Laboratory of environmental radiological surveillance; Laboratorio de vigilancia radiologica ambiental

Energy Technology Data Exchange (ETDEWEB)

Mendez G, A.; Marcial M, F.; Giber F, J.; Montiel R, E.; Leon del V, E.; Rivas C, I.; Leon G, M.V.; Lagunas G, E.; Aragon S, R.; Juarez N, A.; Alfaro L, M.M

1991-12-15

The department of radiological protection of the ININ requests the collaboration of the Engineering Unit for the elaboration of the work project of the laboratory of environmental radiological surveillance. The emission of radioactive substances to the atmosphere like consequence of the normal operation of the Nuclear Center, constitutes an exhibition source from the man to the radiations that it should be appropriately watched over and controlled to be able to determine the population's potential exhibition that it lives in the area of influence of the installation. (Author)

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

International Nuclear Information System (INIS)

Fritzsche, A.E.

1990-11-01

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

Sampling on radiological protection training in diagnostic radiology

International Nuclear Information System (INIS)

Gaona, E.

2001-01-01

Radiological security aspects were evaluated in radiology departments from Mexico City. The study was carried out in two stages, the first one evaluated 40 departments just before the implementation of the new Official Mexican Standards related to Radiological Security and Quality Control in Radiology; in the second stage 33 departments were evaluated 2 years after those standards were implanted, showing a favorable impact of the training programs for the type of answers obtained [es

Aerial radiological survey of the Lawrence Livermore Laboratory (Livermore, California)

International Nuclear Information System (INIS)

Tipton, W.J.

1977-10-01

An airborne radiological survey was conducted during August 1975 over several selected sites in the vicinity of Livermore, California. These sites included the Lawrence Livermore Laboratory, Sandia Livermore Laboratories, LLL Site 300, the Livermore Municipal Golf Course, and the City of Livermore's sewage treatment plant. The radiation results were processed specifically for man-made gamma ray activity. All elevated man-made activity observed during the aerial survey was contained within the site boundaries of the three DOE facilities

Why it is necessary to establish regional radiological laboratories in the Republic of Tajikistan

International Nuclear Information System (INIS)

Salomov, J.A.; Khikmatov, M.

2002-01-01

In this article we have shown the necessity of establishing Regional radiological laboratories in the Republic of Tajikistan. Indeed, the considerable length of Tajikistan's border with such states as Afghanistan and China and taking into account today's situation in Afghanistan there is a possibility of using the territory of the Republic of Tajikistan for illicit trafficking of nuclear material and penetrating of nuclear terrorist in other countries through Tajikistan's border. In this connection, in frontier districts, which can be used for export and import of goods, it is necessary to establish radiological laboratories with the purpose of prevention of illicit trafficking of nuclear materials. To establish these laboratories the Republic of Tajikistan has need for international financing and international organizations' assistance. (author)

324 Building Baseline Radiological Characterization

International Nuclear Information System (INIS)

Reeder, R.J.; Cooper, J.C.

2010-01-01

This report documents the analysis of radiological data collected as part of the characterization study performed in 1998. The study was performed to create a baseline of the radiological conditions in the 324 Building. A total of 85 technical (100 square centimeter (cm 2 )) smears were collected from the Room 147 hoods, the Shielded Materials Facility (SMF), and the Radiochemical Engineering Cells (REC). Exposure rate readings (window open and window closed) were taken at a distance of 2.5 centimeters (cm) and 30 cm from the surface of each smear. Gross beta-gamma and alpha counts of each smear were also performed. The smear samples were analyzed by gamma energy analysis (GEA). Alpha energy analysis (AEA) and strontium-90 analysis were also performed on selected smears. GEA results for one or more samples reported the presence of manganese-54, cobalt-60, silver-108m antimony-125, cesium-134, cesium-137, europium-154, europium-155, and americium-241. AEA results reported the presence of plutonium-239/240, plutonium-238/ 241 Am, curium-243/244, curium-242, and americium-243. Tables 5 through 9 present a summary by location of the estimated maximum removable and total contamination levels in the Room 147 hoods, the SMF, and the REC. The smear sample survey data and laboratory analytical results are presented in tabular form by sample in Appendix A. The Appendix A tables combine survey data documented in radiological survey reports found in Appendix B and laboratory analytical results reported in the 324 Building Physical and Radiological Characterization Study (Berk, Hill, and Landsman 1998), supplemented by the laboratory analytical results found in Appendix C.

A mobile radiological laboratory for rapid response to off-site radiation emergencies

Energy Technology Data Exchange (ETDEWEB)

Katoch, D. S.; Sharma, R. C.; Mehta, D. J.; Raj, V. Venkat [Bhabha Atomic Research Centre, Mumbai (India)

2002-07-01

A mobile radiological laboratory (MRL) has been designed and developed primarily for providing a rapid response to radiation emergencies arising as a consequence of nuclear and/or radiological accidents. It is equipped specifically to monitor the environment and provide quick assessment of radiological hazards to the population living within a radius of 30 km around a nuclear facility. In this paper, various design features of an Indian MRL together with the details of installed equipment are presented. The MRL has been designed for a continuous outdoor operation of about two weeks. It is built on a 10.70 m long air suspension Bus Chassis and has four sections : Driver's Cabin, Main Counting Laboratory, Whole Body Monitor and Rear section housing general utilities. The electric power is provided by two diesel generators during field operation and by 230 V AC mains supply at headquarters and wherever possible. The equipment installed in the MRL includes : Alpha, beta and gamma counting systems and low and high volume air samplers for the assessment of radioactive contents in the samples of air, water, soil and vegetation; environment dose rate meters and a variety of survey meters for evaluating any potential increase in radiation levels; personal dosimeters to control external radiation exposure; personal protective equipment for avoiding skin and clothing contamination; a chair type of whole body monitor for the assessment of internal radioactive contamination of the human body, in particular, thyroidal uptake of radioiodine; an automatic weather station for recording continuously the meteorological parameters and a satellite based global positioning system to continuously track and display the geographical location of the MRL. The calibrations of the installed equipment are presently in progress. Preliminary results obtained for the methods needed for rapid detection of gamma emitters in the environment and human body, namely, in situ gamma spectrometry and

Results of the radiological and chemical characterization of surface impoundments 3539 and 3540 at Oak Ridge National Laboratory, Oak Ridge, Tennessee

International Nuclear Information System (INIS)

Murray, M.E.; Rose, D.A.; Brown, K.S.; Winton, W.; Dean, R.A.; Coe, R.H. III

1998-03-01

A radiological and chemical characterization survey of impoundments 3539 and 3540 at the Oak Ridge National Laboratory (ORNL) was conducted during December 1997. Impoundments 3539 and 3540 are located in the Surface Impoundments Operable Unit (SIOU) of Waste Area Group 1. The investigation was performed by the Measurement Applications and Development Group of the Life Sciences Division of ORNL at the request of the Department of Energy (DOE) Office of Environmental Restoration. Sampling was conducted in order to quantify the presence of polychlorinated biphenyls (PCBs), Resource Conservation and Recovery Act (RCRA) constituents, and other contaminants of interest in support of the Comprehensive Environmental Response, Compensation and Liability Act (CERCLA) remediation for the SIOU> The survey included collection of sediment/clay samples, quality control blank water samples and equipment rinsate samples for chemical and radiological analysis. Results show the samples contain traces of various organic, inorganic, and radioactive materials. Of particular interest are PCB values which demonstrate the impoundments are not regulated under the Toxic Substances Control Act

Surveillance and radiological protection in the Hot Cell laboratory

International Nuclear Information System (INIS)

Ramirez, J.M.; Torre, J. De la; Garcia C, M.A.

2004-01-01

The Hot Cells Laboratory (LCC) located in the National Institute of Nuclear Research are an installation that was designed for the management at distance of 10,000 Curies of Co-60 or other radioactive materials with different values in activity. The management of such materials in the installation, implies to analyze and to determine the doses that the POE will receive as well as the implementation of protection measures and appropriate radiological safety so that is completed the specified by the ALARA concept. In this work it is carried out an evaluation of the doses to receive for the POE when managing radionuclides with maximum activities that can be allowed in function of the current conditions of the cells and an evaluation of results is made with the program of surveillance and radiological protection implemented for the development of the works that carried out in the installation. (Author)

Sampling and Analysis Plan for White Oak Creek Watershed Remedial Investigation supplemental sampling, Oak Ridge National Laboratory, Oak Ridge, Tennessee

International Nuclear Information System (INIS)

1996-05-01

This Sampling and Analysis (SAP) presents the project requirements for proposed soil sampling to support the White Oak Creek Remedial Investigation/Feasibility Study at Oak Ridge National Laboratory. During the Data Quality Objectives process for the project, it was determined that limited surface soils sampling is need to supplement the historical environmental characterization database. The primary driver for the additional sampling is the need to identify potential human health and ecological risks at various sites that have not yet proceeded through a remedial investigation. These sites include Waste Area Grouping (WAG)3, WAG 4, WAG 7, and WAG 9. WAG 4 efforts are limited to nonradiological characterization since recent seep characterization activities at the WAG have defined the radiological problem there

Emergency radiological monitoring and analysis United States Federal Radiological Monitoring and Assessment Center

International Nuclear Information System (INIS)

Thome, D.J.

1994-01-01

The United States Federal Radiological Emergency Response Plan (FRERP) provides the framework for integrating the various Federal agencies responding to a major radiological emergency. Following a major radiological incident the FRERP authorizes the creation of the Federal Radiological Monitoring and Assessment Center (FRMAC). The FRMAC is established to coordinate all Federal agencies involved in the monitoring and assessment of the off-site radiological conditions in support of the impacted states and the Lead Federal Agency (LFA). Within the FRMAC, the Monitoring and Analysis Division is responsible for coordinating all FRMAC assets involved in conducting a comprehensive program of environmental monitoring, sampling, radioanalysis and quality assurance. This program includes: (1) Aerial Radiological Monitoring - Fixed Wing and Helicopter, (2) Field Monitoring and Sampling, (3) Radioanalysis - Mobile and Fixed Laboratories, (4) Radiation Detection Instrumentation - Calibration and Maintenance, (5) Environmental Dosimetry, and (6) An integrated program of Quality Assurance. To assure consistency, completeness and the quality of the data produced, a methodology and procedures handbook is being developed. This paper discusses the structure, assets and operations of FRMAC monitoring and analysis and the content and preparation of this handbook

Northern Marshall Islands radiological survey: sampling and analysis summary

Energy Technology Data Exchange (ETDEWEB)

Robison, W.L.; Conrado, C.L.; Eagle, R.J.; Stuart, M.L.

1981-07-23

A radiological survey was conducted in the Northern Marshall Islands to document reamining external gamma exposures from nuclear tests conducted at Enewetak and Bikini Atolls. An additional program was later included to obtain terrestrial and marine samples for radiological dose assessment for current or potential atoll inhabitants. This report is the first of a series summarizing the results from the terrestrial and marine surveys. The sample collection and processing procedures and the general survey methodology are discussed; a summary of the collected samples and radionuclide analyses is presented. Over 5400 samples were collected from the 12 atolls and 2 islands and prepared for analysis including 3093 soil, 961 vegetation, 153 animal, 965 fish composite samples (average of 30 fish per sample), 101 clam, 50 lagoon water, 15 cistern water, 17 groundwater, and 85 lagoon sediment samples. A complete breakdown by sample type, atoll, and island is given here. The total number of analyses by radionuclide are 8840 for /sup 241/Am, 6569 for /sup 137/Cs, 4535 for /sup 239 +240/Pu, 4431 for /sup 90/Sr, 1146 for /sup 238/Pu, 269 for /sup 241/Pu, and 114 each for /sup 239/Pu and /sup 240/Pu. A complete breakdown by sample category, atoll or island, and radionuclide is also included.

Northern Marshall Islands radiological survey: sampling and analysis summary

International Nuclear Information System (INIS)

Robison, W.L.; Conrado, C.L.; Eagle, R.J.; Stuart, M.L.

1981-01-01

A radiological survey was conducted in the Northern Marshall Islands to document reamining external gamma exposures from nuclear tests conducted at Enewetak and Bikini Atolls. An additional program was later included to obtain terrestrial and marine samples for radiological dose assessment for current or potential atoll inhabitants. This report is the first of a series summarizing the results from the terrestrial and marine surveys. The sample collection and processing procedures and the general survey methodology are discussed; a summary of the collected samples and radionuclide analyses is presented. Over 5400 samples were collected from the 12 atolls and 2 islands and prepared for analysis including 3093 soil, 961 vegetation, 153 animal, 965 fish composite samples (average of 30 fish per sample), 101 clam, 50 lagoon water, 15 cistern water, 17 groundwater, and 85 lagoon sediment samples. A complete breakdown by sample type, atoll, and island is given here. The total number of analyses by radionuclide are 8840 for 241 Am, 6569 for 137 Cs, 4535 for 239+240 Pu, 4431 for 90 Sr, 1146 for 238 Pu, 269 for 241 Pu, and 114 each for 239 Pu and 240 Pu. A complete breakdown by sample category, atoll or island, and radionuclide is also included

Radiological risk guidelines for nonreactor nuclear facilities at the Pacific Northwest Laboratory

International Nuclear Information System (INIS)

Lucas, D.E.; Ikenberry, T.A.

1994-03-01

Radiological risk evaluation guidelines for the public and workers have been developed at the Pacific Northwest Laboratory (PNL) based upon the Nuclear Safety Policy of the US Department of Energy (DOE) established in Secretary of Energy Notice SEN-35-91 (DOE 1991). The DOE nuclear safety policy states that the general public be protected-such that no individual bears significant additional risk to health and safety from the operation of a DOE nuclear facility above the risks to which members of the general population are normally exposed. The radiological risk evaluation guidelines developed at PNL are unique in that they are (1) based upon quantitative risk goals and (2) provide a consistent level of risk management. These guidelines are used to evaluate the risk from radiological accidents that may occur during research and development activities at PNL. A safety analyst uses the frequency of the potential accident and the radiological dose to a given receptor to determine if the accident consequences meet the objectives of the Nuclear Safety Policy

Surface radiological free release program for the Battelle Columbus Laboratory Decommissioning Project

International Nuclear Information System (INIS)

Horton, C.N.

1995-01-01

This paper was prepared for the Second Residual Radioactivity and Recycling Criteria Workshop and discusses decommissioning and decontamination activities at the Battelle Columbus Laboratories Decommissioning Project (BCLDP). The BCLDP is a joint effort between the Department of Energy (DOE) and Battelle Columbus Operations to decontaminate fifteen Battelle-owned buildings contaminated with DOE radioactive materials. The privately owned buildings located across the street from The Ohio State University campus became contaminated with natural uranium and thorium during nuclear research activities. BCLDP waste management is supported by an extensive radiological free-release program. Miscellaneous materials and building surfaces have been free-released from the BCLDP. The free-release program has substantially reduced radioactive waste volumes and supported waste minimization. Free release for unrestricted use has challenged regulators and NRC licensees since the development of early surface-release criteria. This paper discusses the surface radiological free-release program incorporated by the BCLDP and the historical development of the surface radiological free-release criteria. Concerns regarding radiological free-release criteria are also presented. (author)

Post-remedial-action radiological survey of the Westinghouse Advanced Reactors Division Plutonium Fuel Laboratories, Cheswick, Pennsylvania, October 1-8, 1981

International Nuclear Information System (INIS)

Flynn, K.F.; Justus, A.L.; Sholeen, C.M.; Smith, W.H.; Wynveen, R.A.

1984-01-01

The post-remedial-action radiological assessment conducted by the ANL Radiological Survey Group in October 1981, following decommissioning and decontamination efforts by Westinghouse personnel, indicated that except for the Advanced Fuels Laboratory exhaust ductwork and north wall, the interior surfaces of the Plutonium Laboratory and associated areas within Building 7 and the Advanced Fuels Laboratory within Building 8 were below both the ANSI Draft Standard N13.12 and NRC Guideline criteria for acceptable surface contamination levels. Hence, with the exceptions noted above, the interior surfaces of those areas within Buildings 7 and 8 that were included in the assessment are suitable for unrestricted use. Air samples collected at the involved areas within Buildings 7 and 8 indicated that the radon, thoron, and progeny concentrations within the air were well below the limits prescribed by the US Surgeon General, the Environmental Protection Agency, and the Department of Energy. The Building 7 drain lines are contaminated with uranium, plutonium, and americium. Radiochemical analysis of water and dirt/sludge samples collected from accessible Low-Bay, High-Bay, Shower Room, and Sodium laboratory drains revealed uranium, plutonium, and americium contaminants. The Building 7 drain lines hence are unsuitable for release for unrestricted use in their present condition. Low levels of enriched uranium, plutonium, and americium were detected in an environmental soil coring near Building 8, indicating release or spillage due to Advanced Reactors Division activities or Nuclear Fuel Division activities undr NRC licensure. 60 Co contamination was detected within the Building 7 Shower Room and in soil corings from the environs of Building 7. All other radionuclide concentrations measured in soil corings and the storm sewer outfall sample collected from the environs about Buildings 7 and 8 were within the range of normally expected background concentrations

Safety and regulatory aspects of radiological laboratories

International Nuclear Information System (INIS)

Kumar, N.; Saxena, M.K.; Kannan, S.; Pujari, P.K.; Tomar, B.S.

2017-01-01

The erstwhile Radiochemistry Division (RCD) at Radiological Laboratories (RLG) was mainly concerned with the basic research and development work related to actinide chemistry and studies involving nuclear fission. The various activities of the different divisions are development of Non Destructive Assay (NDA) methods for the determination of actinides, characterization of advanced Pu based fuels using latest spectroscopic methods, development of sol-gel route for fabrication of different type of fuels, studies on high temperature thermodynamics of actinide compounds, development of methods for recovery and recycling of fuel scrap, mass spectrometric analysis of nuclear fuels and structural characterization of various uranium and plutonium compounds using X-ray diffraction and fluorescence techniques, trace elements analysis, need-based developmental work, inventory information and control of nuclear materials

Federal Radiological Monitoring and Assessment Center. The analytical response

International Nuclear Information System (INIS)

Nielsen, E.C.

2005-01-01

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

Federal Radiological Monitoring and Assessment Center Analytical Response

International Nuclear Information System (INIS)

Nielsen, E.C.

2003-01-01

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

Radiological analyses of Marshall Islands environmental samples, 1974--1976

International Nuclear Information System (INIS)

Greenhouse, N.A.; Miltenberger, R.P.; Cua, F.T.

1977-01-01

Results are reported from the radiological analysis of environmental samples collected in the Marshall Islands during 1974 through 1976. Most of the samples were collected on or near the Bikini Atoll and included plants, soil, fish, catchment water, and sediments, with emphasis on local marine and terrestrial food items. Data are presented from γ spectral analysis and the content of 90 Sr and transuranic elements in the samples

Upgrading the Medical Physics Calibration Laboratory Towards ISO/IEC 17025: Radiation Standards and Calibration in Diagnostic Radiology

International Nuclear Information System (INIS)

Asmaliza Hashim; Muhammad Jamal Md Isa; Abd Aziz Mhd Ramli; Wan Hazlinda Ismail; Norhayati Abdullah; Shahrul Azlan Azizan; Siti Sara Deraman; Nor Azlin Azraai; Md Khairusalih Md Zin

2010-01-01

Calibration of quality control (QC) test tools used in diagnostic radiology is legally required under the Ministry of Health (MOH) requirement. The Medical Physics Calibration Laboratory of the Malaysian Nuclear Agency is the national focal point for the calibration of quality control test tools used in diagnostic radiology. The Medical Physics Calibration Laboratory has measurement traceability to primary standard dosimetry laboratory (Physikalisch-Technische Bundesanstalt (PTB)), thus providing an interface between the primary standard dosimetry laboratory and Malaysian hospitals, clinics and license class H holder. The Medical Physics Calibration Laboratory facility is comprised of a constant potential x-ray system with a capability of 160 kV tube and a series of reference and working standard ion chambers. The stability of reference and working standard ion chambers was measured using strontium-90. Dosimetric instruments used in diagnostic radiology is calibrated in terms of air kerma to comply with an International Code of Practices of dosimetry for example IAEA's Technical Report Series number 457. The new series of standard radiation qualities was established based on ISO/IEC 61267. The measurement of beam homogeneity was measured using film and ion chamber to define the field size at certain distance and kV output was measured using the spectrometer and non-invasive kVp meter. The uncertainties measurement was determined with expended uncertainties to a level of confidence of approximately 95% (coverage factor k=2). This paper describes the available facility and the effort of the Medical Physics Calibration Laboratory to upgrade the laboratory towards ISO/IEC 17025. (author)

Quality assurance programs at the PNL calibrations laboratory

International Nuclear Information System (INIS)

Piper, R.K.; McDonald, J.C.; Fox, R.A.; Eichner, F.N.

1993-03-01

The calibrations laboratory at Pacific Northwest Laboratory (PNL) serves as a radiological standardization facility for personnel and environmental dosimetry and radiological survey instruments. As part of this function, the calibrations laboratory must maintain radiological reference fields with calibrations traceable to the National Institute of Standards and Technology (NIST). This task is accomplished by a combination of (1) sources or reference instruments calibrated at or by NIST, (2) measurement quality assurance (MQA) interactions with NIST, and (3) rigorous internal annual and quarterly calibration verifications. This paper describes a representative sample of the facilities, sources, and actions used to maintain accurate and traceable fields

Quality assurance plan for the Close Support Laboratory for the remedial investigation at Oak Ridge National Laboratory, Oak Ridge, Tennessee

International Nuclear Information System (INIS)

1993-08-01

The primary purpose of the Close Support Laboratory (CSL) is to provide rapid radiological screening of investigation-derived samples before they are shipped to off-site laboratories for more detailed analyses. Analyses for volatile organic compounds and miscellaneous water quality parameters are also performed at the CSL. CSL data are also used to select samples for off-site laboratory analysis, for rapid qualitative and quantitative determinations, and for other processes when off-site analysis is not needed and/or is impractical. This plan specifies methods of implementing analytical and radiological protocols and procedures for the documentation, handling, control, and analysis of samples and describes the levels of authority and responsibility for laboratory operation. Specific quality control methods used by the CSL for individual analyses are described in project procedures

An aerial radiological survey of the Sandia National Laboratories and surrounding area

International Nuclear Information System (INIS)

Riedhauser, S.R.

1994-06-01

A team from the Remote Sensing Laboratory conducted an aerial radiological survey of the area surrounding the Sandia National Laboratories and Kirtland Air Force Base in Albuquerque, New Mexico, during March and April 1993. The survey team measured the terrestrial gamma radiation at the site to determine the levels of natural and man-made radiation. This survey includes the areas covered by a previous survey in 1981. The results of the aerial survey show a background exposure rate which varies between 5 and 18 μR/h plus an approximate 6 μR/h contribution from cosmic rays. The major radioactive isotopes found in this survey were: potassium-40, thallium-208, bismuth-214, and actinium-228, which are all naturally-occurring isotopes, and cobalt-60, cesium-137, and excess amounts of thallium-208 and actinium-228, which are due to human actions in the survey area. In regions away from man-made activity, the exposure rates inferred from this survey's gamma ray measurements agree almost exactly with the exposure rates inferred from the 1981 survey. In addition to the aerial measurements, another survey team conducted in situ and soil sample radiation measurements at three sites within the survey perimeter. These ground-based measurements agree with the aerial measurements within ± 5%

The Emergency Radiological Monitoring and Analysis Division of the United States Federal Radiological Monitoring and Assessment Center

International Nuclear Information System (INIS)

Thome, D.J.

2000-01-01

The U.S. Federal Radiological Emergency Response Plan (FRERP) provides the framework for integrating the various Federal agencies responding to a major radiological emergency. The FRERP authorises the creation of the Federal Radiological Monitoring and Assessment Center (FRMAC), which is established to co-ordinate all Federal agencies involved in the monitoring and assessment of the off-site radiological conditions in support of the impacted States and the Lead Federal Agency (LFA). Within the FRMAC, the Monitoring and Analysis Division is responsible for co-ordinating all FRMAC assets involved in conducting a comprehensive program of environmental monitoring, sampling, radioanalysis, and quality assurance. This program includes: 1. Aerial Radiological Monitoring - Fixed-Wing and Helicopter; 2. Field Monitoring and Sampling; 3. Radioanalysis - Mobile and Fixed Laboratories; 4. Radiation Detection Instrumentation - Calibration and Maintenance; 5. Environmental Dosimetry; 6. Integrated program of Quality Assurance. To assure consistency, completeness, and the quality of the data produced, a methodology and procedures manual is being developed. This paper discusses the structure, assets, and operations of the FRMAC Monitoring and Analysis Division and the content and preparation of the manual. (author)

Preparing a laboratory for radioanalytical emergency response

International Nuclear Information System (INIS)

Bennett, J.; Webb, C.J.; Isch, S.

2011-01-01

As the state of the nation's ability to respond to a radiological event is examined, it has become apparent that both capacity and capability are lacking. Department of Homeland Security National Planning Scenario 11 is designed to address the planning activities for the response to an attack using radiological dispersal devices. The scenario details show that the cleanup activity will take several years, and that there will be between 360 000 and 1 000 000 environmental samples in the first year. Based on existing capacity and capabilities it would take four to six years to analyze the samples generated at the lower end of the sample range. The Environmental Protection Agency (EPA) has been given responsibility for the remediation activities following a radiological event, and has awarded cooperative agreements to several laboratories to start the process of developing capacity and capabilities. The Connecticut Department of Public Health Laboratory (DPHL) was awarded one of the cooperative agreements. The DPHL has started activities to further those goals by investigating and implementing procedures to ensure that samples with activity higher than normal background can be processed safely, as well as implementing more rapid methods for radiochemical analysis. The DPHL already served as the primacy radiochemistry laboratory for several New England states and thus had a solid foundation to build upon. The DPHL has taken a process flow approach in preparing for radiological emergency response and recommends that radioanalytical laboratories that are reviewing their roles in such a response: - Ensure that their Nuclear Regulatory Commission licenses allow for appropriate radioisotope types and activities; - Develop procedures and processes to ensure that samples with higher activities can be processed safely, with due regard for sample screening and aliquanting samples; - Provide for enhanced radioanalytical contamination control, with careful consideration of sample

Radiological risk guidelines for nonreactor nuclear facilities at the Pacific Northwest Laboratory

International Nuclear Information System (INIS)

Lucas, D.E.; Ikenberry, T.A.

1993-09-01

Radiological risk evaluation guidelines for the public and workers have been developed at the Pacific Northwest Laboratory (PNL) based upon the Nuclear Safety Policy of the US Department of Energy (DOE) established in Secretary of Energy Notice SEN-35-91. The DOE nuclear safety policy states that the general public shall be protected such that no individual bears significant additional risk to health and safety from the operation of a DOE nuclear facility above the risks to which members of the general population are normally exposed. The radiological risk evaluation guidelines developed at PNL are unique in that they are (1) based upon quantitative risk goals and (2) provide a consistent level of risk management. These guidelines are used to evaluate the risk from radiological accidents that may occur during research and development activities at PNL, and are not intended for evaluation of routine exposures. A safety analyst uses the,frequency of the potential accident and the radiological dose to a given receptor to determine if the accident consequences meet the objectives of the Nuclear Safety Policy. The radiological risk evaluation guidelines are an effective tool for assisting in the management of risk at DOE nonreactor nuclear facilities. These guidelines (1) meet the nuclear safety policy of DOE, (2) establish a tool for managing risk at a consistent level within the defined constraints, and (3) set risk at an appropriate level, as compared with other risks encountered by the public and worker. Table S.1 summarizes the guidelines developed in this report

Usability evaluation of Laboratory and Radiology Information Systems integrated into a hospital information system.

Science.gov (United States)

Nabovati, Ehsan; Vakili-Arki, Hasan; Eslami, Saeid; Khajouei, Reza

2014-04-01

This study was conducted to evaluate the usability of widely used laboratory and radiology information systems. Three usability experts independently evaluated the user interfaces of Laboratory and Radiology Information Systems using heuristic evaluation method. They applied Nielsen's heuristics to identify and classify usability problems and Nielsen's severity rating to judge their severity. Overall, 116 unique heuristic violations were identified as usability problems. In terms of severity, 67 % of problems were rated as major and catastrophic. Among 10 heuristics, "consistency and standards" was violated most frequently. Moreover, mean severity of problems concerning "error prevention" and "help and documentation" heuristics was higher than of the others. Despite widespread use of specific healthcare information systems, they suffer from usability problems. Improving the usability of systems by following existing design standards and principles from the early phased of system development life cycle is recommended. Especially, it is recommended that the designers design systems that inhibit the initiation of erroneous actions and provide sufficient guidance to users.

Bi-annual report 1994-1995. Research and operational activities of Central Laboratory for Radiological Protection

International Nuclear Information System (INIS)

1996-01-01

BI-annual report of Central Laboratory for Radiological Protection, Warsaw, shows its activities in 1994-1995. The general information and organization of CLOR have been performed in the opening part of the report. The second part contains extended abstracts of scientific activities especially in: environmental radioactivity monitoring, supervision and control of the users of radioactive sources, dosimetry problems, calibration and standardization of dosimetric equipment, radiobiology and radiological hazard assessment. The report also includes the full list of publications of CLOR scientific staff issued in the period of 1994-1995

Bi-annual report 1994-1995. Research and operational activities of Central Laboratory for Radiological Protection

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-12-31

BI-annual report of Central Laboratory for Radiological Protection, Warsaw, shows its activities in 1994-1995. The general information and organization of CLOR have been performed in the opening part of the report. The second part contains extended abstracts of scientific activities especially in: environmental radioactivity monitoring, supervision and control of the users of radioactive sources, dosimetry problems, calibration and standardization of dosimetric equipment, radiobiology and radiological hazard assessment. The report also includes the full list of publications of CLOR scientific staff issued in the period of 1994-1995.

Bi-annual report 1992-1993. Operational and research activities of Central Laboratory for Radiological Protection

International Nuclear Information System (INIS)

1994-06-01

Bi-annual report of Central Laboratory for Radiological Protection, Warsaw shows its activities in 1992-1993. The general information and organization of CLOR have been shown in the first part of the report. The second part contains extended abstracts of scientific activity, especially in: environmental radioactivity monitoring, supervision and control of the users of radioactive sources, personal dosimetry, calibration and periodical control of dosimetric equipment, radiobiology and radiological hazard assessment. The report also includes the full list of publications of scientists of CLOR issued in the period of 1992-1993

Bi-annual report 1992-1993. Operational and research activities of Central Laboratory for Radiological Protection

Energy Technology Data Exchange (ETDEWEB)

NONE

1994-06-01

Bi-annual report of Central Laboratory for Radiological Protection, Warsaw shows its activities in 1992-1993. The general information and organization of CLOR have been shown in the first part of the report. The second part contains extended abstracts of scientific activity, especially in: environmental radioactivity monitoring, supervision and control of the users of radioactive sources, personal dosimetry, calibration and periodical control of dosimetric equipment, radiobiology and radiological hazard assessment. The report also includes the full list of publications of scientists of CLOR issued in the period of 1992-1993.

Corelations between radiological score with clinical and laboratory parameters in rheumatoid arthritis

Directory of Open Access Journals (Sweden)

Mihaela Chicu

2016-12-01

Full Text Available Staging in rheumatoid arthritis (RA and evaluating the effectiveness of drug treatment involves the determination of radiological scores (for narrowing and erosions, this being the most specific changes and most commonly found in RA.Matherials and methods: Our study was condacted over a period of 12 months in Medical Rehabilitation Clinic of „Sf. Spiridon” Iasi Hospital, on a group of 40 women patients with RA in various stages of evolution. X-ray examination was done on hands and feet at the beginning and the end of the study period. There were computed radiographic Sharp scores for narrowing and erosions and the total score. Erosions were examined for 16 joints in each hand. For narrowing five joints were evaluated. For accuracy, radiological examination was done on mammography film. Rezults:After calculating Sharp scores - Van der Heide version - I compared them with the levels of clinical (HAQ, NAT, NAD, DAS28, bone densitometry and laboratory (ESR, CRP, rheumatoid factor, IL-1β parameters.Conclusions: The values of radiological scores for narrowing and erosions are directly correlate with DAS28, HAQ, rheumatoid factors levels and IgG values, and indirectly correlated with IL-1β levels.

Results of the independent radiological verification survey of the remedial action performed at the former Alba Craft Laboratory site, Oxford, Ohio, (OXO001)

International Nuclear Information System (INIS)

Kleinhans, K.R.; Murray, M.E.; Carrier, R.F.

1996-04-01

Between October 1952 and February 1957, National Lead of Ohio (NLO), a primary contractor for the Atomic Energy Commission (AEC), subcontracted certain uranium machining operations to Alba Craft Laboratory, Incorporated, located at 10-14 West Rose Avenue, Oxford, Ohio. In 1992, personnel from Oak Ridge National Laboratory (ORNL) confirmed the presence of residual radioactive materials from the AEC-related operations in and around the facility in amounts exceeding the applicable Department of Energy (DOE) guidelines. Although the amount of uranium found on the property posed little health hazard if left undisturbed, the levels were sufficient to require remediation to bring radiological conditions into compliance with current guidelines, thus ensuring that the public and the environment are protected. A team from ORNL conducted a radiological verification survey of the former Alba Craft Laboratory property between December 1994 and February 1995. The survey was conducted at the request of DOE and included directly measured radiation levels, the collection and analysis of soil samples to determine concentrations of uranium and certain other radionuclides, and comparison of these data to the guidelines. This document reports the findings of this survey. The results of the independent verification survey of the former Alba Craft Laboratory property demonstrate that all contaminated areas have been remediated to radionuclide concentrations and activity levels below the applicable guideline limits set by DOE

CSU-FDA Collaborative Radiological Health Laboratory annual report 1979

International Nuclear Information System (INIS)

1981-01-01

Highlights of findings by the Collaborative Radiological Health Laboratory (CRHL) on lifetime hazards associated with prenatal and early postnatal exposure to discrete doses of gamma radiation are presented in this volume. The CRHL study is designed to provide information that will facilitate the evaluation of risks to human beings from medical exposure during early development. It is a life span study using beagles exposed at one of several specific times in early development. The CRHL program is multidisciplinary in nature and involves evaluation of a variety of diseases of potential concern for human health. Problems of growth and development, reproductive capacity, degenerative diseases, and aging are among those addressed. Separate abstracts of 20 studies have been prepared for inclusion in the Energy Data Base

Radiological Control Manual

Energy Technology Data Exchange (ETDEWEB)

1993-04-01

This manual has been prepared by Lawrence Berkeley Laboratory to provide guidance for site-specific additions, supplements, and clarifications to the DOE Radiological Control Manual. The guidance provided in this manual is based on the requirements given in Title 10 Code of Federal Regulations Part 835, Radiation Protection for Occupational Workers, DOE Order 5480.11, Radiation Protection for Occupational Workers, and the DOE Radiological Control Manual. The topics covered are (1) excellence in radiological control, (2) radiological standards, (3) conduct of radiological work, (4) radioactive materials, (5) radiological health support operations, (6) training and qualification, and (7) radiological records.

Radiological Control Manual

International Nuclear Information System (INIS)

1993-04-01

This manual has been prepared by Lawrence Berkeley Laboratory to provide guidance for site-specific additions, supplements, and clarifications to the DOE Radiological Control Manual. The guidance provided in this manual is based on the requirements given in Title 10 Code of Federal Regulations Part 835, Radiation Protection for Occupational Workers, DOE Order 5480.11, Radiation Protection for Occupational Workers, and the DOE Radiological Control Manual. The topics covered are (1) excellence in radiological control, (2) radiological standards, (3) conduct of radiological work, (4) radioactive materials, (5) radiological health support operations, (6) training and qualification, and (7) radiological records

Percutaneous cecostomy: Laboratory and clinical experience with a new radiologic technique

International Nuclear Information System (INIS)

Van Sonnenberg, E.; Casola, G.; Wittich, G.R.; Stavas, J.; Quinn, S.F.; Gibbs, J.; Macaulay, S.; Schecter, M.S.; Edwards, K.C.

1987-01-01

Percutaneous cecostomy or colostomy is a new interventional radiology procedure used for colonic decompression due to mechanical obstruction or pseudoobstruction. This paper describes our laboratory and initial clinical work with percutaneous colostomy. In our initial nine patient, it has served as a temporizing (five patients), definitive (three patients), or inadvertent maneuver (one patient). Methods of guidance were CT (three patients) and fluoroscopy (six patients). Catheters were placed both transperitoneally and retroperitoneally; laboratory work focused on these paths of introduction as well as catheter insertion and catheter type. The authors used catheters with retention devices preferentially, and these permit adherence of the colon to the abdominal wall. Both Seldinger and trocar techniques have been utilized. Leakage has resulted in minor abdominal pain; no patient has required operation due to percutaneous cecostomy. All procedures were successful and accomplished their goal

Air kerma standardization for diagnostic radiology, and requirements proposal for calibration laboratories

International Nuclear Information System (INIS)

Ramos, Manoel Mattos Oliveira

2009-01-01

The demand for calibration services and quality control in diagnostic radiology has grown in the country since the publication of the governmental regulation 453, issued by the Ministry of Health in 1998. At that time, to produce results facing the new legislation, many laboratories used different standards and radiation qualities, some of which could be inadequate. The international standards neither supplied consistent radiation qualities and standardization for the different types of equipment available. This situation changed with the publication of the new edition of the IEC 61267 standard, published in 2005. A metrology network was created, but it is not yet accredited by the accreditation organism of the country, INMETRO. The objective of this work was to implement the standardization of the air kerma for the un attenuated qualities (RQR) of IEC 61267, and to develop a requirement proposal for instruments calibration laboratories. Results of interlaboratory comparisons demonstrate that the quantity is standardized and internationally traceable. A laboratory requirement proposal was finalized and it shall be submitted to INMETRO to be used as auxiliary normative document in laboratory accreditation. (author)

Building Connecticut's clinical biodosimetry laboratory surge capacity to mitigate the health consequences of radiological and nuclear disasters: A collaborative approach between the state biodosimetry laboratory and Connecticut's medical infrastructure

International Nuclear Information System (INIS)

Albanese, Joseph; Martens, Kelly; Arnold, Jeffrey L.; Kelley, Katherine; Kristie, Virginia; Forte, Elaine; Schneider, Mark; Dainiak, Nicholas

2007-01-01

further optimize biodosimetry specimen processing protocols in Connecticut. Based on our findings, we conclude that clinical laboratory professionals are an important resource for assisting with the processing biodosimetry specimens that are used for triage of patients from accidental or terrorist-related mass-casualty radiological or nuclear catastrophies. The approach described in this paper to enroll and train clinical laboratorians in sample preparation for dicentric analysis forms the basis for the next step (namely, further training on harvesting cultured cells and preparing cytogenetic slides) in collaborative efforts between the State of Connecticut's Biodosimetry Laboratory and the state's medical infrastructure towards building laboratory surge capacity to estimate radiation dose in victims of a mass casualty event

Radiological survey support activities for the decommissioning of the Ames Laboratory Research Reactor Facility, Ames, Iowa

Energy Technology Data Exchange (ETDEWEB)

Wynveen, R.A.; Smith, W.H.; Sholeen, C.M.; Justus, A.L.; Flynn, K.F.

1984-09-01

At the request of the Engineering Support Division of the US Department of Energy-Chicago Operations Office and in accordance with the programmatic overview/certification responsibilities of the Department of Energy Environmental and Safety Engineering Division, the Argonne National Laboratory Radiological Survey Group conducted a series of radiological measurements and tests at the Ames Laboratory Research Reactor located in Ames, Iowa. These measurements and tests were conducted during 1980 and 1981 while the reactor building was being decontaminated and decommissioned for the purpose of returning the building to general use. The results of these evaluations are included in this report. Although the surface contamination within the reactor building could presumably be reduced to negligible levels, the potential for airborne contamination from tritiated water vapor remains. This vapor emmanates from contamination within the concrete of the building and should be monitored until such time as it is reduced to background levels. 2 references, 8 figures, 6 tables.

Chemical Hygiene Plan for Onsite Measurement and Sample Shipping Facility Activities

International Nuclear Information System (INIS)

Price, W.H.

1998-01-01

This chemical hygiene plan presents the requirements established to ensure the protection of employee health while performing work in mobile laboratories, the sample shipping facility, and at the onsite radiological counting facility. This document presents the measures to be taken to promote safe work practices and to minimize worker exposure to hazardous chemicals. Specific hazardous chemicals present in the mobile laboratories, the sample shipping facility, and in the radiological counting facility are presented in Appendices A through G

Air kerma standardization for diagnostic radiology in a secondary standard laboratory

International Nuclear Information System (INIS)

Ramos, Manoel M.O.; Peixoto, J. Guilherme P.; Lopes, Ricardo T.

2009-01-01

The demand for calibration services and quality control in diagnostic radiology has grown in the country since the publication of the governmental regulation 453, issued by the Brazilian Ministry of Health in 1998. At that time, to produce results facing the new legislation, many laboratories used different standards and radiation qualities, some of which could be inadequate. The international standards neither supplied consistent radiation qualities and standardization for the different types of equipment available. This situation changed with the publication of the new edition of the IEC 61267 standard, published in 2005. The objective of this work was to implement the standardization of the air kerma for the unatenuated qualities (RQR) of IEC 61267 in the National Laboratory of Metrology of the Ionizing Radiations (LNMRI) of the Institute of Radiation Protection and Dosimetry (IRD). Technical procedures were developed together with uncertainty budget. Results of interlaboratory comparisons demonstrate that the quantity is standardized and internationally traceable. (author)

Radiological analysis of materials sampled on the old nuclear test site of In Ekker (Algeria)

International Nuclear Information System (INIS)

Chareyron, Bruno

2010-01-01

After having recalled the context of the French nuclear test campaign in Algeria between 1961 and 1966, this document reports and comments radiological measurements performed on the site of In Ekker, and also results of analysis performed in laboratory (contamination by cesium 137, americium 241, plutonium); recommendations are given

RA radiological characterization database application

International Nuclear Information System (INIS)

Steljic, M.M; Ljubenov, V.Lj. . E-mail address of corresponding author: milijanas@vin.bg.ac.yu; Steljic, M.M.)

2005-01-01

Radiological characterization of the RA research reactor is one of the main activities in the first two years of the reactor decommissioning project. The raw characterization data from direct measurements or laboratory analyses (defined within the existing sampling and measurement programme) have to be interpreted, organized and summarized in order to prepare the final characterization survey report. This report should be made so that the radiological condition of the entire site is completely and accurately shown with the radiological condition of the components clearly depicted. This paper presents an electronic database application, designed as a serviceable and efficient tool for characterization data storage, review and analysis, as well as for the reports generation. Relational database model was designed and the application is made by using Microsoft Access 2002 (SP1), a 32-bit RDBMS for the desktop and client/server database applications that run under Windows XP. (author)

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.

Results of the preliminary radiological survey at the former Diamond Magnesium Company site, Luckey, Ohio (DML001)

International Nuclear Information System (INIS)

Foley, R.D.; Crutcher, J.W.

1990-02-01

As part of the Formerly Utilized Sites Remedial Action Program, the US Department of Energy (DOE) is implementing a radiological survey program to determine the radiological conditions at sites that were used by the department's predecessor agencies. One such site is the former Diamond Magnesium Company facility in Luckey, Ohio. The preliminary radiological survey discussed in this report was conducted at the request of DOE by members of the Measurement Applications and Development group of Oak Ridge National Laboratory in December 1988. The former Diamond Magnesium Company site in Luckey, Ohio, was used as a magnesium reduction plant during World War 2. It was closed in 1945 and reopened in 1949 as a beryllium production facility, operated by Brush Wellman for the US Atomic Energy Commission. The preliminary radiological survey included: a surface gamma scan of part of the property outdoors, collection of surface and subsurface soil samples, and collection of water samples. Laboratory analysis of soil samples showed concentrations of 226 Ra in excess of applicable DOE guidelines. A follow-up, detailed survey is recommended. 9 refs., 10 figs., 4 tabs

Identification of chemical contamination in an aqueous sample using liquid chromatography with mass spectrometry during 2nd NATO mixed samples laboratory exercise

International Nuclear Information System (INIS)

Grolmusova, K.; Tkac, M.

2010-01-01

Biological and radiological screening was conducted to determine the type of biological and radiological contamination for a sample and the reference sample. Biological screening confirmed the presence of biological contamination. Radiological screening confirmed the presence of 235 U. Preliminary chemical screening military confirmed the presence of volatile chemicals (chemical warfare agents, CWA), but refute the presence of non-volatile CWA and their degradation products and precursors (1,2,3 directory Organization for the Prohibition of Chemical Weapons, OPCW). To carry out further analysis it was necessary to adjust the aqueous sample so that it minimizes the possibility of radiological contamination, while maintaining chemical contamination. To remove 235 U from the water sample for selective extraction of chemical contamination SCX cartridges (strong cation exchange) by solid phase extraction were used. To identify chemical contamination (from the list of substances 1, 2, 3 OPCW) GC-MS and LC-MS were used. LC-ESI-MS analysis has demonstrated the presence of unknown substance designated as Chemical A in an aqueous sample. LC-ESI-MS chromatograms of the reference sample, water sample and standard were compared. Unknown substance was identified on the basis of the correlation of retention times and MS spectra of unknown substance Chemical A and standard such as triethanolamine (TEA, a breakdown product of nitrogen mustard - HN 3 fabric from the list 3B17Y OPCW).

A Consistent System for Coding Laboratory Samples

Science.gov (United States)

Sih, John C.

1996-07-01

A formal laboratory coding system is presented to keep track of laboratory samples. Preliminary useful information regarding the sample (origin and history) is gained without consulting a research notebook. Since this system uses and retains the same research notebook page number for each new experiment (reaction), finding and distinguishing products (samples) of the same or different reactions becomes an easy task. Using this system multiple products generated from a single reaction can be identified and classified in a uniform fashion. Samples can be stored and filed according to stage and degree of purification, e.g. crude reaction mixtures, recrystallized samples, chromatographed or distilled products.

Radiological Calibration and Standards Facility

Data.gov (United States)

Federal Laboratory Consortium — PNNL maintains a state-of-the-art Radiological Calibration and Standards Laboratory on the Hanford Site at Richland, Washington. Laboratory staff provide expertise...

Comparability of river suspended-sediment sampling and laboratory analysis methods

Science.gov (United States)

Groten, Joel T.; Johnson, Gregory D.

2018-03-06

Accurate measurements of suspended sediment, a leading water-quality impairment in many Minnesota rivers, are important for managing and protecting water resources; however, water-quality standards for suspended sediment in Minnesota are based on grab field sampling and total suspended solids (TSS) laboratory analysis methods that have underrepresented concentrations of suspended sediment in rivers compared to U.S. Geological Survey equal-width-increment or equal-discharge-increment (EWDI) field sampling and suspended sediment concentration (SSC) laboratory analysis methods. Because of this underrepresentation, the U.S. Geological Survey, in collaboration with the Minnesota Pollution Control Agency, collected concurrent grab and EWDI samples at eight sites to compare results obtained using different combinations of field sampling and laboratory analysis methods.Study results determined that grab field sampling and TSS laboratory analysis results were biased substantially low compared to EWDI sampling and SSC laboratory analysis results, respectively. Differences in both field sampling and laboratory analysis methods caused grab and TSS methods to be biased substantially low. The difference in laboratory analysis methods was slightly greater than field sampling methods.Sand-sized particles had a strong effect on the comparability of the field sampling and laboratory analysis methods. These results indicated that grab field sampling and TSS laboratory analysis methods fail to capture most of the sand being transported by the stream. The results indicate there is less of a difference among samples collected with grab field sampling and analyzed for TSS and concentration of fines in SSC. Even though differences are present, the presence of strong correlations between SSC and TSS concentrations provides the opportunity to develop site specific relations to address transport processes not captured by grab field sampling and TSS laboratory analysis methods.

Sample requirements and design of an inter-laboratory trial for radiocarbon laboratories

International Nuclear Information System (INIS)

Bryant, Charlotte; Carmi, Israel; Cook, Gordon; Gulliksen, Steinar; Harkness, Doug; Heinemeier, Jan; McGee, Edward; Naysmith, Philip; Possnert, Goran; Scott, Marian; Plicht, Hans van der; Strydonck, Mark van

2000-01-01

An on-going inter-comparison programme which is focused on assessing and establishing consensus protocols to be applied in the identification, selection and sub-sampling of materials for subsequent 14 C analysis is described. The outcome of the programme will provide a detailed quantification of the uncertainties associated with 14 C measurements including the issues of accuracy and precision. Such projects have become recognised as a fundamental aspect of continuing laboratory quality assurance schemes, providing a mechanism for the harmonisation of measurements and for demonstrating the traceability of results. The design of this study and its rationale are described. In summary, a suite of core samples has been defined which will be made available to both AMS and radiometric laboratories. These core materials are representative of routinely dated material and their ages span the full range of the applied 14 C time-scale. Two of the samples are of wood from the German and Irish dendrochronologies, thus providing a direct connection to the master dendrochronological calibration curve. Further samples link this new inter-comparison to past studies. Sample size and precision have been identified as being of paramount importance in defining dating confidence, and so several core samples have been identified for more in-depth study of these practical issues. In addition to the core samples, optional samples have been identified and prepared specifically for either AMS and/or radiometric laboratories. For AMS laboratories, these include bone, textile, leather and parchment samples. Participation in the study requires a commitment to a minimum of 10 core analyses, with results to be returned within a year

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

International Nuclear Information System (INIS)

1980-12-01

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

Identification of chemical contamination in an aqueous sample using liquid chromatography with mass spectrometry during 2nd NATO mixed samples laboratory exercise

International Nuclear Information System (INIS)

Grolmusova, K.; Tkac, M.

