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Sample records for site history radiological

  1. Early history of military radiology

    International Nuclear Information System (INIS)

    Eisenberg, R.L.

    1991-01-01

    This paper reports that soon after Roentgen's discovery, physicians in the armed services of the major powers grasped the importance of x-ray sin military surgery. By May of 1896, radiographic examinations were being performed on Italian soldiers returning from the ill-fated Ethiopian campaign. Initially, radiographs were used for foreign body localization and the detection of fractures; later, a full range of diagnostic services was offered. The early challenges of obtaining x-ray examinations in the field - fragility of tubes and plates, mobility of machines and patients, and unpredictability of radiation dosage - became the basis for innovations that would fundamentally alter the daily practice of radiology in civilian life

  2. History of metaphoric signs in radiology

    Energy Technology Data Exchange (ETDEWEB)

    Baker, Stephen R., E-mail: bakersr@umdnj.edu; Noorelahi, Yasser M., E-mail: dr.ynoorelahi@gmail.com; Ghosh, Shanchita, E-mail: Ghoshs1@umdnj.edu; Yang, Lily C., E-mail: yangclily@gmail.com; Kasper, David J., E-mail: dkasp86@gmail.com

    2013-09-15

    Purpose: To survey the nearly 100 year history of metaphoric sign naming in radiology describing the pace of their overall accumulation in the radiology canon, their specific rates of growth by modality and subspecialty and the characteristics of the referents to which the signs are attached. Materials and methods: A comprehensive list of metaphoric signs was compiled from a search of articles in several major English language radiology journals, from a roster compiled in a monograph on the subject published in 1984 and from a search of several databases to find signs published in the first half of the 20th century. Results: The growth of radiological metaphorical signs naming was slow for several decades after the first one was published in 1918. It then increased rapidly until the 1980s encompassing all modalities and subspecialties. Recently the practice has shown a marked and steady decline. Conclusion: Metaphoric sign naming was a frequently reported contribution to the radiological literature in the second half of the 20th century corresponding with Radiology's growth as a descriptive discipline. Its decline since then may be a consequence of Radiology's evolution into a more analytic, data-driven field of inquiry.

  3. History of metaphoric signs in radiology

    International Nuclear Information System (INIS)

    Baker, Stephen R.; Noorelahi, Yasser M.; Ghosh, Shanchita; Yang, Lily C.; Kasper, David J.

    2013-01-01

    Purpose: To survey the nearly 100 year history of metaphoric sign naming in radiology describing the pace of their overall accumulation in the radiology canon, their specific rates of growth by modality and subspecialty and the characteristics of the referents to which the signs are attached. Materials and methods: A comprehensive list of metaphoric signs was compiled from a search of articles in several major English language radiology journals, from a roster compiled in a monograph on the subject published in 1984 and from a search of several databases to find signs published in the first half of the 20th century. Results: The growth of radiological metaphorical signs naming was slow for several decades after the first one was published in 1918. It then increased rapidly until the 1980s encompassing all modalities and subspecialties. Recently the practice has shown a marked and steady decline. Conclusion: Metaphoric sign naming was a frequently reported contribution to the radiological literature in the second half of the 20th century corresponding with Radiology's growth as a descriptive discipline. Its decline since then may be a consequence of Radiology's evolution into a more analytic, data-driven field of inquiry

  4. NOAA History - About This Site

    Science.gov (United States)

    NOAA History Banner gold bar divider home - takes you to index page about the site contacts noaa - takes you to the noaa home page search this site white divider about this site The NOAA History site is the result of the work of many individuals throughout 3d history page NOAA who have been inspired by

  5. 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

  6. Radiological Situation at the Bomb Test Sites

    International Nuclear Information System (INIS)

    Valkovic, V.

    1998-01-01

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

  7. History, heresy and radiology in scientific discovery.

    Science.gov (United States)

    McCredie, J

    2009-10-01

    Nowadays, most drugs reach the market after research has established their pharmacology, safety and efficacy. That was not always the case 50 years ago. Thalidomide was used before its target cell or mode of action were known. Commencing with the thalidomide catastrophe--an epidemic of gross birth defects (1958-1962)--thalidomide's origins are revisited to show how this drug came to be made and sold in the 1950s. Thalidomide intersected with Australian radiology in the 1970s. The site and mode of action of the drug was deduced from X-rays of thalidomide-induced bone defects, which have classical radiological signs of sensory neuropathic osteoarthropathy. The longitudinal reduction deformities follow the distribution of segmental sensory innervation of the limb skeleton, indicating neural crest as the target organ. Injury to one level of neural crest halts normal neurotrophism and deletes the dependent segment--a previously unrecognised embryonic mechanism that explains most non-genetic birth defects. The final common pathway is neural crest injury and failure of normal neurotrophism to result in longitudinal reduction deformities, for example, phocomelia.

  8. History of the radiological protection in Mexico

    International Nuclear Information System (INIS)

    Ortiz M, J. R.

    2008-12-01

    one of its fundamental programs, along with others of similar importance like those of radioactive precipitation measurement. lt was the own National Commission of Nuclear Energy the one that begins the development of certain functions of regulating character. With the birth of the project of the Nuclear Power Plant of Laguna Verde, in the middle of the 1970 decade, the radiological protection in Mexico acquires and additional relevance from different perspective: on the one hand the necessity of the inclusion of a dedicated organization of radiological protection as much of the workers, as if to inhabitants of the zones bordering the nuclear plant. On 1979 it is created the National Commission of Nuclear Safety and Safeguards like exclusively regulating organization in the nuclear and radiological field, which constitutes a landmark in the modern history of the RP in Mexico. The own constant evolution in the RP concepts demands the preparation to confront the new future challenges. (Author)

  9. 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

  10. Nevada National Security Site Radiological Control Manual

    International Nuclear Information System (INIS)

