. Telemetered and portable radiation detector measurements are listed. Detection instrumentation used is described and specific operational procedures are defined

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)

Performance Monitoring for Nuclear Safety Related Instrumentation at PUSPATI TRIGA Reactor (RTP)

International Nuclear Information System (INIS)

Zareen Khan Abdul Jalil Khan; Ridzuan Abdul Mutalib; Mohd Sabri Minhat

2015-01-01

The Reactor TRIGA PUSPATI (RTP) at Malaysia Nuclear Agency is a TRIGA Mark II type reactor and pool type cooled by natural circulation of light water. This paper describe on performance monitoring for nuclear safety related instrumentation in TRIGA PUSPATI Reactor (RTP) of based on various parameter of reactor safety instrument channel such as log power, linear power, Fuel temperature, coolant temperature will take into consideration. Methodology of performance on estimation and monitoring is to evaluate and analysis of reactor parameters which is important of reactor safety and control. And also to estimate power measurement, differential of log and linear power and fuel temperature during reactor start-up, operation and shutdown .This study also focus on neutron power fluctuation from fission chamber during reactor start-up and operation. This work will present result of performance monitoring from RTP which indicated the safety parameter identification and initiate safety action on crossing the threshold set point trip. Conclude that performance of nuclear safety related instrumentation will improved the reactor control and safety parameter during reactor start-up, operation and shutdown. (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.

Cavity Attenuated Phase Shift (CAPS) Monitor Instrument Handbook

Energy Technology Data Exchange (ETDEWEB)

Sedlacek, Arthur J. [Brookhaven National Lab. (BNL), Upton, NY (United States)

2016-04-01

The CAPS PMex monitor is a cavity attenuated phase shift extinction instrument. It operates as an optical extinction spectrometer, using a visible-light-emitting diode (LED) as the light source, a sample cell incorporating two high-reflectivity mirrors centered at the wavelength of the LED, and a vacuum photodiode detector. Its efficacy is based on the fact that aerosols are broadband scatterers and absorbers of light.

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

Development of an instrument for fast monitoring of radiotherapy equipment

International Nuclear Information System (INIS)

Khoury, H.J.; Almeida Melo, F. de; Patriota, J.H.; Oliveira Lira, C.B. de

1990-01-01

Radiation therapy machines need a constant monitoring to assure tumoral dose accuracy. Special attention must be given to linear accelerators which should be checked frequently. By this reason, an instrument was developed at the Nuclear Instrumentation Laboratory DEN/UFPE to measure the output energy and beam symmetry. This instrument use three silicon photodiodes as radiation detectors. Two of then were localized at 5cm and 10cm depht at the central axis and one at 5 cm from the center, at the lateral irradiated field. Changes in the photon spectrum are detected by the ratio of upper to lower photodiode response. The radiation field uniformity is checked by the lateral photodiode. (author) [pt

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)

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)

Calibration of dosemeters and survey instruments for photon

International Nuclear Information System (INIS)

Alamares, A.L.; Caseria, E.S.

1995-01-01

The Philippine Nuclear Research Institute (PNRI), the country's regulatory agency, through its Radiation Protection Unit of the Nuclear Regulations Licensing and Safeguard Division provides the calibration services of nuclear instruments used by various institutions. The periodic calibration and standardization of radiation and protection survey instruments are done to insure correct and valid radiation readings. It is also a regulatory requirement for radiation workers to use only operable and precalibrated survey instruments for their work with radioactive materials. The PNRI maintains and operates the Secondary Standard Dosimetry Laboratory (SSDL). It provides the periodic calibration and standardization of radiation monitoring and protection survey instruments, and also the radiological hazard and performance evaluation surveys of radiotherapy facilities and others. For the calibration of survey instruments, the standard sources of Cs-137 and Co-60 are used. The calibration procedures for survey meters and pocket dosimeters are explained. The clients served are shown. The personnel dosimetry using film badges, the application of ICRU operational quantities, and the problems encountered and recommendations are reported. (K.I.)

Field experience in use of radiation instruments in Cirus reactor

International Nuclear Information System (INIS)

Ramesh, N.; Sharma, R.C.; Agarwal, S.K.; Sawant, D.K.; Yadav, R.K.B.; Prasad, S.K.

2005-01-01

Cirus, located at Bhabha Atomic Research Centre, is a 40 MW (Th) research reactor fuelled by natural uranium, moderated by heavy water and cooled by de-mineralized light water. Graphite is used as reflector in this reactor. The reactor, commissioned in the year 1960, was in operation with availability factor of about 70% till early nineties. There after signs of ageing started surfacing up. After ageing studies, refurbishment plan was finalized and executed during the period from 1997-2002. after successful refurbishment, the reactor is in operation at full power. A wide range of radiation instruments have been used at Cirus for online monitoring of the radiological status of various process systems and environmental releases. Also, variety of survey meters, counting systems and monitors have been used by the health physics unit of the reactor for radiation hazard control. Many of these instruments, which were originally of Canadian design, have undergone changes due to obsolescence or as part of upgradation. This paper describes the experience with the radiation instruments of Cirus, bringing out their effectiveness in meeting the design intent, difficulties faced in their field use, and modifications carried out based on the performance feed back. Also, this paper highlights the areas where further efforts are needed to develop nuclear instrumentation to further strengthen monitoring and surveillance. (author)

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)

Investigation of Stability of Precise Geodetic Instruments Used in Deformation Monitoring

Science.gov (United States)

Woźniak, Marek; Odziemczyk, Waldemar

2017-12-01

Monitoring systems using automated electronic total stations are an important element of safety control of many engineering objects. In order to ensure the appropriate credibility of acquired data, it is necessary that instruments (total stations in most of the cases) used for measurements meet requirements of measurement accuracy, as well as the stability of instrument axis system geometry. With regards to the above, it is expedient to conduct quality control of data acquired using electronic total stations in the context of performed measurement procedures. This paper presents results of research conducted at the Faculty of Geodesy and Cartography at Warsaw University of Technology investigating the stability of "basic" error values (collimation, zero location for V circle, inclination), for two types of automatic total stations: TDA 5005 and TCRP 1201+. Research provided also information concerning the influence of temperature changes upon the stability of investigated instrument's optical parameters. Results are presented in graphical analytic technique. Final conclusions propose methods, which allow avoiding negative results of measuring tool-set geometry changes during conducting precise deformation monitoring measurements.

Development of multifunctional radiation monitoring instrument based on PLC technology

International Nuclear Information System (INIS)

Li Ziqiang; Zhu Yuye; Zhuang Min

2007-01-01

This eight-channel multifunctional Radiation Monitoring Instrument is developed by making use of the built-in high-speed counters and the powerful instruction system of the SIEMES SIMATICS S7 series Programmable Logic Controllers (PLC) to record and process the pulse signal output by the detectors. The instrument with functions, such as analog and digital display, digital storage of digital data, pulse signal generator, network communication, can connect various types of pulse detectors. The initial process can be translated between Graduation Apparatus method and Formula method. the logicality of the high-dosage warning system is processed itself. The signal output will drive the alarm lights and bell directly. This paper mainly describes the configuration, programming and feature of the instrument. (authors)

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.)

Radiological imaging in endocrine hypertension

Directory of Open Access Journals (Sweden)

Chandan J Das

2011-01-01

Full Text Available While different generations of assays have played important role in elucidating causes of different endocrine disorders, radiological techniques are instrumental in localizing the pathology. This statement cannot be truer in any disease entity other than endocrine hypertension. This review makes an effort to highlight the role of different radiological modalities, especially ultrasonography, computed tomography and magnetic resonance imaging, in the evaluation of different causes of endocrine hypertension.

WARMS - a continuous on-line environmental and emergency radiation monitoring system

International Nuclear Information System (INIS)

Ramsden, D.

1984-01-01

The Winfrith Airborne Release Monitoring System (WARMS) is used to monitor the environment around the Winfrith reactor site. It operates continuously monitoring the background radiation at 16 outstations and can provide rapid information should an accidental release occur. WARMS was developed jointly by the Radiological Safety Division and the Control and Instrumentation Division at Winfrith in association with the Safety and Reliability Directorate at Culcheth which developed the software. The system became operational in the autumn of 1983 and has since demonstrated a high degree of reliability and effectiveness. (author)

The regulation of the radiological protection in Mexico

International Nuclear Information System (INIS)

Eibenschutz H, J.

2008-12-01

The regulation antecedents in nuclear question in Mexico are placed in 1950, with the promulgation of L aw that declares national mining reserves the uranium deposits, thorium and the other substances of which obtains fissionable isotopes that can produce nuclear energy , instrument that stipulated the control of uranium, thorium, as to its it indicated it name, and other fissionable substances, on the part of the state, although they were without a doubt the respective institutions, the National Commission of Nuclear Energy in 1955, and the one of the National Commission of Nuclear Safety and Safeguards (CNSNS) in 1979, those that allowed the development of a prescribed frame in the nuclear and radiological areas. One characteristic of the regulation in radiological protection is the variety in the authorities type that have incidence in the regulation, as a result of the different approaches with which it can be approached. For example, in Mexico normative instruments with content in radiological protection exist and are watched over the Health Secretary, who is oriented to the protection of the patient, their relatives and the medical body; Work and Social Welfare Secretary, with a labor approach; Communications and Transport Secretary, which regulates the transport of nuclear and radioactive materials; Finance and Public Credit Secretary, who regulates the import and export of radioactive materials; Environment and Natural Resources Secretary, which regulates the environment protection; Energy Secretary who has responsibilities inside of the p rescribed law of article 27 constitutional in nuclear matter ; and within the energy sector, the CNSNS that expedite and watch the fulfillment of normative in radiological protection and nuclear safety. In order to resist effects of on regulation; frequently inter institutional agreements are carried out in which the areas of monitoring are agreed by each authority. The regulation in radiological protection demands the

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.

The laser absorption spectrometer - A new remote sensing instrument for atmospheric pollution monitoring

Science.gov (United States)

Shumate, M. S.

1974-01-01

An instrument capable of remotely monitoring trace atmospheric constituents is described. The instrument, called a laser absorption spectrometer, can be operated from an aircraft or spacecraft to measure the concentration of selected gases in three dimensions. This device will be particularly useful for rapid determination of pollutant levels in urban areas.

The sensitivity to humidity of radon monitoring instruments

International Nuclear Information System (INIS)

Schmied, H.

1984-01-01

In a project funded by the Swedish Building Research Council (BFR) a continuous radon monitoring instrument (RGA-400 EDA Instr. Inc.) with electrostatic field collection has been calibrated. The original calibration factor gave no reliable radon readings and was therefore corrected for relative humidity by EDA. From four calibrations in the radon chamber at the Swedish Radiation Protection Board (SSI) it was clear that the instrument was sensitive to absolute humidity, which gave better agreement than relative humidity or temperature. Sensitivity to humidity for this principle of measure ment has been presented in various papers without presenting any combined influence with temperature, which can lead to the wrong conclusions, especially when the temperature levels differ. Some laboratories use humidity absorbants to overcome this humidity dependence. In this paper the calibration results for the FGA-400 radon readings only, are presented. (Author)

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)

A Simple Instrumentation System for Large Structure Vibration Monitoring

Directory of Open Access Journals (Sweden)

Didik R. Santoso

2010-12-01

Full Text Available Traditional instrumentation systems used for monitoring vibration of large-scale infrastructure building such as bridges, railway, and others structural building, generally have a complex design. Makes it simple would be very useful both in terms of low-cost and easy maintenance. This paper describes how to develop the instrumentation system. The system is built based on distributed network, with field bus topology, using single-master multi-slave architecture. Master is a control unit, built based on a PC equipped with RS-485 interface. Slave is a sensing unit; each slave was built by integrating a 3-axis vibration sensor with a microcontroller based data acquisition system. Vibration sensor is designed using the main components of a MEMS accelerometer. While the software is developed for two functions: as a control system hardware and data processing. To verify performance of the developed instrumentation system, several laboratory tests have been performed. The result shows that the system has good performance.

Tesla VUPJT instruments for radiation monitoring of working environment and selected aplications

International Nuclear Information System (INIS)

Slezak, V.; Kula, J.; Novakova, O.; Jursova, L.; Severa, L.

1986-01-01

A survey is presented of the current state of development and production of instruments for ionizing radiation monitoring and detection, also listing possible applications in the national economy. (author)

Radiological safety related provisions and instrumentation in Indian PHWRs

International Nuclear Information System (INIS)

Ramamirtham, B.; Dabhadkar, S.B.; Sah, B.M.L.

1994-01-01

The collective radiation doses at the nuclear power plants (NPPs) world-wide have shown a significant downward trend which has resulted due to on-going efforts to keep exposures ALARA and also to meet the recently revised individual exposure limits of ICRP. In keeping with this trend a number of additional designed dose reduction features are also being incorporated in the Indian NPPs. These include better separation and shielding of radioactive systems/equipment, elimination of the use of cobalt-free materials in active systems, improved leak tightness of systems carrying heavy water, augmented ventilation and atmosphere drying systems, etc. The build-up of radiation levels in primary heat transport (PHT) system is controlled by incorporating improvements in the fuel performance and periodic system decontamination. Plant layouts have been modified, to improve the contamination control arrangements and optimum utilisation of dosimetry devices. For better control of internal exposures continuous efforts are on to make the protective gear more user-friendly. Green belts are being established around the NPPs to provide further protection against environmental impact. A number of additional radiation monitoring instruments /systems have been incorporated to provide information on radiation/activity levels, both within the plant and outside areas, particularly during emergency conditions. For processing of data provided by the large numbers of installed radiation instruments and initiating corrective/alarm actions, a computerised system (RADAS) has been provided. (author). 7 refs., 2 tabs

Designing of a mobile decontamination facility (MDF) for preparedness and response to nuclear/radiological emergencies

International Nuclear Information System (INIS)

Joshi, G.H.; Garai, S.K.; Chatterjee, M.K.; Pradeepkumar, K.S.; Sharma, D.N.

2005-01-01

During a radiological emergency in public domain, likelihood of radioactive contamination cannot be completely ruled out. Timely and effective decontamination can significantly reduce possible external and internal radiation exposure to public. The objective of designing of a mobile decontamination facility is to develop the capability for decontaminating affected persons in case of any radiological emergency in public domain. A fully equipped decontamination facility on the wheels will be able to reach at the scene and will be able to decontaminate a large number of victims with the help of optimized decontamination procedures in short duration avoiding unwanted radiation exposure. This self-supporting decontamination facility is designed to be equipped with sufficient number of radiation monitoring instruments, equipments for decontamination, decontamination agents etc. (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)

Radiological instrument

International Nuclear Information System (INIS)

Kronenberg, S.; McLaughlin, W.L.; Seibentritt, C.R. Jr.