2010-01-01

Biological and radiological screening was conducted on a sample and reference sample to determine the type of biological and radiological contamination. Biological screening confirmed the presence of biological contamination. Radiological screening confirmed the presence of 235 U. Preliminary chemical military screening confirmed the presence of volatile chemicals (chemical warfare agents, CWA), but refute the presence of non-volatile CWA and their degradation products and precursors (1,2,3 directory Organization for the Prohibition of Chemical Weapons, OPCW). To carry out further analysis it was necessary to adjust aqueous sample so that it minimizes the possibility of radiological contamination, while maintaining chemical contamination. To remove of 235 U from the water sample for selective extraction of chemical contamination by solid phase extraction (solid phase extraction - SPE) using SCX (strong cation exchange) cartridges were used. To identify chemical contamination (from the list of substances 1, 2, 3 OPCW) GC-MS and LC-MS were used. LC-ESI-MS analysis has demonstrated the presence of an unknown substance designated as Chemical A in an aqueous sample. LC-ESI-MS chromatograms of the reference sample, water sample and standard were compared. Unknown substance has been identified on the basis of the correlation of retention times and MS spectra of unknown substances - chemical A and standard such as triethanolamine (TEA, a breakdown product of nitrogen mustard - HN 3 fabric from the list 3B17Y OPCW).

Use of the Multi-Agency Radiological Laboratory Analytical Protocols Manual (MARLAP) for site cleanup activities

International Nuclear Information System (INIS)

Griggs, J.

1999-01-01

MARLAP is being developed as a multi-agency guidance manual for project managers and radioanalytical laboratories. The document uses a performance based approach and will provide guidance and a framework to assure that laboratory radioanalytical data meets the specific project or program needs and requirements. MARLAP supports a wide range of data collection activities including site characterization and compliance demonstration activities. Current participants include: US Environmental Protection Agency (EPA), US Department of Energy (DOE), US Nuclear Regulatory Commission (NRC), US Department of Defense (DoD), US National Institutes of Standards and Technology (NIST), US Geologic Survey (USGS), US Food and Drug Administration (FDA), Commonwealth of Kentucky, and the State of California. MARLAP is the radioanalytical laboratory counterpart to the Multi-Agency Radiological Survey and Site Investigation Manual (MARSSIM). MARLAP is currently in a preliminary draft stage. (author)

Assessment of eye lens doses in interventional radiology: a simulation in laboratory conditions

International Nuclear Information System (INIS)

Cemusova, Z.; Ekendahl, D.; Judas, L.

2016-01-01

As workers in interventional radiology belong to one of the most occupationally exposed groups, methods for sufficiently accurate quantification of their external exposure are sought. The objective of the authors' experiment was to investigate the relations between eye lens dose and H p (10), H p (3) or H p (0.07) values measured with a conventional whole-body personal thermoluminescence dosemeter (TLD). Conditions of occupational exposure during common interventional procedures were simulated in laboratory. An anthropomorphic phantom represented a physician. The TLDs were fixed to the phantom in different locations that are common for purposes of personal dosimetry. In order to monitor the dose at the eye lens level during the exposures, a special thermoluminescence eye dosemeter was fixed to the phantom's temple. Correlations between doses measured with the whole-body and the eye dosemeters were found. There are indications that personnel in interventional radiology do not need to be unconditionally equipped with additional eye dosemeters, especially if an appropriate whole-body dosimetry system has been already put into practice. (authors)

Laboratory Activity on Sample Handling and Maintaining a Laboratory Notebook through Simple pH Measurements

Science.gov (United States)

Erdmann, Mitzy A.; March, Joe L.

2016-01-01

Sample handling and laboratory notebook maintenance are necessary skills but can seem abstract if not presented to students in context. An introductory exercise focusing on proper sample handling, data collection and laboratory notebook keeping for the general chemistry laboratory was developed to emphasize the importance of keeping an accurate…

Open source laboratory sample rotator mixer and shaker

Directory of Open Access Journals (Sweden)

Karankumar C. Dhankani

2017-04-01

Full Text Available An open-source 3-D printable laboratory sample rotator mixer is developed here in two variants that allow users to opt for the level of functionality, cost saving and associated complexity needed in their laboratories. First, a laboratory sample rotator is designed and demonstrated that can be used for tumbling as well as gentle mixing of samples in a variety of tube sizes by mixing them horizontally, vertically, or any position in between. Changing the mixing angle is fast and convenient and requires no tools. This device is battery powered and can be easily transported to operate in various locations in a lab including desktops, benches, clean hoods, chemical hoods, cold rooms, glove boxes, incubators or biological hoods. Second, an on-board Arduino-based microcontroller is incorporated that adds the functionality of a laboratory sample shaker. These devices can be customized both mechanically and functionally as the user can simply select the operation mode on the switch or alter the code to perform custom experiments. The open source laboratory sample rotator mixer can be built by non-specialists for under US$30 and adding shaking functionality can be done for under $20 more. Thus, these open source devices are technically superior to the proprietary commercial equipment available on the market while saving over 90% of the costs.

Implementation of a DOD ELAP Conforming Quality System at a FUSRAP Site Field Temporary Radiological Screening Laboratory - 13500

International Nuclear Information System (INIS)

Winters, M.S.; McElheny, G.; Houston, L.M.; Masset, M.R.; Spector, H.L.

2013-01-01

A case study is presented on specific program elements that supported the transition of a temporary field radiological screening lab to an accredited operation capable of meeting client quality objectives for definitive results data. The temporary field lab is located at the Formerly Utilized Sites Remedial Action Program Linde Site in Tonawanda, NY. The site is undergoing remediation under the direction of the United States Army Corps of Engineers - Buffalo District, with Cabrera Services Inc. as the remediation contractor and operator of the on-site lab. Analysis methods employed in the on-site lab include gross counting of alpha and beta particle activity on swipes and air filters and gamma spectroscopy of soils and other solid samples. A discussion of key program elements and lessons learned may help other organizations considering pursuit of accreditation for on-site screening laboratories. (authors)

Effective sample labeling

International Nuclear Information System (INIS)

Rieger, J.T.; Bryce, R.W.

1990-01-01

Ground-water samples collected for hazardous-waste and radiological monitoring have come under strict regulatory and quality assurance requirements as a result of laws such as the Resource Conservation and Recovery Act. To comply with these laws, the labeling system used to identify environmental samples had to be upgraded to ensure proper handling and to protect collection personnel from exposure to sample contaminants and sample preservatives. The sample label now used as the Pacific Northwest Laboratory is a complete sample document. In the event other paperwork on a labeled sample were lost, the necessary information could be found on the label

Culture methods of allograft musculoskeletal tissue samples in Australian bacteriology laboratories.

Science.gov (United States)

Varettas, Kerry

2013-12-01

Samples of allograft musculoskeletal tissue are cultured by bacteriology laboratories to determine the presence of bacteria and fungi. In Australia, this testing is performed by 6 TGA-licensed clinical bacteriology laboratories with samples received from 10 tissue banks. Culture methods of swab and tissue samples employ a combination of solid agar and/or broth media to enhance micro-organism growth and maximise recovery. All six Australian laboratories receive Amies transport swabs and, except for one laboratory, a corresponding biopsy sample for testing. Three of the 6 laboratories culture at least one allograft sample directly onto solid agar. Only one laboratory did not use a broth culture for any sample received. An international literature review found that a similar combination of musculoskeletal tissue samples were cultured onto solid agar and/or broth media. Although variations of allograft musculoskeletal tissue samples, culture media and methods are used in Australian and international bacteriology laboratories, validation studies and method evaluations have challenged and supported their use in recovering fungi and aerobic and anaerobic bacteria.

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

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

International Nuclear Information System (INIS)

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

1994-12-01

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

Inter-laboratory exercise on steroid estrogens in aqueous samples

International Nuclear Information System (INIS)

Heath, E.; Kosjek, T.; Andersen, H.R.; Holten Luetzhoft, H.-C.; Adolfson Erici, M.; Coquery, M.; Duering, R.-A.; Gans, O.; Guignard, C.; Karlsson, P.; Manciot, F.; Moldovan, Z.; Patureau, D.; Cruceru, L.; Sacher, F.; Ledin, A.

2010-01-01

An inter-laboratory comparison exercise was organized among European laboratories, under the aegis of EU COST Action 636: 'Xenobiotics in Urban Water Cycle'. The objective was to evaluate the performance of testing laboratories determining 'Endocrine Disrupting Compounds' (EDC) in various aqueous matrices. As the main task three steroid estrogens: 17α-ethinylestradiol, 17β-estradiol and estrone were determined in four spiked aqueous matrices: tap water, river water and wastewater treatment plant influent and effluent using GC-MS and LC-MS/MS. Results were compared and discussed according to the analytical techniques applied, the accuracy and reproducibility of the analytical methods and the nature of the sample matrices. Overall, the results obtained in this inter-laboratory exercise reveal a high level of competence among the participating laboratories for the detection of steroid estrogens in water samples indicating that GC-MS as well as LC-MS/MS can equally be employed for the analysis of natural and synthetic hormones. - Herein are presented the results of the first international inter-laboratory study on determination of selected steroid hormones in environmental aqueous samples.

Methodology of ABNT ISO/IEC GUIA 25 implantation in the laboratories of radionuclides analysis in environmental samples of the Analysis Division/CNEN

International Nuclear Information System (INIS)

Oliveira, Josue Peter de

1997-07-01

The ISO/EEC Guide 25: 1993 Standard G eneral requirements for the competence of calibration and testing laboratories . Is published in Brazil by Brazilian Association for Technical Standards (ABNT) as ABNT ISO/DEC GUIA 25 and establishes general requirements a laboratory must demonstrate to meet, in order to be recognized as having technical competence (accreditation) to carry out specifics calibration or testing. Therefore, the accredited laboratory starts, respectively, taking part from the Brazilian Calibration Network (RBC) or from the Brazilian Testing Laboratories Network (RBLE) . The Environmental Radioanalysis Division (DIAMB) from Environmental Radiological Protection Department (DEPRA) from Institute of Radiation Protection and Dosimetry (IRD) from Brazilian National Nuclear Energy Commission (CNEN) is a laboratory responsible for analyzing radionuclides deriving for the samples from DEPRA's Surveillance Program, research and servings, due to an eventual radionuclide contamination in environment, foods and others raw materials for human consumption; including for importation and exportation products certification purposes. For all these reasons, DIAMB needs its formal recognition for carrying out radionuclides analysis in environmental samples. This work aims to provide a methodology in order to guide a laboratory which has the intention to implement a accreditation process. It also describes policies to meet the requirements related to the Standard, guidance needed to specification of some steps and also comments some points from the Standard in order to become easier all the accreditation process comprehension. (author)

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

International Nuclear Information System (INIS)

1995-09-01

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

Author Contribution to the Pu Handbook II: Chapter 37 LLNL Integrated Sample Preparation Glovebox (TEM) Section

Energy Technology Data Exchange (ETDEWEB)

Wall, Mark A. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

2016-10-25

The development of our Integrated Actinide Sample Preparation Laboratory (IASPL) commenced in 1998 driven by the need to perform transmission electron microscopy studies on naturally aged plutonium and its alloys looking for the microstructural effects of the radiological decay process (1). Remodeling and construction of a laboratory within the Chemistry and Materials Science Directorate facilities at LLNL was required to turn a standard radiological laboratory into a Radiological Materials Area (RMA) and Radiological Buffer Area (RBA) containing type I, II and III workplaces. Two inert atmosphere dry-train glove boxes with antechambers and entry/exit fumehoods (Figure 1), having a baseline atmosphere of 1 ppm oxygen and 1 ppm water vapor, a utility fumehood and a portable, and a third double-walled enclosure have been installed and commissioned. These capabilities, along with highly trained technical staff, facilitate the safe operation of sample preparation processes and instrumentation, and sample handling while minimizing oxidation or corrosion of the plutonium. In addition, we are currently developing the capability to safely transfer small metallographically prepared samples to a mini-SEM for microstructural imaging and chemical analysis. The gloveboxes continue to be the most crucial element of the laboratory allowing nearly oxide-free sample preparation for a wide variety of LLNL-based characterization experiments, which includes transmission electron microscopy, electron energy loss spectroscopy, optical microscopy, electrical resistivity, ion implantation, X-ray diffraction and absorption, magnetometry, metrological surface measurements, high-pressure diamond anvil cell equation-of-state, phonon dispersion measurements, X-ray absorption and emission spectroscopy, and differential scanning calorimetry. The sample preparation and materials processing capabilities in the IASPL have also facilitated experimentation at world-class facilities such as the

Author Contribution to the Pu Handbook II: Chapter 37 LLNL Integrated Sample Preparation Glovebox (TEM) Section

International Nuclear Information System (INIS)

Wall, Mark A.

2016-01-01

The development of our Integrated Actinide Sample Preparation Laboratory (IASPL) commenced in 1998 driven by the need to perform transmission electron microscopy studies on naturally aged plutonium and its alloys looking for the microstructural effects of the radiological decay process (1). Remodeling and construction of a laboratory within the Chemistry and Materials Science Directorate facilities at LLNL was required to turn a standard radiological laboratory into a Radiological Materials Area (RMA) and Radiological Buffer Area (RBA) containing type I, II and III workplaces. Two inert atmosphere dry-train glove boxes with antechambers and entry/exit fumehoods (Figure 1), having a baseline atmosphere of 1 ppm oxygen and 1 ppm water vapor, a utility fumehood and a portable, and a third double-walled enclosure have been installed and commissioned. These capabilities, along with highly trained technical staff, facilitate the safe operation of sample preparation processes and instrumentation, and sample handling while minimizing oxidation or corrosion of the plutonium. In addition, we are currently developing the capability to safely transfer small metallographically prepared samples to a mini-SEM for microstructural imaging and chemical analysis. The gloveboxes continue to be the most crucial element of the laboratory allowing nearly oxide-free sample preparation for a wide variety of LLNL-based characterization experiments, which includes transmission electron microscopy, electron energy loss spectroscopy, optical microscopy, electrical resistivity, ion implantation, X-ray diffraction and absorption, magnetometry, metrological surface measurements, high-pressure diamond anvil cell equation-of-state, phonon dispersion measurements, X-ray absorption and emission spectroscopy, and differential scanning calorimetry. The sample preparation and materials processing capabilities in the IASPL have also facilitated experimentation at world-class facilities such as the

Radiological characterisation on V1 NPP technological systems and buildings - Contamination

International Nuclear Information System (INIS)

Hanzel, Richard; Rapant, Tibor; Svitek, Jaroslav

2012-01-01

: average dose rate, maximum dose rate, average surface contamination of floor and walls and possible identified higher local surface contamination. In the scope of the project, more than 3400 direct dose rates measurements, 1450 direct surface contamination measurements, 1200 laboratory alpha/beta/gamma analysis of outer surfaces, 560 sample analysis of primary circuit technological equipment inner surface, 20 in situ gamma spectrometric measurements and 15 sample analysis of concrete drilling cores, have been performed. Final list of RNV included 8 vectors for contamination. Radiological data of individual items in DDB have been used for determination of total radiological inventory of V1 NPP. (authors)

Law No.12.069 clinical analyses laboratories and radiological surgery it state included into retirement rules to workers from particularly establishment

International Nuclear Information System (INIS)

1953-01-01

It is declared understood in the pension laws that manage the Jubilations and Pensions Office of the Industry and Commerce the personnel that has lent or lend services in the Laboratories of Clinical analysis and in clinics radiological matters [es

Inter-laboratory exercise on steroid estrogens in aqueous samples

Energy Technology Data Exchange (ETDEWEB)

Heath, E., E-mail: ester.heath@ijs.s [Department of Environmental Sciences, Jozef Stefan Institute, Jamova 39, 1000 Ljubljana (Slovenia); Kosjek, T. [Department of Environmental Sciences, Jozef Stefan Institute, Jamova 39, 1000 Ljubljana (Slovenia); Andersen, H.R.; Holten Luetzhoft, H.-C. [Department of Environmental Engineering, Technical University of Denmark, Miljoevej 113, DK-2800 Kgs. Lyngby (Denmark); Adolfson Erici, M. [Stockholm University, ITM SE-106 91 Stockholm (Sweden); Coquery, M. [Cemagref, U.R. QELY, F-69336 Lyon (France); Duering, R.-A. [Giessen University, Institute of Soil Science and Soil Conservation, Giessen (Germany); Gans, O. [Umweltbundesamt GmbH, Unit Organic Analysis, Spittelauer Laende 5, 1090 Vienna (Austria); Guignard, C. [CRP Gabriel Lippmann, EVA, 41 rue du Brill, L-4422 Belvaux (Luxembourg); Karlsson, P. [Lantmannen Analycen AB, Research and Development, Sjoehagsgatan 3 Box 905, 5319, Lidkoeping (Sweden); Manciot, F. [CAE VEOLIA ENVIRONMENT, 1 Place de Turenne, 94417 Saint Maurice Cedex (France); Moldovan, Z. [National Institute of Research and Development for Isotopic and Molecular Technology, Mass Spectrometry Department, Str. Donath 65-103, 400293 Cluj-Napoca (Romania); Patureau, D. [INRA, UR50, Laboratoire de Biotechnologie de l' Environnemet (LBE), Avenue des etangs, F-11100 Narbonne (France); Cruceru, L. [Pollution Control Department, National Research Institute for Industrial Ecology (ECOIND), Sos.Panduri 90-92, sector 5, Bucharest (Romania); Sacher, F. [DVGW-Technologiezentrum Wasser, Karlsruher Strasse 84, 76139 Karlsruhe (Germany); Ledin, A. [Department of Environmental Engineering, Technical University of Denmark, Miljoevej 113, DK-2800 Kgs. Lyngby (Denmark)

2010-03-15

An inter-laboratory comparison exercise was organized among European laboratories, under the aegis of EU COST Action 636: 'Xenobiotics in Urban Water Cycle'. The objective was to evaluate the performance of testing laboratories determining 'Endocrine Disrupting Compounds' (EDC) in various aqueous matrices. As the main task three steroid estrogens: 17alpha-ethinylestradiol, 17beta-estradiol and estrone were determined in four spiked aqueous matrices: tap water, river water and wastewater treatment plant influent and effluent using GC-MS and LC-MS/MS. Results were compared and discussed according to the analytical techniques applied, the accuracy and reproducibility of the analytical methods and the nature of the sample matrices. Overall, the results obtained in this inter-laboratory exercise reveal a high level of competence among the participating laboratories for the detection of steroid estrogens in water samples indicating that GC-MS as well as LC-MS/MS can equally be employed for the analysis of natural and synthetic hormones. - Herein are presented the results of the first international inter-laboratory study on determination of selected steroid hormones in environmental aqueous samples.

Radiological Control Manual. Revision 0, January 1993

Energy Technology Data Exchange (ETDEWEB)

1993-04-01

This manual has been prepared by Lawrence Berkeley Laboratory to provide guidance for site-specific additions, supplements, and clarifications to the DOE Radiological Control Manual. The guidance provided in this manual is based on the requirements given in Title 10 Code of Federal Regulations Part 835, Radiation Protection for Occupational Workers, DOE Order 5480.11, Radiation Protection for Occupational Workers, and the DOE Radiological Control Manual. The topics covered are (1) excellence in radiological control, (2) radiological standards, (3) conduct of radiological work, (4) radioactive materials, (5) radiological health support operations, (6) training and qualification, and (7) radiological records.

50 Years of the Radiological Research Accelerator Facility (RARAF)

OpenAIRE

Marino, Stephen A.

2017-01-01

The Radiological Research Accelerator Facility (RARAF) is in its 50th year of operation. It was commissioned on April 1, 1967 as a collaboration between the Radiological Research Laboratory (RRL) of Columbia University, and members of the Medical Research Center of Brookhaven National Laboratory (BNL). It was initially funded as a user facility for radiobiology and radiological physics, concentrating on monoenergetic neutrons. Facilities for irradiation with MeV light charged particles were d...

Enviromental sampling at remote sites based on radiological screening assessments

International Nuclear Information System (INIS)

Ebinger, M.H.; Hansen, W.R.; Wenz, G.; Oxenberg, T.P.

1996-01-01

Environmental radiation monitoring (ERM) data from remote sites on the White Sands Missile Range, New Mexico, were used to estimate doses to humans and terrestrial mammals from residual radiation deposited during testing of components containing depleted uranium (DU) and thorium (Th). ERM data were used with the DOE code RESRAD and a simple steady-state pathway code to estimate the potential adverse effects from DU and Th to workers in the contaminated zones, to hunters consuming animals from the contaminated zones, and to terrestrial mammals that inhabit the contaminated zones. Assessments of zones contaminated with DU and Th and DU alone were conducted. Radiological doses from Th and DU in soils were largest with a maximum of about 3.5 mrem y -1 in humans and maximum of about 0.1 mrad d -1 in deer. Dose estimates from DU alone in soils were significantly less with a maximum of about 1 mrem y -1 in humans and about 0.04 mrad d -1 in deer. The results of the dose estimates suggest strongly that environmental sampling in these affected areas can be infrequent and still provide adequate assessments of radiological doses to workers, hunters, and terrestrial mammals

Radiological design of hot laboratories

International Nuclear Information System (INIS)

Unruh, C.M.

1976-04-01

The fundamental design objectives for a laboratory where work with highly radioactive and highly toxic materials, such as plutonium and transplutonium nuclides, is performed are (1) to accomplish the purpose of the laboratory; (2) to protect the environment, (3) to provide safe working conditions; and (4) to keep radiation exposure to staff as low as practicable. The major planning and design features of a well engineered plutonium or transplutonium laboratory are given

Radiological design of hot laboratories

International Nuclear Information System (INIS)

Unruh, C.M.

1976-01-01

The fundamental design objectives for a laboratory where work with highly radioactive and highly toxic materials, such as plutonium and transplutonium nuclides, is performed, are (1) to accomplish the purpose of the laboratory, (2) to protect the environment, (3) to provide safe working conditions, and (4) to keep radiation exposure to staff as low as practicable. The major planning and design features of well-engineered plutonium or transplutonium laboratory are given. (author)

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

International Nuclear Information System (INIS)

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

1984-01-01

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

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

Best practice guide for radioactivity measurement laboratories in a post-accident situation

International Nuclear Information System (INIS)

2011-01-01

Published for laboratories likely to be asked to perform radioactivity measurements at the time of or after a radiological or nuclear accident in France or abroad, this guide aims at defining the best practices in terms of laboratory organisation (sample flow management, personnel radioprotection, sample identification and recording, sample cross-contamination risks, result transmission, archiving of data, results and samples, waste dismissal), and in terms of metrology (adaptation to needs in terms of detection limit and measurement uncertainty, preferred use of gamma spectrometry, analysis strategies)

Results of the Radiological Survey at Conviber, Inc., 644 Garfield Street, Springdale, Pennsylvania (CVP001)

International Nuclear Information System (INIS)

Foley, R.D.; Cottrell, W.D.; Crutcher, J.W.

1991-10-01

As part of the Formerly Utilized Sites Remedial Action Program (FUSRAP), the US Department of Energy (DOE) is implementing a radiological survey program to determine the radiological conditions at sites that were used by the department's predecessor agencies. During the mid-1940s, and possibly continuing until 1951, the Conviber site in Springdale, Pennsylvania, was used to machine extruded uranium in support of government efforts. In 1980 a radiological scanning survey of this site was conducted by DOE and Argonne National Laboratory (ANL) staffs. Their report noted one anomaly: elevated radiation levels over a small area inside the building where uranium had been machined. Because much of the floor was inaccessible, for surveying and because of the lack of definitive records documenting use of this site, a comprehensive radiological assessment was recommended. The radiological survey discussed in this report for the site of Conviber, Inc., Springdale, Pennsylvania, was conducted by members of the Measurement Applications and Development Group of Oak Ridge National Laboratory in June of 1989. The survey included a surface gamma scan, collection of concrete and soil samples, and measurement of direct and removable alpha and beta-gamma contamination. One indoor location with a gamma measurement of 20 μR/h was found. In June of 1990 ORNL staff returned to investigate the location with elevated gamma. A hole was drilled through the concrete, gamma measurements were taken, and soil samples were obtained for analyses. In these eight indoor soil samples, concentrations of 238 U ranged from 90 to 20,000 pCi/g. However, under current site use, residual uranium covered by concrete does not pose a health risk

Site characterization report for Building 3506 at Oak Ridge National Laboratory, Oak Ridge, Tennessee. Environmental Restoration Program

Energy Technology Data Exchange (ETDEWEB)

1994-07-01

Building 3506, also known as the Waste Evaporator Facility, is a surplus facility at Oak Ridge National Laboratory (ORNL) slated for decontamination and decommissioning (D&D). The building is located in the ORNL main plant area, to the west of the South Tank Farm and near the intersection of Central Avenue and Third Street. Characterization tasks consisted of three main activities: inspections, radiological measurements, and radiological and chemical sampling and analysis. Inspection reports document general facility conditions, as-built information, and specialized information such as structural evaluations. Radiological measurements define the quantity and distribution of radioactive contaminants; this information is used to calibrate a dose model of the facility and estimate the total activity, in curies, of each major radioactive isotope. The radiological information from sample analyses is used to refine the radiological model of the facility, and the radionuclide and hazardous chemical analyses are used for waste management planning. This report presents data from the field investigation and laboratory analyses in the form of a site description, as-built drawings, summary tables of radiological and chemical contaminant concentrations, and a waste volume estimate.

Site characterization report for Building 3506 at Oak Ridge National Laboratory, Oak Ridge, Tennessee. Environmental Restoration Program

International Nuclear Information System (INIS)

1994-07-01

Building 3506, also known as the Waste Evaporator Facility, is a surplus facility at Oak Ridge National Laboratory (ORNL) slated for decontamination and decommissioning (D ampersand D). The building is located in the ORNL main plant area, to the west of the South Tank Farm and near the intersection of Central Avenue and Third Street. Characterization tasks consisted of three main activities: inspections, radiological measurements, and radiological and chemical sampling and analysis. Inspection reports document general facility conditions, as-built information, and specialized information such as structural evaluations. Radiological measurements define the quantity and distribution of radioactive contaminants; this information is used to calibrate a dose model of the facility and estimate the total activity, in curies, of each major radioactive isotope. The radiological information from sample analyses is used to refine the radiological model of the facility, and the radionuclide and hazardous chemical analyses are used for waste management planning. This report presents data from the field investigation and laboratory analyses in the form of a site description, as-built drawings, summary tables of radiological and chemical contaminant concentrations, and a waste volume estimate

Analysis and radiological assessment of survey results and samples from the beaches around Sellafield

International Nuclear Information System (INIS)

Webb, G.A.M.; Fry, F.A.

1983-12-01

After radioactive sea debris had been found on beaches near the BNFL, Sellafield, plant, NRPB was asked by the Department of the Environment to analyse some of the samples collected and to assess the radiological hazard to members of the public. A report is presented containing an analysis of survey reports for the period 19 November - 4 December 1983 and preliminary results of the analysis of all samples received, together with the Board's recommendations. (author)

Radioactive wastes management in a radiochemistry laboratory

International Nuclear Information System (INIS)

Silva, Ana C.A.; Pereira, Wagner de S; Py Junior, Delcy de A.; Antunes, Ivan M.; Kelecom, Alphonse

2009-01-01

The Laboratorio de Monitoracao Ambiental (AMB) of the Unidade de Tratamento de Minerio (UTM) belonging to the Industrias Nucleares do Brasil is a chemical, radiochemical and radiometric laboratory, that analyses the natural radionuclides present in samples coming from the various installation of Industrias Nucleares do Brasil (INB). To minimize the radiological environmental impact, that laboratory has adopted a washing system of the chapel exhausting, that recirculate the washing water. These water can accumulate the radionuclides coming from the samples, that are liberated together the exhaustion gases from the chapels. Also, the water coming from the analyses and the sample releases (environmental and of the process) represent the liquid effluents of the AMB. The release of this effluent must pass by chemical and radiological criteria. From the radiological viewpoint, that release must be based on the Brazilian Nuclear Energy Commission (CNEN) regulations. This work try to establish the monitoring frequency, the radionuclides to be analysed, the form of liberation of those effluents, and the analytical techniques to be used. The radionuclides to be analysed will be U-nat, Ra-226 and Pb-210, of the uranium series, and the Th-232 and Ra-228, of the thorium series. The effluents must be monitored either before the release or, at least, twice a year. The effluents considered radioactive wastes, will be send to waste dam by the radioprotection service, or to the effluent treatment for controlled liberation for the environment

Aerial radiological survey of the Argonne National Laboratory and surrounding area, Argonne, Illinois. Date of survey: May 1977

International Nuclear Information System (INIS)

1982-12-01

An aerial radiological survey was conducted over the facilities of the Argonne National Laboratory in Argonne, Illinois, on 2 to 13 May 1977. The survey was flown at an altitude of 46 m by a helicopter containing 20 sodium iodide detectors. The line spacing was also 46 m. Enhanced gamma exposure rate levels, which could be attributed to Argonne operations, were observed at many locations

Direct visualization of solute locations in laboratory ice samples

Directory of Open Access Journals (Sweden)

T. Hullar

2016-09-01

Full Text Available Many important chemical reactions occur in polar snow, where solutes may be present in several reservoirs, including at the air–ice interface and in liquid-like regions within the ice matrix. Some recent laboratory studies suggest chemical reaction rates may differ in these two reservoirs. While investigations have examined where solutes are found in natural snow and ice, few studies have examined either solute locations in laboratory samples or the possible factors controlling solute segregation. To address this, we used micro-computed tomography (microCT to examine solute locations in ice samples prepared from either aqueous cesium chloride (CsCl or rose bengal solutions that were frozen using several different methods. Samples frozen in a laboratory freezer had the largest liquid-like inclusions and air bubbles, while samples frozen in a custom freeze chamber had somewhat smaller air bubbles and inclusions; in contrast, samples frozen in liquid nitrogen showed much smaller concentrated inclusions and air bubbles, only slightly larger than the resolution limit of our images (∼ 2 µm. Freezing solutions in plastic vs. glass vials had significant impacts on the sample structure, perhaps because the poor heat conductivity of plastic vials changes how heat is removed from the sample as it cools. Similarly, the choice of solute had a significant impact on sample structure, with rose bengal solutions yielding smaller inclusions and air bubbles compared to CsCl solutions frozen using the same method. Additional experiments using higher-resolution imaging of an ice sample show that CsCl moves in a thermal gradient, supporting the idea that the solutes in ice are present in mobile liquid-like regions. Our work shows that the structure of laboratory ice samples, including the location of solutes, is sensitive to the freezing method, sample container, and solute characteristics, requiring careful experimental design and interpretation of results.

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

Energy Technology Data Exchange (ETDEWEB)

1994-03-01

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

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

International Nuclear Information System (INIS)

1994-03-01

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

Comparison of clinico-radiological features of patients with positive cultures of nontuberculous mycobacteria and patients with tuberculosis

International Nuclear Information System (INIS)

Ba-Hammam, Ahmed; Sharif, Yasir; Masood, Mohammad; Isnani, Arthur; Youssef, Ismael; Kambal, Abdelmageed; Shaikh, Shaffi

2005-01-01

To identify the clinico-radiological features of patients with positive cultures for nontuberculous mycobacteria (NTM) and compare those to a sample of patients with tuberculosis (MTB). A laboratory database was used to retrieve all specimens submitted to King Khalid University Hospital, Riyadh, mycobacteriology laboratory for mycobacterial smears and cultures during the period from October 1999-April 2002. Using this database, the original records of the mycobacteriology laboratory and a review of the patient's health records, a standard proforma was completed that included demographic, clinical, radiological and laboratory information on patients included in this study. The patients were divided into 2 groups; the NTM group, which included patients with positive cultures for NTM and the MTB group, which included a sample of patients with documented tuberculosis. During the study period, 286 patients had positive mycobacterial cultures. Seventy patients (24.5%) grew NTM and 216 (75.5%) grew MTB. For patients with MTB, 54 patients were included as per the selection protocol of the study. There was no difference between the 2 groups in all measured demographic variables. The presence of weight loss and fever was significantly more in the MTB group. Radiologically, the presence of hilar adenopathy was more significant among patients with MTB than those with NTM (17% versus 4%, p=0.02). However, bronchiectatic changes were seen significantly more among NTM patients compared to patients with MTB (26% versus 11%, p=0.03). The isolation of NTM in the mycobacteriology laboratory is high. The clinico-radiological features were not sufficiently specific to differentiate patients with NTM from patients with MTB. Local studies are needed to explore NTM disease in various developing countries and identify the NTM species causing infections in non-immunosuppressed patients in each locality. (author)

Aerial radiological survey of the Fermi National accelerator Laboratory and surrounding area, Batavia, Illinois. Data of survey: 12-14 May 1977

International Nuclear Information System (INIS)

Jobst, J.E.

1981-01-01

An aerial radiological survey was conducted over the facilities of the Fermi National Accelerator Laboratory (Fermilab) near Batavia, Illinois on 12-14 May 1977. The survey was flown at an altitude of 91 m by a helicopter containing 20 sodium iodide detectors. The line spacing was also 91 m. Enhanced gamma exposure rate levels, which could be attributed to Fermilab operations, were observed at seven locations. One additional anomaly, not related to the Laboratory, was also discovered

The Radiological Research Accelerator Facility

International Nuclear Information System (INIS)

Hall, E.J.; Marino, S.A.

1990-07-01

The Radiological Research Accelerator Facility (RARAF) is based on a 4-MV Van de Graaff accelerator, which is used to generate a variety of well-characterized radiation beams for research in radiobiology, radiological physics, and radiation chemistry. It is part of the Center for Radiological Research (CRR) -- formerly the Radiological Research Laboratory (RRL) -- of Columbia University, and its operation is supported as a National Facility by the US Department of Energy (DOE). Fifteen different experiments were run during these 12 months, approximately the same as the previous two years. Brief summaries of each experiment are included. Accelerator usage is summarized and development activities are discussed. 7 refs., 4 tabs

Mobile spectrometric laboratory

International Nuclear Information System (INIS)

Isajenko, K.A.; Lipinski, P.

2002-01-01

The article presents the Mobile Spectrometric Laboratory used by Central Laboratory for Radiological Protection since year 2000. The equipment installed in the Mobile Laboratory and its uses is described. The results of international exercises and intercalibrations, in which the Laboratory participated are presented. (author)

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

Inter-laboratory exercise on steroid estrogens in aqueous samples

DEFF Research Database (Denmark)

Heath, E.; Kosjek, T.; Andersen, Henrik Rasmus

2010-01-01

to the analytical techniques applied, the accuracy and reproducibility of the analytical methods and the nature of the sample matrices. Overall, the results obtained in this inter-laboratory exercise reveal a high level of competence among the participating laboratories for the detection of steroid estrogens......An inter-laboratory comparison exercise was organized among European laboratories, under the aegis of EU COST Action 636: "Xenobiotics in Urban Water Cycle" The objective was to evaluate the performance of testing laboratories determining "Endocrine Disrupting Compounds" (EDC) in various aqueous...

Comparison of leach results from field and laboratory prepared samples

International Nuclear Information System (INIS)

Oblath, S.B.; Langton, C.A.

1985-01-01

The leach behavior of saltstone prepared in the laboratory agrees well with that from samples mixed in the field using the Littleford mixer. Leach rates of nitrates and cesium from the current reference formulation saltstone were compared. The laboratory samples were prepared using simulated salt solution; those in the field used Tank 50 decontaminated supernate. For both nitrate and cesium, the field and laboratory samples showed nearly identical leach rates for the first 30 to 50 days. For the remaining period of the test, the field samples showed higher leach rates with the maximum difference being less than a factor of three. Ruthenium and antimony were present in the Tank 50 supernate in known amounts. Antimony-125 was observed in the leachate and a fractional leach rate was calculated to be at least a factor of ten less than that of 137 Cs. No 106 Ru was observed in the leachate, and the release rate was not calculated. However, based on the detection limits for the analysis, the ruthenium leach rate must also be at least a factor of ten less than cesium. These data are the first measurements of the leach rates of Ru and Sb from saltstone. The nitrate leach rates for these samples were 5 x 10 -5 grams of nitrate per square cm per day after 100 days for the laboratory samples and after 200 days for the field samples. These values are consistent with the previously measured leach rates for reference formulation saltstone. The relative standard deviation in the leach rate is about 15% for the field samples, which all were produced from one batch of saltstone, and about 35% for the laboratory samples, which came from different batches. These are the first recorded estimates of the error in leach rates for saltstone

Laboratory waste minimization during the operation startup phase

International Nuclear Information System (INIS)

Morrison, J.A.

1995-05-01

The Waste Sampling and Characterization Facility (WSCF) Laboratory was opened for occupancy in October, 1994. It is the first of its kind on the Hanford Site, a low level lab located in an area of high level radiological material. The mission of the facility is to analyze process samples from two on-line effluent treatment plants. One of these plants is operating and the other is due to begin operations by the end of 1995. The VSCF also performs air sampling analysis for routine radiological surveillance filter papers drawn from around the Hanford Site. Because this type of laboratory had not been in operation before, there was only speculation about the types and amounts of waste that would be generated. The laboratory personnel assigned to WSCF were assembled from existing labs on the Hanford Site and from outside the Hanford Site community. For some, it was a first time experience working on a site where a twenty mile drive is sometimes required to visit another building. For others, it was a change in the way business is conducted using state-of-the-art equipment, a new building, and a chance to approach issues as a team from the beginning. It is how this team came together and the issues that were discussed, sometimes uncomfortably, that lead to the current success. The outcome of this process is discussed in this paper

Air and smear sample calculational tool for Fluor Hanford Radiological control

International Nuclear Information System (INIS)

BAUMANN, B.L.

2003-01-01

A spreadsheet calculation tool was developed to automate the calculations performed for determining the concentration of airborne radioactivity and smear counting as outlined in HNF--13536, Section 5.2.7, ''Analyzing Air and Smear Samples''. This document reports on the design and testing of the calculation tool. Radiological Control Technicians (RCTs) will save time and reduce hand written and calculation errors by using an electronic form for documenting and calculating work place air samples. Current expectations are RCTs will perform an air sample and collect the filter or perform a smear for surface contamination. RCTs will then survey the filter for gross alpha and beta/gamma radioactivity and with the gross counts utilize either hand calculation method or a calculator to determine activity on the filter. The electronic form will allow the RCT with a few key strokes to document the individual's name, payroll, gross counts, instrument identifiers; produce an error free record. This productivity gain is realized by the enhanced ability to perform mathematical calculations electronically (reducing errors) and at the same time, documenting the air sample

Analytical laboratory and mobile sampling platform

International Nuclear Information System (INIS)

Stetzenbach, K.; Smiecinski, A.

1996-01-01

This is the final report for the Analytical Laboratory and Mobile Sampling Platform project. This report contains only major findings and conclusions resulting from this project. Detailed reports of all activities performed for this project were provided to the Project Office every quarter since the beginning of the project. This report contains water chemistry data for samples collected in the Nevada section of Death Valley National Park (Triangle Area Springs), Nevada Test Site springs, Pahranagat Valley springs, Nevada Test Site wells, Spring Mountain springs and Crater Flat and Amargosa Valley wells

Radiological analysis of environmental samples in some points of the coast of the Gulf of Mexico and Coast of Quintana Roo, Mexico

International Nuclear Information System (INIS)

Salas Mar, Bernardo; Martinez Negrete, Marco Antonio; Ruiz Chavarria, Gerardo; Abarca Munguia, Jose

2008-01-01

Full text: We describe in this paper the results obtained by the project 'Radiological analysis of environmental samples in some points of the coast of the Gulf of Mexico and coast of Quintana Roo, Mexico'. The purpose of the study is to identify and quantify the natural and anthropogenic radionuclides present from sediments, sand and seawater from several sites located along the coast of the Gulf of Mexico and the Caribean Sea. The samples are analysed in a Canberra Multichannel analyzer system for gamma spectrometry, equipped with a detector of hyper pure germanium and a Genie 2000 software, in the 'Laboratory of Radiological Analysis of Environmental Samples', belonging to the Physics Department, Faculty of Sciences, National Autonomous University of Mexico (UNAM). The geographic sites were samples were taken include the states of Tamaulipas, Veracruz, Tabasco, Campeche, Yucatan and Quintana Roo. The results of this studies will be published at the end of the project and we hope they will be useful for the national health and industrial sectors. Until now we have identified and measured the presence of natural radionuclides such as Potassium-40 (K-40), Bismuth 212 (Bi-212), Lead-212 (Pb-212), Bismuth-214 (Bi-214), Lead-214 (Pb-214), Radium-226 (Ra-226), Actinium 228 (Ac-228), Uranium-235 (U-235), as well as some anthropogenic radionuclides found near the Laguna Verde Nuclear Power Plant. The project is scheduled to last for three years, finishing in 2009. At its ending we shall be able to present conclusions and identify some tendencies, in connection with the background and possible radioactive contamination of the studied zones. This project takes place under the auspice of the 'Program of Support to Projects of Research and Technological Innovation' of the National Autonomous University of Mexico. (author)

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

International Nuclear Information System (INIS)

Fritzsche, A.E.

1993-02-01

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

The role of the Secondary Laboratory of Dosimetric calibration in the implementation of the dosimetric magnitudes with radiological protection aims

International Nuclear Information System (INIS)

Perez Medina O, V.; Alvarez R, J.T.; Tovar M, V.M.

2006-01-01

It is very well-known the paper of the net of secondary laboratories of dosimetric calibration of the OAS in the dissemination of the traceability of the dosimetric magnitudes: kerma in air and absorbed dose in water, to the radiotherapy departments, given the high accuracy and precision that require the radiotherapy treatments. However the LSCD has other important areas at least for the development, implementation and evaluation of dosimetric magnitudes denominated operative magnitudes with ends of radiological protection: environmental equivalent dose H*(10), directional equivalent dose H'(0.07) and personal equivalent dose Hp. In the case of radiological protection the LSCD-ININ has been implementing the infrastructure to give service of personal dosimetry for photons and beta particles in terms of the operative magnitudes. For photons: X and gamma rays, it account with a secondary pattern camera PTW T34035 gauged in H * and Hp in the primary laboratory of Germany PTB. For the case of beta radiation its account with an extrapolation camera PTW 23392 with a secondary pattern kit of sources of the type I, gauged in terms of H'(0.07) in the PTB. (Author)

The Viking X ray fluorescence experiment - Sampling strategies and laboratory simulations. [Mars soil sampling

Science.gov (United States)

Baird, A. K.; Castro, A. J.; Clark, B. C.; Toulmin, P., III; Rose, H., Jr.; Keil, K.; Gooding, J. L.

1977-01-01

Ten samples of Mars regolith material (six on Viking Lander 1 and four on Viking Lander 2) have been delivered to the X ray fluorescence spectrometers as of March 31, 1977. An additional six samples at least are planned for acquisition in the remaining Extended Mission (to January 1979) for each lander. All samples acquired are Martian fines from the near surface (less than 6-cm depth) of the landing sites except the latest on Viking Lander 1, which is fine material from the bottom of a trench dug to a depth of 25 cm. Several attempts on each lander to acquire fresh rock material (in pebble sizes) for analysis have yielded only cemented surface crustal material (duricrust). Laboratory simulation and experimentation are required both for mission planning of sampling and for interpretation of data returned from Mars. This paper is concerned with the rationale for sample site selections, surface sampler operations, and the supportive laboratory studies needed to interpret X ray results from Mars.

Status of SRNL radiological field lysimeter experiment-Year 1

Energy Technology Data Exchange (ETDEWEB)

Kaplan, D. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Roberts, K. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Bagwell, L. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

2013-10-01

The Savannah River National Laboratory (SRNL) Radiological Field Lysimeter Experiment is a one-of-a-kind field facility designed to study radionuclide geochemical processes at a larger spatial scale (from grams to tens of kilograms sediment) and temporal scale (from months to 10 years) than is readily afforded through laboratory studies. The lysimeter facility is intended to capture the natural heterogeneity of moisture and temperature regimes in the vadose zone, the unsaturated subsurface region between the surface soil and the underlying aquifer. The 48 lysimeter columns, which contain various radionuclides (and stable iodine), were opened to rainfall infiltration on July 5, 2012. The objective of this report is to provide a status of the lysimeter facility operations and to compile data collected during FY13, including leachate volume, rainfall, and soil moisture and temperature in situ probe data. Radiological leachate data are not presented in this document but will be the subject of a separate document.1 Leachate samples were collected quarterly and shipped to Clemson University for radiological analyses. Rainfall, leachate volume, moisture and temperature probe data were collected continuously. During operations of the facility this year, there were four safety or technical concerns that required additional maintenance: 1) radioactivity was detected in one of the overflow bottles (captured water collected from the secondary containment that does not come in contact with the radiological source material); 2) rainwater accumulated within the sample-bottle storage sheds; 3) overflow containers collected more liquid than anticipated; and 4) significant spider infestation occurred in the sample-bottle storage sheds. To address the first three concerns, each of the lysimeter columns was re-plumbed to improve and to minimize the number of joint unions. To address the fourth concern regarding spiders, new sample-bottle water sheds were purchased and a pest control

Design of laboratory and animal housing unit for radionuclide studies

International Nuclear Information System (INIS)

Anon.

1975-01-01

The design of a combined analytical laboratory and animal housing facility is discussed. By having sample processing facilities in close proximity to the experimental animals, the necessity for transporting biological specimens long distances has been curtailed. In addition, complete radionuclide counting equipment has been installed so that samples need not leave the animal housing site for analysis, a feature based on radiological health requirements. (U.S.)

Sample tracking in an automated cytogenetic biodosimetry laboratory for radiation mass casualties

International Nuclear Information System (INIS)

Martin, P.R.; Berdychevski, R.E.; Subramanian, U.; Blakely, W.F.; Prasanna, P.G.S.

2007-01-01

Chromosome-aberration-based dicentric assay is expected to be used after mass-casualty life-threatening radiation exposures to assess radiation dose to individuals. This will require processing of a large number of samples for individual dose assessment and clinical triage to aid treatment decisions. We have established an automated, high-throughput, cytogenetic biodosimetry laboratory to process a large number of samples for conducting the dicentric assay using peripheral blood from exposed individuals according to internationally accepted laboratory protocols (i.e., within days following radiation exposures). The components of an automated cytogenetic biodosimetry laboratory include blood collection kits for sample shipment, a cell viability analyzer, a robotic liquid handler, an automated metaphase harvester, a metaphase spreader, high-throughput slide stainer and coverslipper, a high-throughput metaphase finder, multiple satellite chromosome-aberration analysis systems, and a computerized sample-tracking system. Laboratory automation using commercially available, off-the-shelf technologies, customized technology integration, and implementation of a laboratory information management system (LIMS) for cytogenetic analysis will significantly increase throughput. This paper focuses on our efforts to eliminate data-transcription errors, increase efficiency, and maintain samples' positive chain-of-custody by sample tracking during sample processing and data analysis. This sample-tracking system represents a 'beta' version, which can be modeled elsewhere in a cytogenetic biodosimetry laboratory, and includes a customized LIMS with a central server, personal computer workstations, barcode printers, fixed station and wireless hand-held devices to scan barcodes at various critical steps, and data transmission over a private intra-laboratory computer network. Our studies will improve diagnostic biodosimetry response, aid confirmation of clinical triage, and medical

Sample tracking in an automated cytogenetic biodosimetry laboratory for radiation mass casualties

Energy Technology Data Exchange (ETDEWEB)

Martin, P.R.; Berdychevski, R.E.; Subramanian, U.; Blakely, W.F. [Armed Forces Radiobiology Research Institute, Uniformed Services University of Health Sciences, 8901 Wisconsin Avenue, Bethesda, MD 20889-5603 (United States); Prasanna, P.G.S. [Armed Forces Radiobiology Research Institute, Uniformed Services University of Health Sciences, 8901 Wisconsin Avenue, Bethesda, MD 20889-5603 (United States)], E-mail: prasanna@afrri.usuhs.mil

2007-07-15

Chromosome-aberration-based dicentric assay is expected to be used after mass-casualty life-threatening radiation exposures to assess radiation dose to individuals. This will require processing of a large number of samples for individual dose assessment and clinical triage to aid treatment decisions. We have established an automated, high-throughput, cytogenetic biodosimetry laboratory to process a large number of samples for conducting the dicentric assay using peripheral blood from exposed individuals according to internationally accepted laboratory protocols (i.e., within days following radiation exposures). The components of an automated cytogenetic biodosimetry laboratory include blood collection kits for sample shipment, a cell viability analyzer, a robotic liquid handler, an automated metaphase harvester, a metaphase spreader, high-throughput slide stainer and coverslipper, a high-throughput metaphase finder, multiple satellite chromosome-aberration analysis systems, and a computerized sample-tracking system. Laboratory automation using commercially available, off-the-shelf technologies, customized technology integration, and implementation of a laboratory information management system (LIMS) for cytogenetic analysis will significantly increase throughput. This paper focuses on our efforts to eliminate data-transcription errors, increase efficiency, and maintain samples' positive chain-of-custody by sample tracking during sample processing and data analysis. This sample-tracking system represents a 'beta' version, which can be modeled elsewhere in a cytogenetic biodosimetry laboratory, and includes a customized LIMS with a central server, personal computer workstations, barcode printers, fixed station and wireless hand-held devices to scan barcodes at various critical steps, and data transmission over a private intra-laboratory computer network. Our studies will improve diagnostic biodosimetry response, aid confirmation of clinical triage, and

Development of radiology in Mongolia

International Nuclear Information System (INIS)

Gonchigsuren, D.; Munkhbaatar, D.; Tuvshinjargal, D.; Onkhuudai, P.

2007-01-01

Full text: Radiology had been introduced in Mongolia by the establishment of the first X-Ray room at the First State Central Hospital in 1934. First radiologists in Mongolia were invited from the former Soviet Union; V. Sokolov, P. Omelchenko and others worked at the ''Burevestnik'' X-ray equipment of Russian production with high X-ray exposure and low capacity; they could perform only limited arts of Xray studies like fluoroscopy of thorax, stomach, esophagus and roentgenography of skull and extremities. The second X- ray equipment has been presented by the close friend of Lenin, the Director of People's Commissariat of Health Protection of the Soviet Union, Dr. N.A. Semashko; the present had been dedicated to the 10th Anniversary of Mongolian Health Care sector. During the military maneuvers at Khalkhin- Gol in 1939, several province hospitals and military hospitals had been supplied by the Xray equipment. During the period 1959-1960 all province hospitals, specialized hospitals had got X-ray unit. In 1955, Radii 226 had been used at first time in Mongolia for a treatment. In 1959, the State Radiological Clinic had been founded as a branch of X-ray cabinet of the First State Central Hospital. By the initiative of the absolvent of University of Leipzig, German Democratic Republic, Dr. P. Onkhuudai, Laboratory of Nuclear Medicine was established on 31 PstP March 1975 at the First State Central Hospital, which performed urography, thyroid and liver studies using Iod-131, Au-198, Hg-203 isotopes. In 1982, the gamma-camera and radio immunological equipment had been donated by the World Health Organization, and the Laboratory of Nuclear Medicine had been reorganized into Department of Nuclear Laboratory. Afterwards, in 1992 CT and SPECT diagnostics had been introduced at the First State Central Hospital, therefore new possibilities for high quality radiological diagnostic in Mongolia had been created. In 2007 the Siemens Magnetom 0.3 Tesla had been installed at the

Radiological diagnostics in hyperparathyroidism

International Nuclear Information System (INIS)

Moedder, U.; Kuhn, F.P.; Gruetzner, G.