    2012-01-01

    This document supersedes DOE/NV/25946--801, 'Nevada Test Site Radiological Control Manual,' Revision 1 issued in February 2010. Brief Description of Revision: A complete revision to reflect a recent change in name for the NTS; changes in name for some tenant organizations; and to update references to current DOE policies, orders, and guidance documents. Article 237.2 was deleted. Appendix 3B was updated. Article 411.2 was modified. Article 422 was re-written to reflect the wording of DOE O 458.1. Article 431.6.d was modified. The glossary was updated. 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) and the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO). Compliance with these requirements will ensure compliance with Title 10 Code of Federal Regulations (CFR) Part 835, 'Occupational Radiation Protection.' Programs covered by this manual are located at the Nevada National Security Site (NNSS); Nellis Air Force Base and North Las Vegas, Nevada; Santa Barbara and Livermore, California; and Andrews Air Force Base, Maryland. In addition, fieldwork by NNSA/NSO at other locations is covered by this manual. Current activities at NNSS include operating low-level radioactive and mixed waste disposal facilities for United States defense-generated waste, assembly and execution of subcritical experiments, assembly/disassembly of special experiments, the storage and use of special nuclear materials, performing criticality experiments, emergency responder training, surface cleanup and site characterization of contaminated land areas, environmental activity by the University system, and nonnuclear test operations, such as controlled spills of hazardous materials at the Hazardous Materials Spill Center. Currently, the major potential for occupational radiation exposure is associated with the burial of

  11. Nevada National Security Site Radiological Control Manual

    Energy Technology Data Exchange (ETDEWEB)

    Radiological Control Managers’ Council

    2012-03-26

    This document supersedes DOE/NV/25946--801, 'Nevada Test Site Radiological Control Manual,' Revision 1 issued in February 2010. Brief Description of Revision: A complete revision to reflect a recent change in name for the NTS; changes in name for some tenant organizations; and to update references to current DOE policies, orders, and guidance documents. Article 237.2 was deleted. Appendix 3B was updated. Article 411.2 was modified. Article 422 was re-written to reflect the wording of DOE O 458.1. Article 431.6.d was modified. The glossary was updated. 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) and the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO). Compliance with these requirements will ensure compliance with Title 10 Code of Federal Regulations (CFR) Part 835, 'Occupational Radiation Protection.' Programs covered by this manual are located at the Nevada National Security Site (NNSS); Nellis Air Force Base and North Las Vegas, Nevada; Santa Barbara and Livermore, California; and Andrews Air Force Base, Maryland. In addition, fieldwork by NNSA/NSO at other locations is covered by this manual. Current activities at NNSS include operating low-level radioactive and mixed waste disposal facilities for United States defense-generated waste, assembly and execution of subcritical experiments, assembly/disassembly of special experiments, the storage and use of special nuclear materials, performing criticality experiments, emergency responder training, surface cleanup and site characterization of contaminated land areas, environmental activity by the University system, and nonnuclear test operations, such as controlled spills of hazardous materials at the Hazardous Materials Spill Center. Currently, the major potential for occupational radiation exposure is associated with the burial of

  12. 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

  13. 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

  14. History and Organizations for Radiological Protection.

    Science.gov (United States)

    Kang, Keon Wook

    2016-02-01

    International Commission on Radiological Protection (ICRP), an independent international organization established in 1925, develops, maintains, and elaborates radiological protection standards, legislation, and guidelines. United Nations Scientific Committee on the Effects of Atomic Radiation (UNSCEAR) provides scientific evidence. World Health Organization (WHO) and International Atomic Energy Agency (IAEA) utilise the ICRP recommendations to implement radiation protection in practice. Finally, radiation protection agencies in each country adopt the policies, and adapt them to each situation. In Korea, Nuclear Safety and Security Commission is the governmental body for nuclear safety regulation and Korea Institute of Nuclear Safety is a public organization for technical support and R&D in nuclear safety and radiation protection.

  15. 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

  16. 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

  17. Uroradiology in 117 year history of radiology

    International Nuclear Information System (INIS)

    Naumov, N.

    2013-01-01

    Full text: Introduction: ‘In order to understand the present and see the future, you must know the past'. This motto, used by Professor Jean-Franois Moreau in his presentation ‘A Century uroradiology in Europe 1896 -1996’, is the occasion, with his consent and participation to complement the presentation not only with what comes as a change in our profession in recent years, but also to celebrate milestones in the development of uroradiology in Bulgaria. One of the major health problems in Europe, not only in the late 19th century, but today is renal calculi. For this reason, five months after the described by Wilhelm Conrad Roentgen X- rays attempts to use them in medical practice by urologists namely in seeking opportunities to demonstrate calculi began. What you will learn: This justifies the first phase, covering 1896-1929, has not only uroradiology but of radiology as a whole, in which it is a hobby of the urologists. Summarizing the main points as in the technical development of radiological equipment, but above all the introduction of diagnostic methods, some of which have not lost their relevance and today, this period naturally ends with one of the most epochal discoveries in medicine and first diagnostic method combining morphological with functional diagnostics - excretory urography . The second step, covering the period of 1929-1960, is characterized by increasing further improvement of the equipment, but also of the applied diagnostic methods, as the urologist is still leading in applying these methods, but now with the technical assistance of the radiologist. After World War II, this approach began to change, besides the appearance of chapters on uroradiology in major guidelines in diagnostic radiology, new methods have been developed, and including vascular contrast diagnostic are made and implemented by radiologists. The third stage, cover the period 1960-1980, entitled ‘Fathers of uroradiology’ account entry of CT low-osmolar nonionic

  18. Denver radium site's - Case history

    International Nuclear Information System (INIS)

    Topolski, T.T.

    1985-01-01

    In developing this case history of the Denver radium sites, an attempt is made to establish the Colorado carnotite connection from the point of discovery to early development and its eventual role in the inception of the National Radium Institute and Denver's radium legacy. Early exploitive mining activities and the exportation of the highest grades of uranium ore to Europe greatly disturbed key officials at the U.S. Bureau of Mines. With its proximity to known carnotite deposits and industrial capacity, Denver's destiny as one of America's early radium production centers became a reality by 1914. With African pitchblend discoveries, Belgium competition spelled the beginning of the end of Denver's romance with radium by 1920. The sites where Denver made or used its radium were lost in obscurity for 60 years and rediscovered in 1979. Thirty one sites and a characterization of their radioactive impact are now a part of the Superfund National Priorities listing for eventual cleanup

  19. 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

  20. Nevada Test Site Radiological Control Manual

    International Nuclear Information System (INIS)

    2009-01-01

    This document supersedes DOE/NV/11718--079, 'NV/YMP Radiological Control Manual,' Revision 5 issued in November 2004. Brief Description of Revision: A complete revision to reflect the recent changes in compliance requirements with 10 CFR 835, and for use as a reference document for Tenant Organization Radiological Protection Programs.

