The Semipalatinsk nuclear test site: a first assessment of the radiological situation and the test-related radiation doses in the surrounding territories.

Science.gov (United States)

Gusev, B I; Abylkassimova, Z N; Apsalikov, K N

1997-09-01

As a result of atmospheric nuclear tests at the Semipalatinsk test site 'Polygon', adjacent territories were contaminated by radionuclide fallout. The population of some districts in the Semipalatinsk oblast were exposed to elevated levels of radiation. Contamination and exposure mostly resulted from early atmospheric tests. The radiological situation of the Semipalatinsk oblast is described. Effective dose estimates due to external and internal exposure attributable to the 1949 and 1953 tests in villages near the Polygon range from 70 mSv to 4470 mSv.

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

Radiological risk assessment of a radioactively contaminated site

International Nuclear Information System (INIS)

Devgun, J.S.

1990-01-01

A limited-scope preliminary assessment of radiological risk has been conducted at a radioactively contaminated site under current site use conditions and based on the available preliminary radiological characterization data for the site. The assessment provides useful input to the remedial action planning for the site. 8 refs., 1 fig., 2 tabs

Radiological criteria for underground nuclear tests

International Nuclear Information System (INIS)

Malik, J.S.; Brownlee, R.R.; Costa, C.F.; Mueller, H.F.; Newman, R.W.

1981-04-01

The radiological criteria for the conduct of nuclear tests have undergone many revisions with the current criteria being 0.17 rad for uncontrolled populations and 0.5 rad for controllable populations. Their effect upon operations at the Nevada Test Site and the current off-site protective plans are reviewed for areas surrounding the Site. The few accidental releases that have occurred are used to establish estimates of probability of release and of hazard to the population. These are then put into context by comparing statistical data on other accidents and cataclysms. The guidelines established by DOE Manual Chapter MC-0524 have never been exceeded during the entire underground nuclear test program. The probability of real hazard to off-site populations appears to be sufficiently low as not to cause undue concern to the citizenry

Radiological criteria for underground nuclear tests

Energy Technology Data Exchange (ETDEWEB)

Malik, J.S.; Brownlee, R.R.; Costa, C.F.; Mueller, H.F.; Newman, R.W.

1981-04-01

The radiological criteria for the conduct of nuclear tests have undergone many revisions with the current criteria being 0.17 rad for uncontrolled populations and 0.5 rad for controllable populations. Their effect upon operations at the Nevada Test Site and the current off-site protective plans are reviewed for areas surrounding the Site. The few accidental releases that have occurred are used to establish estimates of probability of release and of hazard to the population. These are then put into context by comparing statistical data on other accidents and cataclysms. The guidelines established by DOE Manual Chapter MC-0524 have never been exceeded during the entire underground nuclear test program. The probability of real hazard to off-site populations appears to be sufficiently low as not to cause undue concern to the citizenry.

Nevada Test Site Environmental Report 2003

Energy Technology Data Exchange (ETDEWEB)

Bechtel Nevada

2004-10-01

The Nevada Test Site Environmental Report 2003 was prepared by Bechtel Nevada to meet the requirements and guidelines of the U.S. Department of Energy and the information needs of the public. This report is meant to be useful to members of the public, public officials, regulators, and Nevada Test Site contractors. The Executive Summary strives to present in a concise format the purpose of the document, the NTS mission and major programs, a summary of radiological releases and doses to the public resulting from site operations, a summary of non-radiological releases, and an overview of the Nevada Test Site Environmental Management System. The Executive Summary, combined with the following Compliance Summary, are written to meet all the objectives of the report and to be stand-alone sections for those who choose not to read the entire document.

Development and maintenance of the Hanford Site Radiological Control Manual

International Nuclear Information System (INIS)

Munson, L.H.; Selby, J.M.; Vargo, G.J.; Clark, D.L.

1993-04-01

In June 1992 the US Department of Energy (DOE) issued DOE N5480.6, Radiological Control, which set forth DOE's Radiological Control Program and established the framework for its implementation at sites nationwide. Accompanying the Order was the DOE Radiological Control Manual (DOE RCM), which provided the detailed requirements for the program. The Order also mandated Field Office issuance of site-specific radiological control manuals by December 1, 1992. This paper presents the approach taken to develop, review, approve, implement, and subsequently maintain the site-specific manual for the DOE Richland Field Office (RL) at Hanford Site

Nevada Test Site Environmental Report 2007

Energy Technology Data Exchange (ETDEWEB)

Cathy Wills

2008-09-01

The Nevada Test Site Environmental Report 2007 (NTSER) was prepared to meet the information needs of the public and the requirements and guidelines of the U.S. Department of Energy (DOE) for annual site environmental reports. It was prepared by National Security Technologies, LLC (NSTec). This Executive Summary presents the purpose of the document, the major programs conducted at the Nevada Test Site (NTS), NTS key environmental initiatives, radiological releases and potential doses to the public resulting from site operations, a summary of nonradiological releases, implementation status of the NTS Environmental Management System, a summary of compliance with environmental regulations, pollution prevention and waste minimization accomplishments, and significant environmental accomplishments. Much of the content of this Executive Summary is also presented in a separate stand-alone pamphlet titled Nevada Test Site Environmental Report Summary 2007. This NTSER was prepared to satisfy DOE Order 231.1A, Environment, Safety and Health Reporting. Its purpose is to (1) report compliance status with environmental standards and requirements, (2) present results of environmental monitoring of radiological and nonradiological effluents, (3) report estimated radiological doses to the public from releases of radioactive material, (4) summarize environmental incidents of noncompliance and actions taken in response to them, (5) describe the NTS Environmental Management System and characterize its performance, and (6) highlight significant environmental programs and efforts. This report meets these objectives for the NTS and three offsite Nevada facilities mentioned in this report.

Nevada Test Site Environmental Report 2007

International Nuclear Information System (INIS)

Cathy Wills

2008-01-01

The Nevada Test Site Environmental Report 2007 (NTSER) was prepared to meet the information needs of the public and the requirements and guidelines of the U.S. Department of Energy (DOE) for annual site environmental reports. It was prepared by National Security Technologies, LLC (NSTec). This Executive Summary presents the purpose of the document, the major programs conducted at the Nevada Test Site (NTS), NTS key environmental initiatives, radiological releases and potential doses to the public resulting from site operations, a summary of nonradiological releases, implementation status of the NTS Environmental Management System, a summary of compliance with environmental regulations, pollution prevention and waste minimization accomplishments, and significant environmental accomplishments. Much of the content of this Executive Summary is also presented in a separate stand-alone pamphlet titled Nevada Test Site Environmental Report Summary 2007. This NTSER was prepared to satisfy DOE Order 231.1A, Environment, Safety and Health Reporting. Its purpose is to (1) report compliance status with environmental standards and requirements, (2) present results of environmental monitoring of radiological and nonradiological effluents, (3) report estimated radiological doses to the public from releases of radioactive material, (4) summarize environmental incidents of noncompliance and actions taken in response to them, (5) describe the NTS Environmental Management System and characterize its performance, and (6) highlight significant environmental programs and efforts. This report meets these objectives for the NTS and three offsite Nevada facilities mentioned in this report

Radiological assessment of long-term effects at the Semipalatinsk test site. NATO-Semipalatinsk Project 1995/96

International Nuclear Information System (INIS)

Hill, P.; Hille, R.; Bouisset, P.; Calmet, D.; Kluson, J.; Smagulov, S.; Sysebaev, A.

1996-12-01

To determine the long-term consequences of atmospheric atomic bomb tests for the population in the surroundings of the former nuclear weapons test site near Semipalatinsk, studies were performed by international cooperation between Kazakh, French, Czech and German institutions at two measuring locations (Moistik, Maisk) in Kazakhstan. Moistik is a village close to Dolon and downwind of the first atomic bomb explosion on August 29, 1947. Maisk is close to Kurchatov and not too far from ground zero. With financial support from NATO, nine experts from Europe went on a field mission to Kazakhstan in September 1995 to assess, together with Kazakh scientists, the radiological situation as far as external doses, environmental contamination and body burden of man are concerned. The results show that surface contamination from nuclear weapons tests has in the meantime decayed to a large extent. External doses largely correspond to the natural background. The remaining incorporation of longer-lived radionuclides is also slight and in 1995 merely led to an annual dose of less than 1% of the natural radiation exposure for 137 Cs and 90 Sr. The question of a dose contribution by the possible incorporation of 239 Pu remains open. Life in the villages of Maisk and Moistik does not currently involve any radiological threat to the inhabitants. However, dose reconstruction for the older inhabitants directly affected by aboveground atomic weapons tests remains difficult. (orig.)

An aerial radiological survey of Areas 16 and 30, Nevada Test Site: Date of survey: June 1983

International Nuclear Information System (INIS)

Bluitt, C.M.

1986-10-01

An aerial radiological survey of the Nevada Test Site (NTS) was conducted for the US Department of Energy (DOE). The survey period was from 1 June to 16 June 1983, during which airborne measurements were obtained over Areas 16 and 30. The data were used to generate exposure rate, cobalt-60, and cesium-137 spatial distribution maps. The aerial survey results are expressed as exposure rate, cesium-137, and cobalt-60 isopleth contours, superimposed on NTS maps. 12 refs., 16 figs

Radiological design criteria for fusion power test facilities

International Nuclear Information System (INIS)

Singh, M.S.; Campbell, G.W.

1982-01-01

The quest for fusion power and understanding of plasma physics has resulted in planning, design, and construction of several major fusion power test facilities, based largely on magnetic and inertial confinement concepts. We have considered radiological design aspects of the Joint European Torus (JET), Livermore Mirror and Inertial Fusion projects, and Princeton Tokamak. Our analyses on radiological design criteria cover acceptable exposure levels at the site boundary, man-rem doses for plant personnel and population at large, based upon experience gained for the fission reactors, and on considerations of cost-benefit analyses

Nevada Test Site Environmental Report 2005

International Nuclear Information System (INIS)

Cathy A. Wills

2006-01-01

The Nevada Test Site Environmental Report 2005 (NTSER) was prepared to meet the information needs of the public and the requirements and guidelines of the U.S. Department of Energy (DOE) for annual site environmental reports. Its purpose is to (1) report compliance status with environmental standards and requirements, (2) present results of environmental monitoring of radiological and nonradiological effluents, (3) report estimated radiological doses to the public from releases of radioactive material, (4) summarize environmental incidents of noncompliance and actions taken in response to them, (5) describe the NTS Environmental Management System and characterize its performance, and (6) highlight significant environmental programs and efforts

Nevada Test Site Environmental Report 2005

Energy Technology Data Exchange (ETDEWEB)

Cathy A. Wills

2006-10-01

The Nevada Test Site Environmental Report 2005 (NTSER) was prepared to meet the information needs of the public and the requirements and guidelines of the U.S. Department of Energy (DOE) for annual site environmental reports. Its purpose is to (1) report compliance status with environmental standards and requirements, (2) present results of environmental monitoring of radiological and nonradiological effluents, (3) report estimated radiological doses to the public from releases of radioactive material, (4) summarize environmental incidents of noncompliance and actions taken in response to them, (5) describe the NTS Environmental Management System and characterize its performance, and (6) highlight significant environmental programs and efforts.

Work plan for the radiological survey for the David Witherspoon, Incorporated, Landfill-1630 site, Knoxville, Tennessee

International Nuclear Information System (INIS)

1996-07-01

This work plan establishes the methods and requirements for performing a radiological survey at the David Witherspoon, Incorporated, Landfill-1630 Site, Knoxville, Tennessee (DWI 1630 Site) in accordance with requirements under the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA). The radiological survey will identify the radiological contamination level of the equipment and debris stored at the DWI 1630 Site. The data generated from the survey activities will support the decisions for characterization of the equipment/debris and aid in subsequent disposition and waste handling. The survey activities to be performed under this work plan include an equipment radiological survey, a walkover survey, and an immunoassay testing for polychlorinated biphenyls (PCBs). This work plan includes a quality assurance (QA)/quality control (QC) project plan, a health and safety (H ampersand S) plan, and a waste management plan

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)

A web-based test of residents' skills in diagnostic radiology

International Nuclear Information System (INIS)

Finlay, K.; Norman, G.R.; Keane, D.R.; Stolberg, H.

2006-01-01

To develop an objective, Web-based tool for evaluating residents' knowledge of diagnostic radiology. We developed and tested a Web-based evaluation tool (the Diagnostic Radiology Skills Test) that consists of 3 tests, one in each of 3 domains of diagnostic radiology: chest, gastrointestinal, and musculoskeletal imaging. Each test comprises 30 cases representing a range of difficulty in the domain, including normal states, normal variants, typical cases of common diagnoses, and cases with more subtle findings. Cases are presented with a long menu of domain-specific possible diagnoses (response options), each coded for diagnostic appropriateness. Our subjects were 21 residents in postgraduate year (PGY) 2 to 5 and 11 experts in diagnostic radiology. Subjects accessed the tool via a Web site on our Web server. Residents test results were compared for reliability and validity across domain, case, and training level. In addition, results were correlated with commonly used established and objective evaluation tools. The tool demonstrated consistent monotonic improvement in performance with training level. It showed acceptable reliability in discriminating between residents at different performance levels, both within and across training levels (r = 0.53 within level and 0.69 across levels). Test results also had concurrent validity against the American College of Radiology In-Training Examination, a widely accepted objective assessment tool (r = 0.65, P < 0.01), and 2 Objective Structured Clinical Examinations (OSCEs) focusing on diagnostic skills (r = 0.78 and r 0.69, P < 0.01, respectively). Our study demonstrates the feasibility of a Web-based, standardized, objective assessment method for evaluating residents' performance. (author)

Site identification: environmental and radiological considerations

International Nuclear Information System (INIS)

Waite, D.A.

1980-01-01

Radiological and environmental considerations are recognized as being of utmost importance in planning, siting, licensing, operating, and decommissioning a high-level nuclear waste repository. In such a complex undertaking, it is important to identify the major concerns anticipated to arise in all of these phases in order to address them as early as possible in the program. Three representative activities/studies are summarized which will identify some of the important radiological and environmental considerations which must be addressed through this prolonged sequence of events and will indicate how these considerations are being addressed. It should be emphasized that these are only three of many which could have been chosen. The three key activities/studies are: (1) the NWTS Program criteria for identifying repository sites, (2) the generic guide for preparing environmental evaluations for deep drilling and (3) a preliminary environmental assessment for disposal of mined rock during excavation of a repository

Nevada Test Site Environmental Report 2009

Energy Technology Data Exchange (ETDEWEB)

Cathy Wills, ed.

2010-09-13

The Nevada Test Site Environmental Report 2009 was prepared to meet the information needs of the public and the requirements and guidelines of the U.S. Department of Energy (DOE) for annual site environmental reports. It was prepared by National Security Technologies, LLC (NSTec), for the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO). This and previous years’ Nevada Test Site Environmental Reports (NTSERs) are posted on the NNSA/NSO website at http://www.nv.doe.gov/library/publications/aser.aspx. This NTSER was prepared to satisfy DOE Order DOE O 231.1A, “Environment, Safety and Health Reporting.” Its purpose is to (1) report compliance status with environmental standards and requirements, (2) present results of environmental monitoring of radiological and nonradiological effluents, (3) report estimated radiological doses to the public from releases of radioactive material, (4) summarize environmental incidents of noncompliance and actions taken in response to them, (5) describe the NNSA/NSO Environmental Management System and characterize its performance, and (6) highlight significant environmental programs and efforts. This NTSER summarizes data and compliance status for calendar year 2009 at the Nevada Test Site (NTS) and its two support facilities, the North Las Vegas Facility (NLVF) and the Remote Sensing Laboratory (RSL)-Nellis. It also addresses environmental restoration (ER) projects conducted at the Tonopah Test Range (TTR). Through a Memorandum of Agreement, NNSA/NSO is responsible for the oversight of TTR ER projects, and the Sandia Site Office of NNSA (NNSA/SSO) has oversight of all other TTR activities. NNSA/SSO produces the TTR annual environmental report available at http://www.sandia.gov/news/publications/environmental/index.html.

Nevada Test Site annual site environmental report, 1989

Energy Technology Data Exchange (ETDEWEB)

Wruble, D T; McDowell, E M [eds.

1990-11-01

Prior to 1989 annual reports of environmental monitoring and assessment results for the Nevada Test Site (NTS) were prepared in two separate parts. Onsite effluent monitoring and environmental monitoring results were reported in an onsite report prepared by the US Department of Energy, Nevada Operations Office (DOE/NV). Results of the offsite radiological surveillance program conducted by the US Environmental Protection Agency (EPA), Environmental Monitoring Systems Laboratory, Las Vegas, Nevada, were reported separately by that Agency. Beginning with this 1989 annual Site environmental report for the NTS, these two documents are being combined into a single report to provide a more comprehensive annual documentation of the environmental protection program conducted for the nuclear testing program and other nuclear and non-nuclear activities at the Site. The two agencies have coordinated preparation of this combined onsite and offsite report through sharing of information on environmental releases and meteorological, hydrological, and other supporting data used in dose-estimate calculations. 57 refs., 52 figs., 65 tabs.

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

Nevada Test Site Environmental Report 2006 and Site Description (Volume 1)

Energy Technology Data Exchange (ETDEWEB)

Cathy Wills

2007-10-01

The Nevada Test Site Environmental Report 2006 (NTSER) was prepared to meet the information needs of the public and the requirements and guidelines of the U.S. Department of Energy (DOE) for annual site environmental reports. It was prepared by National Security Technologies, LLC (NSTec). This Executive Summary presents the purpose of the document, the major programs conducted at the Nevada Test Site (NTS), NTS key environmental initiatives, radiological releases and potential doses to the public resulting from site operations, a summary of nonradiological releases, implementation status of the NTS Environmental Management System, a summary of compliance with environmental regulations, pollution prevention and waste minimization accomplishments, and significant environmental accomplishments. Much of the content of this Executive Summary is also presented in a separate stand-alone pamphlet titled Nevada Test Site Environmental Report Summary 2006 produced to be a more cost-effective means of distributing information contained in the NTSER to interested DOE stakeholders.

Nevada Test Site Environmental Report 2006 and Site Description (Volume 1)

International Nuclear Information System (INIS)

Cathy Wills

2007-01-01

The Nevada Test Site Environmental Report 2006 (NTSER) was prepared to meet the information needs of the public and the requirements and guidelines of the U.S. Department of Energy (DOE) for annual site environmental reports. It was prepared by National Security Technologies, LLC (NSTec). This Executive Summary presents the purpose of the document, the major programs conducted at the Nevada Test Site (NTS), NTS key environmental initiatives, radiological releases and potential doses to the public resulting from site operations, a summary of nonradiological releases, implementation status of the NTS Environmental Management System, a summary of compliance with environmental regulations, pollution prevention and waste minimization accomplishments, and significant environmental accomplishments. Much of the content of this Executive Summary is also presented in a separate stand-alone pamphlet titled Nevada Test Site Environmental Report Summary 2006 produced to be a more cost-effective means of distributing information contained in the NTSER to interested DOE stakeholders

Radiological effluent and onsite area monitoring report for the Nevada Test Site (January 1986-December 1986)

International Nuclear Information System (INIS)

Gonzalez, D.A.

1987-09-01

This report documents the environmental surveillance program at the Nevada Test Site as conducted by the Department of Energy (DOE) onsite radiological safety contractor from January 1986 through December 1986. It presents results and evaluations of radioactivity measurements in air and water, and of direct gamma radiation exposure rates. It establishes relevant correlations between the data recorded and DOE concentration guides (CG's). External gamma exposure levels and radioactivity in air and water on the Nevada Test Site were low compared to DOE guidelines. The highest average gross beta concentration in air was 0.005% of the DOE concentration guide (CG). The highest average Pu-239 concentration was 7.7% of the standard. The highest average tritium concentration was 0.39% of the standard. Kr-85 concentrations increased slightly from CY-1985 to CY-1986. Xe-133 remained nondetectable with some exceptions. The highest average gross beta concentration in potable water remained within the applicable standard for drinking water. The highest average Pu-239 concentration from contaminated waters was 0.0005% of the concentration guide. The highest average tritium concentration in noncontaminated water was 6% of the level for drinking water required by the National Interim Primary Drinking Water Regulation. The amounts of tritium-bearing effluent released to contaminated waste ponds was calculated and reported to DOE Headquarters. Gamma radiation measurements were roughly the same in CY-1986 relative to the previous year. All surveillance results from the Radioactive Waste Management Site (RWMS) indicate that no detectable releases of radioactive materials occurred in that network in 1986. 29 refs., 14 figs., 23 tabs

Corrective Action Investigation Plan for Corrective Action Unit 104: Area 7 Yucca Flat Atmospheric Test Sites, Nevada National Security Site, Nevada, Revision 0

Energy Technology Data Exchange (ETDEWEB)

Patrick Matthews

2011-08-01

CAU 104 comprises the 15 CASs listed below: (1) 07-23-03, Atmospheric Test Site T-7C; (2) 07-23-04, Atmospheric Test Site T7-1; (3) 07-23-05, Atmospheric Test Site; (4) 07-23-06, Atmospheric Test Site T7-5a; (5) 07-23-07, Atmospheric Test Site - Dog (T-S); (6) 07-23-08, Atmospheric Test Site - Baker (T-S); (7) 07-23-09, Atmospheric Test Site - Charlie (T-S); (8) 07-23-10, Atmospheric Test Site - Dixie; (9) 07-23-11, Atmospheric Test Site - Dixie; (10) 07-23-12, Atmospheric Test Site - Charlie (Bus); (11) 07-23-13, Atmospheric Test Site - Baker (Buster); (12) 07-23-14, Atmospheric Test Site - Ruth; (13) 07-23-15, Atmospheric Test Site T7-4; (14) 07-23-16, Atmospheric Test Site B7-b; (15) 07-23-17, Atmospheric Test Site - Climax These sites are being investigated because existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend corrective action alternatives (CAAs). Additional information will be obtained by conducting a corrective action investigation before evaluating CAAs and selecting the appropriate corrective action for each CAS. The results of the field investigation will support a defensible evaluation of viable CAAs that will be presented in the Corrective Action Decision Document. The sites will be investigated based on the data quality objectives (DQOs) developed on April 28, 2011, by representatives of the Nevada Division of Environmental Protection and the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office. The DQO process was used to identify and define the type, amount, and quality of data needed to develop and evaluate appropriate corrective actions for CAU 104. The releases at CAU 104 consist of surface-deposited radionuclides from 30 atmospheric nuclear tests. The presence and nature of contamination at CAU 104 will be evaluated based on information collected from a field investigation. Radiological contamination will be evaluated based on a comparison

Some issues on radiological consequences analysis in site selection for nuclear power stations

International Nuclear Information System (INIS)

Chen Xiaoqiu; Yue Huiguo

2006-01-01

The three considerations, Site safety and environmental protection and emergency preparedness, are the focus of attention in the evaluation of the suitability of a site for nuclear power station. This paper summarized the basic regulatory requirements for the siting of nuclear power station, described the existing problems on radiological consequences analyses during the siting stage and discussed the is- sues that need to concern in the reviewing of the radiological consequences analyses in the siting appraisal stage. (authors)

The protection of on-site personnel in the event of a radiological accident

International Nuclear Information System (INIS)

Morrey, M.; Simister, D.N.

2003-01-01

The National Radiological Protection Board (NPRB) is responsible in the UK for advising Government and other responsible bodies on the principles for responding to radiological emergencies. NRPB has published appropriate advice on the off-site protection of the public and on the protection of workers involved in taking mitigating actions to reduce the exposure of others. This paper puts forward a suggested framework for the protection of on-site personnel in the event of a radiological emergency which might include a criticality accident. This framework both dovetails with existing planning for the protection of members of the public off-site, and also takes account of specific differences between the situations on and off-site. (author)

Routine Radiological Environmental Monitoring Plan

International Nuclear Information System (INIS)

Bechtel Nevada

1998-01-01

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

Site-specific analysis of radiological and physical parameters for cobbly soils at the Gunnison, Colorado, processing site

International Nuclear Information System (INIS)

1993-10-01

The remedial action at the Gunnison, Colorado, processing site is being performed under the Uranium Mill Tailings Radiation Control Act (UMTRCA) of 1978 [Public Law (PL) 95-6041]. Under UMTRCA, the US Environmental Protection Agency (EPA) is charged with the responsibility of developing appropriate and applicable standards for the cleanup of radiologically contaminated land and buildings at 24 designated sites, including the Gunnison, Colorado, inactive processing site. The remedial action at the processing site will be conducted to remove the tailings and contaminated materials to meet the EPA bulk soil cleanup standards for surface and subsurface soils. The site areas disturbed by remedial action excavation will be either contoured or backfilled with radiologically uncontaminated soil and contoured to restore the site. The final contours will produce a final surface grade that will create positive drainage from the site

Radioactive contamination of former Semipalatinsk test site area

International Nuclear Information System (INIS)

Artem'ev, O.I.; Akhmetov, M.A.; Ptitskaya, L.D.

2001-01-01

The nuclear weapon infrastructure elimination activities and related surveys of radioactive contamination are virtually accomplished at the Semipalatinsk test site (STS). The radioecological surveys accompanied closure of tunnels which were used for underground nuclear testing at Degelen technical field and elimination of intercontinental ballistic missile silo launchers at Balapan technical field. At the same time a ground-based route survey was carried out at the Experimental Field where aboveground tests were conducted and a ground-based area survey was performed in the south of the test site where there are permanent and temporary inhabited settlements. People dwelling these settlements are mainly farmers. The paper presents basic results of radiological work conducted in the course of elimination activities. (author)

Population dose near the Semipalatinsk test site.

Science.gov (United States)

Hille, R; Hill, P; Bouisset, P; Calmet, D; Kluson, J; Seisebaev, A; Smagulov, S

1998-10-01

To determine the consequences of atmospheric atomic bomb tests for the population in the surroundings of the former nuclear weapons test site near Semipalatinsk in Kazakhstan, a pilot study was performed by an international cooperation between Kazakh, French, Czech and German institutions at two villages, Mostik and Maisk. Together with Kazakh scientists, eight experts from Europe carried out a field mission in September 1995 to assess, within the framework of a NATO supported project, the radiological situation as far as external doses, environmental contamination and body burden of man were concerned. A summary of the results obtained is presented. The actual radiological situation near the test site is characterized by fallout contaminations. Cs was found in upper soil layers in concentrations similar to those of the global fallout. Also Sr, Am and Co were observed. The resulting present dose to the population is low. Mean external doses from soil contamination for Maisk and Mostik (0.60-0.63 mSv/year) presently correspond to mean external doses in normal environments. Mean values of the annual internal doses observed in these two villages are below 2 microSv/year for 90Sr. For other radionuclides the internal doses are also negligible.

Population dose near the Semipalatinsk test site

International Nuclear Information System (INIS)

Hille, R.; Hill, P.; Kluson, J.; Seisebaev, A.; Smagulov, S.

1998-01-01

To determine the consequences of atmospheric atomic bomb tests for the population in the surroundings of the former nuclear weapons test site near Semipalatinsk in Kazakhstan, a pilot study was performed by an international cooperation between Kazakh, French, Czech and German institutions at two villages, Mostik and Maisk. Together with Kazakh scientists, eight experts from Europe carried out a field mission in September 1995 to assess, within the framework of a NATO supported project, the radiological situation as far as external doses, environmental contamination and body burden of man were concerned. A summary of the results obtained is presented. The actual radiological situation near the test site is characterized by fallout contaminations. Cs was found in upper soil layers in concentrations similar to those of the global fallout. Also Sr, Am and Co were observed. The resulting present dose to the population is low. Mean external doses from soil contamination for Maisk and Mostik (0.60-0.63 mSv/ year) presently correspond to mean external doses in normal environments. Mean values of the annual internal doses observed in these two villages are below 2 μSv/year for 90 Sr. For other radionuclides the internal doses are also negligible. (orig.)

Finding and evaluating potential radiological problems in the vicinity of uranium milling sites

International Nuclear Information System (INIS)

Goldsmith, W.A.; Yates, W.G.

1982-01-01

The Oak Ridge National Laboratory (ORNL) has been performing radiological surveys at former uranium and thorium milling and processing sites since 1975. Tailings at inactive milling sites usually have a low frequency of human occupancy but continuously generate 222 Rn into the atmosphere. Thus, independent 222 Rn surveys are conducted at the inactive mill sites and their environs by the Mound Facility. Measurements of airborne 222 Rn and 222 Rn flux are made on the sites to define the tailings source term. Concurrently with these measurements, an ambient 222 Rn monitoring network is established off-site and a meteorological station is established at or near the mill site. Unfortunately, tailings are not always confined to the milling site. Radioactivity can migrate to areas outside of site boundaries by wind and water erosion, groundwater transport, spillage of incoming ore, and removal of tailings or other material for private purposes. In order to identify and assess off-site radioactivity on properties in the vicinity of milling sites, a combination of aerial and ground-level radiological monitoring techniques are used. The ground mobile gamma-ray scan is conducted using a vehicle equipped with sensitive gamma-ray detectors. The detectors are shielded so that gamma radiation input is viewed through only one side of the vehicle. This system is capable of precisely locating properties which have anomalously high gamma radiation levels caused by the presence of tailings. Subsequently, these properties are identified as candidate vicinity properties and are scheduled for radiological surveys subject to the property owner's consent. The comprehensive radiological surveys conducted at these vicinity properties determine the amount, type, and location of tailings materials

Radiological risk assessment for radioactive contamination at landfill site

International Nuclear Information System (INIS)

Devgun, J.S.

1990-01-01

A limited-scope preliminary assessment of radiological risk has been conducted for a landfill site where radioactive residues resulting from past uranium ore processing operations are present. Potential radiation doses to an individual under different scenarios have been predicted using the RESRAD computer code. The assessment provides useful input to the remedial action planning for the site that is currently underway. 7 refs., 6 figs., 3 tabs

Site-specific analysis of radiological and physical parameters for cobbly soils at the Gunnison, Colorado, processing site

International Nuclear Information System (INIS)

1994-01-01

The remedial action at the Gunnison, Colorado, processing site is being performed under the Uranium Mill Tailings Radiation Control Act (UMTRCA) of 1978. Under UMTRCA, the US Environmental Protection Agency (EPA) is charged with the responsibility of developing appropriate and applicable standards for the cleanup of radiologically contaminated land and buildings at 24 designated sites, including the Gunnison, Colorado, inactive processing site. Section 108 of Public Law 95-604 states that the US Department of Energy (DOE) shall ''select and perform remedial actions at the designated processing sites and disposal sites in accordance with the general standards'' prescribed by the EPA. Regulations governing the required remedial action at inactive uranium processing sites were promulgated by the EPA in 1983 and are contained in 40 CFR Part 192 (1993), Health and Environmental Protection Standards for Uranium and Thorium Mill Tailings. This document describes the radiological and physical parameters for the remedial action of the soil

Present radiological situation at the Semipalatinsk nuclear test site

International Nuclear Information System (INIS)

Stegar, P.

1996-01-01

The corroboration of environmental contamination levels obtained by independent equipment and measurements of the team was generally good, the best being with recent Russian and Kazakh data using gamma dose rate measurements. Acceptable corroboration was observed for gamma emitting radionuclides in food and environmental samples. The preliminary results on plutonium levels in soil samples from contaminated sites in the polygon showed values comparable with the data reported by Russian scientists.The major sites selected for field work by the team were the settlements around the polygon of Kainar(population of about 10,000) in the south, Sharzhal (2000) and Karaul (5000) in the east, and Dolon (2000 just north of the Irtysh. Akzhar, within the polygon just south of the river, was used as a reference site. Inside the polygon the efforts were concentrated in the Lake Balapan area including the semipermanent farm around Ground Zero, and a selection of sampling sites along the plume paths of atmospheric and above ground explosions. The operations carried out in the field included: gamma dose rate measurements; in situ gamma spectrometry; and the collection of samples of grass, meat, milk, offal, vegetables and soil, as well as biological indicators such as animal bones, mushrooms and moss. The levels of contamination in the soil at the locations specified are shown. The contamination by ' S r in milk, drinking water and the lake water was also measured, together with results for 137 Cs in meat. The external gamma dose rates in settlements and in the polygon, excluding the Lake Balapan and Ground Zero areas, were around 0.1 uGy per hour, against rates of up to 40 uGy per hour around Lake Balapan and Ground Zero. The dose assessment included consideration of all relevant pathways, of which the most important were external gamma exposure from material on or in the ground, inhalation of material resuspended from the ground and consumption of contaminated foods. These

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

Energy Technology Data Exchange (ETDEWEB)

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

2010-05-25

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

Summary of data concerning radiological contamination at well PM-2, Nevada Test Site, Nye County, Nevada

International Nuclear Information System (INIS)

Russell, G.M.; Locke, G.L.

1997-01-01

Analysis of water from well Pahute Mesa No. 2 (PM-2), on Pahute Mesa in the extreme northwestern part of the Nevada Test Site, indicated tritium concentrations above background levels in August 1993. A coordinated investigation of the tritium occurrence in well PM-2 was undertaken by the Hydrologic Resources Management Program of the US Department of Energy. Geologic and hydrologic properties of the hydrogeologic units were characterized using existing information. Soil around the well and water quality in the well were characterized during the investigation. The purpose of this report is to present existing information and results from a coordinated investigation of tritium occurrence. The objectives of the overall investigation include: (1) determination of the type and concentration of contamination; (2) identification of the source and mechanism of contamination; (3) estimation of the extent of radiological contamination; (4) initiation of appropriate monitoring of the contamination; and (5) reporting of investigation results. Compiled and tabulated data of the area are presented. The report also includes characterization of geology, soil, hydrology, and water quality data

Radiological/toxicological sabotage assessments at the Savannah River Site

International Nuclear Information System (INIS)

Johnson, H.D.; Pascal, M.D.; Richardson, D.L.

1995-01-01

This paper describes the methods being employed by Westinghouse Savannah River Company (WSRC) to perform graded assessments of radiological and toxicological sabotage vulnerability at Savannah River Site (SRS) facilities. These assessments are conducted to ensure that effective measures are in place to prevent, mitigate, and respond to a potential sabotage event which may cause an airborne release of radiological/toxicological material, causing an adverse effect on the health and safety of employees, the public, and the environment. Department of Energy (DOE) Notice 5630.3A, open-quotes Protection of Departmental Facilities Against Radiological and Toxicological Sabotage,close quotes and the associated April 1993 DOE-Headquarters guidance provide the requirements and outline an eight-step process for hazardous material evaluation. The process requires the integration of information from a variety of disciplines, including safety, safeguards and security, and emergency preparedness. This paper summarizes WSRC's approach towards implementation of the DOE requirements, and explains the inter-relationships between the Radiological and Toxicological Assessments developed using this process, and facility Hazard Assessment Reports (HAs), Safety Analysis Reports (SARs), and Facility Vulnerability Assessments (VAs)

Routine Radiological Environmental Monitoring Plan. Volume 1

Energy Technology Data Exchange (ETDEWEB)

Bechtel Nevada

1999-12-31

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

Topographical mapping system for radiological and hazardous environments acceptance testing

International Nuclear Information System (INIS)

Armstrong, G.A.; Dochat, G.R.

1997-01-01

During the summer of 1996, the Topographical Mapping System (TMS) for hazardous and radiological environments and its accompanying three-dimensional (3-D) visualization tool, the Interactive Computer-Enhanced Remote-Viewing System (ICERVS), were delivered to Oak Ridge National Laboratory (ORNL). ORNL and Mechanical Technology, Inc., performed final acceptance testing of the TMS during the next eight months. The TMS was calibrated and characterized during this period. This paper covers the calibration, characterization, and acceptance testing of the TMS. Development of the TMS and ICERVS was initiated by the US Department of Energy (DOE) for the purpose of characterization and remediation of underground storage tanks (USTs) at DOE sites across the country. DOE required a 3-D, topographical mapping system suitable for use in hazardous and radiological environments. The intended application is the mapping of the interior of USTs as part of DOE's waste characterization and remediation efforts and to obtain baseline data on the content of the storage tank interiors as well as data on changes in the tank contents and levels brought about by waste remediation steps. Initially targeted for deployment at the Hanford Washington site, the TMS is designed to be a self-contained, compact, and reconfigurable system that is capable of providing rapid, variable-resolution mapping information in poorly characterized workspaces with a minimum of operator intervention

Topographical mapping system for radiological and hazardous environments acceptance testing

Science.gov (United States)

Armstrong, Gary A.; Dochat, G. R.

1997-09-01

During the summer of 1996, the topographical mapping system (TMS) for hazardous and radiological environments and its accompanying three-dimensional (3-D) visualization tool, the interactive computer-enhanced remote-viewing system (ICERVS), were delivered to Oak Ridge National Laboratory (ORNL). ORNL and Mechanical Technology, Inc., performed final acceptance testing of the TMS during the next eight months. The TMS was calibrated and characterized during this period. This paper covers the calibration, characterization, and acceptance testing of the TMS. Development of the TMS and the ICERVS was initiated by the U.S. Department of Energy (DOE) for the purpose of characterization and remediation of underground storage tanks (USTs) at DOE sites across the country. DOE required a 3-D, topographical mapping system suitable for use in hazardous and radiological environments. The intended application is the mapping of the interior of USTs as part of DOE's waste characterization and remediation efforts and to obtain baseline data on the content of the storage tank interiors as well as data on changes in the tank contents and levels brought about by waste remediation steps. Initially targeted for deployment at the Hanford Washington site, the TMS is designed to be a self-contained, compact, reconfigurable system that is capable of providing rapid, variable-resolution mapping information in poorly characterized workspaces with a minimum of operator intervention.

Public transparency Web sites for radiology practices: prevalence of price, clinical quality, and service quality information.

Science.gov (United States)

Rosenkrantz, Andrew B; Doshi, Ankur M

2016-01-01

To assess information regarding radiology practices on public transparency Web sites. Eight Web sites comparing radiology centers' price and quality were identified. Web site content was assessed. Six of eight Web sites reported examination prices. Other reported information included hours of operation (4/8), patient satisfaction (2/8), American College of Radiology (ACR) accreditation (3/8), on-site radiologists (2/8), as well as parking, accessibility, waiting area amenities, same/next-day reports, mammography follow-up rates, examination appropriateness, radiation dose, fellowship-trained radiologists, and advanced technologies (1/8 each). Transparency Web sites had a preponderance of price (and to a lesser extent service quality) information, risking fostering price-based competition at the expense of clinical quality. Copyright © 2016 Elsevier Inc. All rights reserved.

Fruit and vegetable radioactivity survey, Nevada Test Site environs

International Nuclear Information System (INIS)

Andrews, V.E.; Vandervort, J.C.

1978-04-01

During the 1974 growing season, the Environmental Monitoring and Support Laboratory-Las Vegas, of the U.S. Environmental Protection Agency, collected samples of fruits and vegetables grown in the off-site area surrounding the Nevada Test Site. The objective was to estimate the potential radiological dose to off-site residents from consumption of locally grown foodstuffs. Irrigation water and soil were collected from the gardens and orchards sampled. Soil concentrations of cesium-137 and plutonium-239 reflected the effects of close-in fallout from nuclear testing at the Nevada Test Site. The only radionuclide measured in fruit and vegetable samples which might be related to such fallout was strontium-90, for which the first year estimated dose to bone marrow of an adult with an assumed rate of consumption of the food would be 0.14 millirad

Environmental assessment of SP-100 ground engineering system test site: Hanford Site, Richland, Washington

Energy Technology Data Exchange (ETDEWEB)

1988-12-01

The US Department of Energy (DOE) proposes to modify an existing reactor containment building (decommissioned Plutonium Recycle Test Reactor (PRTR) 309 Building) to provide ground test capability for the prototype SP-100 reactor. The 309 Building (Figure 1.1) is located in the 300 Area on the Hanford Site in Washington State. The National Environmental Policy Act (NEPA) requires that Federal agencies assess the potential impacts that their actions may have on the environment. This Environmental Assessment describes the consideration given to environmental impacts during reactor concept and test site selection, examines the environmental effects of the DOE proposal to ground test the nuclear subsystem, describes alternatives to the proposed action, and examines radiological risks of potential SP-100 use in space. 73 refs., 19 figs., 7 tabs.

Automated radiological monitoring at a Russian Ministry of Defence Naval Site

International Nuclear Information System (INIS)

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

2001-01-01

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

CLOSURE REPORT FOR CORRECTIVE ACTION UNIT 115: AREA 25 TEST CELL A FACILITY, NEVADA TEST SITE, NEVADA

International Nuclear Information System (INIS)

2006-01-01

This Closure Report (CR) describes the activities performed to close CAU 115, Area 25 Test Cell A Facility, as presented in the NDEP-approved SAFER Plan (NNSA/NSO, 2004). The SAFER Plan includes a summary of the site history, process knowledge, and closure standards. This CR provides a summary of the completed closure activities, documentation of waste disposal, and analytical and radiological data to confirm that the remediation goals were met and to document final site conditions. The approved closure alternative as presented in the SAFER Plan for CAU 115 (NNSA/NSO, 2004) was clean closure; however, closure in place was implemented under a Record of Technical Change (ROTC) to the SAFER Plan when radiological surveys indicated that the concrete reactor pad was radiologically activated and could not be decontaminated to meet free release levels. The ROTC is included as Appendix G of this report. The objectives of closure were to remove any trapped residual liquids and gases, dispose regulated and hazardous waste, decontaminate removable radiological contamination, demolish and dispose aboveground structures, remove the dewar as a best management practice (BMP), and characterize and restrict access to all remaining radiological contamination. Radiological contaminants of concern (COCs) included cobalt-60, cesium-137, strontium-90, uranium-234/235/236/238, and plutonium-239/240. Additional COCs included Resource Conservation and Recovery Act (RCRA) metals, polychlorinated biphenyls (PCBs), and asbestos

SITE GENERATED RADIOLOGICAL WASTE HANDLING SYSTEM DESCRIPTION DOCUMENT

Energy Technology Data Exchange (ETDEWEB)

S. C. Khamankar

2000-06-20

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

SITE GENERATED RADIOLOGICAL WASTE HANDLING SYSTEM DESCRIPTION DOCUMENT

International Nuclear Information System (INIS)

S. C. Khamankar

2000-01-01

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

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

Off-site response for radiological emergencies

International Nuclear Information System (INIS)

Eldridge, J.S.; Oakes, T.W.; Hubbard, H.M.; Hibbitts, H.W.