1991-01-01

The most important radiologically detectable effects of the primary and secondary hyperparathyroidism of the skeletal system and the periarticular soft tissue structures are presented. In the following sensitivity and specificity of radiological imaging - sonography, scintigraphy, computed tomography, magnetic resonance imaging, arteriography and selective venous sampling - in the preoperative diagnostic of the parathyroid adenomas are discussed. Therefore, radiological imaging can be omitted before primary surgery. It was only in secondary surgery that radiological process proved useful and a guide during surgical intervention. (orig.) [de

Radiological risk assessment of isotope laboratories according to the requirements of the radiation protection ordinance and the protective labour legislation

International Nuclear Information System (INIS)

Stuerm, R.P.; Kuster, M.; Traub, K.

2001-01-01

According to the Swiss Radiation Safety Ordinance the supervising authority may require a safety report from the operator of a radioactive laboratory (Art.95) and establish the methodology of the risk analysis. Isotope laboratories of the chemical industry are supervised by Swiss accident insurance agency (SUVA). In that respect SUVA safeguards both radiation protection issues and general protection of the workers and established guide lines in order to assess conventional risks in industrial premises. In these conventional analysis the working process is analysed according to its possible detriment (death, severe invalidity, slight invalidity, injury with absence, injury without absence) and the probability of occurrence (frequent, seldom, rare, improbable, virtually impossible). According to this the risks are categorised in a matrix as 'high', 'medium' and 'low'. SUVA requested such a risk analysis for two isotope laboratories of B type in Basel in which on the one hand the hazard to the workers on the other hand to the public should be analysed and radiologically assessed. It was proposed to use a methodology established in workers safety and the insurance section. This required a comparison of risks of radiation doses in mSv to the consequences of conventional working accidents (death, invalidity) and the risk perception of the public and politicians. In this paper this risk matrix derived in discussions among the supervising body, the company management, the laboratory head and workers is described. In the opinion of the authors such a comparison between radiological and conventional risks has not been performed up to now and the results obtained here are open to discussion. (orig.) [de

The Radiological Research Accelerator Facility

International Nuclear Information System (INIS)

Hall, E.J.

1992-05-01

The Radiological Research Accelerator Facility (RARAF) is based on a 4-MV Van de Graaff accelerator, which is used to generate a variety of well-characterized radiation beams for research in radiobiology, radiological physics, and radiation chemistry. It is part of the Center for Radiological Research (CRR) -- formerly the Radiological Research Laboratory (RRL) -- of Columbia University, and its operation is supported as a National Facility by the US Department of Energy (DOE). As such, RARAF is available to all potential users on an equal basis, and scientists outside the CRR are encouraged to submit proposals for experiments at RARAF. The operation of the Van de Graaff is supported by the DOE, but the research projects themselves must be supported separately. Experiments performed from May 1991--April 1992 are described

History of aerial surveys in response to radiological incidents and accidents

International Nuclear Information System (INIS)

Jobst, J.E.

1986-01-01

EG and G Energy Measurements Inc., operates the Remote Sensing Laboratory for the US Department of Energy (DOE). The Laboratory plays a key role in the federal response to a radiological incident or accident. It assists the DOE in the establishment of a Federal Radiological Monitoring and Assessment Center (FRMAC). The Remote Sensing Laboratory has played a major role in more than 13 incidents, including lost sources, accidental dispersions, and nuclear reactor incidents

Radiology research in mainland China in the past 10 years: a survey of original articles published in Radiology and European Radiology

International Nuclear Information System (INIS)

Zhang, Long Jiang; Wang, Yun Fei; Yang, Zhen Lu; Lu, Guang Ming; Schoepf, U.J.; Xu, Jiaqian; Li, Enzhong

2017-01-01

To evaluate the features and trends of Radiology research in Mainland China through bibliometric analysis of the original articles published in Radiology and European Radiology (ER) between 2006 and 2015. We reviewed the original articles published in Radiology and ER between 2006 and 2015. The following information was abstracted: imaging subspecialty, imaging technique(s) used, research type, sample size, study design, statistical analysis, study results, funding declarations, international collaborations, number of authors, department and province of the first author. All variables were examined longitudinally over time. Radiology research in Mainland China saw a substantial increase in original research articles published, especially in the last 5 years (P < 0.001). Within Mainland China's Radiology research, neuroradiology, vascular/interventional Radiology, and abdominal Radiology were the most productive fields; MR imaging was the most used modality, and a distinct geographic provenience was observed for articles published in Radiology and ER. Radiology research in Mainland China has seen substantial growth in the past 5 years with neuroradiology, vascular/interventional Radiology, and abdominal Radiology as the most productive fields. MR imaging is the most used modality. Article provenience shows a distinct geographical pattern. (orig.)

Radiology research in mainland China in the past 10 years: a survey of original articles published in Radiology and European Radiology

Energy Technology Data Exchange (ETDEWEB)

Zhang, Long Jiang; Wang, Yun Fei; Yang, Zhen Lu; Lu, Guang Ming [Medical School of Nanjing University, Department of Medical Imaging, Jinling Hospital, Nanjing, Jiangsu (China); Schoepf, U.J. [Medical School of Nanjing University, Department of Medical Imaging, Jinling Hospital, Nanjing, Jiangsu (China); Medical University of South Carolina, Division of Cardiovascular Imaging, Department of Radiology and Radiological Science, Charleston, SC (United States); Xu, Jiaqian [Medical University of South Carolina, Division of Cardiovascular Imaging, Department of Radiology and Radiological Science, Charleston, SC (United States); Li, Enzhong [National Natural Science Foundation of China, Department of Medical Science, Beijing (China)

2017-10-15

To evaluate the features and trends of Radiology research in Mainland China through bibliometric analysis of the original articles published in Radiology and European Radiology (ER) between 2006 and 2015. We reviewed the original articles published in Radiology and ER between 2006 and 2015. The following information was abstracted: imaging subspecialty, imaging technique(s) used, research type, sample size, study design, statistical analysis, study results, funding declarations, international collaborations, number of authors, department and province of the first author. All variables were examined longitudinally over time. Radiology research in Mainland China saw a substantial increase in original research articles published, especially in the last 5 years (P < 0.001). Within Mainland China's Radiology research, neuroradiology, vascular/interventional Radiology, and abdominal Radiology were the most productive fields; MR imaging was the most used modality, and a distinct geographic provenience was observed for articles published in Radiology and ER. Radiology research in Mainland China has seen substantial growth in the past 5 years with neuroradiology, vascular/interventional Radiology, and abdominal Radiology as the most productive fields. MR imaging is the most used modality. Article provenience shows a distinct geographical pattern. (orig.)

The deployment of an innovative real-time radiological soil characterization system

International Nuclear Information System (INIS)

Allen, David; Danahy, Raymond; Laird, Gregory; Seiller, Dale; White, Joan; Janke, Robert

2000-01-01

laboratory analyses. Obtaining actual radiological characterization data from a much greater percentage of the soil under characterization than would be possible with the collection of physical samples has also resulted in more effective remediation of the site. The regulatory climate under which these realtime measurements are performed is briefly discussed

National Radiological Fixed Lab Data

Data.gov (United States)

U.S. Environmental Protection Agency — The National Radiological Fixed Laboratory Data Asset includes data produced in support of various clients such as other EPA offices, EPA Regional programs, DOE,...

Results of the radiological survey at the former Heppenstall Company site, 4620 Hatfield Street, Pittsburgh, Pennsylvania

International Nuclear Information System (INIS)

Cottrell, W.D.; Crutcher, J.W.; Quillen, J.L.

1991-01-01

As part of the Formerly Utilized Sites Remedial Action Program, the US Department of Energy (DOE) is implementing a program to determine the radiological conditions at sites that were used to process radioactive materials under contract with the department's predecessor agencies. During 1955 the former Heppenstall Company site in Pittsburgh, Pennsylvania, was used by an Atomic Energy Commission contractor to process approximately 100,000 lbs of normal uranium metal. Because of insufficient records to document cleanup procedures and to verify the radiological condition of this site, DOE requested a survey. The radiological survey discussed in this report for the site of the former Heppenstall Company, Pittsburgh, Pennsylvania, was conducted by members of the Measurement Applications and Development Group of Oak Ridge National Laboratory in July of 1989. The survey included a surface gamma scan of the warehouse, collection of indoor soil and dust samples and one outdoor sample, and measurement of direct and transferable alpha and beta-gamma activity. Results of this radiological assessment indicate no detection of radiation levels or radionuclide concentrations above DOE guidelines. 7 refs., 5 figs., 3 tabs

Radiology research in mainland China in the past 10 years: a survey of original articles published in Radiology and European Radiology.

Science.gov (United States)

Zhang, Long Jiang; Wang, Yun Fei; Yang, Zhen Lu; Schoepf, U Joseph; Xu, Jiaqian; Lu, Guang Ming; Li, Enzhong

2017-10-01

To evaluate the features and trends of Radiology research in Mainland China through bibliometric analysis of the original articles published in Radiology and European Radiology (ER) between 2006 and 2015. We reviewed the original articles published in Radiology and ER between 2006 and 2015. The following information was abstracted: imaging subspecialty, imaging technique(s) used, research type, sample size, study design, statistical analysis, study results, funding declarations, international collaborations, number of authors, department and province of the first author. All variables were examined longitudinally over time. Radiology research in Mainland China saw a substantial increase in original research articles published, especially in the last 5 years (P Radiology research, neuroradiology, vascular/interventional Radiology, and abdominal Radiology were the most productive fields; MR imaging was the most used modality, and a distinct geographic provenience was observed for articles published in Radiology and ER. Radiology research in Mainland China has seen substantial growth in the past 5 years with neuroradiology, vascular/interventional Radiology, and abdominal Radiology as the most productive fields. MR imaging is the most used modality. Article provenience shows a distinct geographical pattern. • Radiology research in Mainland China saw a substantial increase. • Neuroradiology, vascular/interventional Radiology, and abdominal Radiology are the most productive fields. • MRI is the most used modality in Mainland China's Radiology research. • Guangdong, Shanghai, and Beijing are the most productive provinces.

Successful Sampling Strategy Advances Laboratory Studies of NMR Logging in Unconsolidated Aquifers

Science.gov (United States)

Behroozmand, Ahmad A.; Knight, Rosemary; Müller-Petke, Mike; Auken, Esben; Barfod, Adrian A. S.; Ferré, Ty P. A.; Vilhelmsen, Troels N.; Johnson, Carole D.; Christiansen, Anders V.

2017-11-01

The nuclear magnetic resonance (NMR) technique has become popular in groundwater studies because it responds directly to the presence and mobility of water in a porous medium. There is a need to conduct laboratory experiments to aid in the development of NMR hydraulic conductivity models, as is typically done in the petroleum industry. However, the challenge has been obtaining high-quality laboratory samples from unconsolidated aquifers. At a study site in Denmark, we employed sonic drilling, which minimizes the disturbance of the surrounding material, and extracted twelve 7.6 cm diameter samples for laboratory measurements. We present a detailed comparison of the acquired laboratory and logging NMR data. The agreement observed between the laboratory and logging data suggests that the methodologies proposed in this study provide good conditions for studying NMR measurements of unconsolidated near-surface aquifers. Finally, we show how laboratory sample size and condition impact the NMR measurements.

Differential diagnosis of a solitary pulmonary nodule of the lung on the grounds of selected laboratory tests and radiological examination

International Nuclear Information System (INIS)

Szlachcinska, A.; Kozak, J.

2011-01-01

Objective: To present in detail the diagnosis of solitary pulmonary nodule and especially evaluation of: clinical data, analysis of radiological images, selected laboratory tests. Material and methods: There were 50 patients - 31 men and 19 women at the mean age 58.7 ± 11.4 years old who underwent surgical treatment because of a solitary pulmonary nodule. Interview, physical examination, computed tomography, bronchoscopy, spirometry, and laboratory tests needed for the operation were performed in all these patients. Additionally LDH, fibrinogen, ESR, and the tumour markers CEA, Ca 15-3, Ca 19-9, NSE, SCC, and Cyfra 21-1 were measured from the blood sample collected during admission. Results: Malignant tumour was diagnosed in 24 patients, benign in 26. There is a significant difference between patients with malignant and nonmalignant tumours in age (54.46 years vs. 63.33 years), size of the tumour in the lung scan of chest CT (1.53 cm vs. 1.91 cm) and location (lower right lobe vs. upper right lobe). There is no significant difference between type of tumour and sex, clinical symptoms and laboratory tests. Conclusions: 1. The risk factors of malignancy in patient with solitary pulmonary nodule are: age ≥ 56.5 years, size of the tumour in the lung scan of chest CT ≥ 1.45 cm, location in upper right lobe. 2. LDH, fibrinogen, ESR, and the tumour markers CEA, Ca 15-3, Ca 19-9, NSE, SCC, and Cyfra 21-1 are not useful in differential diagnosis of solitary pulmonary nodule. (authors)

Collaborative Radiological Response Planning

Science.gov (United States)

2013-12-01

DOE and EPA national laboratories .55 Additionally, the GAO conducted a survey of emergency management officials in cities, states and federal...for Biosecurity of UPMC, (2012). After fukushima: Managing the consequences of a radiological release. Retrieved from : http://issuu.com

Surveillance and radiological protection in the Hot Cell laboratory; Vigilancia y proteccion radiologica en el Laboratorio de Celdas Calientes

Energy Technology Data Exchange (ETDEWEB)

Ramirez, J.M.; Torre, J. De la; Garcia C, M.A. [ININ, A.P. 18-1027, 11801 Mexico D.F. (Mexico)

2004-07-01

The Hot Cells Laboratory (LCC) located in the National Institute of Nuclear Research are an installation that was designed for the management at distance of 10,000 Curies of Co-60 or other radioactive materials with different values in activity. The management of such materials in the installation, implies to analyze and to determine the doses that the POE will receive as well as the implementation of protection measures and appropriate radiological safety so that is completed the specified by the ALARA concept. In this work it is carried out an evaluation of the doses to receive for the POE when managing radionuclides with maximum activities that can be allowed in function of the current conditions of the cells and an evaluation of results is made with the program of surveillance and radiological protection implemented for the development of the works that carried out in the installation. (Author)

Low-level waste characterization plan for the WSCF Laboratory Complex

International Nuclear Information System (INIS)

Morrison, J.A.

1994-01-01

The Waste Characterization Plan for the Waste Sampling and Characterization Facility (WSCF) complex describes the organization and methodology for characterization of all waste streams that are transferred from the WSCF Laboratory Complex to the Hanford Site 200 Areas Storage and Disposal Facilities. Waste generated at the WSCF complex typically originates from analytical or radiological procedures. Process knowledge is derived from these operations and should be considered an accurate description of WSCF generated waste. Sample contribution is accounted for in the laboratory waste designation process and unused or excess samples are returned to the originator for disposal. The report describes procedures and processes common to all waste streams; individual waste streams; and radionuclide characterization methodology

Mobile laboratory-based environmental radioactivity analysis capability of the US Environmental Protection Agency

International Nuclear Information System (INIS)

Dempsey, G.; Poppell, S.

1999-01-01

This poster presentation will highlight the capability of the US Environmental Protection Agency, Office of Radiation and Indoor Air to process and analyze environmental and emergency response samples in mobile radiological laboratories. Philosophy of use, construction, analytical equipment, and procedures will be discussed in the poster presentation. Accompanying the poster presentation, EPA will also have a static display of its mobile laboratories at the meeting site. (author)

The Radiological Research Accelerator Facility

International Nuclear Information System (INIS)

Hall, E.J.; Marino, S.A.

1991-05-01

The Radiological Research Accelerator Facility (RARAF) is based on 4-MV Van de Graaff accelerator, which is used to generate a variety of well-characterized radiation beams for research in radiobiology, radiological physics, and radiation chemistry. It is part of the Center for Radiological Research (CRR) -- formerly the Radiological Research Laboratory (RRL) -- of Columbia University, and its operation is supported as a National Facility by the US Department of Energy (DOE). As such, RARAF is available to all potential users on an equal basis, and scientists outside the CRR are encouraged to submit proposals for experiments at RARAF. The operation of the Van de Graaff is supported by the DOE, but the research projects themselves must be supported separately. Brief summaries of research experiments are included. Accelerator usage is summarized and development activities are discussed. 8 refs., 8 tabs

The Radiological Research Accelerator Facility

International Nuclear Information System (INIS)

Hall, E.J.; Marino, S.A.

1993-05-01

The Radiological Research Accelerator Facility (RARAF) is based on a 4-MV Van de Graaff accelerator, which is used to generate a variety of well-characterized radiation beams for research in radiobiology, radiological physics, and radiation chemistry. It is part of the Center for Radiological Research (CRR) - formerly the Radiological Research Laboratory of Columbia University, and its operation is supported as a National Facility by the US Department of Energy (DOE). As such, RARAF is available to all potential users on an equal basis and scientists outside the CRR are encouraged to submit proposals for experiments at RARAF. The operation of the Van de Graaff is supported by the DOE, but the research projects themselves must be supported separately. This report provides a listing and brief description of experiments performed at RARAF during the May 1, 1992 through April 30, 1993

Formerly utilized MED/AEC sites remedial action program. Radiological survey of The George Herbert Jones Chemical Laboratory, The University of Chicago, Chicago, Illinois, June 13-17, 1977

International Nuclear Information System (INIS)

Wynveen, R.A.; Smith, W.H.; Mayes, C.B.; Justus, A.L.

1982-05-01

A comprehensive radiological survey was conducted at George Herbert Jones Chemical Laboratory at the University of Chicago, Chicago, Illinois. Radiochemistry for the MED/AEC project was performed in this building in the 1940s. The building is now used as laboratories, offices, and classrooms. The survey was undertaken to determine the location and quantities of any radioactive materials remaining from the MED/AEC operations. Forty-three spots of contamination possibly resulting from MED/AEC occupancy in 17 rooms exceeded the allowable limits as given in the ANSI Standard N13.12. Under current use conditions, the potential for radiation exposure to occupants of this building from these sources of contamination is remote. Concentrations of radon daughters in the air of the building, as measured with grab-sampling techniques, were below the limit of 0.01 WL above background as given in the Surgeon General's Guidelines. No long-lived radionuclides were detected in any air sample. Concentrations of radionuclides in soil samples from near the laboratory generally indicated background levels. In order to reduce the potential for radiation exposure, remedial measures such as stabilization of the contamination in place would be applicable as a short-term measure. In order to reduce the risk in the event that building modifications take place in the future, health physics procedures and coverage are recommended. The long-term solution would involve decontamination by removal of the radioactive residues from the 17 rooms or areas where contamination possibly resulting from MED/AEC activities was detected

Quality assurance program on the individual monitory service of the Protection Radiology Laboratory of the Universidade Federal de Pernambuco, Recife, PE (Brazil): preliminary results

International Nuclear Information System (INIS)

Antonino, Paulo H.D.; Filho, Joao A.; Silveira, Sueldo V.

1996-01-01

The current stage of the quality assurance program on the individual monitoring service of the Protection Radiology Laboratory of the Universidade Federal de Pernambuco, Recife, PE (Brazil) is presented. The program emphasizes the personnel training and its development is focused to meet national and international standards requirements

Thermoluminescent dosimetry in veterinary diagnostic radiology

International Nuclear Information System (INIS)

Hernández-Ruiz, L.; Jimenez-Flores, Y.; Rivera-Montalvo, T.; Arias-Cisneros, L.; Méndez-Aguilar, R.E.; Uribe-Izquierdo, P.

2012-01-01

This paper presents the results of Environmental and Personnel Dosimetry made in a radiology area of a veterinary hospital. Dosimetry was realized using thermoluminescent (TL) materials. Environmental Dosimetry results show that areas closer to the X-ray equipment are safe. Personnel Dosimetry shows important measurements of daily workday in some persons near to the limit established by ICRP. TL results of radiation measurement suggest TLDs are good candidates as a dosimeter to radiation dosimetry in veterinary radiology. - Highlights: ► Personnel dosimetry in laboratory veterinary diagnostic was determined. ► Student workplaces are safe against radiation. ► Efficiency value of apron lead was determined. ► X-ray beams distribution into veterinarian laboratory was measured.

Clinical and laboratory experience of chorionic villous sampling in ...

African Journals Online (AJOL)

Background: Chorionic villous sampling is a first trimester invasive diagnosis procedure that was introduced in Nigeria <2 decades ago. Objective: The objective of the following study is to review experience with chorionic villous sampling in relation to clinical and laboratory procedures, including general characteristics of ...

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)

Radon induced radiological impact of coal, fly ash and cement samples

International Nuclear Information System (INIS)

Kant, K.; Chauhan, R.P.; Sharma, G.S.; Chakravarti, S.K.

2001-01-01

Coal and its by-product fly ash are technologically important materials being used for power generation and in the manufacture of bricks, sheets, cement, land-filling, etc., respectively. Increased interest in measuring radon concentration in coal, fly ash and cement is due to its health hazards and environmental pollution. As the presence of radon in the environment (indoor and outdoor), soil, ground water, oil and gas deposits contributes the largest fraction of the natural radiation dose to populations, tracking its concentration is thus of paramount importance for radiological protection. Samples of coal and fly ash were collected from different thermal power stations in northern India and cement samples from National Council for Cement and Building Materials, Ballabgarh (Haryana), India and were analysed for radon concentration. For the measurement, alpha sensitive LR-115 type II plastic track detectors were used. Based upon the available data, the annual effective dose and the lifetime fatality risk factors have been calculated. The radon concentration from coal samples varied from 433 ± 28 Bqm -3 to 2086 ± 28 Bqm -3 . The radon concentration from fly ash samples varied from 748 ± 28 Bqm -3 to 1417 ± 111 Bqm -3 and from 158 Bqm -3 to 1810 Bqm -3 in cement samples, with an average of 624 ± 169 Bqm -3 . (author)

Formerly utilized MED/AEC sites remedial action program. Radiological survey of the Middlesex Sampling Plant, Middlesex, New Jersey. Final report

International Nuclear Information System (INIS)

1977-11-01

The results of a radiological survey of the former Middlesex Sampling Plant, Middlesex, New Jersey, are presented in this report. The surveyed property served as a uranium ore sampling plant during the 1940's and early 1950's. It was released for unrestricted use in 1968 following a radiological survey by the Atomic Energy Commission and is now a reserve training center for the U.S. Marine Sixth Motor Transport Battalion. The present survey was undertaken to determine whether the existing radiological status of the property is consistent with current health guidelines and radiation protection practices. The radiological survey included measurement of residual alpha and beta-gamma contamination levels, radon and radon daughter concentrations in buildings, external gamma radiation levels on the site and on adjacent property, and radium concentrations in soil on the site and on adjacent property. Surface contamination levels exceeded U.S. Nuclear Regulatory Commission (NRC) guidelines and 222 Rn concentration levels exceeded the non-occupational maximum permissible concentration MPC/sub a/ of 3 pCi/liter in some structures. These results indicate the possible need for extensive radon and radon daughter measurements in structures both onsite and offsite over periods as suggested by the U.S. Surgeon General

Status report of AMS sample preparation laboratory at GADAM Centre, Gliwice, Poland

Energy Technology Data Exchange (ETDEWEB)

Piotrowska, N., E-mail: natalia.piotrowska@polsl.pl [GADAM Centre of Excellence, Department of Radioisotopes, Institute of Physics, Silesian University of Technology, Gliwice (Poland)

2013-01-15

The laboratory for {sup 14}C AMS sample preparation in the Gliwice Radiocarbon Laboratory has gradually evolved since its start in 1999 to cater for an increase in volume and variety of radiocarbon dating samples. To date, nearly 2000 graphite targets have been produced from materials such as plant macrofossils, charcoal, peat, bones, shells and wood. The equipment comprises a station for chemical preparation and high vacuum lines for production, purification and graphitization of sample carbon dioxide. The present capacity allows preparation of up to 400 targets annually for the needs of scientific projects and external orders for radiocarbon dating continuously received by the GADAM Centre of Excellence. The laboratory's sample preparation protocols and recent improvements are described and its performance during the 10 years of activity is discussed in terms of parameters obtained from reference materials prepared in this laboratory and demonstrated with a few science applications.

Laboratory and Airborne BRDF Analysis of Vegetation Leaves and Soil Samples

Science.gov (United States)

Georgiev, Georgi T.; Gatebe, Charles K.; Butler, James J.; King, Michael D.

2008-01-01

Laboratory-based Bidirectional Reflectance Distribution Function (BRDF) analysis of vegetation leaves, soil, and leaf litter samples is presented. The leaf litter and soil samples, numbered 1 and 2, were obtained from a site located in the savanna biome of South Africa (Skukuza: 25.0degS, 31.5degE). A third soil sample, number 3, was obtained from Etosha Pan, Namibia (19.20degS, 15.93degE, alt. 1100 m). In addition, BRDF of local fresh and dry leaves from tulip tree (Liriodendron tulipifera) and acacia tree (Acacia greggii) were studied. It is shown how the BRDF depends on the incident and scatter angles, sample size (i.e. crushed versus whole leaf,) soil samples fraction size, sample status (i.e. fresh versus dry leaves), vegetation species (poplar versus acacia), and vegetation s biochemical composition. As a demonstration of the application of the results of this study, airborne BRDF measurements acquired with NASA's Cloud Absorption Radiometer (CAR) over the same general site where the soil and leaf litter samples were obtained are compared to the laboratory results. Good agreement between laboratory and airborne measured BRDF is reported.

Nationwide survey of policies and practices related to capillary blood sampling in medical laboratories in Croatia.

Science.gov (United States)

Krleza, Jasna Lenicek

2014-01-01

Capillary sampling is increasingly used to obtain blood for laboratory tests in volumes as small as necessary and as non-invasively as possible. Whether capillary blood sampling is also frequent in Croatia, and whether it is performed according to international laboratory standards is unclear. All medical laboratories that participate in the Croatian National External Quality Assessment Program (N = 204) were surveyed on-line to collect information about the laboratory's parent institution, patient population, types and frequencies of laboratory tests based on capillary blood samples, choice of reference intervals, and policies and procedures specifically related to capillary sampling. Sampling practices were compared with guidelines from the Clinical and Laboratory Standards Institute (CLSI) and the World Health Organization (WHO). Of the 204 laboratories surveyed, 174 (85%) responded with complete questionnaires. Among the 174 respondents, 155 (89%) reported that they routinely perform capillary sampling, which is carried out by laboratory staff in 118 laboratories (76%). Nearly half of respondent laboratories (48%) do not have a written protocol including order of draw for multiple sampling. A single puncture site is used to provide capillary blood for up to two samples at 43% of laboratories that occasionally or regularly perform such sampling. Most respondents (88%) never perform arterialisation prior to capillary blood sampling. Capillary blood sampling is highly prevalent in Croatia across different types of clinical facilities and patient populations. Capillary sampling procedures are not standardised in the country, and the rate of laboratory compliance with CLSI and WHO guidelines is low.

Quality assurance programs from laboratories offering radiological protection services

International Nuclear Information System (INIS)

Marrero Garcia, M.; Prendes Alonso, M.; Jova Sed, L.; Morales Monzon, J.A.

1998-01-01

The implementation of an adequate program for quality assurance in institutions servicing radiological protection programs will become an additional tool to achieve security targets included in that program. All scientific and technical services offered by CPHR employ quality assurance systems

Comparison between Radiology Science Laboratory, Brazil (LCR) and National Research Council, Canada (NRC) of the absorbed dose in water using Fricke dosimetry

International Nuclear Information System (INIS)

Salata, Camila; David, Mariano Gazineu; Almeida, Carlos Eduardo de

2014-01-01

The absorbed dose to water standards for HDR brachytherapy dosimetry developed by the Radiology Science Laboratory, Brazil (LCR) and the National Research Council, Canada (NRC), were compared. The two institutions have developed absorbed dose standards based on the Fricke dosimetry system. There are significant differences between the two standards as far as the preparation and readout of the Fricke solution and irradiation geometry of the holder. Measurements were done at the NRC laboratory using a single Ir-192 source. The comparison of absorbed dose measurements was expressed as the ratio Dw(NRC)/Dw(LCR), which was found to be 1.026. (author)

Radiological accidents: education for prevention and confrontation

International Nuclear Information System (INIS)

Cardenas Herrera, Juan; Fernandez Gomez, Isis Maria

2008-01-01

The purpose of this work is to train and inform on radiological accidents as a preventive measure to improve the people life quality. Radiological accidents are part of the events of technological origin which are composed of nuclear and radiological accidents. As a notable figure is determined that there have been 423 radiological accidents from 1944 to 2005 and among the causes prevail industrial accidents, by irradiations, medical accidents and of laboratories, among others. Latin American countries such as Argentina, Brazil, Mexico and Peru are some where most accidents have occurred by radioactivity. The radiological accidents can have sociological, environmental, economic, social and political consequences. In addition, there are scenarios of potential nuclear accidents and in them the potential human consequences. Also, the importance of the organization and planning in a nuclear emergency is highlighted. Finally, the experience that Cuba has lived on the subject of radiological accidents is described [es

Surface radiological investigation of Trench 5 in Waste Area Grouping 7 at Oak Ridge National Laboratory, Oak Ridge, Tennessee

International Nuclear Information System (INIS)

Goff, D.D.

1991-08-01

A surface radiological investigation of areas encompassing Trench 5 on the Oak Ridge Reservation (ORR) was conducted from May 1990 through November 1990. This survey was led by the author, assisted by various members of the Measurement Applications and Development (MAD) group of the Health and Safety Research Division (HASRD) of Oak Ridge National Laboratory (ORNL) in Oak Ridge, Tennessee. The purpose of the investigation was to determine the presence, nature, and extent of surface radiological contamination at Trench 5, the Homogeneous Reactor Experiment fuel wells, and surrounding areas. Based on the data obtained in the field, interim corrective measures were recommended to limit human exposure to radioactivity and to minimize insult to the environment. It should be stressed that this project was not intended to be a complete site characterization but rather to be a preliminary investigation into the potential contamination problem that might exist as a result of past operations at Trench 5

Molecular Biomedical Imaging Laboratory (MBIL)

Data.gov (United States)

Federal Laboratory Consortium — The Molecular Biomedical Imaging Laboratory (MBIL) is adjacent-a nd has access-to the Department of Radiology and Imaging Sciences clinical imaging facilities. MBIL...

Regional radiological observations of the environment

International Nuclear Information System (INIS)

2014-11-01

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

Sampling and analysis plan for the site characterization of the waste area Grouping 1 groundwater operable unit at Oak Ridge National Laboratory

International Nuclear Information System (INIS)

1994-11-01

Waste Area Grouping (WAG) 1 at Oak Ridge National Laboratory (ORNL) includes all of the former ORNL radioisotope research, production, and maintenance facilities; former waste management areas; and some former administrative buildings. Site operations have contaminated groundwater, principally with radiological contamination. An extensive network of underground pipelines and utilities have contributed to the dispersal of contaminants to a known extent. In addition, karst geology, numerous spills, and pipeline leaks, together with the long and varied history of activities at specific facilities at ORNL, complicate contaminant migration-pathway analysis and source identification. To evaluate the extent of contamination, site characterization activity will include semiannual and annual groundwater sampling, as well as monthly water level measurements (both manual and continuous) at WAG 1. This sampling and analysis plan provides the methods and procedures to conduct site characterization for the Phase 1 Remedial Investigation of the WAG 1 Groundwater Operable Unit

Laboratory Accreditation and the Calibration of Radiologic Measuring Tools

International Nuclear Information System (INIS)

Vancsura, P.; Kovago, J.

1998-01-01

In this paper is presented that accreditation in our days is a strict requirement for a lab for its results could be accepted on international level. Accreditation itself brings to new requirements, among them some are related to the calibration of the radiological measuring equipment

Evaluation of the radiological quality of the water on Bikini and Eneu Islands in 1975: dose assessment based on initial sampling

International Nuclear Information System (INIS)

Noshkin, V.E.; Robison, W.L.; Wong, K.M.; Eagle, R.J.

1977-01-01

This report describes the radiological quality of the groundwater on the two main islands (Eneu and Bikini) of Bikini Atoll during June 1975 (from data obtained from water samples collected at old and new well sites on both islands) and the cistern water on Bikini Island. Based on analyses of these samples, we found that the cistern water from Bikini Island is both chemically and radiologically acceptable as drinking water in accordance with standard limits established by the U.S. Public Health Service. However, on both islands the quality of the groundwater varied from one site to another. At some wells both chemical and radiological quality are acceptable; at others one or both are unacceptable according to U.S. Public Health Standards. The doses we predict from consumption of both cistern and groundwater are acceptable under federal guidelines. However, doses predicted from consumption of groundwater are high enough to warrant careful evaluation of other potential exposure pathways

Nationwide survey of policies and practices related to capillary blood sampling in medical laboratories in Croatia

Science.gov (United States)

Krleza, Jasna Lenicek

2014-01-01

Introduction: Capillary sampling is increasingly used to obtain blood for laboratory tests in volumes as small as necessary and as non-invasively as possible. Whether capillary blood sampling is also frequent in Croatia, and whether it is performed according to international laboratory standards is unclear. Materials and methods: All medical laboratories that participate in the Croatian National External Quality Assessment Program (N = 204) were surveyed on-line to collect information about the laboratory’s parent institution, patient population, types and frequencies of laboratory tests based on capillary blood samples, choice of reference intervals, and policies and procedures specifically related to capillary sampling. Sampling practices were compared with guidelines from the Clinical and Laboratory Standards Institute (CLSI) and the World Health Organization (WHO). Results: Of the 204 laboratories surveyed, 174 (85%) responded with complete questionnaires. Among the 174 respondents, 155 (89%) reported that they routinely perform capillary sampling, which is carried out by laboratory staff in 118 laboratories (76%). Nearly half of respondent laboratories (48%) do not have a written protocol including order of draw for multiple sampling. A single puncture site is used to provide capillary blood for up to two samples at 43% of laboratories that occasionally or regularly perform such sampling. Most respondents (88%) never perform arterialisation prior to capillary blood sampling. Conclusions: Capillary blood sampling is highly prevalent in Croatia across different types of clinical facilities and patient populations. Capillary sampling procedures are not standardised in the country, and the rate of laboratory compliance with CLSI and WHO guidelines is low. PMID:25351353

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)

Radiological survey results at 1 Shady Lane, Lodi, New Jersey (LJ095)

International Nuclear Information System (INIS)

Foley, R.D.; Johnson, C.A.

1995-07-01

The US Department of Energy (DOE) conducted remedial action at the Stepan property in Maywood, New Jersey and several vicinity properties in Lodi, New Jersey as part of the Formerly Utilized Sites Remedial Action Program (FUSRAP). These properties are in the vicinity of the DOE-owned Maywood Interim Storage Site (MISS), adjacent to the former Maywood Chemical Works facility. The property at One Shady Lane, Lodi, New Jersey was not one of these vicinity properties but was surveyed by DOE at the request of the owner. At the request of DOE, a team from Oak Ridge National Laboratory conducted a radiological survey at this property. The purpose of the survey, conducted in November 1994, was to confirm whether remedial actions were to be performed on the property in order to be in compliance with the identified Guidelines. The radiological survey included surface gamma scans and gamma readings at 1 meter, and the collection of soil samples for radionuclide analysis. Results of the survey demonstrated that all radiological measurements on the property at One Shady Lane, Lodi, New Jersey, were comparable to background levels in the area, and well within the limits prescribed by DOE radiological guidelines. Based on the results of the radiological survey data, this property does not meet guidelines for inclusion under FUSRAP

Environmental Measurements Laboratory. Environmental report, September 1, 1981-March 1, 1982

International Nuclear Information System (INIS)

Hardy, E.P. Jr.; Toonkel, L.E.

1982-01-01

This report presents current information from the EML environmental programs, the Radiological and Environmental Research Division at Argonne National Laboratory and the Los Alamos National Laboratory. Two reports on radionuclide data quality assurance are presented in the initial section: one dealing with fallout and biological samples and the other with filtered air samples. These are followed by a report on stratospheric tritium injection by the October 1980 Chinese test. The second section presents recent data from EML progams strontium-90 fallout, radionuclides and trace metals in surface air, radioactivity and trace gases sampled in the stratosphere by aircraft and balloons, strontium-90 in San Francisco and New York diet, milk, and tap water, and cesium-137 in tap water. The third section presents data from Argonne National Laboratory on cesium-137 in Chicago food and from Los Alamos National Laboratory on tritium in the stratosphere. A bibliography of recent publications related to environmental studies is presented. Each section has been abstracted and indexed individually for ERA/EDB

Test objects for evaluating the performance of radiological imaging systems. Leeds radiological test objects

International Nuclear Information System (INIS)

Cowen, A.R.; Clarke, O.F.; Haywood, J.M.; Parker, R.P.

1985-01-01

A range of test objects has been developed to assess the imaging performance of conventional and digital radiological imaging systems. These test objects have arisen as a result of involvement in both the laboratory evaluation of radiological imaging systems and the routine maintenance of such equipment in a large diagnostic radiology department. The philosophy behind the design and application of the test objects is briefly described. Particular attention is paid to the advantages of using the threshold-contrast detail-detectability technique to assess overall imaging performance. The great importance of ensuring optimum imaging performance prior to clinical acceptance is stressed. A strategy for implementing the test objects in a clinical department is present. The diagnostic information content of the clinical images which result measures the success of the quality control procedure adopted. (author)

Evaluation of continued storage of samples at the 325 Laboratory

International Nuclear Information System (INIS)

McVey, C.B.

1996-01-01

This report provides identification of potential Program users for samples that are archived at Pacific Northwest National Laboratory (PNNL) facilities, establishes cost releated to packaging and transportation of these samples to 222-S, for continued storage at 325 facilities, disposal and transfer costs. The report provides a recommendation to dispose of 20 samples, transfer 99 samples to PNNL and to continue storage of the remaining samples at PNNL's 325 facility

NNSA/NV Consequence Management Capabilities for Radiological Emergency Response

International Nuclear Information System (INIS)

Bowman, D. R.

2002-01-01

The U.S. Department of Energy's National Nuclear Security Administration Nevada Operations Office (NNSA/NV) provides an integrated Consequence Management (CM) response capability for the (NNSA) in the event of a radiological emergency. This encompasses planning, technical operations, and home team support. As the lead organization for CM planning and operations, NNSA/NV coordinates the response of the following assets during the planning and operational phases of a radiological accident or incident: (1) Predictive dispersion modeling through the Atmospheric Release Advisory Capability (ARAC) at Lawrence Livermore National Laboratory (LLNL) and the High Consequence Assessment Group at Sandia National Laboratories (SNL); (2) Regional radiological emergency assistance through the eight Radiological Assistance Program (RAP) regional response centers; (3) Medical advice and assistance through the Radiation Emergency Assistance Center/Training Site (REAC/TS) in Oak Ridge, Tennessee; (4) Aerial radiological mapping using the fixed-wing and rotor-wing aircraft of the Aerial Measuring System (AMS); (5) Consequence Management Planning Teams (CMPT) and Consequence Management Response Teams (CMRT) to provide CM field operations and command and control. Descriptions of the technical capabilities employed during planning and operations are given below for each of the elements comprising the integrated CM capability

Radiological protection when handling plutonium in a laboratory for experimental fuels

International Nuclear Information System (INIS)

Fraser, D.C.

1978-01-01

The laboratory for experimental fuels at AEE Winfrith is a small but adaptable workshop capable of fabricating uranium and plutonium as metal or oxide into a variety of fuel elements including pins, plates and coated particle compacts for reactor physics experiments. Experience gained over fifteen years operation has shown that the external radiation dose received by operators, which arises mainly from low energy gamma and X radiation, can be controlled by the widespread use of simple shielding. The radiation from higher energy neutrons cannot be effectively shielded in simple non-automated plant and it becomes more important if large batches of fuel are handled. Inhalation of plutonium oxide is the potentially most important radiological problem. Normally airborne levels of PuO 2 are insignificant; occasionally very high but localised concentrations of airborne material have arisen in working areas, chiefly from minor damage to the flexible part of the containment system, i.e. the gloves and posting bags in glove boxes. Methods employed to measure radiation and inhalation exposure are described and the implications discussed. A fully integrated biological monitoring, in vivo counting and record system is used to ensure that the best estimate of intake is computed for each individual who may be exposed. (author)

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)

Waste sampling and characterization facility (WSCF)

International Nuclear Information System (INIS)

1994-10-01

The Waste Sampling and Characterization Facility (WSCF) complex consists of the main structure (WSCF) and four support structures located in the 600 Area of the Hanford site east of the 200 West area and south of the Hanford Meterology Station. WSCF is to be used for low level sample analysis, less than 2 mRem. The Laboratory features state-of-the-art analytical and low level radiological counting equipment for gaseous, soil, and liquid sample analysis. In particular, this facility is to be used to perform Resource Conservation and Recovery Act (RCRA) of 1976 and Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) of 1980 sample analysis in accordance with U.S. Environmental Protection Agency Protocols, room air and stack monitoring sample analysis, waste water treatment process support, and contractor laboratory quality assurance checks. The samples to be analyzed contain very low concentrations of radioisotopes. The main reason that WSCF is considered a Nuclear Facility is due to the storage of samples at the facility. This maintenance Implementation Plan has been developed for maintenace functions associate with the WSCF

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

Energy Technology Data Exchange (ETDEWEB)

1994-06-01

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

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

International Nuclear Information System (INIS)

1994-06-01

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

Sequim Marine Research Laboratory routine environmental measurements during CY-1978

International Nuclear Information System (INIS)

Houston, J.R.; Blumer, P.J.

1979-03-01

Environmental data collected during 1978 in the vicinity of the Marine Research Laboratory show continued compliance with all applicable state and federal regulations and furthermore show no detectable change from conditions that existed in previous years. Samples collected for radiological analysis included soil, drinking water, bay water, clams, and seaweed. Radiation dose rates at 1 meter aboveground were also measured

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

Empirical insights and considerations for the OBT inter-laboratory comparison of environmental samples

International Nuclear Information System (INIS)

Kim, Sang-Bog; Roche, Jennifer

2013-01-01

Organically bound tritium (OBT) is an important tritium species that can be measured in most environmental samples, but has only recently been recognized as a species of tritium in these samples. Currently, OBT is not routinely measured by environmental monitoring laboratories around the world. There are no certified reference materials (CRMs) for environmental samples. Thus, quality assurance (QA), or verification of the accuracy of the OBT measurement, is not possible. Alternatively, quality control (QC), or verification of the precision of the OBT measurement, can be achieved. In the past, there have been differences in OBT analysis results between environmental laboratories. A possible reason for the discrepancies may be differences in analytical methods. Therefore, inter-laboratory OBT comparisons among the environmental laboratories are important and would provide a good opportunity for adopting a reference OBT analytical procedure. Due to the analytical issues, only limited information is available on OBT measurement. Previously conducted OBT inter-laboratory practices are reviewed and the findings are described. Based on our experiences, a few considerations were suggested for the international OBT inter-laboratory comparison exercise to be completed in the near future. -- Highlights: ► Inter-laboratory OBT comparisons would provide a good opportunity for developing reference OBT analytical procedures. ► The measurement of environmental OBT concentrations has a higher associated uncertainty. ► Certified reference materials for OBT in environmental samples are required

Radiological control manual. Revision 1

Energy Technology Data Exchange (ETDEWEB)

Kloepping, R.

1996-05-01

This Lawrence Berkeley National Laboratory Radiological Control Manual (LBNL RCM) has been prepared to provide guidance for site-specific additions, supplements and interpretation of the DOE Radiological Control Manual. The guidance provided in this manual is one methodology to implement the requirements given in Title 10 Code of Federal Regulations Part 835 (10 CFR 835) and the DOE Radiological Control Manual. Information given in this manual is also intended to provide demonstration of compliance to specific requirements in 10 CFR 835. The LBNL RCM (Publication 3113) and LBNL Health and Safety Manual Publication-3000 form the technical basis for the LBNL RPP and will be revised as necessary to ensure that current requirements from Rules and Orders are represented. The LBNL RCM will form the standard for excellence in the implementation of the LBNL RPP.

Radiological control manual. Revision 1

International Nuclear Information System (INIS)

Kloepping, R.

1996-05-01

This Lawrence Berkeley National Laboratory Radiological Control Manual (LBNL RCM) has been prepared to provide guidance for site-specific additions, supplements and interpretation of the DOE Radiological Control Manual. The guidance provided in this manual is one methodology to implement the requirements given in Title 10 Code of Federal Regulations Part 835 (10 CFR 835) and the DOE Radiological Control Manual. Information given in this manual is also intended to provide demonstration of compliance to specific requirements in 10 CFR 835. The LBNL RCM (Publication 3113) and LBNL Health and Safety Manual Publication-3000 form the technical basis for the LBNL RPP and will be revised as necessary to ensure that current requirements from Rules and Orders are represented. The LBNL RCM will form the standard for excellence in the implementation of the LBNL RPP

Radiological survey results at 914 Black Oak Ridge Road, Wayne, New Jersey (WJ005)

International Nuclear Information System (INIS)

Rodriguez, R.E.; Johnson, C.A.

1995-05-01

The US Department of Energy (DOE) conducted remedial action during 1993 at several vicinity properties in the Wayne and Pequannock Townships in New Jersey as part of the Formerly Utilized Sites Remedial Action Program (FUSRAP). These properties are in the vicinity of the DOE-owned Wayne Interim Storage Site (WISS), formerly the W.R. Grace facility. The property at 914 Black Oak Ridge Road, Wayne, New Jersey was not one of these vicinity properties; however the owner requested that his property be radiologically surveyed. At the request of DOE, a team from Oak Ridge National Laboratory conducted a radiological scoping survey of this property. The purpose of the survey, conducted in early November 1993, was to determine whether any radiological contamination might be present on the property. The radiological survey included surface gamma scans and gamma readings at one meter, and the collection of soil and/or debris samples for radionuclide analysis. Results of the survey demonstrated no radionuclide concentrations or radiation measurements in excess of applicable DOE guidelines

Huelva (phosphogypsum and Cs 137 wastes). Radiological controls on phosphogypsum storage lagoons and of the CRI-9 dump. Measurement of the external exposure. Soil, wastes and water radiological characterization

International Nuclear Information System (INIS)

2007-11-01

This document reports radiological measurements and sampling performed in lagoons where phosphogypsum wastes coming from the Huelva industrial complex are stored. All samples (soils, sediments, solid wastes, waters) were analysed by high resolution gamma spectrometry. First, the authors analyse and report the impact of phosphogypsum storages through on-site gamma radiation measurements and through laboratory analyses. Then they report the assessment of the impact of a specific dump where caesium 137 contaminated wastes are present since an accident which occurred in the Acerinox factory. Some recommendations are given to solve the radioprotection problems created by these storages

Implementation perspective of a Radiological Agent Identification Laboratory - LIAR at CTEx

International Nuclear Information System (INIS)

Santos, Avelino; Silva, Jorge A.V.; Oliveira, Luciano S.R.; Vilela, Paulo R.T.