  1. Nevada Test Site Radiological Control Manual

    Energy Technology Data Exchange (ETDEWEB)

    Radiological Control Managers' Council - Nevada Test Site

    2009-10-01

    This document supersedes DOE/NV/11718--079, “NV/YMP Radiological Control Manual,” Revision 5 issued in November 2004. Brief Description of Revision: A complete revision to reflect the recent changes in compliance requirements with 10 CFR 835, and for use as a reference document for Tenant Organization Radiological Protection Programs.

  2. Radiological and scintigraphic findings in patients with a clinical history of chronic inflammatory back pain

    International Nuclear Information System (INIS)

    Goei The, H.S.; Lemmens, A.J.; Goedhard, G.; Lokkerbol, H.; Rahmy, A.; Linden, S.M. van der; Cats, A.; Steven, M.M.

    1985-01-01

    The prevalence of radiological abnormalities of the sacroiliac joints, the manubriosternal joint, and the lumbar spine were assessed, and quantitative sacroiliac scintigraphy was performed in 151 patients with a history of chronic inflammatory back pain and in 31 controls with non-inflammatory back pain. Sacroiliitis was found in 124 patients (82%), manubriosternal lesions in 84 patients (56%), and lesions of the lumbar spine in 58 patients (38%). In 19 patients (13%), manubriosternal lesions provided the sole radiological abnormality and in five patients (3%) no radiological abnormality could be demonstrated at any of these sites. Quantitative sacroiliac scintigraphy showed increased values in 69 of 137 patients examined (50%), but also in 10 out of 12 control patients with disc degeneration (83%) and is, therefore, nonspecific for inflammatory lesions. Radiological examination of the manubriosternal joint is recommended in patients with inflammatory back pain without radiographic evidence of sacroiliitis. (orig.)

  3. Nevada Test Site Radiological Control Manual. Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    None, None

    2010-02-09

    This document supersedes DOE/NV/25946--801, “Nevada Test Site Radiological Control Manual,” Revision 0 issued in October 2009. Brief Description of Revision: A minor revision to correct oversights made during revision to incorporate the 10 CFR 835 Update; and for use as a reference document for Tenant Organization Radiological Protection Programs.

  4. 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 ...

  5. International Commission on Radiological Protection. History, policies, procedures

    International Nuclear Information System (INIS)

    Lindell, Bo; Dunster, H.J.; Valentin, Jack; )

    2000-01-01

    This report briefly reviews the history, mode of operation, concepts, and current policies of the International Commission on Radiological Protection (ICRP). It touches upon the objectives of the Commission's recommendations, the quantities used, the biological basis of the Commission's policy, the quantitative basis for its risk estimates, the structure of the system of protection, some problems of interpretation and application in that system, and the need for stability, consistency, and clarity in the Commission's recommendations. (author)

  6. Pages of the history of roentgenology and radiology in Latvia

    International Nuclear Information System (INIS)

    Nemiro, E.A.

    1987-01-01

    The history of roentgenology in Latvia is discussed singling out 3 periods in its development: 1) from the discovery of X-rays up to the Great October Socialist Revolution and the establishment of Soviet power in Latvia; 2) the bourgeois period in Latvia (1920-1940); 3) from the beginning of the Great Patriotic War to the present period. The paper is devoted to an analysis of the main historical events and facts pertaining to the formation and further development of roentgenology and radiology in Latvia. The role and importance of the roentgenology and radiology chair and the Republican roentgenoradiological center in the development of roentgenoradiology as independent clinical branches, training of specialists, the development and clinical application of present-day methods of radiation therapy are considered. The chief advances of Latvian radiologists and their contacts with leading specilaists are marked

  7. History of Hanford Site Defense Production (Brief)

    International Nuclear Information System (INIS)

    GERBER, M.S.

    2001-01-01

    This paper acquaints the audience with the history of the Hanford Site, America's first full-scale defense plutonium production site. The paper includes the founding and basic operating history of the Hanford Site, including World War II construction and operations, three major postwar expansions (1947-55), the peak years of production (1956-63), production phase downs (1964-the present), a brief production spurt from 1984-86, the end of the Cold War, and the beginning of the waste cleanup mission. The paper also delineates historical waste practices and policies as they changed over the years at the Hanford Site, past efforts to chemically treat, ''fractionate,'' and/or immobilize Hanford's wastes, and resulting major waste legacies that remain today. This paper presents original, primary-source research into the waste history of the Hanford Site. Finally, the paper places the current Hanford Site waste remediation endeavors in the broad context of American and world history

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

    Energy Technology Data Exchange (ETDEWEB)

    Friesen, H.N.

    1995-06-01

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

  9. 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

  10. Decontamination analysis of a radiologically contaminated site

    International Nuclear Information System (INIS)

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

    1984-01-01

    This paper presents a post-exercise analysis of decontamination options for the NUWAX-83 exercise site. Held in May 1983, the purpose of NUWAX-83 was to evaluate the ability of federal, state and local officials to respond to an accident involving nuclear weapons. A computer program, called DECON, was developed by Pacific Northwest Laboratory and used to conduct the decontamination analysis in November 1983. 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

  11. Interventional radiology (IVR). The history, status quo, and prospect

    International Nuclear Information System (INIS)

    Furui, Shigeru; Kohtake, Hiroshi

    2007-01-01

    Interventional radiology (IVR) is a clinical practice that therapy and/or biopsy are performed under guidance by images obtainable by the contrast angiography, ultrasonography, CT, MRI and so on. This paper describes its history, present status and future prospect. Actual operation procedure, recent trend and progress as well are explained in the order of arterial embolization, IVR in hepatic tumors, PTA (percutaneous transluminal angiography) and MS (metallic stent indwelling), MS applied to others than artery, S-G (stent-graft), IVR in portal hypertension, development of IVR devices in Japan, and radiation exposure and its protection in IVR. Many IVR devices have been developed in Japan for as long as these 30 years, a part of which is marketed. Skin exposure in patients is unavoidable in IVR with X-ray and thereby regulations by Food and Drug Administration (FDA) and International Commission of Radiological Protection (ICRP) are introduced for their benefit. Systems for dose estimation in patients and efforts to reduce the dose are mentioned to be important and radiologists themselves should make effort to decrease their own exposure in consideration of the dose limits defined in the law. Problems in Japan are expensiveness of IVR devices, and slow-paced approval of new devices by authority and by health insurance agent. The author recommends doctors to have expert radiologist's advice in IVR. (R.T.)