1982-01-01

Environmental radiological surveillance under emergency conditions at off-site locations is one of the advisory functions provided by DOE within the ORO jurisdiction. The Department of Environmental Management of ORNL has been requested to provide sampling and analytical assistance at such emergency response activities. We have assembled and identified specific individuals and equipment to provide a rapid response force to perform field measurements for environmental radioactivity releases as a consequence of nuclear accidents. Survey teams for sample collection and field measurements are provided along with analytical assistance to operate the radioactivity measuring equipment in the DOE emergency van

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

Radiological tests versus pathological diagnostics: Complimentary or antagonistic relationship? The experience of a tertiary hospital

Directory of Open Access Journals (Sweden)

Maria A Arafah

2017-01-01

Full Text Available Introduction: Early detection of breast cancer plays a pivotal role in the outcome of the disease. Diagnostic modalities encompass radiological and pathological findings. The aim of this study is to evaluate the correlation between the results of these two modalities in a tertiary hospital. Materials and Methods: From a total of 180 patients, 203 ultrasound-guided breast core needle biopsies (US-CNBs were included in this study over a period of a year (May 2015 - May 2016. All clinical parameters, the site of the biopsy, the size of the needle, the radiological findings, the pathological diagnoses as well as all available follow-up data were reviewed. The concordance between the radiological and pathological results was studied and a statistical analysis conforms to the Pearson Chi-square test was applied. Results: The majority of our patients were above 40 years of age. A strong and statistically significant association was noted between radiological findings and histopathological results (Pearson's Chi-square test = 186.28, P ≤ 0.0001 with only four discordant cases (1.97%. This discrepancy was not statistically associated with age, site of biopsy, needle size, or number of cores obtained (P = 0.621, P = 0.584, P = 0.786, and P = 0.478, respectively. Conclusions: US-CNB is an accurate method in the diagnosis of breast lesions. Radiological and pathological correlation is of utmost importance in relation to patient's care and to reduce false rates. Follow-up of concordant benign lesions is essential. In addition, the importance of a multidisciplinary breast conference during which input from all teams caring for the patient is strongly emphasized.

Volumetric CT-images improve testing of radiological image interpretation skills

Energy Technology Data Exchange (ETDEWEB)

Ravesloot, Cécile J., E-mail: C.J.Ravesloot@umcutrecht.nl [Radiology Department at University Medical Center Utrecht, Heidelberglaan 100, 3508 GA Utrecht, Room E01.132 (Netherlands); Schaaf, Marieke F. van der, E-mail: M.F.vanderSchaaf@uu.nl [Department of Pedagogical and Educational Sciences at Utrecht University, Heidelberglaan 1, 3584 CS Utrecht (Netherlands); Schaik, Jan P.J. van, E-mail: J.P.J.vanSchaik@umcutrecht.nl [Radiology Department at University Medical Center Utrecht, Heidelberglaan 100, 3508 GA Utrecht, Room E01.132 (Netherlands); Cate, Olle Th.J. ten, E-mail: T.J.tenCate@umcutrecht.nl [Center for Research and Development of Education at University Medical Center Utrecht, Heidelberglaan 100, 3508 GA Utrecht (Netherlands); Gijp, Anouk van der, E-mail: A.vanderGijp-2@umcutrecht.nl [Radiology Department at University Medical Center Utrecht, Heidelberglaan 100, 3508 GA Utrecht, Room E01.132 (Netherlands); Mol, Christian P., E-mail: C.Mol@umcutrecht.nl [Image Sciences Institute at University Medical Center Utrecht, Heidelberglaan 100, 3508 GA Utrecht (Netherlands); Vincken, Koen L., E-mail: K.Vincken@umcutrecht.nl [Image Sciences Institute at University Medical Center Utrecht, Heidelberglaan 100, 3508 GA Utrecht (Netherlands)

2015-05-15

Rationale and objectives: Current radiology practice increasingly involves interpretation of volumetric data sets. In contrast, most radiology tests still contain only 2D images. We introduced a new testing tool that allows for stack viewing of volumetric images in our undergraduate radiology program. We hypothesized that tests with volumetric CT-images enhance test quality, in comparison with traditional completely 2D image-based tests, because they might better reflect required skills for clinical practice. Materials and methods: Two groups of medical students (n = 139; n = 143), trained with 2D and volumetric CT-images, took a digital radiology test in two versions (A and B), each containing both 2D and volumetric CT-image questions. In a questionnaire, they were asked to comment on the representativeness for clinical practice, difficulty and user-friendliness of the test questions and testing program. Students’ test scores and reliabilities, measured with Cronbach's alpha, of 2D and volumetric CT-image tests were compared. Results: Estimated reliabilities (Cronbach's alphas) were higher for volumetric CT-image scores (version A: .51 and version B: .54), than for 2D CT-image scores (version A: .24 and version B: .37). Participants found volumetric CT-image tests more representative of clinical practice, and considered them to be less difficult than volumetric CT-image questions. However, in one version (A), volumetric CT-image scores (M 80.9, SD 14.8) were significantly lower than 2D CT-image scores (M 88.4, SD 10.4) (p < .001). The volumetric CT-image testing program was considered user-friendly. Conclusion: This study shows that volumetric image questions can be successfully integrated in students’ radiology testing. Results suggests that the inclusion of volumetric CT-images might improve the quality of radiology tests by positively impacting perceived representativeness for clinical practice and increasing reliability of the test.

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

Energy Technology Data Exchange (ETDEWEB)

Houser, M.R.

1996-02-01

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

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

International Nuclear Information System (INIS)

Houser, M.R.

1996-02-01

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

Nevada Test Site annual site environmental report for calendar year 1998

International Nuclear Information System (INIS)

Black, S.C.; Townsend, Y.E.

1999-01-01

Prior to 1989, annual reports of environmental monitoring and assessment results for the Nevada Test Site (NTS) were prepared in two separate parts. Onsite effluent monitoring and environmental monitoring results were reported in an onsite report prepared by the US Department of Energy, Nevada Operations Office (DOE/NV). Results of the Offsite Radiological Surveillance and Long-Term Hydrological Monitoring Programs conducted by the US Environmental Protection Agency's (EPA) Laboratory (various names) in Las Vegas, Nevada, were reported separately by that Agency. Beginning with the 1989 Annual Site Environmental Report for the NTS, these two documents were combined into a single report to provide a more comprehensive annual documentation of the environmental protection activities conducted for the nuclear testing program and other nuclear and non-nuclear operations at the NTS. The two agencies have coordinated preparation of this tenth combined onsite and offsite report through sharing of information on environmental surveillance and releases as well as meteorological, hydrological, and other supporting data used in dose-estimation calculations

Perspectives of investigation and development of Semipalatinsk Test Site

International Nuclear Information System (INIS)

Kadyrzhanov, K.K.; Lukashenko, S.N.

2008-01-01

Full text: Since the Semipalatinsk Test Site has been stopped and up until now, National Nuclear Center of the Republic of Kazakhstan (NNC RK) in cooperation with other specialist from Kazakhstan and international scientific community have accumulated large scope of information about current radiological situation at Semipalatinsk Nuclear Test Site (SNTS) and adjacent territories. There were revealed all important spots of radioactive contamination, identified main pathways and mechanisms for present and potential proliferation of radioactive substances. Obtained data assure us that present-day SNTS provides no negative impact on population on adjacent to the Site territories excluding people in the water basin of the river Shagan. Compliance with regulatory requirements and special rules for SNTS territory assures radiation safety at commercial activities on the Site. At the same time, the radiological situation does not remain stable; there were revealed the processes of radionuclide migration what requires regular monitoring of radiological situation at SNTS. Taking into account the scale of the Site and the variety of tests performed there, the information available about SNTS can not be completely exhaustive but enables us to propose a scientifically grounded plan for further research and practical measures aimed at remediation and reclamation of lands. implementation of such measures should return up to 80% of the lands to commercial use. SNTS is one of the world largest nuclear test sites with decisive contribution to creation and development of nuclear weapon. To considerable extent, these were works at SNTS which established nuclear parity between the superpowers one of the crucial factors in the history of human civilization in the 20 century. Also taking into account the interest to SNTS paid by international organizations, it is reasonable to initiate a procedure and recognize SNTS as a landmark including it in the UNESCO List of Cultural and Nature

Cleanup Summary Report for the Defense Threat Reduction Agency Fiscal Year 2007, Task 6.7, U12u-Tunnel (Legacy Site), Nevada Test Site, Nevada

International Nuclear Information System (INIS)

2008-01-01

This letter serves as notice of completion for cleanup of the U12u-Tunnel (Legacy Site) as specified in the Defense Threat Reduction Agency (DTRA) Fiscal Year 2007 Statement of Work, Task 6.7. The U12u-Tunnel Legacy Site is located near the intersection of the U12u-Tunnel access road and the U12n-Tunnel access road in Area 12 of the Nevada Test Site (see Figure 1). The site encompasses 1.2 acres and was used to store miscellaneous mining equipment and materials that were used to support DTRA testing in Area 12. Field activities commenced February 11, 2008, and were completed February 20, 2008. Radiological surveys were performed on a drill jumbo and all material stored at the site. The drill jumbo was relocated to U12p-Tunnel portal and consolidated with other critical mining equipment for future use or storage. Ten truck loads of solid waste (53 tons) were shipped to the Nevada Test Site, Area 9 U10c Sanitary Landfill for disposal. No hazardous or radiological waste was generated at this site

Preliminary radiological readings on the old uraniferous mining site of Rophin (Puy-de-Dome)

International Nuclear Information System (INIS)

Chareyron, Bruno

2012-01-01

After a presentation of the site, of the objectives, limits and methodology of the measurement campaign, this document reports and comments the radiological measurements performed by the CRIIRAD on the old uranium mining site of Rophin and its surroundings (gamma radiation). It comments measurements performed 1 meter above the ground and on soils, and anomalies clearly related to past industrial activities. It comments the results of a radiological analysis performed on released waters (uranium 238, radon 222), and on sediments and soils

Formerly utilized MED/AEC sites remedial action program. Radiological survey of the former Watertown arsenal property, Site 34 and Site 41, Watertown, Massachusetts

International Nuclear Information System (INIS)

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

1983-10-01

During the MED/AEC era, work involving radioactive materials was conducted at various sites within the arsenal complex. Building 34 housed a uranium machine shop, and a portion of Building 41 contained a foundry that was used for uranium work. Information provided by site personnel indicated that only depleted uranium was used in these buildings. Results of radiological analyses of contaminated material found at these sites indicated depleted uranium with uranium-236. Both buildings have been razed. The remnants still in place consist of the concrete floor slabs, access drives, and underground utility service trenches. This area is currently under the control of the Watertown Redevelopment Authority of Watertown, Massachusetts. During the period from June 25 through July 1, 1981, the Argonne National Laboratory (ANL), Occupational Health and Safety Division (OHS) Radiological Survey Group (RSG), conducted a radiological survey of Building Sites 34 and 41 at the direction of the US Department of Energy. Significant levels of contamination were found at 33 locations on the pad of Site 34 and in 5 out of 15 soild corings from the perimeter of the pad. No contamination was found on the pad of Site 41; however, two-thirds of this pad was covered with soil up to 4 ft thick. One of the 14 soil corings taken adjacent to the pad of Site 41 had elevated levels of uranium. Levels of contamination in excess of criteria, as identified in ANSI 13.12 and NRC Guidelines, were found at this site. The analyses of the samples from the sewer access points also revealed uranium and radium-226 anomalies. Therefore, according to NRC guidelines dated July 1982, it must be concluded that they are contaminated

Corrective Action Investigation Plan for Corrective Action Unit 570: Area 9 Yucca Flat Atmospheric Test Sites Nevada National Security Site, Nevada, Revision 0

Energy Technology Data Exchange (ETDEWEB)

Patrick Matthews

2012-08-01

CAU 570 comprises the following six corrective action sites (CASs): • 02-23-07, Atmospheric Test Site - Tesla • 09-23-10, Atmospheric Test Site T-9 • 09-23-11, Atmospheric Test Site S-9G • 09-23-14, Atmospheric Test Site - Rushmore • 09-23-15, Eagle Contamination Area • 09-99-01, Atmospheric Test Site B-9A These sites are being investigated because existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend corrective action alternatives (CAAs). Additional information will be obtained by conducting a corrective action investigation before evaluating CAAs and selecting the appropriate corrective action for each CAS. The results of the field investigation will support a defensible evaluation of viable CAAs that will be presented in the Corrective Action Decision Document. The sites will be investigated based on the data quality objectives (DQOs) developed on April 30, 2012, by representatives of the Nevada Division of Environmental Protection and the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office. The DQO process was used to identify and define the type, amount, and quality of data needed to develop and evaluate appropriate corrective actions for CAU 570. The site investigation process will also be conducted in accordance with the Soils Activity Quality Assurance Plan, which establishes requirements, technical planning, and general quality practices to be applied to this activity. The presence and nature of contamination at CAU 570 will be evaluated based on information collected from a field investigation. Radiological contamination will be evaluated based on a comparison of the total effective dose at sample locations to the dose-based final action level. The total effective dose will be calculated as the total of separate estimates of internal and external dose. Results from the analysis of soil samples will be used to calculate internal radiological

Plutonium Particle Migration in the Shallow Vadose Zone: The Nevada Test Site as an Analog Site

Science.gov (United States)

Hunt, J. R.; Smith, D. K.

2004-12-01

The upper meter of the vadose zone in desert environments is the horizon where wastes have been released and human exposure is determined through dermal, inhalation, and food uptake pathways. This region is also characterized by numerous coupled processes that determine contaminant transport, including precipitation infiltration, evapotranspiration, daily and annual temperature cycling, dust resuspension, animal burrowing, and geochemical weathering reactions. While there is considerable interest in colloidal transport of minerals, pathogenic organisms, and contaminants in the vadose zone, there are limited field sites where the actual occurrence of contaminant migration can be quantified over the appropriate spatial and temporal scales of interest. At the US Department of Energy Nevada Test Site, there have been numerous releases of radionuclides since the 1950's that have become field-scale tracer tests. One series of tests was the four safety shots conducted in an alluvial valley of Area 11 in the 1950's. These experiments tested the ability of nuclear materials to survive chemical explosions without initiating fission reactions. Four above-ground tests were conducted and they released plutonium and uranium on the desert valley floor with only one of the tests undergoing some fission. Shortly after the tests, the sites were surveyed for radionuclide distribution on the land surface using aerial surveys and with depth. Additional studies were conducted in the 1970's to better understand the fate of plutonium in the desert that included studies of depth distribution and dust resuspension. More recently, plutonium particle distribution in the soil profile was detected using autoradiography. The results to date demonstrate the vertical migration of plutonium particles to depths in excess of 30 cm in this arid vadose zone. While plutonium migration at the Nevada Test Site has been and continues to be a concern, these field experiments have become analog sites for the

Site decontamination

International Nuclear Information System (INIS)

Bicker, A.E.

1981-01-01

Among the several DOE sites that have been radiologically decontaminated under the auspices of the Nevada Operations Office are three whose physical characteristics are unique. These are the Tatum Dome Test Site (TDTS) near Hattiesburg, Mississippi; a location of mountainous terrain (Pahute Mesa) on the Nevada Test Site; and the GNOME site near Carlsbad, New Mexico. In each case the contamination, the terrain, and the climate conditions were different. This presentation includes a brief description of each site, the methods used to perform radiological surveys, the logistics required to support the decontamination (including health physics and sample analysis), and the specific techniques used to reduce or remove the contamination

Radiological impact of surface water and sediment near uranium mining sites.

Science.gov (United States)

Ivanova, K; Stojanovska, Z; Badulin, V; Kunovska, B; Yovcheva, M

2015-12-01

The aim of this study is to assess the radiological impact of surface water and sediment around uranium mining sites 20 years after their closing. The areas under observations are 31 former classical underground uranium mining and exploratory sites in Bulgaria, named as objects. The extraction and processing of uranium ores in the Republic of Bulgaria were ended in 1992. To assess the radiological impact of radionuclides field expeditions were performed to sample water and bottom sediment. The migration of uranium through surface water was examined as one of the major pathways for contamination spread. The range of uranium concentration in water flowing from the mining sites was from 0.012 to 6.8 mgU l(-1) with a geometric mean of 0.192 mgU l(-1). The uranium concentrations in water downstream the mining sites were approximately 3 times higher than the background value (upstream). The concentrations of Unat, (226)Ra, (210)Pb, and (232)Th in the sediment of downstream river were higher than those upstream by 3.4, 2.6, 2, and 1.7 times, respectively. The distribution coefficient of uranium reflects its high mobility in most of the sites. In order to evaluate the impact on people as well as site prioritization for more detailed assessment and water management, screening dose assessments were done.

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

Energy Technology Data Exchange (ETDEWEB)

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

2017-10-01

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

Radiological dose assessment for residual radioactive material in soil at the clean slate sites 1, 2, and 3, Tonopah Test Range

International Nuclear Information System (INIS)

1997-06-01

A radiological dose assessment has been performed for Clean Slate Sites 1, 2, and 3 at the Tonopah Test Range, approximately 390 kilometers (240 miles) northwest of Las Vegas, Nevada. The assessment demonstrated that the calculated dose to hypothetical individuals who may reside or work on the Clean Slate sites, subsequent to remediation, does not exceed the limits established by the US Department of Energy for protection of members of the public and the environment. The sites became contaminated as a result of Project Roller Coaster experiments conducted in 1963 in support of the US Atomic Energy Commission (Shreve, 1964). Remediation of Clean Slate Sites 1, 2, and 3 is being performed to ensure that the 50-year committed effective dose equivalent to a hypothetical individual who lives or works on a Clean Slate site should not exceed 100 millirems per year. The DOE residual radioactive material guideline (RESRAD) computer code was used to assess the dose. RESRAD implements the methodology described in the DOE manual for establishing residual radioactive material guidelines (Yu et al., 1993a). In May and June of 1963, experiments were conducted at Clean Slate Sites 1, 2, and 3 to study the effectiveness of earth-covered structures for reducing the dispersion of nuclear weapons material as a result of nonnuclear explosions. The experiments required the detonation of various simulated weapons using conventional chemical explosives (Shreve, 1964). The residual radioactive contamination in the surface soil consists of weapons grade plutonium, depleted uranium, and their radioactive decay products

Radiological dose assessment for residual radioactive material in soil at the clean slate sites 1, 2, and 3, Tonopah Test Range

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-06-01

A radiological dose assessment has been performed for Clean Slate Sites 1, 2, and 3 at the Tonopah Test Range, approximately 390 kilometers (240 miles) northwest of Las Vegas, Nevada. The assessment demonstrated that the calculated dose to hypothetical individuals who may reside or work on the Clean Slate sites, subsequent to remediation, does not exceed the limits established by the US Department of Energy for protection of members of the public and the environment. The sites became contaminated as a result of Project Roller Coaster experiments conducted in 1963 in support of the US Atomic Energy Commission (Shreve, 1964). Remediation of Clean Slate Sites 1, 2, and 3 is being performed to ensure that the 50-year committed effective dose equivalent to a hypothetical individual who lives or works on a Clean Slate site should not exceed 100 millirems per year. The DOE residual radioactive material guideline (RESRAD) computer code was used to assess the dose. RESRAD implements the methodology described in the DOE manual for establishing residual radioactive material guidelines (Yu et al., 1993a). In May and June of 1963, experiments were conducted at Clean Slate Sites 1, 2, and 3 to study the effectiveness of earth-covered structures for reducing the dispersion of nuclear weapons material as a result of nonnuclear explosions. The experiments required the detonation of various simulated weapons using conventional chemical explosives (Shreve, 1964). The residual radioactive contamination in the surface soil consists of weapons grade plutonium, depleted uranium, and their radioactive decay products.

Off-site consequences of radiological accidents: methods, costs and schedules for decontamination

International Nuclear Information System (INIS)

Tawil, J.J.; Bold, F.C.; Harrer, B.J.; Currie, J.W.

1985-08-01

This report documents a data base and a computer program for conducting a decontamination analysis of a large, radiologically contaminated area. The data base, which was compiled largely through interviews with knowledgeable persons both in the public and private sectors, consists of the costs, physical inputs, rates and contaminant removal efficiencies of a large number of decontamination procedures. The computer program utilizes this data base along with information specific to the contaminated site to provide detailed information that includes the least costly method for effectively decontaminating each surface at the site, various types of property losses associated with the contamination, the time at which each subarea within the site should be decontaminated to minimize these property losses, the quantity of various types of labor and equipment necessary to complete the decontamination, dose to radiation workers, the costs for surveying and monitoring activities, and the disposal costs associated with radiological waste generated during cleanup. The program and data base are demonstrated with a decontamination analysis of a hypothetical site. 39 refs., 24 figs., 155 tabs

Off-site consequences of radiological accidents: methods, costs and schedules for decontamination

Energy Technology Data Exchange (ETDEWEB)

Tawil, J.J.; Bold, F.C.; Harrer, B.J.; Currie, J.W.

1985-08-01

This report documents a data base and a computer program for conducting a decontamination analysis of a large, radiologically contaminated area. The data base, which was compiled largely through interviews with knowledgeable persons both in the public and private sectors, consists of the costs, physical inputs, rates and contaminant removal efficiencies of a large number of decontamination procedures. The computer program utilizes this data base along with information specific to the contaminated site to provide detailed information that includes the least costly method for effectively decontaminating each surface at the site, various types of property losses associated with the contamination, the time at which each subarea within the site should be decontaminated to minimize these property losses, the quantity of various types of labor and equipment necessary to complete the decontamination, dose to radiation workers, the costs for surveying and monitoring activities, and the disposal costs associated with radiological waste generated during cleanup. The program and data base are demonstrated with a decontamination analysis of a hypothetical site. 39 refs., 24 figs., 155 tabs.

Radiological surveillance of Remedial Action activities at the processing site, Falls City, Texas. Final report

International Nuclear Information System (INIS)

1993-04-01

The Uranium Mill Tailings Remedial Action (UMTRA) Project's Technical Assistance Contractor (TAC) performed a radiological surveillance of the Remedial Action Contractor (RAC), MK-Ferguson and CWM Federal Environmental Services, Inc., at the processing site in Falls City, Texas. This surveillance was conducted March 22--26, 1993. No findings were identified during the surveillance. Three site-specific observations and three programmatic observations are presented in this report. The overall conclusion from the surveillance is that the radiological aspects of the Falls City, Texas, remedial action program are performed adequately. However, some of the observations identify that there is potential for improving certain aspects of the occupational radiological air sampling, ensuring analytical data quality, and in communicating with the DOE and TAC on the ore sampling methods. The TAC has also received and is currently reviewing the RAC's responses regarding the observations identified during the radiological surveillance performed October 29--30, 1992

Finding and evaluating potential radiological problems in the vicinity of uranium milling sites

International Nuclear Information System (INIS)

Goldsmith, W.A.; Yates, W.G.

1982-01-01

Tailings at inactive milling sites usually have a low frequency of human occupancy but continuously generate 222 Rn into the atmosphere. Measurements of airborne 222 Rn and 222 Rn flux are made on the sites to define the tailings source term. Concurrently with these measurements, an ambient 222 Rn monitoring network is established off-site and a meteolrololgical station is established at or near the mill site. Radioactivity can migrate to areas outside of site boundaries by wind and water erosion, groundwater transport, spillage of incoming purposes. In order to identify and assess off-site radioactivity on properties in the vicinity of milling sites, a combination of aerial and ground-level radiological monitoring techniques are used. The ground mobile gamma-ray scan is conducted using a vehicle equipped with sensitive gamma-ray detectors. The detectors are shielded so that gamma radiation input is viewed through only one side of the vehicle. This system is capable of precisely locating properties which have anomalously high gamma radiation levels caused by the presence of tailings. Subsequently, these properties are identified as candidate vicinity properties and are scheduled for radiological surveys subject to the property owner's consent. The comprehensive radiological surveys conducted at these vicinity properties determine the amount, type, and location of tailings materials. Structures on a vicinity property are carefully surveyed to determine the presence or absence of construction-related uses of tailings. If structural uses of tailings are found, air samples are analyzed for 222 Rn progeny, short-term continuous 222 Rn monitoring is instituted, and 222 Rn flux rate from tailings are estimated. If warranted, long-term 222 Rn and progeny measurements are made

Support for external validity of radiological anatomy tests using volumetric images

NARCIS (Netherlands)

Ravesloot, Cécile J.; van der Gijp, Anouk; van der Schaaf, Marieke F.; Huige, Josephine C B M; Vincken, Koen L.; Mol, Christian P.; Bleys, Ronald L A W; ten Cate, Olle T.; van Schaik, Jan P J

2015-01-01

Rationale and Objectives: Radiology practice has become increasingly based on volumetric images (VIs), but tests in medical education still mainly involve two-dimensional (2D) images. We created a novel, digital, VI test and hypothesized that scores on this test would better reflect radiological

Support for external validity of radiological anatomy tests using volumetric images

NARCIS (Netherlands)

Ravesloot, Cecile J.; van der Gijp, Anouk; van der Schaaf, Marieke F; Huige, Josephine C B M; Vincken, Koen L; Mol, Christian P; Bleys, Ronald L A W; ten Cate, Olle T; van Schaik, JPJ

2015-01-01

RATIONALE AND OBJECTIVES: Radiology practice has become increasingly based on volumetric images (VIs), but tests in medical education still mainly involve two-dimensional (2D) images. We created a novel, digital, VI test and hypothesized that scores on this test would better reflect radiological

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

Challenges in radiological impact assessment studies at new sites for nuclear facilities and its safety review and assessment for siting consent

International Nuclear Information System (INIS)

Mukherjee Roy, Susmita; Roshan, A.D.; Bishnoi, L.R.

2018-01-01

One of the basic requirement of site evaluation for a Nuclear Facility (NF) is radiological impact assessment (RIA). This involves evaluation of transportation of radioactive materials discharged from a nuclear facility under normal operational or accidental conditions, through different compartments of environment viz. air, land and water, and finally assessment of its consequences. Amongst others, site characteristics and the site related parameters play major role in evaluation of impact of postulated releases from NPPs. Doses to public from both external and internal exposures are computed to assess potential consequences of a radiological release and acceptability of the site-plant pair is established based on the outcome of this assessment. A comprehensive study of the site characteristics including meteorology, hydrology, hydro-geology and demography of the region along with details of land and water use, bioaccumulation, transfer to and from the environmental matrices is required for accomplishing satisfactory RIA

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

Nevada Test Site Annual Site Environmental Report for Calendar Year - 1999

International Nuclear Information System (INIS)

Townsend, Y.E.; Grossman, R.F.

2000-01-01

Prior to 1989, annual reports of environmental monitoring and assessment results for the Nevada Test Site (NTS) were prepared in two separate parts. Onsite effluent monitoring and environmental monitoring results were reported in an onsite report prepared by the U.S. Department of Energy, Nevada Operations Office (DOE/NV). Results of the Offsite Radiological Surveillance and Long-Term Hydrological Monitoring programs conducted by the U.S. Environmental Protection Agency's (EPA's) Laboratory (various names) in Las Vegas, Nevada, were reported separately by that Agency. Beginning with the 1989 Annual Site Environmental Report for the NTS, these two documents were combined into a single report to provide a more comprehensive annual documentation of the environmental protection activities conducted for the nuclear testing program and other nuclear and non-nuclear operations at the NTS. The two agencies have coordinated preparation of this eleventh combined onsite and offsite report through sharing of information on environmental surveillance and releases as well as meteorological, hydrological, and other supporting data used in dose-estimation calculations

Nevada Test Site Annual Site Environmental Report for Calendar Year - 1999

Energy Technology Data Exchange (ETDEWEB)

Townsend, Y.E.; Grossman, R.F.

2000-10-01

Prior to 1989, annual reports of environmental monitoring and assessment results for the Nevada Test Site (NTS) were prepared in two separate parts. Onsite effluent monitoring and environmental monitoring results were reported in an onsite report prepared by the U.S. Department of Energy, Nevada Operations Office (DOE/NV). Results of the Offsite Radiological Surveillance and Long-Term Hydrological Monitoring programs conducted by the U.S. Environmental Protection Agency's (EPA's) Laboratory (various names) in Las Vegas, Nevada, were reported separately by that Agency. Beginning with the 1989 Annual Site Environmental Report for the NTS, these two documents were combined into a single report to provide a more comprehensive annual documentation of the environmental protection activities conducted for the nuclear testing program and other nuclear and non-nuclear operations at the NTS. The two agencies have coordinated preparation of this eleventh combined onsite and offsite report through sharing of information on environmental surveillance and releases as well as meteorological, hydrological, and other supporting data used in dose-estimation calculations.

Nevada Test Site annual site environmental report for calendar year 1998

Energy Technology Data Exchange (ETDEWEB)

Black, S.C.; Townsend, Y.E.

1999-10-01

Prior to 1989, annual reports of environmental monitoring and assessment results for the Nevada Test Site (NTS) were prepared in two separate parts. Onsite effluent monitoring and environmental monitoring results were reported in an onsite report prepared by the US Department of Energy, Nevada Operations Office (DOE/NV). Results of the Offsite Radiological Surveillance and Long-Term Hydrological Monitoring Programs conducted by the US Environmental Protection Agency's (EPA) Laboratory (various names) in Las Vegas, Nevada, were reported separately by that Agency. Beginning with the 1989 Annual Site Environmental Report for the NTS, these two documents were combined into a single report to provide a more comprehensive annual documentation of the environmental protection activities conducted for the nuclear testing program and other nuclear and non-nuclear operations at the NTS. The two agencies have coordinated preparation of this tenth combined onsite and offsite report through sharing of information on environmental surveillance and releases as well as meteorological, hydrological, and other supporting data used in dose-estimation calculations.

Joint NRC/EPA Sewage Sludge Radiological Survey: Survey Design & Test Site Results

Science.gov (United States)

This report contains the results of a radiological survey of nine publicly POTWs around the country, which was commissioned by the Sewage Sludge Subcommittee, to determine whether and to what extent radionuclides concentrate in sewage treatment wastes.

Decontamination analysis of a radiologically contaminated site

International Nuclear Information System (INIS)

Tawil, J.J.; Strenge, D.L.

1984-02-01

This paper presents an analysis of decontamination options at the NUWAZX-83 exercise site. Held in May 1983, the purpose of the exercise was to evaluate the ability of federal, state and local officials to respond to a radiological accident involving nuclear weapons. A computer program developed by Pacific Northwest Laboratory was used to conduct the decontamination analysis. The program, called DECON, was designed to assist personnel engaged in the planning of decontamination activities. The many features of DECON that are demonstrated in this paper contribute to its potential usefulness as a planning tool for site restoration. Strategies that are analyzed with DECON include: (1) using a Quick-Vac option, under which exterior surfaces are vacuumed before it rains; (2) protecting surfaces against precipitation; (3) prohibiting specific operations on selected surfaces; (4) requiring that specific methods be used on selected surfaces; (5) evaluating the trade-off between cleanup standards and decontamination costs; and (6) varying clean-up standards according to expected human exposure to the surface

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.

Depleted uranium residual radiological risk assessment for Kosovo sites

International Nuclear Information System (INIS)

Durante, Marco; Pugliese, Mariagabriella

2003-01-01

During the recent conflict in Yugoslavia, depleted uranium rounds were employed and were left in the battlefield. Health concern is related to the risk arising from contamination of areas in Kosovo with depleted uranium penetrators and dust. Although chemical toxicity is the most significant health risk related to uranium, radiation exposure has been allegedly related to cancers among veterans of the Balkan conflict. Uranium munitions are considered to be a source of radiological contamination of the environment. Based on measurements and estimates from the recent Balkan Task Force UNEP mission in Kosovo, we have estimated effective doses to resident populations using a well-established food-web mathematical model (RESRAD code). The UNEP mission did not find any evidence of widespread contamination in Kosovo. Rather than the actual measurements, we elected to use a desk assessment scenario (Reference Case) proposed by the UNEP group as the source term for computer simulations. Specific applications to two Kosovo sites (Planeja village and Vranovac hill) are described. Results of the simulations suggest that radiation doses from water-independent pathways are negligible (annual doses below 30 μSv). A small radiological risk is expected from contamination of the groundwater in conditions of effective leaching and low distribution coefficient of uranium metal. Under the assumptions of the Reference Case, significant radiological doses (>1 mSv/year) might be achieved after many years from the conflict through water-dependent pathways. Even in this worst-case scenario, DU radiological risk would be far overshadowed by its chemical toxicity

Foods Found in the Wild Around Nuclear Sites: An Evaluation of Radiological Impact

International Nuclear Information System (INIS)

Green, N.; Wilkins, B.T.; Hammond, D.J.; Davidson, M.F.; Richmond, S.; Brooker, S.

2001-01-01

Habit surveys were carried out around four licensed nuclear sites to identify people who collect foodstuffs from the wild (so-called 'free foods'). In total, around 800 collectors were readily identified, most of whom collected more than one free food. The data indicated that estimates of higher than average doses could reasonably be based on the three foodstuffs of most importance. Foods were selected for further study on the basis of either the number of collectors or the amount consumed. The radionuclides of interest were identified using published information on the discharges from each site. The resultant average and higher than average doses were estimated using the site-specific habit data. For all sites, doses from the consumption of free foods were low and of no radiological importance. Assessments based solely on data for cultivated foods would not therefore have underestimated radiological impact significantly. However, given the wide utilisation of free foods found in this study, for rigorous assessments it would be prudent to take account of the consumption of foods from the wild. (author)

Radiological characterization and challenges at decommissioning sites

International Nuclear Information System (INIS)

Moore, Scott

2002-01-01

Scott Moore described the dose-based radiological characterisation process used in the USA, and four current characterisation issues faced there. His paper emphasized the importance of characterisation to control decommissioning hazards and costs: The License Termination Rule (LTR), Subpart E to 10 CFR Part 20, provides the dose-based criteria that the U.S. Nuclear Regulatory Commission (NRC) uses as the basis for regulating cleanup at material and reactor sites. The LTR permits the release of sites for unrestricted use, if the radioactivity that is distinguishable from background results in a total effective dose equivalent to an average member of a critical group that does not exceed 0.25 milli-Sievert per year (mSv/yr) (25 milli-rem/year) and the residual radioactivity has been reduced to levels that are as low as reasonably achievable. Additionally, the LTR establishes criteria for license termination with restrictions on future land use, which allow for a dose to the critical group of 0.25 mSv/yr (25 milli-rem/year) with restrictions in place, and 1 mSv/yr (100 milli-rem/year) if the restrictions fail. In certain circumstances as outlined in Subpart E, a dose as high as 5 mSv/yr (500 milli-rem/year) is permitted if restrictions fail. Following issuance of the dose-based LTR in 1997, NRC staff developed the Standard Review Plan for Decommissioning Plans (NUREG-1727). NUREG-1727 is a guidance document that describes the methods that NRC has determined are acceptable for implementing the LTR and other decommissioning regulations. While NUREG-1727 is focused on the review of decommissioning plans for nuclear material sites, it provides general guidance that in many cases is applicable to reactor sites (e.g., review criteria for dose-modeling and radiological surveys). In addition to NUREG-1727, staff developed the Standard Review Plan for Evaluating Nuclear Power Reactor License Termination Plans (NUREG-1700) as specific guidance for reactor decommissioning. NUREG

A cross-site vascular radiology on-call service: the Manchester experience

International Nuclear Information System (INIS)

Ashleigh, R.J.; Butterfield, J.S.; Asquith, J.; Chalmers, N.; Murphy, G.

2005-01-01

AIM: A cross-site vascular radiology on-call service was established 5 years ago to cover two vascular centres in Manchester. We aimed to review the service. MATERIALS AND METHODS: A prospective audit of out-of hours referrals and procedures over a three month period (March-May 2003) was undertaken. RESULTS: There were 52 incidents in 49 patients (mean 4 calls per week). Nine involved telephone advice only, the remainder (82%) required a procedure. Angiography was performed on 88% of patients and therapeutic radiological intervention on 50%. 71% of calls occurred at a weekend. 50% of the calls were from vascular surgery and 50% from other sources. The consultant vascular radiologist was present for 93% of procedures. CONCLUSIONS: The workload suggests that a vascular radiology on call service is justified in Manchester. There have been no major problems with its implementation and operation. This is a consultant led service, with very few cases being devolved to a specialist registrar (SpR)

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

International Nuclear Information System (INIS)

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

2010-01-01

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

An aerial radiological survey of the Salmon Site and surrounding area, Lamar County, Mississippi

International Nuclear Information System (INIS)

Kernan, W.J.

1994-05-01

An aerial radiological survey was conducted over the former Atomic Energy Commission Test Site at the Salmon Site and surrounding area between April 20 and May 1, 1992. The Salmon Site is located in Lamar County, Mississippi, approximately 20 miles southwest of Hattiesburg, Mississippi. The purpose of the survey was to measure and document the gamma-ray environment of the Salmon Site and adjacent lands. A contour map showing gamma radiation exposure rates at 1 meter above ground level was constructed from the aerial data and overlaid on a rectified aerial photograph of the area. The exposure rates within the area are between 5 and 8 μR/h. The reported exposure rates include a cosmic-ray contribution estimated to be 3.7 μR/h. Radionuclide assays of soil samples and in situ measurements, taken with a pressurized ion chamber and a high-purity germanium detector, were obtained at 4 locations within the survey boundaries. These measurements were taken in support of and are in agreement with the aerial data

Feasibility, cost and safety of some rehabilitation options for the Maralinga test site

International Nuclear Information System (INIS)

Vande Putte, D.; Tufton, E.P.S.; Myall, M.

1992-01-01

The need to rehabilitate the former nuclear test site at Maralinga has required the development of safe and cost-effective clean-up measures. Options have been investigated, which include fencing-off parts of the site, removing surface soil, mixing surface soil and stabilising the contents of debris pits. The results of the study can be used in selecting the most suitable options or combination of options necessary to achieve a given radiological end-point. (author)

Implementation of the International Code of Practice on Dosimetry in Diagnostic Radiology (TRS 457): Review of Test Results

International Nuclear Information System (INIS)

2011-01-01

In 2007, the IAEA published Dosimetry in Diagnostic Radiology: An International Code of Practice (IAEA Technical Reports Series No. 457). This publication recommends procedures for calibration and dosimetric measurement for the attainment of standardized dosimetry. It also addresses requirements both in standards dosimetry laboratories, especially Secondary Standards Dosimetry Laboratories (SSDLs), and in clinical centres for radiology, as found in most hospitals. The implementation of TRS No. 457 decreases the uncertainty in the dosimetry of diagnostic radiology beams and provides Member States with a unified and consistent framework for dosimetry in diagnostic radiology, which previously did not exist. A coordinated research project (CRP E2.10.06) was established in order to provide practical guidance to professionals at SSDLs and to clinical medical physicists on the implementation of TRS No. 457. This includes the calibration of radiological dosimetry instrumentation, the dissemination of calibration coefficients to clinical centres and the establishment of dosimetric measurement processes in clinical settings. The main goals of the CRP were to: Test the procedures recommended in TRS No. 457 for calibration of radiation detectors in different types of diagnostic beams and measuring instruments for varying diagnostic X ray modalities; Test the clinical dosimetry procedures, including the use of phantoms and patient dose surveys; Report on the practical implementation of TRS No. 457 at both SSDLs and hospital sites. Testing of TRS No. 457 was performed by a group of medical physicists from hospitals and SSDLs from various institutions worldwide

Corrective Action Investigation Plan for Corrective Action Unit 105: Area 2 Yucca Flat Atmospheric Test Sites Nevada National Security Site, Nevada, Revision 0

Energy Technology Data Exchange (ETDEWEB)

Patrick Matthews

2012-09-01

Corrective Action Unit (CAU) 105 is located in Area 2 of the Nevada National Security Site, which is approximately 65 miles northwest of Las Vegas, Nevada. CAU 105 is a geographical grouping of sites where there has been a suspected release of contamination associated with atmospheric nuclear testing. This document describes the planned investigation of CAU 105, which comprises the following corrective action sites (CASs): • 02-23-04, Atmospheric Test Site - Whitney • 02-23-05, Atmospheric Test Site T-2A • 02-23-06, Atmospheric Test Site T-2B • 02-23-08, Atmospheric Test Site T-2 • 02-23-09, Atmospheric Test Site - Turk These sites are being investigated because existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend corrective action alternatives (CAAs). Additional information will be obtained by conducting a corrective action investigation before evaluating CAAs and selecting the appropriate corrective action for each CAS. The results of the field investigation will support a defensible evaluation of viable CAAs that will be presented in the Corrective Action Decision Document. The sites will be investigated based on the data quality objectives (DQOs) developed on April 30, 2012, by representatives of the Nevada Division of Environmental Protection and the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office. The DQO process was used to identify and define the type, amount, and quality of data needed to develop and evaluate appropriate corrective actions for CAU 105. The site investigation process will also be conducted in accordance with the Soils Activity Quality Assurance Plan, which establishes requirements, technical planning, and general quality practices to be applied to this activity. The potential contamination sources associated with all CAU 105 CASs are from atmospheric nuclear testing activities. The presence and nature of contamination at CAU

Guide to radiological accident considerations for siting and design of DOE nonreactor nuclear facilities

International Nuclear Information System (INIS)

Elder, J.C.; Graf, J.M.; Dewart, J.M.; Buhl, T.E.; Wenzel, W.J.; Walker, L.J.; Stoker, A.K.

1986-01-01

This guide was prepared to provide the experienced safety analyst with accident analysis guidance in greater detail than is possible in Department of Energy (DOE) Orders. The guide addresses analysis of postulated serious accidents considered in the siting and selection of major design features of DOE nuclear facilities. Its scope has been limited to radiological accidents at nonreactor nuclear facilities. The analysis steps addressed in the guide lead to evaluation of radiological dose to exposed persons for comparison with siting guideline doses. Other possible consequences considered are environmental contamination, population dose, and public health effects. Choices of models and parameters leading to estimation of source terms, release fractions, reduction and removal factors, dispersion and dose factors are discussed. Although requirements for risk analysis have not been established, risk estimates are finding increased use in siting of major nuclear facilities, and are discussed in the guide. 3 figs., 9 tabs

Environmental surveillance report for the Nevada Test Site (January 1980-December 1980)

International Nuclear Information System (INIS)

Scoggins, W.A.

1981-01-01

Results are presented for the environmental surveillance program at the Nevada Test Site as conducted by the Department of Energy (DOE) onsite radiological safety contractor from January 1980 through December 1980. The results and evaluations of measurements of radioactivity in air and water, and of direct gamma radiation exposure rates are presented. Relevancy to DOE concentration guides (CG'S) is established

An aerial radiological survey of the Central Savannah River Site, Aiken, South Carolina

International Nuclear Information System (INIS)

Feimster, E.L.