2011-01-01

Radiometric analysis at Centro Tecnologico do Exercito, CTEx, have been performed since 1980s, to be applied in the course of pre-operational and operational stages of a subcritical nuclear assembly which was set up into the extinct Instituto de Pesquisas Especiais, IPE. In that time, monitoring, that were based in analytical techniques of gamma spectrometry and total alpha/beta counting, were performed. Nowadays, the aptness of identify radiological and nuclear agents in environmental samples is a deficiency of Division of Defesa Quimica, Biologica e Nuclear, DDQBN, which is legatee of IPE nuclear duty. With the implementation of Laboratorio de Identificacao de Agentes Radiologicos, LIAR, the obsolescence of DDQBN equipment is been solved by the acquisition of modern spectroscopy systems which are supposed able to analyze CTEx environmental matrix samples, according to specific CNEN standard, as well as to perform works that concern diverse activities on civil defense, security, scientific advisory, research, and foreign trade areas. So, this work describes the implementation of LIAR at DDQBN of CTEx and analyses perspectives of its use. Basic functionality, stage of implementation, systems and analytical techniques are described. Finally, the work considers the importance and the foreseen outcomes of LIAR implementation on scientific, technological, economic, social and environmental areas. (author)

Implementation perspective of a Radiological Agent Identification Laboratory - LIAR at CTEx

Energy Technology Data Exchange (ETDEWEB)

Santos, Avelino; Silva, Jorge A.V.; Oliveira, Luciano S.R.; Vilela, Paulo R.T., E-mail: avelino@ctex.eb.br, E-mail: jalberto@ctex.eb.br, E-mail: luciano@ctex.eb.br, E-mail: pauloric@ctex.eb.br [Centro Tecnologico do Exercito (DDQBN/CTEx), Rio de Janeiro, RJ (Brazil). Div. de Defesa Quimica, Biologica e Nuclear

2011-07-01

Radiometric analysis at Centro Tecnologico do Exercito, CTEx, have been performed since 1980s, to be applied in the course of pre-operational and operational stages of a subcritical nuclear assembly which was set up into the extinct Instituto de Pesquisas Especiais, IPE. In that time, monitoring, that were based in analytical techniques of gamma spectrometry and total alpha/beta counting, were performed. Nowadays, the aptness of identify radiological and nuclear agents in environmental samples is a deficiency of Division of Defesa Quimica, Biologica e Nuclear, DDQBN, which is legatee of IPE nuclear duty. With the implementation of Laboratorio de Identificacao de Agentes Radiologicos, LIAR, the obsolescence of DDQBN equipment is been solved by the acquisition of modern spectroscopy systems which are supposed able to analyze CTEx environmental matrix samples, according to specific CNEN standard, as well as to perform works that concern diverse activities on civil defense, security, scientific advisory, research, and foreign trade areas. So, this work describes the implementation of LIAR at DDQBN of CTEx and analyses perspectives of its use. Basic functionality, stage of implementation, systems and analytical techniques are described. Finally, the work considers the importance and the foreseen outcomes of LIAR implementation on scientific, technological, economic, social and environmental areas. (author)

The radiological manifestation of hypophosphatasia

International Nuclear Information System (INIS)

Chen Haisong; Li Xiaofei; Han Yan; Cao Qingxuan; Xu Wenjian

2012-01-01

Objective: To explore the radiological features of hypophosphatasia. Methods: Five cases of hypophosphatasia were definitely diagnosed, which included 3 males and 2 females aged from 5 months to 23 years. The laboratory assays were analyzed, radiological appearances of bone were determined and differential diagnoses were made. Results: The alkaline phosphatase in blood serum of five patients decreased, which were 8, 20, 13, 21, and 18 U/L respectively. Phosphoethanolamine increased in blood serum of the five patients, which were 16.5, 13.5, 21.6, 18.7, and 28.9 μmol/L respectively. Phosphoethanolamine also increased in urine,which were 2350, 9120, 3520, 5280, and 1820 μmol/L respectively. Calcium in blood serum increased, which were 4.2, 5.6, 4.9, 6.1, and 3.5 mmol/L respectively. X-ray images displayed that the density of bone decreased in 5 cases, the metaphyses exhibited widening and cupping in 4 cases, the provisional calcification zone of the metaphysis became thinning or disappearing in 4 cases, long bone bended in 4 cases and pathologically fractured in 1 case. Conclusion: Hypophosphatasia can be indicated by its relatively special radiological appearance, and it can be diagnosed and differentiated from rickets, osteomalacia and osteogenesis imperfect by the laboratory examination combined with its clinical presentation. (authors)

Radiological findings at a South African forensic pathology laboratory in cases of sudden unexpected death in infants

Directory of Open Access Journals (Sweden)

Naomi Fenton-Muir

2012-02-01

Full Text Available Objectives The work serves as a preliminary evaluation of the utility of the full-body radiography in examining cases of SUDI. Setting This paper reviews findings from full-body digital radiography in cases of sudden unexpected death in infants (SUDI in 2008 at the Salt River Forensic Pathology Laboratory in Cape Town. Subjects Cases of SUDI referred to the mortuary and undergoing full-body digital radiography were reviewed (192 cases. Design Imaging reports were cross-referenced with death registry data. Manner of death, cause of death, whether an autopsy had taken place, and radiological findings, were recorded and analysed. Results The absence of bony fractures was recorded as an imaging finding in 40% of cases. The most common type of imaging pathology was lung disease. In cases where autopsies were performed and pathology was found on imaging, the findings of the two methods of examination were consistent. Conclusions Imaging may have served to assist CoD determination based on case history, and therefore full-body radiography may improve the workflow in busy forensic pathology laboratories. More detailed and consistent recording of imaging findings is required before stronger conclusions may be drawn regarding the utility of full body digital imaging of paediatric cases in forensic pathology laboratories.

Frequency distribution of specific activities and radiological hazard assessment in surface beach sand samples collected in Bangsaen beach in Chonburi province, Thailand

Science.gov (United States)

Changkit, N.; Boonkrongcheep, R.; Youngchauy, U.; Polthum, S.; Kessaratikoon, P.

2017-09-01

The specific activities of natural radionuclides (40K, 226Ra and 232Th) in 50 surface beach sand samples collected from Bangsaen beach in Chonburi province in the easthern region of Thailand, were measured and evaluated. Experimental results were obtained by using a high-purity germanium (HPGe) detector and gamma spectrometry analysis system in the special laboratory at Thailand Institute of Nuclear Technology (Public Organization). The IAEA-SOIL-375 reference material was used to analyze the concentration of 40K, 226Ra and 232Th in all samples. It was found that the specific activities of 40K, 226Ra and 232Th were ranged from 510.85 - 771.35, 8.17 - 17.06 and 4.25 - 15.68 Bq/kg. Furthermore, frequency distribution of the specific activities were studied, analyzed and found to be the asymmetrical distribution by using a statistical computer program. Moreover, four radiological hazard indices for the investigated area were also calculated by using the median values of specific activities of 40K, 226Ra and 232Th. The results were also compared with the Office of Atoms for Peace (OAP) annual report data, Thailand and global radioactivity measurement and evaluations.

Handbook of laboratory techniques

International Nuclear Information System (INIS)

2002-01-01

The Nuclear Regulatory Authority in Argentina have laboratories of support to regulations functions on radiological and nuclear safety, safeguards and physical protection, that have a surface of 2950 m 2 in the Ezeiza Atomic Center. The manual describes in seven chapters the different techniques developed and applied in the laboratories along four decades of existence. The chapter 1: Dedicated to the treatment of environmental samples, described the procedures associated with the different types of samples: deposits, waters, sediments, vegetables, milk, fish and diet. The chapter 2: Details 48 radiochemical techniques associated to the measurements of americium 241, carbon 16, strontium 90, iodine 129, plutonium, radium 226, radon, uranium, nickel and actinides. The chapter 3: Describes the measurements techniques of alpha and gamma spectrometry. The different techniques of biological and physical dosimetry are described in the chapters 5 and 6 respectively. The final chapter is dedicated the techniques of external and internal contamination. It s important to emphasize that this manual contains the standardized technologies that the Nuclear Regulatory Authority of Argentina submits regularly to international comparisons

Emergency radiological monitoring and analysis: Federal Radiological Monitoring and Assessment Center

International Nuclear Information System (INIS)

Thome, D.J.

1995-01-01

The US Federal Radiological Emergency Response Plan (FRERP) provides the framework for integrating the various Federal agencies responding to a major radiological emergency. The FRERP authorizes the creation of the Federal Radiological Monitoring and Assessment Center (FRMAC), which is established to coordinate all Federal agencies involved in the monitoring and assessment of the off-site radiological conditions in support of the impacted State(s) and the Lead Federal Agency (LFA). Within the FRMAC, the Monitoring and Analysis Division (M ampersand A) is responsible for coordinating all FRMAC assets involved in conducting a comprehensive program of environmental monitoring, sampling, radioanalysis, and quality assurance. To assure consistency, completeness, and the quality of the data produced, a methodology and procedures manual is being developed. This paper discusses the structure, assets, and operations of the FRMAC M ampersand A and the content and preparation of the manual

Annual environmental monitoring report of the Lawrence Berkeley Laboratory

International Nuclear Information System (INIS)

Schleimer, G.E.

1989-06-01

The Environmental Monitoring Program of the Lawrence Berkeley Laboratory (LBL) is described. Data for 1988 are presented and general trends are discussed. In order to establish whether LBL research activities produced any impact on the population surrounding the laboratory, a program of environmental air and water sampling and continuous radiation monitoring was carried on throughout the year. For 1988, as in the previous several years, dose equivalents attributable to LBL radiological operations were a small fraction of both the relevant radiation protection guidelines (RPG) and of the natural radiation background. 16 refs., 7 figs., 21 tabs

Annual environmental monitoring report of the Lawrence Berkeley Laboratory

Energy Technology Data Exchange (ETDEWEB)

Schleimer, G.E. (ed.)

1989-06-01

The Environmental Monitoring Program of the Lawrence Berkeley Laboratory (LBL) is described. Data for 1988 are presented and general trends are discussed. In order to establish whether LBL research activities produced any impact on the population surrounding the laboratory, a program of environmental air and water sampling and continuous radiation monitoring was carried on throughout the year. For 1988, as in the previous several years, dose equivalents attributable to LBL radiological operations were a small fraction of both the relevant radiation protection guidelines (RPG) and of the natural radiation background. 16 refs., 7 figs., 21 tabs.

Overview of the aerial radiological measuring system (ARMS) program

International Nuclear Information System (INIS)

Deal, L.J.; Doyle, J.F. III.

1975-01-01

Since 1960 EG and G, Inc. has developed and maintained for the U.S. Energy Research and Development Administration (ERDA) a state-of-the-art radiation surveillance program called the Aerial Radiological Measuring System (ARMS). Radiological surveys covering more than 300,000 square miles have been performed. In addition to the radiation detector gear, the system includes an inertial navigation system, radar altimeter, meteorological probes, air sampler, air sample analyzer, multispectral cameras, aerial mapping camera and infrared scanner. The recently improved data acquisition system, REDAR, records all inputs digitally on magnetic tape and is readily mounted in fixed-wing aircraft or helicopters. The data analysis system, REDAC, is mounted in a mobile processing laboratory which accompanies the aircraft on surveys. Radiation isopleth maps, both for gross counts and selected isotopes, can be prepared in the field. Special computer software enables the ARMS to detect changes of less than 1.0 μR/hr in exposure rates between successive surveys of a given site

Troubles for the sustainability of the quality assurance in the laboratories of radiological control in Peru

International Nuclear Information System (INIS)

Gonzales, Susana; Lopez, Edith

2008-01-01

Full text: The Nuclear Energy Peruvian Institute (IPEN) has laboratories which offer services of radiological control. Radiometric analysis in raw and processed foodstuff is requested by several enterprises of both public and private sectors which uses the results for trading purposes like exportation, importation and licitations. The service of assays and calibration with reliable results has become a need due to the external audits performed by accredited laboratories to fulfil the requirements of the Peruvian standard organism. With the support of the International Atomic Energy Agency (IAEA), the IPEN laboratory of radiometric analysis implemented its quality system in 2001 under the ISO IEC 17025 Standard 'General Requirements for the Competence of the Calibration and Testing Laboratories' with the purpose to organize the activities and offer an enhanced service to the clients. The implementation of the quality system has allowed giving a better service with enhanced efficiency to the clients, assuring the reliability of the final output, the analytical results. It had been possible since the laboratories have participated in worldwide proficiency tests sponsored by the IAEA and currently work with reference material. The quality system allows identifying potential faults in any stage of the process in order to prevent any problem in the final output, assuring the appropriate quality of the issued analytical results and to take the necessary corrective actions to avoid those events to happen again. This study has identified and assessed several difficulties and troubles which prevent to fulfil the requirements of the Quality Standard and as a consequence, disable the sustainability of the quality systems and prevent the accreditation. Several proposals and solution alternatives which involve the Executive Staff and the proactive participation of the personnel are presented. (author)

Radiological assessment of decommissioned nuclear facilities

International Nuclear Information System (INIS)

Dickson, H.W.; Cottrell, W.D.

1976-01-01

A radiological survey of the former Middlesex Sampling Plant, Middlesex, New Jersey, has been completed. The surveyed property served as a uranium ore sampling plant during the 1940's and early 1950's. It was released for unrestricted use in 1967 following a radiological survey by the Atomic Energy Commission and is now a reserve training center for the U. S. Marine Sixth Motor Transport Battalion. The present survey was undertaken to determine whether the existing radiological status of the property is consistent with current health standards and radiation protection practices. The radiological survey included measurement of residual alpha, beta, and gamma contamination levels, radon and radon daughter concentrations in buildings, external gamma radiation levels on the site and on adjacent property, and radium concentrations in soil on the site and on adjacent property

Soil sampling intercomparison exercise by selected laboratories of the ALMERA Network

International Nuclear Information System (INIS)

2009-01-01

The IAEA's Seibersdorf Laboratories in Austria have the programmatic responsibility to provide assistance to Member State laboratories in maintaining and improving the reliability of analytical measurement results, both in radionuclide and trace element determinations. This is accomplished through the provision of reference materials of terrestrial origin, validated analytical procedures, training in the implementation of internal quality control, and through the evaluation of measurement performance by the organization of worldwide and regional interlaboratory comparison exercises. The IAEA is mandated to support global radionuclide measurement systems related to accidental or intentional releases of radioactivity in the environment. To fulfil this obligation and ensure a reliable, worldwide, rapid and consistent response, the IAEA coordinates an international network of analytical laboratories for the measurement of environmental radioactivity (ALMERA). The network was established by the IAEA in 1995 and makes available to Member States a world-wide network of analytical laboratories capable of providing reliable and timely analysis of environmental samples in the event of an accidental or intentional release of radioactivity. A primary requirement for the ALMERA members is participation in the IAEA interlaboratory comparison exercises, which are specifically organized for ALMERA on a regular basis. These exercises are designed to monitor and demonstrate the performance and analytical capabilities of the network members, and to identify gaps and problem areas where further development is needed. In this framework, the IAEA organized a soil sampling intercomparison exercise (IAEA/SIE/01) for selected laboratories of the ALMERA network. The main objective of this exercise was to compare soil sampling procedures used by different participating laboratories. The performance evaluation results of the interlaboratory comparison exercises performed in the framework of

ORNL necessary and sufficient standards for environment, safety, and health. Final report of the Identification Team for other industrial, radiological, and non-radiological hazard facilities

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-07-01

This Necessary and Sufficient (N and S) set of standards is for Other Industrial, Radiological, and Non-Radiological Hazard Facilities at Oak Ridge National Laboratory (ORNL). These facility classifications are based on a laboratory-wide approach to classify facilities by hazard category. An analysis of the hazards associated with the facilities at ORNL was conducted in 1993. To identify standards appropriate for these Other Industrial, Radiological, and Non-Radiological Hazard Facilities, the activities conducted in these facilities were assessed, and the hazards associated with the activities were identified. A preliminary hazards list was distributed to all ORNL organizations. The hazards identified in prior hazard analyses are contained in the list, and a category of other was provided in each general hazard area. A workshop to assist organizations in properly completing the list was held. Completed hazard screening lists were compiled for each ORNL division, and a master list was compiled for all Other Industrial, Radiological Hazard, and Non-Radiological facilities and activities. The master list was compared against the results of prior hazard analyses by research and development and environment, safety, and health personnel to ensure completeness. This list, which served as a basis for identifying applicable environment, safety, and health standards, appears in Appendix A.

ORNL necessary and sufficient standards for environment, safety, and health. Final report of the Identification Team for other industrial, radiological, and non-radiological hazard facilities

International Nuclear Information System (INIS)

1998-07-01

This Necessary and Sufficient (N and S) set of standards is for Other Industrial, Radiological, and Non-Radiological Hazard Facilities at Oak Ridge National Laboratory (ORNL). These facility classifications are based on a laboratory-wide approach to classify facilities by hazard category. An analysis of the hazards associated with the facilities at ORNL was conducted in 1993. To identify standards appropriate for these Other Industrial, Radiological, and Non-Radiological Hazard Facilities, the activities conducted in these facilities were assessed, and the hazards associated with the activities were identified. A preliminary hazards list was distributed to all ORNL organizations. The hazards identified in prior hazard analyses are contained in the list, and a category of other was provided in each general hazard area. A workshop to assist organizations in properly completing the list was held. Completed hazard screening lists were compiled for each ORNL division, and a master list was compiled for all Other Industrial, Radiological Hazard, and Non-Radiological facilities and activities. The master list was compared against the results of prior hazard analyses by research and development and environment, safety, and health personnel to ensure completeness. This list, which served as a basis for identifying applicable environment, safety, and health standards, appears in Appendix A

Radiological Research Accelerator Facility

International Nuclear Information System (INIS)

Goldhagen, P.; Marino, S.A.; Randers-Pehrson, G.; Hall, E.J.

1986-01-01

The Radiological Research Accelerator Facility (RARAF) is based on a 4-MV Van de Graaff accelerator, which can be used to generate a variety of well-characterized radiation beams for research in radiobiology and radiological physics. It is part of the Radiological Research Laboratory (RRL), and its operation is supported as a National Facility by the US Department of Energy. RARAF is available to all potential users on an equal basis, with priorities based on the recommendations of a Scientific Advisory Committee. Facilities and services are provided to users, but the research projects themselves must be supported separately. This chapter presents a brief description of current experiments being carried out at RARAF and of the operation of the Facility from January through June, 1986. Operation of the Facility for all of 1985 was described in the 1985 Progress Report for RARAF. The experiments described here were supported by various Grants and Contracts from NIH and DOE and by the Statens Stralskyddsinstitut of Sweden

Interactive, Computer-Based Training Program for Radiological Workers

International Nuclear Information System (INIS)

Trinoskey, P.A.; Camacho, P.I.; Wells, L.

2000-01-01

Lawrence Livermore National Laboratory (LLNL) is redesigning its Computer-Based Training (CBT) program for radiological workers. The redesign represents a major effort to produce a single, highly interactive and flexible CBT program that will meet the training needs of a wide range of radiological workers--from researchers and x-ray operators to individuals working in tritium, uranium, plutonium, and accelerator facilities. The new CBT program addresses the broad diversity of backgrounds found at a national laboratory. When a training audience is homogeneous in terms of education level and type of work performed, it is difficult to duplicate the effectiveness of a flexible, technically competent instructor who can tailor a course to the express needs and concerns of a course's participants. Unfortunately, such homogeneity is rare. At LLNL, they have a diverse workforce engaged in a wide range of radiological activities, from the fairly common to the quite exotic. As a result, the Laboratory must offer a wide variety of radiological worker courses. These include a general contamination-control course in addition to radioactive-material-handling courses for both low-level laboratory (i.e., bench-top) activities as well as high-level work in tritium, uranium, and plutonium facilities. They also offer training courses for employees who work with radiation-generating devices--x-ray, accelerator, and E-beam operators, for instance. However, even with the number and variety of courses the Laboratory offers, they are constrained by the diversity of backgrounds (i.e., knowledge and experience) of those to be trained. Moreover, time constraints often preclude in-depth coverage of site- and/or task-specific details. In response to this situation, several years ago LLNL began moving toward computer-based training for radiological workers. Today, that CBT effort includes a general radiological safety course developed by the Department of Energy's Hanford facility and a

Sampling and analysis plan for the gunite and associated tanks interim remedial action, wall coring and scraping at Oak Ridge National Laboratory, Oak Ridge, Tennessee

International Nuclear Information System (INIS)

1998-02-01

This Sampling and Analysis Plan documents the procedures for collecting and analyzing wall core and wall scraping samples from the Gunite and Associated Tanks. These activities are being conducted to support the Comprehensive Environmental Response, Compensation, and Liability Act at the gunite and associated tanks interim remedial action at Oak Ridge National Laboratory in Oak Ridge, Tennessee. The sampling and analysis activities will be performed in concert with sludge retrieval and sluicing of the tanks. Wall scraping and/or wall core samples will be collected from each quadrant in each tank by using a scraping sampler and/or a coring drill deployed by the Houdini robot vehicle. Each sample will be labeled, transported to the Radioactive Materials Analytical Laboratory, and analyzed for physical and radiological characteristics, including total activity, gross alpha, gross beta, radioactive strontium and cesium, and other alpha- and gamma-emitting radionuclides. The data quality objectives process, based on US Environmental Protection Agency guidance, was applied to identify the objectives of this sampling and analysis. The results of the analysis will be used to (1) validate predictions of a strontium concrete diffusion model, (2) estimate the amount of radioactivity remaining in the tank shells, (3) provide information to correlate with measurements taken by the Gunite Tank Isotope Mapping Probe and the Characterization End Effector, and (4) estimate the performance of the wall cleaning system. This revision eliminates wall-scraping samples from all tanks, except Tank W-3. The Tank W-3 experience indicated that the wall scrapper does not collect sufficient material for analysis

Emergency response exercise of laboratories equipped with gammaspectrometry

International Nuclear Information System (INIS)

Mala, H.; Jezkova, T.; Rulik, P.; Beckova, V.

2014-01-01

Seven laboratories equipped with semiconductor gamma spectrometry (HPGe detectors) are currently included in the Radiation Monitoring Network (RMN) in the Czech Republic. These laboratories have more than 30 spectrometric chains and approximately 20 'experts' and 70 'users' who would guarantee measurements during the radiological emergency (RE). The emergency exercise was carried out in 5 of them in 2014 (in 4 of them also in 2013). The aim was to test repeatedly their capacity in existing technical facilities and with current staff in the event of a RE and identify problems (bottlenecks) in the whole process from receipt of samples to entering the results into the central database of RMN. Duration of the exercise was 12 hours, due to the shortage of staff; work in one 12-hour shift is presumed during a RE, which the laboratories should be able to provide for 14 days. These exercise samples covered a wide range of commodities that would probably come to the laboratories during the RE (aerosol filters, sorbents for sorption of gaseous forms of iodine, fallout, surface and drinking waters, food chain components and soils). Some of the samples were previously spiked with 85 Sr, 88 Y and 40 K (in the exercise these nuclides represented actual contamination that would occur in RE); liquid samples were spiked with 85 Sr and 88 Y and bulk materials with 40 K.During the exercise almost 800 samples were analysed; in addition, the automatic gamma counter (GA) in Prague laboratory measured other 90 samples automatically during the night (samples were prepared during the day-shift). On the basis of the results the total measuring capacity of the laboratories of RMN CR was estimated at about 1300 samples per day. (authors)

Laboratory Validation and Field Assessment of Petroleum Laboratory Technicians' Dermal Exposure to Crude Oil Using a Wipe Sampling Method.

Science.gov (United States)

Galea, Karen S; Mueller, Will; Arfaj, Ayman M; Llamas, Jose L; Buick, Jennifer; Todd, David; McGonagle, Carolyn

2018-05-21

Crude oil may cause adverse dermal effects therefore dermal exposure is an exposure route of concern. Galea et al. (2014b) reported on a study comparing recovery (wipe) and interception (cotton glove) dermal sampling methods. The authors concluded that both methods were suitable for assessing dermal exposure to oil-based drilling fluids and crude oil but that glove samplers may overestimate the amount of fluid transferred to the skin. We describe a study which aimed to further evaluate the wipe sampling method to assess dermal exposure to crude oil, with this assessment including extended sample storage periods and sampling efficiency tests being undertaken at environmental conditions to mimic those typical of outdoor conditions in Saudi Arabia. The wipe sampling method was then used to assess the laboratory technicians' actual exposure to crude oil during typical petroleum laboratory tasks. Overall, acceptable storage efficiencies up to 54 days were reported with results suggesting storage stability over time. Sampling efficiencies were also reported to be satisfactory at both ambient and elevated temperature and relative humidity environmental conditions for surrogate skin spiked with known masses of crude oil and left up to 4 h prior to wiping, though there was an indication of reduced sampling efficiency over time. Nineteen petroleum laboratory technicians provided a total of 35 pre- and 35 post-activity paired hand wipe samples. Ninety-three percent of the pre-exposure paired hand wipes were less than the analytical limit of detection (LOD), whereas 46% of the post-activity paired hand wipes were less than the LOD. The geometric mean paired post-activity wipe sample measurement was 3.09 µg cm-2 (range 1.76-35.4 µg cm-2). It was considered that dermal exposure most frequently occurred through direct contact with the crude oil (emission) or via deposition. The findings of this study suggest that the wipe sampling method is satisfactory in quantifying

Radiological characterization of practices employed at the Center for the Protection and Hygiene of Radiation (CPHR)

International Nuclear Information System (INIS)

Domenech Nieves, H.; Callis Fernandez, E.

1998-01-01

This work makes the radiological characterization of practices carried out at the CPHR to evaluate dose possible restrictions. The characterization was based on data processed from annual individual doses to which workers were exposed during 1994-1997. This was done in a global way and also for different groups of workers identified (Group of Radioactive Refuses; Secondary laboratory of Dosimetric Calibration; the Laboratory of Environmental Radiological Surveillance and the Group that Evaluates Radiological Safety)

Environmental monitoring radiological programs for the nuclear centre and the low level radioactive waste facility in Mexico

International Nuclear Information System (INIS)

Quintero, E.; Cervantes, L.; Rojas, V.

2006-01-01

The National Institute of Nuclear Research of Mexico (ININ) has its Laboratory of Environmental Radiological Monitoring, (LVRA), to assure the critical population and the environment they are not exposed to radiation doses greater than the limits established by the national and international legislation, this laboratory carries out environmental monitoring radiological programs the Nuclear Centre and its surroundings and the Low Level Radioactive Waste Facility (CADER) and its around. In order to carry out these programs the LVRA has rooms for evaporation, drying, grinding, ashing of environmental and food samples, and a laboratory for gamma ray spectrometry, liquid scintillation, alpha-beta gross counting and computer room. Since the year 2000 the (ININ) has tried to implant the quality system ISO 9001:2000 including a its (LVRA). This quality system includes: a Plan of Quality, Quality Manual, programs of technical and administrative document elaboration, technical and administrative procedures, technical and administrative qualification programmes for the laboratory staff, maintenance and calibration programs for measurement systems and finally participation in national and international exercises of intercomparison. The ININ counts with the management of quality assurance to verify these programs, in addition, our Nuclear Regulatory Commission (CNSNS) carries out periodic audits to authorize the of use and handling of radioactive and nuclear material licenses of these facilities. In this work we presented the advances and difficulties found in the implantation of the quality system, also we present the benefits obtained with uses of this system, the samples analyses results, and the calculation of the annual dose to the critical population for the last five years. In addition, we presented the calculation the radionuclides concentration tendencies in different sample types, according to our (CNSNS) requirements. In the same way the results of the calibrations

Results of the radiological survey at 200 State Route 17 (MJ035), Maywood, New Jersey

International Nuclear Information System (INIS)

Foley, R.D.; Crutcher, J.W.; Carrier, R.F.; Floyd, L.M.

1989-02-01

The property discussed in this report and properties in its vicinity contaminated with residues from the former Maywood Chemical Works (MCW) were included as a decontamination research and development project under the DOE Formerly Utilized Sites Remedial Action Program. As part of this project, DOE is conducting radiological surveys in the vicinity of the site to identify properties contaminated with residues derived from the MCW. The principal radionuclide of concern is thorium-232. The radiological survey discussed in this report is part of that effort and was conducted, at the request of DOE, by members of the Measurement Applications and Development Group of Oak Ridge National Laboratory. A radiological survey of the commercial property at 200 State Route 17, Maywood, New Jersey, was conducted during 1987. The survey and sampling of the ground surface and subsurface were carried out on September 2, 1987. 4 refs., 2 figs., 3 tabs

Non-destructive in situ measurement of radiological distributions in Hanford Site waste tanks

International Nuclear Information System (INIS)

Troyer, G.L.

1996-01-01

Measurement of radiological materials in defense nuclear waste stored in underground tanks at the Hanford Site is being used to indicate material distributions. Both safety assessment and future processing challenges are dependent on knowledge of the distribution kinds, and quantities of various key components. Data from CdTe and neutron detector measurements are shown and correlated with physical sampling and laboratory results. The multiple assay approach is shown to increase the confidence about the material distributions. As a result, costs of physical sampling and destructive analyses can be controlled while not severely limiting the uncertainty of results

Idaho National Engineering Laboratory Radiological Control performance indicator report: First quarter, calendar year 1995

International Nuclear Information System (INIS)

Aitken, S.B.

1995-07-01

The INEL Radiological Control Performance Indicator Report is provided quarterly, inaccordance with Article 133 of the INEL Radiological Control Manual. Indicators are used as a measure of performance of the Radiological Control Program and as a motivation for improvement, not as a goal in themselves. These indicators should be used by management to assist in focusing priorities and attention and adherence to As-Low-As-Reasonably-Achievable (ALARA) practices. The ALARA Committees establish ALARA goals for the INEL based on forecasts and goals provided by each facility organizational manager or supervisor.Performance goals are realistic and measurable. Stringent goals are set at least annually to reflect expected workloads and improvement of radiological performance. Goals higher than previous goals may occasionally be set due to changes in work scope or mission. The INEL Radiological Control Performance Indicators consist of: Collective dose in person-rem; average worker dose, maximum dose to a worker, and maximum neutron dose to a worker;the number of skin and clothing contaminations, including the number of contaminated wounds and facial contaminations; the number of radioactive material intakes; the area of Contamination, High Contamination, and Airborne Radioactivity Areas in square feet; and airborne radioactivity events and spills

Radiological characterization of liquid effluent hold up tank for generating data base for future decommissioning

International Nuclear Information System (INIS)

Sapkal, Jyotsna A.; Singh, Pratap; Verma, Amit; Yadav, R.K.B.; Thakare, S.V.

2018-01-01

Operations at Radiological laboratory facilities are involved in fabrication of high activity radioactive sources like 60 Co, 192 1r and 137 Cs, handling of long lived radionuclides like 137 Cs/ 90 Sr, radiochemical processing and production of short-lived radioisotopes for medical diagnosis and treatment of patients. Typical liquid waste management feature at any Radiological Laboratory facility primarily consists of effluent tanks which store the liquid effluent wastes generated during radiochemical processing and fabrication of reactor produced radioisotopes. The liquid waste generated from various laboratories are collected to low level sump tanks from where it is transferred to hold up tanks. The liquid waste is transferred to centralized effluent treatment plant, analysis and characterization of the same is carried out. This paper explains the characterization study of samples drawn from the liquid effluent tank which would be helpful for planning for decontamination as well as for decommissioning and in management of radioactive wastes. In this study the crud deposited at the bottom of tank was collected for gamma spectrometry analysis. Radiation field was measured, at the bottom of the tank for correlating the activity present and the radiation field

Empirical insights and considerations for the OBT inter-laboratory comparison of environmental samples.

Science.gov (United States)

Kim, Sang-Bog; Roche, Jennifer

2013-08-01

Organically bound tritium (OBT) is an important tritium species that can be measured in most environmental samples, but has only recently been recognized as a species of tritium in these samples. Currently, OBT is not routinely measured by environmental monitoring laboratories around the world. There are no certified reference materials (CRMs) for environmental samples. Thus, quality assurance (QA), or verification of the accuracy of the OBT measurement, is not possible. Alternatively, quality control (QC), or verification of the precision of the OBT measurement, can be achieved. In the past, there have been differences in OBT analysis results between environmental laboratories. A possible reason for the discrepancies may be differences in analytical methods. Therefore, inter-laboratory OBT comparisons among the environmental laboratories are important and would provide a good opportunity for adopting a reference OBT analytical procedure. Due to the analytical issues, only limited information is available on OBT measurement. Previously conducted OBT inter-laboratory practices are reviewed and the findings are described. Based on our experiences, a few considerations were suggested for the international OBT inter-laboratory comparison exercise to be completed in the near future. Crown Copyright © 2013. Published by Elsevier Ltd. All rights reserved.

Brookhaven National Laboratory site environmental report for calendar year 1996

Energy Technology Data Exchange (ETDEWEB)

Schroeder, G.L.; Paquette, D.E.; Naidu, J.R.; Lee, R.J.; Briggs, S.L.K.

1998-01-01

This report documents the results of the Environmental Monitoring Program at Brookhaven National Laboratory and summarizes information about environmental compliance for 1996. To evaluate the effect of Brookhaven National Laboratory`s operations on the local environment, measurements of direct radiation, and of a variety of radionuclides and chemical compounds in the ambient air, soil, sewage effluent, surface water, groundwater, fauna, and vegetation were made at the Brookhaven National Laboratory site and at adjacent sites. The report also evaluates the Laboratory`s compliance with all applicable guides, standards, and limits for radiological and non-radiological emissions and effluents to the environment.

Drilling induced damage of core samples. Evidences from laboratory testing and numerical modelling

International Nuclear Information System (INIS)

Lanaro, Flavio

2008-01-01

Extensive sample testing in uniaxial and Brazilian test conditions were carried out for the Shobasama and MIU Research Laboratory Site (Gifu Pref., Japan). The compressive and tensile strength of the samples was observed to be negatively correlated to the in-situ stress components. Such correlation was interpreted as stress-release induced sample damage. Similar stress conditions were then numerically simulated by means of the BEM-DDM code FRACOD 2D in plane strain conditions. This method allows for explicitly consider the influence of newly initiated or propagating fractures on the stress field and deformation of the core during drilling process. The models show that already at moderate stress levels some fracturing of the core during drilling might occur leading to reduced laboratory strength of the samples. Sample damage maps were produced independently from the laboratory test results and from the numerical models and show good agreement with each other. (author)

Radiological reference base line establishment around CENM site

International Nuclear Information System (INIS)

Elkhoukhi, T.; Dehbi, N.; Amechmachi, N.

2008-01-01

Full text: As for any installation presenting risks for its surrounding, CENM (Centre d'Etudes Nucleaires de Maamora) that accommodates TRIGA Mark II Research Reactor and related laboratories is subjected to a statutory requirement stipulating that the CNESTEN (Centre National De L'Energie Des Sciences Et Des Techniques Nucleaires) that is in charge the operating of CENM must define its own environmental monitoring program assuring that the nuclear installation is in appropriateness with its environment. In this frame , since 1996 the team of USE (Unite Surveillance de L'Environnement) is conducting periodic work consisting in in-situ measurement of ambient gamma rays and collect of environmental samples and their preparation for adequate analysis form required for each radioactive measurement system. This first step of the environmental monitoring program allows establishing the radiological base line on the CENM's site. This base line is necessary to inform on the present radiological state in order to detect any change of this state consequently to the operating of the reactor or the arrival of abnormal radioactive panache from any source.

Secondary standards laboratories for ionizing radiation calibrations: the national laboratory interests

International Nuclear Information System (INIS)

Roberson, P.L.; Campbell, G.W.

1984-11-01

The national laboratories are probable candidates to serve as secondary standards laboratories for the federal sector. Representatives of the major Department of Energy laboratories were polled concerning attitudes toward a secondary laboratory structure. Generally, the need for secondary laboratories was recognized and the development of such a program was encouraged. The secondary laboratories should be reviewed and inspected by the National Bureau of Standards. They should offer all of the essential, and preferably additional, calibration services in the field of radiological health protection. The selection of secondary laboratories should be based on economic and geographic criteria and/or be voluntary. 1 ref., 2 tabs

Improved monitoring procedure for Iodine -131 in radiochemical process laboratory

International Nuclear Information System (INIS)

Singh, Pratap; Yadav, R.K.B.; Anilkumar, S.; Gopalakrishnan, R.K.; Chakraborty, S.

2016-01-01

Radiation Hazard Control Unit at Isotope wing provides radiological safety support and advises for safe processing and production of radiopharmaceuticals. Tellurium Oxide (TeO 2 ), irradiated in a nuclear reactor, is processed in a process laboratory for separating 131 I using dry distillation technique. The workplace environment is being assessed for airborne radioactivity using installed Static Air Samplers (SASs). SASs contains two filter media (glass fibre and charcoal impregnated paper) to collect airborne 131 I radioactivity and laboratory air sampled at 50 litres per minutes (lpm). Personal Air Sampler (PAS) consists of three types of filters viz. a glass fibre, charcoal impregnated paper and cartridges containing activated charcoal granules. Three combinations were studied at a sampling rate of 5 lpm

NVLAP activities at Department of Defense calibration laboratories

Energy Technology Data Exchange (ETDEWEB)

Schaeffer, D.M. [Defense Nuclear Agency, Alexandria, VA (United States)

1993-12-31

There are 367 active radiological instrument calibration laboratories within the U.S. Department of Defense (DoD). Each of the four services in DoD manages, operates, and certifies the technical proficiency and competency of those laboratories under their cognizance. Each service has designated secondary calibration laboratories to trace all calibration source standards to the National Institute of Standards and Technology. Individual service radiological calibration programs and capabilities, present and future, are described, as well as the measurement quality assurance (MQA) processes for their traceability. National Voluntary Laboratory Accreditation Program (NVLAP) programs for dosimetry systems are briefly summarized. Planned NVLAP accreditation of secondary laboratories is discussed in the context of current technical challenges and future efforts.

NVLAP activities at Department of Defense calibration laboratories

International Nuclear Information System (INIS)

Schaeffer, D.M.

1993-01-01

There are 367 active radiological instrument calibration laboratories within the U.S. Department of Defense (DoD). Each of the four services in DoD manages, operates, and certifies the technical proficiency and competency of those laboratories under their cognizance. Each service has designated secondary calibration laboratories to trace all calibration source standards to the National Institute of Standards and Technology. Individual service radiological calibration programs and capabilities, present and future, are described, as well as the measurement quality assurance (MQA) processes for their traceability. National Voluntary Laboratory Accreditation Program (NVLAP) programs for dosimetry systems are briefly summarized. Planned NVLAP accreditation of secondary laboratories is discussed in the context of current technical challenges and future efforts

A prequalifying program for evaluating the analytical performance of commercial laboratories

International Nuclear Information System (INIS)

Reith, C.C.; Bishop, C.T.

1987-01-01

Soil and water samples were spiked with known activities of radionuclides and sent to seven commercial laboratories that had expressed an interest in analyzing environmental samples for the Waste Isolation Pilot Plant (WIPP). This Prequalifying Program was part of the selection process for an analytical subcontractor for a three-year program of baseline radiological surveillance around the WIPP site. Both media were spiked at three different activity levels with several transuranic radionuclides, as well as tritium, fission products, and activation products. Laboratory performance was evaluated by calculating relative error for each radionuclide in each sample, assigning grade values, and compiling grades into report cards for each candidate. Results for the five laboratories completing the Prequalifying Program were pooled to reveal differing degrees of difficulty among the treatments and radionuclides. Interlaboratory comparisons revealed systematic errors in the performance of one candidate. The final report cards contained clear differences among overall grades for the five laboratories, enabling analytical performance to be used as a quantitative criterion in the selection of an analytical subcontractor. (author)

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.)

Argonne National Laboratory - West's approach to filter characterization

International Nuclear Information System (INIS)

Miller, T. A.

1999-01-01

Like other DOE facilities, ANL-W uses a variety of nuclear grade, industrial grade, or furnace-type particulate filters to control airborne radioactivity and hazardous contaminants in radiological containment structures or processes. As designed, these filters entrain and ultimately concentrate contaminants in the media. Toxic metal contaminants include cadmium, chromium, lead; and mercury present in sufficient concentrations to exhibit the hazardous waste characteristic of toxicity as defined in 40 CFR 261.24. Radionuclide contaminants deposited in the media may at times accumulate in sufficient quantity to classify the filter as transuranic or remote-handled waste. Upon their removal from the ventilation system, these particulate filters become wastes, which must be characterized to determine their hazardous and radioactive classifications. A well defined filter characterization process is essential for the proper/consistent waste characterization and minimization and for maintaining personnel radiological exposures as-low-as-reasonably-achievable (ALARA) (1,2). ANL-W has developed an approach to filter sampling and characterization to meet these needs. The ANL-W filter sampling and characterization process is designed to ensure representative sampling and/or process knowledge is utilized in characterizing the filters. The data obtained through sampling and/or process knowledge is used to show compliance with the Resource Conservation and Recovery Act (3) and Treatment/Storage/Disposal Facility Waste Acceptance Criteria. The ANL-W filter characterization involves the collection of process information, filter handling and sampling, sample analysis, data management filter characterization, and waste handling. Each element of the process is streamlined to ensure proper characterization while minimizing radiological exposure to maintenance workers, samplers, laboratory personnel, and waste handlers

Radiological, physical, and chemical characterization of transuranic wastes stored at the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

Apel, M.L.; Becker, G.K.; Ragan, Z.K.; Frasure, J.; Raivo, B.D.; Gale, L.G.; Pace, D.P.

1994-03-01

This document provides radiological, physical and chemical characterization data for transuranic radioactive wastes and transuranic radioactive and hazardous (i.e., mixed) wastes stored at the Idaho National Engineering Laboratory and considered for treatment under the Private Sector Participation Initiative Program (PSPI). Waste characterization data are provided in the form of INEL Waste Profile Sheets. These documents provide, for each content code, information on waste identification, waste description, waste storage configuration, physical/chemical waste composition, radionuclide and associated alpha activity waste characterization data, and hazardous constituents present in the waste. Information is provided for 139 waste streams which represent an estimated total volume of 39,380 3 corresponding to a total mass of approximately 19,000,000 kg. In addition, considerable information concerning alpha, beta, gamma, and neutron source term data specific to Rocky Flats Plant generated waste forms stored at the INEL are provided to assist in facility design specification

The intellectual contribution of laboratory medicine professionals to research papers on laboratory medicine topics published in high-impact general medicine journals.

Science.gov (United States)

Escobar, Pedro Medina; Nydegger, Urs; Risch, Martin; Risch, Lorenz

2012-03-01

An author is generally regarded as an individual "who has made substantial intellectual academic contributions to a published study". However, the extent of the contribution that laboratory medicine professionals have made as authors of research papers in high-impact medical journals remains unclear. From 1 January 2004 to 31 March 2009, 4837 original research articles appeared in the: New England Journal of Medicine, Lancet, Annals of Internal Medicine, JAMA and BMJ. Using authorship as an indicator of intellectual contribution, we analyzed articles that included laboratory medicine parameters in their titles in an observational cross-sectional study. We also extracted data regarding radiological topics that were published during the same time within the same journals. Out of 481 articles concerning laboratory medicine topics, 380 provided information on the affiliations of the authors. At least one author from an institution within the field of laboratory medicine was listed in 212 articles (55.8%). Out of 3943 co-authors, only 756 (19.2%) were affiliated with laboratory medicine institutions. Authors from laboratory medicine institutions were listed as the first, last or corresponding authors in 99 articles (26.1%). The comparative proportions for author affiliation from 55 radiology articles were significantly higher, as 72.7% (p=0.026) of articles and 24.8% (p=0.001) of authors indicated an affiliation with a radiology institution. Radiology professionals from 72.7% of the articles were listed as either the first, last or corresponding authors (pgeneral medicine journals.

Geostatistics for radiological characterization: overview and application cases

International Nuclear Information System (INIS)

Desnoyers, Yvon

2016-01-01

The objective of radiological characterization is to find a suitable balance between gathering data (constrained by cost, deadlines, accessibility or radiation) and managing the issues (waste volumes, levels of activity or exposure). It is necessary to have enough information to have confidence in the results without multiplying useless data. Geo-statistics processing of data considers all available pieces of information: historical data, non-destructive measurements and laboratory analyses of samples. The spatial structure modelling is then used to produce maps and to estimate the extent of radioactive contamination (surface and depth). Quantifications of local and global uncertainties are powerful decision-making tools for better management of remediation projects at contaminated sites, and for decontamination and dismantling projects at nuclear facilities. They can be used to identify hot spots, estimate contamination of surfaces and volumes, classify radioactive waste according to thresholds, estimate source terms, and so on. The spatial structure of radioactive contamination makes the optimization of sampling (number and position of data points) particularly important. Geo-statistics methodology can help determine the initial mesh size and reduce estimation uncertainties. Several show cases are presented to illustrate why and how geo-statistics can be applied to a range of radiological characterization where investigated units can represent very small areas (a few m 2 or a few m 3 ) or very large sites (at a country scale). The focus is then put on experience gained over years in the use of geo-statistics and sampling optimization. (author)

The economic impact of poor sample quality in clinical chemistry laboratories: results from a global survey.

Science.gov (United States)

Erdal, Erik P; Mitra, Debanjali; Khangulov, Victor S; Church, Stephen; Plokhoy, Elizabeth

2017-03-01

Background Despite advances in clinical chemistry testing, poor blood sample quality continues to impact laboratory operations and the quality of results. While previous studies have identified the preanalytical causes of lower sample quality, few studies have examined the economic impact of poor sample quality on the laboratory. Specifically, the costs associated with workarounds related to fibrin and gel contaminants remain largely unexplored. Methods A quantitative survey of clinical chemistry laboratory stakeholders across 10 international regions, including countries in North America, Europe and Oceania, was conducted to examine current blood sample testing practices, sample quality issues and practices to remediate poor sample quality. Survey data were used to estimate costs incurred by laboratories to mitigate sample quality issues. Results Responses from 164 participants were included in the analysis, which was focused on three specific issues: fibrin strands, fibrin masses and gel globules. Fibrin strands were the most commonly reported issue, with an overall incidence rate of ∼3%. Further, 65% of respondents indicated that these issues contribute to analyzer probe clogging, and the majority of laboratories had visual inspection and manual remediation practices in place to address fibrin- and gel-related quality problems (55% and 70%, respectively). Probe maintenance/replacement, visual inspection and manual remediation were estimated to carry significant costs for the laboratories surveyed. Annual cost associated with lower sample quality and remediation related to fibrin and/or gel globules for an average US laboratory was estimated to be $100,247. Conclusions Measures to improve blood sample quality present an important step towards improved laboratory operations.

Measurement of radioactivity in the environment - Soil - Part 2: Guidance for the selection of the sampling strategy, sampling and pre-treatment of samples

International Nuclear Information System (INIS)

2007-01-01

This part of ISO 18589 specifies the general requirements, based on ISO 11074 and ISO/IEC 17025, for all steps in the planning (desk study and area reconnaissance) of the sampling and the preparation of samples for testing. It includes the selection of the sampling strategy, the outline of the sampling plan, the presentation of general sampling methods and equipment, as well as the methodology of the pre-treatment of samples adapted to the measurements of the activity of radionuclides in soil. This part of ISO 18589 is addressed to the people responsible for determining the radioactivity present in soil for the purpose of radiation protection. It is applicable to soil from gardens, farmland, urban or industrial sites, as well as soil not affected by human activities. This part of ISO 18589 is applicable to all laboratories regardless of the number of personnel or the range of the testing performed. When a laboratory does not undertake one or more of the activities covered by this part of ISO 18589, such as planning, sampling or testing, the corresponding requirements do not apply. Information is provided on scope, normative references, terms and definitions and symbols, principle, sampling strategy, sampling plan, sampling process, pre-treatment of samples and recorded information. Five annexes inform about selection of the sampling strategy according to the objectives and the radiological characterization of the site and sampling areas, diagram of the evolution of the sample characteristics from the sampling site to the laboratory, example of sampling plan for a site divided in three sampling areas, example of a sampling record for a single/composite sample and example for a sample record for a soil profile with soil description. A bibliography is provided

Estimates of laboratory accuracy and precision on Hanford waste tank samples

International Nuclear Information System (INIS)

Dodd, D.A.

1995-01-01

A review was performed on three sets of analyses generated in Battelle, Pacific Northwest Laboratories and three sets generated by Westinghouse Hanford Company, 222-S Analytical Laboratory. Laboratory accuracy and precision was estimated by analyte and is reported in tables. The sources used to generate this estimate is of limited size but does include the physical forms, liquid and solid, which are representative of samples from tanks to be characterized. This estimate was published as an aid to programs developing data quality objectives in which specified limits are established. Data resulting from routine analyses of waste matrices can be expected to be bounded by the precision and accuracy estimates of the tables. These tables do not preclude or discourage direct negotiations between program and laboratory personnel while establishing bounding conditions. Programmatic requirements different than those listed may be reliably met on specific measurements and matrices. It should be recognized, however, that these are specific to waste tank matrices and may not be indicative of performance on samples from other sources

A radiological and chemical investigation of the 7500 Area Contamination Site at Oak Ridge National Laboratory, Oak Ridge, Tennessee

International Nuclear Information System (INIS)

Williams, J.K.; Foley, R.D.; Tiner, P.F.; Hatmaker, T.L.; Uziel, M.S.; Swaja, R.E.

1993-05-01

A radiological and chemical investigation of the 7500 Area Contamination Site at Oak Ridge National Laboratory (ORNL) was conducted intermittently from February 1992 through May 1992. The investigation was performed by the Measurement Applications and Development Group of the Health and Safety Research Division of ORNL at the request of the US Department of Energy's Oak Ridge Operations Office and the ORNL Environmental Restoration Program. Results of this investigation indicate that the source of radioactive contamination at the point of the contamination incident is from one of the underground abandoned lines. The contamination in soil is likely the result of residual contamination from years of waste transport and maintenance operations (e.g., replacement of degraded joints, upgrading or replacement of entire pipelines, and associated landscaping activities). However, because (1) there is currently an active LLW line positioned in the same subsurface trench with the abandoned lines and (2) the physical condition of the abandoned lines may be brittle, this inquiry could not determine which abandoned line was responsible for the subsurface contamination. Soil sampling at the location of the contamination incident and along the pipeline route was performed in a manner so as not to damage the active LLW line and abandoned lines. Recommendations for corrective actions are included

Radiological protection report 2012

International Nuclear Information System (INIS)

2013-06-01

Two years after the massive release of radiation from the nuclear power plants at Fukushima Dai-ichi, the repercussions continue to preoccupy the radiological and emergency protection community, both in Switzerland and internationally. In Switzerland the Swiss Federal Nuclear Safety Inspectorate (ENSI) has initiated measures as part of the European Union Stress Tests and has its own Fukushima Action Plan. In this Annual Report, ENSI focuses on radiological protection in Swiss nuclear facilities. The average individual dose has changed little compared with previous years. At 0.7 mSv, it is significantly below the limit both for persons exposed to radiation during their work (20 mSv) and the annual average rate of exposure for the population in Switzerland as a whole (5.5 mSv). In terms of collective doses, the extensive maintenance work at the Leibstadt power plant (KKL) resulted in a doubling of rates compared with recent years. However, in the remaining nuclear facilities the rates have not changed significantly. The highest individual dose during the year under review was 13 mSv. Exposure rates in 2012 for all those exposed to radiation during work in facilities subject to ENSI surveillance were below the maximum limit. Greater attention is now being given to work in high and variable radiation fields and in difficult conditions. Swiss nuclear facilities continue to operate a consistent radiological protection approach. Measuring equipment plays an important role in radiological protection. Having conducted a range of inspections and comparative measurements of aerosol-iodine filters and waste water sampling together with measurements in the field of personal dosimetry, ENSI has concluded that the required measuring equipment for radiological protection exists, that this equipment is correctly used and provides reliable data. ENSI maintains a test laboratory that analyses samples from nuclear facilities and their immediate vicinity and also conducts field

Biological Treatment of Petroleum in Radiologically Contaminated Soil

Energy Technology Data Exchange (ETDEWEB)

BERRY, CHRISTOPHER

2005-11-14

This chapter describes ex situ bioremediation of the petroleum portion of radiologically co-contaminated soils using microorganisms isolated from a waste site and innovative bioreactor technology. Microorganisms first isolated and screened in the laboratory for bioremediation of petroleum were eventually used to treat soils in a bioreactor. The bioreactor treated soils contaminated with over 20,000 mg/kg total petroleum hydrocarbon and reduced the levels to less than 100 mg/kg in 22 months. After treatment, the soils were permanently disposed as low-level radiological waste. The petroleum and radiologically contaminated soil (PRCS) bioreactor operated using bioventing to control the supply of oxygen (air) to the soil being treated. The system treated 3.67 tons of PCRS amended with weathered compost, ammonium nitrate, fertilizer, and water. In addition, a consortium of microbes (patent pending) isolated at the Savannah River National Laboratory from a petroleum-contaminated site was added to the PRCS system. During operation, degradation of petroleum waste was accounted for through monitoring of carbon dioxide levels in the system effluent. The project demonstrated that co-contaminated soils could be successfully treated through bioventing and bioaugmentation to remove petroleum contamination to levels below 100 mg/kg while protecting workers and the environment from radiological contamination.