1986-01-01

An instrument is described for measuring radiation, particularly nuclear radiation, comprising: a radiation sensitive structure pivoted toward one end and including a pair of elongated solid members contiguously joined together along their length dimensions and having a common planar interface therebetween. One of the pairs of members is comprised of radiochromic material whose index of refraction changes due to anomolous dispersion as a result of being exposed to nuclear radiation. The pair of members further has mutually different indices of refraction with the member having the larger index of refraction further being transparent for the passage of light and of energy therethrough; means located toward the other end of the structure for varying the angle of longitudinal elevation of the pair of members; means for generating and projecting a beam of light into one end of the member having the larger index of refraction. The beam of light is projected toward the planar interface where it is reflected out of the other end of the same member as a first output beam; means projecting a portion of the beam of light into one end of the member having the larger index of refraction where it traverses therethrough without reflection and out of the other end of the same member as a second output beam; and means adjacent the structure for receiving the first and second output beams, whereby a calibrated change in the angle of elevation of the structure between positions of equal intensity of the first and second output beams prior to and following exposure provides a measure of the radiation sensed due to a change of refraction of the radiochromic material

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)

Remote Monitoring and Instrumentation Strategies for Integral Reactors

International Nuclear Information System (INIS)

Upadhyaya, Belle R.; Lish, Matthew R.; Tarver, Rayan A.; Hines, J. Wesley

2014-01-01

The University of Tennessee is engaged in research and development projects related to instrumentation and controls for small modular reactors (SMR) and integral pressurized water reactors (iPWR). The approach incorporates the deployment of physics-based models for control design and parameter estimation, development of noncontact sensors for flow monitoring, and placement of sensors to maximize fault detection and isolation. The results of research and development illustrate the feasibility of sensor location in space-constrained environment. Major issues and challenges in I and C design are addressed

Remote Monitoring and Instrumentation Strategies for Integral Reactors

Energy Technology Data Exchange (ETDEWEB)

Upadhyaya, Belle R.; Lish, Matthew R.; Tarver, Rayan A.; Hines, J. Wesley [University of Tennessee, Knoxville (United States)

2014-08-15

The University of Tennessee is engaged in research and development projects related to instrumentation and controls for small modular reactors (SMR) and integral pressurized water reactors (iPWR). The approach incorporates the deployment of physics-based models for control design and parameter estimation, development of noncontact sensors for flow monitoring, and placement of sensors to maximize fault detection and isolation. The results of research and development illustrate the feasibility of sensor location in space-constrained environment. Major issues and challenges in I and C design are addressed.

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.

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

Applied research of environmental monitoring using instrumental neutron activation analysis

Energy Technology Data Exchange (ETDEWEB)

Chung, Young Sam; Moon, Jong Hwa; Chung, Young Ju

1997-08-01

This technical report is written as a guide book for applied research of environmental monitoring using Instrumental Neutron Activation Analysis. The contents are as followings; sampling and sample preparation as a airborne particulate matter, analytical methodologies, data evaluation and interpretation, basic statistical methods of data analysis applied in environmental pollution studies. (author). 23 refs., 7 tabs., 9 figs.

A mobile autonomous robot for radiological surveys

International Nuclear Information System (INIS)

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

1992-01-01

The Robotics Development Group at the Savannah River Site is developing an autonomous robot (SIMON) to perform radiological surveys of potentially contaminated floors. The robot scans floors at a speed of one-inch/second and stops, sounds an alarm, and flashes lights when contamination in a certain area is detected. The contamination of interest here is primarily alpha and beta-gamma. The robot, a Cybermotion K2A base, is radio controlled, uses dead reckoning to determine vehicle position, and docks with a charging station to replenish its batteries and calibrate its position. It uses an ultrasonic ranging system for collision avoidance. In addition, two safety bumpers located in the front and the back of the robot will stop the robots motion when they are depressed. Paths for the robot are preprogrammed and the robots motion can be monitored on a remote screen which shows a graphical map of the environment. The radiation instrument being used is an Eberline RM22A monitor. This monitor is microcomputer based with a serial I/0 interface for remote operation. Up to 30 detectors may be configured with the RM22A

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.

L-035: EPR-First Responders: Basic Risk and Protection for First Responders to a Radiological Emergency

International Nuclear Information System (INIS)

2011-01-01

There are some basic actions and self-protective actions to take in an radiological emergency. Radiation is detected with appropriate instrumentation and measuring the rate of exposure (Sv per hour) in contact with radioactive materials involved. Is important to note: Responsive to a radiological emergency, tool to identify radiological risks, radiation protection, radioactive symbol and instrumentation

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 ..

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

International Nuclear Information System (INIS)

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

1993-01-01

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

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,...

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

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)

XML for nuclear instrument control and monitoring: an approach towards standardisation

International Nuclear Information System (INIS)

Bharade, S.K.; Ananthakrishnan, T.S.; Kataria, S.K.; Singh, S.K.

2004-01-01

Communication among heterogeneous system with applications running under different operating systems and applications developed under different platforms has undergone rapid changes due to the adoption of XML standards. These are being developed for different industries like Chemical, Medical, Commercial etc. The High Energy Physics community has already a standard for exchange of data among different applications , under heterogeneous distributed systems like the CMS Data Acquisition System. There are a large number of Nuclear Instruments supplied by different manufactures which are increasingly getting connected. This approach is getting wider acceptance in instruments at reactor sites, accelerator sites and complex nuclear experiments -especially at centres like CERN. In order for these instruments to be able to describe the data which is available from them in a platform independent manner XML approach has been developed. This paper is the first attempt at Electronics Division for proposing an XML standard for control, monitoring, Data Acquisition and Analysis generated by Nuclear Instruments at Accelerator sites, Nuclear Reactor plant and Laboratory. The gamut of Nuclear Instruments include Multichannel Analysers, Health Physics Instruments, Accelerator Control Systems, Reactor Regulating systems, Flux mapping Systems etc. (author)

Raman Spectroscopy for In-Line Water Quality Monitoring — Instrumentation and Potential

Science.gov (United States)

Li, Zhiyun; Deen, M. Jamal; Kumar, Shiva; Selvaganapathy, P. Ravi

2014-01-01

Worldwide, the access to safe drinking water is a huge problem. In fact, the number of persons without safe drinking water is increasing, even though it is an essential ingredient for human health and development. The enormity of the problem also makes it a critical environmental and public health issue. Therefore, there is a critical need for easy-to-use, compact and sensitive techniques for water quality monitoring. Raman spectroscopy has been a very powerful technique to characterize chemical composition and has been applied to many areas, including chemistry, food, material science or pharmaceuticals. The development of advanced Raman techniques and improvements in instrumentation, has significantly improved the performance of modern Raman spectrometers so that it can now be used for detection of low concentrations of chemicals such as in-line monitoring of chemical and pharmaceutical contaminants in water. This paper briefly introduces the fundamentals of Raman spectroscopy, reviews the development of Raman instrumentations and discusses advanced and potential Raman techniques for in-line water quality monitoring. PMID:25230309

Accreditation of professionals for radiological protection in medical and dental radiology at Minas Gerais, Brazil

International Nuclear Information System (INIS)

Silva, Teogenes A. da; Pereira, Elton G.; Alonso, Thessa C.; Guedes, Elton C.; Goncalves, Elaine C.; Nogueira, Maria Angela A.

2000-01-01

The role of the CDTN/CNEN as far as the radiological protection services in the medical and dental radiology has changed a lot due to the new Regulatory Directives. The CDTN/CNEN was recognized as the regional reference center for providing not only radiological survey services, but to coordinate an accreditation procedure for professional persons to be accepted by the State Regulatory Authorities to work at Minas Gerais. All the new activities were formalized in a Cooperation Agreement between the CDTN/CNEN and the Regulatory Authority. This paper describes the accreditation procedure for candidates, the adopted requirements, the intercomparison results among measuring instruments and the main achievements during the first year of the Agreement. (author)

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.)

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

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.

Technological considerations in emergency instrument preparedness

International Nuclear Information System (INIS)

Selby, J.M.

1976-01-01

Emergency preparedness has been emphasized during the development of the nuclear industry. Existing instrumentation technology has been effectively applied to minimizing the probability of accidents. Radiological instrumentation provided for the measurement of ambient radiation levels or routine releases of radioactive material is usually adequate to provide an early warning that an accident is occurring. In contrast, radiological instrumentation capable of providing a reasonable measure of the source term which could be involved in a severe accident has not received enough attention. In emergency planning the capability should be established for identifying as promptly as possible the need for evasive action out in the plant environs and for minimizing the consequences of an accident in terms of resultant human exposure. Therefore instrumentation is required to measure the source term no matter where the point of release might be, together with instrumentation for obtaining meteorological data sufficient to establish the path of the release in the environment

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 Situation at the Bomb Test Sites

International Nuclear Information System (INIS)

Valkovic, V.

1998-01-01

An overview of radiological situation at the selected bomb test sites is presented. The report is based on the reports and measurements performed by IAEA while the author was a head of its Physics-Chemistry-Instrumentation Laboratory. Radiological conditions at Bikini Atoll (USA testing ground), Mururoa and Fangataufa Atolls (French testing ground) and Semipalatinsk (SSSR testing ground) have been discussed in some details. (author)

Introduction to radiological performance assessment

International Nuclear Information System (INIS)

Moss, G.

1995-02-01

A radiological performance assessment is conducted to provide reasonable assurance that performance objectives for low-level radioactive waste (LLW) disposal will be met. Beginning in the early stages of development, a radiological performance assessment continues through the operational phase, and is instrumental in the postclosure of the facility. Fundamental differences exist in the regulation of commercial and defense LLW, but the radiological performance assessment process is essentially the same for both. The purpose of this document is to describe that process in a concise and straightforward manner. This document focuses on radiological performance assessment as it pertains to commercial LLW disposal, but is applicable to US Department of Energy sites as well. Included are discussions on performance objectives, site characterization, and how a performance assessment is conducted. A case study is used to illustrate how the process works as a whole. A bibliography is provided to assist in locating additional information

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)

Development and implantation of a control and data acquisition program for the calibration of instruments for diagnostic radiology; Desenvolvimento e implantacao de um programa de controle e aquisicao de dados na calibracao de instrumentos em radiodiagnostico

Energy Technology Data Exchange (ETDEWEB)

Betti, Flavio

2007-07-01

Design techniques of an automatic control system implementing corrected kerma determination and shutter command in the calibration laboratory at IPEN are shown, as well as the periodic calibration program developed for a monitor chamber for several X-ray beam qualities used for diagnostic radiology and radiation protection instruments. Two reference electrometers, a multichannel secondary standard thermometer, and an absolute pressure barometer were connected to the Rs-232 interface from a PC computer equipped with a National Instruments multi function analog and digital I/O card. LabVIEW{sup MR} was chosen as programming tool, which allowed for the development of a suite of programs for both controlling the shutter timing cycles and the calibration of the monitor chamber against a reference standard. A detailed description of the methods used for troubleshooting, fine tuning of parameters and evaluation of program results is followed by an analysis showing that considerable advantages regarding reduction of time and precision improvements during the calibrations could be achieved by the use of the developed programs, particularly under adverse conditions like those found during short expositions, or instead during long irradiation intervals where fluctuation of parameters like kerma rate or room conditions (temperature or pressure) can be found. (author)

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

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

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

Instrumentation Recommendations for Volcano Monitoring at U.S. Volcanoes Under the National Volcano Early Warning System

Science.gov (United States)

Moran, Seth C.; Freymueller, Jeff T.; LaHusen, Richard G.; McGee, Kenneth A.; Poland, Michael P.; Power, John A.; Schmidt, David A.; Schneider, David J.; Stephens, George; Werner, Cynthia A.; White, Randall A.

2008-01-01

As magma moves toward the surface, it interacts with anything in its path: hydrothermal systems, cooling magma bodies from previous eruptions, and (or) the surrounding 'country rock'. Magma also undergoes significant changes in its physical properties as pressure and temperature conditions change along its path. These interactions and changes lead to a range of geophysical and geochemical phenomena. The goal of volcano monitoring is to detect and correctly interpret such phenomena in order to provide early and accurate warnings of impending eruptions. Given the well-documented hazards posed by volcanoes to both ground-based populations (for example, Blong, 1984; Scott, 1989) and aviation (for example, Neal and others, 1997; Miller and Casadevall, 2000), volcano monitoring is critical for public safety and hazard mitigation. Only with adequate monitoring systems in place can volcano observatories provide accurate and timely forecasts and alerts of possible eruptive activity. At most U.S. volcanoes, observatories traditionally have employed a two-component approach to volcano monitoring: (1) install instrumentation sufficient to detect unrest at volcanic systems likely to erupt in the not-too-distant future; and (2) once unrest is detected, install any instrumentation needed for eruption prediction and monitoring. This reactive approach is problematic, however, for two reasons. 1. At many volcanoes, rapid installation of new ground-1. based instruments is difficult or impossible. Factors that complicate rapid response include (a) eruptions that are preceded by short (hours to days) precursory sequences of geophysical and (or) geochemical activity, as occurred at Mount Redoubt (Alaska) in 1989 (24 hours), Anatahan (Mariana Islands) in 2003 (6 hours), and Mount St. Helens (Washington) in 1980 and 2004 (7 and 8 days, respectively); (b) inclement weather conditions, which may prohibit installation of new equipment for days, weeks, or even months, particularly at

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 ...

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)

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)

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)

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)

Design of a instrumentation module for monitoring ingestive behavior in laboratory studies.

Science.gov (United States)

Fontana, Juan M; Lopez-Meyer, Paulo; Sazonov, Edward S

2011-01-01

The development of accurate and objective tools for monitoring of ingestive behavior (MIB) is one of the most important needs facing studies of obesity and eating disorders. This paper presents the design of an instrumentation module for non-invasive monitoring of food ingestion in laboratory studies. The system can capture signals from a variety of sensors that characterize ingestion process (such as acoustical and other swallowing sensors, strain sensor for chewing detection and self-report buttons). In addition to the sensors, the data collection system integrates time-synchronous video footage that can be used for annotation of subject's activity. Both data and video are simultaneously and synchronously acquired and stored by a LabVIEW-based interface specifically developed for this application. This instrumentation module improves a previously developed system by eliminating the post-processing stage of data synchronization and by reducing the risks of operator's error.

16 CFR Figures 1 and 2 to Part 1204 - Suggested Instrumentation for Current Monitoring Device and High Voltage Facility

Science.gov (United States)

2010-01-01

... 16 Commercial Practices 2 2010-01-01 2010-01-01 false Suggested Instrumentation for Current Monitoring Device and High Voltage Facility 1 Figures 1 and 2 to Part 1204 Commercial Practices CONSUMER... Instrumentation for Current Monitoring Device and High Voltage Facility EC03OC91.008 ...