1991-09-01

An aerial radiological survey was conducted over a 194-square- kilometer (75-square-mile) area encompassing the central portion of the Savannah River Site (SRS). The survey was flown during February 10--27, 1987. These radiological measurements were used as baseline data for the central area and for determining the extent of man-made radionuclide distribution. Previous SRS surveys included small portions of the area; the 1987 survey was covered during the site- wide survey conducted in 1979. Man-made radionuclides (including cobalt-60, cesium-137, protactinium-234m, and elevated levels of uranium-238 progeny) that were detected during the survey were typical of those produced by the reactor operations and material processing activities being conducted in the area. The natural terrestrial radiation levels were consistent with those measured during prior surveys of other SRS areas. 1 refs., 4 figs

Safety Assessment Document for the Spent Reactor Fuel Geologic Storage Test in the Climax Granite Stock at the Nevada Test site

International Nuclear Information System (INIS)

1980-01-01

The objective of the Spent Fuel Geologic Storage Test in the Climax Granite Stock is to evaluate the response of a granitic rock mass to the underground storage of encapsulated spent reactor fuel in a geometry that simulates a module of a large-scale geologic repository. This document reports an assessment of the safety of conducting this test. Descriptions are provided of the geography, meteorology, hydrology, geology, and seismology of the Climax Site; the effects of postulated natural phenomena and other activities at the nevada Test Site on the safety of the test; and the design and operation of the test facility and associated equipment. Evaluations are made of both the radiological and nonradiological impacts of normal operations, abnormal operations, and postulated accidents. It is concluded that conduct of the spent fuel test at the Climax Site will not result in any undue risk to the public, property, environment, or site employees

Modified TCLP test for evaluating the leachability of site-specific wastes

International Nuclear Information System (INIS)

Pier, J.

1996-01-01

The Weldon Spring Site Remedial Action Project (WSSRAP) has developed a site-specific test to assess the leachability of wastes that will be placed in its on-site disposal cell. This test is modelled after the TCLP, but examines an expanded list of parameters and uses an extraction solution that is representative of conditions that are expected to exist in the disposal facility. Following the same logic that guided development of TCLP protocols, the WSSRAP developed concentration guidelines for non-TCLP parameters that were contaminants of concern in its wastes. Response actions, specific to the WSSRAP cell and wastes, were also developed to address constituents that failed to meet these guides. From 1955 to 1966, the US Atomic Energy Commission operated a uranium feed materials plant on this site. Nitroaromatic, and later, radiological wastes were disposed of in the quarry from 1945 until 1970. This paper describes testing to determine whether contaminant concentrations in leachates derived from the major waste-types that will be placed in its on-site disposal cell conform with the Department of Energy's (DOE) as low as reasonably achievable (ALARA) policy. Although the WSSRAP will continue to use the TCLP test to determine if any waste is classified RCRA-hazardous, the site-specific test described in this paper will be used to further assess whether leachate from any waste-type has the potential to adversely impact groundwater

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

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

Energy Technology Data Exchange (ETDEWEB)

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

2015-10-01

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

Radiological audit of remedial action activities at the processing site, transfer site, and Cheney disposal site Grand Junction, Colorado: Audit date, August 9--11, 1993

International Nuclear Information System (INIS)

1993-08-01

The Uranium Mill Tailing Remedial Action (UMTRA) Project's Technical Assistance Contractor (TAC) performed a radiological audit of the Remedial Action Contractor (RAC), MK-Ferguson and CWM Federal Environmental Services, Inc., at the processing site, transfer site, and Cheney disposal site in Grand Junction, Colorado. Jim Hylko and Bill James of the TAC conducted this audit August 9 through 11, 1993. Bob Cornish and Frank Bosiljevec represented the US Department of Energy (DOE). This report presents one programmatic finding, eleven site-specific observations, one good practice, and four programmatic observations

Environmental surveillance report for the Nevada Test Site (January 1981 through December 1981)

International Nuclear Information System (INIS)

Scoggins, W.A.

1982-05-01

This report documents the environmental surveillance program at the Nevada Test Site as conducted by the Department of Energy (DOE) onsite radiological safety contractor from January 1981 through December 1981. The results and evaluations of measurements of radioactivity in air and water, and of direct gamma radiation exposure rates are presented. Relevancy to DOE concentration guides (CG'S) is established

Radiological safety evaluation report for NUWAX-79 exercise

International Nuclear Information System (INIS)

King, W.C.

1979-03-01

An analysis of the radiological safety of the NUWAX-79 exercise to be conducted on the Nevada Test Site in April 1979 is given. An evaluation of the radiological safety to the participants is made using depleted uranium (D-38) in mock weapons parts, and 223 Ra and its daughters as a radioactive contaminant of equipment and terrain. The radiological impact to offsite persons is also discussed, particularly for people living at Lathrop Wells, Nevada, which is located 7 miles south of the site proposed for the exercise. It is the conclusion of this evaluation that the potential radiological risk of this exercise is very low, and that no individual should receive exposure to radioactivity greater than one-tenth of the level permitted under current federal radiation exposure guidelines

Analysis of operation TEAPOT nuclear test ZUCCHINI radiological and meterological data

International Nuclear Information System (INIS)

Quinn, V.E.

1987-03-01

This report describes the Weather Service Nuclear Support Office (WSNSO) analyses of the radiological and meteorological data collected for the ZUCCHINI nuclear test of Operation TEAPOT. Inconsistencies in the radiological data and their resolution are discussed. The methods of normalizing the radiological data to a standard time and estimating fallout-arrival times are presented. The meteorological situations on event day and the following day are described. A comparison of the WSNSO fallout analysis with an analysis performed in the 1950's is presented. The radiological data used to derive the WSNSO 1986 fallout pattern are tabulated in an appendix

Radiology Teaching Files on the Internet

International Nuclear Information System (INIS)

Lim, Eun Chung; Kim, Eun Kyung

1996-01-01

There is increasing attention about radiology teaching files on the Internet in the field of diagnostic radiology. The purpose of this study was to aid in the creation of new radiology teaching file by analysing the present radiology teaching file sites on the Internet with many aspects and evaluating images on those sites, using Macintosh II ci compute r, 28.8kbps TelePort Fax/Modem, Netscape Navigator 2.0 software. The results were as follow : 1. Analysis of radiology teaching file sites (1) Country distribution was the highest in USA (57.5%). (2) Average number of cases was 186 cases and radiology teaching file sites with search engine were 9 sites (22.5%). (3) At the method of case arrangement, anatomic area type and diagnosis type were found at the 10 sites (25%) each, question and answer type was found at the 9 sites (22.5%). (4) Radiology teaching file sites with oro-maxillofacial disorder were 9 sites (22.5%). (5) At the image format, GIF format was found at the 14 sites (35%), and JPEG format found at the 14 sites (35%). (6) Created year was the highest in 1995 (43.7%). (7) Continuing case upload was found at the 35 sites (87.5%). 2. Evaluation of images on the radiology teaching files (1) Average file size of GIF format (71 Kbyte) was greater than that of JPEG format (24 Kbyte). (P<0.001) (2) Image quality of GIF format was better than that of JPEG format. (P<0.001)

An integrated system for conducting radiological surveys of contaminated sites - 16312

International Nuclear Information System (INIS)

McCown, Jay P.; Rogers, Donna M.; Waggoner, Charles A.

2009-01-01

This paper describes an integrated detection system that has been developed to conduct radiological surveys of sites suspected of contamination of materials such as depleted uranium. This system utilizes cerium activated lanthanum bromide and thallium activated sodium iodide gamma detectors and can be easily adapted to include units for detecting neutrons. The detection system includes software controlling the collection of radiological spectra and GPS data. Two different platforms are described for conducting surveys, a modified zero turn radius (ZTR) mower and a three-wheeled cart that is manually pushed. The detection system software controlling data collection has components that facilitate completing a grid-less survey on user specified spacings. Another package confirms that all data quality activities (calibrations, etc.) are conducted prior to beginning the survey and also reviews data to identify areas that have been missed for which data quality falls below user designated parameters. Advanced digital signal processing algorithms are used to enhance the interpretation of spectra for conducting background subtractions and for mapping. Data from radiation detection instruments and GPS antennae are merged and made compatible with mapping using Geosoft Oasis montaj software. A summary of system performance during field-testing is included in the paper. This includes survey rate, detection limits, duty cycle, supporting ancillary equipment/material, and manpower requirements. The rate of false positives and false negatives is discussed with the benefits of surveys conducted using synergetic detection systems such as electromagnetic induction imaging. (authors)

NV/YMP RADIOLOGICAL CONTROL MANUAL

Energy Technology Data Exchange (ETDEWEB)

U.S. DEPARTMENT OF ENERGY, NATIONAL NUCLEAR SECURITY ADMINISTRATION NEVADA SITE OFFICE; BECHTEL NEVADA

2004-11-01

This manual contains the radiological control requirements to be used for all radiological activities conducted by programs under the purview of the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office (NNSA/NSO) and the Yucca Mountain Office of Repository Development (YMORD). Compliance with these requirements will ensure compliance with Title 10 Code of Federal Regulations Part 835 (10 CFR 835), Occupational Radiation Protection. Programs covered by this manual are located at the Nevada Test Site (NTS); Nellis Air Force Base and North Las Vegas, Nevada; Santa Barbara and Pleasanton, California; and at Andrews Air Force Base, Maryland. In addition, field work by NNSA/NSO at other locations is also covered by this manual.

NV/YMP RADIOLOGICAL CONTROL MANUAL

International Nuclear Information System (INIS)

2004-01-01

This manual contains the radiological control requirements to be used for all radiological activities conducted by programs under the purview of the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office (NNSA/NSO) and the Yucca Mountain Office of Repository Development (YMORD). Compliance with these requirements will ensure compliance with Title 10 Code of Federal Regulations Part 835 (10 CFR 835), Occupational Radiation Protection. Programs covered by this manual are located at the Nevada Test Site (NTS); Nellis Air Force Base and North Las Vegas, Nevada; Santa Barbara and Pleasanton, California; and at Andrews Air Force Base, Maryland. In addition, field work by NNSA/NSO at other locations is also covered by this manual

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

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

International Nuclear Information System (INIS)

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

2016-01-01

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

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

Energy Technology Data Exchange (ETDEWEB)

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

2016-09-01

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

Assessment of radiological consequences of routine releases in a site with various nuclear facilities

International Nuclear Information System (INIS)

Lucinio, Elena Albeira Guirado

2003-01-01

This work evaluates the radiological consequences of a nuclear site with a complex of fuel enrichment, conversion, reconversion facilities and a nuclear reactor. A methodology recommended by the Commission of the European Communities (CEC) is used and implemented in the PC-CREAM computer code. This code is composed of six linked modules, which describe the transfer of radionuclides to the environment, the pathways on which people may be exposed to radiation, and the radiological consequences. Radiation doses to a selected population are evaluated taking into account atmospheric and aquatic releases. (author)

Analysis of Operation Plumbbob nuclear test: BOLTZMANN radiological and meteorological data

International Nuclear Information System (INIS)

Steadman, C.R. Jr.; Kennedy, N.C.; Quinn, V.E.

1983-09-01

This report describes the Weather Service Nuclear Support Office (WSNSO) analyses of the radiological and meteorological data collected for the BOLTZMANN nuclear test of Operation PLUMBBOB. Inconsistencies in the radiological data and their resolution are discussed. The methods of converting aerial radiological data to equivalent ground-level values and of estimating fallout arrival times are presented. The meteorological situation on D-day is described. A comparison of the WSNSO fallout analyses with analyses in the late 1950's is presented. The appendices contain tabulated radiological data used in the fallout analyses, and contain discussions of the BOLTZMANN hot spot contention and of the enhanced activity at Portola, California

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

Energy Technology Data Exchange (ETDEWEB)

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

2014-10-01

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

The Department of Energy Nevada Test Site Remote Area Monitoring System

International Nuclear Information System (INIS)

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

1993-01-01

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

Streamlined Approach for Environmental Restoration Plan for Corrective Action Unit 113: Reactor Maintenance, Assembly, and Disassembly Building Nevada Test Site, Nevada

Energy Technology Data Exchange (ETDEWEB)

J. L. Smith

2001-01-01

This Streamlined Approach for Environmental Restoration (SAFER) Plan addresses the action necessary for the closure in place of Corrective Action Unit (CAU) 113 Area 25 Reactor Maintenance, Assembly, and Disassembly Facility (R-MAD). CAU 113 is currently listed in Appendix III of the Federal Facility Agreement and Consent Order (FFACO) (NDEP, 1996). The CAU is located in Area 25 of the Nevada Test Site (NTS) and consists of Corrective Action Site (CAS) 25-04-01, R-MAD Facility (Figures 1-2). This plan provides the methodology for closure in place of CAU 113. The site contains radiologically impacted and hazardous material. Based on preassessment field work, there is sufficient process knowledge to close in place CAU 113 using the SAFER process. At a future date when funding becomes available, the R-MAD Building (25-3110) will be demolished and inaccessible radiologic waste will be properly disposed in the Area 3 Radiological Waste Management Site (RWMS).

Streamlined Approach for Environmental Restoration Plan for Corrective Action Unit 113: Reactor Maintenance, Assembly, and Disassembly Building Nevada Test Site, Nevada

International Nuclear Information System (INIS)

Smith, J. L.

2001-01-01

This Streamlined Approach for Environmental Restoration (SAFER) Plan addresses the action necessary for the closure in place of Corrective Action Unit (CAU) 113 Area 25 Reactor Maintenance, Assembly, and Disassembly Facility (R-MAD). CAU 113 is currently listed in Appendix III of the Federal Facility Agreement and Consent Order (FFACO) (NDEP, 1996). The CAU is located in Area 25 of the Nevada Test Site (NTS) and consists of Corrective Action Site (CAS) 25-04-01, R-MAD Facility (Figures 1-2). This plan provides the methodology for closure in place of CAU 113. The site contains radiologically impacted and hazardous material. Based on preassessment field work, there is sufficient process knowledge to close in place CAU 113 using the SAFER process. At a future date when funding becomes available, the R-MAD Building (25-3110) will be demolished and inaccessible radiologic waste will be properly disposed in the Area 3 Radiological Waste Management Site (RWMS)

European network on the determination of site end points for radiologically contaminated land

International Nuclear Information System (INIS)

Booth, Peter; Lennon, Chris

2007-01-01

Nexia Solutions are currently running a small European network entitled 'European Network on the Determination of Site End Points for Radiologically Contaminated Land (ENDSEP)'. Other network members include NRG (Netherlands), UKAEA (UK), CEA (France), SOGIN (Italy), Wismut (Germany), Saxon State Agency of Environment and Geology (Germany). The network is focused on the technical and socio-economical issues associated with the determination of end points for sites potentially, or actually, impacted by radiological contamination. Such issues will cover: - Those associated with the run up to establishing a site end point; - Those associated with verifying that the end points have been met; and Those associated with post closure. The network's current high level objectives can be summarized as follows: Share experience and best practice in the key issues running up to determining site end points; Gain a better understanding of the potential effects of recent and forthcoming EU legislation; Assess consistency between approaches; Highlight potential gaps within the remit of site end point determination and management; and - Consider the formulation of research projects with a view to sharing time and expense. The programme of work revolves around the following key tasks: - Share information, experience and existing good practice. - Look to determine sustainable approaches to contaminated land site end point management. - Through site visits, gain first hand experience of determining an appropriate end point strategy, and identifying and resolving end point issues. Highlight the key data gaps and consider the development of programmes to either close out these gaps or to build confidence in the approaches taken. Production of position papers on each technical are a highlighting how different countries approach/resolve a specific problem. (authors)

Closure Report for Corrective Action Unit 537: Waste Sites, Nevada Test Site, Nevada

International Nuclear Information System (INIS)

NSTec Environmental Restoration

2007-01-01

Corrective Action Unit (CAU) 537 is identified in the ''Federal Facility Agreement and Consent Order'' (FFACO) of 1996 as Waste Sites. CAU 537 is located in Areas 3 and 19 of the Nevada Test Site, approximately 65 miles northwest of Las Vegas, Nevada, and consists of the following two Corrective Action Sites (CASs): CAS 03-23-06, Bucket; Yellow Tagged Bags; and CAS 19-19-01, Trash Pit. CAU 537 closure activities were conducted in April 2007 according to the FFACO and Revision 3 of the Sectored Clean-up Work Plan for Housekeeping Category Waste Sites (U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office [NNSA/NSO], 2003). At CAS 03-23-06, closure activities included removal and disposal of a 15-foot (ft) by 15-ft by 8-ft tall wooden shed containing wood and metal debris and a 5-gallon plastic bucket containing deteriorated plastic bags with yellow radioactive contamination tape. The debris was transported to the Area 9 U10c Landfill for disposal after being screened for radiological contamination according to the ''NV/YMP Radiological Control Manual'' (NNSA/NSO, 2004). At CAS 19-19-01, closure activities included segregation, removal, and disposal of non-friable, non-regulated asbestos-containing material (ACM) and construction debris. The ACM was determined to be non-friable by waste characterization samples collected prior to closure activities. The ACM was removed and double-bagged by licensed, trained asbestos workers and transported to the Area 9 U10c Landfill for disposal. Construction debris was transported in end-dump trucks to the Area 9 U10c Landfill for disposal. Closure activities generated sanitary waste/construction debris and ACM. Waste generated during closure activities was appropriately managed and disposed. Waste characterization sample results are included as Appendix A of this report, and waste disposition documentation is included as Appendix B of this report. Copies of the Sectored Housekeeping Site Closure

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

Energy Technology Data Exchange (ETDEWEB)

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

2014-09-01

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

An assessment of the radiological impact of sea-dumping at the North East Atlantic dump site

International Nuclear Information System (INIS)

Delow, C.E.; Mobbs, S.F.; Hill, M.D.

1985-04-01

This report describes the models and methodology developed for the assessment of the radiological impact of disposal of low and intermediate level waste on the seabed. The development of the waste package model and the combined model of radionuclide dispersion and interactions with sediments in the world's ocean is outlined. This integrated set of models was used for the radiological assessment of sea dumping at the North-East Atlantic site, which formed part of the recent NEA review of the continued suitability of this site. The predicted radiation doses to man are presented, together with the results of the analysis of the sensitivity of the annual individual doses to critical groups to variations in model parameters. (author)

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

International Nuclear Information System (INIS)

1992-10-01

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

History of creation of Semipalatinsk test nuclear site. Chapter 1

International Nuclear Information System (INIS)

1999-01-01

In 1949 August USSR's Government adopted decision about creation of nuclear site with conditional name Uchebnyj polygon 2. For its building was chosen territory in 140 km from Semipalatinsk city. Semipalatinsk test site consists of the land of three regions: Semipalatinsk, Pavlodar, Karaganda and it occupies 18,500 km 2 of fertile land, rich with minerals. Now this territory was alienated from national using. Polygon was complex object and it incorporated three main zones: Opytnoe Pole, zone of radiation safety, site Sh. Opytnoe Pole was equipped by special constructions ensuring nuclear test conducting, its observing and registration of physical measurements and occupied 2,300 km 2 . Around of the Opytnoe Pole is situated zone of radiation safety with area 45 thousand ha. Site Sh was situated in 14 km from center of Opytnoe Pole and it was intended for distribution of individual protection devices, dosimeters and for conducting of dis-activation and sanitary works. History of the site creation is connected with building of Kurchatov city. In dozen and hundred of kilometers from Kurchatov city there were top secret objects: site Balapan with total area 100,000 ha intended for conducting of nuclear tests in wells with threshold capacity 100-200 kt. Here simultaneously with main problems on the site the military-applied works were conducted on mechanics, physics of combustion, simulation of Earthquakes and determination of seismic stability of buildings and constructions. Research site Degelen with total area 33,100 ha which has been used for underground testing of nuclear charges with small capacity. Site 10 one of large research technical complex on which two reactor units were installed. Main tasks of the complex were as follows: high-temperature fuel materials testing, conducting of fundamental researches in field of physics of fissile products, thermal physics and gas hydrodynamics. On site M a laboratory base for radiochemical, radiological and chemical

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

Plutonium-aerosol emission rates and potential inhalation exposure during cleanup and treatment test at Area 11, Nevada Test Site

International Nuclear Information System (INIS)

Shinn, J.H.; Homan, D.N.

1985-01-01

A Cleanup and Treatment (CAT) test was conducted in 1981 at Area 11, Nevada Test Site. Its purpose was to evaluate the effectiveness of using a large truck-mounted vacuum cleaner similar to those used to clean paved streets for cleaning radiological contamination from the surface of desert soils. We found that four passes with the vehicle removed 97% of the alpha contamination and reduced resuspension by 99.3 to 99.7%. Potential exposure to cleanup workers was slight when compared to natural background exposure. 7 refs., 1 fig., 2 tabs

2016 Annual Inspection and Radiological Survey Results for the Piqua, Ohio, Decommissioned Reactor Site, July 2016

Energy Technology Data Exchange (ETDEWEB)

Zimmerman, Brian [USDOE Office of Legacy Management, Washington, DC (United States); Miller, Michele [Navarro Research and Engineering, Oak Ridge, TN (United States)

2016-07-01

This report presents the findings of the annual inspection and radiological survey of the Piqua, Ohio, Decommissioned Reactor Site (site). The decommissioned nuclear power demonstration facility was inspected and surveyed on April 15, 2016. The site, located on the east bank of the Great Miami River in Piqua, Ohio, was in fair physical condition. There is no requirement for a follow-up inspection, partly because City of Piqua (City) personnel participated in a March 2016 meeting to address reoccurring safety concerns. Radiological survey results from 104 locations revealed no removable contamination. One direct beta activity reading in a floor drain on the 56-foot level (1674 disintegrations per minute [dpm]/100 square centimeters [cm2]) exceeded the minimum detectable activity (MDA). Beta activity has been detected in the past at this floor drain. The reading was well below the action level of 5000 dpm/100 cm2.

Radiological findings of the chondroblastomas on the atypical sites of the skeleton system

International Nuclear Information System (INIS)

Zhang He; Yao Weiwu; Yang Shixun; Li Minghua; Cheng Yingsheng; Zhang Huizhen

2007-01-01

Objective: To review the radiological findings of the chondroblastomas on the atypical sites of the skeleton system. Methods: We collected the total image data of 13 patients who were pathologically confirmed the chondroblastomas on the atypical sites of the bone system from the department of orthopedics in shanghai No. 6 hospital since 1991. Among all the patients, 11 eases were male and others were female. The range of age was 10-50 years and the average age of the patients was 26.2 years old. A retrospective analysis of radiological signs from different diagnostic imaging modalities was made. Results: X-ray examination was underdone on all case. On the plain X-ray films, all cases were lyric lesions. The radiolucent lesions were seen in 10 cases, mixed density in 3 cases. 10 cases manifested expansible contour. Eleven cases were performed computed tomography (CT) examination. On CT, there were visible calcification in 8 cases, sclerotic margin in 10 cases, internal septation in 4 cases. Soft masses could be seen in 3 cases. Magnetic resonance examination (MRI) was done on 5 cases. On T 1 weighted images (T 1 WI) , the lesion was hypo and intermediate intense signal and heterogeneous hyperintense signal on T 2 weighed images (T 2 WI). The fluid-fluid level and solid-fluid level were seen on 3 cases. On one post-contrast examination, the moderate enhancement was seen on the solid portion of the tumor and however, the obvious enhancement on the septation within the lesion. Conclusion: The radiological findings of the chondroblastomas on the atypical sites of the bone system were not suggestive. However, it could display some particular signs of the chondroid tumors such as calcification, septation, etc. To effectively apply the different imaging modalities can be helpful to make a right diagnosis before the operation. (authors)

Streamlined Approach for Environmental Restoration Plan for Corrective Action Unit 107: Low Impact Soil Sites, Nevada Test Site, Nevada

International Nuclear Information System (INIS)

2008-01-01

This Streamlined Approach for Environmental Restoration Plan covers activities associated with Corrective Action Unit (CAU) 107 of the Federal Facility Agreement and Consent Order (FFACO, 1996 (as amended February 2008)). CAU 107 consists of the following Corrective Action Sites (CASs) located in Areas 1, 2, 3, 4, 5, 9, 10, and 18 of the Nevada Test Site. (1) CAS 01-23-02, Atmospheric Test Site - High Alt; (2) CAS 02-23-02, Contaminated Areas (2); (3) CAS 02-23-03, Contaminated Berm; (4) CAS 02-23-10, Gourd-Amber Contamination Area; (5) CAS 02-23-11, Sappho Contamination Area; (6) CAS 02-23-12, Scuttle Contamination Area; (7) CAS 03-23-24, Seaweed B Contamination Area; (8) CAS 03-23-27, Adze Contamination Area; (9) CAS 03-23-28, Manzanas Contamination Area; (10) CAS 03-23-29, Truchas-Chamisal Contamination Area; (11) CAS 04-23-02, Atmospheric Test Site T4-a; (12) CAS 05-23-06, Atmospheric Test Site; (13) CAS 09-23-06, Mound of Contaminated Soil; (14) CAS 10-23-04, Atmospheric Test Site M-10; and (15) CAS 18-23-02, U-18d Crater (Sulky). Based on historical documentation, personnel interviews, site process knowledge, site visits, photographs, engineering drawings, field screening, analytical results, and the results of data quality objectives process (Section 3.0), closure in place with administrative controls or no further action will be implemented for CAU 107. CAU 107 closure activities will consist of verifying that the current postings required under Title 10 Code of Federal Regulations (CFR) Part 835 are in place and implementing use restrictions (URs) at two sites, CAS 03-23-29 and CAS 18-23-02. The current radiological postings combined with the URs are adequate administrative controls to limit site access and worker dose

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

Energy Technology Data Exchange (ETDEWEB)

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

2012-11-12

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

Special Nuclear Material Portal Monitoring at the Nevada Test Site

International Nuclear Information System (INIS)

DeAnn Long; Michael Murphy

2008-01-01

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

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

International Nuclear Information System (INIS)

Lyons, Craig

2010-01-01

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

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

Energy Technology Data Exchange (ETDEWEB)

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

2013-07-01

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

Special Nuclear Material Portal Monitoring at the Nevada Test Site

International Nuclear Information System (INIS)

Mike Murphy

2008-01-01

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

Corrective Action Decision Document for Corrective Action Unit 168: Area 25 and 26 Contaminated Materials and Waste Dumps, Nevada Test Site, Nevada, Rev. No.: 2 with Errata Sheet

Energy Technology Data Exchange (ETDEWEB)

Wickline, Alfred

2006-12-01

This Corrective Action Decision Document has been prepared for Corrective Action Unit (CAU) 168: Area 25 and 26, Contaminated Materials and Waste Dumps, Nevada Test Site, Nevada. The purpose of this Corrective Action Decision Document is to identify and provide a rationale for the selection of a recommended corrective action alternative for each corrective action site (CAS) within CAU 168. The corrective action investigation (CAI) was conducted in accordance with the ''Corrective Action Investigation Plan for Corrective Action Unit 168: Area 25 and 26, Contaminated Materials and Waste Dumps, Nevada Test Site, Nevada'', as developed under the ''Federal Facility Agreement and Consent Order'' (1996). Corrective Action Unit 168 is located in Areas 25 and 26 of the Nevada Test Site, Nevada and is comprised of the following 12 CASs: CAS 25-16-01, Construction Waste Pile; CAS 25-16-03, MX Construction Landfill; CAS 25-19-02, Waste Disposal Site; CAS 25-23-02, Radioactive Storage RR Cars; CAS 25-23-13, ETL - Lab Radioactive Contamination; CAS 25-23-18, Radioactive Material Storage; CAS 25-34-01, NRDS Contaminated Bunker; CAS 25-34-02, NRDS Contaminated Bunker; CAS 25-99-16, USW G3; CAS 26-08-01, Waste Dump/Burn Pit; CAS 26-17-01, Pluto Waste Holding Area; and CAS 26-19-02, Contaminated Waste Dump No.2. Analytes detected during the CAI were evaluated against preliminary action levels (PALs) to determine contaminants of concern (COCs) for CASs within CAU 168. Radiological measurements of railroad cars and test equipment were compared to unrestricted (free) release criteria. Assessment of the data generated from the CAI activities revealed the following: (1) Corrective Action Site 25-16-01 contains hydrocarbon-contaminated soil at concentrations exceeding the PAL. The contamination is at discrete locations associated with asphalt debris. (2) No COCs were identified at CAS 25-16-03. Buried construction waste is present in at least two

Radiological protection guidelines for the Formerly Utilized Sites Remedial Action Program and remote Surplus Facilities Management Program

International Nuclear Information System (INIS)

Gilbert, T.L.

1985-01-01

The need for a definitive basis for radiological guidelines and criteria for FUSRAP became apparent by 1981 and led ORO to sponsor a joint ANL/BNI/LANL/ORO effort under the chairmanship of Wayne Hansen (LANL) that resulted in a final FUSRAP radiological guidelines document in March 1983. A separate effort to develop guidelines for remedial action criteria for SFMP was in progress at PNL. The need to coordinate both efforts with impending revisions of DOE Radiological Protection Standards and impending new developments in EPA and NRC Radiological Protection Standards led to convening of the first DOE Workshop on Remedial Action Criteria in Gaithersburg, Maryland, in February 1984, followed by a second workshop in June 1984 at ANL. The major decisions were to base the criteria on dosimetry models and basic limits currently recommended by the International Commission on Radiological Protection, to emphasize the development and use of site-specific rather than generic guidelines and criteria for residual radionuclide concentrations in the ground, and to prepare a manual to accompany the guidelines that would present procedures and tables for deriving site-specific soil guidelines and criteria for the remedial action programs. A joint ANL/LANL/ORNL/PNL effort to prepare a definitive set of guidelines and a manual has been initiated. The scope, status, and current plans for this effort, and some of the key issues, are presented. 10 references, 1 table

Radiological protection guidelines for the Formerly Utilized Sites Remedial Action Program and Remote Surplus Facilities Management Program

International Nuclear Information System (INIS)

Gilbert, T.L.

1984-01-01

The need for a definitive basis for radiological guidelines and criteria for FUSRAP became apparent by 1981 and led ORO to sponsor a joint ANL/BNI/LANL/ORO effort under the chairmanship of Wayne Hansen (LANL) that resulted in a final FUSRAP radiological guidelines document in March 1983. A separate effort to develop guidelines for remedial action criteria for SFMP was in progress at PNL. The need to coordinate both efforts with impending revisions of DOE Radiological Protection Standards and impending new developments in EPA and NRC Radiological Protection Standards led to convening of the first DOE Workshop on Remedial Action Criteria in Gaithersburg, Maryland, in February 1984, followed by a second workshop in June 1984 at ANL. The major decisions were to base the criteria on dosimetry models and basic limits currently recommended by the International Commission on Radiological Protection, to emphasize the development and use of site-specific rather than generic guidelines and criteria for residual radionuclide concentrations in the ground, and to prepare a manual to accompany the guidelines that would present procedures and tables for deriving site-specific soil guidelines and criteria for the remedial action programs. A joint ANL/LANL/ORNL/PNL effort to prepare a definitive set of guidelines and a manual has been initiated. The scope, status, and current plans for this effort, and some of the key issues, are presented. 10 references, 1 table

Radiologic findings after fundoplication compared with a pH reflux test and symptoms

Energy Technology Data Exchange (ETDEWEB)

Fransson, S.G.; Soekjer, H.; Johansson, K.E.; Tibbling, L.

In a follow-up after fundoplication, 61 patients underwent a double contrast examination of the stomach and a radiologic examination to detect any gastro-oesophageal reflux. The radiologic findings were compared with pH reflux test and symptoms. Gastro-oesophageal reflux was found in 7 patients at radiologic examination. None of these patients had an adequate fundoplication at a double contrast examination of the stomach and all had symptoms indicating reflux. Recurrence of gastro-oesophageal reflux may be shown at the radiologic examination and predicted by the morphologic appearances at the double contrast examination.

Radiologic findings after fundoplication compared with a pH reflux test and symptoms

International Nuclear Information System (INIS)

Fransson, S.G.; Soekjer, H.; Johansson, K.E.; Tibbling, L.; Linkoeping Univ.; Linkoeping Univ.

1986-01-01

In a follow-up after fundoplication, 61 patients underwent a double contrast examination of the stomach and a radiologic examination to detect any gastro-oesophageal reflux. The radiologic findings were compared with pH reflux test and symptoms. Gastro-oesophageal reflux was found in 7 patients at radiologic examination. None of these patients had an adequate fundoplication at a double contrast examination of the stomach and all had symptoms indicating reflux. Recurrence of gastro-oesophageal reflux may be shown at the radiologic examination and predicted by the morphologic appearances at the double contrast examination. (orig.)

Preliminary radiological readings on the old uraniferous mining site of Rophin (Puy-de-Dome); Releves radiologiques preliminaires sur l'ancien site minier uranifere de Rophin (Puy de Dome)

Energy Technology Data Exchange (ETDEWEB)

Chareyron, Bruno

2012-05-02

After a presentation of the site, of the objectives, limits and methodology of the measurement campaign, this document reports and comments the radiological measurements performed by the CRIIRAD on the old uranium mining site of Rophin and its surroundings (gamma radiation). It comments measurements performed 1 meter above the ground and on soils, and anomalies clearly related to past industrial activities. It comments the results of a radiological analysis performed on released waters (uranium 238, radon 222), and on sediments and soils

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

International Nuclear Information System (INIS)

1991-06-01

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

The use of computer decision-making support systems to justify address rehabilitation of the Semipalatinsk test site area

OpenAIRE

Viktoria V. Zaets; Alexey V. Panov

2011-01-01

The paper describes the development of a range of optimal protective measures for remediation of the territory of the Semipalatinsk Test Site. The computer system for decision-making support, ReSCA, was employed for the estimations. Costs and radiological effectiveness of countermeasures were evaluated.

Mobile laboratories: An innovative and efficient solution for radiological characterization of sites under or after decommissioning.

Science.gov (United States)

Goudeau, V; Daniel, B; Dubot, D

2017-04-21

During the operation and the decommissioning of a nuclear site the operator must assure the protection of the workers and the environment. It must furthermore identify and classify the various wastes, while optimizing the associated costs. At all stages of the decommissioning radiological measurements are performed to determine the initial situation, to monitor the demolition and clean-up, and to verify the final situation. Radiochemical analysis is crucial for the radiological evaluation process to optimize the clean-up operations and to the respect limits defined with the authorities. Even though these types of analysis are omnipresent in activities such as the exploitation, the monitoring, and the cleaning up of nuclear plants, some nuclear sites do not have their own radiochemical analysis laboratory. Mobile facilities can overcome this lack when nuclear facilities are dismantled, when contaminated sites are cleaned-up, or in a post-accident situation. The current operations for the characterization of radiological soils of CEA nuclear facilities, lead to a large increase of radiochemical analysis. To manage this high throughput of samples in a timely manner, the CEA has developed a new mobile laboratory for the clean-up of its soils, called SMaRT (Shelter for Monitoring and nucleAR chemisTry). This laboratory is dedicated to the preparation and the radiochemical analysis (alpha, beta, and gamma) of potentially contaminated samples. In this framework, CEA and Eichrom laboratories has signed a partnership agreement to extend the analytical capacities and bring on site optimized and validated methods for different problematic. Gamma-emitting radionuclides can usually be measured in situ as little or no sample preparation is required. Alpha and beta-emitting radionuclides are a different matter. Analytical chemistry laboratory facilities are required. Mobile and transportable laboratories equipped with the necessary tools can provide all that is needed. The main

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.

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

Radiological aerial monitoring in a nuclear emergency

International Nuclear Information System (INIS)

Shin, Hyeongki; Kim, Juyoul; Jung, Gunhyo

2008-01-01

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

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

International Nuclear Information System (INIS)

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

2018-01-01

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

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

International Nuclear Information System (INIS)

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

1998-09-01

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

The use of computer decision-making support systems to justify address rehabilitation of the Semipalatinsk test site area

Directory of Open Access Journals (Sweden)

Viktoria V. Zaets

2011-05-01

Full Text Available The paper describes the development of a range of optimal protective measures for remediation of the territory of the Semipalatinsk Test Site. The computer system for decision-making support, ReSCA, was employed for the estimations. Costs and radiological effectiveness of countermeasures were evaluated.

Radiological consequence analysis with HEU and LEU fuels

Energy Technology Data Exchange (ETDEWEB)

Woodruff, W.L.; Warinner, D.K.; Matos, J.E.

1984-01-01

A model for estimating the radiological consequences from a hypothetical accident in HEU and LEU fueled research and test reactors is presented. Simple hand calculations based on fission product yield table inventories and non-site specific dispersion data may be adequate in many cases. However, more detailed inventories and site specific data on meteorological conditions and release rates and heights can result in substantial reductions in the dose estimates. LEU fuel gives essentially the same doses as HEU fuel. The plutonium buildup in the LEU fuel does not significantly increase the radiological consequences. The dose to the thyroid is the limiting dose. 10 references, 3 figures, 7 tables.

Radiological consequence analysis with HEU and LEU fuels

International Nuclear Information System (INIS)

Woodruff, W.L.; Warinner, D.K.; Matos, J.E.

1984-01-01

A model for estimating the radiological consequences from a hypothetical accident in HEU and LEU fueled research and test reactors is presented. Simple hand calculations based on fission product yield table inventories and non-site specific dispersion data may be adequate in many cases. However, more detailed inventories and site specific data on meteorological conditions and release rates and heights can result in substantial reductions in the dose estimates. LEU fuel gives essentially the same doses as HEU fuel. The plutonium buildup in the LEU fuel does not significantly increase the radiological consequences. The dose to the thyroid is the limiting dose. 10 references, 3 figures, 7 tables

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

International Nuclear Information System (INIS)

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

1985-08-01

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

75 FR 384 - Event Problem Codes Web Site; Center for Devices and Radiological Health; Availability

Science.gov (United States)

2010-01-05

... DEPARTMENT OF HEALTH AND HUMAN SERVICES Food and Drug Administration [Docket No. FDA-2009-N-0576] Event Problem Codes Web Site; Center for Devices and Radiological Health; Availability AGENCY: Food and Drug Administration, HHS. ACTION: Notice. SUMMARY: The Food and Drug Administration (FDA) is announcing...

Radiological control FY 1995 site support program plan WBS 6.7.2.4

International Nuclear Information System (INIS)

1994-09-01

The 1995 Site Support Program Plan (SSPP) brings year planning and execution year planning into a single document. The plan presented consists of the following four major sections: Overview and Introduction - Health physics has been renamed Radiological Control (RadCon) with the role of protecting workers, the public and the environment from the harmful effects of radiation resulting from the DOE Hanford Site Operations; Cost Baselines which contains cost, technical and schedule baselines; Execution Year work Plan - cost summaries and detailed descriptions of the work to be done; Appendix - including brief description of other project activities directly coupled to RadCon

Radiological control FY 1995 site support program plan WBS 6.7.2.4

Energy Technology Data Exchange (ETDEWEB)

1994-09-01

The 1995 Site Support Program Plan (SSPP) brings year planning and execution year planning into a single document. The plan presented consists of the following four major sections: Overview and Introduction - Health physics has been renamed Radiological Control (RadCon) with the role of protecting workers, the public and the environment from the harmful effects of radiation resulting from the DOE Hanford Site Operations; Cost Baselines which contains cost, technical and schedule baselines; Execution Year work Plan - cost summaries and detailed descriptions of the work to be done; Appendix - including brief description of other project activities directly coupled to RadCon.

Shielding in biomedical radiology site

International Nuclear Information System (INIS)

Bergamini, C.; Berardi, P.; Fabbri, E.

2007-01-01

The implementation of a proposed project of radiation protection for diagnostic radiology room may present some difficulties but in practice must be applied operational considerations that make some projects difficult if you must pursue the objectives of the principle of optimization applied to technical problems, dosimetric, economic and social

Post-Remediation Radiological Dose Assessment, Linde Site, Tonawanda, New York

Energy Technology Data Exchange (ETDEWEB)

Kamboj, Sunita [Argonne National Lab. (ANL), Argonne, IL (United States); Durham, Lisa A. [Argonne National Lab. (ANL), Argonne, IL (United States)

2014-06-01

A post-remediation radiological dose assessment was conducted for the Formerly Utilized Sites Remedial Action Program (FUSRAP) Linde Site by using the measured residual concentrations of the radionuclides of concern following the completion of the soils remedial action. The site’s FUSRAP-related contaminants of concern (COCs) are radionuclides associated with uranium processing activities conducted by the Manhattan Engineer District (MED) in support of the Nation’s early atomic energy and weapons program and include radium-226 (Ra-226), thorium-230 (Th-230), and total uranium (Utotal). Remedial actions to address Linde Site soils and structures were conducted in accordance with the Record of Decision for the Linde Site, Tonawanda, New York (ROD) (USACE 2000a). In the ROD, the U.S. Army Corps of Engineers (USACE) determined that the cleanup standards found in Title 40, Part 192 of the Code of Federal Regulations (40 CFR Part 192), the standards for cleanup of uranium mill sites designated under the Uranium Mill Tailings Radiation Control Act (UMTRCA), and the Nuclear Regulatory Commission (NRC) standards for decommissioning of licensed uranium and thorium mills, found in 10 CFR Part 40, Appendix A, Criterion 6(6), are Applicable or Relevant and Appropriate Requirements (ARARs) for cleanup of MED-related contamination at the Linde Site. The major elements of this remedy will involve excavation of the soils with COCs above soil cleanup levels and placement of clean materials to meet the other criteria of 40 CFR Part 192.

In situ radiation measurements at the former Soviet Nuclear Test Site

International Nuclear Information System (INIS)

Tipton, W.J.

1996-06-01

A team from the Remote Sensing Laboratory conducted a series of in situ radiological measurements at the former Soviet Nuclear Test Site near Semipalatinsk, Kazakhstan, during the period of July 21-30, 1994. The survey team measured the terrestrial gamma radiation at selected areas on the site to determine the levels of natural and man-made radiation. The survey was part of a cooperative effort between the United States team and teams of radiation scientists from the National Nuclear Center of the Republic of Kazakhstan and the V.G. Khlopin Radium Institute in St. Petersburg, Russia. In addition to in situ radiation measurements made by the United States and Russian teams, soil samples were collected and analyzed by the Russian and Kazakhstani teams. All teams conducted their measurements at ten locations within the test site. The United States team also made a number of additional measurements to locate and verify the positions of three potential fallout plumes containing plutonium contamination from nonnuclear tests. In addition, the United States team made several measurements in Kurchatov City, the housing area used by personnel and their families who work(ed) at the test sites. Comparisons between the United States and Russian in situ measurements and the soil sample results are presented as well as comparisons with a Soviet aerial survey conducted in 1990-1991. The agreement between the different types of measurements made by all three countries was quite good

The atolls of Mururoa and Fangataufa (French Polynesia). The nuclear testings. Radiological aspects

International Nuclear Information System (INIS)

Martin, G.