  12. History of radiological characterisation in Studsvik - History of radiological characterisation in decommissioning projects in Studsvik

    International Nuclear Information System (INIS)

    Hedvall, Robert

    2012-01-01

    AB SVAFO is a nuclear waste technology and decommissioning company based in Sweden in the scenic surroundings of Studsvik on the Baltic coast. SVAFO is owned by the Swedish nuclear power industry. The company was created in 1992 by Sydsvenska Vaermekraft AB, Vattenfall AB, Forsmarks Kraftgrupp AB and Oskarshamns Kraftgrupp AB as a consequence of the Act on the Financing of the Management of Certain Radioactive Waste etc, from 1988. AB SVAFO's main business is to take care of formerly state-owned spent nuclear waste at the site, including small amounts of nuclear fuel. Buildings are also included, mainly nuclear waste storage buildings and a research reactor. Some buildings have already been decommissioned and all the fuel is treated. In the past 30 years, various decommissioning projects have been carried out, encompassing areas such as an underground research reactor, a Van de Graaff accelerator, 15,000 m 2 of nuclear laboratories, two 150 m 3 underground concrete sludge silos and several waste-storage buildings. Up till now only one or two persons did a simple characterisation before the project started to get the level of contamination. With the start of the decommissioning of the former uranium mine in Ranstad and the R2-reactor, more efforts have been put for the characterisation. The change in methods will be described. (author)

  13. 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

  14. History of Hanford Site Defense Production (Brief)

    Energy Technology Data Exchange (ETDEWEB)

    GERBER, M S

    2001-02-01

    This paper acquaints the audience with the history of the Hanford Site, America's first full-scale defense plutonium production site. The paper includes the founding and basic operating history of the Hanford Site, including World War II construction and operations, three major postwar expansions (1947-55), the peak years of production (1956-63), production phase downs (1964-the present), a brief production spurt from 1984-86, the end of the Cold War, and the beginning of the waste cleanup mission. The paper also delineates historical waste practices and policies as they changed over the years at the Hanford Site, past efforts to chemically treat, ''fractionate,'' and/or immobilize Hanford's wastes, and resulting major waste legacies that remain today. This paper presents original, primary-source research into the waste history of the Hanford Site. Finally, the paper places the current Hanford Site waste remediation endeavors in the broad context of American and world history.

  15. 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)

  16. 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

  17. 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

  18. 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

  19. 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

  20. 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

  1. An aerial radiological survey of the Nevada Test Site

    International Nuclear Information System (INIS)

    Hendricks, T.J.; Riedhauser, S.R.

    1999-01-01

    A team from the Remote Sensing Laboratory conducted an aerial radiological survey of the US Department of Energy's Nevada Test Site including three neighboring areas during August and September 1994. The survey team measured the terrestrial gamma radiation at the Nevada Test Site to determine the levels of natural and man-made radiation. This survey included the areas covered by previous surveys conducted from 1962 through 1993. The results of the aerial survey showed a terrestrial background exposure rate that varied from less than 6 microroentgens per hour (mR/h) to 50 mR/h plus a cosmic-ray contribution that varied from 4.5 mR/h at an elevation of 900 meters (3,000 feet) to 8.5 mR/h at 2,400 meters (8,000 feet). In addition to the principal gamma-emitting, naturally occurring isotopes (potassium-40, thallium-208, bismuth-214, and actinium-228), the man-made radioactive isotopes found in this survey were cobalt-60, cesium-137, europium-152, protactinium-234m an indicator of depleted uranium, and americium-241, which are due to human actions in the survey area. Individual, site-wide plots of gross terrestrial exposure rate, man-made exposure rate, and americium-241 activity (approximating the distribution of all transuranic material) are presented. In addition, expanded plots of individual areas exhibiting these man-made contaminations are given. A comparison is made between the data from this survey and previous aerial radiological surveys of the Nevada Test Site. Some previous ground-based measurements are discussed and related to the aerial data. In regions away from man-made activity, the exposure rates inferred from the gamma-ray measurements collected during this survey agreed very well with the exposure rates inferred from previous aerial surveys

  2. 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

  3. On history of medical radiology in Ukraine: main directions of scientific development (1920-1941)

    International Nuclear Information System (INIS)

    Pilipenko, M.Yi.; Artamonova, N.O.; Busigyina, N.O.

    1994-01-01

    The work is devoted to the history of medical radiology in Ukraine. It deals with principal problems of scientific research development during 1920-1941. The authors describe both known and little known facts of the history of foundation and development of the first Ukrainian radiological, roentgenological and oncological institutes. Main achievements in radiology development i.e. foundation of large specialized research centres in Kharkov, kiev, Odessa, independent departments of roentgenology both at the majority of medical institutes and three advanced training institutes for doctors, organization of ALL-Union and Republican Congresses and Conferences of Radiologists, publication of a special journal > (Problems of Oncology) are described

  4. 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.

  5. Nevada Test Site Radiological Control Manual, Revision 1

    International Nuclear Information System (INIS)

    2010-01-01

    This document supersedes DOE/NV/25946--801, 'Nevada Test Site Radiological Control Manual,' Revision 0 issued in October 2009. Brief Description of Revision: A minor revision to correct oversights made during revision to incorporate the 10 CFR 835 Update; and for use as a reference document for Tenant Organization Radiological Protection Programs. 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) and the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO). Compliance with these requirements will ensure compliance with Title 10 Code of Federal Regulations (CFR) Part 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 Livermore, California; and Andrews Air Force Base, Maryland. In addition, fieldwork by NNSA/NSO at other locations is covered by this manual. The NTS is located in Nye County, Nevada. The NTS is located approximately 105 kilometers (65 miles) northwest of Las Vegas. It is a remote facility that covers approximately 3,500 square kilometers (1,375 square miles) of land. The dimensions of the NTS vary from 46 to 56 kilometers (28 to 35 miles) in width (eastern to western border) and from 64 to 88 kilometers (40 to 55 miles) in length (northern to southern border). The NTS is surrounded to the west, north, and east by additional thousands of acres of land withdrawn from the public domain for use as a protected wildlife range and as a military gunnery range. These public exclusion areas comprise the Nellis Air Force Range complex, previously designated as the Nellis Air Force Base Bombing and Gunnery Range, and the Tonopah Test Range. These two areas provide a buffer zone between the test areas and public lands administered by the Federal Bureau of Land

  6. 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

  7. 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

  8. 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)

  9. The Hanford Site: An anthology of early histories

    International Nuclear Information System (INIS)

    Gerber, M.S.