Board's system of publications. [National Radiological Protection Board

Energy Technology Data Exchange (ETDEWEB)

Gaines, M J [National Radiological Protection Board, Harwell (UK)

1978-07-01

The purpose of each of the several classes of publication issued by the National Radiological Protection Board is stated. The classes are: advice on standards for protection, emergency reference levels, technical reports, instrument evaluation reports, annual research and development reports, three-yearly reports on the work of the NRPB, miscellaneous specialist booklets, publications for the layman, radiological protection bulletin, information sheets, and brochures.

Proceedings of the 5. Regional congress on radiation protection and safety; 2. Iberian and Latin American Congress on Radiological Protection Societies; Regional IRPA Congress

International Nuclear Information System (INIS)

2001-01-01

The Fifth Regional Congress on Radiation Protection and Nuclear Safety has been held in Recife (Brazil), from 29th April to 4th May 2001. The congress was hosted by the Brazilian Radiation Protection Society, under the joint sponsorship of FRALC and UFPE-DEN Department of Nuclear Energy. Its designation as a Regional IRPA Congress has been requested. The main purpose of the meeting was to bring together professionals from the industry, universities and research laboratories to present and discuss the latest research results, and to review the state of the art on applied and fundamental aspects of the radiation protection. These specialists have talked about nuclear safety and radiological protection, radiation natural exposure, biological effect of radiation, radiotherapy and medical radiological safety, radiological safety in industry and research. In their discussions, also were included 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

Hanford double shell tank corrosion monitoring instrument tree prototype

International Nuclear Information System (INIS)

Nelson, J.L.; Edgemon, G.L.; Ohl, P.C.

1995-11-01

High-level nuclear wastes at the Hanford site are stored underground in carbon steel double-shell and single-shell tanks (DSTs and SSTs). The installation of a prototype corrosion monitoring instrument tree into DST 241-A-101 was completed in December 1995. The instrument tree has the ability to detect and discriminate between uniform corrosion, pitting, and stress corrosion cracking (SCC) through the use of electrochemical noise measurements and a unique stressed element, three-electrode probe. The tree itself is constructed of AISI 304L stainless steel (UNS S30403), with probes in the vapor space, vapor/liquid interface and liquid. Successful development of these trees will allow their application to single shell tanks and the transfer of technology to other US Department of Energy (DOE) sites. Keywords: Hanford, radioactive waste, high-level waste tanks, electrochemical noise, probes, double-shell tanks, single-shell tanks, corrosion

Towards the retrieval of tropospheric ozone with the ozone monitoring instrument (OMI)

NARCIS (Netherlands)

Mielonen, T.; De Haan, J.F.; Van Peet, J.C.A.; Eremenko, M.; Veefkind, J.P.

2015-01-01

We have assessed the sensitivity of the operational Ozone Monitoring Instrument (OMI) ozone profile retrieval algorithm to a number of a priori and radiative transfer assumptions. We studied the effect of stray light correction, surface albedo assumptions and a priori ozone profiles on the retrieved

The community environmental monitoring program: a model for stakeholder involvement in environmental monitoring

International Nuclear Information System (INIS)

Hartwell, William T.; Shafer, David S.

2007-01-01

Since 1981, the Community Environmental Monitoring Program (CEMP) has involved stakeholders directly in its daily operation and data collection, as well as in dissemination of information on radiological surveillance in communities surrounding the Nevada Test Site (NTS), the primary location where the United States (US) conducted nuclear testing until 1992. The CEMP is funded by the US Department of Energy's National Nuclear Security Administration, and is administered by the Desert Research Institute (DRI) of the Nevada System of Higher Education. The CEMP provides training workshops for stakeholders involved in the program, and educational outreach to address public concerns about health risk and environmental impacts from past and ongoing NTS activities. The network includes 29 monitoring stations located across an approximately 160,000 km 2 area of Nevada, Utah and California in the southwestern US. The principal radiological instruments are pressurized ion chambers for measuring gamma radiation, and particulate air samplers, primarily for alpha/beta detection. Stations also employ a full suite of meteorological instruments, allowing for improved interpretation of the effects of meteorological events on background radiation levels. Station sensors are wired to state-of-the-art data-loggers that are capable of several weeks of on-site data storage, and that work in tandem with a communications system that integrates DSL and wireless internet, land line and cellular phone, and satellite technologies for data transfer. Data are managed through a platform maintained by the Western Regional Climate Center (WRCC) that DRI operates for the U.S. National Oceanic and Atmospheric Administration. The WRCC platform allows for near real-time upload and display of current monitoring information in tabular and graphical formats on a public web site. Archival data for each station are also available on-line, providing the ability to perform trending analyses or calculate site

Multisensor Instrument for Real-Time Biological Monitoring

Science.gov (United States)

Zhang, Sean (Zhanxiang); Xu, Guoda; Qiu, Wei; Lin, Freddie

2004-01-01

The figure schematically depicts an instrumentation system, called a fiber optic-based integration system (FOBIS), that is undergoing development to enable real-time monitoring of fluid cell cultures, bioprocess flows, and the like. The FOBIS design combines a micro flow cytometer (MFC), a microphotometer (MP), and a fluorescence-spectrum- or binding-force-measuring micro-sensor (MS) in a single instrument that is capable of measuring multiple biological parameters simultaneously or sequentially. The fiber-optic-based integration system is so named because the MFC, the MP, and the MS are integrated into a single optical system that is coupled to light sources and photometric equipment via optical fibers. The optical coupling components also include a wavelength-division multiplexer and diffractive optical elements. The FOBIS includes a laserdiode- and fiber-optic-based optical trapping subsystem (optical tweezers ) with microphotometric and micro-sensing capabilities for noninvasive confinement and optical measurement of relevant parameters of a single cell or other particle. Some of the measurement techniques implemented together by the FOBIS have long been used separately to obtain basic understanding of the optical properties of individual cells and other organisms, the optical properties of populations of organisms, and the interrelationships among these properties, physiology of the organisms, and physical processes that govern the media that surround the organisms. For example, flow cytometry yields information on numerical concentrations, cross-sectional areas, and types of cells or other particles. Micro-sensing can be used to measure pH and concentrations of oxygen, carbon dioxide, glucose, metabolites, calcium, and antigens in a cell-culture fluid, thereby providing feedback that can be helpful in improving control over a bioprocess. Microphotometry (including measurements of scattering and fluorescence) can yield further information about optically

Auto-associative Kernel Regression Model with Weighted Distance Metric for Instrument Drift Monitoring

International Nuclear Information System (INIS)

Shin, Ho Cheol; Park, Moon Ghu; You, Skin

2006-01-01

Recently, many on-line approaches to instrument channel surveillance (drift monitoring and fault detection) have been reported worldwide. On-line monitoring (OLM) method evaluates instrument channel performance by assessing its consistency with other plant indications through parametric or non-parametric models. The heart of an OLM system is the model giving an estimate of the true process parameter value against individual measurements. This model gives process parameter estimate calculated as a function of other plant measurements which can be used to identify small sensor drifts that would require the sensor to be manually calibrated or replaced. This paper describes an improvement of auto associative kernel regression (AAKR) by introducing a correlation coefficient weighting on kernel distances. The prediction performance of the developed method is compared with conventional auto-associative kernel regression

Monitoring student attendance, participation, and performance improvement: an instrument and forms.

Science.gov (United States)

Kosta, Joanne

2012-01-01

When students receive consistent and fair feedback about their behavior, program liability decreases. To help students to have a clearer understanding of minimum program standards and the consequences of substandard performance, the author developed attendance and participation monitoring and performance improvement instruments. The author discusses the tools that address absenteeism, tardiness, unprofessional, and unsafe clinical behaviors among students.

Operation Grenadier. Onsite radiological safety report for announced nuclear tests, October 1984-September 1985

International Nuclear Information System (INIS)

Mullen, O.W.; Eubank, B.F.

1986-09-01

Grenadier was the name assigned to the series of underground nuclear experiments conducted at the Nevada Test Site from October 1, 1984 through September 30, 1985. This report includes those experiments publicly announced. Remote radiation measurements were taken during and after each nuclear experiment by a telemetry system. Monitors with portable radiation detection instruments surveyed reentry routes into ground zeros before other planned entries were made. Continuous surveillance was provided while personnel were in radiation areas and appropriate precautions were taken to protect persons from unnecessary exposure to radiation and toxic gases. Protective clothing and equipment were issued as needed. Complete radiological safety and industrial hygiene coverage was provided during drilling and mineback operations. Telemetered and portable radiation detector measurements are listed. Detection instrumentation used is described and specific operational procedures are defined

Operation fusileer onsite radiological safety report for announced nuclear tests, October 1983-September 1984

International Nuclear Information System (INIS)

Mullen, O.W.; Eubank, B.F.

1985-08-01

Fusileer was the name assigned to the series of underground nuclear experiments conducted at the Nevada Test Site from October 1, 1983 through September 30, 1984. This report is limited to announced nuclear tests. Remote radiation measurements were taken during and after each nuclear experiment by a telemetry system. Monitors with portable radiation detection instruments surveyed reentry routes into ground zeros before other planned entries were made. Continuous surveillance was provided while personnel were in radiation areas and appropriate precautions were taken to protect persons from unnecessary exposure to radiation and toxic gases. Protective clothing and equipment were issued as needed. Complete radiological safety and industrial hygiene coverage was provided during drilling and mineback operations. Telemetered and portable radiation detector measurements are listed. Detection instrumentation used is described and specific operational procedures are defined

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

Aerosols and surface UV products form Ozone Monitoring Instrument observations: An overview

NARCIS (Netherlands)

Torres, O.; Tanskanen, A.; Veihelmann, B.; Ahn, C.; Braak, R.; Bhartia, P.K.; Veefkind, J.P.; Levelt, P.F.

2007-01-01

We present an overview of the theoretical and algorithmic aspects of the Ozone Monitoring Instrument (OMI) aerosol and surface UV algorithms. Aerosol properties are derived from two independent algorithms. The nearUV algorithm makes use of OMI observations in the 350-390 nm spectral region to

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

Instrument evaluation no. 10. Scanray radiation meter type 751

CERN Document Server

Burgess, P H; White, D F

1978-01-01

The various radiations encountered in radiological protection cover a wide range of energies and radiation measurements have to be carried out under an equally broad spectrum of environmental conditions. This report is one of a series intended to give information on the performance characteristics of radiological protection instruments, to assist in the selection of appropriate instruments for a given purpose, to interpret the results obtained with such instruments, and, in particular, to know the likely sources and magnitude of errors that might be associated with measurements in the field. The radiation, electrical and environmental characteristics of radiation protection instruments are considered together with those aspects of the construction which make an instrument convenient for routine use. To provide consistent criteria for instrument performance, the range of tests performed on any particular class of instrument, the test methods and the criteria of acceptable performance are based broadly on the a...

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

Evaluation of the performance of diagnosis monitors in use in Salvador city: pilot study

International Nuclear Information System (INIS)

Garcia, Igor; Geambastiani, Paulo; Ferreira, Mario; Macedo, Eric; Navarro, Marcus; Navarro, Valeria; Pereira, Lara; Jesus, Evandro de; Leite, Handerson Jorge Dourado

2016-01-01

Radiologically, the image quality is the accuracy of the representation of the patient's anatomy. Considering the importance of the performance of the monitors to the overall effectiveness of a practice of diagnostic imaging, the objective of this study is to evaluate the performance of diagnostic monitors in use, using the method described in the report 03 of the AAPA and Spanish protocol, using calibrated instrumentation traceable to NIST and to RBC. The results of the monitors evaluated to date show 100% compliance for geometric distortion tests and internal reflection and 0% compliance to the dependence of luminance test. (author)

Radiological error: analysis, standard setting, targeted instruction and teamworking

International Nuclear Information System (INIS)

FitzGerald, Richard

2005-01-01

Diagnostic radiology does not have objective benchmarks for acceptable levels of missed diagnoses [1]. Until now, data collection of radiological discrepancies has been very time consuming. The culture within the specialty did not encourage it. However, public concern about patient safety is increasing. There have been recent innovations in compiling radiological interpretive discrepancy rates which may facilitate radiological standard setting. However standard setting alone will not optimise radiologists' performance or patient safety. We must use these new techniques in radiological discrepancy detection to stimulate greater knowledge sharing, targeted instruction and teamworking among radiologists. Not all radiological discrepancies are errors. Radiological discrepancy programmes must not be abused as an instrument for discrediting individual radiologists. Discrepancy rates must not be distorted as a weapon in turf battles. Radiological errors may be due to many causes and are often multifactorial. A systems approach to radiological error is required. Meaningful analysis of radiological discrepancies and errors is challenging. Valid standard setting will take time. Meanwhile, we need to develop top-up training, mentoring and rehabilitation programmes. (orig.)

Remote sensing optical instrumentation for enhanced space weather monitoring from the L1 and L5 Lagrange points

Science.gov (United States)

Kraft, S.; Puschmann, K. G.; Luntama, J. P.

2017-09-01

As part of the Space Situational Awareness Programme (SSA), ESA has initiated the assessment of two missions currently foreseen to be implemented to enable enhanced space weather monitoring. These missions utilize the positioning of satellites at the Lagrangian L1 and L5 points. These Phase 0 or Pre-Phase A mission studies are about to be completed and will thereby have soon passed the Mission Definition Review. Phase A studies are planned to start in 2017. The space weather monitoring system currently considers four remote sensing optical instruments and several in-situ instruments to analyse the Sun and the solar wind conditions, in order to provide early warnings of increased solar activity and to identify and mitigate potential threats to society and ground, airborne and space based infrastructure. The suggested optical instruments take heritage from ESA and NASA science missions like SOHO, STEREO and Solar Orbiter, but the instruments are foreseen to be optimized for operational space weather monitoring purposes with high reliability and robustness demands. The instruments are required to provide high quality measurements particularly during severe space weather events. The program intends to utilize the results of the on-going ESA instrument prototyping and technology development activities, and to initiate pre-developments of the operational space weather instruments to ensure the required maturity before the mission implementation.

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)

Effective cloud fractions from the Ozone Monitoring Instrument: theoretical framework and validation

NARCIS (Netherlands)

Stammes, P.; Sneep, M.; Haan, de J.F.; Veefkind, J.P.; Wang, P.; Levelt, P.F.