2007-01-01

This report provides a review of the radiological measures implemented during the thirty year period of French nuclear tests in Polynesian atolls of Mururoa and Fangataufa. It presents full details of the practices deployed throughout these tests, including, in particular, aspects concerning radiological protection for the population and the environment. It contains all the scientific results and measurements of radioactivity performed during this period, providing concrete facts that can be used to assess the consequences these tests have had on the personnel involved, the population and the environment. (author)

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

International Nuclear Information System (INIS)

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

1987-05-01

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

Closure Report for Corrective Action Unit 107: Low Impact Soil Sites, Nevada Test Site, Nevada with ROTC-1

International Nuclear Information System (INIS)

Matthews, Patrick

2009-01-01

CAU 107, ''Low Impact Soil Sites'', consists of 15 CASs in Areas 1, 2, 3, 4, 5, 9, 10, and 18 of the NTS. The closure alternatives included No Further Action and Closure in Place with Administrative Controls. This CR provides a summary of completed closure activities. ROTC Justification: The FFACO UR as published in the Closure Report for Corrective Action Unit 107: Low Impact Soil Sites, Nevada Test Site, Nevada (NNSA/NSO, 2009) states that the UR for CAS 18-23-02, U-18d Crater (Sulky), was implemented for assumed radioactive contamination that could cause a dose greater that 25 millirems per year. This document further clarifies that this was based on particulate releases of radionuclides identified in Radiological Effluents Released from U.S. Continental Tests, 1961 through 1992 (DOE/NV, 1996). The radionuclides listed in this document are krypton (Kr)-85, Kr-85m, Kr-87, Kr-88, rubidium (Rb)-87, strontium (Sr)-89, Sr-91, yttrium (Y)-91, iodine (I)-131, I-132, I-133, I-134, I-135, xeon (Xe)-133, Xe-135, Xe-138, cesium (Cs)-135, Cs-138, barium (Ba)-139, and Ba-140.

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

International Nuclear Information System (INIS)

Feimster, E.L.

1994-04-01

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

General Employee Radiological Training and Radiological Worker Training: Program management manual

International Nuclear Information System (INIS)

1992-10-01

This manual defines and describes the DOE General Employee Radiological Training (GERT) and Radiological Worker I and II (RW I and II) Training programs. It includes material development requirements, standards and policies, and program administration. This manual applies to General Employee Radiological Training and Radiological Worker Training at all DOE contractor sites. The training materials of both GERT and RW I and II training reflect the requirements identified in the DOE Radiological Control Manual and DOE Order 5480.11. The training programs represent the minimum requirement for the standardized core materials. Each contractor shall implement the program in its entirety and may augment the standardized core materials to increase the general employee and radiological worker level of competency

Aerial radiological survey of Areas 18 and 20 Nevada Test Site. Date of survey: October-November 1980

International Nuclear Information System (INIS)

Feimster, E.L.

1985-11-01

Radiological surveys were conducted over Areas 18 and 20 at the Nevada Test Site (NTS) during the period 10 October through 13 November 1980. Separate surveys of the two areas were conducted simultaneously using arrays of NaI(Tl) scintillation crystals mounted on Messerschmitt-Bolkow-Blohm BO-105 and Hughes H-500 helicopters. Exposure rate contour maps due to total terrestrial gamma ray activity were produced for both areas. The most frequently occurring range of exposure rates was 17 to 25 μR/h for both Areas 18 and 20; the total range varied from 12 to 2000 μR/h. These values include an estimated cosmic contribution of 6 μR/h. An isocount rate contour map showing the distribution of count rates measured in the spectral window sensitive to cesium-137 was produced to show the extent of man-made contaminants in Area 18. In a similar manner, an isocount rate contour map showing the distribution of count rates measured in a spectral window sensitive to cobalt-60 was used to show the extent of man-made contaminants in Area 20. The extent of man-made contamination from the effluents of the various events in both areas shows patterns indicative of the prevailing winds during and after the events. Except for the presence of low levels of cesium-137 activity in the eastern half of Area 18, all contaminants can be correlated with the effluents of the various events. In Area 18, cesium-137 activity appears to be spread over about 30 to 40 percent of the eastern half; it does not appear to be directly associated with the events in this area. The distribution and level of background radiation in the two areas are consistent with those measured during previous surveys

Closure Report for Corrective Action Unit 254: Area 25, R-MAD Decontamination Facility, Nevada Test Site, Nevada

Energy Technology Data Exchange (ETDEWEB)

G. N. Doyle

2002-02-01

Corrective Action Unit (CAU) 254 is located in Area 25 of the Nevada Test Site (NTS), approximately 100 kilometers (km) (62 miles) northwest of Las Vegas, Nevada. The site is located within the Reactor Maintenance, Assembly and Disassembly (R-MAD) compound and consists of Building 3126, two outdoor decontamination pads, and surrounding areas within an existing fenced area measuring approximately 50 x 37 meters (160 x 120 feet). The site was used from the early 1960s to the early 1970s as part of the Nuclear Rocket Development Station program to decontaminate test-car hardware and tooling. The site was reactivated in the early 1980s to decontaminate a radiologically contaminated military tank. This Closure Report (CR) describes the closure activities performed to allow un-restricted release of the R-MAD Decontamination Facility.

The radiological testing of consumer products 1976-1978

International Nuclear Information System (INIS)

Wilkins, B.T.; Dixon, D.W.

1979-02-01

The National Radiological Protection Board's source testing laboratory has been operational since 1976. In the intervening period the types of consumer product which have received most attention have been ionisation chamber smoke detectors and liquid crystal digital watches containing gaseous tritium light sources; the results obtained on these two types of device are the main subject of this report. The report also traces the development of the practical appraisal of these devices by the Board and describes the part played by the test results in the evolution of national and international standards. (author)

Scenarios of radiological impacts in the long-term safety analysis of radioactive waste disposal at the Vector Site located in the Chernobyl exclusion zone

Energy Technology Data Exchange (ETDEWEB)

Rybalka, N.; Mykolaichuk, O. [State Nuclear Regulatory Inspectorate of Ukraine, Kyiv (Ukraine); Alekseeva, Z.; Kondratiev, S.; Nikolaev, E. [State Scientific and Technical Center for Nuclear and Radiation Safety, Kyiv (Ukraine)

2013-07-01

In Ukraine, at the Vector site in the Chernobyl exclusion zone, it is planned to dispose of large amounts of radioactive wastes, including those of Chernobyl origin, containing transuranium elements. The paper analyzes the main possible scenarios of radiological impacts of the Vector site for a long-term period after expiration of its active administrative control taking into account location of the Vector site in the exclusion zone. In the paper, assessment of total activities that can be disposed of on site is demonstrated, based on non-exceeding of admissible radiological impacts. (orig.)

Feasibility study to combine the evaluation of radiological and chemical-toxicological effects of old contaminated sites

International Nuclear Information System (INIS)

Jacob, P.; Proehl, G.

1997-01-01

The uranium mining regions of the German Federal States Saxony, Thuringia and Saxony-Anhalt are contaminated by radionuclides and by chemical substances. For both, ionizing radiations and chemicals, concepts and models exists to assess possible health effects for the population living in such areas. However, these assessment models were developed independently for both kinds of contaminants. Therefore, the 9 th Conference of the State Ministers for Environmental Protection have claimed that for the evaluation of contaminated sites the radiological and chemical contaminants should be integrated into a joint assessment. This feasibility study describes the state of the art of the concepts and models used for the evaluation of radiological and chemical contaminants. The similarities and differences of these evaluation methods are identified and discussed. Suggestions are made for an integrated assessment to standardize the evaluation of sites contaminated by radionuclides or chemicals. (orig.) [de

Radiological protection and quality control for diagnostic radiology in China

International Nuclear Information System (INIS)

Baorong, Yue

2008-01-01

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

Comprehensive engineering and radiological survey of the Bochvar VNIINM site

International Nuclear Information System (INIS)

Bazhanov, M.S.; Belousov, S.V.; Grishin, E.Zh.; Kotov, A.L.; Kuznetsov, A.Yu.; Savin, S.K.; Sukhanov, L.P.; Chernikov, M.A.; Utrobin, D.V.

2012-01-01

The comprehensive engineering and radiological survey (CERS) of Bochvar VNIINM war performed in 2010-2012. During the performance of the survey, radiometric measurements were taken to determine the total activity of α-emitting radionuclides in the air of work rooms, gas releases and in the environment, α- and β-emitting radionuclides in the air of work rooms, air releases from the site, waste waters, samples of snow, soil and vegetation, and in process oils. As a result of the work, experience was obtained in performing CERS of buildings and territory, standardized CERS programmes were developed, essential information was collected about radioactive contamination of both buildings and territory of the Bochvar VNIINM [ru

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 safety and risk assessment

International Nuclear Information System (INIS)

Hunter, P.H.; Barg, D.C.; Baird, R.D.; Card, D.H.; de Souza, F.; Elder, J.; Felthauser, K.; Jensen, C.; Winkler, V.

1982-02-01

A brief radiological safety and risk assessment of a nuclear power generation center with an adjacent on-site waste disposal facility at a specific site in the State of Utah is presented. The assessment was conducted to assist in determining the feasibility and practicality of developing a nuclear energy center (NEC) in Utah consisting of nine 1250 MWe nuclear pressurized water reactor (PWR) electrical generating units arranged in 3 clusters of 3 units each known as triads. The site selected for this conceptual study is in the Horse Bench area about 15 miles directly south of the town of Green River, Utah. The radiological issues included direct radiation exposures to on-site workers and the off-site population, release of radioactive material, and effects of these releases for both normal operations and accidental occurrences. The basic finding of this study is that the concept of an NEC in the Green River area, specifically at the Horse Bench site, is radiologically feasible

How to Read Your Radiology Report

Science.gov (United States)

... Site Index A-Z How to Read Your Radiology Report Imaging studies such as magnetic resonance imaging ( ... radiology report. top of page Sections of the Radiology Report Type of exam The type of exam ...

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

International Nuclear Information System (INIS)

1986-09-01

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

Radiological walkover survey at the site of the world's first nuclear reactor using the NAVSTAR global positioning system

International Nuclear Information System (INIS)

Sims, J.; Barry, C.; Efird, C.

1994-01-01

A radiological walkover survey was conducted by Bechtel National, Inc. (BNI) in the spring of 1994 at Site A, the site of the world's first nuclear reactor pilot plant facility. The objective of this survey was to provide comprehensive information regarding surface radiation levels to support identification and documentation of unknown contaminated areas and selection of future sample locations, and provide information for health and safety coverage during field investigations. The technique used represented a new application integrating the radiation measuring instrumentation with the global positioning system (GPS) in real-time differential mode. The integrated mapping and radiation survey system (MARSS) developed by J.S. Bland Associates, Inc. (JSB) simultaneously recorded direct radiation, exposure rate, and position data. Site A is in the Palos Forest Preserve, about 20 miles southwest of downtown Chicago, Illinois. The topography of the site is relatively flat (usually less than 5 % grade), with a maximum grade of 10%. Prior to the survey, the site was staked on 100-ft. centers and roughly 75% of the site was cleared of dense vegetation including trees less than 6 in. in diameter. The survey covered approximately 2 acres each day, including background determinations, source checks, calibrations, and downloading of integrated position data and radiological measurements

Enhanced radiological work planning; TOPICAL

International Nuclear Information System (INIS)

DECKER, W.A.

1999-01-01

The purpose of this standard is to provide Project Hanford Management Contractors (PHMC) with guidance for ensuring radiological considerations are adequately addressed throughout the work planning process. Incorporating radiological controls in the planning process is a requirement of the Hanford Site Radiological Control Manual (HSRCM-I), Chapter 3, Part 1. This standard is applicable to all PHMC contractors and subcontractors. The essential elements of this standard will be incorporated into the appropriate site level work control standard upon implementation of the anticipated revision of the PHMC Administration and Procedure System

Radiological-dose assessments of atolls in the northern Marshall Islands

International Nuclear Information System (INIS)

Robison, W.L.

1983-04-01

The Marshall Islands in the Equatorial Pacific, specifically Enewetak and Bikini Atolls, were the site of US nuclear testing from 1946 through 1958. In 1978, the Northern Marshall Islands Radiological Survey was conducted to evaluate the radiological conditions of two islands and ten atolls downwind of the proving grounds. The survey included aerial external gamma measurements and collection of soil, terrestrial, and marine samples for radionuclide analysis to determine the radiological dose from all exposure pathways. The methods and models used to estimate doses to a population in an environment where natural processes have acted on the source-term radionuclides for nearly 30 y, data bases developed for the models, and results of the radiological dose analyses are described

Nevada Test Site fallout in the area of Enterprise, Utah

International Nuclear Information System (INIS)

Krey, P.W.; Hardy, E.P.; Heit, M.

1980-04-01

The analysis of a sediment core from the Enterprise reservoir in southwestern Utah has provided a record of fallout in the area dating to 1945. Assming that all the 137 Cs fallout that occurred at Enterprise reservoir between 1951 and 1957 came exclusively from the Nevada tests, an upper limit of the integrated deposit from this source is 18 mCi/km 2 of 137 Cs decay corrected to 1979 out of a total of 101 measured in 1979. The maximum infinity dose from the external radiation caused by this Nevada Test Site fallout is estimated to be 1700 mrad. This maximum dose is only a factor of two higher than the cumulative estimated dose in Enterprise derived from the radiological surveys conducted after each test. This indicates that the region around Enterprise reservoir did not experience an intrusion of fallout from NTS greatly in excess of what had been deduced from the post-shot external radiation surveys

On the population dose close to the Semipalatinsk Nuclear Test Site

International Nuclear Information System (INIS)

Hill, P.; Peterson, L.; Pivovarov, S.; Rukhin, A.; Seredavina, T.; Sushkova, N.; Artemyev, O.; Abildinova, G.

2008-01-01

Full text: As a result of nuclear weapon tests at the Semipalatinsk Nuclear Test Site (SNTS) radiation exposure of inhabitants in surrounding villages has occurred over a period of several decades. Despite a number of published reports the determination of cumulative doses to the associated population and its uncertainty has not been finalized yet. Among the factors complicating this task are a) the time passed, b) the lack of direct personal dosimetry within the population possibly exposed, c) significant migration (out and in), d) inhomogeneous distribution of radionuclide deposition, e) new settlers at the SNTS and f) economic activities at the SNTS. This paper reports on the contribution of the ISTC-project K-465.2 'Complex examination of Semipalatinsk Test Site Region's population by advanced dosimetry methods' in assessing the population dose. The main results have been obtained during a period of three years by using the recent methodological progress made in EPR dosimetry on tooth enamel. Tooth enamel of people from settlements Dolon, Bodene, Cheremushki, Mostik, which were affected mainly by the first atomic explosion 1949, settlement Sarjal, affected by the first thermonuclear explosion in 1953, and as a control village Maysk, where radiological and meteorological records suggest that there was no significant radionuclide deposition near this village despite its position at the borders of SNTS, were investigated. Fresh tooth samples were used, which reflect well the current radiological situation. Additional measurements included e.g. environmental monitoring and in-vivo monitoring. EPR results suggest the existence of two sub-populations with different dose distributions: One with doses in the range of expected values from both natural background and SNTS testing, and another one with still higher doses not explained by the observed radioactive contamination. This finding is rather surprising. Additional research is needed to obtain a better statistic

Operation Aqueduct: Onsite radiological safety report for announced nuclear tests, October 1989--September 1990

International Nuclear Information System (INIS)

Hernandez, G.M.; Jacklin, A.K.

1992-01-01

Aqueduct was the name assigned to the series of underground nuclear weapons tests conducted at the Nevada Test Site (NTS) from October 1, 1989, through September 30, 1990. This report includes those experiments publicly announced. Remote radiation measurements were taken during and after each nuclear event by a telemetry system. Reynolds Electrical ampersand Engineering Co., Inc. (REECO) Health Protection Department (HPD) Radiation Protection Technicians (RPTS) with portable radiation detection instruments surveyed reentry routes into ground zeros (GZ) before other planned entries were made. Continuous surveillance was provided while personnel were in radiation areas and appropriate precautions were taken to protect persons from unnecessary exposure to radiation and toxic gases. Protective clothing and equipment were issued as needed. Complete radiological safety and industrial hygiene (IH) coverage was provided during drilling and mineback operations. Telemetered and portable radiation detector measurements are listed. Detection instrumentation used is described and specific operational procedures are defined

Radiological safety evaluation for a Waste Transfer Facility at Savannah River Site

International Nuclear Information System (INIS)

Ades, M.J.

1993-01-01

This paper provides a review of the radiological safety evaluation performed for a Waste Transfer Facility (WTF) located at the Savannah River Site (SRS). This facility transfers liquid radioactive waste between various waste processing facilities and waste storage facilities. The WTF includes functional components such as the diversion box and the pump pits, waste transfer lines, and the outside yard service piping and electrical services. The WSRC methodology is used to evaluate the consequences of postulated accidents that result in the release of radioactive material. Such accidents include transfer line breaks, underground liquid pathway release, fire in pump tank cells and HEPA filters, accidents due to natural phenomena, and externally induced events. Chemical hazards accidents are not considered. The analysis results indicate that the calculated mean onsite and offsite radiological consequences are bounded by the corresponding WSRC dose limits for each accident considered. Moreover, the results show that the maximum onsite and offsite doses calculated for the WTF are lower than the maximum doses determined for the whole radioactive waste facility where the WTF is located

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

International Nuclear Information System (INIS)

Lyons, Craig

2010-01-01

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

Radiology and social media: are private practice radiology groups more social than academic radiology departments?

Science.gov (United States)

Glover, McKinley; Choy, Garry; Boland, Giles W; Saini, Sanjay; Prabhakar, Anand M

2015-05-01

This study assesses the prevalence of use of the most commonly used social media sites among private radiology groups (PRGs) and academic radiology departments (ARDs). The 50 largest PRGs and the 50 ARDs with the highest level of funding from the National Institutes of Health were assessed for presence of a radiology-specific social media account on Facebook, Twitter, Instagram, Pinterest, YouTube, and LinkedIn. Measures of organizational activity and end-user activity were collected, including the number of posts and followers, as appropriate; between-group comparisons were performed. PRGs adopted Facebook 12 months earlier (P = .02) and Twitter 18 months earlier (P = .02) than did ARDs. A total of 76% of PRGs maintained ≥1 account on the social media sites included in the study, compared with 28% of ARDs (P Instagram, 2%. The prevalence of radiology-specific social media accounts for ARDs was: Facebook, 18%; LinkedIn, 0%; Twitter, 24%; YouTube, 6%; Pinterest, 0%; and Instagram, 0%. There was no significant difference between ARDs and PRGs in measures of end-user or organizational activity on Facebook or Twitter. Use of social media in health care is emerging as mainstream, with PRGs being early adopters of Facebook and Twitter in comparison with ARDs. Competitive environments and institutional policies may be strong factors that influence how social media is used by radiologists at the group and department levels. Copyright © 2015 American College of Radiology. Published by Elsevier Inc. All rights reserved.

Radiological site assessment at sun rose claim utilizing ScanPlot{sup SM} technology

Energy Technology Data Exchange (ETDEWEB)

Downey, H., E-mail: heath.downey@amecfw.com [Amec Foster Wheeler, Portland, ME (United States)

2015-07-01

ScanPlot{sup SM} gamma spectroscopy land survey system was utilized for the overland survey of uranium at the Sun Rose Claim in the Northwest Territories. The Sun Rose Claim is a former uranium exploration site and previous investigations had identified uranium ore and waste rock. ScanPlot{sup SM} radiological scan surveys were performed utilizing a backpack system. ScanPlot{sup SM} platform utilized spectroscopy grade sodium iodide detectors configured for optimal spatial coverage and radiation detection. Survey locations were recorded using an on-board global positioning system (GPS). The radiological spectral data from the radiation detectors is automatically logged and linked with the GPS coordinates to an on-board computer to create isocontour figures using a color scale to represent radioactivity levels. The advantage of utilizing the ScanPlot{sup SM} system for this assessment is that the nature and extent of uranium is provided without having to collect and assay a large number of samples. (author)

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

Corrective Action Investigation Plan for Corrective Action Unit 137: Waste Disposal Sites, Nevada Test Site, Nevada

International Nuclear Information System (INIS)

Wickline, Alfred

2005-01-01

This Corrective Action Investigation Plan (CAIP) contains project-specific information including facility descriptions, environmental sample collection objectives, and criteria for conducting site investigation activities at Corrective Action Unit (CAU) 137: Waste Disposal Sites. This CAIP has been developed in accordance with the ''Federal Facility Agreement and Consent Order'' (FFACO) (1996) that was agreed to by the State of Nevada, the U.S. Department of Energy (DOE), and the U.S. Department of Defense. Corrective Action Unit 137 contains sites that are located in Areas 1, 3, 7, 9, and 12 of the Nevada Test Site (NTS), which is approximately 65 miles (mi) northwest of Las Vegas, Nevada (Figure 1-1). Corrective Action Unit 137 is comprised of the eight corrective action sites (CASs) shown on Figure 1-1 and listed below: (1) CAS 01-08-01, Waste Disposal Site; (2) CAS 03-23-01, Waste Disposal Site; (3) CAS 03-23-07, Radioactive Waste Disposal Site; (4) CAS 03-99-15, Waste Disposal Site; (5) CAS 07-23-02, Radioactive Waste Disposal Site; (6) CAS 09-23-07, Radioactive Waste Disposal Site; (7) CAS 12-08-01, Waste Disposal Site; and (8) CAS 12-23-07, Waste Disposal Site. The Corrective Action Investigation (CAI) will include field inspections, radiological surveys, geophysical surveys, sampling of environmental media, analysis of samples, and assessment of investigation results, where appropriate. Data will be obtained to support corrective action alternative evaluations and waste management decisions. The CASs in CAU 137 are being investigated because hazardous and/or radioactive constituents may be present in concentrations that could potentially pose a threat to human health and the environment. Existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend corrective action alternatives for the CASs. Additional information will be generated by conducting a CAI before evaluating and selecting corrective action

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

International Nuclear Information System (INIS)

1992-10-01

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

Open-field test site

Science.gov (United States)

Gyoda, Koichi; Shinozuka, Takashi

1995-06-01

An open-field test site with measurement equipment, a turn table, antenna positioners, and measurement auxiliary equipment was remodelled at the CRL north-site. This paper introduces the configuration, specifications and characteristics of this new open-field test site. Measured 3-m and 10-m site attenuations are in good agreement with theoretical values, and this means that this site is suitable for using 3-m and 10-m method EMI/EMC measurements. The site is expected to be effective for antenna measurement, antenna calibration, and studies on EMI/EMC measurement methods.

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

Radiological surveillance of Remedial Action activities at the processing site, Ambrosia Lake, New Mexico, April 12--16, 1993. Final report

International Nuclear Information System (INIS)

1993-04-01

The Uranium Mill Tailings Remedial Action (UMTRA) Project's Technical Assistance Contractor (TAC) performed a radiological surveillance of the Remedial Action Contractor (RAC), MK-Ferguson and CWM Federal Environmental Services, Inc., at the processing site in Ambrosia Lake, New Mexico. The requirements and attributes examined during the audit were developed from reviewing working-level procedures developed by the RAC. Objective evidence, comments, and observations were verified based on investigating procedures, documentation, records located at the site, personal interviews, and tours of the site. No findings were identified during this audit. Ten site-specific observations, three good practice observations, and five programmatic observations are presented in this report. The overall conclusion from the surveillance is that the radiological aspects of the Ambrosia Lake, New Mexico, remedial action program are performed adequately. The results of the good practice observations indicate that the site health physics (HP) staff is taking the initiative to address and resolve potential issues, and implement suggestions useful to the UMTRA Project. However, potential exists for improving designated storage areas for general items, and the RAC Project Office should consider resolving site-specific and procedural inconsistencies

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

Energy Technology Data Exchange (ETDEWEB)

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

2010-06-15

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

Radiation Protection Research: Radiological Assessment

International Nuclear Information System (INIS)

Zeevaert, T.

2000-01-01

The objectives of SCK-CEN's research in the field of radiological impact assessment are (1) to elaborate and to improve methods and guidelines for the evaluation of restoration options for contaminated sites; (2) to develop, test and improve biosphere models for the performance assessment of radioactive waste disposal in near-surface or geological repositories; (3) to asses the impact of releases from nuclear or industrial installations. Main achievements in these areas for 2000 are summarised

Radiology in Medical Education: A Pediatric Radiology Elective as a Template for Other Radiology Courses.

Science.gov (United States)

Hilmes, Melissa A; Hyatt, Eddie; Penrod, Cody H; Fleming, Amy E; Singh, Sudha P

2016-03-01

Traditionally, the pediatric radiology elective for medical students and pediatric residents constituted a morning teaching session focused mainly on radiography and fluoroscopy. A more structured elective was desired to broaden the exposure to more imaging modalities, create a more uniform educational experience, and include assessment tools. In 2012, an introductory e-mail and formal syllabus, including required reading assignments, were sent to participants before the start date. A rotating weekly schedule was expanded to include cross-sectional imaging (ultrasound, CT, MR) and nuclear medicine. The schedule could accommodate specific goals of the pediatric resident or medical student, as requested. Starting in 2013, an online pre-test and post-test were developed, as well as an online end-of-rotation survey specific to the pediatric radiology elective. Taking the Image Gently pledge was required. A scavenger hunt tool, cue cards, and electronic modules were added. Pre-test and post-test scores, averaged over 2 years, showed improvement in radiology knowledge, with scores increasing by 27% for medical students and 21% for pediatric residents. Surveys at the end of the elective were overwhelmingly positive, with constructive criticism and complimentary comments. We have successfully created an elective experience in radiology that dedicates time to education while preserving the workflow of radiologists. We have developed tools to provide a customized experience with many self-directed learning opportunities. Our tools and techniques are easily translatable to a general or adult radiology elective. Copyright © 2016 American College of Radiology. Published by Elsevier Inc. All rights reserved.

Corrective Action Investigation Plan for Corrective Action Unit 541: Small Boy Nevada National Security Site and Nevada Test and Training Range, Nevada with ROTC 1

Energy Technology Data Exchange (ETDEWEB)

Matthews, Patrick [Navarro-Intera, LLC (N-I), Las Vegas, NV (United States)

2014-09-01

Corrective Action Unit (CAU) 541 is co-located on the boundary of Area 5 of the Nevada National Security Site and Range 65C of the Nevada Test and Training Range, approximately 65 miles northwest of Las Vegas, Nevada. CAU 541 is a grouping of sites where there has been a suspected release of contamination associated with nuclear testing. This document describes the planned investigation of CAU 541, which comprises the following corrective action sites (CASs): 05-23-04, Atmospheric Tests (6) - BFa Site; 05-45-03, Atmospheric Test Site - Small Boy. These sites are being investigated because existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend corrective action alternatives (CAAs). Additional information will be obtained by conducting a corrective action investigation before evaluating CAAs and selecting the appropriate corrective action for each CAS. The results of the field investigation will support a defensible evaluation of viable CAAs that will be presented in the investigation report. The sites will be investigated based on the data quality objectives (DQOs) developed on April 1, 2014, by representatives of the Nevada Division of Environmental Protection; U.S. Air Force; and the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Field Office. The DQO process was used to identify and define the type, amount, and quality of data needed to develop and evaluate appropriate corrective actions for CAU 541. The site investigation process also will be conducted in accordance with the Soils Activity Quality Assurance Plan, which establishes requirements, technical planning, and general quality practices to be applied to this activity. The potential contamination sources associated with CASs 05-23-04 and 05-45-03 are from nuclear testing activities conducted at the Atmospheric Tests (6) - BFa Site and Atmospheric Test Site - Small Boy sites. The presence and nature of

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

International Nuclear Information System (INIS)

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

1986-09-01

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

Formerly utilized MED/AEC Sites Remedial Action Program. Radiological survey of the Pennsylvania Railroad Landfill Site, Burrell Township, Pennsylvnia. Final Report

International Nuclear Information System (INIS)

1979-02-01

A radiological survey was conducted at the Pennsylvania Railroad Landfill Site in Burrell Township, Pennsylvania. In 1956 and 1957, approximately 11,600 tons of radioactive material was dumped at this site and was apparently scattered over an area of loss than 10 acres. The survey included measurement of the following: external gamma radiation at 1 m above the surface and at the surface throughout the site; beta--gamma dose rates at 1 cm from the surface throughout the site; concentrations of 226 Ra and 238 U in surface and subsurface soil on the site; concentrations of 210 Pb, 226 Ra, 230 Th, and 238 U in subsurface water on the site and in surface water on and near the site; and the extent of atmospheric transport of 222 Rn and progeny from the site. The general location of the residues transported to the site, except possibly small, scattered quantities of materials, was determined from the survey. In some areas on the site, beta--gamma dose rates of 1 cm from the surface were above pertinent guidelines.Analyses of sediment from water samples taken from drainage areas near the site indicate that some radioactive material is being carried from the site by surface run-off. Results of this survey indicate that there is no significant atmospheric transport of 222 Rn from the site

Radiological problems in Kazakhstan

International Nuclear Information System (INIS)

Kadyrzhanov, K.K.; Lukashenko, S.N.

2001-01-01

Kazakhstan historical development and available mineral resources have pre-determined a scale of radiological problems in the state. Kazakhstan keeps leading positions in the world in explored uranium resources and hydrocarbon raw. More than five hundred nuclear explosions were performed in various regions of Kazakhstan. There is necessity to carry out remediation actions at the former test sites of Kazakhstan, especially at the Semipalatinsk test-site (STS). But because of the high cost of such actions it should be expedient to carry out them only in case of emergency and inclusion of the former test sites lands to the national economic activity, as in general, under conditions of competent policy of inhabitants, STS doesn't represent a hazard. At the same time, we ought not to lose an invaluable scientific material of test-sites. It is necessary to keep some areas of Semipalatinsk test-site as a rarities, reflected the important stages of the human evolution. Test-sites should be considered as world laboratory for studies of artificial radionuclides behaviour in natural medium. Illustrations of radiation-hazardous objects, of used technologies and procedures, under the Kazakhstan Republic instance, show that main power industries lead to the common increase of radioactivity materials in human environment. Mankind certainly will become aware of fact that industrial activities, under the current level of science and technologies development, will lead to the common increase of radioactivity materials in human environment. Solving of radioecological problems is possible only when people review their approach to a radioactivity, as a whole. Not only specialists involved in this field, but also all local population have to know rules of radiation safety and how reasonable manage with radioactive materials

Radiological Worker II Training, Course 20301 (Live), Course 12909 (Test)

Energy Technology Data Exchange (ETDEWEB)

Harris, Jimmy D. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2017-01-13

Radiological worker training is the basic building block for any additional radiological training you may receive. Upon completing radiological worker training, you will have the basic knowledge needed to work safely, using proper radiological practices, in areas where radiological hazards exist. You will also have a better understanding of the hazards and responsibilities associated with radiological work to help prevent the carelessness that can occur when working continually with or around radioactive material. This course does not qualify you for any specific radiological work. You may be required to take additional training at individual facilities to address facility- and job-specific hazards and procedures.

Radiological protection tests for products which can lead to exposure of the public to ionizing radiation

International Nuclear Information System (INIS)

Hill, M.D.; Wrixon, A.D.; Wilkins, B.T.

1976-07-01

Testing plays an important role in deciding whether products which irradiate the general public are acceptable from a radiological protection point of view. This report discusses the role which testing should play in decision-making and develops a systematic approach to the testing of products. As an example of this approach, a proposed test programme for ionisation chamber smoke detectors is described. The use of test results as a basis for design specifications and performance requirements in the development of radiological protection standards for products is discussed. A description of the relevant standards is included. (author)

An aerial radiological survey of L Lake and Steel Creek, Savannah River Site, Aiken, South Carolina

International Nuclear Information System (INIS)

Feimster, E.L.

1992-11-01

An aerial radiological survey was conducted over a portion of the Savannah River Site along the Steel Creek Corridor during the period of July 16--31, 1986. Similar surveys of this area were performed in 1974, 1979, 1982, 1983, and 1985. This survey was flown with the same survey parameters and coverage as the 1985 survey to obtain measurements of both natural and man-made gamma radiation. These radiological measurements were used to determine if there had been any changes in concentration, spatial distribution, or estimated equivalent annual dose (mrem/yr) of the natural terrestrial background or man-made contaminants detected during the 1985 survey and earlier. The 1986 data are presented as isodose rate contour maps with overlays of corresponding 1985 survey data

Rocketdyne division annual site environmental report, Santa Susana Field Laboratory and De Soto Sites, 1992

Energy Technology Data Exchange (ETDEWEB)

none,

1993-12-14

This annual report discusses environmental monitoring at two manufacturing and test operations sites operated in the Los Angeles area by the Rocketdyne Division of Rockwell International Corporation. These are identified as the Santa Susana Field Laboratory (SSFL) and the De Soto site. These sites have been used for manufacturing, R&D, engineering, and testing in a broad range of technical fields, primarily rocket engine propulsion and nuclear reactor technology. The De Soto site is essentially light industry with some laboratory-scale R&D and has little potential impact on the environment. The SSFL site, because of its large size (2,668 acres), warranted comprehensive monitoring to assure protection of the environment. The purpose of this report is to present information on environmental and effluent monitoring primarily for the regulatory agencies involved in controlling environmental remediation, i.e., the U.S. DOE, the Nuclear Regulatory Commission (NRC), and the California State Department of Health Services (DHS) Radiologic Health Branch (RHB). For that reason, information concentrates on Area IV at SSFL as this is the site of the former nuclear operations. While the major area of interest is radiological, this report also includes a discussion of nonradiological monitoring at SSFL.

Rocketdyne division annual site environmental report, Santa Susana Field Laboratory and De Soto Site, 1991

Energy Technology Data Exchange (ETDEWEB)

none,

1992-12-03

This annual report discusses environmental monitoring at two manufacturing and test operations sites operated in the Los Angeles area by the Rocketdyne Division of Rockwell International Corporation. These are identified as the Santa Susana Field Laboratory (SSFL) and the De Soto site. These sites have been used for manufacturing, R&D, engineering, and testing in a broad range of technical fields, primarily rocket engine propulsion and nuclear reactor technology. The De Soto site is essentially light industry with some laboratory-scale R&D and has little potential impact on the environment. The SSFL site, because of its large size (2.668 acres), warranted comprehensive monitoring to assure protection of the environment. The purpose of this report is to present information on environmental and effluent monitoring primarily for the regulatory agencies involved in controlling operations with nuclear fuel or nuclear reactors. i.e., the U.S. DOE and the California State Department of Health Services (DHS). Radiologic Health Branch (RHB). For that reason. information concentrates on Area IV at SSFL as this is the site of the former nuclear operations. While the major area of interest is radiological, this report also includes a discussion of nonradiological monitoring at SSFL.

Rocketdyne division annual site environmental report, Santa Susana Field Laboratory and De Soto Sites, 1993

Energy Technology Data Exchange (ETDEWEB)

None, None

1994-10-21

This annual report discusses environmental monitoring at two manufacturing and test operations sites operated in the Los Angeles area by the Rocketdyne Division of Rockwell International Corporation. These are identified as the Santa Susana Field Laboratory (SSFL) and the De Soto site. These sites have been used for manufacturing, R&D, engineering, and testing in a broad range of technical fields, primarily rocket engine propulsion and nuclear reactor technology. The De Soto site is essentially light industry with some laboratory-scale R&D and has little potential impact on the environment. The SSFL site, because of its large size (2,668 acres), warranted comprehensive monitoring to assure protection of the environment. The purpose of this report is to present information on environmental and effluent monitoring primarily for the regulatory agencies involved in controlling environmental remediation, i.e., the U.S. DOE, the Nuclear Regulatory Commission (NRC), and the California State Department of Health Services (DHS) Radiologic Health Branch (RHB). For that reason, information concentrates on Area IV at SSFL as this is the site of the former nuclear operations. While the major area of interest is radiological, this report also includes a discussion of nonoradiological monitoring at SSFL.

Radio-ecological characterization and radiological assessment in support of regulatory supervision of legacy sites in northwest Russia

International Nuclear Information System (INIS)

Sneve, M.K.; Kiselev, M.; Shandala, N.K.

2014-01-01

The Norwegian Radiation Protection Authority has been implementing a regulatory cooperation program in the Russian Federation for over 10 years, as part of the Norwegian government's Plan of Action for enhancing nuclear and radiation safety in northwest Russia. The overall long-term objective has been the enhancement of safety culture and includes a special focus on regulatory supervision of nuclear legacy sites. The initial project outputs included appropriate regulatory threat assessments, to determine the hazardous situations and activities which are most in need of enhanced regulatory supervision. In turn, this has led to the development of new and updated norms and standards, and related regulatory procedures, necessary to address the often abnormal conditions at legacy sites. This paper presents the experience gained within the above program with regard to radio-ecological characterization of Sites of Temporary Storage for spent nuclear fuel and radioactive waste at Andreeva Bay and Gremikha in the Kola Peninsula in northwest Russia. Such characterization is necessary to support assessments of the current radiological situation and to support prospective assessments of its evolution. Both types of assessments contribute to regulatory supervision of the sites. Accordingly, they include assessments to support development of regulatory standards and guidance concerning: control of radiation exposures to workers during remediation operations; emergency preparedness and response; planned radionuclide releases to the environment; development of site restoration plans, and waste treatment and disposal. Examples of characterization work are presented which relate to terrestrial and marine environments at Andreeva Bay. The use of this data in assessments is illustrated by means of the visualization and assessment tool (DATAMAP) developed as part of the regulatory cooperation program, specifically to help control radiation exposure in operations and to support

Corrective Action Investigation Plan for Corrective Action Unit 487: Thunderwell Site, Tonopah Test Range, Nevada (Rev. No.: 0, January 2001)

Energy Technology Data Exchange (ETDEWEB)

DOE/NV

2001-01-02

This Corrective Action Investigation Plan contains the U.S. Department of Energy, Nevada Operations Office's (DOE/NV's) approach to collect the data necessary to evaluate corrective action alternatives (CAAs) appropriate for the closure of Corrective Action Unit (CAU) 487, Thunderwell Site, Tonopah Test Range (TTR), Nevada, under the Federal Facility Agreement and Consent Order. Corrective Action Unit 487 consists of a single Corrective Action Site (CAS), RG 26-001-RGRV, Thunderwell Site. The site is located in the northwest portion of the TTR, Nevada, approximately five miles northwest of the Area 3 Control Point and closest to the Cactus Flats broad basin. Historically, Sandia National Laboratories in New Mexico used CAU 487 in the early to mid-1960s for a series of high explosive tests detonated at the bottom of large cylindrical steel tubes. Historical photographs indicate that debris from these tests and subsequent operations may have been scattered and buried throughout the site. A March 2000 walk-over survey and a July 2000 geophysical survey indicated evidence of buried and surface debris in dirt mounds and areas throughout the site; however, a radiological drive-over survey also performed in July 2000 indicated that no radiological hazards were identified at this site. Based on site history, the scope of this plan is to resolve the problem statement identified during the Data Quality Objectives process that detonation activities at this CAU site may have resulted in the release of contaminants of concern into the surface/subsurface soil including total volatile and total semivolatile organic compounds, total Resource Conservation and Recovery Act metals, radionuclides, total petroleum hydrocarbons, and high explosives. Therefore, the scope of corrective action field investigation will involve excavation, drilling, and extensive soil sampling and analysis activities to determine the extent (if any) of both the lateral and vertical contamination

An automated radiological survey method for performing site remediation and decommissioning

International Nuclear Information System (INIS)

Handy, R.G.; Bolch, W.E.; Harder, G.F.; Tolaymat, T.M.

1994-01-01

A portable, computer-based method of performing environmental monitoring and assessment for site remediation and decommissioning has been developed. The integrated system has been developed to provide for survey time reductions and real-time data analysis. The technique utilizes a notebook 486 computer with the necessary hardware and software components that makes it possible to be used in an almost unlimited number of environmental monitoring and assessment scenarios. The results from a pilot, open-quotes hide-and-seekclose quotes gamma survey and an actual alpha decontamination survey were elucidated. It was found that a open-quotes hide-and-seekclose quotes survey could come up with timely and accurate conclusions about the position of the source. The use of the automated system in a Th-232 alpha survey resulted in a reduction in the standard time necessary to do a radiological survey. In addition, the ability to analyze the data on-site allowed for identification and location of areas which needed further decontamination. Finally, a discussion on possible future improvements and field conclusions was made

SA Journal of Radiology: Site Map

African Journals Online (AJOL)

Journal Home · Journals · SA Journal of Radiology · About · Log In · Register · Advanced Search · By Author · By Title. Issues. Current Issue · Archives · Open Journal Systems · Help. ISSN: 2078-6778. AJOL African Journals Online. HOW TO USE AJOL... for Researchers · for Librarians · for Authors · FAQ's · More about AJOL ...

Introduction to radiological performance assessment

International Nuclear Information System (INIS)

Moss, G.

1995-02-01

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

Sustainable land use planning at the Semipalatinsk Nuclear Test Site

International Nuclear Information System (INIS)

Coughtrey, P.J.; Ridgway, R.B.; Baumann, P.

2001-01-01

Full text: The UK Department for International Development (DFID) has recently agreed to support a project to develop a participatory sustainable land use plan for areas affected by nuclear weapons testing at Semipalatinsk. This three year project is expected to be initiated in April 2001 and will form one component of the United Nations Development Programme (UNDP) Semipalatinsk Rehabilitation Programme. The project will be undertaken by a combination of Kazakh organizations working with UK consultants and will meet its overall aim through the following main activities: Development of institutional capacity in data management and analysis; Provision of information and education on environmental contamination, hazards and risks; Development of a participatory land use planning process and piloting of the process in specific areas and communities around the test site; Integration of mineral resource extraction in the land planning process with a focus- on water resource and environmental protection and participatory approaches to resolving land use conflicts; Development of legislative tools to permit the implementation of environmental management of resource exploitation. The project will make use of both modern satellite-based imagery and more traditional methods to determine the potential for different land uses within the test site. The results obtained will be incorporated with additional information on land use. radiological and hydrological conditions at the test site through a geographical information system (GIS) provided by the project. The GIS will form the core component for collation and distribution of information on options available for use of different areas of the test site and its vicinity. A participatory rural appraisal, using tried and tested techniques, will identify local interest groups in land use planning and identify the details of their stake in the process. The groups will include owners-herders, employee-herders, and subsistence

Investigation of possible methods for equipment self-tests in digital radiology

International Nuclear Information System (INIS)

Zoetelief, J.; Idris, H. H. E.; Jansen, J. T. M.