Radionuclide metrology: traceability and response to a radiological accident

Energy Technology Data Exchange (ETDEWEB)

Tauhata, L.; Cruz, P.A.L. da; Silva, C.J. da; Delgado, J.U.; Oliveira, A.E. de; Oliveira, E.M. de; Poledna, R.; Loureiro, J. dos S.; Ferreira Filho, A.L.; Silva, R.L. da; Filho, O. L.T.; Santos, A.R.L. dos; Veras, E.V. de; Rangel, J. de A.; Quadros, A.L.L.; Araújo, M.T.F. de; Souza, P.S. de; Ruzzarim, A.; Conceição, D.A. da; Iwahara, A., E-mail: palcruz@ird.gov.br [Instituto de Radioproteção e Dosimetria (LNMRI/IRD/CNEN-RJ), Rio de Janeiro, RJ (Brazil). Lab. Nacional de Metrologia das Radiações Ionizantes

2017-07-01

In the case of a radiological accident, there are characteristic phases: discovery and initial assistance with first aid; the triage and monitoring of the affected population; the release of the affected people; forward the victims to medical care; as well as the preparation of the report on the accident. In addition, studies and associated researches performed in the later period. Monitors, dosimeters and measuring systems should be calibrated by contaminating radionuclide standards. The radioactive sources used must be metrologically reliable. In Brazil, this function is performed by LNMRI/IRD/CNEN, designated by INMETRO, which Radionuclide Metrology Laboratory is responsible for the standardization and supply of radioactive sources in diverse geometries and matrices. This laboratory has a stock of radionuclide solutions with controlled environmental variables for the preparation of sources, which are calibrated and standardized by mean of primary and secondary systems. It is also responsible for the dissemination of standards and, in order to establish the metrological traceability of national standards, participates in international key-comparisons promoted by BIPM and regional metrology organizations. Internally, it promotes the National Comparison Programs for laboratories for the analysis of environmental samples and the traceability for producing centers of radiopharmaceuticals and Nuclear Medicine Services in the country. The paper presents the demand for {sup 137}Cs related to the radioactive accident in Goiania/Brazil and the significant results for the main radionuclides standardized by the Radionuclide Metrology Laboratory for international key-comparisons and national comparisons to provide metrological traceability. With the obtained results, the LNMRI of Brazil integrates the international metrology BIPM network and fulfills its function of supplying, with about a hundred of radioactive standards, the country's needs in different applications

Radionuclide metrology: traceability and response to a radiological accident

International Nuclear Information System (INIS)

Tauhata, L.; Cruz, P.A.L. da; Silva, C.J. da; Delgado, J.U.; Oliveira, A.E. de; Oliveira, E.M. de; Poledna, R.; Loureiro, J. dos S.; Ferreira Filho, A.L.; Silva, R.L. da; Filho, O. L.T.; Santos, A.R.L. dos; Veras, E.V. de; Rangel, J. de A.; Quadros, A.L.L.; Araújo, M.T.F. de; Souza, P.S. de; Ruzzarim, A.; Conceição, D.A. da; Iwahara, A.

2017-01-01

In the case of a radiological accident, there are characteristic phases: discovery and initial assistance with first aid; the triage and monitoring of the affected population; the release of the affected people; forward the victims to medical care; as well as the preparation of the report on the accident. In addition, studies and associated researches performed in the later period. Monitors, dosimeters and measuring systems should be calibrated by contaminating radionuclide standards. The radioactive sources used must be metrologically reliable. In Brazil, this function is performed by LNMRI/IRD/CNEN, designated by INMETRO, which Radionuclide Metrology Laboratory is responsible for the standardization and supply of radioactive sources in diverse geometries and matrices. This laboratory has a stock of radionuclide solutions with controlled environmental variables for the preparation of sources, which are calibrated and standardized by mean of primary and secondary systems. It is also responsible for the dissemination of standards and, in order to establish the metrological traceability of national standards, participates in international key-comparisons promoted by BIPM and regional metrology organizations. Internally, it promotes the National Comparison Programs for laboratories for the analysis of environmental samples and the traceability for producing centers of radiopharmaceuticals and Nuclear Medicine Services in the country. The paper presents the demand for 137 Cs related to the radioactive accident in Goiania/Brazil and the significant results for the main radionuclides standardized by the Radionuclide Metrology Laboratory for international key-comparisons and national comparisons to provide metrological traceability. With the obtained results, the LNMRI of Brazil integrates the international metrology BIPM network and fulfills its function of supplying, with about a hundred of radioactive standards, the country's needs in different applications

Nationwide study of the radiological screening of water for human consumption

International Nuclear Information System (INIS)

Velazquez M, R.; Aguilar P, M. del C.; Carreon G, E.; Parissi C, A.

2014-10-01

A screening test was carried out to the drinking water in the main cities of our country (Mexico). This study arises from the need that existed of having a radiological policy support in drinking water, which involved: the State Laboratory of Public Health of Veracruz State which has radiation analytical infrastructure. The study design was aimed to have the elements for further sanitary and/or epidemiological studies, so it was considered only the urban population to concentrate the major population of the country, as well as impact factors of water pollution by radiological materials: soils, precipitation, etc. The result of 928 samples from 14 states are presented and shows that they are consistent with the expected results, unable to be conclusive because the state participation was only of 43.5%, of which only 31% completed the shipment of samples in rainy and dry seasons. The State Laboratory of Public Health of Veracruz State has authorized methods by the Comision Federal para la Proteccion contra Riesgos Sanitarios (COFEPRIS) for the determination of gross beta and gross alpha radioactivity by the method of direct evaporation of samples of drinking water. A system of proportional flow detection under background calibrated was used. In the determination of gross beta values no greater than those established by the current national standard were detected. For gross alpha determination, the states with high rainfall and no mining industry located in the southeast of the country have lower values for gross alpha activity that the states in the north center of the country. Point values of gross alpha activity were detected in some states exceeding the standard values. (Author)

Intervention of hydrogen analysis laboratory for radioactive materials study

International Nuclear Information System (INIS)

Bruno, N.; Vinces, H.; Figueroa, S.

1996-01-01

The objective of the practice was the measurement of the hydrogen concentration on structural material from the Central Nuclear Atucha I (CNA-I) cooling channels using a LECO gas analyser. Original samples were previously separated into fractions at the Laboratiorio para Ensayos de Post-Irradiacion (LAPEP), Centro Atomico Ezeiza. The practice and the preliminary conditions of the laboratory and equipment to reduce the occupational dose for personnel and the work area contamination are described in this paper. In addition to the training activity for workers, the radiological control performed during the intervention and procedure followed to decontaminate LECO and the laboratory are summarized here. (authors)

Emergency response exercise of laboratories equipped with gamma spectrometry

International Nuclear Information System (INIS)

Mala, H.; Jezkova, T.; Rulik, P.; Beckova, V. et al.

2014-01-01

Seven laboratories equipped with semiconductor gamma spectrometry (HPGe detectors) are currently included in the Radiation Monitoring Network (RMN) in the Czech Republic. These laboratories have more than 30 spectrometric chains and approximately 20 'experts' and 70 'users' who would guarantee measurements during the radiological emergency (RE). The emergency exercise was carried out in 5 of them in 2014 (in 4 of them also in 2013). The aim was to test repeatedly their capacity in existing technical facilities and with current staff in the event of a RE and identify problems (bottlenecks) in the whole process from receipt of samples to entering the results into the central database of RMN. Duration of the exercise was 12 hours, due to the shortage of staff; work in one 12-hour shift is presumed during a RE, which the laboratories should be able to provide for 14 days. These exercise samples covered a wide range of commodities that would probably come to the laboratories during the RE (aerosol filters, sorbents for sorption of gaseous forms of iodine, fallout, surface and drinking waters, food chain components and soils). Some of the samples were previously spiked with 85 Sr, 88 Y and 40 K (in the exercise these nuclides represented actual contamination that would occur in RE); liquid samples were spiked with 85 Sr and 88 Y and bulk materials with 40 K.During the exercise almost 800 samples were analysed; in addition, the automatic gamma counter (GA) in Prague laboratory measured other 90 samples automatically during the night (samples were prepared during the day-shift). On the basis of the results the total measuring capacity of the laboratories of RMN CR was estimated at about 1300 samples per day. (authors)

Radiological contamination control training for laboratory research

International Nuclear Information System (INIS)

1997-02-01

This program management guide describes the proper implementation standard for core training as outlined in the DOE Radiological Control (RadCon) Manual. The guide is to assist those individuals, both within the Department of Energy (DOE) and Managing and Operating (M and O) contractors, identified as having responsibility for implementing the core training recommended by the RadCon Manual. The management guide is divided into the following sections: introduction; instructional materials development; training program standards and policies; and course-specific information. The goal of the core training program is to provide a standardized, baseline knowledge for those individuals completing the core training. Standardization of the knowledge provides personnel with the information necessary to perform their assigned duties at a predetermined level of expertise. Implementing a core training program ensures consistent and appropriate training of personnel

Directory of personnel responsible for radiological health programs

International Nuclear Information System (INIS)

1977-01-01

This is a directory of professional personnel who administer the radiological health program activities in state and local governmental agencies. Included in the directory is a listing of each state health officer or the head of the agency responsible for the radiological health program. The name, address, and telephone number of the radiological health personnel are listed, followed by the alternate contact who, in many instances, may be chief of a larger administrative unit of which the radiological health program is a subunit. The address for the program is also included if it differs from the official health department or agency. Generally, the titles of the personnel listed will indicate the administrative status of the radiological health program. The directory also includes a list of key professional personnel in the Bureau of Radiological Health, Radiation Operations Staff, Regional Radiological Health Representatives, Winchester Engineering and Analytical Center, Food and Drug Administration; Office of Radiation Programs, Regional Radiation Representatives, National Environmental Research Center, and Eastern Environmental Radiation Laboratory, Environmental Protection Agency; selected personnel in the U.S. Nuclear Regulatory Commission; and selected personnel in the National Bureau of Standards

Results of the radiological survey at 136 West Central Avenue (MJ030), Maywood, New Jersey

International Nuclear Information System (INIS)

Foley, R.D.; Crutcher, J.W.; Carrier, R.F.; Floyd, L.M.

1989-02-01

As a result of the Energy and Water Appropriations Act of Fiscal Year 1984, the property discussed in this report and properties in its vicinity contaminated with residues from the former Maywood Chemical Works (MCW) were included as a decontamination research and development project under the DOE Formerly Utilized Sites Remedial Action Program. As part of this project, DOE is conducting radiological surveys in the vicinity of the site to identify properties contaminated with residues derived from the MCW. The principal radionuclide of concern is thorium-232. The radiological survey discussed in this report is part of that effort and was conducted, at the request of DOE by members of the Measurement Applications and Development Group of Oak Ridge National Laboratory. A radiological survey of the private, residential property at 136 West Central Avenue, Maywood, New Jersey, was conducted during 1987. The survey and sampling of the ground surface and subsurface were carried out on April 29, 1987

Measuring Radionuclides in the environment: radiological quantities and sampling designs

International Nuclear Information System (INIS)

Voigt, G.

1998-10-01

One aim of the workshop was to support and provide an ICRU report committee (International Union of Radiation Units) with actual information on techniques, data and knowledge of modern radioecology when radionuclides are to be measured in the environment. It has been increasingly recognised that some studies in radioecology, especially those involving both field sampling and laboratory measurements, have not paid adequate attention to the problem of obtaining representative, unbiased samples. This can greatly affect the quality of scientific interpretation, and the ability to manage the environment. Further, as the discipline of radioecology has developed, it has seen a growth in the numbers of quantities and units used, some of which are ill-defined and which are non-standardised. (orig.)

A radiological control implementation guide

International Nuclear Information System (INIS)

Hamley, S.A.

1993-01-01

A manual is being developed to explain to line managers how radiological controls are designed and implemented. The manual also fills a gap in the Health Physics literature between textbooks and on-the-floor procedures. It may be helpful to new Health Physicists with little practical experience and to those wishing to improve self-assessment, audit, and appraisal processes. Many audits, appraisals, and evaluations have indicated a need for cultural change, increased vigor and example, and more effective oversight by line management. Inadequate work controls are a frequent and recurring problem identified in occurrence reports and accident investigations. Closer study frequently indicates that many line managers are willing to change and want to achieve excellence, but no effective guidance exists that will enable them to understand and implement a modern radiological control program. The manual is now in draft form and includes information that will be of use to line managers dealing with improving radiological performance and the practical aspects of radiological controls implementation. The manual is expected to be completed by the fall of 1993 and to be used in conjunction with a performance-based self-assessment training program at the Oak Ridge National Laboratory

Final report: survey and removal of radioactive surface contamination at environmental restoration sites, Sandia National Laboratories/New Mexico. Volume 2

International Nuclear Information System (INIS)

Lambert, K.A.; Mitchell, M.M.; Jean, D.; Brown, C.; Byrd, C.S.

1997-09-01

This report contains the Appendices A-L including Voluntary Corrective Measure Plans, Waste Management Plans, Task-Specific Health and Safety Plan, Analytical Laboratory Procedures, Soil Sample Results, In-Situ Gamma Spectroscopy Results, Radionuclide Activity Summary, TCLP Soil Sample Results, Waste Characterization Memoranda, Waste Drum Inventory Data, Radiological Risk Assessment, and Summary of Site-Specific Recommendations

The method of Sample Management in Neutron Activation Analysis Laboratory-Serpong

International Nuclear Information System (INIS)

Elisabeth-Ratnawati

2005-01-01

In the testing laboratory used by neutron activation analysis method, sample preparation is the main factor and it can't be neglect. The error in the sample preparation can give result with lower accuracy. In this article is explained the scheme of sample preparation i.e sample receive administration, the separate of sample, fluid and solid sample preparation, sample grouping, irradiation, sample counting and holding the sample post irradiation. If the management of samples were good application based on Standard Operation Procedure, therefore each samples has good traceability. To optimize the management of samples is needed the trained and skilled personal and good facility. (author)

The use of importance sampling in a trial assessment to obtain converged estimates of radiological risk

International Nuclear Information System (INIS)

Johnson, K.; Lucas, R.

1986-12-01

In developing a methodology for assessing potential sites for the disposal of radioactive wastes, the Department of the Environment has conducted a series of trial assessment exercises. In order to produce converged estimates of radiological risk using the SYVAC A/C simulation system an efficient sampling procedure is required. Previous work has demonstrated that importance sampling can substantially increase sampling efficiency. This study used importance sampling to produce converged estimates of risk for the first DoE trial assessment. Four major nuclide chains were analysed. In each case importance sampling produced converged risk estimates with between 10 and 170 times fewer runs of the SYVAC A/C model. This increase in sampling efficiency can reduce the total elapsed time required to obtain a converged estimate of risk from one nuclide chain by a factor of 20. The results of this study suggests that the use of importance sampling could reduce the elapsed time required to perform a risk assessment of a potential site by a factor of ten. (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

Physical correlates of radiologic heart volume

International Nuclear Information System (INIS)

Christie, D.

1978-01-01

Radiologic heart volume was calculated on a 10 per cent random sample of subjects examined in the London Civil Service Health Survey. Data were available for 1 188 men over the age of 40, and the importance of correcting radiologic heart volume for body size, age and heart rate was demonstrated. After these variables were taken into account, the most important association found was with blood pressure. Radiologic heart volume has potential value in cardiovascular screening programmes. (Auth.)

Environmental surveillance master sampling schedule

Energy Technology Data Exchange (ETDEWEB)

Bisping, L E

1992-01-01

Environmental surveillance of the Hanford Site and surrounding areas is conducted by the Pacific Northwest Laboratory (PNL) for the US Department of Energy (DOE). This document contains the planned schedule for routine sample collection for the Surface Environmental Surveillance Project (SESP) and Ground-Water Monitoring Project. Samples for radiological analyses include Air-Particulate Filter, gases and vapor; Water/Columbia River, Onsite Pond, Spring, Irrigation, and Drinking; Foodstuffs/Animal Products including Whole Milk, Poultry and Eggs, and Beef; Foodstuffs/Produce including Leafy Vegetables, Vegetables, and Fruit; Foodstuffs/Farm Products including Wine, Wheat and Alfalfa; Wildlife; Soil; Vegetation; and Sediment. Direct Radiation Measurements include Terrestrial Locations, Columbia River Shoreline Locations, and Onsite Roadway, Railway and Aerial, Radiation Surveys.

Internal medicine. An illustrated radiological guide

International Nuclear Information System (INIS)

Al-Tubaikh, Jarrah Ali; Sabah Hospital, Kuwait

2010-01-01

This book explains how radiology can be a powerful tool for establishing the diagnosis of many internal medicine diseases that are usually diagnosed on the basis of their laboratory or clinical presentation. It is organized in the classic fashion for internal medicine books, with eleven chapters covering the different internal medicine specialties. Within these chapters, more than 450 diseases are considered, some of which are rarely encountered but are nonetheless significant. For each disease, radiological and clinical features are displayed in images and high-quality digital medical illustrations, and those differential diagnoses are identified that can be ruled out by imaging alone. In addition, the pathophysiology underlying the radiological features is described, enabling the reader to understand why a particular sign is seen on MR images, CT scans, or plain radiographs. The book will serve as an excellent radiological atlas for internal medicine practitioners and family physicians, showing disease presentations that may be hard to find in standard medical textbooks and explaining which imaging modalities are likely to be most informative in particular patients. (orig.)

Development of low-level environmental sampling capabilities for uranium at Brazilian and Argentine laboratories by ABACC

International Nuclear Information System (INIS)

Guidicini, Olga Mafra; Hembree Junior, Doyle M.; Carter, Joel A.; Hayes, Susan; Whitaker, Michael; Olsen, Khris

2003-01-01

The Brazilian-Argentine Agency for Accounting and Control of Nuclear Materials (ABACC) with assistance from the U.S. Department of Energy (DOE) began a program to evaluate environmental sampling capabilities at laboratories in Argentina and Brazil in June 1998. The program included staff training conducted in South America and the United States. Several laboratory evaluation exercises were also conducted using standard swipe samples prepared by the International Atomic Energy Agency (IAEA) and a National Institute of Standards and Technology Standard Reference Material 1547, Peach Leaves. The results of these exercises demonstrated that several laboratories were capable of accurately determining the total uranium and uranium isotopic distribution in the peach leaves. To build on these successes, another exercise using standard swipe samples prepared by the IAEA was conducted. A total of 8 sets of 15 swipe samples were prepared and distributed to the six ABACC support laboratories and to two of DOE's Network of Analytical Laboratories (NWAL) that support IAEA's environmental sampling program Throughout this project, the ABACC laboratories have shown steady progress in contamination control and improvements to the accuracy and precision of their measurements. The results of the latest exercises demonstrate that ABACC now has support laboratories in both Argentina and Brazil that have the capability to measure both the amount and isotopic composition of uranium at levels expected in typical environmental samples (i.e., sub-microgram quantities). This presentation will discuss the final results for the exercise with uranium swipe samples and discuss future activities to develop measurement capabilities for total and isotopic plutonium in environmental samples. (author)

Seeps and springs sampling and analysis plant for the Environmental Monitoring Plan at Waste Area Grouping 6, Oak Ridge National Laboratory, Oak Ridge, Tennessee

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-09-01

This Sampling and Analysis Plan addresses the monitoring, sampling, and analysis activities that will be conducted at seeps and springs and at two french drain outlets in support of the Environmental Monitoring Plan for Waste Area Grouping (WAG) 6. WAG 6 is a shallow-land-burial disposal facility for low-level radioactive waste at Oak Ridge National Laboratory, a research facility owned by the U.S. Department of Energy and operated by Lockheed Martin Energy System, Inc. Initially, sampling will be conducted at as many as 15 locations within WAG 6 (as many as 13 seeps and 2 french drain outlets). After evaluating the results obtained and reviewing the observations made by field personnel during the first round of sampling, several seeps and springs will be chosen as permanent monitoring points, together with the two french drain outlets. Baseline sampling of these points will then be conducted quarterly for 1 year (i.e., four rounds of sampling after the initial round). The samples will be analyzed for various geochemical, organic, inorganic, and radiological parameters. Permanent sampling points having suitable flow rates and conditions may be outfitted with automatic flow-monitoring equipment. The results of the sampling and flow-monitoring efforts will help to quantify flux moving across the ungauged perimeter of the site and will help to identify changes in releases from the contaminant sources.

Seeps and springs sampling and analysis plant for the Environmental Monitoring Plan at Waste Area Grouping 6, Oak Ridge National Laboratory, Oak Ridge, Tennessee

International Nuclear Information System (INIS)

1995-09-01

This Sampling and Analysis Plan addresses the monitoring, sampling, and analysis activities that will be conducted at seeps and springs and at two french drain outlets in support of the Environmental Monitoring Plan for Waste Area Grouping (WAG) 6. WAG 6 is a shallow-land-burial disposal facility for low-level radioactive waste at Oak Ridge National Laboratory, a research facility owned by the U.S. Department of Energy and operated by Lockheed Martin Energy System, Inc. Initially, sampling will be conducted at as many as 15 locations within WAG 6 (as many as 13 seeps and 2 french drain outlets). After evaluating the results obtained and reviewing the observations made by field personnel during the first round of sampling, several seeps and springs will be chosen as permanent monitoring points, together with the two french drain outlets. Baseline sampling of these points will then be conducted quarterly for 1 year (i.e., four rounds of sampling after the initial round). The samples will be analyzed for various geochemical, organic, inorganic, and radiological parameters. Permanent sampling points having suitable flow rates and conditions may be outfitted with automatic flow-monitoring equipment. The results of the sampling and flow-monitoring efforts will help to quantify flux moving across the ungauged perimeter of the site and will help to identify changes in releases from the contaminant sources

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

In-Process Analysis Program for the Isolock sampler at the Gunite and Associated Tanks, Oak Ridge National Laboratory, Oak Ridge, Tennessee

International Nuclear Information System (INIS)

1998-05-01

The In-Process Analysis Program documents the requirements for handling, transporting, and analyzing waste slurry samples gathered by the Bristol Isolock slurry sampler from the Gunite and Associated Tanks at Oak Ridge National Laboratory in Oak Ridge, Tennessee. Composite samples will be gathered during sludge retrieval operations, labeled, transported to the appropriate laboratory, and analyzed for physical and radiological characteristics. Analysis results will be used to support occupational exposure issues, basic process control management issues, and prediction of radionuclide flow

The Radiological Research Accelerator Facility:

International Nuclear Information System (INIS)

Hall, E.J.; Goldhagen, P.

1988-07-01

The Radiological Research Accelerator Facility (RARAF) is based on a 4-MV Van de Graaff accelerator, which is used to generated a variety of well-characterized radiation beams for research in radiobiology, radiological physics, and radiation chemistry. It is part of the Radiological Research Laboratory (RRL) of Columbia University, and its operation is supported as a National Facility by the U.S. Department of Energy. As such, RARAF is available to all potential users on an equal basis, and scientists outside the RRL are encouraged to submit proposals for experiments at RARAF. Facilities and services are provided to users, but the research projects themselves must be supported separately. RARAF was located at BNL from 1967 until 1980, when it was dismantled and moved to the Nevis Laboratories of Columbia University, where it was then reassembled and put back into operation. Data obtained from experiment using RARAF have been of pragmatic value to radiation protection and to neutron therapy. At a more fundamental level, the research at RARAF has provided insight into the biological action of radiation and especially its relation to energy distribution in the cell. High-LET radiations are an agent of special importance because they can cause measurable cellular effects by single particles, eliminating some of the complexities of multievent action and more clearly disclosing basic features. This applies particularly to radiation carcinogenesis. Facilities are available at RARAF for exposing objects to different radiations having a wide range of linear energy transfers (LETs)

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)

Radiologic science for technologists

International Nuclear Information System (INIS)

Bushong, S.C.

1988-01-01

This book provides in-depth coverage of physics, biology and protection for the radiologic technology student. It presents a significant portion of all of the science required of radiologic technology students under one cover. Chapter content reflects a readable and practical organization with outlines listed on the first page of each chapter and sample problems at the end. New to this edition are: new and expanded sections on radiation techniques, digital imaging, and magnetic resonance imaging and ultrasound

Results of the radiological survey at 266 East Spring Valley Avenue (MJ024), Hackensack, New Jersey

International Nuclear Information System (INIS)

Foley, R.D.; Crutcher, J.W.; Carrier, R.F.; Floyd, L.M.

1989-02-01

As a result of the Energy and Water Appropriations Act of Fiscal Year 1984, the property discussed in this report and properties in its vicinity contaminated with residues from the former Maywood Chemical Works (MCW) were included as a decontamination research and development project under the DOE Formerly Utilized Sites Remedial Action Program. As part of this project, DOE is conducting radiological surveys in the vicinity of the site to identify properties contaminated with residues derived from the MCW. The principal radionuclide of concern is thorium-232. The radiological survey discussed in this report is part of that effort and was conducted, at the request of DOE, by members of the Measurement Applications and Development Group of Oak Ridge National Laboratory. A radiological survey of the private, residential property at 266 East Spring Valley Avenue, Hackensack, New Jersey, was conducted during 1987. The survey and sampling of the ground surface and subsurface were carried out on April 23, 1987. 4 refs., 2 figs., 3 tabs

Sampling and analysis plan for sampling of liquid waste streams generated by 222-S Laboratory Complex operations

International Nuclear Information System (INIS)

Benally, A.B.

1997-01-01

This Sampling and Analysis Plan (SAP) establishes the requirements and guidelines to be used by the Waste Management Federal Services of Hanford, Inc. personnel in characterizing liquid waste generated at the 222-S Laboratory Complex. The characterization process to verify the accuracy of process knowledge used for designation and subsequent management of wastes consists of three steps: to prepare the technical rationale and the appendix in accordance with the steps outlined in this SAP; to implement the SAP by sampling and analyzing the requested waste streams; and to compile the report and evaluate the findings to the objectives of this SAP. This SAP applies to portions of the 222-S Laboratory Complex defined as Generator under the Resource Conservation and Recovery Act (RCRA). Any portion of the 222-S Laboratory Complex that is defined or permitted under RCRA as a treatment, storage, or disposal (TSD) facility is excluded from this document. This SAP applies to the liquid waste generated in the 222-S Laboratory Complex. Because the analytical data obtained will be used to manage waste properly, including waste compatibility and waste designation, this SAP will provide directions for obtaining and maintaining the information as required by WAC173-303

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)

Radiological survey results at 5 Porter Street, Beverly, Massachusetts (VB019)

International Nuclear Information System (INIS)

Foley, R.D.; Johnson, C.A.

1992-07-01

At the request of the US Department of Energy (DOE), a team from Oak Ridge National Laboratory conducted a radiological survey at 5 Porter Street, Beverly, Massachusetts. The survey was performed in May 1991. The purpose of the survey was to determine if uranium from work performed under government contract at the former Ventron facility had migrated off-site to neighboring areas. The survey included a surface gamma scan and the collection of soil samples for radionuclide analyses. Results of the survey demonstrated no radionuclide concentrations or radiation measurements in excess of the DOE Formerly Utilized Site Remedial Action Program guidelines

Radiological survey results at 2 Porter Street, Beverly, Massachusetts (VB005)

International Nuclear Information System (INIS)

Foley, R.D.; Carrier, R.F.

1992-08-01

At the request of the US Department of Energy (DOE), a team from Oak Ridge National Laboratory conducted a radiological survey at 2 Porter Street, Beverly, Massachusetts. The survey was performed in May 1991. The purpose of the survey was to determine if uranium dust from work performed under government contract at the former Ventron facility had migrated off-site to neighboring areas. The survey included a surface gamma scan and the collection of soil samples fore radionuclide analyses. Results of the survey demonstrated no radionuclide concentrations or radiation measurements in excess of the DOE Formerly Utilized Sites Remedial Action Program guidelines

Radiological survey results at 9 Porter Street, Beverly, Massachusetts (VB020)

International Nuclear Information System (INIS)

Foley, R.D.; Johnson, C.A.

1992-07-01

At the request of the US Department of Energy (DOE), a team from Oak Ridge National Laboratory conducted a radiological survey at 9 Porter Street, Beverly, Massachusetts. The survey was performed in May 1991. The purpose of the survey was to determine if uranium from work performed under government contract at the former Ventron facility had migrated off-site to neighboring areas. The survey included a surface gamma scan and the collection of soil samples for radionuclide analyses. Results of the survey demonstrated no radionuclide concentrations or radiation measurements in excess of the DOE Formerly Utilized Sites Remedial Action Program guidelines

Radiological dose assessments in the northern Marshall Islands (1989--1991)

International Nuclear Information System (INIS)

Sun, L.C.; Meinhold, C.B.; Moorthy, A.R.; Clinton, J.H.; Kaplan, E.

1992-01-01

The present Brookhaven National Laboratory (BNL) Marshall Islands Radiological Safety Program (MIRSP) began in 1987 with funding from the US Department of Energy (DOE). The objectives of the MIRSP are to determine the radionuclides present in the bodies of those people potentially exposed to residual radionuclide from weapon tests and fallout, and to assess their present and lifetime dose from external and internal sources. Field bioassay missions involving whole body counting (WBC) and urine sample collection have, therefore, been important components of the program. WBC is used to measure γ-emitters, such as 40 K, 60 Co and 137 Cs, present in individuals. Urine samples are used to measure α and β-emitting nuclides, such as 239 Pu and 90 Sr, that are undetectable by WBC routine methods

Conventional radiology and genetic dose

International Nuclear Information System (INIS)

Gonzalez-Vila, V.; Fernandez, A.; Rivera, F.; Martinez, M.; Gomez, A.; Luis, J.

1992-01-01

A research project was established in 1984 to evaluate the expected genetic abnormalities due to radiation received by the population attending the Outpatient Radiological Service due to medical radiological practices. The study was conducted in 1985 (12 weeks chosen by random). The equivalent gonadal dose was the chosen parameter, representing the social cost of the radiology. Samples of 2945 men and 2929 women were considered in the study. The number of genetic abnormalities, in relation to the mean age of reproduction (a generation every 30 years), was 2.13 cases per million in the first generation and 15.97 cases per million at equilibrium. The authors interpretation is that both the method and the expected genetic detriment are suitable procedures for the characterisation of the Radiological Service as a radiation source. (author)

Enhancement of the radiological protection in the Nuclear Medicine Centres in Peru

International Nuclear Information System (INIS)

Lopez, Edith; Gonzales, Susana; Zapata, Luis

2008-01-01

Full text: The Laboratory of Internal Dosimetry (LDI) of the Nuclear Energy Peruvian Institute (IPEN) is the laboratory which offers the service of internal dosimetry to the IPEN personnel who works handling non sealed radioactive sources. The Laboratory has participated in several intercomparison exercises featuring in vivo measurements, in vitro methods and dose calculations with acceptable results, which are indicators that the laboratory results are reliable. The National Program of Radiological Protection for occupational exposed workers, who handles non sealed radioactive sources, allows involving the IPEN occupational exposed workers and the Nuclear Medicine Centres Personnel. In Peru, there are 5000 occupational exposed workers, 3500 of them are controlled through external dosimetry. There are approximately 230 occupational exposed workers to non sealed radioactive sources, 67 of them are registered in the National Regulatory Authority and 20 are controlled radiologically. The aim of this study is the enhancement of the radiological safety of the personnel who works in the Nuclear Medicine Centres and handles non sealed radioactive sources. As part of this work, activities addressed to improve the radiological safety of the occupational exposed workers were taken place such as: supply of technical documents about radiological safety, performance of surveys and polls and the organization of a workshop involving the participation of several health professionals working in this field. The situation of the control measures in the radiation protection of the patients and occupational exposed workers, based in updated regulatory documents, have been assessed and it allowed knowing and learning that the occupational exposed workers of the Nuclear Medicine Centres could perform their own monitoring program since they have potential capabilities like Iodine Uptake Systems and calibrated Gamma cameras. This study involves 15 public and private institutions. (author)

Dosimetry in Diagnostic Radiology for Paediatric Patients

International Nuclear Information System (INIS)

2013-01-01

both in standards dosimetry laboratories and clinical centres for radiology, as found in most hospitals. A coordinated research project was established in order to provide practical guidance to professionals at the Secondary Standards Dosimetry Laboratories (SSDLs) and to clinical medical physicists on the implementation of TRS 457, including the establishment of dosimetric measurement processes in clinical settings. Among the recommendations from the coordinated research project (see IAEA Human Health Reports No. 4, published in 2011) was the need for guidance on dosimetric standards and methodologies related to dosimetry for paediatric patients undergoing diagnostic radiology

Radiological transportation risk assessment of the shipment of sodium-bonded fuel from the Fast Flux Test Facility to the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

Green, J.R.

1995-01-01

This document was written in support of Environmental Assessment: Shutdown of the Fast Flux Test Facility (FFTF), Hanford Site, Richland, Washington. It analyzes the potential radiological risks associated with the transportation of sodium-bonded metal alloy and mixed carbide fuel from the FFTF on the Hanford Site in Washington State to the Idaho Engineering Laboratory in Idaho in the T-3 Cask. RADTRAN 4 is used for the analysis which addresses potential risk from normal transportation and hypothetical accident scenarios

Radiological transportation risk assessment of the shipment of sodium-bonded fuel from the Fast Flux Test Facility to the Idaho National Engineering Laboratory

Energy Technology Data Exchange (ETDEWEB)

Green, J.R.

1995-01-31

This document was written in support of Environmental Assessment: Shutdown of the Fast Flux Test Facility (FFTF), Hanford Site, Richland, Washington. It analyzes the potential radiological risks associated with the transportation of sodium-bonded metal alloy and mixed carbide fuel from the FFTF on the Hanford Site in Washington State to the Idaho Engineering Laboratory in Idaho in the T-3 Cask. RADTRAN 4 is used for the analysis which addresses potential risk from normal transportation and hypothetical accident scenarios.

Radiological NESHAP ANNUAL REPORT CY 2016.

Energy Technology Data Exchange (ETDEWEB)

Evelo, Stacie [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

2017-06-01

This report provides a summary of the radionuclide releases from the United States (U.S.) Department of Energy (DOE) National Nuclear Security Administration facilities at Sandia National Laboratories, New Mexico (SNL/NM) during Calendar Year (CY) 2016, including the data, calculations, and supporting documentation for demonstrating compliance with 40 Code of Federal Regulation (CFR) 61, Subpart H--NATIONAL EMISSION STANDARDS FOR EMISSIONS OF RADIONUCLIDES OTHER THAN RADON FROM DEPARTMENT OF ENERGY FACILITIES (Radiological NESHAP). A description is given of the sources and their contributions to the overall dose assessment. In addition, the maximally exposed individual (MEI) radiological dose calculation and the population dose to local and regional residents are discussed.

Radiological contamination by depleted uranium in the Al-Tahreer tower building

International Nuclear Information System (INIS)

Al-Ataby, N.R.; Aisa, B.H.; Jebir, H.M.; Hatem, J.N.

2011-01-01

The research plan included assessment of the radioactivity of the Al-Tahreer Tower Building (the Turkish restaurant recent) through direct measurements and sampling of soil for the four floors (1th,2th,3th,4th) of the building, which contains fourteen floor in addition to the basement, by using portable radiation detection equipment to know the increasing in the levels of exposure and contamination resulting from the bombing a Al-Tahreer Tower building by depleted uranium bullets, the results of radiological surveys by using the portable contamination radiation detection (CAB) indicated readings of contaminated soil reached to 60 c/sec, and parts of shells of depleted uranium reached to 90 c/ sec , while the natural contamination rate in the area is (0.5 c/sec), the natural exposure rate in the area is 9 μR/ hr but the higher exposure rate reached to 60 μR / hr when the device (Ludlum) putting on the contaminated regions(distance about 0.5 cm). The radiological analyses of the collected soil samples were done in the laboratory of the center of Radiological Researches in the Ministry of sciences and Technology by using gamma spectrometry (which contains High-purity Germanium Detector) with a efficiency of 40% and resolution 2 keV for Energy, 1.33 Mev,collection,preparations and tests of soil samples were all done according to IAEA.The normal concentration for Th 234 and Pa 234 m in the soil samples taken from areas near to the building (can consider as background radiation region) is in range 41 Bq /Kg for Th 234 ,and nil for pa 234 m ,while higher concentration of Th 234 in contaminated soil is 1194 Bq/kg,and 1664 Bq/kg for pa 234 m which is a clear indication of the presence of high concentrations an isotope of uranium 238 as they are supposed to be in equilibrium radiation. The major aim of this study include removal the contaminated regions in the building, to protect the population and the environment from the effect of radiological contamination which

GHSI emergency radionuclide bioassay laboratory network - summary of the second exercise

International Nuclear Information System (INIS)

Li, Chunsheng; Ko, Raymond; Quayle, Debora; Sadi, Baki; Bartizel, Christine; Battisti, Paolo; Boettger, Axel; Bouvier, Celine; Paquet, Francois; CapoteCuellar, Antonio; Carr, Zhanat; Hammond, Derek; Hartmann, Martina; Heikkinen, Tarja; Jones, Robert L.; Kim, Eunjoo; Koga, Roberto; Kukhta, Boris; Mitchell, Lorna; Morhard, Ryan; Rulik, Petr; Sergei, Aleksanin; Sierra, Inmaculada; Oliveira Sousa, Wandersonde; Szabo, Gyula

2017-01-01

The Global Health Security Initiative (GHSI) established a laboratory network within the GHSI community to develop collective surge capacity for radionuclide bioassay in response to a radiological or nuclear emergency as a means of enhancing response capability, health outcomes and community resilience. GHSI partners conducted an exercise in collaboration with the WHO Radiation Emergency Medical Preparedness and Assistance Network and the IAEA Response and Assistance Network, to test the participating laboratories (18) for their capabilities in in vitro assay of biological samples, using a urine sample spiked with multiple high-risk radionuclides ( 90 Sr, 106 Ru, 137 Cs, and 239 Pu). Laboratories were required to submit their reports within 72 h following receipt of the sample, using a pre-formatted template, on the procedures, methods and techniques used to identify and quantify the radionuclides in the sample, as well as the bioassay results with a 95% confidence interval. All of the participating laboratories identified and measured all or some of the radionuclides in the sample. However, gaps were identified in both the procedures used to assay multiple radionuclides in one sample, as well as in the methods or techniques used to assay specific radionuclides in urine. Two-third of the participating laboratories had difficulties in determining all the radionuclides in the sample. Results from this exercise indicate that challenges remain with respect to ensuring that results are delivered in a timely, consistent and reliable manner to support medical interventions. Laboratories within the networks are encouraged to work together to develop and maintain collective capabilities and capacity for emergency bioassay, which is an important component of radiation emergency response. (authors)

On the improvement of blood sample collection at clinical laboratories.

Science.gov (United States)

Grasas, Alex; Ramalhinho, Helena; Pessoa, Luciana S; Resende, Mauricio G C; Caballé, Imma; Barba, Nuria

2014-01-09

Blood samples are usually collected daily from different collection points, such hospitals and health centers, and transported to a core laboratory for testing. This paper presents a project to improve the collection routes of two of the largest clinical laboratories in Spain. These routes must be designed in a cost-efficient manner while satisfying two important constraints: (i) two-hour time windows between collection and delivery, and (ii) vehicle capacity. A heuristic method based on a genetic algorithm has been designed to solve the problem of blood sample collection. The user enters the following information for each collection point: postal address, average collecting time, and average demand (in thermal containers). After implementing the algorithm using C programming, this is run and, in few seconds, it obtains optimal (or near-optimal) collection routes that specify the collection sequence for each vehicle. Different scenarios using various types of vehicles have been considered. Unless new collection points are added or problem parameters are changed substantially, routes need to be designed only once. The two laboratories in this study previously planned routes manually for 43 and 74 collection points, respectively. These routes were covered by an external carrier company. With the implementation of this algorithm, the number of routes could be reduced from ten to seven in one laboratory and from twelve to nine in the other, which represents significant annual savings in transportation costs. The algorithm presented can be easily implemented in other laboratories that face this type of problem, and it is particularly interesting and useful as the number of collection points increases. The method designs blood collection routes with reduced costs that meet the time and capacity constraints of the problem.

Radiological manifestations of intestinal tuberculosis

International Nuclear Information System (INIS)

Im, Jae Hoon

1974-01-01

Radiological findings of 87 cases of intestinal tuberculosis are analyzed and presented. The diagnosis was based on histopathology in 29 cases, and on clinical ground and radiological findings in 58 cases. The radio of male and female patients was 4:6, and peak incidence is between 10 and 30. Abdominal pain, diarrhea, weight loss, fever and general weakness are frequent symptoms, and tenderness of abdomen, ascites with abdominal distension, malnutrition and emaciation are frequent signs of the patients. Laboratory investigation reveal anemia, raised ESR, hypoalbuminaemia and positive occult blood reaction in the stool in most of the patients. Chest film show activity pulmonary tuberculosis in only 1/3 patients. There is no pathognomonic radiological findings in intestinal tuberculosis and their manifestations are protean, and differentiation from other inflammatory diseases and malignant tumors in gastrointestinal tract is very difficult on radiological ground alone. However, in patients with complaining vague abdominal symptoms and signs, the radiological diagnosis is most certain means in the decision of existence of organic lesion and suggestion of tuberculosis in the gastrointestinal tract and its extent as yet. Multiplicity of the lesion, involvement of adjacent organ such as peritoneum or mesenteric lymph nodes, typical nodularity or irregularity of mesenteric border and existence of active pulmonary tuberculosis are the suggestive findings of intestinal tuberculosis. In the diagnosis of inflammatory disease or malignant tumor of gastrointestinal tract, the possibility of tuberculosis should be borne in mind, and vice versa

Radiological manifestations of intestinal tuberculosis

Energy Technology Data Exchange (ETDEWEB)

Im, Jae Hoon [Seoul National University College of Medicine, Seoul (Korea, Republic of)

1974-10-15

Radiological findings of 87 cases of intestinal tuberculosis are analyzed and presented. The diagnosis was based on histopathology in 29 cases, and on clinical ground and radiological findings in 58 cases. The radio of male and female patients was 4:6, and peak incidence is between 10 and 30. Abdominal pain, diarrhea, weight loss, fever and general weakness are frequent symptoms, and tenderness of abdomen, ascites with abdominal distension, malnutrition and emaciation are frequent signs of the patients. Laboratory investigation reveal anemia, raised ESR, hypoalbuminaemia and positive occult blood reaction in the stool in most of the patients. Chest film show activity pulmonary tuberculosis in only 1/3 patients. There is no pathognomonic radiological findings in intestinal tuberculosis and their manifestations are protean, and differentiation from other inflammatory diseases and malignant tumors in gastrointestinal tract is very difficult on radiological ground alone. However, in patients with complaining vague abdominal symptoms and signs, the radiological diagnosis is most certain means in the decision of existence of organic lesion and suggestion of tuberculosis in the gastrointestinal tract and its extent as yet. Multiplicity of the lesion, involvement of adjacent organ such as peritoneum or mesenteric lymph nodes, typical nodularity or irregularity of mesenteric border and existence of active pulmonary tuberculosis are the suggestive findings of intestinal tuberculosis. In the diagnosis of inflammatory disease or malignant tumor of gastrointestinal tract, the possibility of tuberculosis should be borne in mind, and vice versa.

Seeps and springs sampling and analysis plan for the environmental monitoring plan for Waste Area Grouping 6 at Oak Ridge National Laboratory, Oak Ridge, Tennessee

Energy Technology Data Exchange (ETDEWEB)

1994-08-01

This Sampling and Analysis Plan addresses the monitoring, sampling, and analysis activities that will be conducted at seeps and springs and at two french drain outlets in support of the Environmental Monitoring Plan for Waste Area Grouping (WAG) 6. WAG 6 is a shallow-land-burial disposal facility for low-level radioactive waste at Oak Ridge National Laboratory, a research facility owned by the US Department of Energy and operated by Martin Marietta Energy Systems, Inc. Initially, sampling will be conducted at as many as 15 locations within WAG 6 (as many as 13 seeps and 2 french drain outlets). After evaluating the results obtained and reviewing the observations made by field personnel during the first round of sampling, several seeps and springs will be chosen as permanent monitoring points, together with the two french drain outlets. Baseline sampling of these points will then be conducted quarterly for 1 year (i.e., four rounds of sampling after the initial round). The samples will be analyzed for various geochemical, organic, inorganic, and radiological parameters. Permanent sampling points having suitable flow rates and conditions may be outfitted with automatic flow-monitoring equipment. The results of the sampling and flow-monitoring efforts will help to quantify flux moving across the ungauged perimeter of the site and will help to identify changes in releases from the contaminant sources.

Seeps and springs sampling and analysis plan for the environmental monitoring plan for Waste Area Grouping 6 at Oak Ridge National Laboratory, Oak Ridge, Tennessee

International Nuclear Information System (INIS)

1994-08-01

This Sampling and Analysis Plan addresses the monitoring, sampling, and analysis activities that will be conducted at seeps and springs and at two french drain outlets in support of the Environmental Monitoring Plan for Waste Area Grouping (WAG) 6. WAG 6 is a shallow-land-burial disposal facility for low-level radioactive waste at Oak Ridge National Laboratory, a research facility owned by the US Department of Energy and operated by Martin Marietta Energy Systems, Inc. Initially, sampling will be conducted at as many as 15 locations within WAG 6 (as many as 13 seeps and 2 french drain outlets). After evaluating the results obtained and reviewing the observations made by field personnel during the first round of sampling, several seeps and springs will be chosen as permanent monitoring points, together with the two french drain outlets. Baseline sampling of these points will then be conducted quarterly for 1 year (i.e., four rounds of sampling after the initial round). The samples will be analyzed for various geochemical, organic, inorganic, and radiological parameters. Permanent sampling points having suitable flow rates and conditions may be outfitted with automatic flow-monitoring equipment. The results of the sampling and flow-monitoring efforts will help to quantify flux moving across the ungauged perimeter of the site and will help to identify changes in releases from the contaminant sources

Pacific Northwest National Laboratory Facility Radionuclide Emission Points and Sampling Systems

International Nuclear Information System (INIS)

Barfuss, Brad C.; Barnett, J. M.; Ballinger, Marcel Y.

2009-01-01

Battelle-Pacific Northwest Division operates numerous research and development laboratories in Richland, Washington, including those associated with the Pacific Northwest National Laboratory (PNNL) on the Department of Energy's Hanford Site that have the potential for radionuclide air emissions. The National Emission Standard for Hazardous Air Pollutants (NESHAP 40 CFR 61, Subparts H and I) requires an assessment of all effluent release points that have the potential for radionuclide emissions. Potential emissions are assessed annually. Sampling, monitoring, and other regulatory compliance requirements are designated based upon the potential-to-emit dose criteria found in the regulations. The purpose of this document is to describe the facility radionuclide air emission sampling program and provide current and historical facility emission point system performance, operation, and design information. A description of the buildings, exhaust points, control technologies, and sample extraction details is provided for each registered or deregistered facility emission point. Additionally, applicable stack sampler configuration drawings, figures, and photographs are provided

Pacific Northwest National Laboratory Facility Radionuclide Emission Points and Sampling Systems

Energy Technology Data Exchange (ETDEWEB)

Barfuss, Brad C.; Barnett, J. Matthew; Ballinger, Marcel Y.

2009-04-08

Battelle—Pacific Northwest Division operates numerous research and development laboratories in Richland, Washington, including those associated with the Pacific Northwest National Laboratory (PNNL) on the Department of Energy’s Hanford Site that have the potential for radionuclide air emissions. The National Emission Standard for Hazardous Air Pollutants (NESHAP 40 CFR 61, Subparts H and I) requires an assessment of all effluent release points that have the potential for radionuclide emissions. Potential emissions are assessed annually. Sampling, monitoring, and other regulatory compliance requirements are designated based upon the potential-to-emit dose criteria found in the regulations. The purpose of this document is to describe the facility radionuclide air emission sampling program and provide current and historical facility emission point system performance, operation, and design information. A description of the buildings, exhaust points, control technologies, and sample extraction details is provided for each registered or deregistered facility emission point. Additionally, applicable stack sampler configuration drawings, figures, and photographs are provided.

Synchrotron environmental laboratory (SUL) at Anka

International Nuclear Information System (INIS)

Denecke, M.A.