2008-01-01

The Dutch-Finnish Ozone Monitoring Instrument (OMI) on board NASA's EOS-Aura satellite is measuring ozone, NO2, and other trace gases with daily global coverage. To correct these trace gas retrievals for the presence of clouds, there are two OMI cloud products, based on different physical processes,

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)

Recent Japanese Industrial Standards concerned with radiological monitors

International Nuclear Information System (INIS)

Katoh, Akira

1983-01-01

JIS has achieved large role to keep the quality and performance of products above certain levels and to assure the uniformity and interchangeability. The JIS in radiation field is roughly divided into that of radiation measurement and that of X-ray generators, and there were about 90 standards as of the end of March, 1983. The equipment related to radiation is large variety, small quantity products, and highly technical compound products. For the inspection and test, special instruments are required. Though some merchandise related to radiation is specified to indicate JIS marks, actually there is not anything that obtained the approval. The JIS related to radiation can be said the recommendation standards, and it is a feature that the standards of software are regarded as important. Two or three drafts of new JIS related mainly to environmental gamma-ray monitoring and X-ray equipment have been drawn up every year. Here, the JIS regarding radiation measurement, which is published after March 1, 1983, is outlined. The method of establishing JIS, JIS published or expected to be published, JIS of hardware and software, the contents of four standards, that is, environmental gamma-ray continuous monitor, method of its calibration, thermo-luminescence dosimeter and survey meter for X-ray and gamma-ray, the international standards and so on are reported. (Kako, I.)

The Fermi Gamma-ray Burst Monitor Instrument

International Nuclear Information System (INIS)

Bhat, P. N.; Briggs, M. S.; Connaughton, V.; Paciesas, W. S.; Preece, R. D.; Meegan, C. A.; Lichti, G. G.; Diehl, R.; Greiner, J.; Kienlin, A. von; Fishman, G. J.; Kouveliotou, C.; Kippen, R. M.

2009-01-01

The Fermi Gamma-ray Space Telescope launched on June 11, 2008 carries two experiments onboard--the Large Area Telescope (LAT) and the Gamma-ray Burst Monitor (GBM). The primary mission of the GBM instrument is to support the LAT in observing γ-ray bursts (GRBs) by providing low-energy measurements with high temporal and spectral resolution as well as rapid burst locations over a large field-of-view (≥8 sr). The GBM will complement the LAT measurements by observing GRBs in the energy range 8 keV to 40 MeV, the region of the spectral turnover in most GRBs. The GBM detector signals are processed by the onboard digital processing unit (DPU). We describe some of the hardware features of the DPU and its expected limitations during intense triggers.

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

Long open-path instrument for simultaneously monitoring of methane, CO2 and water vapor

Science.gov (United States)

Simeonov, Valentin; Parlange, Marc

2013-04-01

A new, long open-path instrument for monitoring of path-averaged methane, CO2 and water vapor concentrations will be presented. The instrument is built on the monostatic scheme (transceiver -distant retroreflector). A VCSEL with a central wavelength of 1654 nm is used as a light source. The receiver is built around a 20 cm Newtonian telescope. The design optical path length is 2000 m but can be further extended. To avoid distortions in the shape of the spectral lines caused by atmospheric turbulences they are scanned within 1 µs. The expected concentration resolution for the above mentioned path length is of the order of 2 ppb for methane, 100 ppb for CO2 and 100 ppm for water vapor. The instrument is developed at the Swiss Federal Institute of Technology - Lausanne (EPFL) Switzerland and will be used within the GAW+ CH program for long-term monitoring of background methane and CO2 concentrations in the Swiss Alps. The initial calibration validation tests at EPFL were completed in December 2012 and the instrument will be installed at the beginning of 2013 at the High Altitude Research Station Jungfraujoch (HARSJ). The HARSJ is located at 3580 m ASL and is one of the 24 global GAW stations. One of the goals of the project is to compare path-averaged to the ongoing point measurements of methane in order to identify possible influence of the station. Future deployments of a copy of the instrument include the Canadian arctic and Siberian wetlands. The instrument can be used for ground truthing of satellite observation as well.

Monitoring and Hardware Management for Critical Fusion Plasma Instrumentation

Directory of Open Access Journals (Sweden)

Carvalho Paulo F.

2018-01-01

Full Text Available Controlled nuclear fusion aims to obtain energy by particles collision confined inside a nuclear reactor (Tokamak. These ionized particles, heavier isotopes of hydrogen, are the main elements inside of plasma that is kept at high temperatures (millions of Celsius degrees. Due to high temperatures and magnetic confinement, plasma is exposed to several sources of instabilities which require a set of procedures by the control and data acquisition systems throughout fusion experiments processes. Control and data acquisition systems often used in nuclear fusion experiments are based on the Advanced Telecommunication Computer Architecture (AdvancedTCA® standard introduced by the Peripheral Component Interconnect Industrial Manufacturers Group (PICMG®, to meet the demands of telecommunications that require large amount of data (TB transportation at high transfer rates (Gb/s, to ensure high availability including features such as reliability, serviceability and redundancy. For efficient plasma control, systems are required to collect large amounts of data, process it, store for later analysis, make critical decisions in real time and provide status reports either from the experience itself or the electronic instrumentation involved. Moreover, systems should also ensure the correct handling of detected anomalies and identified faults, notify the system operator of occurred events, decisions taken to acknowledge and implemented changes. Therefore, for everything to work in compliance with specifications it is required that the instrumentation includes hardware management and monitoring mechanisms for both hardware and software. These mechanisms should check the system status by reading sensors, manage events, update inventory databases with hardware system components in use and maintenance, store collected information, update firmware and installed software modules, configure and handle alarms to detect possible system failures and prevent emergency

Monitoring and Hardware Management for Critical Fusion Plasma Instrumentation

Science.gov (United States)

Carvalho, Paulo F.; Santos, Bruno; Correia, Miguel; Combo, Álvaro M.; Rodrigues, AntÓnio P.; Pereira, Rita C.; Fernandes, Ana; Cruz, Nuno; Sousa, Jorge; Carvalho, Bernardo B.; Batista, AntÓnio J. N.; Correia, Carlos M. B. A.; Gonçalves, Bruno

2018-01-01

Controlled nuclear fusion aims to obtain energy by particles collision confined inside a nuclear reactor (Tokamak). These ionized particles, heavier isotopes of hydrogen, are the main elements inside of plasma that is kept at high temperatures (millions of Celsius degrees). Due to high temperatures and magnetic confinement, plasma is exposed to several sources of instabilities which require a set of procedures by the control and data acquisition systems throughout fusion experiments processes. Control and data acquisition systems often used in nuclear fusion experiments are based on the Advanced Telecommunication Computer Architecture (AdvancedTCA®) standard introduced by the Peripheral Component Interconnect Industrial Manufacturers Group (PICMG®), to meet the demands of telecommunications that require large amount of data (TB) transportation at high transfer rates (Gb/s), to ensure high availability including features such as reliability, serviceability and redundancy. For efficient plasma control, systems are required to collect large amounts of data, process it, store for later analysis, make critical decisions in real time and provide status reports either from the experience itself or the electronic instrumentation involved. Moreover, systems should also ensure the correct handling of detected anomalies and identified faults, notify the system operator of occurred events, decisions taken to acknowledge and implemented changes. Therefore, for everything to work in compliance with specifications it is required that the instrumentation includes hardware management and monitoring mechanisms for both hardware and software. These mechanisms should check the system status by reading sensors, manage events, update inventory databases with hardware system components in use and maintenance, store collected information, update firmware and installed software modules, configure and handle alarms to detect possible system failures and prevent emergency scenarios

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.

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

Traceability of a panoramic gamma irradiator using different TLD systems as transfer Instruments; Trazabilidad de un irradiador panoramico mediante sistemas de dosimetria TL

Energy Technology Data Exchange (ETDEWEB)

Romero, A. M.; Saez, J. C

1994-07-01

This work shows the calibration in terms of the new operational radiological quantities Hp (10) and H(10) for different TLD systems (Harshaw TLD-100 and Panasonic UD-002) used in personal and environmental monitoring. The irradiations were performed in the Spanish Reference Laboratory in radiation protection levels, managed by the CIEMAT Metrology of ionizing radiations Unit. With those data, different calibrations of a panoramic gamma irradiator in terms of the radiological quantity for unit of time were established, providing the traceability of the irradiator to the Reference Laboratory using the corresponding TLD systems as transfer instruments. (Author) 9 refs.

Traceability of a panoramic gamma irradiator using different TLD systems as transfer instruments; Trazabilidad de un irradiador panoramico mediante sistemas de dosimetria TL

Energy Technology Data Exchange (ETDEWEB)

Romero, A.M.; Saez, J.C.

1994-08-01

This work shows the calibration in terms of the new operational radiological quantities Hp(10) and H*(10) for different TLD systems (Harshaw TLD-100 and Panasonic UD-802) used in personal and environmental monitoring. The irradiations were performed in the Spanish Reference Laboratory in radiation protection levels, managed by the CIEMAT Metrology of ionizing radiations Unit. With these data, different calibrations of a panoramic gamma irradiator in terms of the radiological quantity for unit of time were established, providing the traceability of the irradiator to the Reference Laboratory using the corresponding TLD systems as transfer instruments. (Author) 9 refs.

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

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.

Paleontology investigations aided by medical radiology

International Nuclear Information System (INIS)

Lansu, M.J.; Carpenter, K.; Albano, J.; Meals, R.; Brady, L.W.

1987-01-01

Medical radiology instruments provide useful tools for nondestructive investigations in other scientific fields. To date, 15 paleontology specimens have been studied using conventional diagnostic units, therapy simulators, and CT scanners. Most specimens, individual marine animals or large dinosaur heads, needed a combination of studies to complete the investigation. Among the results shown are the inner ear of a Plesiosaurus, which is 76 million years old, and a pearl attached to an extinct clam species, which is 1 million years old. The results confirm the usefulness of radiology as a tool in the field of paleontology

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

Statutory Instrument No 48 of 1992. Radiological Protection Act, 1991 (Establishment day) Order, 1992

International Nuclear Information System (INIS)

1992-03-01

This order appoints 1st April 1992 as the day on which the Radiological Protection Institute of Ireland is established. From that day the Radiological Protection Institute of Ireland will take over the functions of An Bord Fuinnimh Nuicleigh

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)

Operation GUARDIAN onsite radiological safety report, October 1980-September 1981

International Nuclear Information System (INIS)

Mullen, O.W.; Eubank, B.F.

1983-02-01

GUARDIAN was the name assigned to the series of underground nuclear experiments conducted at the Nevada Test Site from October 1, 1980 to September 30, 1981. Remote radiation measurements were taken during and after each nuclear experiment by a telemetry system. Monitors with portable radiation detection intruments surveyed reentry routes into ground zeroes before other planned entries were made. Continuous surveillance was provided while personnel were in radiation areas and appropriate precautions were taken to protect persons from unnecessary exposure to radiation and toxic gases. Protective clothing and equipment were issued as needed. Complete radiological safety and industrial hygiene coverage was provided during drilling and mineback operations. Telemetered and portable radiation detector measurements are listed. Detection instrumentation used is described and specific operational procedures are defined

RIMS/sup tm/ - radiological information management system: software package EI-029-S86

International Nuclear Information System (INIS)

Anon.

1988-01-01

RIMS/sup tm/ has been developed for health physics record keeping and reporting. It provides for the management needs relating to radiological information control at a nuclear facility. The program is comprised of the following modules: Personnel Radiological Information, Radiological Work Permit, Radiation Survey Records, Access Control, ALARA Reporting, and Respirator and Survey Instrument Inventory Modules

RIMS/sup tm/ - radiological information management system: software package EI-029-S86

Energy Technology Data Exchange (ETDEWEB)

1988-01-01

RIMS/sup tm/ has been developed for health physics record keeping and reporting. It provides for the management needs relating to radiological information control at a nuclear facility. The program is comprised of the following modules: Personnel Radiological Information, Radiological Work Permit, Radiation Survey Records, Access Control, ALARA Reporting, and Respirator and Survey Instrument Inventory Modules.

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)

Code of practice and design principles for installed radiological protection systems

International Nuclear Information System (INIS)

Powell, R.G.

1979-03-01

For some years there has been comprehensive guidance documentation for Nuclear Reactor Instrumentation, but apparently no corresponding guide for designers and installers of Radiological Protection Instrumentation. A small group of instrumentation engineers discussed this lack of a suitable guide, and they examined the main points on which it should be based. This document attempts to present a comprehensive and detailed review of these points. It is intended to give an overall coverage and serve as a reference document for specific points; it should also be of value to the newcomer to the Radiological Protection Instrumentation field. This Code of Practice represents a standard of good practice and takes the form of recommendations only. Each installation must be assessed individually, and agreement on its suitability must be reached locally by the designers and the officers responsible for safety and operation. (author)

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

Novel instrumentation for online monitoring of stationary beds and their height for settling slurries

CSIR Research Space (South Africa)

Ilgner, Hartmut J

2016-06-01

Full Text Available stream_source_info Ilgner_2016.pdf.txt stream_content_type text/plain stream_size 1057 Content-Encoding UTF-8 stream_name Ilgner_2016.pdf.txt Content-Type text/plain; charset=UTF-8 10th North American Conference... on Multiphase Technology 2016, Banff, Canada 8 – 10 June 2016 Novel instrumentation for online monitoring of stationary beds and their height for settling slurries H J Ilgner ABSTRACT: Novel instrumentation has been developed to detect stationary...