    1993-10-01

    This report discusses the following topics: Memories of War: Pearl Harbor and the Genesis of the Hanford Site; safety has always been promoted at the Hanford Site; women have an important place in Hanford Site history; the boom and bust cycle: A 50-year historical overview of the economic impacts of Hanford Site Operations on the Tri-Cities, Washington; Hanford's early reactors were crucial to the sites's history; T-Plant made chemical engineering history; the UO 3 plant has a long history of service. PUREX Plant: the Hanford Site's Historic Workhorse. PUREX Plant Waste Management was a complex challenge; and early Hanford Site codes and jargon

  10. 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

  11. In situ radiological characterization to support a test excavation at a liquid waste disposal site

    International Nuclear Information System (INIS)

    Keele, B.D.; Bauer, R.G.; Blewett, G.R.; Troyer, G.L.

    1994-05-01

    An in situ radiological detection system was developed to support a small test excavation at a liquid waste disposal site at the Hanford Site in Richland, Washington. Instrumentation, calibration and comparisons to samples are discussed

  12. 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

  13. Radiology

    International Nuclear Information System (INIS)

    Lissner, J.

    1985-01-01

    Diagnostic radiology is still the foremost of all innovative medical disciplines. This has many advantages but also some handicaps, e.g. the siting problem of medical equipment whose clinical potential is not fully known. This applies in particular to nuclear spin tomography, where the Laender governments and the Scientific Council seen to agree that all universities should have the appropriate equipment as soon as possible in order to intensify interdisciplinary research. Formerly, in the case of computerized tomography, there was less readiness. As a result, the siting of CT equipment is less organically structured. A special handicap of innovative fields is the problem of training and advanced training. The Chamber of Medicine and the Association of Doctors Participating in the Health Insurance Plan have issued regulations aimed at a better standardisation in this field. (orig.) [de

  14. Black History, Inc! Investigating the Production of Black History through Walmart's Corporate Web Site

    Science.gov (United States)

    King, LaGarrett J.; Brown, Anthony L.

    2012-01-01

    Social and public sites are becoming a popular medium for intellectual consumption of Black history. Given the educational climate in which many students' exposure to Black history may come from outside of schools, the authors examine how Walmart's Black History Month Web site produced simplistic and safe narratives about African American history.

  15. Heart in anatomy history, radiology, anthropology and art.

    Science.gov (United States)

    Marinković, S; Lazić, D; Kanjuh, V; Valjarević, S; Tomić, I; Aksić, M; Starčević, A

    2014-05-01

    Anthropologic, artistic and medical significance of heart inspired usto undertake this multidisciplinary study. Amongst the 24 obtained echocardiograms and phonograms, 1 was used for a Photoshop processing. In addition, over 20,000 art work reproductions were examined in this study. Artistic and symbolic presentation of heart started some 15,000 years ago. First heart models were made by the Egyptian and Olmec civilisations. Ancient cultures regarded heart as the seat of the soul, spirit and intelligence. First anatomical and artistic images of heart were created by Leonardo da Vinci in the15th century, and first wax models by the Italian anatomists in the 17th century. Mediaeval religious symbolism of heart was replaced in the Renaissance and later on mainly by its role in the romantic love. Anatomical heart art continued in the 18th and 19th centuries through the works of Sénac, Cloquet, Hirschfeldand Bourgery. Some modern artists, such as Dalí, Kahlo, Rivera, Warhol, Ivanjicki, Vital, Kober and Mastrlova, created the anatomical heart images or sculptures, whereas some others, such as Duchamp, Klee, Miró, Matisse and Dine, presented heart symbol in their artworks. New radiologic technologies produce fine images of heart, some of which are similar to the works of modern artists. Heart biology and symbolism have had a tremendous influence on our culture, including art and medical sciences. New radiologic techniques and computer technology have produced such images of heart, which substantially improved diagnosis, but also enhanced the heart aesthetics.

  16. Radiology

    International Nuclear Information System (INIS)

    Edholm, P.R.

    1990-01-01

    This is a report describing diagnostic techniques used in radiology. It describes the equipment necessary for, and the operation of a radiological department. Also is described the standard methods used in radiodiagnosis. (K.A.E.)

  17. The Hanford Site: An anthology of early histories

    Energy Technology Data Exchange (ETDEWEB)

    Gerber, M.S.

    1993-10-01

    This report discusses the following topics: Memories of War: Pearl Harbor and the Genesis of the Hanford Site; safety has always been promoted at the Hanford Site; women have an important place in Hanford Site history; the boom and bust cycle: A 50-year historical overview of the economic impacts of Hanford Site Operations on the Tri-Cities, Washington; Hanford`s early reactors were crucial to the sites`s history; T-Plant made chemical engineering history; the UO{sub 3} plant has a long history of service. PUREX Plant: the Hanford Site`s Historic Workhorse. PUREX Plant Waste Management was a complex challenge; and early Hanford Site codes and jargon.

  18. 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

  19. 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

  20. 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

  1. 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

  2. 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.

  3. 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

  4. 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

  5. History of critical experiments at Pajarito Site

    Energy Technology Data Exchange (ETDEWEB)

    Paxton, H.C.

    1983-03-01

    This account describes critical and subcritical assemblies operated remotely at the Pajarito Canyon Site at the Los Alamos National Laboratory. Earliest assemblies, directed exclusively toward the nuclear weapons program, were for safety tests. Other weapon-related assemblies provided neutronic information to check detailed weapon calculations. Topsy, the first of these critical assemblies, was followed by Lady Godiva, Jezebel, Flattop, and ultimately Big Ten. As reactor programs came to Los Alamos, design studies and mockups were tested at Pajarito Site. For example, nearly all 16 Rover reactors intended for Nevada tests were preceded by zero-power mockups and proof tests at Pajarito Site. Expanded interest and capability led to fast-pulse assemblies, culminating in Godiva IV and Skua, and to the Kinglet and Sheba solution assemblies.

  6. History of critical experiments at Pajarito Site

    International Nuclear Information System (INIS)

    Paxton, H.C.