2002-01-01

A research facility dedicated to environmental/geochemical research, the Synchrotron Environmental Laboratory (SUL), is planned to be installed and operated at ANKA. ANKA is the new synchrotron facility at the Research Centre Karlsruhe (FZK), Karlsruhe, Germany. ANKA is now in commissioning and planning operations for the fall of 2000. As the Institute for Nuclear Waste Disposal (INE) at FZK conducts a vigorous synchrotron-based research programme, INE was instrumental in the original impetus for installing such a facility at ANKA. These research activities at INE concentrate on actinide speciation in nuclear waste forms, geological media and geochemical model systems. In order for INE to direct their synchrotron research activities to ANKA, equipment and licensing required for performing experiments on actinide-containing samples is required. One great advantage of performing experiments on actinide-containing samples at ANKA is that the INE radiological laboratories lie in the near vicinity of the facility. This will minimise transport hazards and costs and allow experiments to be performed on samples whose characteristics may change with time. Experiments on radioactive samples with activities below the exemption level, according to German regulations, will be possible at ANKA at the start of operations. Licensing for work on higher levels of activity will be applied for in the future. The decades of experience in radiological work at FZK will facilitate development of procedure and equipment as prerequisites to licensing. A consortium of synchrotron radiation-user groups with environmental research interests has specified their requirements and needs for this facility. This scientific case serves as the foundation for the SUL design and is the basis for an application for federal funding. The SUL design reflects the heterogeneity and complexity of challenges facing researchers in the environmental/geochemical sciences. X-ray absorption fine structure (XAFS

Radiologic diagnosis of abestos-ralated lung cancer

International Nuclear Information System (INIS)

Kim, Yoon Kyung; Kim, Jeung Sook; Kim, Yoo Kyung

2015-01-01

Asbestos was previously widely used due to its many favorable characteristics, such as durability, flexibility, and inexpensiveness. Asbestos has been prohibited in Korea since 2009, however, asbestos-related diseases remain an important public health issue because of its long latency time. Lung cancer is one of the most harmful asbestos-related diseases and patients with asbestos-related lung cancer receive compensation by law. The diagnosis of asbestos-related diseases is based on a detailed interview regarding the asbestos exposure, in addition to clinical, radiological, pathological, and laboratory data. This review provides a radiologic diagnosis of asbestos-related lung cancer

Radiologic diagnosis of abestos-ralated lung cancer

Energy Technology Data Exchange (ETDEWEB)

Kim, Yoon Kyung [Dept. of Radiology, Gachon University Gil Medical Center, Incheon (Korea, Republic of); Kim, Jeung Sook [Dept. of Radiology, Dongguk University Ilsan Hospital, Goyang (Korea, Republic of); Kim, Yoo Kyung [Dept. of Radiology, Mokdong Hospital, Ewha Womans University School of Medicine, Seoul (Korea, Republic of)

2015-12-15

Asbestos was previously widely used due to its many favorable characteristics, such as durability, flexibility, and inexpensiveness. Asbestos has been prohibited in Korea since 2009, however, asbestos-related diseases remain an important public health issue because of its long latency time. Lung cancer is one of the most harmful asbestos-related diseases and patients with asbestos-related lung cancer receive compensation by law. The diagnosis of asbestos-related diseases is based on a detailed interview regarding the asbestos exposure, in addition to clinical, radiological, pathological, and laboratory data. This review provides a radiologic diagnosis of asbestos-related lung cancer.

Fixatives Used for Decommissioning and Maintenance of Radiological Facilities – 17537

Energy Technology Data Exchange (ETDEWEB)

Demmer, Rick; Fox, Don; Reese, Stephen; Banford, Anthony; Dodds, Jonathan

2017-01-01

The Idaho National Laboratory (INL) and the United Kingdom (UK) National Nuclear Laboratory (NNL) have been collaborating for several years on materials and methods for the fogged/misted introduction of fixatives into radiologically contaminated facilities. The objective of the project is to deliver a process for reducing airborne radiological and/or mercury contamination and affixing loose contamination in place, thereby reducing contamination risk to employees and decreasing D&D cost and schedule. The developed process provides a reliable, unmanned method of introducing a coating that captures and fixes contamination in place within facilities. The INL coating, termed FX2, has undergone extensive non-radiological testing, including determination that it is non-flammable, affixes contamination and flows well through unusual geometries (testing at Florida International University). A series of non-active fogging trials for activity knock/tie-down application have been completed at NNL Workington on behalf of Idaho National Laboratory (INL). These trials performed by the NNL employed commercially available agricultural fogging equipment and the INL’s knock/tie-down latex formulation (FX-2). This testing successfully demonstrated the ability of the fogging devices to successfully spray the FX-2 formulation within various scenarios, and prepared the project for a radioactive trial. The INL has also developed a mercury vapor reducing form of the coating termed FX-Hg, which has shown great promise in laboratory studies.

Pacific Northwest National Laboratory Facility Radionuclide Emissions Units and Sampling Systems

Energy Technology Data Exchange (ETDEWEB)

Barnett, J. Matthew; Brown, Jason H.; Walker, Brian A.

2012-04-01

Battelle–Pacific Northwest Division operates numerous research and development (R&D) laboratories in Richland, WA, including those associated with Pacific Northwest National Laboratory (PNNL) on the U.S. Department of Energy (DOE)’s Hanford Site and PNNL Site that have the potential for radionuclide air emissions. The National Emission Standard for Hazardous Air Pollutants (NESHAP 40 CFR 61, Subparts H and I) requires an assessment of all emission units that have the potential for radionuclide air emissions. Potential emissions are assessed annually by PNNL staff members. Sampling, monitoring, and other regulatory compliance requirements are designated based upon the potential-to-emit dose criteria found in the regulations. The purpose of this document is to describe the facility radionuclide air emission sampling program and provide current and historical facility emission unit system performance, operation, and design information. For sampled systems, a description of the buildings, exhaust units, control technologies, and sample extraction details is provided for each registered emission unit. Additionally, applicable stack sampler configuration drawings, figures, and photographs are provided. Deregistered emission unit details are provided as necessary for up to 5 years post closure.

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 Laboratory (SRL) is developing a mobile autonomous robot that performs radiological surveys of potentially contaminated floors. The robot is called SIMON, which stands for Semi-Intelligent Mobile Observing Navigator. Certain areas of SRL are classified as radiologically controlled areas (RCAs). In an RCA, radioactive materials are frequently handled by workers, and thus, the potential for contamination is ever present. Current methods used for floor radiological surveying includes labor-intensive manual scanning or random smearing of certain floor locations. An autonomous robot such as SIMON performs the surveying task in a much more efficient manner and will track down contamination before it is contacted by humans. SIMON scans floors at a speed of 1 in./s and stops and alarms upon encountering contamination. Its environment is well defined, consisting of smooth building floors with wide corridors. The kind of contaminations that SIMON is capable of detecting are alpha and beta-gamma. The contamination levels of interest are low to moderate

Radiological survey results at Porter Street City Park, Beverly, Massachusetts (VB026)

International Nuclear Information System (INIS)

Foley, R.D.; Johnson, C.A.

1992-08-01

At the request of the US Department of Energy (DOE), a team from Oak Ridge National Laboratory conducted a radiological survey at the Porter Street City Park, Beverly, Massachusetts. The survey was performed in May 1991. The purpose of the survey was to determine if uranium from work performed under government contract at the former Ventron facility had migrated off-site to neighboring areas. The survey included a surface gamma scan and the collection of soil samples for radionuclide analyses. Results of the survey demonstrated no radionuclide concentrations or radiation measurements in excess of the DOE Formerly Utilized Sites Remedial Action Program guidelines

The NRPB Chilton Calibration Laboratory for radiological protection measurements

International Nuclear Information System (INIS)

Iles, W.J.

1982-01-01

The Calibration Laboratory in NRPB Headquarters is intended as an authoritative reference laboratory for all aspects of radiation protection level instrument calibrations for X-, gamma and beta radiations and to be complementary to the national primary standards of the National Physical Laboratory. The gamma ray, filtered X-ray, fluorescence X-ray and beta ray facilities are described. (U.K.)

Characteristics and trends of radiology research: a survey of original articles published in AJR and Radiology between 2001 and 2010.

Science.gov (United States)

Lim, Kyoung Ja; Yoon, Dae Young; Yun, Eun Joo; Seo, Young Lan; Baek, Sora; Gu, Dong Hyeon; Yoon, Soo Jeong; Han, Ari; Ku, You Jin; Kim, Sam Soo

2012-09-01

To determine the characteristics and trends of the original articles published in two major American radiology journals, AJR American Journal of Roentgenology (AJR) and Radiology, between 2001 and 2010. This was a retrospective bibliometric analysis that did not involve human subjects and was exempt from institutional review board approval. All 6542 original articles published in AJR and Radiology between 2001 and 2010 were evaluated. The following information was abstracted from each article: radiologic subspecialty, radiologic technique used, type of research, sample size, study design, statistical analysis, study outcome, declared funding, number of authors, affiliation of the first author, and country of the first author. In addition, all the variables examined were presented along with the trend over time. The most common subspecialty of study was abdominal (1219 of 6542, 18.6%), followed by vascular/interventional (804 of 6542, 12.3%). A total of 3744 (57.2%) original articles used magnetic resonance (MR) imaging or computed tomography (CT), 5495 (84.1%) were clinical research articles, 3060 (46.8%) had sample size of more than 50, 4087 (62.5%) were retrospective, 4714 (72.1%) performed statistical analysis, 6225 (95.2%) showed positive study outcome, 4784 (73.1%) were not funded, 3942 (60.3%) had four to seven authors, and 5731 (87.6%) were written by the primary author who was from a department of radiology or radiology-related specialties. The United States published 45.5% (2975 of 6542) of the articles, followed by Japan (n = 525, 8.0%), Germany (n = 485, 7.4%), and South Korea (n = 455, 7.0%). In the time trend analysis, the following variables showed a significantly positive trend: cardiac subspecialty, CT and MR imaging as the radiologic techniques, type of research as other (nonbasic, nonclinical), sample size of more than 50, four to seven as the number of authors, medicine-related department of the first author, and South Korea and Italy as

A TWO-STAGE MODEL OF RADIOLOGICAL INSPECTION: SPENDING TIME

International Nuclear Information System (INIS)

BROWN, W.S.

2000-01-01

The paper describes a model that visually portrays radiological survey performance as basic parameters (surveyor efficiency and criteria, duration of pause, and probe speed) are varied; field and laboratory tests provided typical parameter values. The model is used to illustrate how practical constraints on the time allotted to the task can affect radiological inspection performance. Similar analyses are applicable to a variety of other tasks (airport baggage inspection, and certain types of non-destructive testing) with similar characteristics and constraints

Radiologically contaminated lead shot reuse at the Idaho National Engineering Laboratory (INEL)

International Nuclear Information System (INIS)

Heileson, W.M.; Grant, R.P.

1995-01-01

This project involved the utilization of radioactively contaminated lead shot located at the Radioactive Waste Management Complex (RWMC) for radiation shielding on a radioactive liquid process tank located at Argonne National Laboratory-West (ANL-W). The use of previously contaminated shot precludes the radioactive contamination of clean shot. With limited treatment and disposal options for contaminated lead shot, the reuse of lead for shielding is significant due to the inherent characteristic of becoming a mixed waste when radiologically contaminated. The INEL conducted a lead cleanup campaign in 1990. This was designed to ensure control of potential Resource Conservation and Recovery Act (RCRA) regulated waste. Contaminated lead from throughout the INEL, was containerized per the lead Waste Acceptance Criteria at the generator sites. Limited areas at the INEL are designated for mixed waste storage. As a result, some of the lead was stored at the RWMC in the air support weather shield (ASWS). This lead was contaminated with small amounts of fission product contamination. The lead was in the form of shot, brick, sheet, casks, and other various sized pieces. In 1993, ANL-W identified a need for lead shot to be used as shielding in a radioactive liquid waste storage and processing tank at the Fuel Cycle Facility (FCF). The contaminated lead used on this project had been in storage as mixed waste at the RWMC. This paper will focus on the processes and problems encountered to utilize the contaminated lead shot

Application of computers in a radiological survey program

International Nuclear Information System (INIS)

Berven, B.A.; Blair, M.S.; Doane, R.W.; Little, C.A.; Perdue, P.T.

1984-01-01

Computers have become increasingly important in data analysis and data management as well as assisting in report preparation in the Oak Ridge National Laboratory (ORNL) Radiological Survey Activities (RASA) Program. The primary function of the RASA program is to collect, analyze, report, and manage data collected to characterize the radiological condition of potentially contaminated sites identified in the Department of Energy's (DOE) remedial action programs. Three different computer systems are routinely utilized in ORNL/RASA operations. Two of these systems are employed in specific functions. A Nuclear Data (ND) 682 is used to perform isotopic analysis of gamma spectroscopic data generated by high-purity germanium detectors for air, water and soil samples. The ND682 employs a 16,000-channel analyzer that is routinely used with four germanium spectrometers. Word processing and data management are accomplished using the INtext system implemented on a DEC PDP-11 computer. A group of personal computers are used to perform a diverse number of functions. These computer systems are Commodore Business Machines (CBM) Model 8032 with a dual floppy disk storage medium and line printers (with optional X-Y plotters). The CBM's are utilized for: (1) data analysis -- raw data from radiation detection instrumentation are stored and manipulated with customized computer programs; (2) data reduction -- raw data are converted into report-ready tables using customized programs; (3) data management -- radionuclide data on each air, water and soil sample are stored on diskettes along with location of archived samples; and (4) program management -- site surveys and report status are tracked by computer files as well as program budget information to provide contemporary information of program status

Aerial radiological survey of the Idaho National Engineering Laboratory, Idaho Falls, Idaho. Date of survey: June 1982

International Nuclear Information System (INIS)

1984-02-01

An aerial radiological survey of the Idaho National Engineering Laboratory (INEL) was conducted during June 1982 by EG and G Energy Measurements, Inc. for the United States Department of Energy (DOE). The survey consisted of airborne measurements of both natural and man-made gamma radiation from the terrain surface in and around the INEL site. These measurements allowed an estimate of the distribution of isotopic concentrations in the survey area. Results are reported as isopleths superimposed on maps and photographs of the area. Gamma ray energy spectra are also presented for the net man-made radionuclides. The survey was designed to cover all of the area within a 2 mile radius of any facility at the INEL. Several areas of man-made activity were detected. These areas are all known working or storage areas which are associated with normal operations at the INEL. 3 references, 48 figures, 5 tables

Laboratory sample turnaround times: do they cause delays in the ED?

Science.gov (United States)

Gill, Dipender; Galvin, Sean; Ponsford, Mark; Bruce, David; Reicher, John; Preston, Laura; Bernard, Stephani; Lafferty, Jessica; Robertson, Andrew; Rose-Morris, Anna; Stoneham, Simon; Rieu, Romelie; Pooley, Sophie; Weetch, Alison; McCann, Lloyd

2012-02-01

Blood tests are requested for approximately 50% of patients attending the emergency department (ED). The time taken to obtain the results is perceived as a common reason for delay. The objective of this study was therefore to investigate the turnaround time (TAT) for blood results and whether this affects patient length of stay (LOS) and to identify potential areas for improvement. A time-in-motion study was performed at the ED of the John Radcliffe Hospital (JRH), Oxford, UK. The duration of each of the stages leading up to receipt of 101 biochemistry and haematology results was recorded, along with the corresponding patient's LOS. The findings reveal that the mean time for haematology results to become available was 1 hour 6 minutes (95% CI: 29 minutes to 2 hours 13 minutes), while biochemistry samples took 1 hour 42 minutes (95% CI: 1 hour 1 minute to 4 hours 21 minutes), with some positive correlation noted with the patient LOS, but no significant variation between different days or shifts. With the fastest 10% of samples being reported within 35 minutes (haematology) and 1 hour 5 minutes (biochemistry) of request, our study showed that delays can be attributable to laboratory TAT. Given the limited ability to further improve laboratory processes, the solutions to improving TAT need to come from a collaborative and integrated approach that includes strategies before samples reach the laboratory and downstream review of results. © 2010 Blackwell Publishing Ltd.

Trends in radiological and environmental protection at high energy accelerator laboratories

International Nuclear Information System (INIS)

Perry, D.R.; Shaw, K.B.; Stapleton, G.B.; Thomas, R.H.

1991-03-01

The serious study of high-energy particle accelerator radiological protection began in the early 1950s and has continued since then. This paper treats the subject in seven stages, and begins by briefly reviewing the work done until the 80s, which comprises the first five stages. These are, observation of high radiation levels, shielding studies, dosimetry, induced activity and the environmental effects. The sixth stage, control by legislation and regulation, is discussed in detail. Over the past twenty years there have been significant additions to radiological protection standards: from a scientifically based estimate of risk to a social desire to reduce exposure to levels determined only by the ''best practical means (BPM)'' or as it is currently understood in the United States of America ''best available technology (BAT)''. The implications of this trend are explored, and the success with which changing standards have been followed is studied with the aid of data derived from personnel doses. The last stage is the decommissioning or disposal of high energy accelerators. (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

Tank Vapor Sampling and Analysis Data Package for Tank 241-Z-361 Sampled 09/22/1999 and 09/27/1999, During Sludge Core Removal

International Nuclear Information System (INIS)

VISWANATH, R.S.

1999-01-01

This data package presents sampling data and analytical results from the September 22 and 27, 1999, headspace vapor sampling of Hanford Site Tank 241-2-361 during sludge core removal. The Lockheed Martin Hanford Corporation (LMHC) sampling team collected the samples and Waste Management Laboratory (WML) analyzed the samples in accordance with the requirements specified in the 241-2361 Sludge Characterization Sampling and Analysis Plan, (SAP), HNF-4371/Rev. 1, (Babcock and Wilcox Hanford Corporation, 1999). Six SUMMA(trademark) canister samples were collected on each day (1 ambient field blank and 5 tank vapor samples collected when each core segment was removed). The samples were radiologically released on September 28 and October 4, 1999, and received at the laboratory on September 29 and October 6, 1999. Target analytes were not detected at concentrations greater than their notification limits as specified in the SAP. Analytical results for the target analytes and tentatively identified compounds (TICs) are presented in Section 2.2.2 starting on page 2B-7. Three compounds identified for analysis in the SAP were analyzed as TICs. The discussion of this modification is presented in Section 2.2.1.2

Document: the radiological survey of the environment

International Nuclear Information System (INIS)

Gerno, Linden; Leprieur, F.; Janssens, A.

2002-01-01

The document presents the radiological survey of the environment in France today with a comparison of the situation in Switzerland, Germany and Belgium. The evolution of the policy in this activity is also concerned. The laboratories and their monitoring equipment, the regulation and the social impacts are discussed. (A.L.B.)

Environmental behavior of technetium in soil and vegetation: implications for radiological impact assessment

International Nuclear Information System (INIS)

Hoffman, F.O.

1982-04-01

Significant radiological exposures have been estimated for hypothetical atmospheric releases of Tc-99 from gaseous diffusion facilities when vegetation-to-soil concentration ratios representative of laboratory experiments are substituted for generic default values assumed in current regulatory models. To test the relevancy of these laboratory ratios, field investigations were conducted to obtain measurements of the vegetation-to-soil concentration ratio for Tc-99 in samples collected near operating gaseous diffusion facilities and to observe the dynamic behavior of technetium in soil and vegetation following a single application of a sprayed solution of /sup 95m/TcO 4 - Comparison of observed field concentration ratios and calculated steady-state concentration ratios with ratios obtained from previous laboratory experiments indicates that concentration ratios obtained from field data are one to two orders of magnitude less than those obtained from the laboratory. Furthermore, a substantial accumulation of technetium in soil and vegetation may not occur over long periods of time, since concentrations of technetium in both environmental media were observed to decrease with time subsequent to initial application of /sup 95m/TcO 4 -

Nationwide survey of policies and practices related to capillary blood sampling in medical laboratories in Croatia

OpenAIRE

Lenicek Krleza, Jasna

2014-01-01

Introduction: Capillary sampling is increasingly used to obtain blood for laboratory tests in volumes as small as necessary and as non-invasively as possible. Whether capillary blood sampling is also frequent in Croatia, and whether it is performed according to international laboratory standards is unclear. Materials and methods: All medical laboratories that participate in the Croatian National External Quality Assessment Program (N = 204) were surveyed on-line to collect information about t...

Radiological protection at particle accelerators: An overview

International Nuclear Information System (INIS)

Thomas, R.H.

1991-01-01

Radiological protection began with particle accelerators. Many of the concerns in the health physics profession today were discovered at accelerator laboratories. Since the mid-1940s, our understanding has progressed through seven stages: observation of high radiation levels; shielding; development of dosimetric techniques; studies of induced activity and environmental impact; legislative and regulatory concerns; and disposal. The technical and scientific aspects of accelerator radiation safety are well in hand. In the US, there is an urgent need to move away from a ''best available technology'' philosophy to risk-based health protection standards. The newer accelerators will present interesting radiological protection issues, including copious muon production and high LET (neutron) environments

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.

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.

Capillary blood sampling: national recommendations on behalf of the Croatian Society of Medical Biochemistry and Laboratory Medicine.

Science.gov (United States)

Krleza, Jasna Lenicek; Dorotic, Adrijana; Grzunov, Ana; Maradin, Miljenka

2015-01-01

Capillary blood sampling is a medical procedure aimed at assisting in patient diagnosis, management and treatment, and is increasingly used worldwide, in part because of the increasing availability of point-of-care testing. It is also frequently used to obtain small blood volumes for laboratory testing because it minimizes pain. The capillary blood sampling procedure can influence the quality of the sample as well as the accuracy of test results, highlighting the need for immediate, widespread standardization. A recent nationwide survey of policies and practices related to capillary blood sampling in medical laboratories in Croatia has shown that capillary sampling procedures are not standardized and that only a small proportion of Croatian laboratories comply with guidelines from the Clinical Laboratory Standards Institute (CLSI) or the World Health Organization (WHO). The aim of this document is to provide recommendations for capillary blood sampling. This document has been produced by the Working Group for Capillary Blood Sampling within the Croatian Society of Medical Biochemistry and Laboratory Medicine. Our recommendations are based on existing available standards and recommendations (WHO Best Practices in Phlebotomy, CLSI GP42-A6 and CLSI C46-A2), which have been modified based on local logistical, cultural, legal and regulatory requirements. We hope that these recommendations will be a useful contribution to the standardization of capillary blood sampling in Croatia.

Determination of Crack Area on Lead Apron used in Diagnostic Radiology

International Nuclear Information System (INIS)

Norriza Mohd Isa; Muhammad Jamal Muhammad Isa; Asmaliza Hashim

2014-01-01

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

Radiological protection report 2012; Strahlenschutzbericht 2012

Energy Technology Data Exchange (ETDEWEB)

NONE

2013-06-15

Two years after the massive release of radiation from the nuclear power plants at Fukushima Dai-ichi, the repercussions continue to preoccupy the radiological and emergency protection community, both in Switzerland and internationally. In Switzerland the Swiss Federal Nuclear Safety Inspectorate (ENSI) has initiated measures as part of the European Union Stress Tests and has its own Fukushima Action Plan. In this Annual Report, ENSI focuses on radiological protection in Swiss nuclear facilities. The average individual dose has changed little compared with previous years. At 0.7 mSv, it is significantly below the limit both for persons exposed to radiation during their work (20 mSv) and the annual average rate of exposure for the population in Switzerland as a whole (5.5 mSv). In terms of collective doses, the extensive maintenance work at the Leibstadt power plant (KKL) resulted in a doubling of rates compared with recent years. However, in the remaining nuclear facilities the rates have not changed significantly. The highest individual dose during the year under review was 13 mSv. Exposure rates in 2012 for all those exposed to radiation during work in facilities subject to ENSI surveillance were below the maximum limit. Greater attention is now being given to work in high and variable radiation fields and in difficult conditions. Swiss nuclear facilities continue to operate a consistent radiological protection approach. Measuring equipment plays an important role in radiological protection. Having conducted a range of inspections and comparative measurements of aerosol-iodine filters and waste water sampling together with measurements in the field of personal dosimetry, ENSI has concluded that the required measuring equipment for radiological protection exists, that this equipment is correctly used and provides reliable data. ENSI maintains a test laboratory that analyses samples from nuclear facilities and their immediate vicinity and also conducts field

ORIGINAL ARTICLES Assessment of routine laboratory screening of ...

African Journals Online (AJOL)

clinical examination rather than failing to perform blanket laboratory and radiological ... additional information to that obtained from a thorough history and clinical ... reviewed to determine the patient's diagnosis and management plan. ... system were considered not to have had laboratory investigations performed.

Automated blood-sample handling in the clinical laboratory.

Science.gov (United States)

Godolphin, W; Bodtker, K; Uyeno, D; Goh, L O

1990-09-01

The only significant advances in blood-taking in 25 years have been the disposable needle and evacuated blood-drawing tube. With the exception of a few isolated barcode experiments, most sample-tracking is performed through handwritten or computer-printed labels. Attempts to reduce the hazards of centrifugation have resulted in air-tight lids or chambers, the use of which is time-consuming and cumbersome. Most commonly used clinical analyzers require serum or plasma, distributed into specialized containers, unique to that analyzer. Aliquots for different tests are prepared by handpouring or pipetting. Moderate to large clinical laboratories perform so many different tests that even multi-analyzers performing multiple analyses on a single sample may account for only a portion of all tests ordered for a patient. Thus several aliquots of each specimen are usually required. We have developed a proprietary serial centrifuge and blood-collection tube suitable for incorporation into an automated or robotic sample-handling system. The system we propose is (a) safe--avoids or prevents biological danger to the many "handlers" of blood; (b) small--minimizes the amount of sample taken and space required to adapt to the needs of satellite and mobile testing, and direct interfacing with analyzers; (c) serial--permits each sample to be treated according to its own "merits," optimizes throughput, and facilitates flexible automation; and (d) smart--ensures quality results through monitoring and intelligent control of patient identification, sample characteristics, and separation process.

A study regarding measurements of bacterial contamination levels in radiology room equipment

Energy Technology Data Exchange (ETDEWEB)

Choi, Eun Jin [Dept. of Public Health and Medicine, Dongshin University Graduate School, Naju (Korea, Republic of); Song, Hyeon Je [Dept. of Clinical Pathology, Gwangju Health University, Gwangju (Korea, Republic of); Dong, Kyung Rae; Kim, Chang Bok [Dept. of Radiological Technology, Gwangju Health University, Gwangju (Korea, Republic of); Ryu, Jae Kwang [Dept. of Nuclear Medicine, Asan Medical Center, Seoul (Korea, Republic of)

2017-03-15

Reported some level of bacteria in areas that are well made contact in Radiology imaging room evaluate the importance of cleanliness in the hospital management of equipment to check for the presence of pathogenic bacteria. Gwang-ju and Jeol-la city and medium-sized hospitals in the material with a cotton swab and rub evenly Radiology selection cassette, a handle, Apron of the imaging apparatus having the most contact with patients from July 2016 to August 2016 as a target in place and special studios 6, and saline solution will placed in a test tube containing. The swab sample was diluted 1,000 times, you can see the bacteria and the intestinal bacterial selective medium Trypticase Soy Agar (TSA), Muller-Hinton Agar (MHA), EosinMethylene Blue (EMB), ENDO (BD, NJ, USA) then incubated smear to. In the incubator (incubator, SANYO, Japan) was observed after incubation of bacteria and counting the total number of bacteria also Colonies (colony) suspected intestinal bacteria were isolated and cultured on KIA medium (BD, NJ, USA). As a result, it was found that this came Gram positive Coccus A hospital handle the F hospital, from the C Gram positive Coccus cassette and handle the F hospital. The striking yellow coloring Staphylococcus aureus 110 agar (STA 110) in the medium sample, but it is suspected staphylococcal Coccus to the final identifcation in the laboratory is not a single specimen of the two samples from Gram positive Coccus biochemical identifcation. Identifcation Kit is an API could not, it was thought to be non-Staphylococcus aureus was cultured on blood agar suggesting that (BAP) blood of dance. Dynamic tests were conducted biochemical API kit of the two samples were identifed from Gram positive Coccus bacteria Escherichia coli (E. coli) is F hospital cassette was confrmed Eenterobacter cloaca in A hospital possession. Did not aggregate O-26, O-111, O-157 and the serum test was conducted in the laboratory from the E. coli F cassette hospital.

A study regarding measurements of bacterial contamination levels in radiology room equipment

International Nuclear Information System (INIS)

Choi, Eun Jin; Song, Hyeon Je; Dong, Kyung Rae; Kim, Chang Bok; Ryu, Jae Kwang

2017-01-01

Reported some level of bacteria in areas that are well made contact in Radiology imaging room evaluate the importance of cleanliness in the hospital management of equipment to check for the presence of pathogenic bacteria. Gwang-ju and Jeol-la city and medium-sized hospitals in the material with a cotton swab and rub evenly Radiology selection cassette, a handle, Apron of the imaging apparatus having the most contact with patients from July 2016 to August 2016 as a target in place and special studios 6, and saline solution will placed in a test tube containing. The swab sample was diluted 1,000 times, you can see the bacteria and the intestinal bacterial selective medium Trypticase Soy Agar (TSA), Muller-Hinton Agar (MHA), EosinMethylene Blue (EMB), ENDO (BD, NJ, USA) then incubated smear to. In the incubator (incubator, SANYO, Japan) was observed after incubation of bacteria and counting the total number of bacteria also Colonies (colony) suspected intestinal bacteria were isolated and cultured on KIA medium (BD, NJ, USA). As a result, it was found that this came Gram positive Coccus A hospital handle the F hospital, from the C Gram positive Coccus cassette and handle the F hospital. The striking yellow coloring Staphylococcus aureus 110 agar (STA 110) in the medium sample, but it is suspected staphylococcal Coccus to the final identifcation in the laboratory is not a single specimen of the two samples from Gram positive Coccus biochemical identifcation. Identifcation Kit is an API could not, it was thought to be non-Staphylococcus aureus was cultured on blood agar suggesting that (BAP) blood of dance. Dynamic tests were conducted biochemical API kit of the two samples were identifed from Gram positive Coccus bacteria Escherichia coli (E. coli) is F hospital cassette was confrmed Eenterobacter cloaca in A hospital possession. Did not aggregate O-26, O-111, O-157 and the serum test was conducted in the laboratory from the E. coli F cassette hospital

Recommended procedures for performance testing of radiobioassay laboratories: Volume 2, In vitro samples

International Nuclear Information System (INIS)

Fenrick, H.W.; MacLellan, J.A.

1988-11-01

Draft American National Standards Institute (ANSI) Standard N13.30 (Performance Criteria for Radiobioassay) was developed for the US Department of Energy and the US Nuclear Regulatory Commission to help ensure that bioassay laboratories provide accurate and consistent results. The draft standard specifies the criteria for defining the procedures necessary to establish a bioassay performance-testing laboratory and program. The bioassay testing laboratory will conduct tests to evaluate the performance of service laboratories. Pacific Northwest Laboratory helped develop testing procedures as part of an effort to evaluate the performance criteria by testing the existing measurement capabilities of various bioassay laboratories. This report recommends guidelines for the preparation, handling, storage, distribution, shipping, and documentation of in vitro test samples (artificial urine and fecal matter) for indirect bioassay. The data base and recommended records system for documenting radiobioassay performance at the service laboratories are also presented. 8 refs., 3 tabs

ICP/AES radioactive sample analyses at Pacific Northwest Laboratory

International Nuclear Information System (INIS)

Matsuzaki, C.L.; Hara, F.T.

1986-03-01

Inductively coupled argon plasma atomic emission spectroscopy (ICP/AES) analyses of radioactive materials at Pacific Northwest Laboratory (PNL) began about three years ago upon completion of the installation of a modified Applied Research Laboratory (ARL) 3560. Funding for the purchase and installation of the ICP/AES was provided by the Nuclear Waste Materials Characterization Center (MCC) established at PNL by the Department of Energy in 1979. MCC's objective is to ensure that qualified materials data are available on waste materials. This paper is divided into the following topics: (1) Instrument selection considerations; (2) initial installation of the simultaneous system with the source stand enclosed in a 1/2'' lead-shielded glove box; (3) retrofit installation of the sequential spectrometer; and (4) a brief discussion on several types of samples analyzed. 1 ref., 7 figs., 1 tab

Radiology today

International Nuclear Information System (INIS)

Donner, M.W.; Heuck, F.H.W.

1981-01-01

The book encompasses the proceedings of a postgraduate course held in Salzburg in June 1980. 230 radiologists from 17 countries discussed here the important and practical advances of diagnostic radiology, nuclear medicine and ultrasound as they contribute to gastrointestinal, urologic, skeletal, cardiovascular, pediatric, and neuroradiology. The book contains 55 single contributions of different authors to the following main themes: Cardiovascular, Radiology, pulmonary radiology, gastrointestinal radiology, urinary tract radiology, skeletal radiology, mammography, lymphography, ultrasound, ENT radiology, and neuroradiology. (orig./MG)

Radioactive Waste Management Complex low-level waste radiological performance assessment

Energy Technology Data Exchange (ETDEWEB)

Maheras, S.J.; Rood, A.S.; Magnuson, S.O.; Sussman, M.E.; Bhatt, R.N.

1994-04-01

This report documents the projected radiological dose impacts associated with the disposal of radioactive low-level waste at the Radioactive Waste Management Complex at the Idaho National Engineering Laboratory. This radiological performance assessment was conducted to evaluate compliance with applicable radiological criteria of the US Department of Energy and the US Environmental Protection Agency for protection of the public and the environment. The calculations involved modeling the transport of radionuclides from buried waste, to surface soil and subsurface media, and eventually to members of the public via air, groundwater, and food chain pathways. Projections of doses were made for both offsite receptors and individuals inadvertently intruding onto the site after closure. In addition, uncertainty and sensitivity analyses were performed. The results of the analyses indicate compliance with established radiological criteria and provide reasonable assurance that public health and safety will be protected.

Radioactive Waste Management Complex low-level waste radiological performance assessment

International Nuclear Information System (INIS)

Maheras, S.J.; Rood, A.S.; Magnuson, S.O.; Sussman, M.E.; Bhatt, R.N.

1994-04-01

This report documents the projected radiological dose impacts associated with the disposal of radioactive low-level waste at the Radioactive Waste Management Complex at the Idaho National Engineering Laboratory. This radiological performance assessment was conducted to evaluate compliance with applicable radiological criteria of the US Department of Energy and the US Environmental Protection Agency for protection of the public and the environment. The calculations involved modeling the transport of radionuclides from buried waste, to surface soil and subsurface media, and eventually to members of the public via air, groundwater, and food chain pathways. Projections of doses were made for both offsite receptors and individuals inadvertently intruding onto the site after closure. In addition, uncertainty and sensitivity analyses were performed. The results of the analyses indicate compliance with established radiological criteria and provide reasonable assurance that public health and safety will be protected

Lawrence Berkeley National Laboratory 1995 site environmental report

Energy Technology Data Exchange (ETDEWEB)

Balgobin, D.; Javandel, I.; Lackner, G.; Smith, C.; Thorson, P.; Tran, H.

1996-07-01

The 1995 Site Environmental Report summarizes environmental activities at the Ernest Orlando Lawrence Berkeley National Laboratory (LBNL) for the 1995 calendar year. The report strives to present environmental data in a manner that characterizes the performance and compliance status of the environmental management programs. The report also discusses significant highlights and plans of these programs. Topics discussed include: environmental monitoring, environmental compliance programs, air quality, water quality, ground water protection, sanitary sewer monitoring, soil and sediment quality, vegetation and foodstuffs monitoring, and special studies which include preoperational monitoring of building 85 and 1995 sampling results, radiological dose assessment, and quality assessment.

Lawrence Berkeley National Laboratory 1995 site environmental report

International Nuclear Information System (INIS)

Balgobin, D.; Javandel, I.; Lackner, G.; Smith, C.; Thorson, P.; Tran, H.

1996-07-01

The 1995 Site Environmental Report summarizes environmental activities at the Ernest Orlando Lawrence Berkeley National Laboratory (LBNL) for the 1995 calendar year. The report strives to present environmental data in a manner that characterizes the performance and compliance status of the environmental management programs. The report also discusses significant highlights and plans of these programs. Topics discussed include: environmental monitoring, environmental compliance programs, air quality, water quality, ground water protection, sanitary sewer monitoring, soil and sediment quality, vegetation and foodstuffs monitoring, and special studies which include preoperational monitoring of building 85 and 1995 sampling results, radiological dose assessment, and quality assessment

Laboratory Sampling Guide

Science.gov (United States)

2012-05-11

environment, and by ingestion of foodstuffs that have incorporated C-14 by photosynthesis . Like tritium, C-14 is a very low energy beta emitter and is... bacterial growth and to minimize development of solids in the sample. • Properly identify each sample container with name, SSN, and collection start and...sampling in the same cardboard carton. The sample may be kept cool or frozen during collection to control odor and bacterial growth. • Once

Automation of the radiological survey process: USRADS ultrasonic ranging and data system

International Nuclear Information System (INIS)

Berven, B.A.; Blair, M.S.; Little, C.A.

1987-01-01

The Radiological Survey Activities (RASA) program at Oak Ridge National Laboratory (ORNL) serves as the Inclusion Survey Contractor (ISC) in the Department of Energy's (DOE) Uranium Mill Tailings Remedial Action project (UMTRAP). The ISC is to identify properties in the vicinity of 24 inactive uranium mill sites suspected of having 226 Ra-bearing uranium mill tailings by-product material originating from the processing of uranium ore contamination. Mobile gamma scanning was the primary method used to identify these properties. Once identified, the ISC conducts an inclusion survey. This survey performs sufficient radiological measurements to determine if uranium mill tailing contamination is present, and, if so, if it is in excess of relevant Environmental Protection Agency (EPA) criteria. Radon emanating from 226 Ra is the primary pathway of exposure to human occupants at these sites. EPA criteria focus on controlling 226 Ra concentration in soil. The concentration of 226 Ra in soil can be measured directly by soil sampling and subsequent gamma spectrographic analysis of the sample, or by direct measurement of the gamma exposure rate at the soil surface using portable instrumentation in the field. In both methods, the concentration of 226 Ra is inferred by examining the frequency of gamma emission of 214 Bi, a radioactive decay product in the 238 U decay chain

Preliminary assessment of the radiological impact for individual waste management areas at the Oak Ridge National Laboratory: Status report

International Nuclear Information System (INIS)

Sears, M.B.

1987-09-01

This study estimates the radiological impact (i.e., the potential doses) for individual waste management areas at the Oak Ridge National Laboratory and ranks the areas for remedial action based on the off-site doses that result from these discharges to White Oak Creek. Dose estimates are given for the drinking water pathway based on known discharges from White Oak Dam. Estimates are also made of doses for eating fish caught in the Clinch River near the confluence with White Oak Creek. The results of a search for data concerning the discharges of 90 Sr, 3 H, 137 Cs, and 60 Co from individual waste management areas are presented. A qualitative assessment is presented, and areas are ranked for remedial investigation based on the available information. 29 refs., 8 figs., 45 tabs

NV/YMP radiological control manual, Revision 2

International Nuclear Information System (INIS)

Gile, A.L.

1996-11-01

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

NV/YMP radiological control manual, Revision 2

Energy Technology Data Exchange (ETDEWEB)

Gile, A.L. [comp.

1996-11-01

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

Hypermetabolic Thyroid Incidentaloma on Positron Emission Tomography: Review of Laboratory, Radiologic, and Pathologic Characteristics

Directory of Open Access Journals (Sweden)

Mehrdad Bakhshayesh Karam

2017-01-01

Full Text Available Introduction. Incidental hypermetabolic thyroid lesions on Positron Emission Tomography have significant clinical value and may harbor malignancy. In this study we evaluated laboratory, radiologic, and pathologic characteristics of incidental hypermetabolic thyroid lesions. Materials and Methods. We evaluated 18 patients prospectively with various malignancies and hypermetabolic thyroid incidentaloma. The thyroid function tests, ultrasound assessment, and guided FNA biopsy were performed on all cases. Results. We included 9 male and 9 female patients with mean age of 51 years. Most common malignancy was colon cancer. Metabolic activity quantification using maximum standard uptake value demonstrated range between 1.4 and 65.4 with mean value of 9.4. We found highest metabolic activity in patients with lung adenocarcinoma, B-cell lymphoma, and colon adenocarcinoma. On ultrasound exam most thyroid lesions were of solid, hypoechoic, noncalcified nature with either normal or peripheral increased vascularity. FNA biopsy report was benign in 15 cases and malignant or highly suggestive for malignancy in 3 other cases. Two of the three malignant cases demonstrated metabolic activity higher than average SUV max. Conclusion. Most thyroid hypermetabolic incidentalomas are benign lesions, while higher values of SUV max are in favor of malignancy. This mandates further evaluation of incidentally found thyroid hypermetabolic lesions on routine PET/CT scans.

Radiology compared with xenon—133 scanning and bronchoscopic lobar sampling as methods for assessing regional lung function in patients with emphysema

Science.gov (United States)

Barter, C. E.; Hugh-Jones, P.; Laws, J. W.; Crosbie, W. A.

1973-01-01

Regional lung function was assessed by radiographic methods, by regional function studies using xenon-133 scans, and by lobar sampling with a mass spectrometer flow-meter at bronchoscopy in 12 patients who subsequently had bullae resected at operation. The information given by these three methods of regional assessment was subsequently compared with the findings at operation. When only one lobe was abnormal on the radiographs, these alone were adequate to locate the major site of the emphysema and the regional tests gave relatively little extra information. The xenon scan was sometimes helpful in assessing the state of the remaining lung, but this information could be deduced from the radiographs and overall lung function tests, especially the carbon monoxide transfer and mechanical measurements. Bronchoscopic sampling was helpful in determining whether the affected lobe was acting as a ventilated dead-space. When more than one lobe was affected the regional function tests supplemented the radiographs in defining the site of bullous change as well as locating dead space. Xenon scans, although widely employed for such preoperative assessments, added little to the topographical information obtained by careful radiology. The combination of radiology, lobar sampling, and overall function tests is recommended for assessing which emphysematous patients are likely to benefit from surgery. Images PMID:4685209

Decontamination and decommission of a radiochemical laboratory building complex

International Nuclear Information System (INIS)

Zoubek, Norbert

2008-01-01

Full text: Handling of unsealed radioactive substances for research and development purposes in chemical or pharmaceutical industries or research centres as well as production of radioactive substances (e.g. for applications in nuclear medicine or industry) requires operation of special radiochemical laboratories. In general, operation of radiochemical laboratories is strongly regulated by the government and national authorities. The operator needs a permit related to radiological protection. In general, technical requirements for such facilities are very high. To ensure high safety standards with respect to the employees and the environment, several radiological protection measures have to be taken. These measures (for example special shielding or ventilation and waste water systems) depend on various factors, e.g. activity in use, kind of nuclides, chemical properties and volatility of substances. In order to close-down such radiochemical laboratories some radiological protection measures have to be maintained to ensure protection of both humans and the environment induced by possible residual contaminations within the facility including technical inventory. However, a later reuse of the facility as a non-radioactive facility requires removal of all radioactive contamination with respect to national regulation. Resulting radioactive wastes have to be disposed of under control of competent authorities. Based on the experience of a decontamination and decommission project for a former radiochemical laboratory complex, the main steps necessary to release such a facility are discussed. Analytical aspects of initial conditions, necessary organisational structures within the project, resources needed estimation and exploration of the radiological situation in the laboratory, elaboration of a measuring strategy and decontamination methods as well as different waste disposal routes in relation to different waste types are reported. (author)

Sampling for Air Chemical Emissions from the Life Sciences Laboratory II

Energy Technology Data Exchange (ETDEWEB)

Ballinger, Marcel Y. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Lindberg, Michael J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

2017-03-30

Sampling for air chemical emissions from the Life Science Laboratory II (LSL-II) ventilation stack was performed in an effort to determine potential exposure of maintenance staff to laboratory exhaust on the building roof. The concern about worker exposure was raised in December 2015 and several activities were performed to assist in estimating exposure concentrations. Data quality objectives were developed to determine the need for and scope and parameters of a sampling campaign to measure chemical emissions from research and development activities to the outside air. The activities provided data on temporal variation of air chemical concentrations and a basis for evaluating calculated emissions. Sampling for air chemical emissions was performed in the LSL-II ventilation stack over the 6-week period from July 26 to September 1, 2016. A total of 12 sampling events were carried out using 16 sample media. Resulting analysis provided concentration data on 49 analytes. All results were below occupational exposure limits and most results were below detection limits. When compared to calculated emissions, only 5 of the 49 chemicals had measured concentrations greater than predicted. This sampling effort will inform other study components to develop a more complete picture of a worker’s potential exposure from LSL-II rooftop activities. Mixing studies were conducted to inform spatial variation in concentrations at other rooftop locations and can be used in conjunction with these results to provide temporal variations in concentrations for estimating the potential exposure to workers working in and around the LSL-II stack.

Professional Acceptance Of Electronic Images In Radiologic Practice

Science.gov (United States)

Gitlin, Joseph N.; Curtis, David J.; Kerlin, Barbara D.; Olmsted, William W.

1983-05-01

During the past four years, a large number of radiographic images have been interpreted in both film and video modes in an effort to determine the utility of digital/analogue systems in general practice. With the cooperation of the Department of Defense, the MITRE Corporation, and several university-based radiology departments, the Public Health Service has participated in laboratory experiments and a teleradiology field trial to meet this objective. During the field trial, 30 radiologists participated in the interpretation of more than 4,000 diagnostic x-ray examinations that were performed at distant clinics, digitized, and transmitted to a medical center for interpretation on video monitors. As part of the evaluation, all of the participating radiologists and the attending physicians at the clinics were queried regarding the teleradiology system, particularly with respect to the diagnostic quality of the electronic images. The original films for each of the 4,000 examinations were read independently, and the findings and impressions from each mode were compared to identify discrepancies. In addition, a sample of 530 cases was reviewed and interpreted by a consensus panel to measure the accuracy of findings and impressions of both film and video readings. The sample has been retained in an automated archive for future study at the National Center of Devices and Radiological Health facilities in Rockville, Maryland. The studies include a comparison of diagnostic findings and impressions from 1024 x 1024 matrices with those obtained from the 512 x 512 format used in the field trial. The archive also provides a database for determining the effect of data compression techniques on diagnostic interpretations and establishing the utility of image processing algorithms. The paper will include an analysis of the final results of the field trial and preliminary findings from the ongoing studies using the archive of cases at the National Center for Devices and Radiological

Results of the radiological survey at Diebold Safe Company, 1550 Grand Boulevard, Hamilton, Ohio (HO001)

International Nuclear Information System (INIS)

Foley, R.D.; Floyd, L.M.

1990-02-01

At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducted investigative radiological surveys at Diebold Safe Company, 1550 Grand Boulevard, Hamilton, Ohio in 1988 and 1989. The purpose of the surveys was to determine whether the property was contaminated with radioactive residues, principally 238 U. The surveys included gamma scans; direct and transferable measurements of alpha, beta, and gamma radiation levels; and dust, debris, air, and soil sampling for radionuclide analyses. 6 refs., 6 figs., 5 tabs

Annual course of retraining for the occupational exposure personnel of the laboratory of internal dosimetry

International Nuclear Information System (INIS)

Alfaro L, M.M.

2002-09-01

The general objective of this report is to instruct the personnel in the basic concepts of radiological protection and in the Manual of Procedures of Radiological Safety of the Laboratory of Internal Dosimetry. Also, to exchange experiences during the activities that are carried out in the laboratory and in the knowledge of abnormal situations. The referred Manual consists of 14 procedures and 5 instructions which are listed in annex of this document. The content of this course consists of three topics: 1. Basic principles of radiological protection to reduce the received dose equivalent. 2. Use of radiation measurer equipment. 3. Emergency procedures of the laboratory of internal dosimetry. (Author)

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)

Radiological characterization of spent control rod assemblies

International Nuclear Information System (INIS)

Lepel, E.A.; Robertson, D.E.; Thomas, C.W.; Pratt, S.L.; Haggard, D.L.

1995-10-01

This document represents the final report of an ongoing study to provide radiological characterizations, classifications, and assessments in support of the decommissioning of nuclear power stations. This report describes the results of non-destructive and laboratory radionuclide measurements, as well as waste classification assessments, of BWR and PWR spent control rod assemblies. The radionuclide inventories of these spent control rods were determined by three separate methodologies, including (1) direct assay techniques, (2) calculational techniques, and (3) by sampling and laboratory radiochemical analyses. For the BWR control rod blade (CRB) and PWR burnable poison rod assembly (BPRA), 60 Co and 63 Ni, present in the stainless steel cladding, were the most abundant neutron activation products. The most abundant radionuclide in the PWR rod cluster control assembly (RCCA) was 108m Ag (130 yr halflife) produced in the Ag-In-Cd alloy used as the neutron poison. This radionuclide will be the dominant contributor to the gamma dose rate for many hundreds of years. The results of the direct assay methods agree very well (±10%) with the sampling/radiochemical measurements. The results of the calculational methods agreed fairly well with the empirical measurements for the BPRA, but often varied by a factor of 5 to 10 for the CRB and the RCCA assemblies. If concentration averaging and encapsulation, as allowed by 10CFR61.55, is performed, then each of the entire control assemblies would be classified as Class C low-level radioactive waste

Pediatric radiology for medical-technical radiology assistants/radiologists

International Nuclear Information System (INIS)

Oppelt, Birgit

2010-01-01

The book on pediatric radiology includes the following chapter: differences between adults and children; psycho-social aspects concerning the patient child in radiology; relevant radiation doses in radiology; help for self-help: simple phantoms for image quality estimation in pediatric radiology; general information; immobilization of the patient; pediatric features for radiological settings; traumatology; contrast agents; biomedical radiography; computerized tomography; NMR imaging; diagnostic ultrasonography; handling of stress practical recommendations; medical displays.

Results of the radiological survey at the former ore storage site, Palmerton, Pennsylvania (PP001)

International Nuclear Information System (INIS)

Cottrell, W.D.; Quillen, J.L.; Crutcher, J.W.

1990-12-01

As part of the Formerly Utilized Sites Remedial Action Program (FUSRAP), the US Department of Energy (DOE) is implementing a radiological survey program to determine the radiological conditions at sites that were used by the department's predecessor agencies. The radiological survey discussed in this report for the former ore storage site in Palmerton, Pennsylvania, is part of the FUSRAP effort and was conducted at the request of DOE by members of the Measurement Applications and Development group of Oak Ridge National Laboratory (ORNL) in 1988. In 1953 and 1954 the Atomic Energy Commission (AEC) established an ore stockpile on the property of the New Jersey Zinc Corporation in Palmerton, Pennsylvania. Approximately 57 truckloads of ore (about 360 tons) were stored at this site and remained there until 1973, when the AEC initiated a clean-up program. The 1988 ORNL radiological survey included a gamma scan at the ground surface, gamma measurements at discrete locations at the surface and at 1 m above the surface, gamma logging of 80 auger holes, and collection of 161 surface and subsurface soil samples. Of these 161 soil samples, 98% were below DOE guidelines for 226 Ra concentration in soil. Interpretation of the data suggests small, isolated spots of residual ore. The data indicate that it is highly unlikely that an individual living or working on this site could receive a radiation dose approaching the 100 mrem annual limit. However, it is suggested that DOE evaluate potential exposures at this site to ensure compliance with their policy that all exposures to radiation are reduced to levels that are as low as reasonably achievable. 4 refs., 88 figs., 4 tabs

Technical assessment of compliance with workplace air sampling requirements in the 300 Area

International Nuclear Information System (INIS)

Olsen, P.A.