2005-01-01

Quality control in digital radiology can be time-consuming. Equipment self-tests may significantly decrease staff workload. The two most essential parameters for radiology systems are image quality and patient dose. Concerning patient dose, information on the dose-area product (DAP) values generally forms the basis for assessment of patient dose. DAP-values can be measured using a transmission ionisation chamber or calculated from equipment settings. In the present study, various image quality parameters were derived using a contrast-detail (C-D) phantom. The investigation included a computer-aided assessment of C-D images, which produced various parameters, and also parameters based upon scoring by human observers. In addition, another parameter was calculated from modulation transfer function (MTF) measurements. The automatically calculated parameters showed good correlation with human readings, although the number of X-ray systems studied is still limited. We propose a combined evaluation of DAP and automatically calculated C-D or MTF parameters for equipment self-tests. (authors)

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

International Nuclear Information System (INIS)

1987-03-01

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

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

Radiological bile acid absorption test {sup 75}SeHCAT in patients with diarrhoea of unknown cause

Energy Technology Data Exchange (ETDEWEB)

Rudberg, U. [St. Goeran`s Hospital, Stockholm (Sweden). Dept. of Diagnostic Radiology; Nylander, B. [St. Goeran`s Hospital, Stockholm (Sweden). Dept. of Internal Medicine

1996-09-01

Purpose: The purpose with this study was to investigate the usefulness of the {sup 75}SeHCAT test in patients suffering from `functional` diarrhoea and to disclose earlier radiological investigations performed in the course of disease. Material and Methods: Twenty patients with chronic diarrhoea of unknown cause were investigated with the {sup 75}SeHCAT test. The cholestyramine test and an estimation of oro-caecal transit time (OCTT) were also performed in 13 and 10 patients respectively. Results: Ten patients had low 7-day retention ({<=}15%). Nine of these were tested with cholestyramine and 8 showed complete relief from the diarrhoea. The cholestyramine test had no effect on the 4 patients with normal bile acid retention. No correlation was found between the retention of {sup 75}SeHCAT and OCCT. A total of 80 inconclusive gastrointestinal barium examinations were performed during the course of disease. Conclusion: Pathological bile acid retention, studied with the radiological {sup 75}SeHCAT test, is common in patients with diarrhoea of unknown cause. The test should be performed earlier in the course of disease in order to prevent unnecessary radiological investigations and to reduce patient suffering and distress. (orig.).

Clinical and radiological evidence of the recurrence of reversible pegvisomant-related lipohypertrophy at the new site of injection in two women with acromegaly: a case series

Directory of Open Access Journals (Sweden)

Rochira Vincenzo

2012-01-01

Full Text Available Abstract Introduction Pegvisomant-related lipohypertrophy may revert when changing the site of injection, but the lipohypertrophy may recur at the new site of injection. The strength of evidence, however, is weak and comes from information obtained from physical examination only. Case presentation We studied two Caucasian women with acromegaly, aged 51 and 71 years, with pegvisomant-related lipohypertrophy. Our two patients were evaluated at baseline, when the site of pegvisomant injection was the periumbilical abdominal region, and then four months after switching the injection site from the abdomen to both thighs. Both physical examination and radiological studies (magnetic resonance imaging and dual energy X-ray absorptiometry demonstrated that the abdominal lipohypertrophy progressively reverted in both patients after switching the site of injection to the thighs. However, lipohypertrophy reappeared at the new site of injection. The radiological outcome confirmed the reversibility of pegvisomant-related lipohypertrophy and strengthened the body of evidence on this issue. Conclusion In clinical practice, physical examination of the injection site or sites leads to an early detection of lipohypertrophy during pegvisomant treatment. Radiological procedures may be of help to confirm subcutaneous fat changes and for a precise monitoring of fat redistribution. Patients should get appropriate information about lipohypertrophy before starting pegvisomant treatment since the rotation of the site of injection may prevent lipohypertrophy.

Computer-Based Testing: Test Site Security.

Science.gov (United States)

Rosen, Gerald A.

Computer-based testing places great burdens on all involved parties to ensure test security. A task analysis of test site security might identify the areas of protecting the test, protecting the data, and protecting the environment as essential issues in test security. Protecting the test involves transmission of the examinations, identifying the…

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

International Nuclear Information System (INIS)

Bechtel Nevada

2005-01-01

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

Corrective Action Investigation Plan for Corrective Action Unit 487: Thunderwell Site, Tonopah Test Range, Nevada (Rev. No.: 0, January 2001); TOPICAL

International Nuclear Information System (INIS)

2001-01-01

This Corrective Action Investigation Plan contains the U.S. Department of Energy, Nevada Operations Office's (DOE/NV's) approach to collect the data necessary to evaluate corrective action alternatives (CAAs) appropriate for the closure of Corrective Action Unit (CAU) 487, Thunderwell Site, Tonopah Test Range (TTR), Nevada, under the Federal Facility Agreement and Consent Order. Corrective Action Unit 487 consists of a single Corrective Action Site (CAS), RG 26-001-RGRV, Thunderwell Site. The site is located in the northwest portion of the TTR, Nevada, approximately five miles northwest of the Area 3 Control Point and closest to the Cactus Flats broad basin. Historically, Sandia National Laboratories in New Mexico used CAU 487 in the early to mid-1960s for a series of high explosive tests detonated at the bottom of large cylindrical steel tubes. Historical photographs indicate that debris from these tests and subsequent operations may have been scattered and buried throughout the site. A March 2000 walk-over survey and a July 2000 geophysical survey indicated evidence of buried and surface debris in dirt mounds and areas throughout the site; however, a radiological drive-over survey also performed in July 2000 indicated that no radiological hazards were identified at this site. Based on site history, the scope of this plan is to resolve the problem statement identified during the Data Quality Objectives process that detonation activities at this CAU site may have resulted in the release of contaminants of concern into the surface/subsurface soil including total volatile and total semivolatile organic compounds, total Resource Conservation and Recovery Act metals, radionuclides, total petroleum hydrocarbons, and high explosives. Therefore, the scope of corrective action field investigation will involve excavation, drilling, and extensive soil sampling and analysis activities to determine the extent (if any) of both the lateral and vertical contamination and whether

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.

Using SAFRAN Software to Assess Radiological Hazards from Dismantling of Tammuz-2 Reactor Core at Al-tuwaitha Nuclear Site

Science.gov (United States)

Abed Gatea, Mezher; Ahmed, Anwar A.; jundee kadhum, Saad; Ali, Hasan Mohammed; Hussein Muheisn, Abbas

2018-05-01

The Safety Assessment Framework (SAFRAN) software has implemented here for radiological safety analysis; to verify that the dose acceptance criteria and safety goals are met with a high degree of confidence for dismantling of Tammuz-2 reactor core at Al-tuwaitha nuclear site. The activities characterizing, dismantling and packaging were practiced to manage the generated radioactive waste. Dose to the worker was considered an endpoint-scenario while dose to the public has neglected due to that Tammuz-2 facility is located in a restricted zone and 30m berm surrounded Al-tuwaitha site. Safety assessment for dismantling worker endpoint-scenario based on maximum external dose at component position level in the reactor pool and internal dose via airborne activity while, for characterizing and packaging worker endpoints scenarios have been done via external dose only because no evidence for airborne radioactivity hazards outside the reactor pool. The in-situ measurements approved that reactor core components are radiologically activated by Co-60 radioisotope. SAFRAN results showed that the maximum received dose for workers are (1.85, 0.64 and 1.3mSv/y) for activities dismantling, characterizing and packaging of reactor core components respectively. Hence, the radiological hazards remain below the low level hazard and within the acceptable annual dose for workers in radiation field

American College of Radiology Accreditation Program for mammographic screening sites: Physical evaluation criteria

International Nuclear Information System (INIS)

Hendrick, R.E.; Haus, A.G.; Hubbard, L.B.; Lasky, H.J.; McCrohan, J.; McLelland, R.; Rothenberg, L.N.; Tanner, R.L.; Zinninger, M.D.

1987-01-01

The American College of Radiology has initiated a program for the accreditation of mammographic screening sites, which includes evaluation by mail of image quality and average glandular breast dose. Image quality is evaluated by use of a specially designed phantom (a modified RMI 152D Mammographic Phantom) containing simulated microcalcifications, fibrils and masses. Average glandular dose to a simulated 4.5-cm-thick (50% glandular, 50% fat) compressed breast is evaluated by thermoluminescent dosimeter measurements of entrance exposure and half value layer. Standards for acceptable image quality and patient doses are presented and preliminary results of the accreditation program are discussed

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

Radiological operating experience at FFTF [Fast Flux Test Facility

International Nuclear Information System (INIS)

Bunch, W.L.; Prevo, P.R.

1986-11-01

The Fast Flux Test Facility has been in operation for approximately five years, including about one thousand days of full power operation of the Fast Test Reactor. During that time the collective dose equivalents received by operating personnel have been about two orders of magnitude lower than those typically received at commercial light water reactors. No major contamination problems have been encountered in operating and maintaining the plant, and release of radioactive gas to the environment has been minimal and well below acceptable limits. All shields have performed satisfactorily. Experience to date indicates an apparent radiological superiority of liquid metal reactor systems over current light water plants

A radiological consequence analysis with HEU and LEU fuels

International Nuclear Information System (INIS)

Woodruff, W.L.; Warinner, D.K.; Matos, J.E.

1985-01-01

A model for estimating the radiological consequences from a hypothetical accident in HEU and LEU fueled research and test reactors is presented. Simple hand calculations based on fission product yield table inventories and nonsite specific dispersion data may be adequate in many cases. However, more detailed inventories and site specific data on meteorological conditions and release rates and heights can result in substantial reductions in the dose estimates. LEU fuel gives essentially the same doses as HEU fuel. The plutonium buildup in the LEU fuel does not significantly increase the radiological consequences. The dose to the thyroid is the limiting dose. (author)

Radiological assessment and optimization

International Nuclear Information System (INIS)

Zeevaert, T.; Sohier, A.

1998-01-01

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

Mobile Radiological Laboratories Intercomparison Measurements - Chernobyl

International Nuclear Information System (INIS)

Martincic, R.; Glavic-Cindro, D.; Korun, M.; Pucelj, B.; Vodenik, B.

2001-01-01

Full text: In last decade different institutions in European countries have organised periodic intercomparison exercises of mobile radiological laboratories to improve the preparedness of emergency monitoring teams. The 12th Regular Workshop on Mobile Radiological Laboratories was held in Exclusion Zone of the Chernobyl NPP, Ukraine from September 13 to September 18, 1999 under the acronym MORAL-12. The European Centre of Technological Safety (TESEC), Kiev, Ukraine and J. Stefan Institute, Ljubljana, Slovenia organised Intercomparison Measurements 99 jointly under the auspices of the International Atomic Energy Agency (IAEA). Nineteen teams from 9 countries and IAEA participated in the Workshop. Six field and personal and equipment contamination control exercises were prepared and conducted at two measuring sites with very different ambient dose rate levels. The Workshop pointed out that such exercises are very valuable for rapid, efficient and harmonised emergency response in case of nuclear or radiological emergency. The teams had an opportunity to test their ability to perform field measurements in the contaminated environment, and to report results on the spot, as well as to test their emergency preparedness and persistence. They gained new experiences for fieldwork under stress conditions. An overview and results of these intercomparison measurements are presented and lessons learned are discussed. (author)

Intermodal transportation of low-level radioactive waste to the Nevada Test Site

International Nuclear Information System (INIS)

1998-09-01

The Nevada Test Site (NTS) presently serves as a disposal site for low-level radioactive waste (LLW) generated by DOE-approved generators. The environmental impacts resulting from the disposal of LLW at the NTS are discussed in the Final Environmental Impact Statement (EIS) for the Nevada Test Site Off-Site Locations in the State of Nevada (NTS EIS). During the formal NTS EIS scoping period, it became clear that transportation of LLW was an issue that required attention. Therefore, the Nevada Transportation Protocol Working Group (TPWG) was formed in 1995 to identify, prioritize, and understand local issues and concerns associated with the transportation of LLW to the NTS. Currently, generators of LLW ship their waste to the NTS by legal-weight truck. In 1995, the TPWG suggested the DOE could reduce transportation costs and enhance public safety by using rail transportation. The DOE announced, in October 1996, that they would study the potential for intermodal transportation of LLW to the NTS, by transferring the LLW containers from rail cars to trucks for movements to the NTS. The TPWG and DOE/NV prepared the NTS Intermodal Transportation Facility Site and Routing Evaluation Study to present basic data and analyses on alternative rail-to-truck transfer sites and related truck routes for LLW shipments to the NTS. This Environmental Assessment (EA) identifies the potential environmental impacts and transportation risks of using new intermodal transfer sites and truck routes or continuing current operations to accomplish the objectives of minimizing radiological risk, enhancing safety, and reducing cost. DOE/NV will use the results of the assessment to decide whether or not to encourage the LLW generators and their transportation contractors to change their current operations to accomplish these objectives

Calculating the radiological parameters used in non-human biota dose assessment tools using ERICA Tool and site-specific data

Energy Technology Data Exchange (ETDEWEB)

Sotiropoulou, Maria [INRASTES, NCSR ' ' Demokritos' ' , Environmental Radioactivity Laboratory, Athens (Greece); Aristotle University of Thessaloniki, Atomic and Nuclear Physics Laboratory, Thessaloniki (Greece); Florou, Heleny [INRASTES, NCSR ' ' Demokritos' ' , Environmental Radioactivity Laboratory, Athens (Greece); Kitis, Georgios [Aristotle University of Thessaloniki, Atomic and Nuclear Physics Laboratory, Thessaloniki (Greece)

2017-11-15

The substantial complexity in ecosystem-radionuclide interactions is difficult to be represented in terms of radiological doses. Thus, radiological dose assessment tools use typical exposure situations for generalized organisms and ecosystems. In the present study, site-specific data and radioactivity measurements of terrestrial organisms (grass and herbivore mammals) and abiotic components (soil) are provided. The retrieved data are used in combination with the ERICA Assessment Tool for calculation of radiological parameters. The process of radionuclide transfer within ecosystem components is represented using concentration ratios (CRs), while for the calculation of dose rates the dose conversion coefficient (DCC) methodology is applied. Comparative assessments are performed between the generic and assessment-specific radiological parameters and between the resulting dose rates. Significant differences were observed between CRs calculated in this study and those reported in the literature for cesium and thorium, which can easily be explained. On the other hand, CRs calculated for radium are in very good agreement with those reported in the literature. The DCCs exhibited some small differences between the reference and the assessment-specific organism due to mass differences. The differences were observed for internal and external dose rates, but they were less pronounced for total dose rates which are typically used in the assessment of radiological impact. The results of the current work can serve as a basis for further studies of the radiological parameters in environments that have not been studied yet. (orig.)

Report on the pre-operational environmental radiological and micrometeorological studies around Kaiga Atomic Power Project site

International Nuclear Information System (INIS)

1999-08-01

This report presents a summary of the results of preoperational environmental radiological and micro- meteorological studies carried out during the year 1992, 1993, 1995, 1998 and 1999. Baseline radioactivity levels in Kaiga environment originating from 137 Cs, 90 Sr and natural radionuclides are given. Micro-meteorological data includes that from SODAR, tower and surface instruments. The data is compared with that observed at other NPP Sites in the country. (author)

Radiological Programs- Ambient Radon at the Yucca Mountain Site (SCPB:NA)

International Nuclear Information System (INIS)

TRW

1999-01-01

This report summarizes the results of the ambient radon monitoring activities conducted by the Radiological/Environmental Field Programs Department of the Civilian Radioactive Waste Management and Operating Contractor (CRWMS M and O), Yucca Mountain Site Characterization Office. Overall, outdoor radon concentrations measured at the Yucca Mountain site were within the range of those reported for other areas in Nevada and the continental United States. Though there was some evidence of trends with time at some monitoring sites, regional atmospheric radon concentrations to date, do not appear to have changed significantly since the inception of site characterization activities. A preliminary dose assessment yielded an estimated annual effective dose equivalent of 134 mrem based on a continuous exposure to the average ambient radon concentration measured at the Yucca Mountain site. Concentrations were measured using two types of systems, passive electret ion chambers (EIC) and continuous radon monitors (CRM). The EICs produced time-averaged radon concentration data and the CRMs were used to study radon fluctuations over time. Between 1991 and 1995, the mean radon concentration at the site, as measured by EICs placed one meter above ground level, was 0.32 ± 0.15 pCi L -1 . Radon concentrations varied between monitoring locations and between years. Station NF38, located near the North Portal of the Exploratory Studies Facility (ESF), exhibited the highest overall average radon concentration at 0.55 pCi L -1 (1992 to 1995). Concentrations appear to cycle diurnally, generally peaking in the early morning hours and being lowest in the afternoon. The data also suggested that radon concentrations may fluctuate seasonally. The work accomplished between 1991 and 1995, established radon levels in the general area surrounding Yucca Mountain. It is recommended that further work focus directly on those locations that have the greatest potential for influencing ambient radon levels

Internet use in radiology: results of a nationwide survey

Energy Technology Data Exchange (ETDEWEB)

Vorbeck, F; Zimmermann, C; Vorbeck-Meister, I; Kainberger, F; Imhof, H

1999-08-01

Purpose: To determine the number of radiologists who currently have Internet access, their use patterns on the Internet for Radiology purposes, the web sites they would recommend, and the potential site access to the Internet that they would like to see in the future. In addition, this study analyzed the best way to find nationwide radiological sites and their content. Materials and Methods: In a nationwide survey, 854 Austrian radiologist were asked to fill out and return a questionnaire about Internet access, current problems, current and future use, which web site they recommend, and about the use of e-mail. Next, the available nationwide radiological sites were searched with seven major search engines using 37 different keywords, as well as by category search, and by searching for links on the homepages of the radiological departments of all Universities of Austria. Then, the offered information of the founded pages was classified in categories. Results: Of the 210 (24.6%) radiologists who returned the questionnaire, 154 (73%) had Internet access. Time expenditure was considered the main problem using the Internet. The Internet was used for literature research by 69% of the radiologists with Internet access, for e-mail by 60%, and for congress information by 57%. In future, 43% would like to read electronic journals more often and 39% would like to use the web more intensively for scientific congresses. At the present time, we found 17 radiological web sites in Austria. The most promising way to find these sites was to use the search engines Alta Vista and Hotbot. Fifteen (88%) sites offered information for patients, seven (41%) for radiologists, five (29%) for students, and four (24%) for researchers. Summary: Many radiologists in Austria already have Internet access, although time expenditure was considered the main problem with Internet use. Survey responses showed a need for electronic journals. To our point of view, Universities and radiological societies

Internet use in radiology: results of a nationwide survey

International Nuclear Information System (INIS)

Vorbeck, F.; Zimmermann, C.; Vorbeck-Meister, I.; Kainberger, F.; Imhof, H.

1999-01-01

Purpose: To determine the number of radiologists who currently have Internet access, their use patterns on the Internet for Radiology purposes, the web sites they would recommend, and the potential site access to the Internet that they would like to see in the future. In addition, this study analyzed the best way to find nationwide radiological sites and their content. Materials and Methods: In a nationwide survey, 854 Austrian radiologist were asked to fill out and return a questionnaire about Internet access, current problems, current and future use, which web site they recommend, and about the use of e-mail. Next, the available nationwide radiological sites were searched with seven major search engines using 37 different keywords, as well as by category search, and by searching for links on the homepages of the radiological departments of all Universities of Austria. Then, the offered information of the founded pages was classified in categories. Results: Of the 210 (24.6%) radiologists who returned the questionnaire, 154 (73%) had Internet access. Time expenditure was considered the main problem using the Internet. The Internet was used for literature research by 69% of the radiologists with Internet access, for e-mail by 60%, and for congress information by 57%. In future, 43% would like to read electronic journals more often and 39% would like to use the web more intensively for scientific congresses. At the present time, we found 17 radiological web sites in Austria. The most promising way to find these sites was to use the search engines Alta Vista and Hotbot. Fifteen (88%) sites offered information for patients, seven (41%) for radiologists, five (29%) for students, and four (24%) for researchers. Summary: Many radiologists in Austria already have Internet access, although time expenditure was considered the main problem with Internet use. Survey responses showed a need for electronic journals. To our point of view, Universities and radiological societies

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

Closure Report for Corrective Action Unit 135: Areas 25 Underground Storage Tanks, Nevada Test Site, Nevada

Energy Technology Data Exchange (ETDEWEB)

D. H. Cox

2001-06-01

Corrective Action Unit (CAU) 135, Area 25 Underground Storage Tanks, was closed in accordance with the approved Corrective Action Plan (DOE/NV, 2000). CAU 135 consists of three Corrective Action Sites (CAS). Two of these CAS's were identified in the Corrective Action Investigation Data Quality Objective meeting as being improperly identified as underground storage tanks. CAS 25-02-03 identified as the Deluge Valve Pit was actually an underground electrical vault and CAS 25-02-10 identified as an Underground Storage Tank was actually a former above ground storage tank filled with demineralized water. Both of these CAS's are recommended for a no further action closure. CAS 25-02-01 the Underground Storage Tanks commonly referred to as the Engine Maintenance Assembly and Disassembly Waste Holdup Tanks and Vault was closed by decontaminating the vault structure and conducting a radiological verification survey to document compliance with the Nevada Test Site unrestricted use release criteria. The Area 25 Underground Storage Tanks, (CAS 25-02-01), referred to as the Engine Maintenance, Assembly, and Disassembly (E-MAD) Waste Holdup Tanks and Vault, were used to receive liquid waste from all of the radioactive and cell service area drains at the E-MAD Facility. Based on the results of the Corrective Action Investigation conducted in June 1999, discussed in ''The Corrective Action Investigation Plan for Corrective Action Unit 135: Area 25 Underground Storage Tanks, Nevada Test Site, Nevada'' (DOE/NV, 199a), one sample from the radiological survey of the concrete vault interior exceeded radionuclide preliminary action levels. The analytes from the sediment samples exceeded the preliminary action levels for polychlorinated biphenyls, Resource Conservation and Recovery Act metals, total petroleum hydrocarbons as diesel-range organics, and radionuclides. The CAU 135 closure activities consisted of scabbling radiological ''hot spots

Underground Nuclear Testing Program, Nevada Test Site

International Nuclear Information System (INIS)

1975-09-01

The Energy Research and Development Administration (ERDA) continues to conduct an underground nuclear testing program which includes tests for nuclear weapons development and other tests for development of nuclear explosives and methods for their application for peaceful uses. ERDA also continues to provide nuclear explosive and test site support for nuclear effects tests sponsored by the Department of Defense. This Supplement extends the Environmental Statement (WASH-1526) to cover all underground nuclear tests and preparations for tests of one megaton (1 MT) or less at the Nevada Test Site (NTS) during Fiscal Year 1976. The test activities covered include numerous continuing programs, both nuclear and non-nuclear, which can best be conducted in a remote area. However, if nuclear excavation tests or tests of yields above 1 MT or tests away from NTS should be planned, these will be covered by separate environmental statements

Radiation-related monitoring and environmental research at the Nevada Test Site

International Nuclear Information System (INIS)

Anspaugh, L.R.; Patton, S.E.; Shinn, J.H.; Black, S.C.; Costa, C.F.; Elle, D.R.; Essington, E.H.; Gilbert, R.O.; Gonzalez, D.A.; Hunter, R.B.; Medica, P.A.; McArthur, R.D.; Thompson, C.B.; O'Farrell, T.P.; Romney, E.M.

1990-01-01

Beginning with the first nuclear-weapons-related tests at the Nevada Test Site (NTS) in 1951, a radiation-related monitoring program was established to determine the levels and distribution of radionuclides released. Primary methods involved survey-meter-equipped field-monitoring teams and placement of film badges and air-sampling devices at fixed locations. Beginning in the mid-1950s, more stringent standards, the results of this monitoring program, and the results of related research programs led to increased engineering efforts to reduce local fallout. With passage of the National Environmental Policy Act and increased concern about possible effects of radiation exposure, environmental activities related to the NTS increased. There is now an extensive monitoring program at the NTS to assess radiological conditions resulting from past tests and from continued testing of nuclear-weapons devices. In populated areas near NTS, there is also a monitoring effort that relies on assistance from local communities. Other efforts include reconstruction of radiation doses received by offsite residents during the 1950s and 1960s, determination of the current inventory and distribution of radionuclides in surface soil, and studies of the movement of radionuclides in the desert ecosystem

A study on the food consumption rates for off-site radiological dose assessment around Korean Nuclear Power Plants

International Nuclear Information System (INIS)

Lee, Gab Bock; Chung, Yang Geun

2008-01-01

The internal dose by food consumption mostly accounts for radiological dose of public around Nuclear Power Plants (NPPs). But, food consumption rates applied to off-site dose calculation in Korea which are the result of field investigation around Kori NPP by the KAERI (Korea Atomic Energy Research Institute) in 1988, are not able to reflect the latest dietary characteristics of Korean. The food consumption rates to be used for radiological dose assessment in Korea are based on the maximum individual of US NRC (Nuclear Regulatory Commission) Regulatory Guide 1.109. However, the representative individual of the critical group is considered in the recent ICRP (International Commission on Radiological Protection) recommendation and European nations' practice. Therefore, the study on the re-establishment of the food consumption rates for individual around nuclear power plant sites in Korea was carried out to reflect on the recent change of the Korean dietary characteristics and to apply the representative individual of critical group to domestic regulations. The ministry of Health and Welfare Affairs has investigated the food and nutrition of nations every 3 years based on the Law of National Health Improvement. The statistical data such as mean, standard deviation, various percentile values about food consumption rates to be used for the representative individual of the critical group were analyzed by using the raw data of the national food consumption survey in 2001∼2002. Also, the food consumption rates for maximum individual are re-estimated

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)

Radiology

International Nuclear Information System (INIS)

Meyers, M.A.

1989-01-01

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

The use of Leeds Test Objects in the assessment of the performance of radiological imaging systems: an introduction

International Nuclear Information System (INIS)

Cowen, A.R.

1986-01-01

Over the preceding decade the Leeds Radiological Imaging Group have developed a range of test objects with which to assess the performance of radiological imaging systems. The types of imaging equipment which can be assessed include X-ray image intensifier television systems, small-format 100mm/105mm fluorography systems and radiographic screen-film combinations. We have recently extended our interest to the evaluation of digital radiological imaging equipment including digital subtraction fluorography and digital (greyscale) radiographic imaging systems. These test objects were initially developed for the purpose of evaluating imaging performance under laboratory conditions but they have also proved useful under field (clinical) conditions. (author)

Mixed waste characterization and certification at the Nevada Test Site

International Nuclear Information System (INIS)

Kawamura, T.A.; Dodge, R.L.; Fitzsimmons, P.K.

1988-01-01

The Radioactive Waste Management Project at the Nevada Test Site (NTS) was recently granted interim status by the state of Nevada to receive mixed waste. The RCRA Part B permit application has been revised and submitted to the state. Preliminary indications are that the permit will be granted. In conjunction with revision of the Part B permit application, pertinent DOE guidelines governing waste acceptance criteria and waste characterization were also revised. The guidelines balance the need for full characterization of hazardous constituents with ALARA precepts. Because it is not always feasible to obtain a full chemical analysis without undue or unnecessary radiological exposure of personnel, process knowledge is considered an acceptable method of waste characterization. A balance of administrative controls and verification procedures, as well as careful documentation and high standards of quality assurance, are essential to the characterization and certification program developed for the NTS

Aerial radiological surveys of Steed Pond, Savannah River Site: Dates of surveys, 1984--1989

International Nuclear Information System (INIS)

Fritzsche, A.E.; Jobst, J.E.

1993-09-01

From June 1984 to August 1985, three aerial radiological surveys were conducted over Steed Pond at the Savannah River Site in South Carolina. In addition, Steed Pond was included in larger-area surveys of the Savannah River Site in subsequent years. The surveys were conducted by the Remote Sensing Laboratory of EG ampersand G Energy Measurements, Inc., Las Vegas, Nevada, for the US Department of Energy. Airborne measurements were obtained for both natural and man-made gamma radiation over Steed Pond and surrounding areas. The first survey was conducted when the pond was filled to normal capacity for the time of the year. On September 1, 1984, the Steed Pond dam spillway failed causing the pond to drain. The four subsequent surveys were conducted with the pond drained. The second survey and the third were conducted to study silt deposits exposed by the drop in water level after the spillway's opening. Steed Pond data from the February 1987 and April 1989 Savannah River Site surveys have been included to bring this study up to date

Radiological assessment of surface water quality around proposed uranium mining site in India.

Science.gov (United States)

Jha, S K; Lenka, P; Gothankar, S; Tripathi, R M; Puranik, V D; Khating, D T

2009-06-01

The gross alpha and gross beta activities were estimated for radiological assessment of surface water quality around the proposed uranium mining site Kylleng Pyndengsohiong Mawthabah (Domiasiat), West Khasi Hills District, Meghalaya situated in a high rainfall area (12,000mm) in India. 189 Surface water samples were collected over different seasons of the year from nine different locations covering around 100km(2). Gross beta activities were found to vary from 144 to 361mBq/L which is much below the prescribed WHO limit of 1000mBq/L for drinking water. Gross alpha activities varied from 61 to 127mBq/L. These values are much below the reported gross alpha values by other countries. In about 7% of the samples the alpha activities remain exceeded the WHO guideline limit of 100mBq/L. Surface water samples collected during the summer season of the year show higher activity whereas low activity was found from samples collected during monsoon season. Results show that all water sources are acceptable as drinking water for human consumption from the radiological point of view, the higher gross alpha concentrations in a few locations remains so only for short duration during the summer season.

Radiological assessment of surface water quality around proposed uranium mining site in India

International Nuclear Information System (INIS)

Jha, S.K.; Lenka, P.; Gothankar, S.; Tripathi, R.M.; Puranik, V.D.; Khating, D.T.

2009-01-01

The gross alpha and gross beta activities were estimated for radiological assessment of surface water quality around the proposed uranium mining site Kylleng Pyndengsohiong Mawthabah (Domiasiat), West Khasi Hills District, Meghalaya situated in a high rainfall area (12,000 mm) in India. 189 Surface water samples were collected over different seasons of the year from nine different locations covering around 100 km 2 . Gross beta activities were found to vary from 144 to 361 mBq/L which is much below the prescribed WHO limit of 1000 mBq/L for drinking water. Gross alpha activities varied from 61 to 127 mBq/L. These values are much below the reported gross alpha values by other countries. In about 7% of the samples the alpha activities remain exceeded the WHO guideline limit of 100 mBq/L. Surface water samples collected during the summer season of the year show higher activity whereas low activity was found from samples collected during monsoon season. Results show that all water sources are acceptable as drinking water for human consumption from the radiological point of view, the higher gross alpha concentrations in a few locations remains so only for short duration during the summer season.

618-11 Burial Ground USRADS radiological surveys

International Nuclear Information System (INIS)

Wendling, M.A.

1994-01-01

This report summarizes and documents the results of the radiological surveys conducted from February 4 through February 10, 1993 over the 618-11 Burial Ground, Hanford Site, Richland, Washington. In addition, this report explains the survey methodology using the Ultrasonic Ranging and Data System (USRADS). The 618-11 Burial Ground radiological survey field task consisted of two activities: characterization of the specific background conditions and the radiological survey of the area. The radiological survey of the 618-11 Burial Ground, along with the background study, were conducted by Site Investigative Surveys Environmental Restoration Health Physics Organization of the Westinghouse Hanford Company. The survey methodology was based on utilization of the Ultrasonic Ranging and Data System (USRADS) for automated recording of the gross gamma radiation levels at or near six (6) inches and at three (3) feet from the surface soil

Radiological control technician: Training program management manual

International Nuclear Information System (INIS)

1992-10-01

This manual defines and describes the DOE Radiological Control Technician Core Training Program qualification and training process, material development requirements, standards and policies, and administration. The manual applies to Radiological Control Technician Training Programs at all DOE contractor sites

Formerly utilized MED/AEC sites Remedial Action Program. Radiological survey of the former Watertown Arsenal property GSA site Watertown, Massachusetts

International Nuclear Information System (INIS)

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

1983-10-01

The complete radiological survey of all the buildings located on the GSA site revealed no contamination. However, significant contamination was found on the site grounds. A total of approximately 6 m 2 of surface area exhibited elevated radiation levels. The area of contamination is centered around Section I (the burn area) and spreads out from this point. The contamination includes the subsurface, descending to the water table at the 6-ft level in some places. The contamination is primarily reprocessed depleted uranium. The ambient radiation level in the vicinity of the contamination as measured with a pressurized ionization chamber is significantly above background levels (up to 18 μR/h). As expected, no significant levels of radon contamination were found in any of the air samples. These levels of contamination of exceed the criteria as defined in ANSI 13.12 and the NRC Guidelines. The ambient radiation levels (up to 18 μR/h) are not in excess of criteria as defined in Appendix 6

Radiological field survey problems and solutions

International Nuclear Information System (INIS)

Deming, E.J.; Boerner, A.J.

1986-01-01

Situations often arise during radiological field surveys which require the health physicist to improvise and/or make spot decisions. At times these situations can be humorous, but they can also present hazards more serious than normal radiological considerations. This presentation will depict various problematic situations encountered by Oak Ridge Associated Universities Radiological Site Assessment Program in the course of performing field environmental surveys. Detailing these potential hazards can alert other field survey groups to problems they may encounter

Radionuclide radiology

International Nuclear Information System (INIS)

Scarsbrook, A.F.; Graham, R.N.J.; Perriss, R.W.; Bradley, K.M.

2006-01-01

This is the fourth in a series of short reviews of internet-based radiological educational resources, and will focus on radionuclide radiology and nuclear medicine. What follows is a list of carefully selected websites to save time in searching them out. Most of the sites cater for trainee or non-specialist radiologists, but may also be of interest to specialists for use in teaching. This article may be particularly useful to radiologists interested in the rapidly expanding field of positron emission tomography computed tomography (PET-CT). Hyperlinks are available in the electronic version of this article and were all active at the time of going to press (February 2006)

Improving Site-Specific Radiological Performance Assessments - 13431

Energy Technology Data Exchange (ETDEWEB)

Tauxe, John; Black, Paul; Catlett, Kate; Lee, Robert; Perona, Ralph; Stockton, Tom; Sully, Mike [Neptune and Company, Inc., Los Alamos, New Mexico 87544 (United States)

2013-07-01

An improved approach is presented for conducting complete and defensible radiological site-specific performance assessments (PAs) to support radioactive waste disposal decisions. The basic tenets of PA were initiated some thirty years ago, focusing on geologic disposals and evaluating compliance with regulations. Some of these regulations were inherently probabilistic (i.e., addressing uncertainty in a quantitative fashion), such as the containment requirements of the U.S. Environmental Protection Agency's (EPA's) 40 CFR 191, Environmental Radiation Protection Standards for Management and Disposal of Spent Nuclear Fuel, High-Level and Transuranic Radioactive Wastes, Chap. 191.13 [1]. Methods of analysis were developed to meet those requirements, but at their core early PAs used 'conservative' parameter values and modeling approaches. This limited the utility of such PAs to compliance evaluation, and did little to inform decisions about optimizing disposal, closure and long-term monitoring and maintenance, or, in general, maintaining doses 'as low as reasonably achievable' (ALARA). This basic approach to PA development in the United States was employed essentially unchanged through the end of the 20. century, principally by the U.S. Department of Energy (DOE). Performance assessments developed in support of private radioactive waste disposal operations, regulated by the U.S. Nuclear Regulatory Commission (NRC) and its agreement states, were typically not as sophisticated. Discussion of new approaches to PA is timely, since at the time of this writing, the DOE is in the midst of revising its Order 435.1, Radioactive Waste Management [2], and the NRC is revising 10 CFR 61, Licensing Requirements for Land Disposal of Radioactive Waste [3]. Over the previous decade, theoretical developments and improved computational technology have provided the foundation for integrating decision analysis (DA) concepts and objective-focused thinking, plus

Improving Site-Specific Radiological Performance Assessments - 13431

International Nuclear Information System (INIS)

Tauxe, John; Black, Paul; Catlett, Kate; Lee, Robert; Perona, Ralph; Stockton, Tom; Sully, Mike

2013-01-01

An improved approach is presented for conducting complete and defensible radiological site-specific performance assessments (PAs) to support radioactive waste disposal decisions. The basic tenets of PA were initiated some thirty years ago, focusing on geologic disposals and evaluating compliance with regulations. Some of these regulations were inherently probabilistic (i.e., addressing uncertainty in a quantitative fashion), such as the containment requirements of the U.S. Environmental Protection Agency's (EPA's) 40 CFR 191, Environmental Radiation Protection Standards for Management and Disposal of Spent Nuclear Fuel, High-Level and Transuranic Radioactive Wastes, Chap. 191.13 [1]. Methods of analysis were developed to meet those requirements, but at their core early PAs used 'conservative' parameter values and modeling approaches. This limited the utility of such PAs to compliance evaluation, and did little to inform decisions about optimizing disposal, closure and long-term monitoring and maintenance, or, in general, maintaining doses 'as low as reasonably achievable' (ALARA). This basic approach to PA development in the United States was employed essentially unchanged through the end of the 20. century, principally by the U.S. Department of Energy (DOE). Performance assessments developed in support of private radioactive waste disposal operations, regulated by the U.S. Nuclear Regulatory Commission (NRC) and its agreement states, were typically not as sophisticated. Discussion of new approaches to PA is timely, since at the time of this writing, the DOE is in the midst of revising its Order 435.1, Radioactive Waste Management [2], and the NRC is revising 10 CFR 61, Licensing Requirements for Land Disposal of Radioactive Waste [3]. Over the previous decade, theoretical developments and improved computational technology have provided the foundation for integrating decision analysis (DA) concepts and objective-focused thinking, plus a Bayesian approach to

Bureau of radiological health compliance testing procedures for cabinet S-ray systems

International Nuclear Information System (INIS)

Miller, E.A.; Sprau, D.

1976-01-01

A manual has been developed by the Bureau of Radiological Health of the Food and Drug Administration to establish procedures for the routine field testing of cabinet x-ray systems to determine compliance with the Federal Performance Standard for Cabinet X-Ray Systems, 21 CFR 1020.40. The manual provides specific instructions for testing each model of cabinet x-ray system. Results from the inspection are recorded on a data from which is designed to permit automatic data processing

Corrective Action Plan for Corrective Action Unit 135: Area 25 Underground Storage Tanks, Nevada Test Site, Nevada

International Nuclear Information System (INIS)

Cox, D. H.

2000-01-01

The Area 25 Underground Storage Tanks site Corrective Action Unit (CAU) 135 will be closed by unrestricted release decontamination and verification survey, in accordance with the Federal Facility Agreement and Consert Order (FFACO, 1996). The CAU includes one Corrective Action Site (CAS). The Area 25 Underground Storage Tanks, (CAS 25-02-01), referred to as the Engine-Maintenance Assembly and Disassembly (E-MAD) Waste Holdup Tanks and Vault, were used to receive liquid waste from all of the radioactive drains at the E-MAD Facility. Based on the results of the Corrective Action Investigation conducted in June 1999 discussed in the Corrective Action Investigation Plan for Corrective Action Unit 135: Area 25 Underground Storage Tanks, Nevada Test Site, Nevada (DOE/NV,1999a), one sample from the radiological survey of the concrete vault interior exceeded radionuclide preliminary action levels. The analytes from the sediment samples that exceeded the preliminary action levels are polychlorinated biphenyls, Resource Conservation and Recovery Act metals, total petroleum hydrocarbons as diesel-range organics, and radionuclides. Unrestricted release decontamination and verification involves removal of concrete and the cement-lined pump sump from the vault. After verification that the contamination has been removed, the vault will be repaired with concrete, as necessary. The radiological- and chemical-contaminated pump sump and concrete removed from the vault would be disposed of at the Area 5 Radioactive Waste Management Site. The vault interior will be field surveyed following removal of contaminated material to verify that unrestricted release criteria have been achieved

Corrective Action Plan for Corrective Action Unit 135: Area 25 Underground Storage Tanks, Nevada Test Site, Nevada

Energy Technology Data Exchange (ETDEWEB)

D. H. Cox

2000-07-01

The Area 25 Underground Storage Tanks site Corrective Action Unit (CAU) 135 will be closed by unrestricted release decontamination and verification survey, in accordance with the Federal Facility Agreement and Consert Order (FFACO, 1996). The CAU includes one Corrective Action Site (CAS). The Area 25 Underground Storage Tanks, (CAS 25-02-01), referred to as the Engine-Maintenance Assembly and Disassembly (E-MAD) Waste Holdup Tanks and Vault, were used to receive liquid waste from all of the radioactive drains at the E-MAD Facility. Based on the results of the Corrective Action Investigation conducted in June 1999 discussed in the Corrective Action Investigation Plan for Corrective Action Unit 135: Area 25 Underground Storage Tanks, Nevada Test Site, Nevada (DOE/NV,1999a), one sample from the radiological survey of the concrete vault interior exceeded radionuclide preliminary action levels. The analytes from the sediment samples that exceeded the preliminary action levels are polychlorinated biphenyls, Resource Conservation and Recovery Act metals, total petroleum hydrocarbons as diesel-range organics, and radionuclides. Unrestricted release decontamination and verification involves removal of concrete and the cement-lined pump sump from the vault. After verification that the contamination has been removed, the vault will be repaired with concrete, as necessary. The radiological- and chemical-contaminated pump sump and concrete removed from the vault would be disposed of at the Area 5 Radioactive Waste Management Site. The vault interior will be field surveyed following removal of contaminated material to verify that unrestricted release criteria have been achieved.

Guide to radiological accident considerations for siting and design of DOE nonreactor nuclear facilities

International Nuclear Information System (INIS)

Elder, J.; Graf, J.M.

1984-01-01

DOE Office of Nuclear Safety has sponsored preparation of a guidance document to aid field offices and contractors in their analyses of consequences of postulated major accidents. The guide addresses the requirements of DOE Orders 5480.1A, Chapter V, and 6430.1, including the general requirement that DOE nuclear facilities be sited, designed, and operated in accordance with standards, codes, and guides consistent with those applied to comparable licensed nuclear facilities. The guide includes both philosophical and technical information in the areas of: siting guidelines doses applied to an offsite reference person; consideration also given to an onsite reference person; physical parameters, models, and assumptions to be applied when calculating doses for comparison to siting criteria; and potential accident consequences other than radiological dose to a reference person which might affect siting and major design features of the facility, such as environmental contamination, population dose, and associated public health effects. Recommendations and/or clarifications are provided where this could be done without adding new requirements. In this regard, the guide is considered a valuable aid to the safety analyst, especially where requirements have been subject to inconsistent interpretation or where analysis methods are in transition, such as use of dose model (ICRP 2 or ICRP 30) or use of probabilistic methods of risk analysis in the siting and design of nuclear facilities

Radiological characterization of the TAN-IET facility

Energy Technology Data Exchange (ETDEWEB)

Koeppen, L.D.; Rodriguez, S.V.; Wheeler, O.A.; Cadwell, E.D.; Simpson, O.D.