Project of an integrated calibration laboratory of instruments at IPEN

International Nuclear Information System (INIS)

Barros, Gustavo Adolfo San Jose

2009-01-01

The Calibration Laboratory of Instruments of Instituto de Pesquisas Energeticas e Nucleares offers calibration services of radiation detectors used in radioprotection, diagnostic radiology and radiotherapy, for IPEN and for external facilities (public and private). One part of its facilities is located in the main building, along with other laboratories and study rooms, and another part in an isolated building called Bunker. For the optimization, modernization and specially the safety, the laboratories in the main building shall be transferred to an isolated place. In this work, a project of an integrated laboratory for calibration of instruments was developed, and it will be an expansion of the current Calibration Laboratory of Instruments of IPEN. Therefore, a series of radiometric monitoring of the chosen localization of the future laboratory was realized, and all staff needs (dimensions and disposition of the study rooms and laboratories) were defined. In this project, the laboratories with X ray equipment, alpha and beta radiation sources were located at an isolated part of the building, and the wall shielding was determined, depending on the use of each laboratory. (author)

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

Validation of low-cost ozone measurement instruments suitable for use in an air-quality monitoring network

International Nuclear Information System (INIS)

Williams, David E; Henshaw, Geoff S; Bart, Mark; Laing, Greer; Wagner, John; Naisbitt, Simon; Salmond, Jennifer A

2013-01-01

This paper presents a novel low-cost instrument that uses a sensor based on conductivity changes of heated tungstic oxide, which is capable of accurately measuring ambient concentrations of ozone. A combination of temperature steps and air flow-rate steps is used to continually reset and re-zero the sensor. A two-stage calibration procedure is presented, in which a nonlinear transformation converts sensor resistance to a signal linear in ozone concentration, then a linear correlation is used to align the calibration with a reference instrument. The required calibration functions specific for the sensor, and control system for air flow rate and sensor temperature, are housed with the sensor in a compact, simple-to-exchange assembly. The instrument can be operated on solar power and uses cell phone technology to enable monitoring in remote locations. Data from field trials are presented here to demonstrate that both the accuracy and the stability of the instrument over periods of months are within a few parts-per-billion by volume. We show that common failure modes can be detected through measurement of signals available from the instrument. The combination of long-term stability, self-diagnosis, and simple, inexpensive repair means that the cost of operation and calibration of the instruments is significantly reduced in comparison with traditional reference instrumentation. These instruments enable the economical construction and operation of ozone monitoring networks of accuracy, time resolution and spatial density sufficient to resolve the local gradients that are characteristic of urban air pollution. (paper)

A telemedicine instrument for Internet-based home monitoring of thoracoabdominal motion in patients with respiratory diseases

Science.gov (United States)

da Silva Junior, Evert Pereira; Esteves, Guilherme Pompeu; Dames, Karla Kristine; Melo, Pedro Lopes de

2011-01-01

Changes in thoracoabdominal motion are highly prevalent in patients with chronic respiratory diseases. Home care services that use telemedicine techniques and Internet-based monitoring have the potential to improve the management of these patients. However, there is no detailed description in the literature of a system for Internet-based monitoring of patients with disturbed thoracoabdominal motion. The purpose of this work was to describe the development of a new telemedicine instrument for Internet-based home monitoring of thoracoabdominal movement. The instrument directly measures changes in the thorax and abdomen circumferences and transfers data through a transmission control protocol/Internet protocol connection. After the design details are described, the accuracy of the electronic and software processing units of the instrument is evaluated by using electronic signals simulating normal subjects and individuals with thoracoabdominal motion disorders. The results obtained during in vivo studies on normal subjects simulating thoracoabdominal motion disorders showed that this new system is able to detect a reduction in abdominal movement that is associated with abnormal thoracic breathing (p telemedicine scenarios, which can reduce the costs of assistance offered to patients with respiratory diseases.

Semi-portable whole body counter deployable during post-radiological accident

International Nuclear Information System (INIS)

Panchal, C.G.; Bansode, P.Y.; Vinod, M.; Sarade, Bhagyashree; Jain, R.K.; Jakati, R.K.; Pithawa, C.K.

2012-01-01

A versatile whole body counter with the state of art electronics has been indigenously designed and developed which can be readily deployed for use during nuclear emergency. This instrument is designed to quickly identify and quantify the activity of high energy photon emitters accumulated particularly in vital organs like thyroid, lungs besides the body of the victims of the radiological incident or accident. Special features of the instruments are swivel type detectors assembly mountable on a wall or table top and detachable collimator configurable to assess the internal contamination selectively to meet protective measures of the radiological accidents, mechanically rugged and functionally reliable to perform in contaminated environmental field conditions. (author)

Automatic modal identification of cable-supported bridges instrumented with a long-term monitoring system

Science.gov (United States)

Ni, Y. Q.; Fan, K. Q.; Zheng, G.; Chan, T. H. T.; Ko, J. M.

2003-08-01

An automatic modal identification program is developed for continuous extraction of modal parameters of three cable-supported bridges in Hong Kong which are instrumented with a long-term monitoring system. The program employs the Complex Modal Indication Function (CMIF) algorithm to identify modal properties from continuous ambient vibration measurements in an on-line manner. By using the LabVIEW graphical programming language, the software realizes the algorithm in Virtual Instrument (VI) style. The applicability and implementation issues of the developed software are demonstrated by using one-year measurement data acquired from 67 channels of accelerometers deployed on the cable-stayed Ting Kau Bridge. With the continuously identified results, normal variability of modal vectors caused by varying environmental and operational conditions is observed. Such observation is very helpful for selection of appropriate measured modal vectors for structural health monitoring applications.

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

Sulfur dioxide emissions from Peruvian copper smelters detected by the ozone monitoring instrument

NARCIS (Netherlands)

Carn, S.A.; Krueger, A.J.; Krotkov, N.A.; Yang, Kai; Levelt, P.F.

2007-01-01

We report the first daily observations of sulfur dioxide (SO2) emissions from copper smelters by a satellite-borne sensor - the Ozone Monitoring Instrument (OMI) on NASA's EOS/Aura spacecraft. Emissions from two Peruvian smelters (La Oroya and Ilo) were detected in up to 80% of OMI overpasses

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

Instrument evaluation no. 17. Wallac automatic alarm dosimeter type RAD21

CERN Document Server

Burgess, P H

1980-01-01

The various radiations encountered in radiological protection cover a wide range of energies and radiation measurements have to be carried out under an equally broad spectrum of environmental conditions. This report is one of a series intended to give information on the performance characteristics of radiological protection instruments, to assist in the selection of appropriate instruments for a given purpose, to interpret the results obtained with such instruments, and, in particular, to know the likely sources and magnitude of errors that might be associated with measurements in the field. The radiation, electrical and environmental characteristics of radiation protection instruments are considered together with those aspects of the construction which make an instrument convenient for routine use. To provide consistent criteria for instrument performance, the range of tests performed on any particular class of instrument, the test methods and the criteria of acceptable performance are based broadly on the a...

Statutory Instrument no. 1230, The National Radiological Protection Board (Extension of Functions) Order 1974

International Nuclear Information System (INIS)

1974-01-01

This Order, which came into operation of 1st August 1974, extends the functions and powers of the National Radiological Protection Board, which was established by the Radiological Protection Act 1970 so as to cover research and the giving of advice on the dangers of radiation which is electromagnetic but not ionizing. (NEA) [fr

An efficient network for interconnecting remote monitoring instruments and computers

International Nuclear Information System (INIS)

Halbig, J.K.; Gainer, K.E.; Klosterbuer, S.F.

1994-01-01

Remote monitoring instrumentation must be connected with computers and other instruments. The cost and intrusiveness of installing cables in new and existing plants presents problems for the facility and the International Atomic Energy Agency (IAEA). The authors have tested a network that could accomplish this interconnection using mass-produced commercial components developed for use in industrial applications. Unlike components in the hardware of most networks, the components--manufactured and distributed in North America, Europe, and Asia--lend themselves to small and low-powered applications. The heart of the network is a chip with three microprocessors and proprietary network software contained in Read Only Memory. In addition to all nonuser levels of protocol, the software also contains message authentication capabilities. This chip can be interfaced to a variety of transmission media, for example, RS-485 lines, fiber topic cables, rf waves, and standard ac power lines. The use of power lines as the transmission medium in a facility could significantly reduce cabling costs

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

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)

Radiation monitoring and measuring instrument developed by Turkish Atomic Energy Authority

International Nuclear Information System (INIS)

Kuecuekarslan, N.; Gueven, A.

2001-01-01

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

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.

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 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)

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)

Dose rate mapping and quantitative analysis of radioactive deposition with simple monitoring instruments in Finland after the Chernobyl accident.

Energy Technology Data Exchange (ETDEWEB)

Koivukoski, J. [Ministry of the Interior, Rescue Dept., Helsinki (Finland); Paatero, J. [Finnish Meteorological Inst., Helsinki (Finland)], E-mail: janne.koivukoski@intermin.fi

2013-03-01

This article reviews the Finnish dose-rate mapping equipment and the system to process the obtained results, which were used immediately after the 1986 Chernobyl accident. We present the results of the external gamma-radiation monitoring carried out with simple civil-defence gamma monitoring instruments and compare them with the subsequent deposition mapping performed with research-grade instruments. The analysis shows that the quality of radiation mapping is good enough for decision makers to direct protective measures to the right areas. This review also demonstrates that a simple stationary external gamma radiation monitoring network can be effectively used for early warning in radiation emergency situations. (orig.)

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)

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)

Automated Instrumentation, Monitoring and Visualization of PVM Programs Using AIMS

Science.gov (United States)

Mehra, Pankaj; VanVoorst, Brian; Yan, Jerry; Lum, Henry, Jr. (Technical Monitor)

1994-01-01

We present views and analysis of the execution of several PVM (Parallel Virtual Machine) codes for Computational Fluid Dynamics on a networks of Sparcstations, including: (1) NAS Parallel Benchmarks CG and MG; (2) a multi-partitioning algorithm for NAS Parallel Benchmark SP; and (3) an overset grid flowsolver. These views and analysis were obtained using our Automated Instrumentation and Monitoring System (AIMS) version 3.0, a toolkit for debugging the performance of PVM programs. We will describe the architecture, operation and application of AIMS. The AIMS toolkit contains: (1) Xinstrument, which can automatically instrument various computational and communication constructs in message-passing parallel programs; (2) Monitor, a library of runtime trace-collection routines; (3) VK (Visual Kernel), an execution-animation tool with source-code clickback; and (4) Tally, a tool for statistical analysis of execution profiles. Currently, Xinstrument can handle C and Fortran 77 programs using PVM 3.2.x; Monitor has been implemented and tested on Sun 4 systems running SunOS 4.1.2; and VK uses XIIR5 and Motif 1.2. Data and views obtained using AIMS clearly illustrate several characteristic features of executing parallel programs on networked workstations: (1) the impact of long message latencies; (2) the impact of multiprogramming overheads and associated load imbalance; (3) cache and virtual-memory effects; and (4) significant skews between workstation clocks. Interestingly, AIMS can compensate for constant skew (zero drift) by calibrating the skew between a parent and its spawned children. In addition, AIMS' skew-compensation algorithm can adjust timestamps in a way that eliminates physically impossible communications (e.g., messages going backwards in time). Our current efforts are directed toward creating new views to explain the observed performance of PVM programs. Some of the features planned for the near future include: (1) ConfigView, showing the physical topology

Instrumentation development for real time brainwave monitoring.

Energy Technology Data Exchange (ETDEWEB)

Anderson, Lawrence Frederick; Clough, Benjamin W.

2005-12-01

The human brain functions through a chemically-induced biological process which operates in a manner similar to electrical systems. The signal resulting from this biochemical process can actually be monitored and read using tools and having patterns similar to those found in electrical and electronics engineering. The primary signature of this electrical activity is the ''brain wave'', which looks remarkably similar to the output of many electrical systems. Likewise, the device currently used in medical arenas to read brain electrical activity is the electroencephalogram (EEG) which is synonymous with a multi-channel oscilloscope reading. Brain wave readings and recordings for medical purposes are traditionally taken in clinical settings such as hospitals, laboratories or diagnostic clinics. The signal is captured via externally applied scalp electrodes using semi-viscous gel to reduce impedance. The signal will be in the 10 to 100 microvolt range. In other instances, where surgeons are attempting to isolate particular types of minute brain signals, the electrodes may actually be temporarily implanted in the brain during a preliminary procedure. The current configurations of equipment required for EEGs involve large recording instruments, many electrodes, wires, and large amounts of hard disk space devoted to storing large files of brain wave data which are then eventually analyzed for patterns of concern. Advances in sensors, signal processing, data storage and microelectronics over the last decade would seem to have paved the way for the realization of devices capable of ''real time'' external monitoring, and possible assessment, of brain activity. A myriad of applications for such a capability are likewise presenting themselves, including the ability to assess brain functioning, level of functioning and malfunctioning. Our plan is to develop the sensors, signal processing, and portable instrumentation package which could

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)

Special Nuclear Material Portal Monitoring at the Nevada Test Site

International Nuclear Information System (INIS)

DeAnn Long; Michael Murphy

2008-01-01

Prior to April 2007, acceptance and performance testing of the various Special Nuclear Material (SNM) monitoring devices at the Nevada Test Site (NTS) was performed by the Radiological Health Instrumentation department. Calibration and performance testing on the PM-700 personnel portal monitor was performed, but there was no test program for the VM-250 vehicle portal monitor. The handheld SNM monitors, the TSA model 470B, were being calibrated annually, but there was no performance test program. In April of 2007, the Material Control and Accountability Manager volunteered to take over performance testing of all SNM portal monitors at NTS in order to strengthen the program and meet U.S. Department of Energy Order requirements. This paper will discuss the following activities associated with developing a performance testing program: changing the culture, learning the systems, developing and implementing procedures, troubleshooting and repair, validating the process, physical control of equipment, acquisition of new systems, and implementing the performance test program

Special Nuclear Material Portal Monitoring at the Nevada Test Site

International Nuclear Information System (INIS)

Mike Murphy

2008-01-01

In the past, acceptance and performance testing of the various Special Nuclear Material (SNM) monitoring devices at the Nevada Test Site has been performed by the Radiological Health Instrumentation Department. Calibration and performance tests on the PM-700 personnel portal monitor were performed but there was no test program for the VM-250 vehicle portal monitor because it had never been put into service. The handheld SNM monitors, the TSA model 470B, were being calibrated annually, but there was no program in place to test them quarterly. In April of 2007, the Material Control and Accountability (MC and A) Manager at the time decided that the program needed to be strengthened and MC and A took over performance testing of all SNM portal monitoring equipment. This paper will discuss the following activities associated with creating a performance testing program: changing the culture, learning the systems, writing procedures, troubleshooting/repairing, validating the process, control of equipment, acquisition of new systems, and running the program

REMOTE AREA RADIATION MONITORING (RARM) ALTERNATIVES ANALYSIS

International Nuclear Information System (INIS)

NELSON RL

2008-01-01

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

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

Development of a generic system for real-time data access and remote control of multiple in-situ water quality monitoring instruments

Science.gov (United States)

Wright, S. A.; Bennett, G. E.; Andrews, T.; Melis, T. S.; Topping, D. J.

2005-05-01

Currently, in-situ monitoring of water quality parameters (e.g. water temperature, conductivity, turbidity) in the Colorado River ecosystem typically consists of deploying instruments in the river, retrieving them at a later date, downloading the datalogger, then examining the data; an arduous process in the remote settings of Grand Canyon. Under this protocol, data is not available real-time and there is no way to detect problems with the instrumentation until after retrieval. The next obvious stage in the development of in-situ monitoring in Grand Canyon was the advent of one-way telemetry, i.e. streaming data in real-time from the instrument to the office and/or the world-wide-web. This protocol allows for real-time access to data and the identification of instrumentation problems, but still requires a site visit to address instrument malfunctions, i.e. the user does not have the ability to remotely control the instrument. At some field sites, such as the Colorado River in Grand Canyon, site visitation is restricted by remoteness and lack of traditional access routes (i.e. roads). Even at less remote sites, it may still be desirable to have two-way communication with instruments in order to, for example, diagnose and potentially fix instrumentation problems, change sampling parameters to save battery power, etc., without having to visit the site. To this end, the U.S. Geological Survey, Grand Canyon Monitoring and Research Center, is currently developing and testing a high-speed, two-way communication system that allows for real-time data access and remote control of instrumentation. The approach tested relies on internet access and may be especially useful in areas where land-line or cellular connections are unavailable. The system is composed of off-the-shelf products, uses a commercial broadband satellite service, and is designed in a generic way such that any instrument that communicates through RS-232 communication (i.e. a serial port) is compatible with

Research and development in radiological protection

International Nuclear Information System (INIS)

Butragueno, J. L.; Villota, C.; Gutierrez, C.; Rodriguez, A.