1995-01-01

The purpose of this Technical Work Document is to satisfy HSRCM-1, the ''Hanford Site Radiological Control Manual.'' Article 551.4 of that manual states a requirement for a documented study of facility workplace air sampling programs (WPAS). This first revision of the original Supporting Document covers the period from January 1, 1995 to December 31, 1995. HSRCM-1 is the primary guidance for radiological control at Westinghouse Hanford Company (WHC). It was written to implement DOE/EH-0256T ''US Department of Energy Radiological Control Manual'' as it applies to programs at Hanford. As such, it complies with Title 10, Part 835 of the Code of Federal Regulations. There are also several Department of Energy (DOE) Orders, national consensus standards, and reports that provide criteria, standards, and requirements for workplace air sampling programs. This document provides a summary of these, as they apply to WHC facility workplace air sampling programs. This document also provides an evaluation of the compliance of 300 Areas' workplace air sampling program to the criteria, standards, and requirements and documents compliance with the requirements where appropriate. Where necessary, it also indicates changes needed to bring specific locations into compliance. The areas evaluated were the 340 Facility, the Advanced Reactor Operations Division Facilities, the N Reactor Fuels Supply Facility, and The Geotechnical Engineering Laboratory

Materials and Methods for Streamlined Laboratory Analysis of Environmental Samples, FY 2016 Report

Energy Technology Data Exchange (ETDEWEB)

Addleman, Raymond S. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Naes, Benjamin E. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); McNamara, Bruce K. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Olsen, Khris B. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Chouyyok, Wilaiwan [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Willingham, David G. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Spigner, Angel C. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

2016-11-30

The International Atomic Energy Agency (IAEA) relies upon laboratory analysis of environmental samples (typically referred to as “swipes”) collected during on-site inspections of safeguarded facilities to support the detection and deterrence of undeclared activities. Unfortunately, chemical processing and assay of the samples is slow and expensive. A rapid, effective, and simple extraction process and analysis method is needed to provide certified results with improved timeliness at reduced costs (principally in the form of reduced labor), while maintaining or improving sensitivity and efficacy. To address these safeguard needs the Pacific Northwest National Laboratory (PNNL) explored and demonstrated improved methods for environmental sample (ES) analysis. Improvements for both bulk and particle analysis were explored. To facilitate continuity and adoption, the new sampling materials and processing methods will be compatible with existing IAEA protocols for ES analysis. PNNL collaborated with Oak Ridge National Laboratory (ORNL), which performed independent validation of the new bulk analysis methods and compared performance to traditional IAEA’s Network of Analytical Laboratories (NWAL) protocol. ORNL efforts are reported separately. This report describes PNNL’s FY 2016 progress, which was focused on analytical application supporting environmental monitoring of uranium enrichment plants and nuclear fuel processing. In the future the technology could be applied to other safeguard applications and analytes related to fuel manufacturing, reprocessing, etc. PNNL’s FY 2016 efforts were broken into two tasks and a summary of progress, accomplishments and highlights are provided below. Principal progress and accomplishments on Task 1, Optimize Materials and Methods for ICP-MS Environmental Sample Analysis, are listed below. • Completed initial procedure for rapid uranium extraction from ES swipes based upon carbonate-peroxide chemistry (delivered to ORNL for

Patient Evaluation and Preparation in Vascular and Interventional Radiology: What Every Interventional Radiologist Should Know (Part 1: Patient Assessment and Laboratory Tests)

Energy Technology Data Exchange (ETDEWEB)

Taslakian, Bedros, E-mail: btaslakian@gmail.com [NYU Langone Medical Center, Department of Radiology (United States); Sebaaly, Mikhael Georges, E-mail: ms246@aub.edu.lb; Al-Kutoubi, Aghiad, E-mail: mk00@aub.edu.lb [American University of Beirut Medical Center, Department of Diagnostic Radiology (Lebanon)

2016-03-15

Performing an interventional procedure imposes a commitment on interventional radiologists to conduct the initial patient assessment, determine the best course of therapy, and provide long-term care after the procedure is completed. After patient referral, contact with the referring physician and multidisciplinary team approach is vital. In addition, clinical history, physical examination, as well as full understanding of the pre-procedural laboratory results and imaging findings can guide the interventional radiologist to implement the most appropriate management plan, avoid unnecessary procedures, and prevent complications to achieve a successful outcome. We provide a comprehensive, methodical review of pre-procedural care and management in patients undergoing vascular and interventional radiology procedures.

Patient Evaluation and Preparation in Vascular and Interventional Radiology: What Every Interventional Radiologist Should Know (Part 1: Patient Assessment and Laboratory Tests)

International Nuclear Information System (INIS)

Taslakian, Bedros; Sebaaly, Mikhael Georges; Al-Kutoubi, Aghiad

2016-01-01

Performing an interventional procedure imposes a commitment on interventional radiologists to conduct the initial patient assessment, determine the best course of therapy, and provide long-term care after the procedure is completed. After patient referral, contact with the referring physician and multidisciplinary team approach is vital. In addition, clinical history, physical examination, as well as full understanding of the pre-procedural laboratory results and imaging findings can guide the interventional radiologist to implement the most appropriate management plan, avoid unnecessary procedures, and prevent complications to achieve a successful outcome. We provide a comprehensive, methodical review of pre-procedural care and management in patients undergoing vascular and interventional radiology procedures

Data analysis for radiological characterisation: Geostatistical and statistical complementarity

International Nuclear Information System (INIS)

Desnoyers, Yvon; Dubot, Didier

2012-01-01

Radiological characterisation may cover a large range of evaluation objectives during a decommissioning and dismantling (D and D) project: removal of doubt, delineation of contaminated materials, monitoring of the decontamination work and final survey. At each stage, collecting relevant data to be able to draw the conclusions needed is quite a big challenge. In particular two radiological characterisation stages require an advanced sampling process and data analysis, namely the initial categorization and optimisation of the materials to be removed and the final survey to demonstrate compliance with clearance levels. On the one hand the latter is widely used and well developed in national guides and norms, using random sampling designs and statistical data analysis. On the other hand a more complex evaluation methodology has to be implemented for the initial radiological characterisation, both for sampling design and for data analysis. The geostatistical framework is an efficient way to satisfy the radiological characterisation requirements providing a sound decision-making approach for the decommissioning and dismantling of nuclear premises. The relevance of the geostatistical methodology relies on the presence of a spatial continuity for radiological contamination. Thus geo-statistics provides reliable methods for activity estimation, uncertainty quantification and risk analysis, leading to a sound classification of radiological waste (surfaces and volumes). This way, the radiological characterization of contaminated premises can be divided into three steps. First, the most exhaustive facility analysis provides historical and qualitative information. Then, a systematic (exhaustive or not) surface survey of the contamination is implemented on a regular grid. Finally, in order to assess activity levels and contamination depths, destructive samples are collected at several locations within the premises (based on the surface survey results) and analysed. Combined with

Results of the radiological verification survey of the partial remediation at 90 Avenue C, Lodi, New Jersey (LJ079V)

International Nuclear Information System (INIS)

Foley, R.D.; Johnson, C.A.

1994-02-01

The property at 90 Avenue C, Lodi, New Jersey is one of the vicinity properties of the former Maywood Chemical Works, Maywood, New Jersey designated for remedial action by the US Department of Energy (DOE). In July 1991, Bechtel National, Inc. performed a partial remedial action on this property. At the request of DOE, a team from Oak Ridge National Laboratory conducted an independent radiological verification survey in July, 1991 at this site. The purpose of the verification survey was to ensure the effectiveness of remedial actions performed within FUSRAP and to confirm the site's compliance with DOE guidelines. The radiological survey included surface gamma scans indoors and outdoors, ground-level beta-gamma measurements, and systematic and biased soil and material sampling. Results of the verification survey demonstrated that all radiological measurements on the portions of the property that had been remediated were within DOE guidelines. However, there still remains a portion of the property to be remediated that is not covered by this verification survey

Emergency response exercise of laboratories equipped with gamma spectrometry

Energy Technology Data Exchange (ETDEWEB)

Mala, Helena; Rulik, Petr; Jezkova, Tereza; Beckova, Vera [National Radiation Protection Institute (SURO), 140 00 Praha 28 (Czech Republic)

2014-07-01

At present 7 laboratories equipped with semiconductor gamma spectrometry (HPGe detectors) are included in the Radiation Monitoring Network (RMN) in the Czech Republic. These laboratories have 31 spectrometric chains and approximately 20 'experts' and 70 'users' who would guarantee measurements during a radiological emergency (RE). The stress exercise (a load test) was carried out in 4 of them. The aim was to test their measuring capacity in existing technical facilities and staff in the event of a RE and identify problems (bottlenecks) in the whole process from receipt of samples to entering the results into the central database of RMN. Duration of the exercise was 8 to 14 hours. Due to lack of staff, work in one 12-hour shift during a RE is presumed, which the laboratories should be able to provide for 14 days. Exercise samples covered a wide range of commodities that would probably come to the laboratories during RE (aerosol filters, adsorbed gaseous forms of iodine, fallout, surface and drinking waters, food chain components and soils). Some of the samples were previously spiked with {sup 85}Sr, {sup 88}Y and {sup 40}K (these nuclides represented actual nuclides that would occur in RE); soil samples contained higher values of {sup 137}Cs activity originating from the Chernobyl accident. Almost 40 employees took part in the exercise and measurements were carried out at 18 spectrometric chains. An automatic gamma counter which allows automatic operation of two HPGe detectors including the analysis of the spectra with a storage for up to 180 sample containers was operating in one of the laboratories involved in the exercise. The procedures in individual laboratories varied slightly depending on the staff and laboratory space available. During the exercise about 700 samples were evaluated; in addition, gamma-automat measured other 80 samples in the 'night shift'. 700 samples, this means 40 samples per a spectrometric chain or, from

Use of proficiency samples to assess diagnostic laboratories in France performing a Trichinella digestion assay.

Science.gov (United States)

Vallée, Isabelle; Macé, Pauline; Forbes, Lorry; Scandrett, Brad; Durand, Benoit; Gajadhar, Alvin; Boireau, Pascal

2007-07-01

Routine diagnosis of animal trichinellosis for food safety and trade relies on a method of artificial digestion to free Trichinella muscle larvae from meat for subsequent identification by microscopy. As part of a quality control system, the French National Reference Laboratory (NRL) initiated ring trials to determine the sensitivity of the test performed in the 72 routine diagnostic laboratories in France. A method was devised to obtain calibrated meat samples containing known numbers of capsules with Trichinella spiralis muscle larvae. This method was based on an incomplete artificial digestion of Trichinella-infected mice carcasses to allow the collection of intact Trichinella capsules. Capsules were placed into a meatball of 100 +/- 2 g of pork and horsemeat to produce proficiency samples. Three categories of samples were prepared: small (3 to 5 capsules), medium (7 to 10), and large (12 to 15). The sensitivity was expressed as the percentage of muscle larvae recovered from each proficiency sample. Reproducibility was tested with ring trials organized between two NRLs (France and Canada), and a reference sensitivity of 84.9% was established. National ring trials were then organized in France, with the 72 routine diagnostic laboratories each receiving four proficiency samples per session. After five sessions, an improvement in the digest test sensitivity was observed. Results at the fifth session indicated sensitivities of 78.60% +/- 23.70%, 81.19% +/- 19.59%, and 80.52% +/- 14.71% muscle larvae for small, medium, and large samples, respectively. This study supports the use of proficiency samples to accurately evaluate the performance of routine diagnostic laboratories that conduct digestion tests for animal trichinellosis diagnosis.

Development of an inventory/archive program for the retention, management, and disposition of tank characterization samples at the 222-S laboratory

International Nuclear Information System (INIS)

Seidel, C.M.

1998-01-01

The Hanford Tank Waste Remediation Systems (TWRS) Characterization Program is responsible for coordinating the sampling and analysis of the 177 large underground storage tanks at the Hanford site. The 222-S laboratory has been the primary laboratory for chemical analysis of this highly-radioactive material and has been accumulating these samples for many years. As part of the Fiscal Year 1998 laboratory work scope, the 222-S laboratory has performed a formal physical inventory of all tank characterization samples which are currently being stored. In addition, an updated inventory/archive program has been designed. This program defines sample storage, retention, consolidation, maintenance, and disposition activities which will ensure that the sample integrity is preserved to the greatest practical extent. In addition, the new program provides for continued availability of waste material in a form which will be useful for future bench-scale studies. Finally, when the samples have exceeded their useful lifetime, the program provides for sample disposition from,the laboratory in a controlled, safe and environmentally compliant manner. The 222-S laboratory maintains custody over samples of tank waste material which have been shipped to the laboratory for chemical analysis. The storage of these samples currently requires an entire hotcell, fully dedicated to sample archive storage, and is rapidly encroaching on additional hotcell space. As additional samples are received, they are beginning to limit the 222-S laboratory hotcell utility for other activities such as sample extrusion and subsampling. The 222-S laboratory tracks the number of sample containers and the mass of each sample through an internal database which has recently been verified and updated via a physical inventory

Surface radiological investigations at environmental research area 11, 137Cs- and 60Co-contaminated plots at Oak Ridge National Laboratory, Oak Ridge, Tennessee

International Nuclear Information System (INIS)

Uziel, M.S.; Tiner, P.F.; Williams, J.K.

1993-02-01

A surface radiological investigation at the 137 Cs- and 6O Co-contaminated forest area (Chestnut Ridge east and west plots) was conducted from January 1992 through August 1992. Results of the survey revealed numerous spots and small areas of surface contamination that followed the original placement of feeders used for 6O Co- and 137 Cs-labeled seeds in a 1969--1970 study. Surface gamma exposure rates reached 380 μR/h at the east plot and 400 μR/h at the west plot, but approximately one-half and one- third, respectively, of the identified anomalies did not exceed 39 μR/h. Results of soil sample analyses demonstrated that 137 Cs and 6O Co were responsible for the elevated radiation levels. Radionuclides were found below the surface at soil sample locations, in some cases at depths below 18 in. The same pattern of subsurface contamination may be present at other elevated surface spots at both plots. These survey results show that current radiological conditions at the site remain an environmental problem. Recommendations for corrective actions are included

Surface radiological investigations along State Highway 95, Lagoon Road, and Melton Valley Drive, Oak Ridge Reservation, Oak Ridge, Tennessee

International Nuclear Information System (INIS)

Tiner, P.F.; Uziel, M.S.; Rice, D.E.; Williams, J.K.

1995-08-01

The surface radiological investigation along State Highway 95, Lagoon Road, and Melton Valley Drive at the Oak Ridge Reservation was conducted as part of the Oak Ridge National Laboratory Environmental Restoration Program Surveillance and Maintenance activities. This report was prepared to document results of the investigation and subsequent remedial actions. The report details surface gamma radiation levels including gamma anomalies; surface beta radiation levels including beta anomalies; results of analysis of soil, water, and vegetation samples and smear samples collected from paved surfaces; remediation activities conducted as a result of the survey; and recommendations for further corrective measures

Los Alamos National Laboratory TRU waste sampling projects

International Nuclear Information System (INIS)

Yeamans, D.; Rogers, P.; Mroz, E.

1997-01-01

The Los Alamos National Laboratory (LANL) has begun characterizing transuranic (TRU) waste in order to comply with New Mexico regulations, and to prepare the waste for shipment and disposal at the Waste Isolation Pilot Plant (WIPP), near Carlsbad, New Mexico. Sampling consists of removing some head space gas from each drum, removing a core from a few drums of each homogeneous waste stream, and visually characterizing a few drums from each heterogeneous waste stream. The gases are analyzed by GC/MS, and the cores are analyzed for VOC's and SVOC's by GC/MS and for metals by AA or AE spectroscopy. The sampling and examination projects are conducted in accordance with the ''DOE TRU Waste Quality Assurance Program Plan'' (QAPP) and the ''LANL TRU Waste Quality Assurance Project Plan,'' (QAPjP), guaranteeing that the data meet the needs of both the Carlsbad Area Office (CAO) of DOE and the ''WIPP Waste Acceptance Criteria, Rev. 5,'' (WAC)

Hospital management of mass radiological casualties: reassessing exposures from contaminated victims of an exploded radiological dispersal device (RDD)

International Nuclear Information System (INIS)

Ansari, Armin; Harper, Frederick Taylor; Smith, James M.

2005-01-01

One of the key issues in the aftermath of an exploded radiological dispersal device from a terrorist event is that of the contaminated victim and the concern among healthcare providers for the harmful exposures they may receive in treating patients, especially if the patient has not been thoroughly decontaminated. This is critically important in the event of mass casualties from a nuclear or radiological incident because of the essential rapidity of acute medical decisions and that those who have life- or limb-threatening injuries may have treatment unduly delayed by a decontamination process that may be unnecessary for protecting the health and safety of the patient or the healthcare provider. To estimate potential contamination of those exposed in a radiological dispersal device event, results were used from explosive aerosolization tests of surrogate radionuclides detonated with high explosives at the Sandia National Laboratories. Computer modeling was also used to assess radiation dose rates to surgical personnel treating patients with blast injuries who are contaminated with any of a variety of common radionuclides. It is demonstrated that exceptional but plausible cases may require special precautions by the healthcare provider, even while managing life-threatening injuries of a contaminated victim from a radiological dispersal device event.

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

International Nuclear Information System (INIS)

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

2004-01-01

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

The LLNL Multiuser Tandem Laboratory computer-controlled radiation monitoring system

International Nuclear Information System (INIS)

Homann, S.G.

1992-01-01

The Physics Department of the Lawrence Livermore National Laboratory (LLNL) recently constructed a Multiuser Tandem Laboratory (MTL) to perform a variety of basic and applied measurement programs. The laboratory and its research equipment were constructed with support from a consortium of LLNL Divisions, Sandia National Laboratories Livermore, and the University of California. Primary design goals for the facility were inexpensive construction and operation, high beam quality at a large number of experimental stations, and versatility in adapting to new experimental needs. To accomplish these goals, our main design decisions were to place the accelerator in an unshielded structure, to make use of reconfigured cyclotrons as effective switching magnets, and to rely on computer control systems for both radiological protection and highly reproducible and well-characterized accelerator operation. This paper addresses the radiological control computer system

1995 Site environmental report Sandia National Laboratories, Albuquerque, New Mexico

Energy Technology Data Exchange (ETDEWEB)

Shyr, L.J.; Duncan, D. [eds.; Sanchez, R.

1996-09-01

This 1995 report contains data from routine radiological and non-radiological environmental monitoring activities. Summaries of significant environmental compliance programs in progress, such as National Environmental Policy Act documentation, environmental permits, environmental restoration and various waste management programs at Sandia National Laboratories in Albuquerque, New Mexico, are included.

1995 Site environmental report Sandia National Laboratories, Albuquerque, New Mexico

International Nuclear Information System (INIS)

Shyr, L.J.; Duncan, D.; Sanchez, R.

1996-09-01

This 1995 report contains data from routine radiological and non-radiological environmental monitoring activities. Summaries of significant environmental compliance programs in progress, such as National Environmental Policy Act documentation, environmental permits, environmental restoration and various waste management programs at Sandia National Laboratories in Albuquerque, New Mexico, are included

Identification of Forensic Samples via Mitochondrial DNA in the Undergraduate Biochemistry Laboratory

Science.gov (United States)

Millard, Julie T.; Pilon, André M.

2003-04-01

A recent forensic approach for identification of unknown biological samples is mitochondrial DNA (mtDNA) sequencing. We describe a laboratory exercise suitable for an undergraduate biochemistry course in which the polymerase chain reaction is used to amplify a 440 base pair hypervariable region of human mtDNA from a variety of "crime scene" samples (e.g., teeth, hair, nails, cigarettes, envelope flaps, toothbrushes, and chewing gum). Amplification is verified via agarose gel electrophoresis and then samples are subjected to cycle sequencing. Sequence alignments are made via the program CLUSTAL W, allowing students to compare samples and solve the "crime."

Clinical and radiological aspects of limited forms of infiltrative pulmonary tuberculosis and slowly resolving pneumonia

International Nuclear Information System (INIS)

Caraiani, Olga; Lesnic, Evelina; Niguleanu, Adriana; Niguleanu, Radu

2016-01-01

Despite of a clearly defined diagnostic algorithm of pulmonary tuberculosis, low sensibility of contemporary laboratory methods in limited forms of pulmonary tuberculosis contributes to a difficult differential diagnosis with community acquired pneumonia, especially with slowly resolving pneumonia. A case-control, prospective, selective, comparative and descriptive study was performed using a group of 180 patients, divided into two samples: I group - 125 cases with limited form of pulmonary infiltrative tuberculosis; II group - 55 cases with slowly resolving community-acquired pneumonia. The findings identified the prevalence of intoxication syndrome in the slowly resolving pneumonia sample. Lung destructions and bronchogenous dissemination was identified only in the tuberculosis sample. A higher impact of comorbidities and old age was more relevant in slowly resolving pneumonia sample. Clinical and radiological improvement was established in most patients of both groups, but the considerable resorption of lung infiltrates predominated in slowly resolving pneumonia sample. (authors)

Analysis of radioactive contaminations and radiological hazard in Poland after the Chernobyl reactor accident

International Nuclear Information System (INIS)

Zarnowiecki, K.

1988-01-01

It is a report on radiological impact in Poland following the Chernobyl reactor accident prepared in the Central Laboratory for Radiological Protection. The results of measurement and its analysis are presented. Isotopic composition of the contamined air and the concentration of radionuclides are determined. The trajectories of the airborne radioactive material movement from Chernobyl to Poland at the last days of April 1986 are presented. Assessment of the radiological risk of the population is done. 38 refs., 20 figs., 11 tabs. (M.F.W.)

Radiological Worker Training: Radiological Worker 2 study guides

International Nuclear Information System (INIS)

1992-10-01

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

Radiological Society of North America

Science.gov (United States)

... RSNA Permissions Librarian Guide Subscriptions & Licensing Free Samples & Online Trial Radiology Legacy Collection Services Promote Your Offerings Manage Your Account Contact Us Agency Guide Pricing Commision Rates Customer Service Contact Us Advertising Editorial Fellowships Policies FAQs ...

Radiological dose assessments in the northern Marshall Islands (1989--1991)

International Nuclear Information System (INIS)

Sun, L.C.; Meinhold, C.B.; Moorthy, A.R.; Clinton, J.H.; Kaplan, E.

1991-11-01

The Republic of the Marshall Islands (RMI) is located in the central Pacific Ocean about 3500 km southwest of Hawaii and 4500 km east of Manila, Philippines. It consists of 34 atolls and 2 coral islands, having a total land area of about 180 km 2 , distributed over more than 2.5 x 10 6 of ocean. Between 1946 and 1958 the United states conducted nuclear tests there: 43 at Enewetak and 23 at Bikini. Thirty-three years after the cessation of nuclear testing in the RMI, the impact of these operations on the health and radiological safety of the people living in or planning to return to their contaminated homelands is still an important concern. The present Brookhaven National Laboratory (BNL) Marshall Islands Radiological Safety Program (MIRSP) began in 1987 with funding from the US Department of Energy (DOE). The objectives of the MIRSP are to determine the radionuclides present in the bodies of those people potentially exposed to residual radionuclide from weapon tests and fallout, and to assess their present and lifetime dose from external and internal sources. Field bioassay missions involving whole-body counting (WBC) and urine sample collection have, therefore, been important components of the program. WBC is used to measure γ-emitters, such as 40 K, 60 Co and 137 Cs, present in individuals. Urine samples are used to measure α and β-emitting nuclides such as 239 Pu and 90 Sr, that are undetectable by WBC routine methods

Recommended radiological air sampling and internal contamination control at nuclear power plants

International Nuclear Information System (INIS)

Rich, B.L.; Ritter, P.D.; Martz, D.E.

1984-01-01

It has long been recognized by the NRC Technical Staffs that estimating the quantity of radioactivity inhaled by an individual worker involved large uncertainties. General air samples usually produce concentrations lower than those in the workers Breathing Zone (BZ). NRC guides have recognized this problem by specifying air monitoring programs which sample the Breathing Zone or concentrations known to be higher than that actually inhaled. In addition the availability of suitable samplers to obtain BZ samples and the practicality of requiring their use was somewhat in question to the NRC technical staff. AN NRC development contract was issued to provide a detailed review of the technical aspects of the problems and recommendations for practical upgrade of federal guidance. This project accomplished a review of the nuclear industry experience and knowledge through a literature search, site visits to representative licensed facilities, telephone surveys of many others, laboratory testing of personal air samplers (lapel samplers) and aerosol diffusion experiments to verify key conclusions and assumptions

Radiological assessment of dam water and sediments for natural ...

African Journals Online (AJOL)

Radiological assessment of dam water and sediments for natural radioactivity and its overall health detriments. ... No artificial gamma emitting radionuclide was detected in the samples. The projected ... However, the chances of radiological hazard to the health of human from radioactivity in the soil were generally low.

Radiological clerkships as a critical curriculum component in radiology education

International Nuclear Information System (INIS)

Kourdioukova, Elena V.; Verstraete, Koenraad L.; Valcke, Martin

2011-01-01

Objective: The aim of this research was to explore the perceived value of clinical clerkships in the radiology curriculum as well as the impact of radiology clerkship on students' beliefs about the profession of radiology as a whole and as a career. Methods: This study is a sequel to a previous survey in which student perceptions about radiology curriculum components were investigated. The present study focuses on a further analysis of a subsection in this study, based on 14 statements about radiology clerkship and two statements about radiology as a career. Results: Perceived usefulness of the aspects of radiology clerkship as 'radiology examination', 'skills development' and 'diagnosis focus' were awarded the highest scores. The predict value of the subscale 'radiology examination' on the level of performance was very high (adjusted R 2 = 0.19, p < .001). Conclusion: Students expressed highly favorable evaluation of clerkship as a learning environment to learn to order and to interpret imaging studies as well as an unique possibility to attend various radiological examinations and to access to specific radiology software systems, as well as to get a better view on radiology and to improve image interpretation skills. This positive attitude towards clerkship is closely tied to students' beliefs about the profession of radiology as a whole. These aspects of dedicated radiology clerkship are crucial for effective and high-quality education as well as for the choice of radiology as a career.

Diagnostic radiology 1987

International Nuclear Information System (INIS)

Margulis, A.R.; Gooding, C.A.

1987-01-01

This is the latest version of the continuing education course on diagnostic radiology given yearly by the Department of Radiology at the University of California, San Francisco. The lectures are grouped into sections on gastrointestinal radiology, mammography, uroradiology, magnetic resonance, hepatobiliary radiology, pediatric radiology, ultrasound, interventional radiology, chest radiology, nuclear medicine, cardiovascular radiology, and skeletal radiology. Each section contains four to eight topics. Each of these consists of text that represents highlights in narrative form, selected illustrations, and a short bibliography. The presentation gives a general idea of what points were made in the lecture

Radiation and Health Technology Laboratory Capabilities

Energy Technology Data Exchange (ETDEWEB)

Goles, Ronald W.; Johnson, Michelle Lynn; Piper, Roman K.; Peters, Jerry D.; Murphy, Mark K.; Mercado, Mike S.; Bihl, Donald E.; Lynch, Timothy P.

2003-07-15

The Radiological Standards and Calibrations Laboratory, a part of Pacific Northwest National Laboratory (PNNL)(a) performs calibrations and upholds reference standards necessary to maintain traceability to national standards. The facility supports U.S. Department of Energy (DOE) programs at the Hanford Site, programs sponsored by DOE Headquarters and other federal agencies, radiological protection programs at other DOE and commercial nuclear sites and research and characterization programs sponsored through the commercial sector. The laboratory is located in the 318 Building of the Hanford Site's 300 Area. The facility contains five major exposure rooms and several laboratories used for exposure work preparation, low-activity instrument calibrations, instrument performance evaluations, instrument maintenance, instrument design and fabrication work, thermoluminescent and radiochromic Dosimetry, and calibration of measurement and test equipment (M&TE). The major exposure facilities are a low-scatter room used for neutron and photon exposures, a source well room used for high-volume instrument calibration work, an x-ray facility used for energy response studies, a high-exposure facility used for high-rate photon calibration work, a beta standards laboratory used for beta energy response studies and beta reference calibrations and M&TE laboratories. Calibrations are routinely performed for personnel dosimeters, health physics instrumentation, photon and neutron transfer standards alpha, beta, and gamma field sources used throughout the Hanford Site, and a wide variety of M&TE. This report describes the standards and calibrations laboratory.

Expressing analytical performance from multi-sample evaluation in laboratory EQA.

Science.gov (United States)

Thelen, Marc H M; Jansen, Rob T P; Weykamp, Cas W; Steigstra, Herman; Meijer, Ron; Cobbaert, Christa M

2017-08-28

To provide its participants with an external quality assessment system (EQAS) that can be used to check trueness, the Dutch EQAS organizer, Organization for Quality Assessment of Laboratory Diagnostics (SKML), has innovated its general chemistry scheme over the last decade by introducing fresh frozen commutable samples whose values were assigned by Joint Committee for Traceability in Laboratory Medicine (JCTLM)-listed reference laboratories using reference methods where possible. Here we present some important innovations in our feedback reports that allow participants to judge whether their trueness and imprecision meet predefined analytical performance specifications. Sigma metrics are used to calculate performance indicators named 'sigma values'. Tolerance intervals are based on both Total Error allowable (TEa) according to biological variation data and state of the art (SA) in line with the European Federation of Clinical Chemistry and Laboratory Medicine (EFLM) Milan consensus. The existing SKML feedback reports that express trueness as the agreement between the regression line through the results of the last 12 months and the values obtained from reference laboratories and calculate imprecision from the residuals of the regression line are now enriched with sigma values calculated from the degree to which the combination of trueness and imprecision are within tolerance limits. The information and its conclusion to a simple two-point scoring system are also graphically represented in addition to the existing difference plot. By adding sigma metrics-based performance evaluation in relation to both TEa and SA tolerance intervals to its EQAS schemes, SKML provides its participants with a powerful and actionable check on accuracy.

Formerly utilized MED/AEC sites remedial action program. Radiological survey of the West Stands, New Chemistry Lab and Annex, and Ricketts Laboratory, the University of Chicago, Chicago, Illinois, August 31-September 2, 1977

International Nuclear Information System (INIS)

Wynveen, R.A.; Smith, W.H.; Mayes, C.B.; Justus, A.L.

1982-05-01

A radiological survey was conducted at the former locations of the West Stands, the New Chemistry Lab and Annex, and Ricketts Laboratory at the University of Chicago, Chicago, Illinois. General radiochemistry and/or physics research for the MED/AEC program was performed at these sites during the 1940s. The buildings have since been razed. The survey was undertaken to determine the presence of any radionuclides remaining from the MED/AEC operations that could have been spilled or released from the former structures. Environmental soil samples (corings) were collected from the areas where the West Stands, New Chemistry Lab and Annex, and Ricketts Laboratory once stood. The soil corings were taken at what appeared to be undisturbed locations near the sites of the three former facilities. Analyses of the soil corings included determination of the concentrations of 137 Cs, the 232 Th decay chain, the 226 Ra decay chain, and uranium in the soil. The levels of uranium and the 226 Ra decay chain found in the samples indicated that no concentrations above natural background levels were present. Slightly elevated levels of 60 Co were found in soil taken from the top 5 cm of the ground at two sampling sites, but this activity was presumed to have been traceable to induced activity from contaminated stainless steel that had been stored in the area during operations not related to MED/AEC activities. No increased radiation dose attributable to exposure to residual radioactivity from MED/AEC activities is expected

Evaluation of NAA laboratory results in inter-comparison on determination of trace elements in food and environmental samples

International Nuclear Information System (INIS)

Diah Dwiana Lestiani; Syukria Kurniawati; Natalia Adventini

2012-01-01

Inter-comparison program is a good tool for improving quality and to enhance the accuracy and precision of the analytical techniques. By participating in this program, laboratories could demonstrate their capability and ensuring the quality of analysis results generated by analytical laboratories. The Neutron Activation Analysis (NAA) laboratory at National Nuclear Energy Agency of Indonesia (BATAN), Nuclear Technology Center for Materials and Radiometry-PTNBR laboratory participated in inter-comparison tests organized by NAA working group. Inter-comparison BATAN 2009 was the third inter-laboratory analysis test within that project. The participating laboratories were asked to analyze for trace elements using neutron activation analysis as the primary technique. Three materials were distributed to the participants representing foodstuff, and environmental material samples. Samples were irradiated in rabbit facility of G.A. Siwabessy reactor with neutron flux ~ 10 13 n.cm -2 .s -1 , and counted with HPGe detector of gamma spectrometry. Several trace elements in these samples were detected. The accuracy and precision evaluation based on International Atomic Energy Agency (IAEA) criteria was applied. In this paper the PTNBR NAA laboratory results is evaluated. (author)

Planning and preparedness for radiological emergencies at nuclear power stations

International Nuclear Information System (INIS)

Thomson, R.; Muzzarelli, J.

1996-01-01

The Radiological Emergency Preparedness (REP) Program was created after the March 1979 accident at the Three Mile Island nuclear power station. The Federal Emergency Management Agency (FEMA) assists state and local governments in reviewing and evaluating state and local REP plans and preparedness for accidents at nuclear power plants, in partnership with the US Nuclear Regulatory Commission (NRC), which evaluates safety and emergency preparedness at the power stations themselves. Argonne National Laboratory provides support and technical assistance to FEMA in evaluating nuclear power plant emergency response exercises, radiological emergency plans, and preparedness

The radiological research accelerator facility. Progress report, December 1, 1995--November 30, 1996

International Nuclear Information System (INIS)

Hall, E.J.; Marino, S.A.

1996-08-01

The Radiological Research Accelerator Facility (RARAF) is based on a 4-MV Van de Graaff accelerator, which is used to generate a variety of well-characterized radiation beams for research in radiobiology, radiological physics, and radiation chemistry. It is part of the Center for Radiological Research (CRR) - formerly the Radiological Research Laboratory (RRL) - of Columbia University, and its operation is supported as a National Facility by the U.S. Department of Energy (DOE). As such, RARAF is available to all potential users on an equal basis and scientists outside the CRR are encouraged to submit proposals for experiments at RARAF. The operation of the Van de Graaff is supported by the DOE, but the research projects themselves must be supported separately. RARAF was conceived in the mid-1960s by Drs. Victor P. Bond of Brookhaven National Laboratory (BNL) and Harald H. Rossi of Columbia University as a research resource dedicated to radiobiology and radiological physics and was officially established on January 1, 1967. The RARAF Van de Graaff accelerator originally served as the injector for the Cosmotron, a 2-GeV accelerator operated at BNL in the 1950s and early 1960s. The immediate aim was to provide a source of monoenergetic neutrons for studies in radiation biology, dosimetry, and microdosimetry. In other major projects the energetic ions produced were utilized directly. RARAF was located at BNL from 1967 until 1980, when it was dismantled and moved to the Nevis Laboratories of Columbia University, where it was then reassembled and returned to operation. This report contains the following information on RARAF: RARAF user's guide; scientific advisory committee; research using RARAF; accelerator utilization and operation; and development of the facilities

Radiological, physical, and chemical characterization of low-level alpha contaminated wastes stored at the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

Apel, M.L.; Becker, G.K.; Ragan, Z.K.; Frasure, J.; Raivo, B.D.; Gale, L.G.; Pace, D.P.

1994-03-01

This document provides radiological, physical, and chemical characterization data for low-level alpha-contaminated radioactive and low-level alpha-contaminated radioactive and hazardous (i.e., mixed) wastes stored at the Idaho National Engineering Laboratory and considered for treatment under the Private Sector Participation Initiative Program. Waste characterization data are provided in the form of INEL Waste Profile Sheets. These documents provide, for each content code, information on waste identification, waste description, waste storage configuration, physical/chemical waste composition, radionuclide and associated alpha activity waste characterization data, and hazardous constituents present in the waste. Information is provided for 97 waste streams which represent an estimated total volume of 25,450 m 3 corresponding to a total mass of approximately 12,000,000 kg. In addition, considerable information concerning alpha, beta, gamma, and neutron source term data specific to Rocky Flats-generated waste forms stored at the INEL are provided to assist in facility design specification

Radiological, physical, and chemical characterization of low-level alpha contaminated wastes stored at the Idaho National Engineering Laboratory

Energy Technology Data Exchange (ETDEWEB)

Apel, M.L.; Becker, G.K.; Ragan, Z.K.; Frasure, J.; Raivo, B.D.; Gale, L.G.; Pace, D.P.

1994-03-01

This document provides radiological, physical, and chemical characterization data for low-level alpha-contaminated radioactive and low-level alpha-contaminated radioactive and hazardous (i.e., mixed) wastes stored at the Idaho National Engineering Laboratory and considered for treatment under the Private Sector Participation Initiative Program. Waste characterization data are provided in the form of INEL Waste Profile Sheets. These documents provide, for each content code, information on waste identification, waste description, waste storage configuration, physical/chemical waste composition, radionuclide and associated alpha activity waste characterization data, and hazardous constituents present in the waste. Information is provided for 97 waste streams which represent an estimated total volume of 25,450 m 3 corresponding to a total mass of approximately 12,000,000 kg. In addition, considerable information concerning alpha, beta, gamma, and neutron source term data specific to Rocky Flats-generated waste forms stored at the INEL are provided to assist in facility design specification.

Decision Tree and Survey Development for Support in Agricultural Sampling Strategies during Nuclear and Radiological Emergencies

International Nuclear Information System (INIS)

Yi, Amelia Lee Zhi; Dercon, Gerd

2017-01-01

In the event of a severe nuclear or radiological accident, the release of radionuclides results in contamination of land surfaces affecting agricultural and food resources. Speedy accumulation of information and guidance on decision making is essential in enhancing the ability of stakeholders to strategize for immediate countermeasure strategies. Support tools such as decision trees and sampling protocols allow for swift response by governmental bodies and assist in proper management of the situation. While such tools exist, they focus mainly on protecting public well-being and not food safety management strategies. Consideration of the latter is necessary as it has long-term implications especially to agriculturally dependent Member States. However, it is a research gap that remains to be filled.

Handbook of laboratory techniques; Manual de tecnicas de laboratorio

Energy Technology Data Exchange (ETDEWEB)

NONE

2002-07-01

The Nuclear Regulatory Authority in Argentina have laboratories of support to regulations functions on radiological and nuclear safety, safeguards and physical protection, that have a surface of 2950 m{sup 2} in the Ezeiza Atomic Center. The manual describes in seven chapters the different techniques developed and applied in the laboratories along four decades of existence. The chapter 1: Dedicated to the treatment of environmental samples, described the procedures associated with the different types of samples: deposits, waters, sediments, vegetables, milk, fish and diet. The chapter 2: Details 48 radiochemical techniques associated to the measurements of americium 241, carbon 16, strontium 90, iodine 129, plutonium, radium 226, radon, uranium, nickel and actinides. The chapter 3: Describes the measurements techniques of alpha and gamma spectrometry. The different techniques of biological and physical dosimetry are described in the chapters 5 and 6 respectively. The final chapter is dedicated the techniques of external and internal contamination. It s important to emphasize that this manual contains the standardized technologies that the Nuclear Regulatory Authority of Argentina submits regularly to international comparisons.

AERIAL RADIOLOGICAL SURVEYS

International Nuclear Information System (INIS)

Proctor, A.E.

1997-01-01

Measuring terrestrial gamma radiation from airborne platforms has proved to be a useful method for characterizing radiation levels over large areas. Over 300 aerial radiological surveys have been carried out over the past 25 years including U.S. Department of Energy (DOE) sites, commercial nuclear power plants, Formerly Utilized Sites Remedial Action Program/Uranium Mine Tailing Remedial Action Program (FUSRAP/UMTRAP) sites, nuclear weapons test sites, contaminated industrial areas, and nuclear accident sites. This paper describes the aerial measurement technology currently in use by the Remote Sensing Laboratory (RSL) for routine environmental surveys and emergency response activities. Equipment, data-collection and -analysis methods, and examples of survey results are described

The Northern Marshall Islands radiological survey: A quality control program for radiochemical and gamma spectroscopy analysis

International Nuclear Information System (INIS)

Kehl, S.R.; Mount, M.E.; Robison, W.L.

1995-09-01

From 1979 to 1989, approximately 25,000 Post Northern Marshall Islands Radiological Survey (PNMIRS) samples were collected, and over 71,400 radiochemical and gamma spectroscopy analyses were performed to establish the concentration of 90 Sr, 137 Cs, 241 Am, and plutonium isotopes in soil, vegetation, fish, and animals in the Northern Marshall Islands. While the Low Level Gamma Counting Facility (B379) in the Health and Ecological Assessment (HEA) division accounted for over 80% of all gamma spectroscopy analyses, approximately 4889 radiochemical and 5437 gamma spectroscopy analyses were performed on 4784 samples of soil, vegetation, terrestrial animal, and marine organisms by outside laboratories. Four laboratories were used by Lawrence Livermore National Laboratory (LLNL) to perform the radiochemical analyses: Thermo Analytical Norcal, Richmond, California (TMA); Nuclear Energy Services, North Carolina State University (NCSU); Laboratory of Radiation Ecology, University of Washington (LRE); and Health and Ecological Assessment (HEA) division, LLNL, Livermore, California. Additionally, LRE and NCSU were used to perform gamma spectroscopy analyses. The analytical precision and accuracy were monitored by including blind duplicates and natural matrix standards in each group of samples analyzed. On the basis of reported analytical values for duplicates and standards, 88% of the gamma and 87% of the radiochemical analyses in this survey were accepted. By laboratory, 93% of the radiochemical analyses by TMA; 88% of the gamma-ray spectrometry and 100% of the radiochemistry analyses by NCSU; 89% of the gamma spectroscopy and 87% of the radiochemistry analyses by LRE; and 90% of the radiochemistry analyses performed by HEA's radiochemistry department were accepted

Radiology fundamentals

CERN Document Server

Singh, Harjit

2011-01-01

""Radiology Fundamentals"" is a concise introduction to the dynamic field of radiology for medical students, non-radiology house staff, physician assistants, nurse practitioners, radiology assistants, and other allied health professionals. The goal of the book is to provide readers with general examples and brief discussions of basic radiographic principles and to serve as a curriculum guide, supplementing a radiology education and providing a solid foundation for further learning. Introductory chapters provide readers with the fundamental scientific concepts underlying the medical use of imag

Study of the performance of diagnostic radiology instruments during calibration

International Nuclear Information System (INIS)

Freitas, Rodrigo N. de; Vivolo, Vitor; Potiens, Maria da Penha A.

2008-01-01

Full text: The instruments used in diagnostic radiology measurements represent 8 % of the tested instruments by the calibration laboratory of IPEN annually (approximately 1600 in 2007). Considering that the calibration of this kind of instrument is performed biannually it is possible to conclude that almost 300 instruments are being used to measure the air kerma in diagnostic radiology clinics to determine the in beam values (in front of the patient), attenuated measurements (behind the patient) and scattered radiation. This work presents the results of the calibration of the instruments used in mammography, computed tomography, dental and conventional diagnostic radiology dosimetry, performed during the period of 2005 to 2007. Their performances during the calibrations measurements were evaluated. Although at the calibration laboratory there are three available series of radiation quality to this type of calibration (RQR, N and M, according to standards IEC 61267 and ISO 4037-1.), the applications can be assorted (general radiology, computed tomography, mammography, radiation protection and fluoroscopy). Depending on its design and behaviour , one kind of instrument can be used for one or more type of applications. The instruments normally used for diagnostic radiology measurements are ionization chambers with volumes varying from 3 to 1800 cm 3 , and can be cylindrical, spherical or plane parallel plates kind. They usually are sensitive to photon particles, with energies greater than 15 keV and can be used up to 1200 keV. In this work they were tested in X radiation fields from 25 to 150 kV, in specific qualities depending on the utilization of the instrument. The calibration results of 390 instruments received from 2005 to 2007 were analyzed. About 20 instruments were not able to be calibrated due to bad functioning. The calibration coefficients obtained were between 0.88 and 1.24. The uncertainties were always less than ± 3.6% to instruments used in scattered

Radiologic findings of dwarfism

International Nuclear Information System (INIS)

Hwang, M. S.; Oh, K. K.; Park, C. Y.; Kim, D. H.; Kim, D. H.

1981-01-01

The stature of human is very important factor in human-being, especially in childhood. The stature depends on various different conditions, such as familial factor, constitutional factor, chromosomal anomalies, skeletal disorders, or endocrinopathies. The early diagnosis of dwarfism is very important problem, because if appropriate treatment is delayed, the complication or sequales are more increased. The survey of familial history or patient's past history, detail check up of physical examination, radiological evaluation, and other laboratory examinations are essentially needed for the accurate diagnosis of dwarfism. Among the patients admitted to Yonsei University college of Medicine, Severance Hospital since 1963, with chief complaint of short stature or other associated diseases, an analysis of radiological findings were made for the 72 cases of chromosomal anomalies, skeletal dysplasia, and cretinism in which radiologic evaluation was available. The conclusions are as follows; 1. The cause of short stature are chromosomal anomalies (48 cases), skeletal dysplasia (14 cases) and cretinism (10 cases). 2. in chromosomal anomalies, 43 cases of mongolism and 5 cease of Turner's syndrome are noted. In mongolism, 18 cases among the 30 cases below 1 year old are distributed below the 10 percentile of height. On radiologic findings, 11 paired ribs (22/43), congenital heart disease (14/43), decreased iliac index (8/12), and associated anomalies or diseases, such as pneumonia (14 cases), C1-C2 dislocation (1 case), imperforated anus (1 case), Morgagni's hernia (1 case) and leukemia with sepsis (1 case). In Turner's syndrome, decreased bone density (5/5), positive metacarpal sign (2/5), positive carpal sign (1/5), change of knee joint (3/5), hypoplasia of (1/3), and increased carrying angle of elbows (1/3) are noted

Radiologic findings of dwarfism

Energy Technology Data Exchange (ETDEWEB)

Hwang, M. S.; Oh, K. K.; Park, C. Y.; Kim, D. H. [Yonsei University, College of Medicine, Seoul (Korea, Republic of); Kim, D. H. [Yonsei Univ., Seoul (Korea, Republic of)

1981-06-15

The stature of human is very important factor in human-being, especially in childhood. The stature depends on various different conditions, such as familial factor, constitutional factor, chromosomal anomalies, skeletal disorders, or endocrinopathies. The early diagnosis of dwarfism is very important problem, because if appropriate treatment is delayed, the complication or sequales are more increased. The survey of familial history or patient's past history, detail check up of physical examination, radiological evaluation, and other laboratory examinations are essentially needed for the accurate diagnosis of dwarfism. Among the patients admitted to Yonsei University college of Medicine, Severance Hospital since 1963, with chief complaint of short stature or other associated diseases, an analysis of radiological findings were made for the 72 cases of chromosomal anomalies, skeletal dysplasia, and cretinism in which radiologic evaluation was available. The conclusions are as follows; 1. The cause of short stature are chromosomal anomalies (48 cases), skeletal dysplasia (14 cases) and cretinism (10 cases). 2. in chromosomal anomalies, 43 cases of mongolism and 5 cease of Turner's syndrome are noted. In mongolism, 18 cases among the 30 cases below 1 year old are distributed below the 10 percentile of height. On radiologic findings, 11 paired ribs (22/43), congenital heart disease (14/43), decreased iliac index (8/12), and associated anomalies or diseases, such as pneumonia (14 cases), C1-C2 dislocation (1 case), imperforated anus (1 case), Morgagni's hernia (1 case) and leukemia with sepsis (1 case). In Turner's syndrome, decreased bone density (5/5), positive metacarpal sign (2/5), positive carpal sign (1/5), change of knee joint (3/5), hypoplasia of (1/3), and increased carrying angle of elbows (1/3) are noted.

Performance of the Brazilian laboratories on radionuclide analysis in environmental samples

International Nuclear Information System (INIS)

Vianna, Maria Elizabeth; Tauhata, Luiz; Oliveira, Josue P.; Oliveira, Antonio E.; Clain, Almir F.; Garcia, Luiz Carlos; Conceicao, Cirilo C. da

1995-01-01

The performance of fifteen Brazilian environmental radioanalytical laboratories was evaluated after their participation in nine intercomparison runs of the National Intercomparison Program, PNI, offered by the Instituto de Radioprotecao e Dosimetria, CNEN. A total of 549 radionuclide determinations in environmental samples were evaluated. The results classified as Good ranged from 56.4% for Alpha and Beta Gross determinations up to 84.9% for Gamma spectrometry determinations. These results shows that the best performance in radionuclide determination is reached in gamma spectrometry analyses and the worst in Alpha and Beta Gross determinations. This general behavior is similar to the one reached by other laboratories in international intercomparison programs. (author). 1 ref., 1 fig., 1 tab

Results of the radiological and beryllium verification survey at the Peek Street Site, Schenectady, New York (SY001V)

International Nuclear Information System (INIS)

Foley, R.D.; Johnson, C.A.; Carrier, R.F.; Allred, J.F.

1994-10-01

At the request of the U.S. Department of Energy (DOE), a team from Oak Ridge National Laboratory conducted an independent verification radiological and non-radioactive beryllium survey at the Peek Street site, located at 425 Peek Street, Schenectady, New York. The purpose of the survey, conducted during 1993 and continuing through January 1994, was to confirm the success of the remedial actions performed to remove any beryllium concentrations or radioactive materials in excess of the identified guidelines. The verification survey included surface gamma scans and gamma readings at one meter indoors and outdoors, alpha and beta scans inside the structure, and the collection of soil, dust and debris samples and smears for radionuclide and beryllium analyses. Results of the survey demonstrated that all radiological and beryllium measurements on the property were within applicable DOE guidelines. Based on all data collected, the industrial property at 425 Peek Street and the adjacent state-owned bike path in Schenectady, New York, conforms to all applicable radiological and non-radioactive beryllium guidelines established for this site by DOE and approved by the State of New York

[Psychoactive substances in biological samples--toxicological laboratory data].