1982-06-01

The Initial Engine Test (IET) facility is located on the Idaho National Engineering Laboratory (INEL) site at the north end of Test Area North (TAN). The IET facility was constructed and used for the Aircraft Nuclear Propulsion Program during the 1950's and was later used for two other programs: the Space Nuclear Auxiliary Power Transient (SNAP-TRAN) and the Hallam Decontamination and Decommissioning Project. The facility is no longer in use, therefore, a complete radiological characterization was conducted at the IET site. The characterization included measurements of beta-gamma dose rates; beta-gamma and alpha surface contamination; concentrations of selected radionuclides in subsurface storage tanks, surface soil, the exhaust duct, stack and test pad; and a walk-over surface survey of the entire facility. The information contained in this report will be of great value as the IET facility goes through the decommissioning and decontamination process.

Radiology trainer. Musculoskeletal system

International Nuclear Information System (INIS)

Staebler, A.; Erlt-Wagner, B.

2006-01-01

This book enables students to simulate examinations. The Radiology Trainer series comprises the whole knowledge of radiology in the form of case studies for self-testing. It is based on the best-sorted German-language collection of radiological examinations of all organ regions. Step by step, radiological knowledge is trained in order to make diagnoses more efficient. The book series ensures optimal preparation for the final medical examinations and is also a valuable tool for practical training. (orig.)

Radiological bioconcentration factors for aquatic, terrestrial, and wetland ecosystems at the Savannah River Site

International Nuclear Information System (INIS)

Cummins, C.L.

1994-09-01

As a result of operations at the Savannah River Site (SRS), over 50 radionuclides have been released to the atmosphere and to onsite streams and seepage basins. Now, many of these radionuclides are available to aquatic and/or terrestrial organisms for uptake and cycling through the food chain. Knowledge about the uptake and cycling of these radionuclides is now crucial in evaluating waste management and clean-up alternatives for the site. Numerous studies have been conducted at the SRS over the past forty years to study the uptake and distribution of radionuclides in the Savannah River Site environment. In many instances, bioconcentration factors have been calculated to quantify the uptake of a radionuclide by an organism from the surrounding medium (i.e., soil or water). In the past, it has been common practice to use bioconcentration factors from the literature because site-specific data were not readily available. However, because of the variability of bioconcentration factors due to experimental or environmental conditions, site-specific data should be used when available. This report compiles and summarizes site-specific bioconcentration factors for selected radionuclides released at the Savannah River Site (SRS). An extensive literature search yielded site-specific bioconcentration factors for cesium, strontium, cobalt, plutonium, americium, curium, and tritium. These eight radionuclides have been the primary radionuclides studied at SRS because of their long half lives or because they are major contributors to radiological dose from exposure. For most radionuclides, it was determined that the site-specific bioconcentration factors were higher than those reported in literature. This report also summarizes some conditions that affect radionuclide bioavailability to and bioconcentration by aquatic and terrestrial organisms

Double tracks test site characterization report

International Nuclear Information System (INIS)

1996-05-01

This report presents the results of site characterization activities performed at the Double Tracks Test Site, located on Range 71 North, of the Nellis Air Force Range (NAFR) in southern Nevada. Site characterization activities included reviewing historical data from the Double Tracks experiment, previous site investigation efforts, and recent site characterization data. The most recent site characterization activities were conducted in support of an interim corrective action to remediate the Double Tracks Test Site to an acceptable risk to human health and the environment. Site characterization was performed using a phased approach. First, previously collected data and historical records sere compiled and reviewed. Generalized scopes of work were then prepared to fill known data gaps. Field activities were conducted and the collected data were then reviewed to determine whether data gaps were filled and whether other areas needed to be investigated. Additional field efforts were then conducted, as required, to adequately characterize the site. Characterization of the Double Tracks Test Site was conducted in accordance with the US Department of Energy's (DOE) Streamlined Approach for Environmental Restoration (SAFER)

Mixed waste characterization and certification at the Nevada Test Site

International Nuclear Information System (INIS)

Kawamura, T.A.; Dodge, R.L.; Fitzsimmons, P.K.

1988-01-01

The Radioactive Waste Management Project (RWMP) at the Nevada Test Site (NTS) was recently granted interim status by the state of Nevada to receive mixed waste (MW). The RCRA Part B permit application has been revised and submitted to the state. Preliminary indications are that the permit will be granted. In conjunction with revision of the Part B Permit application, pertinent DOE guidelines governing waste acceptance criteria (WAC) and waste characterization were also revised. The guidelines balance the need for full characterization of hazardous constituents with as low as reasonably achievable (ALARA) precepts. Because it is not always feasible to obtain a full chemical analysis without undue or unnecessary radiological exposure of personnel, process knowledge is considered an acceptable method of waste characterization. A balance of administrative controls and verification procedures, as well as careful documentation and high standards of quality assurance, are essential to the characterization and certification program developed for the NTS

Quality assurance in diagnostic radiology in Hungary - first experiences in acceptance testing

International Nuclear Information System (INIS)

Porubszky, T.; Pellet, S.; Ballay, L.; Talian, L.; Giczi, F.

2003-01-01

It is a general experience that optimum imaging with minimum patient doses, moreover, the safe operation and long life of X-ray equipment can be assured by regular measurement of technical parameters and checking of their constancy (routine performance testing) only. These tests are generally known as quality control, while together with the so-called corrective actions and its management it is called (physical-technical) quality assurance (QA). In the European Union, Directive 97/43/EURATOM about radiation protection of patients requires - among others - the good practice of (physical-technical) quality assurance. In Hungary, Decree No. 31/2001. (X.3.) of the Minister of Health harmonizes all of its requirements. Acceptance testing of new diagnostic X-ray equipment is assigned to NPHC-NRIRR. QA has been a daily practice in radiation therapy and nuclear medicine for a long time. A National Patient Dose Assessment Programme has also successfully run since 1989. We had, however, only few preliminaries in QA in diagnostic radiology in the second half of the eighties. Nowadays there are running QA programmes in some hospitals and mammography centres. he testing activity of our institute is independent from manufacturers, it is run within the frame of an accredited testing laboratory, using calibrated measuring instruments and based on valid international standards. So the started way of implementing QA in diagnostic radiology needs a lot of further efforts, adapting experiences of other countries, and also some financial help to reach an acceptable level in the EU. (authors)

Resettlement of Bikini Atoll U.S. Nuclear Test Site

International Nuclear Information System (INIS)

Robinson, W.L.; Conrado, C.L.; Stuart, M.L.; Stoker, A.C.; Hamilton, T.F.

1999-01-01

The US conducted a nuclear testing program at Bikini and Enewetak Atolls in the Marshall Islands from 1946 through 1958. Several atolls, including Bikini, were contaminated as a result of the nuclear detonations. Since 1974 the authors have conducted an extensive research and monitoring program to determine the radiological conditions at the atolls, identify the critical radionuclides and pathways, estimate the radiological dose to current or resettling populations, and develop remedial measures to reduce the dose to atoll populations. This paper describes exposure pathways and radionuclides; composition of atoll soils; radionuclide transport and dose estimates; remedial measures; and reduction in dose from a combined option

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

IAEA Perspectives on Radiological Characterisation

International Nuclear Information System (INIS)

O'Sullivan, Patrick; Ljubenov, Vladan

2012-01-01

Requirements for characterization of radiological and other hazards in nuclear facilities are reflected in the IAEA Safety Standards. WS-R-5, Safety Requirements for Decommissioning of Facilities using Radioactive Material, includes a requirement that 'During the preparation of the final decommissioning plan, the extent and type of radioactive material (irradiated and contaminated structures and components) at the facility shall be determined by means of a detailed characterization survey and on the basis of records collected during the operational period'. The subsidiary Safety Guide WS-G-2.1, Decommissioning of Nuclear Power Plants and Research Reactors, further elaborates that 'A survey of radiological and non-radiological hazards provides an important input for the safety assessment and for implementing a safe approach during the work'. Although the characterisation requirements addressed in the Safety Standards relate primarily to the detailed survey activities undertaken following the shutdown of the facility, it is evident that radiological characterization is of relevance to all major phases of the lifetime of a nuclear facility, including: - the siting phase - baseline surveys are undertaken to determine background radiation levels; - the construction phase - construction materials are retained to support future calculations of radioactivity distributions; - the operational phase - surveys are done regularly, with additional surveys being required following incidents involving plant contamination; - the transition phase - detailed radiological surveys are required to support the development of the final decommissioning plan; and - the closure phase - a final survey of the site and any remaining structures will be needed to support an application for release of the site from regulatory control. In the case of facilities that are already shut down, the main purpose of radiological characterisation is to provide a reliable database of information on the

An overview of background environmental radiological surveillance around Kudankulam nuclear power project site

International Nuclear Information System (INIS)

Rajan, M.P.; Vijayakumar, B.; George, Thomas; Rajan, P.S.; Rana, B.K.; Kumar, M.; Hegde, A.G.; Chougaonkar, M.P.

2005-01-01

A modern Environmental Survey Laboratory (ESL) equipped with state-of-art nuclear counting, chemical and ecological equipment's has been set up at Kudankulam at the very beginning of construction activities to carry out pre operational and baseline radioactivity measurements. Construction activities for the two VVER type 1000 MWe reactors at the site are progressing ahead of schedule and the first unit is slated to be critical in the year 2007. This paper presents the results of environmental radiological surveillance carried out for the last one year in Kudankulam environs. General radiation background in the area varies in the range of 0.1 - 0.7 μGy/h and elevated levels as high as 20 μGy/h are noticed in beach areas. The major contribution to the background radiation in high background areas comes from 232 Th and its daughter products. The concentrations of 40 K are of normal order and comparable to other NPP sites and normal background areas. The concentrations of fallout nuclides are very low and are at global fallout levels. (author)

Radiological diagnosis of gastrointestinal bleeding

International Nuclear Information System (INIS)

Neufang, K.F.R.; Gross-Fengels, W.; Lorenz, R.

1990-01-01

In the diagnosis of acute gastrointestinal bleeding, endoscopy holds the first place today. Radiological investigations are indispensable whenever endoscopy cannot precisely localise the bleeding site, whenever a tumour is present or suspected, in all cases of lower gastrointestinal bleeding, and in haemobilia. A tailored radiological approach is recommended. The radiological basis programme should be at least a complete abdominal ultrasound study and plain abdominal radiograms. CT and ERCP scans may become necessary in selected cases. As a rule, angiographical localisation of the bleeding site will be successful only in the acute stage; selective visceral arteriograms have to be obtained, which may be executed in the digital subtraction technique in patients who are cooperating and clinically stable. Angiodysplasias and aneurysms, however, may be demonstrated angiographically in the interval as well. Upper and/or lower G.I. tract studies with barium or water-soluble contrast media may be indicated in the interval in order to demonstrate tumours, metastatic lesions, diverticula and gut malformations. (orig.) [de

Population distribution around the Nevada Test Site, 1984

International Nuclear Information System (INIS)

Smith, D.D.; Coogan, J.S.

1984-08-01

The Environmental Monitoring Systems Laboratory (EMSL-LV) conducts an offsite radiological safety program outside the boundaries of the Nevada Test Site. As part of this program, the EMSL-LV maintains a comprehensive and current listing of all rural offsite residents and dairy animals within the controllable sectors (areas where the EMSL-LV could implement protective or remedial actions that would assure public safety). This report was produced to give a brief overview of the population distribution and information on the activities within the controllable sectors. Obviously the numbers of people in a sector change dependent upon the season of the year, and such diverse information as the price of minerals which relates to the opening and closing of mining operations. Currently, the controllable sectors out to 200 kilometers from the Control Point on the NTS are considered to be the entire northeast, north-northeast, north, north-northwest, west-northwest sectors and portions of the east and east-northeast sectors. The west-southwest and south-southwest sections are considered controllable out to 40 to 80 kilometers. No major population centers or dairy farms lie within these sectors. 7 references, 5 figures, 2 tables

Radiological classification of mandibular fractures

International Nuclear Information System (INIS)

Mihailova, H.

2009-01-01

Mandibular fractures present the biggest part (up to 97%) of the facial bone fractures. Method of choice for diagnosing of mandibular fractures is conventional radiography. The aim of the issue is to present an unified radiological classification of mandibular fractures for the clinical practice. This classification includes only those clinical symptoms of mandibular fracture which could be radiologically objectified: exact anatomical localization (F1-F6), teeth in fracture line (Ta,Tb), grade of dislocation (D I, D II), occlusal disturbances (O(+), O(-)). Radiological symptoms expressed by letter and number symbols are systematized in a formula - FTDO of mandibular fractures similar to TNM formula for tumours. FTDO formula expresses radiological diagnose of each mandibular fracture but it doesn't include neither the site (left or right) of the fracture, nor the kind and number of fractures. In order to express topography and number of fractures the radiological formula is transformed into a decimal fraction. The symbols (FTD) of right mandible fracture are written in the numerator and those of the left site - in the denominator. For double and multiple fractures between the symbols for each fracture we put '+'. Symbols for occlusal disturbances are put down opposite, the fractional line. So topographo-anatomical formula (FTD/FTD)xO is formed. In this way the whole radiological information for unilateral, bilateral, single or multiple fractures of the mandible is expressed. The information in the radiological topography anatomic formula, resp. from the unified topography-anatomic classification ensures a quick and exact X-ray diagnose of mandibular fracture. In this way contributes to get better, make easier and faster X-ray diagnostic process concerning mandibular fractures. And all these is a precondition for prevention of retardation of the diagnosis mandibular fracture. (author)

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)

Radiological survey of the inactive uranium-mill tailings at the Spook site, Converse County, Wyoming

International Nuclear Information System (INIS)

Haywood, F.F.; Christian, D.J.; Chou, K.D.; Ellis, B.S.; Lorenzo, D.; Shinpaugh, W.H.

1980-05-01

Results of a radiological survey performed at the Spook site in Converse County, Wyoming, in June 1976, are presented. The mill at this site was located a short distance from the open-pit mine where the ore was obtained and where part of the tailings was dumped into the mine. Several piles of overburden or low-grade ore in the vicinity were included in the measurements of above-ground gamma exposure rate. The average exposure rate over these piles varied from 14 μR/hr, the average background exposure rate for the area, to 140 μR/hr. The average exposure rate for the tailings and former mill area was 220 μR/hr. Movement of tailings particles down dry washes was evident. The calculated concentration of 226 Ra in ten holes as a function of depth is presented graphically

Corrective Action Investigation Plan for Corrective Action Unit 137: Waste Disposal Sites, Nevada Test Site, Nevada, Rev. No.:0

Energy Technology Data Exchange (ETDEWEB)

Wickline, Alfred

2005-12-01

This Corrective Action Investigation Plan (CAIP) contains project-specific information including facility descriptions, environmental sample collection objectives, and criteria for conducting site investigation activities at Corrective Action Unit (CAU) 137: Waste Disposal Sites. This CAIP has been developed in accordance with the ''Federal Facility Agreement and Consent Order'' (FFACO) (1996) that was agreed to by the State of Nevada, the U.S. Department of Energy (DOE), and the U.S. Department of Defense. Corrective Action Unit 137 contains sites that are located in Areas 1, 3, 7, 9, and 12 of the Nevada Test Site (NTS), which is approximately 65 miles (mi) northwest of Las Vegas, Nevada (Figure 1-1). Corrective Action Unit 137 is comprised of the eight corrective action sites (CASs) shown on Figure 1-1 and listed below: (1) CAS 01-08-01, Waste Disposal Site; (2) CAS 03-23-01, Waste Disposal Site; (3) CAS 03-23-07, Radioactive Waste Disposal Site; (4) CAS 03-99-15, Waste Disposal Site; (5) CAS 07-23-02, Radioactive Waste Disposal Site; (6) CAS 09-23-07, Radioactive Waste Disposal Site; (7) CAS 12-08-01, Waste Disposal Site; and (8) CAS 12-23-07, Waste Disposal Site. The Corrective Action Investigation (CAI) will include field inspections, radiological surveys, geophysical surveys, sampling of environmental media, analysis of samples, and assessment of investigation results, where appropriate. Data will be obtained to support corrective action alternative evaluations and waste management decisions. The CASs in CAU 137 are being investigated because hazardous and/or radioactive constituents may be present in concentrations that could potentially pose a threat to human health and the environment. Existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend corrective action alternatives for the CASs. Additional information will be generated by conducting a CAI before evaluating and selecting

Nevada National Security Site Environmental Report 2016

Energy Technology Data Exchange (ETDEWEB)

Wills (editor), Cathy [National Security Technologies, LLC. (NSTec), Mercury, NV (United States)

2017-09-07

This Nevada National Security Site Environmental Report (NNSSER) was prepared to satisfy DOE Order DOE O 231.1B, “Environment, Safety and Health Reporting.” Its purpose is to (1) report compliance status with environmental standards and requirements, (2) present results of environmental monitoring of radiological and nonradiological effluents, (3) report estimated radiological doses to the public from releases of radioactive material, (4) summarize environmental incidents of noncompliance and actions taken in response to them, (5) describe the National Nuclear Security Administration Nevada Field Office (NNSA/NFO) Environmental Management System and characterize its performance, and (6) highlight significant environmental programs and efforts. This NNSSER summarizes data and compliance status for calendar year 2016 at the Nevada National Security Site (NNSS) and its two Nevada-based support facilities, the North Las Vegas Facility (NLVF) and the Remote Sensing Laboratory–Nellis (RSL-Nellis). It also addresses environmental restoration (ER) projects conducted at the Tonopah Test Range (TTR) and the Nevada Test and Training Range (NTTR). NNSA/NFO directs the management and operation of the NNSS and six sites across the nation. In addition to the NNSA itself, the six sites include two in Nevada (NLVF and RSL-Nellis) and four in other states (RSL-Andrews in Maryland, Livermore Operations in California, Los Alamos Operations in New Mexico, and Special Technologies Laboratory in California). Los Alamos, Lawrence Livermore, and Sandia National Laboratories are the principal organizations that sponsor and implement the nuclear weapons programs at the NNSS. National Security Technologies, LLC (NSTec), is the current Management and Operating contractor accountable for the successful execution of work and ensuring that work is performed in compliance with environmental regulations. The six sites all provide support to enhance the NNSS as a location for its multiple

Radiological survey results for the Peek Street site properties, Schenectady, New York

International Nuclear Information System (INIS)

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

1992-08-01

The Peek Street Industrial Facility, located at 425 Peek Street, Schenectady, New York, was operated by the General Electric Company for the Atomic Energy Commission (AEC) between 1947 and 1955. A variety of operations using radioactive materials were conducted at the site, but the main activities were to design an intermediate breeder reactor and to develop a chemical process for the recovery of uranium and plutonium from spent reactor fuel. Nonradioactive beryllium metal was machined on the site for breeder reactor application. The 4.5-acre site was decommissioned and released in October 1955. A radiological survey was conducted by Oak Ridge National Laboratory in November 1989. The survey included scan and grid point measurements of direct radiation levels outdoors on the five properties and inside the factory building, and radionuclide analysis of samples collected from each property. Radionuclide concentrations were determined in outdoor surface and subsurface soil samples from each property and in dust, debris, and structural materials from inside the factory building. Auger holes were logged to assess location and extent of possible subsurface residual soil radioactivity. Radionuclide concentrations were deter-mined in both indoor and outdoor water samples and in selected samples of vegetation. The presence of fixed and transferable surface residual radioactivity was investigated inside the factory building and on discarded materials outdoors on the property. High-volume air samples as well as additional selected indoor and outdoor soil samples were analyzed to determine levels of elemental beryllium

Assessment of the radiological impact of gamma and radon dose rates at former U mining sites in Tajikistan

International Nuclear Information System (INIS)

Lespukh, E.; Stegnar, P.; Yunusov, M.; Tilloboev, H.; Zyazev, G.; Kayukov, P.; Hosseini, A.; Strømman, G.; Salbu, B.

2013-01-01

An assessment of the radiological situation due to exposure to gamma radiation, radon ( 222 Rn) and thoron ( 220 Rn) was carried out at former uranium (U) mining and processing sites in Taboshar and at Digmai in Tajikistan. Gamma dose rate measurements were made using various field instruments. 222 Rn/ 220 Rn measurements were carried out with field instruments for instantaneous measurements and then discriminative 222 Rn/ 220 Rn solid state nuclear track detectors (SSNTD) were used for longer representative measurements. The detectors were exposed for an extended period of time in different outdoor and indoor public and residential environments at the selected U legacy sites. The results showed that gamma, 222 Rn and 220 Rn doses were in general low, which consequently implies a low to relatively low radiological risk. The radiation doses deriving from external radiation (gamma dose rate), indoor 222 Rn and 220 Rn with their short-lived progenies did not exceed national or international standards. At none of the sites investigated did the average individual annual effective doses exceed 10 mSv, the recommended threshold value for the general public. A radiation hazard could be associated with exceptional situations, such as elevated exposures to ionizing radiation at the Digmai tailings site and/or in industrial facilities, where gamma and 222 Rn/ 220 Rn dose rates could reach values of several 10 mSv/a. Current doses of ionizing radiation do not represent a hazard to the health of the resident public, with the exception of some specific situations. These issues should be adequately addressed to further reduce needless exposure of the resident public to ionizing radiation

White Paper: Curriculum in Interventional Radiology.

Science.gov (United States)

Mahnken, Andreas H; Bücker, Arno; Hohl, Christian; Berlis, Ansgar

2017-04-01

Purpose  Scope and clinical importance of interventional radiology markedly evolved over the last decades. Consequently it was acknowledged as independent subspecialty by the "European Union of Medical Specialists" (UEMS). Based on radiological imaging techniques Interventional Radiology is an integral part of Radiology. Materials und Methods  In 2009 the German Society for Interventional Radiology and minimally-invasive therapy (DeGIR) developed a structured training in Interventional Radiology. In cooperation with the German Society of Neuroradiology (DGNR) this training was extended to also cover Interventional Neuroradiology in 2012. Tailored for this training in Interventional Radiology a structured curriculum was developed, covering the scope of this modular training. Results  The curriculum is based on the DeGIR/DGNR modular training concept in Interventional Radiology. There is also an European Curriculum and Syllabus for Interventional Radiology developed by the "Cardiovascular and Interventional Radiological Society of Europe" (CIRSE). The presented curriculum in Interventional Radiology is designed to provide a uniform base for the training in Interventional Radiology in Germany, based on the competencies obtained during residency. Conclusion  This curriculum can be used as a basis for training in Interventional Radiology by all training sites. Key Points: · Interventional Radiology is an integral part of clinical radiology. · The German Society for Interventional Radiology and minimally-invasive therapy (DeGIR) developed a curriculum in Interventional Radiology. · This curriculum is an integrative basis for the training in interventional. Citation Format · Mahnken AH, Bücker A, Hohl C et al. White Paper: Curriculum in Interventional Radiology. Fortschr Röntgenstr 2017; 189: 309 - 311. © Georg Thieme Verlag KG Stuttgart · New York.

An evaluation of the chemical, radiological, and ecological conditions of West Lake on the Hanford site

Energy Technology Data Exchange (ETDEWEB)

Poston, T.M.; Price, K.L.; Newcomer, D.R.

1991-03-01

West Lake and its immediate surrounding basin represent a unique habitat that is dominated by highly saline water and soil. The basin offers a valuable research site for studies of a rare and complex wetland area in the desert. This report is an evaluation of the chemical, radiological, and ecological conditions at West Lake and describes how ground water influences site properties. The scope of this evaluation consisted of a sampling program in 1989 and a review of data from the perspective of assessing the impact of Hanford Site operations on the physical, chemical, and ecological conditions of West Lake and its surrounding basin. The water level in West Lake fluctuates in relation to changes in the water table. The connection between West Lake and ground water is also supported by the presence of {sup 3}H and {sup 99}Tc in the ground water and in the lake. There are relatively high concentrations of uranium in West Lake; the highest concentrations are found in the northernmost isolated pool. Analyses of water, sediment, vegetation, and soil indicate possible shifts of isotropic ratios that indicate a reduction of {sup 235}U. Uranium-236 was not detected in West Lake water; its presence would indicate neutron-activated {sup 235}U from fuel reprocessing at Hanford. Trace metals are found at elevated concentrations in West Lake. Arsenic, chromium, copper, and zinc were found at levels in excess of US Environmental Protection Agency water quality criteria. Levels of radiological and chemical contamination in the West Lake basin are relatively low. Concentrations of fission isotopes exceed those that could be explained by atmospheric fallout, but fall short of action levels for active waste management areas. 31 refs., 8 figs., 18 tabs.

An evaluation of the chemical, radiological, and ecological conditions of West Lake on the Hanford site

International Nuclear Information System (INIS)

Poston, T.M.; Price, K.L.; Newcomer, D.R.

1991-03-01

West Lake and its immediate surrounding basin represent a unique habitat that is dominated by highly saline water and soil. The basin offers a valuable research site for studies of a rare and complex wetland area in the desert. This report is an evaluation of the chemical, radiological, and ecological conditions at West Lake and describes how ground water influences site properties. The scope of this evaluation consisted of a sampling program in 1989 and a review of data from the perspective of assessing the impact of Hanford Site operations on the physical, chemical, and ecological conditions of West Lake and its surrounding basin. The water level in West Lake fluctuates in relation to changes in the water table. The connection between West Lake and ground water is also supported by the presence of 3 H and 99 Tc in the ground water and in the lake. There are relatively high concentrations of uranium in West Lake; the highest concentrations are found in the northernmost isolated pool. Analyses of water, sediment, vegetation, and soil indicate possible shifts of isotropic ratios that indicate a reduction of 235 U. Uranium-236 was not detected in West Lake water; its presence would indicate neutron-activated 235 U from fuel reprocessing at Hanford. Trace metals are found at elevated concentrations in West Lake. Arsenic, chromium, copper, and zinc were found at levels in excess of US Environmental Protection Agency water quality criteria. Levels of radiological and chemical contamination in the West Lake basin are relatively low. Concentrations of fission isotopes exceed those that could be explained by atmospheric fallout, but fall short of action levels for active waste management areas. 31 refs., 8 figs., 18 tabs

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...

Background report for the formerly utilized Manhattan Engineer District/Atomic Energy Commission sites program

Energy Technology Data Exchange (ETDEWEB)

None

1980-09-01

The Department of Energy is conducting a program to determine radiological conditions at sites formerly used by the Army Corps of Engineers' Manhattan Engineer District and the Atomic Energy Commission in the early years of nuclear energy development. Also included in the program are sites used in the Los Alamos plutonium development program and the Trinity atomic bomb test site. Materials, equipment, buildings, and land became contaminated, primarily with naturally occurring radioactive nuclides. They were later decontaminated in accordance with the standards and survey methods in use at that time. Since then, however, radiological criteria, and proposed guidelines for release of such sites for unrestricted use have become more stringent as research on the effects of low-level radiation has progressed. In addition, records documenting some of these decontamination efforts cannot be found, and the final radiological conditions of the sites could not be adequately determined from the records. As a result, the Formerly Utilized Sites Program was initiated in 1974 to identify these formerly used sites and to reevaluate their radiological status. This report covers efforts through June 1980 to determine the radiological status of sites for which the existing conditions could not be clearly defined. Principal contractor facilities and associated properties have already been identified and activities are continuing to identify additional sites. Any new sites located will probably be subcontractor facilities and areas used for disposal of contractor waste or equipment; however, only limited information regarding this equipment and material has been collected to date. As additional information becomes available, supplemental reports will be published.

Distributed radiology clerkship for the core clinical year of medical school.

Science.gov (United States)

Chew, Felix S

2002-11-01

The central role that diagnostic radiology has in the modern practice of medicine has not always been reflected in radiology's place in the curriculum. We developed a new radiology clerkship for undergraduate medical students during their core clinical year that was supported by Web technology. The assumptions underlying the design of the clerkship were that radiology is best learned from radiologists and that students are most receptive to learning radiology when it is related to concurrent patient care experiences. Beginning in May 2000, a required radiology clerkship experience was incorporated into the core clinical year at Wake Forest University School of Medicine. The core clinical year was organized into three 16-week blocks of clerkships. Two or four independent half-day radiology tutorial sessions were included with each clerkship block, and attended by all students in the block (approximately 35 students), regardless of their specific clerkship assignments. There were ten different radiology tutorials, each given three times during the year as students rotated through the clerkship blocks. Thus, each student attended a radiology tutorial session every four to eight weeks during the year. The topics covered during the tutorials were correlated with the content of the clerkship blocks and included adult and pediatric chest radiology, adult and pediatric abdominal radiology, body CT, neuroradiology, obstetric ultrasound, gynecologic ultrasound, osteoporosis, adult and pediatric fractures, mammography, and cervical spine trauma. The tutorials included pre- and post-test, lectures, case presentations, and sometimes tours of the radiology department. The educational emphasis was on pragmatic case-based learning exercises, development of verbal and visual vocabulary, and learning when and where to seek more information. To provide continuity and organization, Web-based curriculum materials were designed and implemented as a component of the clerkship. The home

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

International Nuclear Information System (INIS)

1996-02-01

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

Finding a criterion for site evaluation by weighting radiological, meteorological and demographic data

International Nuclear Information System (INIS)

Doury, A.; Gerard, R.

1975-01-01

The general problem of compatibility between given installations and their site, as well as more specific problems such as those associated with decisions to be taken in regard to demographic equilibrium in the environment, logically involve finding quantitative or at any rate semiquantitative criteria that will enable selection to be made under the least subjective conditions possible. Since the air is frequently the principal primary vector of effluents, especially in the case of an accident, atmospheric discharges are considered first separately. As the task is to find a ''site security index'' integrating the meteorological and demographic data with radiological data relating to the potential sources and the consequences of contamination, the authors first consider the possibility of using the man.rem concept, which has the advantage of possessing the dimension of a collective dose. In view of the objections that have been raised, particularly in connection with the controversy over the existence of a threshold for the dose-equivalent effect relation, a number of other practices are described and discussed. The conclusions are complex and subject to revision. Several definitions of site security indices can be identified and, pending the final decision stage, actually put into use, in conjunction with specific maps or graphs serving to reveal potentially important features which might be obscured by excessive integrations or summations

Nevada Test Site Waste Acceptance Criteria

International Nuclear Information System (INIS)

U.S. Department of Energy, Nevada Operations Office, Waste Acceptance Criteria

1999-01-01

This document provides the requirements, terms, and conditions under which the Nevada Test Site will accept low-level radioactive and mixed waste for disposal; and transuranic and transuranic mixed waste for interim storage at the Nevada Test Site

Environmental assessment for double tracks test site, Nevada Test Site, Nye County, Nevada

International Nuclear Information System (INIS)

1996-04-01

The U.S. Department of Energy, Nevada Operations Office (DOE/NV), with appropriate approvals from the U.S. Air Force (USAF), proposes to conduct environmental restoration operations at the Double Tracks test site located on the Nellis Air Force Range (NAFR) in Nye County, Nevada. This environmental assessment (EA) evaluates the potential environmental consequences of four alternative actions for conducting the restoration operation and of the no action alternative. The EA also identifies mitigation measures, where appropriate, designed to protect natural and cultural resources and reduce impacts to human health and safety. The environmental restoration operation at the Double Tracks test site would serve two primary objectives. First, the proposed work would evaluate the effectiveness of future restoration operations involving contamination over larger areas. The project would implement remediation technology options and evaluate how these technologies could be applied to the larger areas of contaminated soils on the Nevada Test Site (NTS), the Tonopah Test Range (TTR), and the NAFR. Second, the remediation would provide for the removal of plutonium contamination down to or below a predetermined level which would require cleanup of 1 hectare (ha) (2.5 acres), for the most likely case, or up to 3.0 ha (7.4 acres) of contaminated soil, for the upper bounding case

Bioremediation of Petroleum and Radiological Contaminated Soils at the Savannah River Site: Laboratory to Field Scale Applications

Energy Technology Data Exchange (ETDEWEB)

BRIGMON, ROBINL.

2004-06-07

In the process of Savannah River Site (SRS) operations limited amounts of waste are generated containing petroleum, and radiological contaminated soils. Currently, this combination of radiological and petroleum contaminated waste does not have an immediate disposal route and is being stored in low activity vaults. SRS developed and implemented a successful plan for clean up of the petroleum portion of the soils in situ using simple, inexpensive, bioreactor technology. Treatment in a bioreactor removes the petroleum contamination from the soil without spreading radiological contamination to the environment. This bioreactor uses the bioventing process and bioaugmentation or the addition of the select hydrocarbon degrading bacteria. Oxygen is usually the initial rate-limiting factor in the biodegradation of petroleum hydrocarbons. Using the bioventing process allowed control of the supply of nutrients and moisture based on petroleum contamination concentrations and soil type. The results of this work have proven to be a safe and cost-effective means of cleaning up low level radiological and petroleum-contaminated soil. Many of the other elements of the bioreactor design were developed or enhanced during the demonstration of a ''biopile'' to treat the soils beneath a Polish oil refinery's waste disposal lagoons. Aerobic microorganisms were isolated from the aged refinery's acidic sludge contaminated with polycyclic aromatic hydrocarbons (PAHs). Twelve hydrocarbon-degrading bacteria were isolated from the sludge. The predominant PAH degraders were tentatively identified as Achromobacter, Pseudomonas Burkholderia, and Sphingomonas spp. Several Ralstonia spp were also isolated that produce biosurfactants. Biosurfactants can enhance bioremediation by increasing the bioavailability of hydrophobic contaminants including hydrocarbons. The results indicated that the diversity of acid-tolerant PAH-degrading microorganisms in acidic oil wastes may

Radiological characteristics and radiation protection requirements in the remediation of uranium mining and milling sites in Hungary

International Nuclear Information System (INIS)

Juhasz, L.; Szerbin, P.; Lendvai, Z.; Csoevari, M.; Benkovics, I.; Varhegyi, A.

2002-01-01

After more than 35 years of operation the uranium mining and milling facilities located near the city of Pecs in the south of Hungary were finally shut down by the end of 1997. Appropriate strategies and complex plans have been prepared for the implementation of remedial action. The main principle involved in the planning of site restoration work is the application of a step-by-step approach, taking into account local conditions in the given area to the maximum extent possible. As every site considered for restoration has its own particular specifications, different solutions are, in effect, needed for each individual mining and milling site. Due to the lack of approved national regulations, a written authorisation must be obtained in relation to specific issues affecting remedial action. The radiological requirements affecting both the reuse and restoration of affected areas call for the establishment of radiation limits. (orig.)

The radiological diagnosis of bone tumors

International Nuclear Information System (INIS)

Freyschmidt, J.

1979-01-01

Since the definitive diagnosis of very many bone tumors is not only histological but also radiological it is important that the latter examination be of high quality. Prior to biopsy the differential diagnosis should be narrowed down as far as possible radiologically. The radiological procedures include conventional X-ray examination in two projections, tomography, angiography, and computerized tomography. Tomography can reveal the borders of the tumor and minute clacifications within the tumor. Angiography may show atypically vascularized areas and thus be helpful in choosing the best site for biopsy and in making a prognosis. It might reveal, for example, unusual vascularization or penetration of tumor into blood vessels. Computerized tomography allows precise delineation of the intraosseous and extraosseous borders of the tumor, and is particularly useful in this respect in regions in which angiography has its technical limitations, such as the pelvis and the spine. The radiological assessment of a tumor or tumor-like lesion should take account of the structural changes, the site of the lesion, and the age and sex of the patient. The report should include a statement about the malignancy of the lesion. (orig.) [de

Environmental remediation. Strategies and techniques for cleaning radioactively contaminated sites

International Nuclear Information System (INIS)

Falck, W. Eberhard

2001-01-01

Actions for a cleaner and safety environment have risen on social and political agendas in recent years. They include efforts to remediate contaminated sites posing a radiological risk to humans and the surrounding environment. Radiological risks can result from a variety of nuclear and non-nuclear activities. They include: nuclear or radiological accidents; nuclear weapons production and testing; poor radioactive waste management and disposal practices; industrial manufacturing involving radioactive materials; conventional mining and milling of ores and other production processes, e.g. oil and gas production, resulting in enhanced concentrations of naturally occurring radioactive materials (NORMs). The IAEA has developed a comprehensive programme directed at the remediation of radioactively contaminated sites. The programme collates and distributes knowledge about contaminated sites; appropriate methods for their characterization; assessment of their potential environmental and radiological impact; and applicable methods for their clean-up, following internationally recommended safety criteria. The overall resources, and which are technologically less advanced, to focus their efforts and chose appropriate strategies for the abatement or removal of exposure to radiation. An important aspect is the intention to 'close the loop' in the nuclear fuel cycle in the interests of sustainable energy development including nuclear power

Genitourinary and breast radiology

International Nuclear Information System (INIS)

Perriss, R.W.; Graham, R.N.J.; Scarsbrook, A.F.

2006-01-01

This is the sixth in a series of short reviews of internet-based radiological learning resources and will focus on genitourinary (GU) and breast radiology. Below are details of a few of the higher quality resources currently available. Most of the sites cater for medical students and trainee or non-specialist radiologists, but may be also be of interest to specialists, especially for use in teaching. Hyperlinks are available in the electronic version of this article and were all active at the time of going to press (July 2006)

Gastrointestinal and hepatobiliary radiology

International Nuclear Information System (INIS)

Graham, R.N.J.; Perriss, R.W.; Scarsbrook, A.F.

2006-01-01

This is the fifth in the series of short reviews of internet-based radiological learning resources and will focus on gastrointestinal (GI) and hepatobiliary radiology. Below are details of a few of the higher quality resources currently available. Most of the sites cater for medical students and trainee or non-specialist radiologists, but may be also be of interest to specialists, especially for use in teaching. Hyperlinks are available in the electronic version of this article and were all active at the time of going to press (May 2006)

Assessment of the Nevada Test Site as a Site for Distributed Resource Testing and Project Plan: March 2002

Energy Technology Data Exchange (ETDEWEB)

Horgan, S.; Iannucci, J.; Whitaker, C.; Cibulka, L.; Erdman, W.

2002-05-01

The objective of this project was to evaluate the Nevada Test Site (NTS) as a location for performing dedicated, in-depth testing of distributed resources (DR) integrated with the electric distribution system. In this large scale testing, it is desired to operate multiple DRs and loads in an actual operating environment, in a series of controlled tests to concentrate on issues of interest to the DR community. This report includes an inventory of existing facilities at NTS, an assessment of site attributes in relation to DR testing requirements, and an evaluation of the feasibility and cost of upgrades to the site that would make it a fully qualified DR testing facility.

Site Release Report for C-Well Pipeline, UE-25 Large Rocks Test Site, and 29 GSF Test Pits

International Nuclear Information System (INIS)

K.E. Rasmuson

2002-01-01

The U.S. Department of Energy has implemented a program to reclaim lands disturbed by site characterization at Yucca Mountain. Long term goals of the program are to re-establish processes on disturbed sites that will lead to self-sustaining plant communities. The Biological Opinion for Yucca Mountain Site Characterization Studies required that the U.S. Department of Energy develop a Reclamation Standards and Monitoring Plan to evaluate the success of reclamation efforts. According to the Reclamation Standards and Monitoring Plan, reclaimed sites will be monitored periodically, remediated if necessary, and eventually compared to an appropriate reference area to determine whether reclamation goals have been achieved and the site can be released from further monitoring. Plant cover, density, and species richness (success parameters) on reclaimed sites are compared to 60 percent of the values (success criteria) for the same parameters on the reference area. Small sites (less than 0.1 ha) are evaluated for release using qualitative methods while large sites (greater than 0.1 ha) are evaluated using quantitative methods. In the summer of 2000, 31 small sites reclaimed in 1993 and 1994 were evaluated for reclamation success and potential release from further monitoring. Plant density, cover, and species richness were estimated on the C-Well Pipeline, UE-25 Large Rocks test site, and 29 ground surface facility test pits. Evidence of erosion, reproduction and natural recruitment, exotic species abundance, and animal use (key attributes) also were recorded for each site and used in success evaluations. The C-Well Pipeline and ground surface facility test pits were located in a ''Larrea tridentata - Ephedra nevadensis'' vegetation association while the UE-25 Large Rocks test site was located in an area dominated by ''Coleogyne ramosissima and Ephedra nevadensis''. Reference areas in the same vegetation associations with similar slope and aspect were chosen for comparison to

Site Release Reports for C-Well Pipeline, UE-25 Large Rocks Test Site, and 29 GSF Test Pits

Energy Technology Data Exchange (ETDEWEB)

K.E. Rasmuson

2002-04-02

The U.S. Department of Energy has implemented a program to reclaim lands disturbed by site characterization at Yucca Mountain. Long term goals of the program are to re-establish processes on disturbed sites that will lead to self-sustaining plant communities. The Biological Opinion for Yucca Mountain Site Characterization Studies required that the U.S. Department of Energy develop a Reclamation Standards and Monitoring Plan to evaluate the success of reclamation efforts. According to the Reclamation Standards and Monitoring Plan, reclaimed sites will be monitored periodically, remediated if necessary, and eventually compared to an appropriate reference area to determine whether reclamation goals have been achieved and the site can be released from further monitoring. Plant cover, density, and species richness (success parameters) on reclaimed sites are compared to 60 percent of the values (success criteria) for the same parameters on the reference area. Small sites (less than 0.1 ha) are evaluated for release using qualitative methods while large sites (greater than 0.1 ha) are evaluated using quantitative methods. In the summer of 2000, 31 small sites reclaimed in 1993 and 1994 were evaluated for reclamation success and potential release from further monitoring. Plant density, cover, and species richness were estimated on the C-Well Pipeline, UE-25 Large Rocks test site, and 29 ground surface facility test pits. Evidence of erosion, reproduction and natural recruitment, exotic species abundance, and animal use (key attributes) also were recorded for each site and used in success evaluations. The C-Well Pipeline and ground surface facility test pits were located in a ''Larrea tridentata - Ephedra nevadensis'' vegetation association while the UE-25 Large Rocks test site was located in an area dominated by ''Coleogyne ramosissima and Ephedra nevadensis''. Reference areas in the same vegetation associations with similar slope

A digital library of radiology images.