    1983-03-01

    This account describes critical and subcritical assemblies operated remotely at the Pajarito Canyon Site at the Los Alamos National Laboratory. Earliest assemblies, directed exclusively toward the nuclear weapons program, were for safety tests. Other weapon-related assemblies provided neutronic information to check detailed weapon calculations. Topsy, the first of these critical assemblies, was followed by Lady Godiva, Jezebel, Flattop, and ultimately Big Ten. As reactor programs came to Los Alamos, design studies and mockups were tested at Pajarito Site. For example, nearly all 16 Rover reactors intended for Nevada tests were preceded by zero-power mockups and proof tests at Pajarito Site. Expanded interest and capability led to fast-pulse assemblies, culminating in Godiva IV and Skua, and to the Kinglet and Sheba solution assemblies

  7. 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

  8. 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

  9. Radiology

    International Nuclear Information System (INIS)

    Sykora, A.

    2006-01-01

    In this text-book basic knowledge about radiology, biomedical diagnostic methods (radiography, computer tomography), nuclear medicine and safety and radiation protection of personnel on the radiodiagnostic place of work are presented

  10. 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)

  11. Semipalatinsk nuclear test site: History of building and function

    International Nuclear Information System (INIS)

    Sergazina, G.M.; Balmukhanov, S.B.

    1999-01-01

    A vast materials on history of Semipalatinsk nuclear test site creation and it building and function are presented. Authors with big reliability report one page of Kazakhstan's history. In steppe on naked place thousands of soldiers and officers, construct and military specialists have built the nuclear site on which during 40 years were conducting nuclear tests . Prolonged chronic radiation on population living near by site results to tragedy which is confessed by General Assembly of United Nations. In the book aspects of test site conversion and rehabilitation of injured population are considered. The book consists of introduction, three chapters and conclusion. The book is intended to wide circle of readers. (author)

  12. Work history and mortality risks in 90,268 US radiological technologists.

    Science.gov (United States)

    Liu, Jason J; Freedman, D Michal; Little, Mark P; Doody, Michele M; Alexander, Bruce H; Kitahara, Cari M; Lee, Terrence; Rajaraman, Preetha; Miller, Jeremy S; Kampa, Diane M; Simon, Steven L; Preston, Dale L; Linet, Martha S

    2014-12-01

    There have been few studies of work history and mortality risks in medical radiation workers. We expanded by 11 years and more outcomes our previous study of mortality risks and work history, a proxy for radiation exposure. Using Cox proportional hazards models, we estimated mortality risks according to questionnaire work history responses from 1983 to 1989 through 2008 by 90,268 US radiological technologists. We controlled for potential confounding by age, birth year, smoking history, body mass index, race and gender. There were 9566 deaths (3329 cancer and 3020 circulatory system diseases). Mortality risks increased significantly with earlier year began working for female breast (p trend=0.01) and stomach cancers (p trend=0.01), ischaemic heart (p trend=0.03) and cerebrovascular diseases (p trend=0.02). The significant trend with earlier year first worked was strongly apparent for breast cancer during baseline through 1997, but not 1998-2008. Risks were similar in the two periods for circulatory diseases. Radiological technologists working ≥5 years before 1950 had elevated mortality from breast cancer (HR=2.05, 95% CI 1.27 to 3.32), leukaemia (HR=2.57, 95% CI 0.96 to 6.68), ischaemic heart disease (HR=1.13, 95% CI 0.96 to 1.33) and cerebrovascular disease (HR=1.28, 95% CI 0.97 to 1.69). No other work history factors were consistently associated with mortality risks from specific cancers or circulatory diseases, or other conditions. Radiological technologists who began working in early periods and for more years before 1950 had increased mortality from a few cancers and some circulatory system diseases, likely reflecting higher occupational radiation exposures in the earlier years. Published by the BMJ Publishing Group Limited. For permission to use (where not already granted under a licence) please go to http://group.bmj.com/group/rights-licensing/permissions.

  13. 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)

  14. 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

  15. Radiological survey following decontamination activities near the TA-45 site

    International Nuclear Information System (INIS)

    Gunderson, T.; Buhl, T.; Romero, R.; Salazar, J.

    1983-07-01

    Three areas at the site of a former radioactive liquid waste treatment plant at Los Alamos National Laboratory were decontaminated during 1982 by Bechtel Corporation, with health physics support provided by Eberline Instrument Corporation, under the Department of Energy's Formerly Utilized Sites Remedial Action Program (FUSRAP). Before decontamination, there were above-background concentrations of gross alpha, gross beta, 238 Pu, 239 240 Pu, 241 Am, 90 Sr, and 137 Cs in the surface soils. These combined concentrations were above operational decontamination guidelines for surface soil contamination. After cleanup operations, radionuclide concentrations in surface soils at all three sites were within decontamination guidelines

  16. Mobile radiological monitoring around Nuclear Power Plant site at Tarapur

    International Nuclear Information System (INIS)

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

    2008-01-01

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

  17. Synopsis of History of American Society for Therapeutic Radiology and Oncology 1958-2008

    International Nuclear Information System (INIS)

    Montana, Gustavo S.

    2008-01-01

    Purpose: To provide a synopsis of the history of the association of radiation oncologists in the United States, currently known as the American Society for Therapeutic Radiology and Oncology (ASTRO), with the occasion of the 50th anniversary of the organization. Methods and Materials: The history of ASTRO, from its beginning as the American Club of Therapeutic Radiologists, is the subject of a book that is to be released with the occasion of the 50th Annual Meeting of the Society in 2008. This book was prepared by members of ASTRO's History Committee and History Working Subcommittee. The source material for the book was the archives of the Society and recorded interviews, conducted by members of the subcommittee, of members of the Society and of the past and present Society staff. The book was also based on previously published material. This article used the source material used for the Society anniversary book. Results: This synopsis of the history of the Society will provide a source of reference for anyone interested in the history of the Society from its foundation in 1958 to the present, 2008

  18. 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.

  19. 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

  20. Regulatory Aspects for Site Selection for Radiological and Nuclear Installations

    International Nuclear Information System (INIS)

    Sirag, N.M.