2004-01-01

The objective of Radiological Protection is to guarantee that neither people, be they workers or members of the public, or the environment are exposed to radiological risks considered by society to be unacceptable. Among the various resources available to meet this objective is Research and Development (R and D), which is carried out in three areas: I. Radiological protection of persons: (a) knowledge of the biological effects of radiations, in order to determine the relationship that exists between radiation exposure dose and its effects on health; (b) the development of new personal dosimetry techniques in order to adapt to new situations, instrumental techniques and information management technologies allowing for better assessment of exposure dose; and (c) development of the principle of radiological protection optimisation (ALARA), which has been set up internationally as the fundamental principle on which radiological protection interventions are based. II. Assessment of environmental radiological impact, the objective of which is to assess the nature and magnitude of situations of exposure to ionising radiations as a result of the controlled or uncontrolled release of radioactive material to the environment, and III.Reduction of the radiological impact of radioactive wastes, the objective of which is to develop radioactive material and waste management techniques suitable for each situation, in order to reduce the risks associated with their definitive management or their release to the environment. Briefly described below are the strategic lines of R and D of the CSN, the Electricity Industry, Ciemat and Enresa in the aforementioned areas. (Author)

Technological considerations in emergency instrument preparedness

International Nuclear Information System (INIS)

Selby, J.M.

1975-01-01

The types of emergency instrumentation systems necessary to characterize the severity and extent of radiation accidents and to aid in the protection of operating personnel and personnel living near the plant are discussed. These include instruments for direct measurement of the airborne radioactive material within the facility, fixed instrumentation for ambient dose rate monitoring or area monitoring, and portable instruments for environmental monitoring

Audit of radiology communication systems for critical, urgent, and unexpected significant findings

International Nuclear Information System (INIS)

Duncan, K.A.; Drinkwater, K.J.; Dugar, N.; Howlett, D.C.

2016-01-01

Aim: To determine the compliance of UK radiology departments and trusts/healthcare organisations with National Patient Safety Agency and Royal College of Radiologist's published guidance on the communication of critical, urgent, and unexpected significant radiological findings. Materials and methods: A questionnaire was sent to all UK radiology department audit leads asking for details of their current departmental policy regarding the issuing of alerts; use of automated electronic alert systems; methods of notification of clinicians of critical, urgent, and unexpected significant radiological findings; monitoring of results receipt; and examples of the more common types of serious pathologies for which alerts were issued. Results: One hundred and fifty-four of 229 departments (67%) responded. Eighty-eight percent indicated that they had a policy in place for the communication of critical, urgent, and unexpected significant radiological findings. Only 34% had an automated electronic alert system in place and only 17% had a facility for service-wide electronic tracking of radiology reports. In only 11 departments with an electronic acknowledgement system was someone regularly monitoring the read rate. Conclusion: There is wide variation in practice across the UK with regard to the communication and monitoring of reports with many departments/trusts not fully compliant with published UK guidance. Despite the widespread use of electronic systems, only a minority of departments/trusts have and use electronic tracking to ensure reports have been read and acted upon. - Highlights: • UK wide audit of communication of significant radiology results. • 88% of departments have a communication policy in place. • 34% of departments have an automated electronic alert system. • 17% of Trusts have facility for service wide electronic tracking of radiology reports.

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

ICRP Publication 139: Occupational Radiological Protection in Interventional Procedures.

Science.gov (United States)

López, P Ortiz; Dauer, L T; Loose, R; Martin, C J; Miller, D L; Vañó, E; Doruff, M; Padovani, R; Massera, G; Yoder, C

2018-03-01

In recent publications, such as Publications 117 and 120, the Commission provided practical advice for physicians and other healthcare personnel on measures to protect their patients and themselves during interventional procedures. These measures can only be effective if they are encompassed by a framework of radiological protection elements, and by the availability of professionals with responsibilities in radiological protection. This framework includes a radiological protection programme with a strategy for exposure monitoring, protective garments, education and training, and quality assurance of the programme implementation. Professionals with responsibilities in occupational radiological protection for interventional procedures include: medical physicists; radiological protection specialists; personnel working in dosimetry services; clinical applications support personnel from the suppliers and maintenance companies; staff engaged in training, standardisation of equipment, and procedures; staff responsible for occupational health; hospital administrators responsible for providing financial support; and professional bodies and regulators. This publication addresses these elements and these audiences, and provides advice on specific issues, such as assessment of effective dose from dosimeter readings when an apron is worn, estimation of exposure of the lens of the eye (with and without protective eyewear), extremity monitoring, selection and testing of protective garments, and auditing the interventional procedures when occupational doses are unusually high or low (the latter meaning that the dosimeter may not have been worn).

Applicability of 1994-1995 USRADS reg-sign surveys of Bear Creek Valley flood plain and Operable Unit 1 to the radiological characterization of Y-12 grassy/wooded areas

International Nuclear Information System (INIS)

Bogard, J.S.; Hamm, R.N.; Brown, K.S.

1997-03-01

This document, provided in support of the Y-12 Site Radiological Characterization Study, analyzes the utility of data from two reports by Chemrad Tennessee Corporation in identifying radiological contamination in excess of contamination control guidelines at the surface of soils in the Bear Creek Valley Flood Plain (BCVFP) and in Y-12 Operable Unit 1 (OU1). The Chemrad reports were developed under subcontract to Science Applications International Corporation for their remedial investigation of these sites for Martin Marietta Energy Systems Environmental Restoration Division. Surveys were performed by Chemrad using the UltraSonic Ranging and Data System (USRADS reg-sign), which utilizes ultrasonic triangulation to determine the location of a survey technician at the same time that radiological monitoring data are telemetered from his instruments to a remote receiving station. Floor monitor and Geiger-Mueller pancake meter results from the USRADS reg-sign surveys are shown to be sufficiently precise to reliably detect contamination in excess of the limiting radioactivity value of 1,000 dpm/100 cm 2 for removable uranium contamination specified in 10 CFR 835 Appendix D. MicroRem meter survey results, also included as part of the USRADS reg-sign surveys, indicate that the derived limiting value of 56.8 μrem/h for penetrating dose at 1 m (corresponding to 100 mrem/γ) was not exceeded. However, both the pancake meter and floor monitor results suggest that surface contamination exceeding 1,000 dpm/100 cm 2 is not uncommon. Sites in OU1 and BCVFP were visited, and independent surveys made with hand-held instruments, to confirm conclusions about the USRADS close-quote survey results and to verify that these results are from contamination uniformly distributed on the soil surface, and not from discrete sources which are not likely transferred to shoes, vehicles, or clothing

Instrumentation of Lysimeter Experiments and Monitoring of Soil Parameters

International Nuclear Information System (INIS)

Schmid, T.; Tallos, A.; Millan, R.; Vera, R.; Recreo, F.

2004-01-01

This study forms part of the project Mercurio and Recuperation de Terrenos Afectados por Mercurio Ambiental (RETAMA) , which determines the behaviour of mercury in the soil-plant system within the area of Almaden. The objective of this work is to instrument lysimeters with a set of electronic sensors to monitor physical and chemical soil parameters (moisture content, soil temperature, soil water matrix potential, Eh and pH) over a period of a complete vegetation cycle for selected crops. Physical and chemical soil analyses have been carried out on samples two soil profiles marking the extreme perimeter where the lysimeters were extracted. The monitoring data obtained every half hour show that the physicochemical conditions of the soils in the lysimeter can be correlated with the type of cultivation in the lysimeters. The results for parameters such as soil water matrix potential and the soil temperature reflect the diurnal changes; and fluctuations of the Eh can be related to the biological activities in the soils and are within oxid and sub oxid conditions. Slight fluctuations have been observed for the pH and constant volumetric moisture content is maintained during the period of no hydric stress. (Author) 16 refs

Instrumentation of Lysimeter Experiments and Monitoring of Soil Parameters

Energy Technology Data Exchange (ETDEWEB)

Schmid, T.; Tallos, A.; Millan, R.; Vera, R.; Recreo, F.

2004-07-01

This study forms part of the project Mercurio and Recuperation de Terrenos Afectados por Mercurio Ambiental (RETAMA), which determines the behaviour of mercury in the soil-plant system within the area of Almaden. The objective of this work is to instrument lysimeters with a set of electronic sensors to monitor physical and chemical soil parameters (moisture content, soil temperature, soil water matrix potential. Eh and pH) over a period of a complete vegetation cycle for selected crops. Physical and chemical soil analyses have been carried out on samples two soil profiles marking the extreme perimeter where the lysimeters were extracted. The monitoring data obtained every half hour show that the physicochemical conditions of the soils in the lysimeter can be correlated with the type of cultivation in the lysimeters. The results for parameters such as soil water matrix potential and the soil temperature reflect the diurnal changes; and fluctuations of the Eh can be related to the biological activities in the soils and are within oxid and suboxic conditions. Slight fluctuations have been observed for the pH and constant volumetric moisture content is maintained during the period of no hydric stress. (Author) 16 refs.

Guidelines for planning and design of mobile radiological units

Energy Technology Data Exchange (ETDEWEB)

Schelenz, R [Federal Office for Environmental Radioactivity in Food, Total Diet and Infant Food, Federal Research Centre for Nutrition, Karlsruhe (Germany)

1995-07-01

A significant number of mobile radiological units are in operation worldwide aiming to provide reliable radiological data. They mainly have been designed and constructed on a national basis according to the particular needs and commitments of the specific laboratory or country. In most cases, these units are intended to be used in emergency situations for in-situ radiological measurements of accidentally released radioactivity, sometimes for monitoring environmental pollution. As the purpose of these units is very diversified in regard to the kind of vehicle and its in-built measuring equipment the varying outfit of these units cannot be adopted in general for other countries aiming to improve their capability for in-situ radiological measurement. In order to achieve harmonization of equipment and comparability of radiological data being obtained from field measurements it is necessary to have general guidelines available for designing mobile radiological units taking into account different sceneries and tasks to be achieved. In the very early stages of an accident most of the information available on the quantity of radioactive material being released, its radionuclide composition and the likely progression of the accident will come from the operator, and will be based on the conditions in the plant. Few environmental monitoring results from off-side can be expected within the first few hours. In this very early phase, decisions on the application of protective measures will therefore, be based largely on plant status and forecasts of changes in that status as well as on meteorological data. As time progresses, results will increasingly become available from the monitoring of radionuclides in the environment (e.g. dose rates and concentration of radionuclides in air and particular materials such as water, food etc). Monitoring results can be used to estimate potential doses to people and the need for further protective measures can thus be determined from a

Guidelines for planning and design of mobile radiological units

International Nuclear Information System (INIS)

Schelenz, R.

1995-01-01

A significant number of mobile radiological units are in operation worldwide aiming to provide reliable radiological data. They mainly have been designed and constructed on a national basis according to the particular needs and commitments of the specific laboratory or country. In most cases, these units are intended to be used in emergency situations for in-situ radiological measurements of accidentally released radioactivity, sometimes for monitoring environmental pollution. As the purpose of these units is very diversified in regard to the kind of vehicle and its in-built measuring equipment the varying outfit of these units cannot be adopted in general for other countries aiming to improve their capability for in-situ radiological measurement. In order to achieve harmonization of equipment and comparability of radiological data being obtained from field measurements it is necessary to have general guidelines available for designing mobile radiological units taking into account different sceneries and tasks to be achieved. In the very early stages of an accident most of the information available on the quantity of radioactive material being released, its radionuclide composition and the likely progression of the accident will come from the operator, and will be based on the conditions in the plant. Few environmental monitoring results from off-side can be expected within the first few hours. In this very early phase, decisions on the application of protective measures will therefore, be based largely on plant status and forecasts of changes in that status as well as on meteorological data. As time progresses, results will increasingly become available from the monitoring of radionuclides in the environment (e.g. dose rates and concentration of radionuclides in air and particular materials such as water, food etc). Monitoring results can be used to estimate potential doses to people and the need for further protective measures can thus be determined from a

Recommended radiological controls for tritium operations

International Nuclear Information System (INIS)

Mansfield, G.

1992-01-01

This informal report presents recommendations for an adequate radiological protection program for tritium operations. Topics include hazards analysis, facility design, personnel protection equipment, training, operational procedures, radiation monitoring, to include surface and airborne tritium contamination, and program management

Measurement of dose equivalent with personal dosemeters and instrumentation of radiological protection in the new operative magnitudes ICRU, for external fields of radiation beta. Part IV. Survey of the angular response of instruments used in radiological protection in secondary patron fields of beta radiation (90Sr/90Y (1850 MBq and 74 MBq), 204TI (18.5 MBq) and 147Pm (518 MBq)

International Nuclear Information System (INIS)

Alvarez R, J.T.

1994-02-01

Tests type were made (type test) in the following commercial instrumentation commonly used in radiological protection: Geiger-Mueller Counters (FH40 FE), Plastic Scintillators (NE-BP/6/4A), Ionization Chambers (RO-5) and Proportional Counters (HP-100A; gas:P-10). With object of checking the possibility that these they can carry out the new operative unit ICRU, H' (0.07; α). The tests consisted on determining the energy and angular response of the detectors in secondary patron fields of beta radiation, for isotopes of 90 Sr/ 90 Y (1850 MBq and 74 MBq and 147 Pm(518 MBq). The results show the inadequate of these commercial instruments for the realization of the H' operative unit (0.07; α) in beta external fields. Due to flaws in the design, construction and calibration of the instruments for this type of radiation fields (Author)

RI Mapping System for Identification of Radiological Contamination in Environmental Water Supply System

Energy Technology Data Exchange (ETDEWEB)

Na, Teresa W.; Ha, Jang Ho; Kim, Han Soo; Lee, Seung Hyun [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Na, Teresa W.; Lee, Rena [Ewha Womans Univ., Hospital, Seoul (Korea, Republic of)

2012-03-15

The interest of radiation protection has risen due to accidents of the Nuclear Power Plant, nuclear terrorism, and the radiological contamination in the city, In this respect, the development of environmental radiation monitoring for the radiological contaminants has been studied. In this study, the experiment for the radiological contamination in the water supply pipe line system has been simulated and preliminarily tested. The CsI(Tl)-PIN diode detectors were used and the preliminary test of radiation monitoring system was performed as multi detection system. The 2D image reconstruction algorithm was also developed for feasibility of the constructed multi-detection system.