Science.gov (United States)

Gomółka, Ewa; Wilimowska, Jolanta; Piekoszewski, Wojciech; Groszek, Barbara

2004-01-01

The subject of the research was the analysis of frequency and type of psychoactive substances used, basing on the determinations the blood and/or urine samples, performed in the toxicological laboratory of the Department of Clinical and Industrial Toxicology Jagiellonian University in Kraków in the period from December 2001 to November 2003. From 17,649 performed determinations--45.5% were positive. 50% of the positive determinations were psychoactive substances. The most often psychoactive substance determined was ethyl alcohol (52.86%), next benzodiazepines (17.41%), amphetamines (10.54%), opiates (8.05%), THC (6.87%), barbiturates (3.74%), and occasionally atropine and cocaine. There was observed a variety of mixed, simultaneously taking psychoactive substances, especially ethyl alcohol, opiates, amphetamine derivatives and cannabinoids. The analysis of the occurrence of psychoactive substances in biological samples from patients treated in different hospital departments, others hospitals and ordered by private persons also was performed. In the last two years 369 private patients ordered psychoactive substances determinations and 78 of them were positive.

Radiologic findings of neonatal sepsis

International Nuclear Information System (INIS)

Kim, Sam Soo; Han, Dae Hee; Choi, Guk Myeong; Jung, Hye Won; Yoon, Hye Kyung; Han, Bokyung Kim; Lee, Nam Yong

1997-01-01

To review the simple radiographic and sonographic findings in infants with neonatal sepsis. We retrospectively analyzed simple chest and abdominal radiographs, and brain sonograms in 36 newborn infants (preterm : term=23 :13). With neonatal sepsis diagnosed by blood culture and clinical manifestations. Pulmonary parenchymal infiltrate excluding respiratory distress syndrome and pulmonary edema or atelectasis was found in 22 infants (61%). Paralytic ileus, hepatosplenomegaly, and necrotizing enterocolitis were present in 18(50%), 9(25%), and 1(3%) infants, respectively, while skeletal changes suggesting osteomyelitis were found in three. Brain sonography was performed in 29 infants and in four, abnormalities were seen ; these comprised three germinal matrix hemorrhages and one intraparenchymal hemorrhage. In six patients(17%) radiologic examinations revealed no abnormality. In patients with neonatal sepsis, pulmonary infiltrates and paralytic ileus were common abnormalities. Although these were nonspecific, radiologic findings may be used to supplement clinical and laboratory findings in diagnosing neonatal sepsis and planning its treatment

Radiologic findings of neonatal sepsis

Energy Technology Data Exchange (ETDEWEB)

Kim, Sam Soo; Han, Dae Hee; Choi, Guk Myeong; Jung, Hye Won [Seoul National Univ. College of Medicine, Seoul (Korea, Republic of); Yoon, Hye Kyung; Han, Bokyung Kim; Lee, Nam Yong [Sansung Medical Center, Seoul (Korea, Republic of)

1997-06-01

To review the simple radiographic and sonographic findings in infants with neonatal sepsis. We retrospectively analyzed simple chest and abdominal radiographs, and brain sonograms in 36 newborn infants (preterm : term=23 :13). With neonatal sepsis diagnosed by blood culture and clinical manifestations. Pulmonary parenchymal infiltrate excluding respiratory distress syndrome and pulmonary edema or atelectasis was found in 22 infants (61%). Paralytic ileus, hepatosplenomegaly, and necrotizing enterocolitis were present in 18(50%), 9(25%), and 1(3%) infants, respectively, while skeletal changes suggesting osteomyelitis were found in three. Brain sonography was performed in 29 infants and in four, abnormalities were seen ; these comprised three germinal matrix hemorrhages and one intraparenchymal hemorrhage. In six patients(17%) radiologic examinations revealed no abnormality. In patients with neonatal sepsis, pulmonary infiltrates and paralytic ileus were common abnormalities. Although these were nonspecific, radiologic findings may be used to supplement clinical and laboratory findings in diagnosing neonatal sepsis and planning its treatment.

Artificial Neural Network for Total Laboratory Automation to Improve the Management of Sample Dilution.

Science.gov (United States)

Ialongo, Cristiano; Pieri, Massimo; Bernardini, Sergio

2017-02-01

Diluting a sample to obtain a measure within the analytical range is a common task in clinical laboratories. However, for urgent samples, it can cause delays in test reporting, which can put patients' safety at risk. The aim of this work is to show a simple artificial neural network that can be used to make it unnecessary to predilute a sample using the information available through the laboratory information system. Particularly, the Multilayer Perceptron neural network built on a data set of 16,106 cardiac troponin I test records produced a correct inference rate of 100% for samples not requiring predilution and 86.2% for those requiring predilution. With respect to the inference reliability, the most relevant inputs were the presence of a cardiac event or surgery and the result of the previous assay. Therefore, such an artificial neural network can be easily implemented into a total automation framework to sensibly reduce the turnaround time of critical orders delayed by the operation required to retrieve, dilute, and retest the sample.

Poul Erik Andersen's radiological work on Osteochondrodysplasias and interventional radiology

DEFF Research Database (Denmark)

Andersen, Poul Erik

2011-01-01

Hospital. His significant experience and extensive scientific work has led to many posts in the Danish Society of Interventional Radiology, the European Society of Radiology and the Cardiovascular and Interventional Radiological Society of Europe, where he is a fellow and has passed the European Board...... of Interventional Radiology - The European qualification in Interventional Radiology....

Analytical laboratory quality assurance guidance in support of EM environmental sampling and analysis activities

International Nuclear Information System (INIS)

1994-05-01

This document introduces QA guidance pertaining to design and implementation of laboratory procedures and processes for collecting DOE Environmental Restoration and Waste Management (EM) ESAA (environmental sampling and analysis activities) data. It addresses several goals: identifying key laboratory issues and program elements to EM HQ and field office managers; providing non-prescriptive guidance; and introducing environmental data collection program elements for EM-263 assessment documents and programs. The guidance describes the implementation of laboratory QA elements within a functional QA program (development of the QA program and data quality objectives are not covered here)

Establishment of exposure dose assessment laboratory in National Radiation Emergency Medical Center (NREMC)

Energy Technology Data Exchange (ETDEWEB)

Yoo, Jae Ryong; Ha, Wi Ho; Yoon, Seok Won; Han, Eun Ae; Lee, Seung Sook [Korea Institute of Radiological and Medical Sciences, Seoul (Korea, Republic of)

2011-10-15

As unclear industry grown, 432 of the nuclear power plants are operating and 52 of NPPs are under construction currently. Increasing use of radiation or radioisotopes in the field of industry, medical purpose and research such as non-destructive examination, computed tomography and x-ray, etc. constantly. With use of nuclear or radiation has incidence possibility for example the Fukushima NPP incident, the Goiania accident and the Chernobyl Nuclear accident. Also the risk of terror by radioactive material such as Radiological Dispersal Device(RDD) etc. In Korea, since the 'Law on protection of nuclear facilities and countermeasure for radioactive preparedness was enacted in 2003, the Korean institute of Radiological and Medical Sciences(KIRAMS) was established for the radiation emergency medical response in radiological disaster due to nuclear accident, radioactive terror and so on. Especially National Radiation Emergency Medical Center(NREMC) has the duty that is protect citizens from nuclear, radiological accidents or radiological terrors through the emergency medical preparedness. The NREMC was established by the 39-article law on physical protection of nuclear material and facilities and measures for radiological emergencies. Dose assessment or contamination survey should be performed which provide the radiological information for medical response. For this reason, the NREMC establish and re-organized dose assessment system based on the existing dose assessment system of the NREMC recently. The exposure dose could be measured by physical and biological method. With these two methods, we can have conservative dose assessment result. Therefore the NREMC established the exposure dose assessment laboratory which was re-organized laboratory space and introduced specialized equipment for dose assessment. This paper will report the establishment and operation of exposure dose assessment laboratory for radiological emergency response and discuss how to enhance

Use of the analytical tree technique to develop a radiological protection program

International Nuclear Information System (INIS)

Domenech N, H.; Jova S, L.

1996-01-01

The results obtained by the Cuban Center for Radiological Protection and Hygiene by using an analytical tree technique to develop its general operational radiation protection program are presented. By the application of this method, some factors such as the organization of the radiation protection services, the provision of administrative requirements, the existing general laboratories requirements, the viability of resources and the current documentation was evaluated. Main components were considered such as: complete normative and regulatory documentation; automatic radiological protection data management; scope of 'on the-job'and radiological protection training for the personnel; previous radiological appraisal for the safety performance of the works and application of dose constrains for the personnel and the public. The detailed development of the program allowed to identify the basic aims to be achieved in its maintenance and improvement. (authors). 3 refs

Viability study of a construction of invasive high voltage meter for the National Reference Laboratory of the Brazilian Net Calibration in Diagnostic Radiology, the National Laboratory of Metrology of the Ionizing Radiation - LNMRI

International Nuclear Information System (INIS)

Quaresma, D.S.; Peixoto, J.G.P.; Pereira, M.A.G.

2007-01-01

This work has studied the parameters for the construction of an invasive high voltage meter for the National Reference Laboratory of the Brazilian Net Calibration in Diagnostic Radiology, the National Laboratory of Metrology of the Ionizing Radiation - LNMRI. This study took into consideration the necessity of quality control of the of X-rays equipment required by Ministry of Health - MS, through the regulation N.453. To satisfy the demands of the MS, the recommendation of the norm IEC 61676 was analyzed by using the quantity of Practical Peak Voltage (PPV) in the measurements of the voltage discharge applied to the X-rays tubes, the infra structures of metrology available in the country to offer tracking the components of the high voltage meter through INMETRO and the difficulty of adaptation of the high voltage meter analyser III U in relation to the Pan tak HF160 equipment in which respect the connection of the high voltage cable and the voltage limitations due to the electric configuration of the high voltage generator of the constant potential Pantak HF160 equipment. (author)

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

Chronicle of pediatric radiology

International Nuclear Information System (INIS)

Benz-Bohm, Gabriele; Richter, Ernst

2012-01-01

The chronicle of pediatric radiology covers the following issues: Development of pediatric radiology in Germany (BRD, DDR, pediatric radiological accommodations); development of pediatric radiology in the Netherlands (chronology and pediatric radiological accommodations); development of pediatric radiology in Austria (chronology and pediatric radiological accommodations); development of pediatric radiology in Switzerland (chronology and pediatric radiological accommodations).

Radiological survey results at 4400 Piehl Road, Ottawa Lake, Michigan

International Nuclear Information System (INIS)

Foley, R.D.; Johnson, C.A.

1993-04-01

At the request of the US Department of Energy (DOE), a team from Oak Ridge National Laboratory conducted a radiological survey at 4400 Piehl Road in Ottawa Lake, Michigan. The survey was performed in September, 1992. The purpose of the survey was to determine if materials containing uranium from work performed under government contract at the former Baker Brothers facility in Toledo, Ohio had been transported off-site to this neighboring area. The radiological survey included surface gamma scans indoors and outdoors, alpha and beta scans inside the house and attached garage, beta-gamma scans of the hard surfaces outside, and the collection of soil, water, and dust samples for radionuclide analyses. Results of the survey demonstrated that the majority of the measurements on the property were within DOE guidelines. However, the presence of isolated spots of uranium contamination were found in two areas where materials were allegedly transported to the property from the former Baker Brothers site. Uranium uptake by persons on the property by ingestion is fairly unlikely, but inhalation is a possibility. Based on these findings, it is recommended that the residential property at 4400 Piehl Road in Ottawa Lake, Michigan be considered for inclusion under FUSRAP

Annual environmental monitoring report of the Lawrence Berkeley Laboratory

International Nuclear Information System (INIS)

Schleimer, G.E.

1983-04-01

In order to establish whether LBL research activities produces any impact on the population surrounding the Laboratory, a program of environmental air and water sampling and continuous radiation monitoring was carried on throughout the year. For 1982, as in the previous several years, doses attributable to LBL radiological operations were a small fraction of the relevant radiation protection guidelines (RPG). The maximum perimeter dose equivalent was less than or equal to 24.0 mrem (the 1982 dose equivalent measured at the Building 88 monitoring station B-13A, about 5% of the RPG). The total population dose equivalent attributable to LBL operations during 1982 was less than or equal to 16 man-rem, about 0.002% of the RPG of 170 mrem/person to a suitable sample of the population

Use of standard laboratory methods to obviate routine dithiothreitol treatment of blood samples with daratumumab interference.

Science.gov (United States)

Lintel, Nicholas J; Brown, Debra K; Schafer, Diane T; Tsimba-Chitsva, Farai M; Koepsell, Scott A; Shunkwiler, Sara M

2017-01-01

Daratumumab is an antibody currently used in the treatment of patients with refractory multiple myeloma. Blood samples from patients being treated with daratumumab may show panreactivity during pre-transfusion testing. To facilitate the provision of blood components for such patients, it is recommended that a baseline phenotype or genotype be established prior to starting treatment with daratumumab. If patient red blood cells (RBCs) require phenotyping after the start of daratumumab treatment, dithiothreitol (DTT) treatment of the patient's RBCs should be performed. The medical charts of four patients treated with daratumumab were reviewed. The individual number of doses ranged from 1 to 14; patient age ranged from 55 to 78 years; two men and two women were included in the review. Type and screen data were obtained from samples collected over 33 encounters with a range of 1 to 13 encounters per patient. All samples were tested initially by automated solid-phase testing. Any reactivity with solid phase led to tube testing with either low-ionic-strength saline, polyethylene glycol, or both. If incubation failed to eliminate the reactivity, the sample was sent to a reference laboratory for DTT treatment and phenotyping. Of the 33 samples tested, 23 (69.7%) samples had reactivity in solid-phase testing. In 8 of the 10 samples that did not react in solid-phase, testing was conducted more than four half-lives after the last dose of daratumumab. Of the 23 that had reactivity in solid-phase, 16 (69.6%) samples demonstrated loss of reactivity using common laboratory methods. For the seven patients whose sample reactivity was not initially eliminated, six were provided with phenotypically matched blood based on prior molecular testing. Only one sample was sent out for DTT treatment. These results suggest that daratumumab interference with pre-transfusion testing can be addressed using common laboratory methods. This finding could save time and money for laboratories that do

Decontamination and decommissioning of laboratory solutions enriched uranium (IR-01 b)

International Nuclear Information System (INIS)

Diaz Arocas, P. P.; Sama Colao, J.; Garcia Diaz, A.; Torre Rodriguez, J.; Martinez, A.; Argiles, E.; Garrido Delgado, C.

2010-01-01

Completed actions decontamination and decommissioning of the Laboratory of Enriched Uranium Solutions, attached to the Radioactivity lR-0l CIEMAT, was carried out final radiological control of the laboratory. From the documentation generated proceeded to request modification of the IR-01 installation by closing its laboratory IR-01 b.

Second Professional Specialization in Radiological Protection in Peru

International Nuclear Information System (INIS)

Medina-Gironzini, E.

2004-01-01

Considering that professionals with studies, training and experience in Radiological Protection as a Second Professional Specialization must be recognized, the Peruvian Institute of Nuclear Energy (IPEN), which is the institution responsible for the promotion and control of ionizing radiations in the country, has sign a specific agreement with the Universidad Nacional Mayor de San Marcos, in order to develop these courses. They are based on the content of the Post Graduate Course on Radiological Protection and Nuclear Safety of the Universidad de Buenos Aires, in Argentina, where more than 360 people from 27 different countries have been trained in the last 20 years. People who have a professional degree in Sciences or Engineering, and who fulfill the requirements demanded by the University, study this Second Professional Specialization in Radiological Protection. The studies last 2 years and the courses cover the following subjects: Nuclear Physics, Basic Mathematics, Basic Biology, Radiation Sources, Interaction between Radiation and Matter, Radiation Detection and Measurement, Biological effects of ionizing radiations, Radiological protection in the use of radiations in industry and medicine, Regulatory aspects, and nuclear safety - radiological protection interface. IPEN has taken the responsibility to carry out these studies due to its experience in the organization, together with different Universities, of six Masters in Nuclear Energy, four Masters in Medical Physics, one Master in Nuclear Physics, one Master in Nuclear Chemistry, and two Specialization in Nuclear Medicine. For this purpose, IPEN has the Superior Center of Nuclear Studies (CSEN), which has trained more than 2200 people in radiological protection in more than 30 years. CSEN is the first center in the country to train people in the area of nuclear energy and radiological protection. It has the best staff of professors with a both a great education and professional experience, as well as

Second Professional Specialization in Radiological Protection in Peru

Energy Technology Data Exchange (ETDEWEB)

Medina-Gironzini, E.

2004-07-01

Considering that professionals with studies, training and experience in Radiological Protection as a Second Professional Specialization must be recognized, the Peruvian Institute of Nuclear Energy (IPEN), which is the institution responsible for the promotion and control of ionizing radiations in the country, has sign a specific agreement with the Universidad Nacional Mayor de San Marcos, in order to develop these courses. They are based on the content of the Post Graduate Course on Radiological Protection and Nuclear Safety of the Universidad de Buenos Aires, in Argentina, where more than 360 people from 27 different countries have been trained in the last 20 years. People who have a professional degree in Sciences or Engineering, and who fulfill the requirements demanded by the University, study this Second Professional Specialization in Radiological Protection. The studies last 2 years and the courses cover the following subjects: Nuclear Physics, Basic Mathematics, Basic Biology, Radiation Sources, Interaction between Radiation and Matter, Radiation Detection and Measurement, Biological effects of ionizing radiations, Radiological protection in the use of radiations in industry and medicine, Regulatory aspects, and nuclear safety - radiological protection interface. IPEN has taken the responsibility to carry out these studies due to its experience in the organization, together with different Universities, of six Masters in Nuclear Energy, four Masters in Medical Physics, one Master in Nuclear Physics, one Master in Nuclear Chemistry, and two Specialization in Nuclear Medicine. For this purpose, IPEN has the Superior Center of Nuclear Studies (CSEN), which has trained more than 2200 people in radiological protection in more than 30 years. CSEN is the first center in the country to train people in the area of nuclear energy and radiological protection. It has the best staff of professors with a both a great education and professional experience, as well as

Questions to the radiological protection in the Universidad Nacional Autonoma de Mexico

International Nuclear Information System (INIS)

Salas M, B.

2014-08-01

In the Physics Department of the Sciences Faculty of the Universidad Nacional Autonoma de Mexico (UNAM) exist at least 3 sites where radioactive sources and generating equipment s of ionizing radiation are managed: The Modern Physics Laboratory, the Radiological Analysis of Environmental Samples Workshop and the Collisions Workshop; the first of them has two neutron sources, in addition to other emitted sources of gamma and beta radiation. The neutron sources are of Americium 241-Beryllium and other of Californium-252 which have been operated outside of the control of the Comision Nacional de Seguridad Nuclear y Salvaguardias (CNSNS) that is the regulator organ in Mexico in nuclear matter, because the Operation License No. 183/85, with file number 657 that protected them, lost their validity from August 13, 1987 (25 years behind), what motivated to that the CNSNS assured them. Later to the closing of the Radiological Analysis of Environmental Samples Workshop was believed that a Barium-133 source had been extracted in an illegal way; an investigation realized by the CNSNS determined that the radioactive source was always inside of the detection systems and radiation measurement, for what this source was never lost. In the Collisions Workshop operated an Experimental Accelerator of Particles that the CNSNS prohibited its operation for not having the corresponding license. These examples can be considered as bad practices of radiological protection that should be pointed out to eradicate their promotion and to avoid this way the exposure to the radiation of the occupational exposed personnel and people in general, being also avoided dose of unnecessary radiation. The Instituto Federal de Acceso a la Informacion Publica y Proteccion de Datos (IFAI) in Mexico was a key factor to obtain the information that allowed the realization of this work that was carried out in the Sciences Faculty of the UNAM. (Author)

Use of Low-Fidelity Simulation Laboratory Training for Teaching Radiology Residents CT-Guided Procedures.

Science.gov (United States)

Picard, Melissa; Nelson, Rachel; Roebel, John; Collins, Heather; Anderson, M Bret

2016-11-01

To determine the benefit of the addition of low-fidelity simulation-based training to the standard didactic-based training in teaching radiology residents common CT-guided procedures. This was a prospective study involving 24 radiology residents across all years in a university program. All residents underwent standard didactic lecture followed by low-fidelity simulation-based training on three common CT-guided procedures: random liver biopsy, lung nodule biopsy, and drain placement. Baseline knowledge, confidence, and performance assessments were obtained after the didactic session and before the simulation training session. Approximately 2 months later, all residents participated in a simulation-based training session covering all three of these procedures. Knowledge, confidence, and performance data were obtained afterward. These assessments covered topics related to preprocedure workup, intraprocedure steps, and postprocedure management. Knowledge data were collected based on a 15-question assessment. Confidence data were obtained based on a 5-point Likert-like scale. Performance data were obtained based on successful completion of predefined critical steps. There was significant improvement in knowledge (P = .005), confidence (P simulation-based training to the standard didactic curriculum for all procedures. This study suggests that the addition of low-fidelity simulation-based training to a standard didactic-based curriculum is beneficial in improving resident knowledge, confidence, and tested performance of common CT-guided procedures. Copyright © 2016 American College of Radiology. Published by Elsevier Inc. All rights reserved.

Imaging and radiology

Science.gov (United States)

Interventional radiology; Diagnostic radiology; X-ray imaging ... DIAGNOSTIC RADIOLOGY Diagnostic radiology helps health care professionals see structures inside your body. Doctors that specialize in the interpretation ...

Sampling and Analysis Plan for Verification Sampling of LANL-Derived Residual Radionuclides in Soils within Tract A-18-2 for Land Conveyance

Energy Technology Data Exchange (ETDEWEB)

Ruedig, Elizabeth [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2017-08-30

Public Law 105-119 directs the U.S. Department of Energy (DOE) to convey or transfer parcels of land to the Incorporated County of Los Alamos or their designees and to the Department of Interior, Bureau of Indian Affairs, in trust for the Pueblo de San Ildefonso. Los Alamos National Security is tasked to support DOE in conveyance and/or transfer of identified land parcels no later than September 2022. Under DOE Order 458.1, Radiation Protection of the Public and the Environment (O458.1, 2013) and Los Alamos National Laboratory (LANL or the Laboratory) implementing Policy 412 (P412, 2014), real property with the potential to contain residual radioactive material must meet the criteria for clearance and release to the public. This Sampling and Analysis Plan (SAP) is a second investigation of Tract A-18-2 for the purpose of verifying the previous sampling results (LANL 2017). This sample plan requires 18 projectspecific soil samples for use in radiological clearance decisions consistent with LANL Procedure ENV-ES-TP-238 (2015a) and guidance in the Multi-Agency Radiation Survey and Site Investigation Manual (MARSSIM, 2000). The sampling work will be conducted by LANL, and samples will be evaluated by a LANL-contracted independent lab. However, there will be federal review (verification) of all steps of the sampling process.

2017 Annual Terrestrial Sampling Plan for Sandia National Laboratories/New Mexico on Kirtland Air Force Base

Energy Technology Data Exchange (ETDEWEB)

Griffith, Stacy R. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

2017-02-01

The 2017 Annual Terrestrial Sampling Plan for Sandia National Laboratories/New Mexico on Kirtland Air Force Base has been prepared in accordance with the “Letter of Agreement Between Department of Energy, National Nuclear Security Administration, Sandia Field Office (DOE/NNSA/SFO) and 377th Air Base Wing (ABW), Kirtland Air Force Base (KAFB) for Terrestrial Sampling” (signed January 2017), Sandia National Laboratories, New Mexico (SNL/NM). The Letter of Agreement requires submittal of an annual terrestrial sampling plan.

2018 Annual Terrestrial Sampling Plan for Sandia National Laboratories/New Mexico on Kirtland Air Force Base.

Energy Technology Data Exchange (ETDEWEB)

Griffith, Stacy R. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

2018-01-01

The 2018 Annual Terrestrial Sampling Plan for Sandia National Laboratories/New Mexico on Kirtland Air Force Base has been prepared in accordance with the “Letter of Agreement Between Department of Energy, National Nuclear Security Administration, Sandia Field Office (DOE/NNSA/SFO) and 377th Air Base Wing (ABW), Kirtland Air Force Base (KAFB) for Terrestrial Sampling” (signed January 2017), Sandia National Laboratories, New Mexico (SNL/NM). The Letter of Agreement requires submittal of an annual terrestrial sampling plan.

Air kerma standardization for diagnostic radiology, and requirements proposal for calibration laboratories; Padronizacao da grandeza Kerma no ar para radiodiagnostico e proposta de requisitos para laboratorios de calibracao

Energy Technology Data Exchange (ETDEWEB)

Ramos, Manoel Mattos Oliveira

2009-07-01

The demand for calibration services and quality control in diagnostic radiology has grown in the country since the publication of the governmental regulation 453, issued by the Ministry of Health in 1998. At that time, to produce results facing the new legislation, many laboratories used different standards and radiation qualities, some of which could be inadequate. The international standards neither supplied consistent radiation qualities and standardization for the different types of equipment available. This situation changed with the publication of the new edition of the IEC 61267 standard, published in 2005. A metrology network was created, but it is not yet accredited by the accreditation organism of the country, INMETRO. The objective of this work was to implement the standardization of the air kerma for the un attenuated qualities (RQR) of IEC 61267, and to develop a requirement proposal for instruments calibration laboratories. Results of interlaboratory comparisons demonstrate that the quantity is standardized and internationally traceable. A laboratory requirement proposal was finalized and it shall be submitted to INMETRO to be used as auxiliary normative document in laboratory accreditation. (author)

Radiological characterization survey results for Gaskill Hall, Miami University, Oxford, Ohio (OXO015)

International Nuclear Information System (INIS)

Kleinhans, K.R.; Murray, M.E.; Carrier, R.F.

1996-04-01

Between October 1952 and February 1957, National Lead of Ohio (NLO), a primary contractor for the Atomic Energy Commission (AEC), subcontracted certain uranium machining operations to Alba Craft Laboratory, Incorporated, located at 10-14 West Rose Avenue, Oxford, Ohio. In 1992, personnel from Oak Ridge National Laboratory (ORNL) confirmed the presence of residual radioactive materials from the AEC-related operations in and around the facility in amounts exceeding the applicable Department of Energy (DOE) guidelines. Although the amount of uranium found on the property posed little health hazard if left undisturbed, the levels were sufficient to require remediation to bring radiological conditions into compliance with current guidelines, thus ensuring that the public and the environment are protected. Because it was suspected that uranium may have been used in the past in the immediate vicinity of Alba Craft in a Miami University building a team from ORNL, performed a radiological characterization survey of that structure in January 1994. The survey was conducted at the request of DOE as a precautionary measure to ensure that no radioactive residuals were present at levels exceeding guidelines. The survey included the determination of directly measured radiation levels and the collection of smear samples to detect possible removable alpha and beta-gamma activity levels, and comparison of these data to the guidelines. Results of the survey showed that all measurements were below the applicable guideline limits set by DOE

Implementation of the Gamma Monitor Calibration Laboratory (LABCAL) of the Institute of Chemical, Biological, Radiological and Nuclear Defense (IDQBRN) of the Technology Center of the Brazilian Army (CTEx)

Energy Technology Data Exchange (ETDEWEB)

Balthar, Mario Cesar V.; Amorim, Aneuri de; Santos, Avelino dos and others, E-mail: mariobalthar@gmail.com [Centro Tecnológico do Exército (IDQBRN/CTEx), Rio de Janeiro, RJ (Brazil). Instituto de Defesa Química, Biológica, Radiológica e Nuclear

2017-07-01

The objective of this work is to describe the implementation and adaptation stages of the Gamma Monitor Calibration Laboratory (Laboratório de Calibração de Monitores Gama - LABCAL) of the Institute of Chemical, Biological, Radiological and Nuclear Defense (Instituto de Defesa Química, Biológica, Radiológica e Nuclear - IDQBRN) of the Technology Center of the Brazilian Army (Centro Tecnológico do Exército - CTEx). Calibration of the radiation monitors used by the Brazilian Army will be performed by quantitatively measuring the ambient dose equivalent, in compliance with national legislation. LABCAL still seeks licensing from CNEN and INMETRO. The laboratory in intended to supply the total demand for calibration of ionizing radiation devices from the Brazilian Army. (author)

Implementation of the Gamma Monitor Calibration Laboratory (LABCAL) of the Institute of Chemical, Biological, Radiological and Nuclear Defense (IDQBRN) of the Technology Center of the Brazilian Army (CTEx)

International Nuclear Information System (INIS)

Balthar, Mario Cesar V.; Amorim, Aneuri de; Santos, Avelino dos and others

2017-01-01

The objective of this work is to describe the implementation and adaptation stages of the Gamma Monitor Calibration Laboratory (Laboratório de Calibração de Monitores Gama - LABCAL) of the Institute of Chemical, Biological, Radiological and Nuclear Defense (Instituto de Defesa Química, Biológica, Radiológica e Nuclear - IDQBRN) of the Technology Center of the Brazilian Army (Centro Tecnológico do Exército - CTEx). Calibration of the radiation monitors used by the Brazilian Army will be performed by quantitatively measuring the ambient dose equivalent, in compliance with national legislation. LABCAL still seeks licensing from CNEN and INMETRO. The laboratory in intended to supply the total demand for calibration of ionizing radiation devices from the Brazilian Army. (author)

Herbert M. Parker: Publications and contributions to radiological and health physics

International Nuclear Information System (INIS)

Kathren, R.L.; Baalman, R.W.; Bair, W.J.

1986-01-01

For more than a half century, Herbert M. Parker was a leading force in radiological physics. As a scientist, he was codeveloper of a systematic dosimetry scheme for implant therapy and the innovative proposer of radiological units with unambiguous physical and biological bases. He made seminal contributions to the development of scientifically based radiation protection standards and, as an administrator and manager as well as scientist, helped the Hanford Laboratories to achieve preeminance in several areas, including radiation biology, radioactive waste disposal, and environmental radioactivity. This volume brings together, sometimes from obscure sources, his works

The EnzymeTracker: an open-source laboratory information management system for sample tracking.

Science.gov (United States)

Triplet, Thomas; Butler, Gregory

2012-01-26

In many laboratories, researchers store experimental data on their own workstation using spreadsheets. However, this approach poses a number of problems, ranging from sharing issues to inefficient data-mining. Standard spreadsheets are also error-prone, as data do not undergo any validation process. To overcome spreadsheets inherent limitations, a number of proprietary systems have been developed, which laboratories need to pay expensive license fees for. Those costs are usually prohibitive for most laboratories and prevent scientists from benefiting from more sophisticated data management systems. In this paper, we propose the EnzymeTracker, a web-based laboratory information management system for sample tracking, as an open-source and flexible alternative that aims at facilitating entry, mining and sharing of experimental biological data. The EnzymeTracker features online spreadsheets and tools for monitoring numerous experiments conducted by several collaborators to identify and characterize samples. It also provides libraries of shared data such as protocols, and administration tools for data access control using OpenID and user/team management. Our system relies on a database management system for efficient data indexing and management and a user-friendly AJAX interface that can be accessed over the Internet. The EnzymeTracker facilitates data entry by dynamically suggesting entries and providing smart data-mining tools to effectively retrieve data. Our system features a number of tools to visualize and annotate experimental data, and export highly customizable reports. It also supports QR matrix barcoding to facilitate sample tracking. The EnzymeTracker was designed to be easy to use and offers many benefits over spreadsheets, thus presenting the characteristics required to facilitate acceptance by the scientific community. It has been successfully used for 20 months on a daily basis by over 50 scientists. The EnzymeTracker is freely available online at http

Radiological English

Energy Technology Data Exchange (ETDEWEB)

Ribes, R. [Hospital Reina Sofia, Cordoba (Spain). Servicio de Radiologia; Ros, P.R. [Harvard Medical School, Boston, MA (United States). Div. of Radiology

2007-07-01

The book is an introductory book to radiological English on the basis that there are a lot of radiologists, radiology residents, radiology nurses, radiology students, and radiographers worldwide whose English level is indeterminate because their reading skills are much higher than their fluency. It is intended to help those health care professionals who need English for their work but do not speak English on a day-to-day basis. (orig.)

Radiological English

International Nuclear Information System (INIS)

Ribes, R.; Ros, P.R.

2007-01-01

The book is an introductory book to radiological English on the basis that there are a lot of radiologists, radiology residents, radiology nurses, radiology students, and radiographers worldwide whose English level is indeterminate because their reading skills are much higher than their fluency. It is intended to help those health care professionals who need English for their work but do not speak English on a day-to-day basis. (orig.)

Handbook of radiologic procedures

International Nuclear Information System (INIS)

Hedgcock, M.

1986-01-01

This book is organized around radiologic procedures with each discussed from the points of view of: indications, contraindications, materials, method of procedures and complications. Covered in this book are: emergency radiology chest radiology, bone radiology, gastrointestinal radiology, GU radiology, pediatric radiology, computerized tomography, neuroradiology, visceral and peripheral angiography, cardiovascular radiology, nuclear medicine, lymphangiography, and mammography

Aerial radiological survey of the Brookhaven National Laboratory and surrounding area, Upton, New York. Date of survey: June 1983

International Nuclear Information System (INIS)

Hobaugh, J.L.

1985-02-01

An aerial radiological survey was performed from 11 to 13 June 1983, over approximately a 64-square-kilometer (25-square-mile) area surrounding the Brookhaven National Laboratory (BNL). BNL is located in the center of Suffolk County, Long Island, New York. All gamma radiation data were collected by flying east-west lines spaced 76 meters (250 feet) apart at an altitude of 46 meters (150 feet) above ground level. Count rates obtained from the aerial platform were converted to exposure rates at 1 meter above the ground. The average background exposure rate in the survey area ranged from 5 to 10 microroentgens per hour (μR/h). The reported exposure rate values include an estimated cosmic ray contribution of 4.0 μR/h. Ground-based measurements made during the same time period were compared to the aerial survey results. Pressurized ion chamber readings and soil samples were taken from two locations within the aerial survey boundaries. Exposure rate values obtained from these measurement techniques were in agreement with those obtained from the aerial data. A total of 23 areas of man-made radioactivity were identified. The dominant isotopes found over these areas were cesium-137, sodium-22, manganese-54, and cobalt-60. A similar survey was conducted in May 1980. The 1983 survey results were similar to the 1980 results. Three areas of low level man-made activity were not reproduced by the 1983 data. Ten new areas were detected. The major difference occurred because of the increased sensitivity and spatial reduction brought on by lowering the altitude and decreasing the line spacing. 8 refs., 28 figs., 4 tabs

Quality assurance programme in diagnostic radiology

International Nuclear Information System (INIS)

Yacovenco, A.A.

1996-01-01

One hundred years after the discovery of X-rays, they continue being nowadays part of physicians' daily activities, and the diagnosis through the use of X-ray equipment is one of the most important fields in clinical medicine, thus becoming the most important cause of human exposure to artificial sources. For this reason, in the last twenty years, most of the developed countries did the utmost to establish programs which could warrant the quality of the radiographic image. Aiming the protection of human being against the harmful effects of ionizing radiations, in December 1980, World Health Organization decided to form a group of professionals highly experienced in medical radiology, and initiate an inspection and quality control program. In September 1988, the Group of Studies of the Program Related to Radiological Protection of the Commission in the European Communities, prepared a working paper in which guidelines were set up regarding quality of images, dosage to patient, and associated radiographic factors, necessary to obtain acceptable radiologic performance. In Brazil, efforts driven in this direction, guided by some equipment testing, starting in 1990, began to be more known. When the Director and the Head of Radiology in the Military Police Hospital of the State of Rio de Janeiro (HPM) reamed about these efforts, they decided to contact the Institute for Radioprotection and Dosimetry (IRD) of Comissao Nacional de Energia Nuclear and submit the problem of low radiologic performance and increasing rates of rejection. Thus, with the coincidence of interests and needs, along with a proposal from the Commission of the European Communities (CEC), IRD decided to offer the author laboratory support to elaborate a Quality Assurance Program (QAP) to be implemented in HPM. (author)

Radiological dose assessments in the northern Marshall Islands (1989--1991)

International Nuclear Information System (INIS)

Sun, L.C.; Meinhold, C.B.; Moorthy, A.R.; Clinton, J.H.; Kaplan, E.

1991-12-01

The Republic of the Marshall Islands (RMI) is located in the central Pacific Ocean about 3500 km southeast of Hawaii and 4500 km east of Manila, Philippines. It consists of 34 atolls and 2 coral island, having a total land area of about 180 km 2 , distributed over more than 2.5 x 10 6 km 2 of ocean. Between 1946 and 1958 the United States conducted nuclear tests there: 43 at Enewetak and 23 at Bikini. Thirty-three years after the cessation of nuclear testing in the RMI, the impact of these operations on the health and radiological safety of the people living in or planing to return to their contaminated homelands is still an important concern. The present Brookhaven National Laboratory (BNL) Marshall Islands Radiological Safety Program (MIRSP) began in 1987 with funding from the US Department of Energy (DOE). The objectives of the MIRSP are to determine the radionuclides present in the bodies of those people potentially exposed to residual radionuclide from weapon tests and fallout, and to assess their present and lifetime dose from external and internal sources. Field bioassay missions involving whole-body counting (WBC) and urine sample collection have, therefore, been important components of the program. WBC is used to measure γ-emitters, such as 40 K, 60 Co and 137 Cs, present in individuals. Urine samples are used to measure α and β-emitting nuclides, such as 239 Pu and 90 Sr, that are undetectable by WBC routine methods. 6 refs

Blood sample collection and patient identification demand improvement: a questionnaire study of preanalytical practices in hospital wards and laboratories.

Science.gov (United States)

Wallin, Olof; Söderberg, Johan; Van Guelpen, Bethany; Stenlund, Hans; Grankvist, Kjell; Brulin, Christine

2010-09-01

Scand J Caring Sci; 2010; 24; 581-591 
 Blood sample collection and patient identification demand improvement: a questionnaire study of preanalytical practices in hospital wards and laboratories   Most errors in venous blood testing result from human mistakes occurring before the sample reach the laboratory.   To survey venous blood sampling (VBS) practices in hospital wards and to compare practices with hospital laboratories.   Staff in two hospitals (all wards) and two hospital laboratories (314 respondents, response rate 94%), completed a questionnaire addressing issues relevant to the collection of venous blood samples for clinical chemistry testing.   The findings suggest that instructions for patient identification and the collection of venous blood samples were not always followed. For example, 79% of the respondents reported the undesirable practice (UDP) of not always using wristbands for patient identification. Similarly, 87% of the respondents noted the UDP of removing venous stasis after the sampling is finished. Compared with the ward staff, a significantly higher proportion of the laboratory staff reported desirable practices regarding the collection of venous blood samples. Neither education nor the existence of established sampling routines was clearly associated with VBS practices among the ward staff.   The results of this study, the first of its kind, suggest that a clinically important risk of error is associated with VBS in the surveyed wards. Most important is the risk of misidentification of patients. Quality improvement of blood sample collection is clearly needed, particularly in hospital wards. © 2009 The Authors. Journal compilation © 2009 Nordic College of Caring Science.

RSVP radiology

International Nuclear Information System (INIS)

Kirks, D.R.; Chaffee, D.J.

1990-01-01

This paper develops a relative scale of value for pediatric radiology (RSVPR). Neither the HCFA/ACA Relative Value Scale nor the Workload Measurement System developed by Health and Welfare Canada specifically addressed pediatric radiologic examinations. Technical and professional charges for examinations at Children's Hospital Medical Center were reviewed and compared with time and cost analysis. A scale was developed with chest radiography (PA and lateral views) assigned a value of 1. After review by pediatric radiologic technologists, radiologic administrators, pediatric radiologists, and chairs of departments of children's hospitals, this proposed scale was modified to reflect more accurately relative value components of pediatric radiologic and imaging examinations

Radiological anatomy - evaluation of integrative education in radiology.

Science.gov (United States)

Dettmer, S; Schmiedl, A; Meyer, S; Giesemann, A; Pabst, R; Weidemann, J; Wacker, F K; Kirchhoff, T

2013-09-01

Evaluation and analysis of the integrative course "Radiological Anatomy" established since 2007 at the Medical School Hannover (MHH) in comparison with conventional education. Anatomy and radiology are usually taught separately with a considerable time lag. Interdisciplinary teaching of these associated subjects seems logical for several reasons. Therefore, the integrative course "Radiological Anatomy" was established in the second year of medical education, combining these two closely related subjects. This interdisciplinary course was retrospectively evaluated by consideration of a student questionnaire and staff observations. The advantages and disadvantages of integrative teaching in medical education are discussed. The course ratings were excellent (median 1; mean 1.3 on a scale of 1 to 6). This is significantly (p radiology increased during the course (88 %). According to the students' suggestions the course was enhanced by a visitation in the Department of Radiology and the additional topic central nervous system. Integrative teaching of anatomy and radiology was well received by the students. Both, anatomical and radiological comprehension and the motivation to learn were improved. However, it should be considered, that the amount of work and time required by the teaching staff is considerably increased compared to traditional teaching. © Georg Thieme Verlag KG Stuttgart · New York.

Analysis of the Radiology Reports from Radiology Clinics

International Nuclear Information System (INIS)

Kim, Eun Jin; Kwack, Kyu Sung; Cho, Jae Hyun; Jang, Eun Ho

2009-01-01

The purpose of this study was to investigate the form and content of the radiology reports from radiology clinics in Korea. One hundred and sixty six radiology reports from 49 radiology clinics were collected, and these reports were referred to the academic tertiary medical center from March 2008 to February 2009. These included reports for CT (n = 18), MRI (n = 146) and examinations not specified (n = 2). Each report was evaluated for the presence of required contents (demographics, technical information, findings, conclusion, the name, license number and signature of the radiologist and the referring facility). These requirements were based on the guideline of the American College of Radiology and the previous research. The name of the patient, the gender, the body part, the type of examination, the time of examination and the conclusion, the name of the radiologist and the name of facility were well recorded in over 90% of the radiology reports. However, the identification number of the patient, the referring facility, the referring physician, the use of contrast material, the clinical information, the time of dictation, the signature of the radiologist and the license number of the radiologist were poorly recorded (less than 50%). The optimal format of a radiology report should be established for reliable and valid communication with clinicians

Radiological characterisation of V1 NPP technological systems and buildings - Activation

International Nuclear Information System (INIS)

Kristofova, Kristina; Rapant, Tibor; Svitek, Jaroslav

2012-01-01

V1 NPP at Jaslovske Bohunice site has been finally shutdown after 28 years of successful operation in 2006 (Unit 1) and 2008 (Unit 2). At present, both units are finally shutdown and since July 2011 under decommissioning license. The preparation of V1 NPP decommissioning has been supported and partly financed by the Bohunice International Decommissioning Support Fund (BIDSF), under the administration of the European Bank for Reconstruction and Development. From 06/2008 to 12/2011 AMEC Nuclear Slovakia, together with partners STM Power and EWN GmbH, carried out BIDSF B6.4 project - Decommissioning database development (DDB). The main purpose of the B6.4 project was to develop a physical and radiological inventory database to support V1 NPP decommissioning process planning and performance. One of the specific deliverable tasks within the B6.4 project was deliverable D12 - Characterization of activated equipment and civil structures based on measurement, sampling and analyses performed on the samples. The scope of deliverable services within D12 task consisted of: 1. Categorization of activated components ; 2. Development of single working programs for their radiological monitoring and sampling ; 3. Preparation of sampling device and revision of all handling equipment; 4. Dose rate monitoring and sampling of: - Civil structures from reactors shaft on both units ; - Components placed in HLW storage, (so called 'Mogilnik') - connection rods, absorbers ; of control rod assemblies and neutron flux measurement channels ; - Reactor pressure vessel and shielding assemblies at both units of V1 NPP, reactor; internals from Unit 2 of V1 NPP; 5. Analysis of samples ; 6. Determination of radiological inventory ; 7. Import of radiological data for activated components into DDB. During sampling, mainly remotely controlled sampling device and radiation resistant camera with LED lightening for visual checking of all performed activities was used. In total, 125 samples have been taken

1985 Effluent and environmental monitoring report for the Bettis Atomic Power Laboratory

International Nuclear Information System (INIS)

1985-01-01

The results of the radiological and non-radiological environmental monitoring programs for 1985 at the Bettis Laboratory are presented. The results obtained from the monitoring programs demonstrate that the existing procedures ensure that all environmental releases during 1985 were in accordance with applicable State and Federal regulations. Evaluation of the environmental data indicates that operation of the Laboratory continued to have no adverse effect on the quality of the environment. Furthermore, a conservative assessment of radiation exposure to the general public as a result of Laboratory operations demonstrated that the dose received by any member of the public was well below the most restrictive dose limits prescribed by the Environmental Protection Agency and the Department of Energy

The significance of radiological control documentation in litigation

International Nuclear Information System (INIS)

Lodde, G.M.; Murphy, T.D.

1988-01-01

Commercial nuclear facilities accumulate radiological control program data and documents generated and retained pursuant to regulatory, license, and technical specification requirements. During and following the Three Mile Island Unit 2 (TMI-2) accident, many documents were produced that would not normally have been produced. Shortly after the accident, the US Nuclear Regulatory Commission (NRC) issued an order requiring the retention of all data, including documentary material and physical samples relating to the TMI-2 accident (44 Fed. Reg. 30788, May 29, 1979). Three years later, the NRC vacated the requirement to retain catalogued physical samples, provided the radioactivity data had been properly recorded, allowing disposal of many samples. After the TMI-2 accident, GPU Nuclear Corporation (GPU) designed and implemented an effective and efficient record management program for TMI. This Computer-Assisted Records and Information Retrieval System (CARIRS) was developed to assess the official record for TMI, which is maintained as a microform. GPU also retains hard copies of selected radiological control documents for potential litigation. This paper describes the use of radiological control documentation in the postaccident litigation and the magnitude of document production required to support that litigation

Radiological analysis of materials sampled on the old nuclear test site of In Ekker (Algeria); Analyses radiologiques de materiaux preleves sur l'ancien site d'essais nucleaires d'In Ekker (Algerie)

Energy Technology Data Exchange (ETDEWEB)

Chareyron, Bruno

2010-02-11

After having recalled the context of the French nuclear test campaign in Algeria between 1961 and 1966, this document reports and comments radiological measurements performed on the site of In Ekker, and also results of analysis performed in laboratory (contamination by cesium 137, americium 241, plutonium); recommendations are given

Archive of Geosample Data and Information from the Woods Hole Oceanographic Institution (WHOI) Seafloor Samples Laboratory

Data.gov (United States)

National Oceanic and Atmospheric Administration, Department of Commerce — The Woods Hole Oceanographic Institution (WHOI) Seafloor Samples Laboratory is a partner in the Index to Marine and Lacustrine Geological Samples (IMLGS) database,...

Sampling of reactor pressure vessel and core internals

International Nuclear Information System (INIS)

Oberhaeuser, Ralf

2012-01-01

, AREVA has developed various dedicated studies and already carried out sampling activities during the last years in different countries. First step of work is the identification of representative sampling positions and proving the accessibility taking into account the most suitable techniques. In general, scratch, drilling and so-called shuttle as well as lens samples are available with their different advantages and disadvantages. An intensive sampling above and below the core center axis reduces the modeling uncertainties in these areas which arise from the relative distance from the neutron flux, from rescattering effects and from different materials. After this a detailed planning of the work execution on-site provides a trouble-free and time optimized project process taking into account the relevant protection goals. The samples are then transported to our accredited radiological laboratory for detailed analysis resulting in a respective analysis report. In the end the customer has a precise overview over the radiological condition of its RPV and the internals to optimize the radioactive waste management. (author)

Idaho National Engineering Laboratory Radiological Control Performance Indicator Report. Fourth quarter -- year-end report, Calendar year 1995

International Nuclear Information System (INIS)

Reavis, R.

1996-03-01

The INEL Radiological Control Performance Indicator Report is comprised of a description of the indicator and the criteria used for measurement. Indicators evaluated in this report include: collective radiation dose; average worker radiation dose; maximum radiation dose to a worker; maximum neutron dose to a worker; number of skin contaminations; number of clothing contaminations; airborne events; total radiological intakes; contamination areas; high contamination area; airborne radioactivity area; and radioactive spills

Introduction of radiological protection; Pengenalan kepada perlindungan radiologi

Energy Technology Data Exchange (ETDEWEB)

NONE

1988-12-31

The chapter briefly discussed the following subjects: basic principles of radiological protection , dose limit which was suggested, stochastic and nonstochastic effects, equivalent dose and alternative of it`s calculation, limit for the publics, ICRP (International Commission for Radiological Protection) recommendations, and the principles of radiological protection. Dangerous radiation sources also briefly summarized i.e. x-ray generators, reactor nucleus.

Summary of Laboratory Capabilities Fact Sheets Waste Sampling and Characterization Facility and 222-S Laboratory Complex

International Nuclear Information System (INIS)

HADLEY, R.M.

2002-01-01

This summary of laboratory capabilities is provided to assist prospective responders to the CH2M HILL Hanford Group, Inc. (CHG) Requests for Proposal (RFP) issued or to be issued. The RFPs solicit development of treatment technologies as categorized in the CHG Requests for Information (RFI): Solid-Liquid Separations Technology - SOL: Reference-Number-CHG01; Cesium and Technetium Separations Technology - SOL: Reference-Number-CHG02; Sulfate Removal Technology - SOL: Reference-Number-CHG03; Containerized Grout Technology - SOL: Reference-Number-CHG04; Bulk Vitrification Technology - SOL: Reference-Number-CHG05; and TRU Tank Waste Solidification for Disposal at the Waste Isolation Pilot Plant - SOL: Reference-Number-CHG06 Hanford Analytical Services, Technology Project Management (TPM), has the capability and directly related experience to provide breakthrough innovations and solutions to the challenges presented in the requests. The 222-S Complex includes the 70,000 sq ft 222-S Laboratory, plus several support buildings. The laboratory has 11 hot cells for handling and analyzing highly radioactive samples, including tank farm waste. Inorganic, organic, and radiochemical analyses are performed on a wide variety of air, liquid, soil, sludge, and biota samples. Capabilities also include development of process technology and analytical methods, and preparation of analytical standards. The TPM staff includes many scientists with advanced degrees in chemistry (or closely related fields), over half of which are PhDs. These scientists have an average 20 years of Hanford experience working with Hanford waste in a hot cell environment. They have hundreds of publications related to Hanford tank waste characterization and process support. These would include, but are not limited to, solid-liquid separations engineering, physical chemistry, particle size analysis, and inorganic chemistry. TPM has had revenues in excess of $1 million per year for the past decade in above

The Idaho National Engineering Laboratory site environmental report for calendar year 1989