Science.gov (United States)

Kahn, Charles E

2006-01-01

A web-based virtual library of peer-reviewed radiological images was created for use in education and clinical decision support. Images were obtained from open-access content of five online radiology journals and one e-learning web site. Figure captions were indexed by Medical Subject Heading (MeSH) codes, imaging modality, and patient age and sex. This digital library provides a new, valuable online resource.

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

Radio-ecological characterization and radiological assessment in support of regulatory supervision of legacy sites in northwest Russia.

Science.gov (United States)

Sneve, M K; Kiselev, M; Shandala, N K

2014-05-01

The Norwegian Radiation Protection Authority has been implementing a regulatory cooperation program in the Russian Federation for over 10 years, as part of the Norwegian government's Plan of Action for enhancing nuclear and radiation safety in northwest Russia. The overall long-term objective has been the enhancement of safety culture and includes a special focus on regulatory supervision of nuclear legacy sites. The initial project outputs included appropriate regulatory threat assessments, to determine the hazardous situations and activities which are most in need of enhanced regulatory supervision. In turn, this has led to the development of new and updated norms and standards, and related regulatory procedures, necessary to address the often abnormal conditions at legacy sites. This paper presents the experience gained within the above program with regard to radio-ecological characterization of Sites of Temporary Storage for spent nuclear fuel and radioactive waste at Andreeva Bay and Gremikha in the Kola Peninsula in northwest Russia. Such characterization is necessary to support assessments of the current radiological situation and to support prospective assessments of its evolution. Both types of assessments contribute to regulatory supervision of the sites. Accordingly, they include assessments to support development of regulatory standards and guidance concerning: control of radiation exposures to workers during remediation operations; emergency preparedness and response; planned radionuclide releases to the environment; development of site restoration plans, and waste treatment and disposal. Examples of characterization work are presented which relate to terrestrial and marine environments at Andreeva Bay. The use of this data in assessments is illustrated by means of the visualization and assessment tool (DATAMAP) developed as part of the regulatory cooperation program, specifically to help control radiation exposure in operations and to support

Corrective Action Decision Document for Corrective Action Unit 322: Areas 1 and 3 Release Sites and Injection Wells Nevada Test Site, Nevada, Rev. No. 0

Energy Technology Data Exchange (ETDEWEB)

Robert Boehlecke

2004-12-01

This Corrective Action Decision Document has been prepared for Corrective Action Unit (CAU) 322, Areas 1 and 3 Release Sites and Injection Wells, Nevada Test Site, Nevada, in accordance with the ''Federal Facility Agreement and Consent Order'' (1996). Corrective Action Unit 322 is comprised of the following corrective action sites (CASs): (1) 01-25-01 - AST Release Site; (2) 03-25-03 - Mud Plant and AST Diesel Release; and (3) 03-20-05 - Injection Wells and BOP Shop. The purpose of this Corrective Action Decision Document is to identify and provide the rationale for the recommendation of a corrective action alternative for each CAS within CAU 322. Corrective action investigation activities were performed from April 2004 through September 2004, as set forth in the Corrective Action Investigation Plan. The purposes of the activities as defined during the data quality objectives process were: (1) Determine if contaminants of concern (COCs) are present; (2) If COCs are present, determine their nature and extent; and (3) Provide sufficient information and data to recommend appropriate corrective actions for the CASs. Analytes detected during the corrective action investigation were evaluated against appropriate preliminary action levels to identify contaminants of concern for each corrective action site. Radiological field measurements were compared to unrestricted release criteria. Assessment of the data generated from investigation activities revealed the following: (1) CAS 01-25-01 contains an AST berm contaminated with total petroleum hydrocarbons (TPH) diesel-range organics (DRO). (2) CAS 03-25-03 includes two distinct areas: Area A where no contamination remains from a potential spill associated with an AST, and Area B where TPH-DRO contamination associated with various activities at the mud plant was identified. The Area B contamination was found at various locations and depths. (3) CAS 03-25-03 Area B contains TPH-DRO contamination at various

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

International Nuclear Information System (INIS)

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

1996-01-01

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

Implementation of a Radiological Safety Coach program

Energy Technology Data Exchange (ETDEWEB)

Konzen, K.K. [Safe Sites of Colorado, Golden, CO (United States). Rocky Flats Environmental Technology Site; Langsted, J.M. [M.H. Chew and Associates, Golden, CO (United States)

1998-02-01

The Safe Sites of Colorado Radiological Safety program has implemented a Safety Coach position, responsible for mentoring workers and line management by providing effective on-the-job radiological skills training and explanation of the rational for radiological safety requirements. This position is significantly different from a traditional classroom instructor or a facility health physicist, and provides workers with a level of radiological safety guidance not routinely provided by typical training programs. Implementation of this position presents a challenge in providing effective instruction, requiring rapport with the radiological worker not typically developed in the routine radiological training environment. The value of this unique training is discussed in perspective with cost-savings through better radiological control. Measures of success were developed to quantify program performance and providing a realistic picture of the benefits of providing one-on-one or small group training. This paper provides a description of the unique features of the program, measures of success for the program, a formula for implementing this program at other facilities, and a strong argument for the success (or failure) of the program in a time of increased radiological safety emphasis and reduced radiological safety budgets.

Implementation of a Radiological Safety Coach program

International Nuclear Information System (INIS)

Konzen, K.K.

1998-01-01

The Safe Sites of Colorado Radiological Safety program has implemented a Safety Coach position, responsible for mentoring workers and line management by providing effective on-the-job radiological skills training and explanation of the rational for radiological safety requirements. This position is significantly different from a traditional classroom instructor or a facility health physicist, and provides workers with a level of radiological safety guidance not routinely provided by typical training programs. Implementation of this position presents a challenge in providing effective instruction, requiring rapport with the radiological worker not typically developed in the routine radiological training environment. The value of this unique training is discussed in perspective with cost-savings through better radiological control. Measures of success were developed to quantify program performance and providing a realistic picture of the benefits of providing one-on-one or small group training. This paper provides a description of the unique features of the program, measures of success for the program, a formula for implementing this program at other facilities, and a strong argument for the success (or failure) of the program in a time of increased radiological safety emphasis and reduced radiological safety budgets

Radiological protection Program of CDTN

International Nuclear Information System (INIS)

1983-01-01

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

Closure Report for Corrective Action Unit 118: Area 27 Super Kukla Facility, Nevada Test Site, Nevada, Revision 0

International Nuclear Information System (INIS)

Mark Burmeister

2007-01-01

This CR provides documentation and justification for the closure of CAU 118 without further corrective action. This justification is based on process knowledge and the results of the investigative and closure activities conducted in accordance with the CAU 118 SAFER Plan: Streamlined Approach for Environmental Restoration (SAFER) Plan for CAU 118: Area 27 Super Kukla Facility, Nevada Test Site, Nevada (NNSA/NSO, 2006). The SAFER Plan provides information relating to site history as well as the scope and planning of the investigation. This CR also provides the analytical and radiological survey data to confirm that the remediation goals were met as specified in the CAU 118 SAFER Plan (NNSA/NSO, 2006). The Nevada Division of Environmental Protection (NDEP) approved the CAU 118 SAFER Plan (Murphy, 2006), which recommends closure in place with use restrictions (URs)

NEVADA TEST SITE WASTE ACCEPTANCE CRITERIA

International Nuclear Information System (INIS)

U.S. DEPARTMENT OF ENERGY, NATIONAL NUCLEAR SECURITY ADMINISTRATION, NEVADA SITE OFFICE

2005-01-01

This document establishes the U. S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO) waste acceptance criteria (WAC). The WAC provides the requirements, terms, and conditions under which the Nevada Test Site will accept low-level radioactive and mixed waste for disposal. Mixed waste generated within the State of Nevada by NNSA/NSO activities is accepted for disposal. It includes requirements for the generator waste certification program, characterization, traceability, waste form, packaging, and transfer. The criteria apply to radioactive waste received at the Nevada Test Site Area 3 and Area 5 Radioactive Waste Management Site for storage or disposal

The radiological impact of 50 years of uranium mining in France. The necessity of a site satisfying restructuring by Cogema-Areva

International Nuclear Information System (INIS)

2005-01-01

In a first text, the author briefly describes the radioprotection risks related to uranium mining, gives an overview of the characteristics of extraction residues in uranium extraction factories. Then, after having presented the case of the Limousin region in France, he outlines the high level of contamination of the environment of the mining sites, recalls the extraction process and discusses the careless use of the extracted radioactive rocks and materials. He outlines the insufficient management and processing of liquid effluents, the risk associated with the dispersal of contaminated scrap metals and of radioactive ores. He also discusses air contamination due to dusts and radioactive gases. He comments the issue of long term storage of uranium mining residues. He outlines the responsibility of the Administration and comments the trial against Cogema which took place in 2005. He outlines how restructuring of all the concerned sites is a challenging issue for our future. A second text in English describes radiological hazards from uranium mining (uranium by-products, radiological situation before and during extraction, long term contamination after mines closure, problems posed by tailing disposal)

Radiological survey and evaluation of the fallout area from the Trinity test: Chupadera Mesa and White Sands Missile Range, New Mexico

International Nuclear Information System (INIS)

Hansen, W.R.; Rodgers, J.C.

1985-06-01

Current radiological conditions were evaluated for the site of the first nuclear weapons test, the Trinity test, and the associated fallout zone. The test, located on White Sands Missile Range, was conducted as part of the research with nuclear materials for the World War II Manhattan Engineer District atomic bomb project. Some residual radioactivity attributable to the test was found in the soils of Ground Zero on White Sands Missile Range and the areas that received fallout from the test. The study considered relevant information including historical records, environmental data extending back to the 1940s, and new data acquired by field sampling and measurements. Potential exposures to radiation were evaluated for current land uses. Maximum estimated doses on Chupadera Mesa and other uncontrolled areas are less than 3% of the DOE Radiation Protection Standards (RPSs). Radiation exposures during visits to the US Army-controlled Ground Zero area are less than 1 mrem per annual visit or less than 0.2% of the RPS for a member of the public. Detailed data and interpretations are provided in appendixes. 14 figs., 45 tabs

Radiological survey and evaluation of the fallout area from the Trinity test: Chupadera Mesa and White Sands Missile Range, New Mexico

Energy Technology Data Exchange (ETDEWEB)

Hansen, W.R.; Rodgers, J.C.

1985-06-01

Current radiological conditions were evaluated for the site of the first nuclear weapons test, the Trinity test, and the associated fallout zone. The test, located on White Sands Missile Range, was conducted as part of the research with nuclear materials for the World War II Manhattan Engineer District atomic bomb project. Some residual radioactivity attributable to the test was found in the soils of Ground Zero on White Sands Missile Range and the areas that received fallout from the test. The study considered relevant information including historical records, environmental data extending back to the 1940s, and new data acquired by field sampling and measurements. Potential exposures to radiation were evaluated for current land uses. Maximum estimated doses on Chupadera Mesa and other uncontrolled areas are less than 3% of the DOE Radiation Protection Standards (RPSs). Radiation exposures during visits to the US Army-controlled Ground Zero area are less than 1 mrem per annual visit or less than 0.2% of the RPS for a member of the public. Detailed data and interpretations are provided in appendixes. 14 figs., 45 tabs.

Corrective Action Plan for Corrective Action Unit 254: Area 25 R-MAD Decontamination Facility Nevada Test Site, Nevada

International Nuclear Information System (INIS)

Obi, C.M.

2000-01-01

The Area 25 Reactor Maintenance, Assembly, and Disassembly Decontamination Facility is identified in the Federal Facility Agreement and Consent Order (FFACO) as Corrective Action Unit (CAU) 254. CAU 254 is located in Area 25 of the Nevada Test Site and consists of a single Corrective Action Site CAS 25-23-06. CAU 254 will be closed, in accordance with the FFACO of 1996. CAU 254 was used primarily to perform radiological decontamination and consists of Building 3126, two outdoor decontamination pads, and surrounding soil within an existing perimeter fence. The site was used to decontaminate nuclear rocket test-car hardware and tooling from the early 1960s through the early 1970s, and to decontaminate a military tank in the early 1980s. The site characterization results indicate that, in places, the surficial soil and building materials exceed clean-up criteria for organic compounds, metals, and radionuclides. Closure activities are expected to generate waste streams consisting of nonhazardous construction waste. petroleum hydrocarbon waste, hazardous waste, low-level radioactive waste, and mixed waste. Some of the wastes exceed land disposal restriction limits and will require off-site treatment before disposal. The recommended corrective action was revised to Alternative 3- ''Unrestricted Release Decontamination, Verification Survey, and Dismantle Building 3126,'' in an addendum to the Correction Action Decision Document

Rocketdyne Division annual site environmental report Santa Susana Field Laboratory and Desoto sites 1995

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-07-30

This annual report discusses environmental monitoring at two manufacturing and test operations sites operated in the Los Angeles area by the Rocketdyne Division of Rockwell International Corporation (Rocketdyne). These are identified as the Santa Susana Field Laboratory (SSFL) and the DeSoto site. The sites have been used for manufacturing, R&D, engineering, and testing in a broad range of technical fields, primarily rocket engine propulsion and nuclear reactor technology. The DeSoto site essentially comprises office space and light industry with no remaining radiological operations, and has little potential impact on the environment. The SSFL site, because of its large size (2,668 acres), warrants comprehensive monitoring to assure protection of the environment. SSFL consists of four administrative areas used for research, development, and test operations as well as a buffer zone. A portion of Area I and all of Area II are owned by the U.S. Government and assigned to the National Aeronautics and Space Administration (NASA). A portion of Area IV is under option for purchase by the Department of Energy (DOE).

Rocketdyne Division annual site environmental report Santa Susana Field Laboratory and Desoto sites 1995

International Nuclear Information System (INIS)

1996-01-01

This annual report discusses environmental monitoring at two manufacturing and test operations sites operated in the Los Angeles area by the Rocketdyne Division of Rockwell International Corporation (Rocketdyne). These are identified as the Santa Susana Field Laboratory (SSFL) and the DeSoto site. The sites have been used for manufacturing, R ampersand D, engineering, and testing in a broad range of technical fields, primarily rocket engine propulsion and nuclear reactor technology. The DeSoto site essentially comprises office space and light industry with no remaining radiological operations, and has little potential impact on the environment. The SSFL site, because of its large size (2,668 acres), warrants comprehensive monitoring to assure protection of the environment. SSFL consists of four administrative areas used for research, development, and test operations as well as a buffer zone. A portion of Area I and all of Area II are owned by the U.S. Government and assigned to the National Aeronautics and Space Administration (NASA). A portion of Area IV is under option for purchase by the Department of Energy (DOE)

Kauai Test Facility hazards assessment document

Energy Technology Data Exchange (ETDEWEB)

Swihart, A

1995-05-01

The Department of Energy Order 55003A requires facility-specific hazards assessment be prepared, maintained, and used for emergency planning purposes. This hazards assessment document describes the chemical and radiological hazards associated with the Kauai Test Facility, Barking Sands, Kauai, Hawaii. The Kauai Test Facility`s chemical and radiological inventories were screened according to potential airborne impact to onsite and offsite individuals. The air dispersion model, ALOHA, estimated pollutant concentrations downwind from the source of a release, taking into consideration the toxicological and physical characteristics of the release site, the atmospheric conditions, and the circumstances of the release. The greatest distance to the Early Severe Health Effects threshold is 4.2 kilometers. The highest emergency classification is a General Emergency at the {open_quotes}Main Complex{close_quotes} and a Site Area Emergency at the Kokole Point Launch Site. The Emergency Planning Zone for the {open_quotes}Main Complex{close_quotes} is 5 kilometers. The Emergency Planning Zone for the Kokole Point Launch Site is the Pacific Missile Range Facility`s site boundary.

Kauai Test Facility hazards assessment document

International Nuclear Information System (INIS)

Swihart, A.

1995-05-01

The Department of Energy Order 55003A requires facility-specific hazards assessment be prepared, maintained, and used for emergency planning purposes. This hazards assessment document describes the chemical and radiological hazards associated with the Kauai Test Facility, Barking Sands, Kauai, Hawaii. The Kauai Test Facility's chemical and radiological inventories were screened according to potential airborne impact to onsite and offsite individuals. The air dispersion model, ALOHA, estimated pollutant concentrations downwind from the source of a release, taking into consideration the toxicological and physical characteristics of the release site, the atmospheric conditions, and the circumstances of the release. The greatest distance to the Early Severe Health Effects threshold is 4.2 kilometers. The highest emergency classification is a General Emergency at the open-quotes Main Complexclose quotes and a Site Area Emergency at the Kokole Point Launch Site. The Emergency Planning Zone for the open-quotes Main Complexclose quotes is 5 kilometers. The Emergency Planning Zone for the Kokole Point Launch Site is the Pacific Missile Range Facility's site boundary

Organizational decentralization in radiology.

Science.gov (United States)

Aas, I H Monrad

2006-01-01

At present, most hospitals have a department of radiology where images are captured and interpreted. Decentralization is the opposite of centralization and means 'away from the centre'. With a Picture Archiving and Communication System (PACS) and broadband communications, transmitting radiology images between sites will be far easier than before. Qualitative interviews of 26 resource persons were performed in Norway. There was a response rate of 90%. Decentralization of radiology interpretations seems less relevant than centralization, but several forms of decentralization have a role to play. The respondents mentioned several advantages, including exploitation of capacity and competence. They also mentioned several disadvantages, including splitting professional communities and reduced contact between radiologists and clinicians. With the new technology decentralization and centralization of image interpretation are important possibilities in organizational change. This will be important for the future of teleradiology.

Estimating risk at a Superfund site contaminated with radiological and chemical wastes

International Nuclear Information System (INIS)

Temeshy, A.; Liedle, J.M.; Sims, L.M.; Efird, C.R.

1992-01-01

This paper describes the method and results for estimating carcinogenic and noncarcinogenic effects at a Superfund site that is radiologically and chemically contaminated. Risk to receptors from disposal of waste in soil and resulting contamination of groundwater, air, surface water, and sediment is quantified. Specific risk assessment components which are addressed are the exposure assessment, toxicity assessment, and the resulting risk characterization. In the exposure assessment, potential exposure pathways are identified using waste disposal inventory information for soil and modeled information for other media. Models are used to calculate future radionuclide concentrations in groundwater, soil, surface water and air. Chemical exposure concentrations are quantified using site characterization data. Models are used to determine concentrations of chemicals in surface water and in air. Toxicity parameters used to quantify the dose-response relationship associated with the carcinogenic contaminants are slope factors and with noncarcinogenic contaminants are reference doses. In the risk characterization step, results from the exposure assessment and toxicity assessment are summarized and integrated into quantitative risk estimates for carcinogens and hazard induces for noncarcinogens. Calculated risks for carcinogenic contaminants are compared with EPA's target risk range. At WAG 6, the risk from radionuclides and chemicals for an on-WAG homesteader exceeds EPA's target risk range. Hazard indices are compared to unity for noncarcinogenic contaminants. At WAG 6, the total pathway hazard index for the on-WAG homesteader exceeds unity

Nevada Test Site Waste Acceptance Criteria (NTSWAC)

Energy Technology Data Exchange (ETDEWEB)

NNSA/NSO Waste Management Project

2008-06-01

This document establishes the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office, Nevada Test Site Waste Acceptance Criteria (NTSWAC). The NTSWAC provides the requirements, terms, and conditions under which the Nevada Test Site will accept low-level radioactive (LLW) and LLW Mixed Waste (MW) for disposal.

Nevada Test Site Waste Acceptance Criteria (NTSWAC)

International Nuclear Information System (INIS)

NNSA/NSO Waste Management Project

2008-01-01

This document establishes the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office, Nevada Test Site Waste Acceptance Criteria (NTSWAC). The NTSWAC provides the requirements, terms, and conditions under which the Nevada Test Site will accept low-level radioactive (LLW) and LLW Mixed Waste (MW) for disposal

Radiological Characterization and Final Facility Status Report Tritium Research Laboratory

International Nuclear Information System (INIS)

Garcia, T.B.; Gorman, T.P.

1996-08-01

This document contains the specific radiological characterization information on Building 968, the Tritium Research Laboratory (TRL) Complex and Facility. We performed the characterization as outlined in its Radiological Characterization Plan. The Radiological Characterization and Final Facility Status Report (RC ampersand FFSR) provides historic background information on each laboratory within the TRL complex as related to its original and present radiological condition. Along with the work outlined in the Radiological Characterization Plan (RCP), we performed a Radiological Soils Characterization, Radiological and Chemical Characterization of the Waste Water Hold-up System including all drains, and a Radiological Characterization of the Building 968 roof ventilation system. These characterizations will provide the basis for the Sandia National Laboratory, California (SNL/CA) Site Termination Survey .Plan, when appropriate

Nevada National Security Site Environmental Report 2010

Energy Technology Data Exchange (ETDEWEB)

C. Wills, ed.

2011-09-13

This NNSSER was prepared to satisfy DOE Order DOE O 231.1B, “Environment, Safety and Health Reporting.” Its purpose is to (1) report compliance status with environmental standards and requirements, (2) present results of environmental monitoring of radiological and nonradiological effluents, (3) report estimated radiological doses to the public from releases of radioactive material, (4) summarize environmental incidents of noncompliance and actions taken in response to them, (5) describe the NNSA/NSO Environmental Management System and characterize its performance, and (6) highlight significant environmental programs and efforts. This NNSSER summarizes data and compliance status for calendar year 2010 at the Nevada National Security Site (NNSS) (formerly the Nevada Test Site) and its two support facilities, the North Las Vegas Facility (NLVF) and the Remote Sensing Laboratory–Nellis (RSL-Nellis). It also addresses environmental restoration (ER) projects conducted at the Tonopah Test Range (TTR). Through a Memorandum of Agreement, NNSA/NSO is responsible for the oversight of TTR ER projects, and the Sandia Site Office of NNSA (NNSA/SSO) has oversight of all other TTR activities. NNSA/SSO produces the TTR annual environmental report available at http://www.sandia.gov/news/publications/environmental/index.html.

Model testing for the remediation assessment of a radium contaminated site in Olen, Belgium

International Nuclear Information System (INIS)

Sweeck, Lieve; Kanyar, Bela; Krajewski, Pawel; Kryshev, Alexander; Lietava, Peter; Nenyei, Arpad; Sazykina, Tatiana; Yu, Charley; Zeevaert, Theo

2005-01-01

Environmental assessment models are used as decision-aiding tools in the selection of remediation options for radioactively contaminated sites. In most cases, the effectiveness of the remedial actions in terms of dose savings cannot be demonstrated directly, but can be established with the help of environmental assessment models, through the assessment of future radiological impacts. It should be emphasized that, given the complexity of the processes involved and our current understanding of how they operate, these models are simplified descriptions of the behaviour of radionuclides in the environment and therefore imperfect. One way of testing and improving the reliability of the models is to compare their predictions with real data and/or the predictions of other models. Within the framework of the Remediation Assessment Working Group (RAWG) of the BIOMASS (BIOsphere Modelling and ASSessment) programme coordinated by IAEA, two scenarios were constructed and applied to test the reliability of environmental assessment models when remedial actions are involved. As a test site, an area of approximately 100 ha contaminated by the discharges of an old radium extraction plant in Olen (Belgium) has been considered. In the first scenario, a real situation was evaluated and model predictions were compared with measured data. In the second scenario the model predictions for specific hypothetical but realistic situations were compared. Most of the biosphere models were not developed to assess the performance of remedial actions and had to be modified for this purpose. It was demonstrated clearly that the modeller's experience and familiarity with the mathematical model, the site and with the scenario play a very important role in the outcome of the model calculations. More model testing studies, preferably for real situations, are needed in order to improve the models and modelling methods and to expand the areas in which the models are applicable

An aerial radiological survey of the Tonopah Test Range including Clean Slate 1,2,3, Roller Coaster, decontamination area, Cactus Springs Ranch target areas. Central Nevada

International Nuclear Information System (INIS)

Proctor, A.E.; Hendricks, T.J.

1995-08-01

An aerial radiological survey was conducted of major sections of the Tonopah Test Range (TTR) in central Nevada from August through October 1993. The survey consisted of aerial measurements of both natural and man-made gamma radiation emanating from the terrestrial surface. The initial purpose of the survey was to locate depleted uranium (detecting 238 U) from projectiles which had impacted on the TTR. The examination of areas near Cactus Springs Ranch (located near the western boundary of the TTR) and an animal burial area near the Double Track site were secondary objectives. When more widespread than expected 241 Am contamination was found around the Clean Slates sites, the survey was expanded to cover the area surrounding the Clean Slates and also the Double Track site. Results are reported as radiation isopleths superimposed on aerial photographs of the area

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

Science.gov (United States)

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

2018-03-15

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

Corrective Action Investigation Plan for Corrective Action Unit 571: Area 9 Yucca Flat Plutonium Dispersion Sites, Nevada National Security Site, Nevada, Revision 0

Energy Technology Data Exchange (ETDEWEB)

Bailey, Bernadine; Matthews, Patrick

2013-07-01

CAU 571 is a grouping of sites where there has been a suspected release of contamination associated with nuclear testing. This document describes the planned investigation of CAU 571, which comprises the following corrective action sites (CASs): • 09-23-03, Atmospheric Test Site S-9F • 09-23-04, Atmospheric Test Site T9-C • 09-23-12, Atmospheric Test Site S-9E • 09-23-13, Atmospheric Test Site T-9D • 09-45-01, Windrows Crater These sites are being investigated because existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend corrective action alternatives (CAAs). Additional information will be obtained by conducting a corrective action investigation before evaluating CAAs and selecting the appropriate corrective action for each CAS. The results of the field investigation will support a defensible evaluation of viable CAAs that will be presented in the investigation report. The sites will be investigated based on the data quality objectives (DQOs) developed on March 6, 2013, by representatives of the Nevada Division of Environmental Protection and the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office (now the Nevada Field Office). The DQO process was used to identify and define the type, amount, and quality of data needed to develop and evaluate appropriate corrective actions for CAU 571. The site investigation process will also be conducted in accordance with the Soils Activity Quality Assurance Plan, which establishes requirements, technical planning, and general quality practices to be applied to this activity. The potential contamination sources associated with CAU 571 CASs are from nuclear testing activities. The DQO process resulted in an assumption that total effective dose (TED) within a default contamination boundary exceeds the final action level (FAL) and requires corrective action. The presence and nature of contamination outside the default

DOE Radiological Control Manual Core Training Program

International Nuclear Information System (INIS)

Scott, H.L.; Maisler, J.

1993-01-01

Over the past year, the Department of Energy (DOE) Office of Health (EH-40) has taken a leading role in the development of new standardized radiological control training programs for use throughout the DOE complex. The Department promulgated its Radiological Control (RadCon) Manual in June 1992. To ensure consistent application of the criteria presented in the RadCon Manual, standardized radiological control core training courses and training materials have been developed for implementation at all DOE facilities. In producing local training programs, standardized core courses are to be supplemented with site-specific lesson plans, viewgraphs, student handbooks, qualification standards, question banks, and wallet-sized training certificates. Training programs for General Employee Radiological Training, Radiological Worker I and II Training, and Radiological Control Technician Training have been disseminated. Also, training committees under the direction of the Office of Health (EH-40) have been established for the development of additional core training courses, development of examination banks, and the update of the existing core training courses. This paper discusses the current activities and future direction of the DOE radiological control core training program

Nevada Test Site Environmental Report 2005, Attachment A - Site Description

International Nuclear Information System (INIS)

Cathy A. Wills

2006-01-01

This appendix to the ''Nevada Test Site Environmental Report 2005'', dated October 2006 (DOE/NV/11718--1214; DOE/NV/25946--007) expands on the general description of the Nevada Test Site (NTS) presented in the Introduction. Included are subsections that summarize the site?s geological, hydrological, climatological, and ecological setting. The cultural resources of the NTS are also presented. The subsections are meant to aid the reader in understanding the complex physical and biological environment of the NTS. An adequate knowledge of the site's environment is necessary to assess the environmental impacts of new projects, design and implement environmental monitoring activities for current site operations, and assess the impacts of site operations on the public residing in the vicinity of the NTS. The NTS environment contributes to several key features of the site which afford protection to the inhabitants of adjacent areas from potential exposure to radioactivity or other contaminants resulting from NTS operations. These key features include the general remote location of the NTS, restricted access, extended wind transport times, the great depths to slow-moving groundwater, little or no surface water, and low population density. This appendix complements the annual summary of monitoring program activities and dose assessments presented in the main body of this report

Nevada Test Site Environmental Report 2005, Attachment A - Site Description

Energy Technology Data Exchange (ETDEWEB)

Cathy A. Wills

2006-10-01

This appendix to the ''Nevada Test Site Environmental Report 2005'', dated October 2006 (DOE/NV/11718--1214; DOE/NV/25946--007) expands on the general description of the Nevada Test Site (NTS) presented in the Introduction. Included are subsections that summarize the site?s geological, hydrological, climatological, and ecological setting. The cultural resources of the NTS are also presented. The subsections are meant to aid the reader in understanding the complex physical and biological environment of the NTS. An adequate knowledge of the site's environment is necessary to assess the environmental impacts of new projects, design and implement environmental monitoring activities for current site operations, and assess the impacts of site operations on the public residing in the vicinity of the NTS. The NTS environment contributes to several key features of the site which afford protection to the inhabitants of adjacent areas from potential exposure to radioactivity or other contaminants resulting from NTS operations. These key features include the general remote location of the NTS, restricted access, extended wind transport times, the great depths to slow-moving groundwater, little or no surface water, and low population density. This appendix complements the annual summary of monitoring program activities and dose assessments presented in the main body of this report.

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

International Nuclear Information System (INIS)

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

2012-01-01

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

TENORM radiological survey of Utica and Marcellus Shale

International Nuclear Information System (INIS)

Ying, Leong; O’Connor, Frank

2013-01-01

Comprehensive on-site radiological survey of processed sludge drilled materials extracted from the oil and gas production activities in the Utica and Marcellus Shale in Ohio has been conducted with a shielded isotopic identifier incorporating an advanced patented algorithmic processor to measure low-activity levels in compliance with environmental standards. - highlights: • First on-site radiological survey of processed shale sludge from oil and gas fields. • Mobile spectroscopic radiation inspection system with shielding for low-activity measurements. • Quantification of Ra-226 and Ra-228 radionuclides contamination in soil samples

Results of clinical and radiologic mass-screening tests of the locomotor system of miners in Hungary

Energy Technology Data Exchange (ETDEWEB)

Bene, E.; Temesvary, P.; Szilagyi, M.; Pera, F.

Clinical and radiological screening tests on the locomotor system of 250 workers being active in mines were accomplished by the authors. The test results of 125 miners working underground were compared with those of a control group consisting of equally 125 workers of the same age category, but engaged in open mining. As a result of the investigation it could be stated that miners working in underground mines were affected by diseases of the organs of motion at a very early stage, and in a greater proportion. The most serious deformations were observed with development irregularities and development variations. The development of degenerative locomotor diseases is promoted in Hungary by the working conditions prevailing underground. The completion of the examination procedure of fitness for work by clinical and radiological examinations of the locomotor system is important and highly recommended. The investigation carried out by the authors may serve as a model for the screening tests to be made on the locomotor system of industrial workers.

Colloid research for the Nevada Test Site

International Nuclear Information System (INIS)

Bryant, E.A.

1992-05-01

Research is needed to understand the role of particulates in the migration of radionuclides away from the sites of nuclear tests at the Nevada Test Site. The process of testing itself may produce a reservoir of particles to serve as vectors for the transport of long-lived radionuclides in groundwater. Exploratory experiments indicate the presence of numerous particulates in the vicinity of the Cambric test but a much lower loading in a nearby well that has been pumped continuously for 15 years. Recent groundwater colloid research is briefly reviewed to identify sampling and characterization methods that may be applicable at the Nevada Test Site

Phase II Documentation Overview of Corrective Action Unit 98: Frenchman Flat, Nevada Test Site, Nye County, Nevada, Revision 1

Energy Technology Data Exchange (ETDEWEB)

Greg Ruskauff

2010-04-01

The U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office (NNSA/NSO) initiated the Underground Test Area (UGTA) Subproject to assess and evaluate radiologic groundwater contamination resulting from underground nuclear testing at the NTS. These activities are overseen by the Federal Facility Agreement and Consent Order (FFACO) (1996, as amended March 2010). For Frenchman Flat, the UGTA Subproject addresses media contaminated by the underground nuclear tests, which is limited to geologic formations within the saturated zone or 100 meters (m) or less above the water table. Transport in groundwater is judged to be the primary mechanism of migration for the subsurface contamination away from the Frenchman Flat underground nuclear tests. The intent of the UGTA Subproject is to assess the risk to the public from the groundwater contamination produced as a result of nuclear testing. The primary method used to assess this risk is the development of models of flow and contaminant transport to forecast the extent of potentially contaminated groundwater for the next 1,000 years, establish restrictions to groundwater usage, and implement a monitoring program to verify protectiveness. For the UGTA Subproject, contaminated groundwater is that which exceeds the radiological standards of the Safe Drinking Water Act (CFR, 2009) the State of Nevada’s groundwater quality standard to protect human health and the environment. Contaminant forecasts are expected to be uncertain, and groundwater monitoring will be used in combination with land-use control to build confidence in model results and reduce risk to the public. Modeling forecasts of contaminant transport will provide the basis for negotiating a compliance boundary for the Frenchman Flat Corrective Action Unit (CAU). This compliance boundary represents a regulatory-based distinction between groundwater contaminated or not contaminated by underground testing. Transport modeling simulations

Nevada National Security Site Environmental Report 2011

International Nuclear Information System (INIS)

Wills, Cathy

2012-01-01

This report was prepared to meet the information needs of the public and the requirements and guidelines of the U.S. Department of Energy (DOE) for annual site environmental reports. It was prepared by National Security Technologies, LLC (NSTec), for the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO). This and previous years reports, called Annual Site Environmental Reports (ASERs), Nevada Test Site Environmental Reports (NTSERs), and, beginning in 2010, Nevada National Security Site Environmental Reports (NNSSERs), are posted on the NNSA/NSO website at http://www.nv.energy.gov/library/publications/aser.aspx. This NNSSER was prepared to satisfy DOE Order DOE O 231.1B, 'Environment, Safety and Health Reporting.' Its purpose is to (1) report compliance status with environmental standards and requirements, (2) present results of environmental monitoring of radiological and nonradiological effluents, (3) report estimated radiological doses to the public from releases of radioactive material, (4) summarize environmental incidents of noncompliance and actions taken in response to them, (5) describe the NNSA/NSO Environmental Management System and characterize its performance, and (6) highlight significant environmental programs and efforts. This NNSSER summarizes data and compliance status for calendar year 2011 at the Nevada National Security Site (NNSS) (formerly the Nevada Test Site) and its two support facilities, the North Las Vegas Facility (NLVF) and the Remote Sensing Laboratory-Nellis (RSL-Nellis). It also addresses environmental restoration (ER) projects conducted at the Tonopah Test Range (TTR). Through a Memorandum of Agreement, NNSA/NSO is responsible for the oversight of TTR ER projects, and the Sandia Site Office of NNSA (NNSA/SSO) has oversight of all other TTR activities. NNSA/SSO produces the TTR annual environmental report available at http://www.sandia.gov/news/publications/environmental/index.html.

Nevada National Security Site Environmental Report 2011

Energy Technology Data Exchange (ETDEWEB)

Cathy Wills, ed

2012-09-12

This report was prepared to meet the information needs of the public and the requirements and guidelines of the U.S. Department of Energy (DOE) for annual site environmental reports. It was prepared by National Security Technologies, LLC (NSTec), for the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO). This and previous years reports, called Annual Site Environmental Reports (ASERs), Nevada Test Site Environmental Reports (NTSERs), and, beginning in 2010, Nevada National Security Site Environmental Reports (NNSSERs), are posted on the NNSA/NSO website at http://www.nv.energy.gov/library/publications/aser.aspx. This NNSSER was prepared to satisfy DOE Order DOE O 231.1B, 'Environment, Safety and Health Reporting.' Its purpose is to (1) report compliance status with environmental standards and requirements, (2) present results of environmental monitoring of radiological and nonradiological effluents, (3) report estimated radiological doses to the public from releases of radioactive material, (4) summarize environmental incidents of noncompliance and actions taken in response to them, (5) describe the NNSA/NSO Environmental Management System and characterize its performance, and (6) highlight significant environmental programs and efforts. This NNSSER summarizes data and compliance status for calendar year 2011 at the Nevada National Security Site (NNSS) (formerly the Nevada Test Site) and its two support facilities, the North Las Vegas Facility (NLVF) and the Remote Sensing Laboratory-Nellis (RSL-Nellis). It also addresses environmental restoration (ER) projects conducted at the Tonopah Test Range (TTR). Through a Memorandum of Agreement, NNSA/NSO is responsible for the oversight of TTR ER projects, and the Sandia Site Office of NNSA (NNSA/SSO) has oversight of all other TTR activities. NNSA/SSO produces the TTR annual environmental report available at http://www.sandia.gov/news/publications/environmental/index.html.

Duquesne Light Company 1982 annual radiological environmental report. Volume 2

International Nuclear Information System (INIS)

1982-01-01

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

Formerly utilized MED/AEC sites, Remedial Action Program: radiological survey of the Hooker Chemical Company, Niagara Falls, New York. Final report

International Nuclear Information System (INIS)

1977-01-01

Results of a radiological survey of a portion of the Hooker Chemical Company, Niagara Falls, New York, are presented. The survey was conducted over 5.5-acres in which uranium-bearing materials were handled in the early 1940's. The survey included direct measurements of alpha, beta-gamma, and external gamma radiation throughout the site, measurement of transferable alpha and beta contamination levels in the buildings, determination of uranium and radium concentrations in the soild on the site, measurement of radon and radon daughter concentrations in the buildings, and determination of radionuclide concentrations in surface water samples. The results of the survey indicate that radiation levels throughout the site are within pertinent guidelines for unrestricted release of the property

An assessment of the reported leakage of anthropogenic radionuclides from the underground nuclear test sites at Amchitka Island, Alaska, USA to the surface environment

International Nuclear Information System (INIS)

Dasher, Douglas; Hanson, Wayne; Read, Stan; Faller, Scott; Farmer, Dennis; Efurd, Wes; Kelley, John; Patrick, Robert

2002-01-01

Three underground nuclear tests representing approximately 15-16% of the total effective energy released during the United States underground nuclear testing program from 1951 to 1992 were conducted at Amchitka Island, Alaska. In 1996, Greenpeace reported that leakage of radionuclides, 241 Am and 239+240 Pu, from these underground tests to the terrestrial and freshwater environments had been detected. In response to this report, a federal, state, tribal and non-governmental team conducted a terrestrial and freshwater radiological sampling program in 1997. Additional radiological sampling was conducted in 1998. An assessment of the reported leakage to the freshwater environment was evaluated by assessing 3 H values in surface waters and 240 Pu/ 239 Pu ratios in various sample media. Tritium values ranged from 0.41 Bq/l±0.11 two sigma to 0.74 Bq/l±0.126 two sigma at the surface water sites sampled, including the reported leakage sites. Only at the Long Shot test site, where leakage of radioactive gases to the near-surface occurred in 1965, were higher 3 H levels of 5.8 Bq/l±0.19 two sigma still observed in 1997, in mud pit no. 3. The mean 240 Pu/ 239 Pu for all of the Amchitka samples was 0.1991±0.0149 one standard deviation, with values ranging from 0.1824±1.43% one sigma to 0.2431±6.56% one sigma. The measured 3 H levels and 240 Pu/ 239 Pu ratios in freshwater moss and sediments at Amchitka provide no evidence of leakage occurring at the sites reported by Buske and Miller (1998 Nuclear-Weapons-Free America and Alaska Community Action on Toxics, Anchorage, Ak, p. 38) and Miller and Buske (1996 Nuclear Flashback: The Return to Anchitka, p. 35). It was noted that the marine sample; 240 Pu/ 239 Pu ratios are statistically different than the global fallout ratios presented by Krey et al. (1976) and Kelley, Bond, and Beasley (1999). The additional non-fallout component 240 Pu/ 239 Pu ratio, assuming a single unique source, necessary to modify the global fallout 240

IRSN's monitoring strategy for former uranium mining sites: regional radiological report approach

Energy Technology Data Exchange (ETDEWEB)

Audrey, L.L.; Marie-Odile, G.; Damien, T. [Institut de radioportection et de surete nucleaire - IRSN (France)

2014-07-01

Radiological monitoring of the environment in France was one of the basic missions assigned to the IRSN upon its creation. It is performed regularly through measurement and sampling networks across France, particularly around nuclear facilities. To supplement this system and increase its effectiveness and utility, IRSN recently began issuing regional baseline reference states using radiological reporting. Application of this reporting is currently underway in regions where uranium was mined. The Dordogne river basin is one of twenty basins impacted by uranium mining. Covering some twenty sites, it was selected by IRSN for its initial mining reporting. The objective is to gain detailed knowledge of the distribution of natural radioactivity related to the presence of uranium and its radioactive decay products, including radium, in mining areas and the river basin in general. This knowledge will supplement data already available as part of AREVA's regulatory site reporting, and provide access to a baseline reference state for radioactivity in the environment at local and regional levels. Since the impact of former uranium mining sites is basically tied to water circulation, sampling projects are designed based on the drainage system. Samples are taken of water, sediment and biological indicators such as fish and aquatic plants. Samples are then analysed to determine uranium, radium and polonium concentration. An initial sampling campaign took place in October 2012. It involved an initial contact with local organisations (Regional Directorate for the Environment, Town and Country Planning and Housing (DREAL), local information and oversight committee (Clis), regional public watershed board (EPIDOR), water agencies, mayors, hunting clubs, fishing federation, farmers, etc.). It will be supplemented by a second sampling campaign in late spring 2013 designed to take into account any local issues, including those associated with local water usage (irrigation, livestock

Massive radiological releases profoundly differ from controlled releases

International Nuclear Information System (INIS)

Pascucci-Cahen, Ludivine; Patrick, Momal

2013-01-01

In this article, the authors report identification and assessment of different types of costs associated with nuclear accidents. They first outline that these cost assessments must be as exhaustive or comprehensive as possible. While referring to past accidents, they define the different categories of costs: on-site costs (decontamination and dismantling, electricity not produced on the site), off-site costs (health costs, psychological costs, farming losses), image-related costs (impact on food and farm product exports, decrease of other exports), costs related to energy production, costs related to contaminated areas (refugees, lands). They give an assessment of a severe nuclear accident (i.e. an accident with important but controlled radiological releases) in France and outline that it would be a national catastrophe which could be however managed. They discuss the possible variations of the estimated costs. Then, they show that a major accident (i.e. an accident with massive radiological releases) in France would be an unmanageable European catastrophe because of the radiological consequences, of high economic costs, and of huge losses

Radiological survey of the former Kellex Research Facility, Jersey City, New Jersey

International Nuclear Information System (INIS)

Berven, B.A.; Dickson, H.W.; Goldsmith, W.A.; Johnson, W.M.; Cottrell, W.D.; Doane, R.W.; Haywood, F.F.; Ryan, M.T.; Shinpaugh, W.H.