Design of a monitoring network over France in case of a radiological accidental release

Science.gov (United States)

Abida, Rachid; Bocquet, Marc; Vercauteren, Nikki; Isnard, Olivier

The Institute of Radiation Protection and Nuclear Safety (France) is planning the set-up of an automatic nuclear aerosol monitoring network over the French territory. Each of the stations will be able to automatically sample the air aerosol content and provide activity concentration measurements on several radionuclides. This should help monitor the French and neighbouring countries nuclear power plants set. It would help evaluate the impact of a radiological incident occurring at one of these nuclear facilities. This paper is devoted to the spatial design of such a network. Here, any potential network is judged on its ability to extrapolate activity concentrations measured on the network stations over the whole domain. The performance of a network is quantitatively assessed through a cost function that measures the discrepancy between the extrapolation and the true concentration fields. These true fields are obtained through the computation of a database of dispersion accidents over one year of meteorology and originating from 20 French nuclear sites. A close to optimal network is then looked for using a simulated annealing optimisation. The results emphasise the importance of the cost function in the design of a network aimed at monitoring an accidental dispersion. Several choices of norm used in the cost function are studied and give way to different designs. The influence of the number of stations is discussed. A comparison with a purely geometric approach which does not involve simulations with a chemistry-transport model is performed.

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)

Educational treasures in Radiology: The Radiology Olympics - striving for gold in Radiology education

OpenAIRE

Talanow, Roland

2010-01-01

This article focuses on Radiology Olympics (www.RadiologyOlympics.com) - a collaboration with the international Radiology community for Radiology education, Radiolopolis (www.Radiolopolis.com). The Radiology Olympics honour the movers and shakers in Radiology education and offer an easy to use platform for educating medical professionals based on Radiology cases.

Radiology

International Nuclear Information System (INIS)

Bigot, J.M.; Moreau, J.F.; Nahum, H.; Bellet, M.

1990-01-01

The 17th International Congress of Radiology was conducted in two separate scientific sessions, one for radiodiagnosis and one for radiation oncology. Topics covered are: Radiobiology -radioprotection; imaging and data processing; contrast media; MRI; nuclear medicine; radiology and disasters; radiology of tropical diseases; cardiovascular radiology; interventional radiology; imaging of trauma; imaging of chest, gastro-intestinal tract, breast and genito-urinary tract; imaging in gynecology;imaging in oncology; bone and joint radiology; head and neck-radiology; neuro-radiology. (H.W.). refs.; fig.; tabs

Audit of radiology communication systems for critical, urgent, and unexpected significant findings.

Science.gov (United States)

Duncan, K A; Drinkwater, K J; Dugar, N; Howlett, D C

2016-03-01

To determine the compliance of UK radiology departments and trusts/healthcare organisations with National Patient Safety Agency and Royal College of Radiologist's published guidance on the communication of critical, urgent, and unexpected significant radiological findings. A questionnaire was sent to all UK radiology department audit leads asking for details of their current departmental policy regarding the issuing of alerts; use of automated electronic alert systems; methods of notification of clinicians of critical, urgent, and unexpected significant radiological findings; monitoring of results receipt; and examples of the more common types of serious pathologies for which alerts were issued. One hundred and fifty-four of 229 departments (67%) responded. Eighty-eight percent indicated that they had a policy in place for the communication of critical, urgent, and unexpected significant radiological findings. Only 34% had an automated electronic alert system in place and only 17% had a facility for service-wide electronic tracking of radiology reports. In only 11 departments with an electronic acknowledgement system was someone regularly monitoring the read rate. There is wide variation in practice across the UK with regard to the communication and monitoring of reports with many departments/trusts not fully compliant with published UK guidance. Despite the widespread use of electronic systems, only a minority of departments/trusts have and use electronic tracking to ensure reports have been read and acted upon. Copyright © 2015 The Royal College of Radiologists. Published by Elsevier Ltd. All rights reserved.

Key Performance Indicators in Radiology: You Can't Manage What You Can't Measure.

Science.gov (United States)

Harvey, H Benjamin; Hassanzadeh, Elmira; Aran, Shima; Rosenthal, Daniel I; Thrall, James H; Abujudeh, Hani H

2016-01-01

Quality assurance (QA) is a fundamental component of every successful radiology operation. A radiology QA program must be able to efficiently and effectively monitor and respond to quality problems. However, as radiology QA has expanded into the depths of radiology operations, the task of defining and measuring quality has become more difficult. Key performance indicators (KPIs) are highly valuable data points and measurement tools that can be used to monitor and evaluate the quality of services provided by a radiology operation. As such, KPIs empower a radiology QA program to bridge normative understandings of health care quality with on-the-ground quality management. This review introduces the importance of KPIs in health care QA, a framework for structuring KPIs, a method to identify and tailor KPIs, and strategies to analyze and communicate KPI data that would drive process improvement. Adopting a KPI-driven QA program is both good for patient care and allows a radiology operation to demonstrate measurable value to other health care stakeholders. Copyright © 2015 Mosby, Inc. All rights reserved.

The Ozone Monitoring Instrument: overview of 14 years in space

Science.gov (United States)

Levelt, Pieternel F.; Joiner, Joanna; Tamminen, Johanna; Pepijn Veefkind, J.; Bhartia, Pawan K.; Stein Zweers, Deborah C.; Duncan, Bryan N.; Streets, David G.; Eskes, Henk; van der A, Ronald; McLinden, Chris; Fioletov, Vitali; Carn, Simon; de Laat, Jos; DeLand, Matthew; Marchenko, Sergey; McPeters, Richard; Ziemke, Jerald; Fu, Dejian; Liu, Xiong; Pickering, Kenneth; Apituley, Arnoud; González Abad, Gonzalo; Arola, Antti; Boersma, Folkert; Miller, Christopher Chan; Chance, Kelly; de Graaf, Martin; Hakkarainen, Janne; Hassinen, Seppo; Ialongo, Iolanda; Kleipool, Quintus; Krotkov, Nickolay; Li, Can; Lamsal, Lok; Newman, Paul; Nowlan, Caroline; Suleiman, Raid; Gijsbert Tilstra, Lieuwe; Torres, Omar; Wang, Huiqun; Wargan, Krzysztof

2018-04-01

This overview paper highlights the successes of the Ozone Monitoring Instrument (OMI) on board the Aura satellite spanning a period of nearly 14 years. Data from OMI has been used in a wide range of applications and research resulting in many new findings. Due to its unprecedented spatial resolution, in combination with daily global coverage, OMI plays a unique role in measuring trace gases important for the ozone layer, air quality, and climate change. With the operational very fast delivery (VFD; direct readout) and near real-time (NRT) availability of the data, OMI also plays an important role in the development of operational services in the atmospheric chemistry domain.

Some emergency instrumentation

Energy Technology Data Exchange (ETDEWEB)

Burgess, P H

1986-10-01

The widespread release of activity and the resultant spread of contamination after the Chernobyl accident resulted in requests to NRPB to provide instruments for, and expertise in, the measurement of radiation. The most common request was for advice on the usefulness of existing instruments, but Board staff were also involved in their adaptation or in the development of new instruments specially to meet the circumstances of the accident. The accident occurred on 26 April. On 1 May, NRPB was involved at Heathrow Airport in the monitoring of the British students who had returned from Kiev and Minsk. The main purpose was to reassure the students by checking that their persons and belongings did not have significant surface contamination. Additional measurements were also made of iodine activity in thyroid using hand-held detectors or a mobile body monitor. This operation was arranged with the Foreign and Commonwealth Office, which had also received numerous requests for instruments from embassies and consulates in countries close to the scene of the accident. There was concern for the well-being of staff and other United Kingdom nationals who resided in or intended to visit the most affected countries. The board supplied suitable instruments, and the FCO distributed them to embassies. The frequency of environmental monitoring was increased from 29 April in anticipation of contamination and appropriate Board instrumentation was deployed. After the Chernobyl cloud arrived in the UK on 2 May, there were numerous requests from local government, public authorities, private companies and members of the public for information and advice on monitoring equipment and procedures. Some of these requirements could be met with existing equipment but members of the public were usually advised not to proceed. At a later stage, the contamination of foodstuffs and livestock required the development of an instrument capable of detecting low levels of {sup 137}Cs and {sup 134}Cs in food

Virtual instrument for controlling and monitoring digitalized power supply in SSRF

International Nuclear Information System (INIS)

Tang Junlong; Chen Huanguang; Chinese Academy of Sciences, Beijing; Xu Ruinian; Shen Tianjian; Li Deming

2006-01-01

The Shanghai Synchrotron Radiation Facility (SSRF) needs extremely precise power supplies for their various magnets. A digital controller is being developed for the power converters of the SSRF power supply (PS). In the digital controller, a fully digital pulse-width modulator (PWM) directly controls the power unit insulated gate bipolar transistor (IGBT) of the PS. A program in LabVIEW language has been developed to control and monitor the digital PS via serial communication (RS232) from a PC and to modify its parameters as well. In this article, the software design of the virtual instrument for controlling and monitoring digitalized PS and its associated functions are described, and the essential elements of the program graphical main-VI and sub-VI source code are presented and explained. The communication protocol and the structure of the developed system are also included in this article. (authors)

Hanford Radiological Protection Support Services Annual Report for 1998

Energy Technology Data Exchange (ETDEWEB)

DE Bihl; JA MacLellan; ML Johnson; RK Piper; TP Lynch

1999-05-14

During calendar year (CY) 1998, the Pacific Northwest National Laboratory (PNNL) performed its customary radiological protection support services in support of the U.S. Department of Energy (DOE) Richland Operations OffIce (RL) and the Hanford contractors. These services included: 1) external dosimetry, 2) internal dosimetry, 3) in vivo measurements, 4) radiological records, 5) instrument calibra- tion and evaluation, and 6) calibration of radiation sources traceable to the National Institute of Standards and Technology (MST). The services were provided under a number of projects as summarized here.

Instruments for calibration and monitoring of the LHCb Muon Detector

CERN Document Server

Deplano, C; Lai, A

2006-01-01

The subject of this Ph. D. thesis is the study and the development of the instruments needed to monitor and calibrate the Muon Detector of the LHCb (Large Hadron Collider beauty) experiment. LHCb is currently under installation at the CERN Large Hadron Collider (LHC) and will start to take data during 2007. The experiment will study B mesons decays to achieve a profound understanding of favour physics in the Standard Model framework and to search signs of new physics beyond. Muons can be found in the final states of many B-decays which are sensitive to CP violation. The Muon Detector has the crucial role to identify the muon particles generated by the b-hadron decays through a measurement of their transverse momentum, already at the first trigger level (Level-0). A 95% effciency in events selection is required for the Muon Trigger, which operates at the Level-0. 1380 detectors are used to equip the whole Muon System and the corresponding 122,112 readout channels must be time aligned and monitored with a resol...

International Society of Radiology and Radiation Protection

International Nuclear Information System (INIS)

Standertskjoeld-Nordenstam, C.G.

2001-01-01

The purpose of the International Society of Radiology (ISR), as being the global organization of radiologists, is to promote and help co-ordinate the progress of radiology throughout the world. In this capacity and as a co-operating organization of the IAEA, the ISR has a specific responsibility in the global radiological protection of patients. Globally, there are many users of medical radiation, and radiology may be practised in the most awkward circumstances. The individuals performing X ray studies as well as those interpreting them may be well trained, as in industrialized parts of the world, but also less knowledgeable, as in developing areas. The problems of radiological protection, both of patients and of radiation workers, still exist, and radiation equipment is largely diffused throughout the world. That is why a conference like this is today as important as ever. Radiation protection is achieved through education, on the one hand, and legislation, on the other. Legislation and regulation are the instruments of national authorities. The means of the ISR are education and information. Good radiological practice is something that can be taught. The ISR is doing this mainly through the biannual International Congress of Radiology (ICR), now arranged in an area of radiological need; the three previous ICRs were in China, in India and in South America; the next one is going to be in Mexico in 2002. The goal of the ICR is mainly to be an instructive and educational event, especially designed for the needs of its surrounding region. The ISR is aiming at producing educational material. The International Commission on Radiological Education (ICRE), as part of the ISR, is launching the production of a series of educational booklets, which also include radiation protection. The ICRE is actively involved in shaping and organizing the educational and scientific programme of the ICRs

Development of Real-Time Coal Monitoring Instrument

Energy Technology Data Exchange (ETDEWEB)

Rajan Gurjar, Ph.D.

2010-06-17

Relying on coal for energy requires optimizing the extraction of heat content from various blends of coal fuel and reducing harmful constituents and byproducts. Having a real-time measurement instrument provides relevant information about toxic constituents released in the atmosphere from burning coal and optimizes the performance of a power plant. A few commercial instruments exist and have been in operation for more than a decade. However, most of these instruments are based on radioactive sources and are bulky, expensive and time-consuming. The proposed instrument is based on the Laser Induced Breakdown Spectroscopy (LIBS). The advantage of LIBS is that it is a standoff instrument, does not require sample preparation and provides precise information about sample constituents.

Compilation of historical radiological data collected in the vicinity of the WIPP site

International Nuclear Information System (INIS)

Bradshaw, P.L.; Louderbough, E.T.

1987-01-01

The Radiological Baseline Program (RBP) at the Waste Isolation Pilot Plant (WIPP) has been implemented to characterize the radiological conditions at the site prior to receipt of radioactive wastes. Because southeastern New Mexico was the site of an underground nuclear test in 1961, various sampling programs have intermittently monitored background and elevated radiation levels in the vicinity of the WIPP. In addition, radiological characterization of the site region was performed during the 1970's in support of the WIPP Environmental Impact Statement. The historical data are drawn primarily from monitoring activities of the US Public Health Service (PHS), the Environmental Protection Agency (EPA), US Geological Survey (USGS) and Sandia National Laboratories, Albuquerque (SNLA). Information on air and water quality, meat, milk, biota and vegetation is included in the report. This survey is intended to provide a source of reference for historical data on radiological conditions in the vicinity of the WIPP site prior to the establishment of a systematic Radiological Baseline Program. 31 refs., 1 fig

Evolution of the radiological protection paradigms

International Nuclear Information System (INIS)

Sordi, Gian Maria A.A.