    2016-01-01

    The purpose of this research is to check in one of the considerations necessary for any new nuclear facility. A previous study that was conducted using a questionnaire reported that general admission to the public, aesthetic considerations, and characteristics associated with the site are able to adequately accept the existence of new nuclear facilities. The findings of this research revealed that public involvement in the process of site selection and in the design of nuclear power plants, an understanding of their point of view is an important aspect of a participatory approach. An important factor for any new nuclear program is to improve confidence in the energy choices in the future. A survey was conducted on 1304 adults to, to get the main goal. The study concluded showed that the prevalence of culture of safety reflected on the public acceptance of the site, especially if it takes into account the aesthetic and environmental considerations.

  1. 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

  2. Measurement techniques for radiological characterization of contaminated sites

    Energy Technology Data Exchange (ETDEWEB)

    Loos, M

    1996-09-18

    Once the decision is taken to characterize a contaminated site, appropriate measurement techniques must be selected. The choice will depend on the available information, on the nature and extent of the contamination, as well as on available resources (staff and budget). Some techniques are described on the basis of examples of characterization projects (e.g. Olen area in Belgium).

  3. Radiological impact of 2016 operations at the Savannah River Site

    Energy Technology Data Exchange (ETDEWEB)

    Minter, K. L. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Jannik, G. T. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Dixon, K. M. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

    2017-06-01

    This report presents the environmental dose assessment methods and the estimated potential doses to the offsite public from 2016 Savannah River Site (SRS) air and liquid radioactive releases. Also documented are potential doses from special-case exposure scenarios, such as the consumption of wildlife or goat milk.

  4. 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...

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

    International Nuclear Information System (INIS)

    Chareyron, Bruno

    2010-01-01

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

  6. A radiological disadvantage for siting a repository at Yucca Mountain

    International Nuclear Information System (INIS)

    Spiegler, P.

    1996-01-01

    At Yucca mountain, the disposal of large amounts of U-238, U-234, and Pu-238 will result in a long term build-up of Rn-222. In time, because of erosion, the repository horizon will move closer to the surface and large amounts of Rn-222 gas will be able to leak into the atmosphere. The area surrounding Yucca Mountain will become a site of high radioactive background. Sullivan and Pescatore have brought the issue to the attention of the DOE

  7. 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)

  8. Cerebral metastasis masquerading as cerebritis: A case of misguiding history and radiological surprise!

    Directory of Open Access Journals (Sweden)

    Ashish Kumar

    2013-01-01

    Full Text Available Cerebral metastases usually have a characteristic radiological appearance. They can be differentiated rather easily from any infective etiology. Similarly, positive medical history also guides the neurosurgeon towards the possible diagnosis and adds to the diagnostic armamentarium. However, occasionally, similarities on imaging may be encountered where even history could lead us in the wrong direction and tends to bias the clinician. We report a case of a 40-year-old female with a history of mastoidectomy for otitis media presenting to us with a space occupying lesion in the right parietal region, which was thought pre-operatively as an abscess along with the cerebritis. Surprisingly, the histopathology proved it to be a metastatic adenocarcinoma. Hence, a ring enhancing lesion may be a high grade neoplasm/metastasis/abscess, significant gyral enhancement; a feature of cerebritis is not linked with a neoplastic etiology more often. This may lead to delayed diagnosis, incorrect prognostication and treatment in patients having coincidental suggestive history of infection. We review the literature and highlight the key points helping to differentiate an infective from a neoplastic pathology which may look similar at times.

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

    International Nuclear Information System (INIS)

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

    1984-01-01

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

  10. History of the Clinical Institute of Radiology in Ljubljana on its 80th anniversary (1923-2003). Historia Magistra Vitae

    International Nuclear Information System (INIS)

    Jevtic, V.

    2004-01-01

    Background. The manuscript presents a short history of the Clinical Radiology Institute in Ljubljana, University Clinical Centre, and the leading radiological institution in Slovenia since its establishment in 1923. Throughout its history the Institute has been faced with numerous obstacles. Its major problems have always included the lack of professional and economical independence, which has made it difficult for the Institute to keep up with the fast technological development of the world's radiology, as well as the shortage of radiologists and radiographers with the consequence of the excessive work load and difficulties in educational and research activities. Despite some serious problems the expertise of the Institute's leadership, together with the enthusiasm of all radiologists and radiographers, has enabled a continuous professional and technological development which is the basis of today's high quality diagnostic and interventional radiology. Many of the remarkable achievements would not have been possible without some extraordinary personalities who laid down the solid foundations of today's Institute. Conclusions. Eighty years of Clinical Radiology Institute in Ljubljana is a history of the successful development of the republic's leading radiological institution, a success based on determination, unity and the professional integrity of all its members and management. (author)

  11. 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.

  12. 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

  13. 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

  14. The history of MR imaging as seen through the pages of radiology.

    Science.gov (United States)

    Edelman, Robert R

    2014-11-01

    The first reports in Radiology pertaining to magnetic resonance (MR) imaging were published in 1980, 7 years after Paul Lauterbur pioneered the first MR images and 9 years after the first human computed tomographic images were obtained. Historical advances in the research and clinical applications of MR imaging very much parallel the remarkable advances in MR imaging technology. These advances can be roughly classified into hardware (eg, magnets, gradients, radiofrequency [RF] coils, RF transmitter and receiver, MR imaging-compatible biopsy devices) and imaging techniques (eg, pulse sequences, parallel imaging, and so forth). Image quality has been dramatically improved with the introduction of high-field-strength superconducting magnets, digital RF systems, and phased-array coils. Hybrid systems, such as MR/positron emission tomography (PET), combine the superb anatomic and functional imaging capabilities of MR imaging with the unsurpassed capability of PET to demonstrate tissue metabolism. Supported by the improvements in hardware, advances in pulse sequence design and image reconstruction techniques have spurred dramatic improvements in imaging speed and the capability for studying tissue function. In this historical review, the history of MR imaging technology and developing research and clinical applications, as seen through the pages of Radiology, will be considered.

  15. 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.

  16. 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

  17. 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)

  18. 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

  19. 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

  20. 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

  1. 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

  2. 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.

  3. 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

  4. 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.

  5. 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

  6. 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

  7. 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

  8. 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

  9. 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)

  10. 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.

  11. On history of medical radiology development in Ukraine: war period and after war reconstruction (1941-1947)

    International Nuclear Information System (INIS)

    Pilipenko, M.Yi.; Artamonova, N.O.; Busigyina, N.O.; Kononenko, O.K.