1982-02-01

A radiological survey has been conducted at the site of the former Kellex Corporation Research Facility in Jersey City, New Jersey. Kellex played a major role in the Manhattan Project, particularly in the area of engineering research in gaseous diffusion for uranium enrichment. As a result of those operations and subsequent work with radioactive materials, this site was selected for a radiological survey by the Department of Energy (DOE) [then Energy Research and Development Administration (ERDA)] in its program aimed at reviewing and documenting the radiological status of properties associated with early source material contracts. The survaty included measurement of external gamma radiation, beta-gamma surface dose rates, alpha and beta surface contamination, concentrations of selected radionuclides in surface and subsurface soil and water on the site, and background radiation in the northern part of New Jersey. The results of the radiological survey indicate radionuclide concentrations in the soil and water on the former Kellex property are within background levels, with the exception of nine isolated and well-defined areas on the site of the former Kellex Laboratory

Nevada Test Site Environmental Report 2007 Attachment A: Site Description

Energy Technology Data Exchange (ETDEWEB)

Cathy Wills

2008-09-01

This appendix expands on the general description of the Nevada Test Site (NTS) presented in the Introduction to the Nevada Test Site Environmental Report 2007 (U.S. Department of Energy [DOE], 2008). Included are subsections that summarize the site's geological, hydrological, climatological, and ecological setting. The cultural resources of the NTS are also presented. The subsections are meant to aid the reader in understanding the complex physical and biological environment of the NTS. An adequate knowledge of the site's environment is necessary to assess the environmental impacts of new projects, design and implement environmental monitoring activities for current site operations, and assess the impacts of site operations on the public residing in the vicinity of the NTS. The NTS environment contributes to several key features of the site which afford protection to the inhabitants of adjacent areas from potential exposure to radioactivity or other contaminants resulting from NTS operations. These key features include the general remote location of the NTS, restricted access, extended wind transport times, the great depths to slow-moving groundwater, little or no surface water, and low population density. This attachment complements the annual summary of monitoring program activities and dose assessments presented in the main body of this report.

Computer-aided resource planning and scheduling for radiological services

Science.gov (United States)

Garcia, Hong-Mei C.; Yun, David Y.; Ge, Yiqun; Khan, Javed I.

1996-05-01

There exists tremendous opportunity in hospital-wide resource optimization based on system integration. This paper defines the resource planning and scheduling requirements integral to PACS, RIS and HIS integration. An multi-site case study is conducted to define the requirements. A well-tested planning and scheduling methodology, called Constrained Resource Planning model, has been applied to the chosen problem of radiological service optimization. This investigation focuses on resource optimization issues for minimizing the turnaround time to increase clinical efficiency and customer satisfaction, particularly in cases where the scheduling of multiple exams are required for a patient. How best to combine the information system efficiency and human intelligence in improving radiological services is described. Finally, an architecture for interfacing a computer-aided resource planning and scheduling tool with the existing PACS, HIS and RIS implementation is presented.

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.

Evaluation of the Non-Transient Hydrologic Source Term from the CAMBRIC Underground Nuclear Test in Frenchman Flat, Nevada Test Site

International Nuclear Information System (INIS)

Tompson, A B; Maxwell, R M; Carle, S F; Zavarin, M; Pawloski, G A.; Shumaker, D E

2005-01-01

Hydrologic Source Term (HST) calculations completed in 1998 at the CAMBRIC underground nuclear test site were LLNL's first attempt to simulate a hydrologic source term at the NTS by linking groundwater flow and transport modeling with geochemical modeling (Tompson et al., 1999). Significant effort was applied to develop a framework that modeled in detail the flow regime and captured all appropriate chemical processes that occurred over time. However, portions of the calculations were simplified because of data limitations and a perceived need for generalization of the results. For example: (1) Transient effects arising from a 16 years of pumping at the site for a radionuclide migration study were not incorporated. (2) Radionuclide fluxes across the water table, as derived from infiltration from a ditch to which pumping effluent was discharged, were not addressed. (3) Hydrothermal effects arising from residual heat of the test were not considered. (4) Background data on the ambient groundwater flow direction were uncertain and not represented. (5) Unclassified information on the Radiologic Source Term (RST) inventory, as tabulated recently by Bowen et al. (2001), was unavailable; instead, only a limited set of derived data were available (see Tompson et al., 1999). (6) Only a small number of radionuclides and geochemical reactions were incorporated in the work. (7) Data and interpretation of the RNM-2S multiple well aquifer test (MWAT) were not available. As a result, the current Transient CAMBRIC Hydrologic Source Term project was initiated as part of a broader Phase 2 Frenchman Flat CAU flow and transport modeling effort. The source term will be calculated under two scenarios: (1) A more specific representation of the transient flow and radionuclide release behavior at the site, reflecting the influence of the background hydraulic gradient, residual test heat, pumping experiment, and ditch recharge, and taking into account improved data sources and modeling

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

Worker radiological protection: occupational medical aspects

International Nuclear Information System (INIS)

Cardenas Herrera, Juan; Fernandez Gomez, Isis Maria

2008-01-01

Radiation exposures experienced by workers are widely explained. The first evidences of biological effects, the implications for human health and the radiological protection have been covered. The conceptual structure that covers the radiological protection and adequate protection without limiting benefits, the scientific basis of radiology, the benefits and risks of the radiological protection are specified. The effective per capita doses are exposed in medical uses both for Latin America and for other regions in the average radiology, dental radiology, nuclear medicine and radiotherapy. The manners of occupational exposures in the medicine are presented. Industrial uses have also its average effective dose in the industrial irradiation, industrial radiography and radioisotopes production. Within the natural radiation the natural sources can significantly contribute to occupational exposure and have their average effective dose. Occupational medical surveillance to be taken into industrial sites is detailed. In addition, the plan of international action for the solution of dilemmas of occupational exposures is mentioned and the different dilemmas of radioactive exposure are showed. The external irradiation, the acute diseases by radiations, the cutaneous syndrome of the chronic radiation, the radioactive contamination, the internal radioactive contamination, the combined lesion and accidental exposures are also treated [es

Radiological characterisation on V1 NPP technological systems and buildings - Contamination

International Nuclear Information System (INIS)

Hanzel, Richard; Rapant, Tibor; Svitek, Jaroslav

2012-01-01

Since 2001, the preparation of V1 NPP practical decommissioning has been supported and partly financed by the Bohunice International Decommissioning Support Fund, under the administration of the European bank for Reconstruction and development. AMEC Nuclear Slovakia, together with partners STM Power and EWN GmbH, performed BIDSF B.4 project - Decommissioning database development. The main purpose of the B6.4 project was to develop a comprehensive physical and radiological inventory database to support RAW management development of the decommissioning studies and decommissioning project of Bohunice V1 NPP. AMEC Nuclear Slovakia was responsible mainly for DDB design, planning documents and physical and radiological characterization including sampling and analyses of the plant controlled area. The objective of V1 NPP radiological characterization was summarisation of sampling and analyses results, description of methodology used for radiological characterization and determination of the V1 NPP radiological inventory. Results of the characterization survey included the identification and distribution of contamination in buildings, structures, and other site facilities or other impacted media. The characterization survey clearly identified those portions of the site that have been affected by site activities and are contaminated. The survey also identified the portions of the site that have not been affected by these activities and can be marked as 'not impacted'. Radiological data have been presented also on the basis of index RAI level, where 5 radiological classes have been defined. On the basis of sampling and analyses results following radiological parameters have been assigned to all impacted components and civil structures included in DDB: dose rate in contact, dose rate in distance 1 m, external surface contamination, internal surface contamination and volume/mass contamination. Each room in controlled area has been described by following radiological parameters

Formerly utilized MED/AEC sites Remedial Action Program. Radiological survey of the St. Louis Airport Storage Site, St. Louis, Missouri. Final report. [U, Ra-bearing wastes stored in 1940-60's

Energy Technology Data Exchange (ETDEWEB)

None

1979-09-01

Results of two radiological surveys of the St. Louis-Lambert Airport property, formerly known as the Airport Storage Site, St. Louis, Missouri, are presented. Uranium- and radium-bearing waste materials were stored from the 1940's to the late 1960's in this area. The surveys included direct measurements of beta-gamma radiation; determination of uranium, actinium, and radium concentrations in soil samples and from bore holes; determination of radionuclide concentrations in groundwater and surface water; measurement of radon flux from the ground surface; and measurements of /sup 222/Rn in air near the site. Results indicate that some offsite drainage pathways are becoming contaminated, probably by runoff from the site; no migration of /sup 222/Rn from the site was observed.

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

Corrective Action Investigation Plan for Corrective Action Unit 409: Other Waste Sites, Tonopah Test Range, Nevada (Rev. 0)

International Nuclear Information System (INIS)

2000-01-01

This Corrective Action Investigation Plan contains the U.S. Department of Energy, Nevada Operations Office's approach to collect the data necessary to evaluate corrective action alternatives appropriate for the closure of Corrective Action Unit (CAU) 409 under the Federal Facility Agreement and Consent Order. Corrective Action Unit 409 consists of three Corrective Action Sites (CASs): TA-53-001-TAB2, Septic Sludge Disposal Pit No.1; TA-53-002-TAB2, Septic Sludge Disposal Pit No.2; and RG-24-001-RGCR, Battery Dump Site. The Septic Sludge Disposal Pits are located near Bunker Two, close to Area 3, on the Tonopah Test Range. The Battery Dump Site is located at the abandoned Cactus Repeater Station on Cactus Peak. The Cactus Repeater Station was a remote, battery-powered, signal repeater station. The two Septic Sludge Disposal Pits were suspected to be used through the late 1980s as disposal sites for sludge from septic tanks located in Area 3. Based on site history collected to support the Data Quality Objectives process, contaminants of potential concern are the same for the disposal pits and include: volatile organic compounds (VOCs), semivolatile organic compounds, total petroleum hydrocarbons (TPHs) as gasoline- and diesel-range organics, polychlorinated biphenyls, Resource Conservation and Recovery Act metals, and radionuclides (including plutonium and depleted uranium). The Battery Dump Site consists of discarded lead-acid batteries and associated construction debris, placing the site in a Housekeeping Category and, consequently, no contaminants are expected to be encountered during the cleanup process. The corrective action the at this CAU will include collection of discarded batteries and construction debris at the Battery Dump Site for proper disposal and recycling, along with photographic documentation as the process progresses. The corrective action for the remaining CASs involves the collection of background radiological data through borings drilled at

Radiological environmental monitoring around the mining sites in Argentina

International Nuclear Information System (INIS)

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

2004-01-01

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

[Modern education in histopathology and radiology].

Science.gov (United States)

Maas, Mario; Mooi, Wolter J

2011-01-01

Radiological and pathological imaging constitute an essential part of modern medicine. Furthermore, by showing microscopic and radiological images many pathological processes can be made clearer and easier to understand. This has consequences for education. Many medical faculties are switching partly or entirely to the use of 'virtual microscopy', which amounts to studying digitalised histological preparations with the help of software that shows striking similarities to Google Earth. The requesting physician of the future will be able to make the most effective use of radiological tests when he or she has been trained in 'radiological thinking'. Students must realise that radiology depends not just on looking, as one might at holiday snaps, but more especially on interpreting what is seen. By using modern aids, it is possible to test the listeners' knowledge during lectures as a basis for the rest of the presentation. Collections of educational images are now widely available, including on the Internet.

Federal Radiological Monitoring and Assessment Center Overview of FRMAC Operations

International Nuclear Information System (INIS)

1998-01-01

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

Nevada National Security Site Environmental Report 2012

Energy Technology Data Exchange (ETDEWEB)

Wills, Cathy

2013-09-11

This report was prepared to meet the information needs of the public and the requirements and guidelines of the U.S. Department of Energy (DOE) for annual site environmental reports. It was prepared by National Security Technologies, LLC (NSTec), for the U.S. Department of Energy, National Nuclear Security Administration Nevada Field Office (NNSA/NFO) (formerly designated as the Nevada Site Office [NNSA/NSO]). The new field office designation occurred in March 2013. Published reports cited in this 2012 report, therefore, may bear the name or authorship of NNSA/NSO. This and previous years’ reports, called Annual Site Environmental Reports (ASERs), Nevada Test Site Environmental Reports (NTSERs), and, beginning in 2010, Nevada National Security Site Environmental Reports (NNSSERs), are posted on the NNSA/NFO website at http://www.nv.energy.gov/library/publications/aser.aspx. This NNSSER was prepared to satisfy DOE Order DOE O 231.1B, “Environment, Safety and Health Reporting.” Its purpose is to (1) report compliance status with environmental standards and requirements, (2) present results of environmental monitoring of radiological and nonradiological effluents, (3) report estimated radiological doses to the public from releases of radioactive material, (4) summarize environmental incidents of noncompliance and actions taken in response to them, (5) describe the NNSA/NFO Environmental Management System and characterize its performance, and (6) highlight significant environmental programs and efforts. This NNSSER summarizes data and compliance status for calendar year 2012 at the Nevada National Security Site (NNSS) (formerly the Nevada Test Site) and its two support facilities, the North Las Vegas Facility (NLVF) and the Remote Sensing Laboratory–Nellis (RSL-Nellis). It also addresses environmental restoration (ER) projects conducted at the Tonopah Test Range (TTR) and the Nevada Test and Training Range (NTTR). Through a Memorandum of Agreement, NNSA/NFO is

Evaluation of Final Radiological Conditions at Areas of the Niagara Falls Storage Site Remediated under the Formerly Utilized Sites Remedial Action Program -12184

Energy Technology Data Exchange (ETDEWEB)

Clayton, Christopher [U.S Department of Energy Office of Legacy Management, Washington, DC; Kothari, Vijendra [U.S Department of Energy Office of Legacy Management, Morgantown, West Virginia; Starr, Ken [U.S Department of Energy Office of Legacy Management, Westminster, Colorado; Widdop, Michael; Gillespie, Joey [SM Stoller Corporation, Grand Junction, Colorado

2012-02-26

The U. S. Department of Energy (DOE) methods and protocols allow evaluation of remediation and final site conditions to determine if remediated sites remain protective. Two case studies are presented that involve the Niagara Falls Storage Site (NFSS) and associated vicinity properties (VPs), which are being remediated under the Formerly Utilized Sites Remedial Action Program (FUSRAP). These properties are a part of the former Lake Ontario Ordnance Works (LOOW). In response to stakeholders concerns about whether certain remediated NFSS VPs were putting them at risk, DOE met with stakeholders and agreed to evaluate protectiveness. Documentation in the DOE records collection adequately described assessed and final radiological conditions at the completed VPs. All FUSRAP wastes at the completed sites were cleaned up to meet DOE guidelines for unrestricted use. DOE compiled the results of the investigation in a report that was released for public comment. In conducting the review of site conditions, DOE found that stakeholders were also concerned about waste from the Separations Process Research Unit (SPRU) at the Knolls Atomic Power Laboratory (KAPL) that was handled at LOOW. DOE agreed to determine if SPRU waste remained at that needed to be remediated. DOE reviewed records of waste characterization, historical handling locations and methods, and assessment and remediation data. DOE concluded that the SPRU waste was remediated on the LOOW to levels that pose no unacceptable risk and allow unrestricted use and unlimited exposure. This work confirms the following points as tenets of an effective long-term surveillance and maintenance (LTS&M) program: Stakeholder interaction must be open and transparent, and DOE must respond promptly to stakeholder concerns. DOE, as the long-term custodian, must collect and preserve site records in order to demonstrate that remediated sites pose no unacceptable risk. DOE must continue to maintain constructive relationships with the U

Closure Report for Corrective Action Unit 116: Area 25 Test Cell C Facility, Nevada National Security Site, Nevada

Energy Technology Data Exchange (ETDEWEB)

NSTec Environmental Restoration

2011-09-29

This Closure Report (CR) presents information supporting closure of Corrective Action Unit (CAU) 116, Area 25 Test Cell C Facility. This CR complies with the requirements of the Federal Facility Agreement and Consent Order (FFACO) that was agreed to by the State of Nevada; the U.S. Department of Energy (DOE), Environmental Management; the U.S. Department of Defense; and DOE, Legacy Management (FFACO, 1996 [as amended March 2010]). CAU 116 consists of the following two Corrective Action Sites (CASs), located in Area 25 of the Nevada National Security Site: (1) CAS 25-23-20, Nuclear Furnace Piping and (2) CAS 25-41-05, Test Cell C Facility. CAS 25-41-05 consisted of Building 3210 and the attached concrete shield wall. CAS 25-23-20 consisted of the nuclear furnace piping and tanks. Closure activities began in January 2007 and were completed in August 2011. Activities were conducted according to Revision 1 of the Streamlined Approach for Environmental Restoration Plan for CAU 116 (U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office [NNSA/NSO], 2008). This CR provides documentation supporting the completed corrective actions and provides data confirming that closure objectives for CAU 116 were met. Site characterization data and process knowledge indicated that surface areas were radiologically contaminated above release limits and that regulated and/or hazardous wastes were present in the facility.

Influence of radiological emphysema on lung function test in idiopathic pulmonary fibrosis.

Science.gov (United States)

Bodlet, Aline; Maury, Gisèle; Jamart, Jacques; Dahlqvist, Caroline

2013-11-01

Idiopathic pulmonary fibrosis (IPF) is one of the most frequent interstitial lung disease. Emphysema can be associated with IPF as described in the «Combined pulmonary fibrosis and emphysema» syndrome. The primary endpoint of this retrospective cohort study was to evaluate the impact of the association of IPF and emphysema on lung function tests parameters (FVC, TLC, FEV1, FEV1/FVC and DLCO). The secondary endpoint was to assess the impact of the associated radiological emphysema on lung function parameters used in the du Bois prognostic score recently developed by Ron du Bois et al. We retrospectively reviewed the medical files of 98 patients with lung fibrosis who were followed in our University Hospital with access to pharmacological studies and lung transplantation from 1981 to 2011. Fifty six patients were considered for analysis. The collected data included gender, age, smoking history and respiratory hospitalizations. We also analysed their pulmonary functional parameters along with radiological characteristics, in particular the presence of emphysema which was assessed on thoracic high resolution CT scan. The du Bois score was retrospectively calculated from these data. TLC and FVC at diagnosis were significantly higher in the IPF-E group compared to the IPF group (respectively 86.6 ± 17.2% pv versus 72.0 ± 15.0% pv; p: 0.004 and 86.8 ± 18.4% pv versus 72.6 ± 20.6% pv; p: 0.020). The [Formula: see text] used in the calculation of the du Bois prognostic score was significantly higher in the IPF-E group. By cons, [Formula: see text] was not statistically different between the two groups. Radiological emphysema associated with IPF had an impact on pulmonary function tests. Despite this difference, the du Bois score was not statistically different between these two groups. Nevertheless, after one year of follow up, the patients with emphysema were in a subclass with a lower mortality rate than those without emphysema. Copyright © 2013 Elsevier

Radiological emergency: Malaysian preparedness and response

International Nuclear Information System (INIS)

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

2011-01-01

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

Radiation consequences of the nuclear tests on the Semipalatinsk test site

International Nuclear Information System (INIS)

Logachev, V.A.; Logacheva, L.A.

2001-01-01

In the paper the results of retrospective evaluation for radiation situation and radiation doses of population in the zones of the Semipalatinsk test site activity influence are presented. For the measurements the data obtained during analysis, study and summarizing of the archival materials including information on nuclear tests on this site and results of radiation surveys, those were carried out after each test were used. The information testifying most substantial environment contamination taking place after four surface explosions (29.08.1949, 24.09.1951, 12.08.1953, 24.08.1956) is presented as well. After these dose-forming explosions the irradiation doses of the population inhabiting out the regime zone have been exceeded the maximum permissible levels. Results of analysis of archival materials were used for assessment of doses of internal and external irradiation of residents of inhabited points situated on the both the territory of the Republic of Kazakhstan - mainly close to the test site - and the territories of a number of regions of the Russian Federation are locating on the little distance from the tests site

Rocketdyne Propulsion & Power DOE Operations Annual Site Environmental Report 1996

Energy Technology Data Exchange (ETDEWEB)

Tuttle, R. J. [The Boeing Company, Canoga Park, CA (United States)

1997-11-10

This annual report discusses environmental monitoring at two manufacturing and test operations sites operated in the Los Angeles area by Rocketdyne Propulsion & Power of Boeing North American. Inc. (formerly Rockwell International Corporation). These are identified as the Santa Susana Field Laboratory (SSFL and the De Soto site. The sites have been used for manufacturing; R&D, engineering, and testing in a broad range of technical fields, primarily rocket engine propulsion and nuclear reactor technology. The De Soto site essentially comprises office space and light industry with no remaining radiological operations, and has little potential impact on the environment. The SSFL site, because of its large size (2.668 acres), warrants comprehensive monitoring to ensure protection of the environment.

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

International Nuclear Information System (INIS)

McKinney, S.M.

1995-04-01

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

1980 annual radiological environmental report. Volume 2

International Nuclear Information System (INIS)

1980-01-01

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

Radiological status of the environment around the site of Saint-Pierre (Cantal). IRSN Third-party expertise. Part 1: situational analysis and additional studies to be performed

International Nuclear Information System (INIS)

2006-01-01

This document reports the first part of a study which aimed at verifying the relevance of available studies and measurements for the Saint-Pierre ancient mining site and regarding risks related to radioactivity. More specifically, this study aimed at defining the most precisely as possible the perimeter of potential influence of this site for three pollution vectors (water, air, soils) with respect to available studies and in terms of necessary additional studies, at assessing the radiological impact on populations living, working or staying at the neighbourhood of this restored site, and at proposing an evolution of the current survey arrangement in order to make it more adapted and reliable. This first part is dedicated to the analysis of all existing documents in order to define required additional elements (analysis, sampling, surveys, and so on) for a better knowledge of the present radiological status of the studied site. After a presentation of the physical and human characteristics of the site, and of its geological and mineralogical context, and recalled the past mining activities (extraction, processing, wastes, waste rock and tailings), the report proposes an analysis per component: external exposure, radon and dusts, underground waters, surface waters, sediments, aquatic fauna and flora, food products. An assessment and recommendations are formulated. Financial aspects are discussed

A consequence index approach to identifying radiological sabotage targets

International Nuclear Information System (INIS)

Altman, W.D.; Hockert, J.W.

1988-01-01

One of the threats to concern to facilities using significant quantities of radioactive material is radiological sabotage. Both the Department of Energy (DOE) and the U.S. Nuclear Regulatory Commission have issued guidance to facilities for radiological sabotage protection. At those facilities where the inventories of radioactive materials change frequently, there is an operational need for a technically defensible method of determining whether or not the inventory of radioactive material at a given facility poses a potential radiological sabotage risk. In order to determine quickly whether a building is a potential radiological sabotage target, Lawrence Livermore National Loaboratory (LLNL) has developed a radiological sabotage consequence index that provides a conservative estimate of the maximum potential off-site consequences of a radiological sabotage attempt involving the facility. This radiological sabotage consequence index can be used by safeguards and security staff to rapidly determine whether a change in building operations poses a potential radiological sabotage risk. In those cases where such a potential risk is identified, a more detailed radiological sabotage vulnerability analysis can be performed

Industrial Sites Project Establishment of Final Action Levels

International Nuclear Information System (INIS)

Boehlecke, Robert F.

2006-01-01

The U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO) oversees numerous sites on the Nevada Test Site (NTS) and other locations in the State of Nevada that have been impacted by activities related to the development and testing of nuclear devices and by other activities. NNSA/NSO is responsible for protecting members of the public, including site workers, from harmful exposure to both chemical and radiological contaminants at these sites as they remediate these sites. The Nevada Division of Environmental Protection (NDEP) is the primary state agency responsible for protection of human health and the environment with respect to chemical and radiological wastes. In 1996 the DOE, U.S. Department of Defense, and the State of Nevada entered into an agreement known as the ''Federal Facility Agreement and Consent Order'' (FFACO) (1996). Appendix VI to the FFACO describes the strategy employed to plan, implement, and complete environmental corrective action activities at NTS and other locations in the state of Nevada. One of the categories of corrective action units (CAUs) is Industrial Sites, which consists of approximately 1,150 locations that may require some level of investigation and corrective action. To evaluate the need for the extent of corrective action at a particular site, NNSA/NSO assesses the potential impacts to receptors by comparing measurements of contaminant concentrations to risk-based (chemical) and dose-based (radionuclide) standards (action levels). Preliminary action levels (PALs) are established as part of the data quality objective (DQO) process, and are presented in one or more FFACO documents generated as part of the corrective action process. This document formally defines and clarifies the NDEP-approved process NNSA/NSO Industrial Sites Project uses to fulfill the requirements of the FFACO and state regulations. This process establishes final action levels (FALs) based on the risk

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)

Development of radiological profiles for U.S. Department of Energy low-level mixed wastes

International Nuclear Information System (INIS)

Wilkins, B.D.; Meshkov, N.K.; Dolak, D.A.; Wang, Y.Y.

1995-01-01

Radiological profiles have been developed by Argonne National Laboratory for low-level mixed wastes (LLMWs) that are under the management of the US Department of Energy (DOE). These profiles have been used in the Office of Environmental Management Programmatic Environmental Impact Statement (EM PEIS) to support the analysis of environmental and health risks associated with the various waste management strategies. The radiological characterization of DOE LLMWs is generally inadequate and has made it difficult to develop a site- and waste-stream-dependent radiological profile for LLMWs. On the basis of the operational history of the DOE sites, a simple model was developed to generate site-dependent and waste-stream-independent radiological profiles for LLMWs. This paper briefly discusses the assumptions used in this model and the uncertainties in the results

Emergency radiology

International Nuclear Information System (INIS)

Keats, T.E.

1986-01-01

This book is the German, translated version of the original published in 1984 in the U.S.A., entitled 'Emergency Radiology'. The publication for the most part is made up as an atlas of the radiological images presenting the findings required for assessment of the emergency cases and their first treatment. The test parts' function is to explain the images and give the necessary information. The material is arranged in seven sections dealing with the skull, the facial part of the skull, the spine, thorax, abdominal region, the pelvis and the hip, and the limbs. With 690 figs [de

Terrorism: the threat of a radiological device

International Nuclear Information System (INIS)

Kingshott, B.F.

2005-01-01

Full text: This paper will discuss terrorism from the perspective of a terrorist organization building and detonating a 'dirty bomb' with a radiological component. The paper will discuss how such devices are made and how security of radiological material world wide will minimize the risk of such devices being used. It will discuss the threat assessments against nuclear waste processing and storage sites, threats to nuclear plants and other sites and the adequacy of current security. It will also discuss the phenomenon of suicide attacks by the bomb carriers and the role of the media in informing and educating the general public of the consequences should such a device be detonated. (author)

Radiological audit of remedial action activities at the processing sites Mexican Hat, Utah and Monument Valley, Arizona. Audit date: May 3--7, 1993, Final report

International Nuclear Information System (INIS)

1993-05-01

The Uranium Mill Tailings Remedial Action (UMTRA) Project's Technical Assistance Contractor (TAC) performed a radiological audit of the Remedial Action Contractor (RAC), MK-Ferguson and CWM Federal Environmental Services, Inc., at the processing sites in Mexican Hat, Utah, and Monument Valley, Arizona. This audit was conducted May 3--7, 1993, by Bill James and Gerry Simiele of the TAC. Three site-specific findings and four observations were identified during the audit and are presented in this report. The overall conclusion from the audit is that the majority of the radiological aspects of the Mexican Hat, Utah, and Monument Valley, Arizona, remedial action programs are performed adequately. However, the findings identify that there is some inconsistency in following procedures and meeting requirements for contamination control, and a lack of communication between the RAC and the DOE on variances from the published remedial action plan (RAP)

Health effects models for off-site radiological consequence analysis on nuclear reactor accidents (II)

Energy Technology Data Exchange (ETDEWEB)

Homma, Toshimitsu [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment; Takahashi, Tomoyuki [Kyoto Univ., Kumatori, Osaka (Japan). Research Reactor Inst; Yonehara, Hidenori [National Inst. of Radiological Sciences, Chiba (Japan)] [eds.

2000-12-01

This report is a revision of JAERI-M 91-005, 'Health Effects Models for Off-Site Radiological Consequence Analysis of Nuclear Reactor Accidents'. This revision provides a review of two revisions of NUREG/CR-4214 reports by the U.S. Nuclear Regulatory Commission which is the basis of the JAERI health effects models and other several recent reports that may impact the health effects models by international organizations. The major changes to the first version of the JAERI health effects models and the recommended parameters in this report are for late somatic effects. These changes reflect recent changes in cancer risk factors that have come from longer followup and revised dosimetry in major studies on the Japanese A-bomb survivors. This report also provides suggestions about future revisions of computational aspects on health effects models. (author)

Health effects models for off-site radiological consequence analysis on nuclear reactor accidents (II)

International Nuclear Information System (INIS)

Homma, Toshimitsu

2000-12-01

This report is a revision of JAERI-M 91-005, 'Health Effects Models for Off-Site Radiological Consequence Analysis of Nuclear Reactor Accidents'. This revision provides a review of two revisions of NUREG/CR-4214 reports by the U.S. Nuclear Regulatory Commission which is the basis of the JAERI health effects models and other several recent reports that may impact the health effects models by international organizations. The major changes to the first version of the JAERI health effects models and the recommended parameters in this report are for late somatic effects. These changes reflect recent changes in cancer risk factors that have come from longer followup and revised dosimetry in major studies on the Japanese A-bomb survivors. This report also provides suggestions about future revisions of computational aspects on health effects models. (author)

Nevada Test Site Environmental Report 2009, Attachment A: Site Description

Energy Technology Data Exchange (ETDEWEB)

Cathy Wills, ed.

2010-09-13

This attachment expands on the general description of the Nevada Test Site (NTS) presented in the Introduction to the Nevada Test Site Environmental Report 2009. Included are subsections that summarize the site’s geological, hydrological, climatological, and ecological setting. The cultural resources of the NTS are also presented. The subsections are meant to aid the reader in understanding the complex physical and biological environment of the NTS. An adequate knowledge of the site’s environment is necessary to assess the environmental impacts of new projects, design and implement environmental monitoring activities for current site operations, and assess the impacts of site operations on the public residing in the vicinity of the NTS. The NTS environment contributes to several key features of the site that afford protection to the inhabitants of adjacent areas from potential exposure to radioactivity or other contaminants resulting from NTS operations. These key features include the general remote location of the NTS, restricted access, extended wind transport times, the great depths to slow-moving groundwater, little or no surface water, and low population density. This attachment complements the annual summary of monitoring program activities and dose assessments presented in the main body of this report.

ERC Radiological Glovebag Program

International Nuclear Information System (INIS)

Nellesen, A.L.

1997-07-01

This document establishes the requirements and responsibilities for the standardized methods for installation, use, and dismantlement of glovebags within the Hanford Site Environmental Contractor Radiological Glovebag Program. This document addresses the following topics: Containment selection and fabrication, Glovebag fabrication, Containment installation and inspection, General glovebag containment work practices, Emergency situations, and Containment removal

Corrective Action Decision Document for Corrective Action Unit 536: Area 3 Release Site, Nevada Test Site, Nevada, Revision 0 with Errata

Energy Technology Data Exchange (ETDEWEB)

Boehlecke, Robert

2004-11-01

This Corrective Action Decision Document (CADD) has been prepared for Corrective Action Unit (CAU) 536: Area 3 Release Site, Nevada Test Site (NTS), Nevada, in accordance with the Federal Facility Agreement and Consent Order (FFACO) that was agreed to by the State of Nevada, the U.S. Department of Energy (DOE), and the U.S Department of Defense (FFACO, 1996). The NTS is approximately 65 miles (mi) northwest of Las Vegas, Nevada (Figure 1-1). Corrective Action Unit 536 is comprised of a single Corrective Action Site (CAS), 03-44-02, Steam Jenny Discharge, and is located in Area 3 of the NTS (Figure 1-2). The CAU was investigated in accordance with the Corrective Action Investigation Plan (CAIP) and Record of Technical Change (ROTC) No. 1 (NNSA/NV, 2003). The CADD provides or references the specific information necessary to support the recommended corrective action alternative selected to complete closure of the site. The CAU 536, Area 3 Release Site, includes the Steam Jenny Discharge (CAS 03-44-02) that was historically used for steam cleaning equipment in the Area 3 Camp. Concerns at this CAS include contaminants commonly associated with steam cleaning operations and Area 3 Camp activities that include total petroleum hydrocarbons (TPH), unspecified solvents, radionuclides, metals, and polychlorinated biphenyls (PCBs). The CAIP for Corrective Action Unit 536: Area 3 Release Site, Nevada Test Site, Nevada (NNSA/NV, 2003), provides additional information relating to the history, planning, and scope of the investigation; therefore, it will not be repeated in this CADD. This CADD identifies potential corrective action alternatives and provides a rationale for the selection of a recommended corrective action alternative for the CAS within CAU 536. The evaluation of corrective action alternatives is based on process knowledge and the results of the investigative activities conducted in accordance with the CAIP (NNSA/NV, 2003) that was approved prior to the start of the

Review at Bikini Atoll. Assessing radiological conditions at Bikini Atoll and the prospects for resettlement

International Nuclear Information System (INIS)

Stegnar, P.

1998-01-01

Some testing during the development of the atomic bomb was done in countries that do not have the infrastructure and expertise for evaluating any associated radiation risks. In such cases, outside expertise is needed to obtain independent advice about the radiological situation caused by residual radioactive material from nuclear testing. The IAEA has been requested by the governments of a number of its Member States to provide assistance in this context. Among the former nuclear test sites which the IAEA has reviewed is the Bikini Atoll of the Marshall Islands. Based on its review, the IAEA Advisory Group determined that no further corroboration of the measurements and assessments of the radiological conditions at Bikini Atoll is necessary. The data that have been collected are of sufficient quality to allow an appropriate evaluation to be performed. The limited IAEA monitoring of the area provided a good quality assurance verification of the previously collected data. It was recommended that Bikini Island should not be permanently resettled under the present radiological conditions. This recommendation was based on the assumption that persons resettling on the island would consume a diet of entirely locally produced food. The radiological data support that if a diet of this type were permitted, it could lead to an annual effective dose of about 15 mSv. This level was judged to require intervention of some type for radiation protection purposes

Extension of academic pediatric radiology to the community setting: experience in two sites

International Nuclear Information System (INIS)

Ecklund, K.; Share, J.C.

2000-01-01

Background. Children are better served by radiologists and technical personnel trained in the care of pediatric patients. However, a variety of obstacles may limit the access of children to dedicated pediatric imaging facilities. Objective. We designed and implemented two models for providing community-based imaging by academic pediatric radiologists. Materials and methods. The first site was an outpatient clinic staffed by physicians from the university-affiliated children's hospital. Imaging services included radiography, fluoroscopy, and ultrasound. The second site was a full-service community hospital radiology department staffed by a group practice, with pediatric imaging covered by the children's hospital radiologists. Facility, equipment, and protocol modifications were required to maintain quality standards. Success of these models was determined by volume statistics, referring physician/patient satisfaction surveys, and quality-assurance (QA) programs. Results. The outpatient satellite had a 48 % increase in total examinations from the first year to the second year and 87 % the third year. Pediatric examinations in the community hospital increased over 1000 % the first 7 months. Referring physicians reported increased diagnostic information and patient satisfaction compared to previous service. QA efforts revealed improved image quality when pediatric radiologists were present, but some continuing difficulties off-hours. Conclusion. We successfully implemented pediatric imaging programs in previously underserved communities. This resulted in increased pediatric radiologist supervision and interpretation of examinations performed on children and improved referring physician and patient satisfaction. (orig.)

Inappropriateness of cardiovascular radiological imaging testing; a tertiary care referral center study.

Directory of Open Access Journals (Sweden)

Clara Carpeggiani

Full Text Available AIMS: Radiological inappropriateness in medical imaging leads to loss of resources and accumulation of avoidable population cancer risk. Aim of the study was to audit the appropriateness rate of different cardiac radiological examinations. METHODS AND PRINCIPAL FINDINGS: With a retrospective, observational study we reviewed clinical records of 818 consecutive patients (67 ± 12 years, 75% males admitted from January 1-May 31, 2010 to the National Research Council - Tuscany Region Gabriele Monasterio Foundation cardiology division. A total of 940 procedures were audited: 250 chest x-rays (CXR; 240 coronary computed tomographies (CCT; 250 coronary angiographies (CA; 200 percutaneous coronary interventions (PCI. For each test, indications were rated on the basis of guidelines class of recommendation and level of evidence: definitely appropriate (A, including class I, appropriate, and class IIa, probably appropriate, uncertain (U, class IIb, probably inappropriate, or inappropriate (I, class III, definitely inappropriate. Appropriateness was suboptimal for all tests: CXR (A = 48%, U = 10%, I = 42%; CCT (A = 58%, U = 24%, I = 18%; CA (A = 45%, U = 25%, I = 30%; PCI (A = 63%, U = 15%, I = 22%. Top reasons for inappropriateness were: routine on hospital admission (70% of inappropriate CXR; first line application in asymptomatic low-risk patients (42% of CCT or in patients with unchanged clinical status post-revascularization (20% of CA; PCI in patients either asymptomatic or with miscellaneous symptoms and without inducible ischemia on non-invasive testing (36% of inappropriate PCI. CONCLUSION AND SIGNIFICANCE: Public healthcare system--with universal access paid for with public money--is haemorrhaging significant resources and accumulating avoidable long-term cancer risk with inappropriate cardiovascular imaging prevention.

MTR radiological database for SRS spent nuclear fuel facilities

International Nuclear Information System (INIS)

Blanchard, A.

2000-01-01

A database for radiological characterization of incoming Material Test Reactor (MTR) fuel has been developed for application to the Receiving Basin for Offsite Fuels (RBOF) and L-Basin spent fuel storage facilities at the Savannah River Site (SRS). This database provides a quick quantitative check to determine if SRS bound spent fuel is radiologically bounded by the Reference Fuel Assembly used in the L-Basin and RBOF authorization bases. The developed database considers pertinent characteristics of domestic and foreign research reactor fuel including exposure, fuel enrichment, irradiation time, cooling time, and fuel-to-moderator ratio. The supplied tables replace the time-consuming studies associated with authorization of SRS bound spent fuel with simple hand calculations. Additionally, the comprehensive database provides the means to overcome resource limitations, since a series of simple, yet conservative, hand calculations can now be performed in a timely manner and replace computational and technical staff requirements

Conversion of Semipalatinsk test site

International Nuclear Information System (INIS)

Cherepnin, Yu. S.

1997-01-01

The conversion of the former defense enterprises of STS (Semipalatinsk Test Sate) started under very difficult conditions, when not only research and production activity, but all social life of Kurchatov city were conversed which was caused by a fast curtailment and restationing of Russian military units from the test site. A real risk of a complete destruction of the whole research and production structure of the city existed. From this point of view, the decision of the Republic of Kazakhstan Government to create the National Nuclear Center on the base of the test site research enterprises was actual and timely. During 1993, three research institutes of NNC RK - Institute of Atomic Energy, Institute of Geophysics Research and Institute of Radiation Safety and Environment were established. This decision, under conditions of the Ussr disintegration and liquidation of the test site military divisions, allowed to preserve the qualified personnel, to provide and follow-up the operation of nuclear dangerous facilities, to develop and start the realization of the full scale conversion program.At present time, directions and structure of basic research work in NNC RK are as follows: - liquidation of nuclear explosions consequences; - liquidation of technological infrastructure used for preparation and conduction of nuclear weapon testing; - creation of technology, equipment and places for acceptance and storage of radioactive wastes; - working out of atomic energy development conception in Kazakhstan; - study of reactor core melt behavior under severe accidents in NPP; - development of methods and means of nuclear testing detection, continuous monitoring of nuclear explosions; - experimental work on a study of structure materials behavior of ITER thermonuclear reactor; - creation of industries requiring a lage implementation of science

Database on radioecological situation in Semipalatinsk nuclear test site

International Nuclear Information System (INIS)

Turkebaev, T.Eh.; Kislitsin, S.B.; Lopuga, A.D.; Kuketaev, A.T.; Kikkarin, S.M.

1999-01-01

One of the main objectives of the National Nuclear Center of the Republic of Kazakstan is to define radioecological situation in details, conduct a continuous monitoring and eliminate consequences of nuclear explosions at Semipalatinsk nuclear test site. Investigations of Semipalatinsk nuclear test site area contamination by radioactive substances and vindication activity are the reasons for development of computer database on radioecological situation of the test site area, which will allow arranging and processing the available and entering information about the radioecological situation, assessing the effect of different testing factors on the environment and health of the Semipalatinsk nuclear test site area population.The described conception of database on radioecological situation of the Semipalatinsk nuclear test site area cannot be considered as the final one. As new information arrives, structure and content of the database is updated and optimized. New capabilities and structural elements may be provided if new aspects in Semipalatinsk nuclear test site area contamination study (air environment study, radionuclides migration) arise

Site release in the decommissioning of nuclear installations

International Nuclear Information System (INIS)

Revilla, Jose Luis; Sanz, Maria Teresa; Marugan, Inmaculada; Simon, Inmaculada; Martin, Manuel; Solis, Susana; Sterling, Agustina

2008-01-01

Spanish regulatory framework for the decommissioning process of a nuclear facility ends up with a decommission statement, which releases the licence-holder of the facility from its responsibilities as an operator. It also establishes -where a restricted site release applies- the appropriate future use restrictions, and the responsible of both maintaining such restrictions and ensuring their compliance. Releasing a site implies eliminating all radiological monitoring. The Regulations, however, did not specify either the radiological conditions to be met for the site to be released, or the possibility of a partial release -with or without restrictions-. In case of restricted site release, the Regulations did not specify either the required criteria for such a release. This paper presents the main features of the Safety Instruction IS-13 'Radiological criteria for the release of nuclear facilities sites' issued recently by the Spanish Nuclear Safety Council as a new specific regulation. This Safety Instruction establishes the requirements and conditions for the release of nuclear facility sites, that is, radiological criteria on the effective dose to the public, partial release of nuclear facility sites and restricted release of nuclear facility sites. (author).

Physical and Radiological Characterisation of Measuring Sites Within The Croatian Gamma Dose Rate Early Warning Network

International Nuclear Information System (INIS)