2009-01-01

We consider as initial radiological protection paradigms those in vigour after the release of the atomic energy for pacific usages in 1955. In that occasion, only one paradigm was introduced, presently named dose limitation system. After arguing about the basis that raised the paradigm, we introduced the guidance, that is, the measurements to be implemented to comply with the paradigm. In that occasion, they were two, i.e., the radiation dose monitoring and the workplace classification. Afterwards, the reasons that caused the radiological protection paradigms changes in force until 1995 are discussed. The initial paradigm was modified introducing the justification and the optimization principles, adding that the radiological protection should be economical and effective. The guidance also increased to four: personal monitoring, workplace classification, reference level and workers classification. Afterwards, we give the main justifications for the present paradigms that besides the formers were added the dose constraints, the potential exposure and the annual risk limits. Due to these modifications, the workers classifications were eliminated from the guidance, but the potential exposure and the search for the dose constraints were added. Eventually, we discuss the tendencies for the next future and the main changes introduced by the ICRP in the Publication 103, 2007. (author)

Advances in radiation protection monitoring

International Nuclear Information System (INIS)

1978-01-01

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

Application of geographic information system for radiologic emergency response

International Nuclear Information System (INIS)

Best, R.G.; Doyle, J.F.; Mueller, P.G.

1998-01-01

Comprehensive and timely radiological, cultural, and environmental data are required in order to make informed decisions during a radiological emergency. Within the Federal Radiological Monitoring and Assessment Center (FRMAC), there is a continuing effort to improve the data management and communication process. The most recent addition to this essential function has been the development of the Field Analysis System for Emergency Response (FASER). It is an integrated system with compatible digital image processing and Geographic Information System (GIS) capabilities. FASER is configured with commercially available off-the-shelf hardware and software components. To demonstrate the potential of the FASER system for radiological emergency response, the system has been utilized in interagency FRMAC exercises to analyze the available spatial data to help determine the impact of a hypothetical radiological release and to develop mitigation plans. (R.P.)

Radiological assessment for bauxite mining and alumina refining.

Science.gov (United States)

O'Connor, Brian H; Donoghue, A Michael; Manning, Timothy J H; Chesson, Barry J

2013-01-01

Two international benchmarks assess whether the mining and processing of ores containing Naturally Occurring Radioactive Material (NORM) require management under radiological regulations set by local jurisdictions. First, the 1 Bq/g benchmark for radionuclide head of chain activity concentration determines whether materials may be excluded from radiological regulation. Second, processes may be exempted from radiological regulation where occupational above-background exposures for members of the workforce do not exceed 1 mSv/year. This is also the upper-limit of exposure prescribed for members of the public. Alcoa of Australia Limited (Alcoa) has undertaken radiological evaluations of the mining and processing of bauxite from the Darling Range of Western Australia since the 1980s. Short-term monitoring projects have demonstrated that above-background exposures for workers do not exceed 1 mSv/year. A whole-of-year evaluation of above-background, occupational radiological doses for bauxite mining, alumina refining and residue operations was conducted during 2008/2009 as part of the Alcoa NORM Quality Assurance System (NQAS). The NQAS has been guided by publications from the International Commission on Radiological Protection (ICRP), the International Atomic Energy Agency (IAEA) and the Australian Radiation Protection and Nuclear Safety Agency (ARPANSA). The NQAS has been developed specifically in response to implementation of the Australian National Directory on Radiation Protection (NDRP). Positional monitoring was undertaken to increase the accuracy of natural background levels required for correction of occupational exposures. This is important in view of the small increments in exposure that occur in bauxite mining, alumina refining and residue operations relative to natural background. Positional monitoring was also undertaken to assess the potential for exposure in operating locations. Personal monitoring was undertaken to characterise exposures in Similar

Nuclear incident monitor criticality alarm instrument for the Savannah River Site: Technical manual

International Nuclear Information System (INIS)

Jenkins, J.B.

1996-01-01

The Savannah River Site is a Department of Energy facility. The facility stores, processes, and works with fissionable material at a number of locations. Technical standards and US Department of Energy orders, require these locations to be monitored by criticality alarm systems under certain circumstances. The Savannah River Site calls such instruments Nuclear Incident Monitors or NIMs. The Sole purpose of the Nuclear Incident Monitor is to provide an immediate evacuation signal in the case of an accidental criticality in order to minimize personnel exposure to radiation. The new unit is the third generation Nuclear Incident Monitor at the Savannah River Site. The second generation unit was developed in 1979. It was designed to eliminate vacuum-tube circuits, and was the first solid state NIM at SRS. The major design objectives of the second generation NIM were to improve reliability and reduce maintenance costs. Ten prototype units have been built and tested. This report describes the design of the new NIM and the testing that took place to verify its acceptability

Proceedings of the Department of Energy workshop on Workplace Aerosol Monitoring

Energy Technology Data Exchange (ETDEWEB)

Kenoyer, J. L.; Vallario, E. J.; Murphy, B. L.

1987-02-01

The workshop on Workshop Aerosol Monitoring was held October 28-30, 1985 in Napa, California and was sponsored by the US Department of Energy, Radiological Controls Division. This workshop brought together participants from the United States, England, France, and West Germany who represented government, research, and industry. The participants discussed the types of air sampling and air monitoring instrumentation that are currently being developed, the problems that need to be addressed in order to obtain ''representative'' samples, and the need for a lower minimum detectable activity to protect the worker from inhalation of radionuclides in a timely manner. This proceedings includes papers and speeches that were presented at the workshop, plus edited transcripts of panel and open discussions, and question and answer sessions.

Effluent and environmental monitoring of Chalk River Laboratories

Energy Technology Data Exchange (ETDEWEB)

Pilgrim, T.; De Waele, C.; Gallagher, C. [Atomic Energy of Canada Limited, Chalk River, ON (Canada)

2014-07-01

Atomic Energy of Canada Limited's (AECL's) Environmental Protection Program has been gathering environmental monitoring data at its Chalk River Laboratories (CRL) for over 60 years. The comprehensive effluent and environmental monitoring program at CRL consists of more than 600 sampling locations, including the Ottawa River, with approximately 60,000 analyses performed on air and liquid effluent parameters each year. Monitoring for a variety of radiological and non-radiological parameters is regularly conducted on various media, including ambient air, foodstuff (e.g. milk, fish, garden produce, large game, and farm animals), groundwater, Ottawa River water and other surface water on and off-site. The purpose of the monitoring program is to verify that past and current radiological and non-radiological emissions derived from AECL operations and activities, such as process water effluent into the Ottawa River, are below regulatory limits and demonstrate that CRL operations do not negatively affect the quality of water on or leaving the site. In fact, ongoing program reports demonstrate that radiological emissions are well below regulatory limits and have been declining for the past five years, and that non-radiological contaminants do not negatively affect the quality of water on and off the site. Two updated Canadian Standards Association (CSA) standards for Effluent and Environmental monitoring have come into effect and have resulted in some changes to the AECL Program. This presentation will discuss effluent and surface water monitoring results, the observed trends, the changes triggered by the CSA standards, and a path forward for the future. (author)

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)

Radiological protection in underground uranium mines

International Nuclear Information System (INIS)

Napolitano, Celia Marina

1978-01-01

The radiosanitary hazards that workers of an uranium ore can suffer were studied. The more used control methods for the the evaluation of doses received by the workers was studied too. It was developed a technique using the scintillation chamber method for the detection of radon. Emanation and diffusion methods were used for extraction of radon from water. A program of radiological protection based on ICRP recommendation was analysed for uranium mines. This program includes: ventilation needs calculation methods, a study of radiological protection optimization based on 'cost-benefit' analysis, a monitoring plan and a study about radioactive waste management. (author)

Mobilization suited for each radiological emergency

International Nuclear Information System (INIS)

Chambrette, V.

2013-01-01

This poster presents the role played by IRSN (French Institute for Radiation protection and Nuclear Safety) in case of radiological alert. This alert can be sent by the administration, a fire brigade, a nuclear operator or a remote monitor of radioactivity. In case of an emergency situation: IRSN provides radiological intervention and assistance on the site. In case of national crisis organization, IRSN will implement the emergency technical center and will send a mobile cell to the Operational Command Station of the Prefecture concerned. In both cases IRSN will be in charge of assessing the individuals' exposure and the impact on the environment

The Ozone Monitoring Instrument: overview of 14 years in space

Directory of Open Access Journals (Sweden)

P. F. Levelt

2018-04-01

Full Text Available This overview paper highlights the successes of the Ozone Monitoring Instrument (OMI on board the Aura satellite spanning a period of nearly 14 years. Data from OMI has been used in a wide range of applications and research resulting in many new findings. Due to its unprecedented spatial resolution, in combination with daily global coverage, OMI plays a unique role in measuring trace gases important for the ozone layer, air quality, and climate change. With the operational very fast delivery (VFD; direct readout and near real-time (NRT availability of the data, OMI also plays an important role in the development of operational services in the atmospheric chemistry domain.

Mission Analysis for Using Preventive Radiological/Nuclear Detection Equipment for Consequence Management

Energy Technology Data Exchange (ETDEWEB)

Buddemeier, Brooke R. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Wood-Zika, Annmarie R. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Haynes, Daniel [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Klemic, Gladys A. [US Dept. of Homeland Security National Urban Security Technology Lab., Manhattan, NY (United States); Musolino, Stephen V. [Brookhaven National Lab. (BNL), Upton, NY (United States)

2017-09-01

The overall objective of this project is to research, evaluate, and test first responder preventive radiological/nuclear detection (PRND) equipment to provide state and local agencies with scientific guidance on how to effectively use this equipment for response after a radiological/nuclear release or detonation. While the equipment being tested in this effort has been specifically designed by technology manufacturers and purchased by responders for preventive detection and source interdiction operations, the fleet of PRND equipment can help fill critical needs for radiological instrumentation should a consequence management (CM) response take place, as it is currently the most widely available and fielded radiological instrumentation by state and local agencies. This effort will provide scientific guidance on the most effective way to utilize this class of equipment for consequence management missions. Gaining a better understanding of how PRND equipment can operate and perform for these missions will allow for recommendations on the tactical approach responders can use for consequence management operations. PRND equipment has been placed into service by federal, state, and local agencies throughout the nation. If the equipment capability and limitations are taken into account, this large inventory can be leveraged to support the emergency response in the aftermath of a radiological or nuclear event. With several hundred makes and models of PRND equipment, often with significantly different detection capabilities that do not align with their nominal PRND equipment type, development of a streamlined categorization scheme with respect to consequence management missions was the first step to identifying safe and effective uses of PRND equipment for radiological/nuclear incident response.

Radiologic accidents in industrial gamma radiography - Brazilian cases

International Nuclear Information System (INIS)

Silva, Francisco Cesar Augusto da

1997-01-01

Three severe radiological accidents in industrial gamma radiography happened in Brazil during the period of 1985 to 1988. Five operators and nineteen public people were involved. These accidents caused some injuries in parts of the body, mainly hands and fingers. The main causes were faults in source monitoring, inadequate routine procedures and unknowing of radiation warning symbol by public people. The present paper shows the Brazilian cases of radiological accidents and makes some analysis of them. (author)

Radiological Protection Institute of Ireland activities and responsibilities

International Nuclear Information System (INIS)

1994-01-01

This brochure describes the Radiological Protection Institute of Ireland's functions and responsibilities which relate principally to the monitoring of radioactivity in the environment and of radiation doses received by people occupationally or otherwise; regulation of the uses of ionising radiation in medicine, industry and elsewhere; assistance in developing national preparedness for response to a radiological emergency; and providing information and advice to government, other organisations and the general public on matters relating to ionising radiation. ills

Computational radiology for orthopaedic interventions

CERN Document Server

Li, Shuo

2016-01-01

This book provides a cohesive overview of the current technological advances in computational radiology, and their applications in orthopaedic interventions. Contributed by the leading researchers in the field, this volume covers not only basic computational radiology techniques such as statistical shape modeling, CT/MRI segmentation, augmented reality and micro-CT image processing, but also the applications of these techniques to various orthopaedic interventional tasks. Details about following important state-of-the-art development are featured: 3D preoperative planning and patient-specific instrumentation for surgical treatment of long-bone deformities, computer assisted diagnosis and planning of periacetabular osteotomy and femoroacetabular impingement, 2D-3D reconstruction-based planning of total hip arthroplasty, image fusion for  computer-assisted bone tumor surgery, intra-operative three-dimensional imaging in fracture treatment, augmented reality based orthopaedic interventions and education, medica...

Evaluation of the current fast neutron flux monitoring instrumentation applied to LFR demonstrator ALFRED. Capabilities and limitations

International Nuclear Information System (INIS)

Lepore, Luigi; Remetti, Romolo; Cappelli, Mauro

2015-01-01

Among Gen IV projects for future nuclear power plants, Lead Fast Reactors (LFR) seem to be a very interesting solution due to their benefits in terms of fuel cycle, coolant-safety and waste management. The novelty of the matter causes some open issues about coolant chemical aspect, structural aspects, monitoring instrumentation, etc. Particularly hard neutron flux spectra would make traditional neutron instrumentation unfit to all reactor conditions, i.e. source, intermediate, and power range. Identification of new models of nuclear instrumentation specialized for LFR neutron flux monitoring asks for an accurate evaluation of the environment the sensor will work in. In this study, thermal-hydraulics and chemical conditions for LFR core environment will be assumed, as the neutron flux will be studied extensively by means of the Monte Carlo transport code MCNPX. The core coolant’s high temperature drastically reduces the candidate instrumentation, because only some kind of fission chambers and Self Powered Neutron Detectors can be operated in such an environment. This work aims to evaluate the capabilities of the available instrumentation (usually designed for Sodium Fast Reactors, SFRs) when exposed to the neutron spectrum derived from ALFRED, a pool-type small-power LFR project to demonstrate the feasibility of this technology into the European framework. This paper shows that such instruments do follow the power evolution, but they are not completely suitable to detect the whole range of reactor power. Some improvements are then possible in order to increase the signal-to-noise ratio, by optimizing each instrument in the range of reactor power, such to get the best solution. Some new detector designs are here proposed, and the possibilities for prototyping and testing by means of a fast reactor investigated. (author)

A report on CERN’s radiological impact

CERN Multimedia

2007-01-01

The Swiss and French authorities have just published a report showing that CERN’s radiological impact is negligible. The CERN Safety Commission’s Environment Team inspects the river Allondon. Since its foundation more than 50 years ago, questions about the Laboratory’s hypothetical radiological impact have been asked repeatedly by the public. These questions are partly due to the name CERN which, for historical reasons, contains the word nuclear. On 16 October, the Swiss and French authorities published a report that takes stock of CERN’s true radiological impact, providing a detailed and documented answer for all those who wonder about the risks of radioactivity. In their report, the Swiss Office fédéral de la santé publique (OFSP) and the French Institut de radioprotection et de sûreté nucléaire (IRSN), the two bodies responsible for monitoring radiological risks in CERN’s Host States, concluded that CERN’s impac...

Analysis of body surface radiological contamination for inbound people from Japan to China during the Fukushima nuclear accident

International Nuclear Information System (INIS)

Yuan Long; Ma Weidong; Lei Cuiping; Chen Huifang; Li Yuwen; Liu Ying

2012-01-01