    1994-01-01

    The paper is devoted to history of Ukrainian medical radiology development, namely main problems of its scientific and practical aspects of development during 1941-1947. The authors describe the work of Ukrainian roentgenologists and radiologists during the war and after war restoration of radiological service. Contribution of Ukrainian scientists to practical and theoretical achievements of military roentgenology is shown. Operative mobilization of all the forces for restoration of destroyed during the war years roentgenological service allowed to start scientific research within a short term (already in 1945)

  12. 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)

  13. 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

  14. 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

  15. 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)

  16. 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)

  17. Malpractice suits in chest radiology: an evaluation of the histories of 8265 radiologists.

    Science.gov (United States)

    Baker, Stephen R; Patel, Ronak H; Yang, Lily; Lelkes, Valdis M; Castro, Alejandro

    2013-11-01

    The aim of this study was to present rates of claims, causes of error, percentage of cases resulting in a judgment, and average payments made by radiologists in chest-related malpractice cases in a survey of 8265 radiologists. The malpractice histories of 8265 radiologists were evaluated from the credentialing files of One-Call Medical Inc., a preferred provider organization for computed tomography/magnetic resonance imaging in workers' compensation cases. Of the 8265 radiologists, 2680 (32.4%) had at least 1 malpractice suit. Of those who were sued, the rate of claims was 55.1 per 1000 person years. The rate of thorax-related suits was 6.6 claims per 1000 radiology practice years (95% confidence interval, 6.0-7.2). There were 496 suits encompassing 48 different causes. Errors in diagnosis comprised 78.0% of the causes. Failure to diagnose lung cancer was by far the most frequent diagnostic error, representing 211 cases or 42.5%. Of the 496 cases, an outcome was known in 417. Sixty-one percent of these were settled in favor of the plaintiff, with a mean payment of $277,230 (95% confidence interval, 226,967-338,614). Errors in diagnosis, and among them failure to diagnose lung cancer, were by far the most common reasons for initiating a malpractice suit against radiologists related to the thorax and its contents.

  18. 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

  19. 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

  20. Radiology Physician Extenders: A Literature Review of the History and Current Roles of Physician Extenders in Medical Imaging.

    Science.gov (United States)

    Sanders, Vicki L; Flanagan, Jennifer

    2015-01-01

    The purpose of the literature review was to assess the origins of radiology physician extenders and examine the current roles found in the literature of advanced practice physician extenders within medical imaging. Twenty-six articles relating to physician assistants (PAs), nurse practitioners (NPs), radiologist assistants (RAs), and nuclear medicine advanced associates (NMAAs) were reviewed to discern similarities and differences in history, scope of practice, and roles in the medical imaging field. The literature showed PAs and NPs are working mostly in interventional radiology. PAs, NPs, and RAs perform similar tasks in radiology, including history and physicals, evaluation and management, preprocedure work-up, obtaining informed consent, initial observations/reports, and post-procedure follow-up. NPs and PAs perform a variety of procedures but most commonly vascular access, paracentesis, and thoracentesis. RAs perform gastrointestinal, genitourinary, nonvascular invasive fluoroscopy procedures, and vascular access procedures. The review revealed NMAAs are working in an advanced role, but no specific performances of procedures was found in the literature, only suggested tasks and clinical competencies. PAs, NPs, and RAs are currently the three main midlevel providers used in medical imaging. These midlevel providers are being used in a variety of ways to increase the efficiency of the radiologist and provide diagnostic and therapeutic radiologic procedures to patients. NMAAs are being used in medical imaging but little literature is available on current roles in clinical practice. More research is needed to assess the exact procedures and duties being performed by these medical imaging physician extenders.

  1. 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.

  2. Description of radiological problems at inactive uranium mill sites and formerly utilized MED/AEC sites

    International Nuclear Information System (INIS)

    Jacobs, D.G.; Dickson, H.W.

    1979-02-01

    During the early years of development of the nuclear program in the United States, more than a hundred sites were used by the Manhattan Engineer District (MED), and the U.S. Atomic Energy Commission (AEC), and/or its uranium suppliers. Many of these sites are no longer used for such activities, but in many cases, the real estate remains contaminated with radioactivity and can be a potential source of exposure to members of the general public. In addition, 22 inactive uranium mill tailings sites exist in the western part of the United States. Radioactive contamination conditions range from slight contamination on the surfaces of buildings and equipment to extensive contamination of the subsoil. The Department of Energy is conducting a program to assure that adequate precautions are taken in the management of these properties to provide the cost-effective protection of public health while permitting further use of land and other resources. Several issues which should be considered in the development of an effective policy for long-term management of such properties are identified

  3. Description of radiological problems at inactive uranium mill sites and formerly utilized MED/AEC sites

    Energy Technology Data Exchange (ETDEWEB)

    Jacobs, D.G.; Dickson, H.W.

    1979-02-01

    During the early years of development of the nuclear program in the United States, more than a hundred sites were used by the Manhattan Engineer District (MED), and the U.S. Atomic Energy Commission (AEC), and/or its uranium suppliers. Many of these sites are no longer used for such activities, but in many cases, the real estate remains contaminated with radioactivity and can be a potential source of exposure to members of the general public. In addition, 22 inactive uranium mill tailings sites exist in the western part of the United States. Radioactive contamination conditions range from slight contamination on the surfaces of buildings and equipment to extensive contamination of the subsoil. The Department of Energy is conducting a program to assure that adequate precautions are taken in the management of these properties to provide the cost-effective protection of public health while permitting further use of land and other resources. Several issues which should be considered in the development of an effective policy for long-term management of such properties are identified.

  4. 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)

  5. 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

  6. 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

  7. Ecological risk assessment for radiological and chemical contaminants at a site with historical contamination

    International Nuclear Information System (INIS)

    Garisto, N.C.; Janes, A.; Peters, R.

    2010-01-01

    An Ecological Risk Assessment was carried out for a uranium conversion facility in Ontario, located on a site with a history of contamination. The ERA assessed risk to aquatic and terrestrial biota from exposure to radionuclides and non-radionuclides in soil and groundwater associated with the site. The results indicated no undue risk to aquatic biota from radionuclides. Small potential risks were identified for terrestrial biota at limited locations associated with this industrial site. Recommendations are provided for follow-up risk-informed activities. (author)

  8. Methodological aspects of creating a radiological 'passport' of the former Semipalatinsk nuclear test site

    International Nuclear Information System (INIS)

    Dubasov, Yu.V.; Smagulov, S.G.; Tukhvatulin, Sh.T.

    2002-01-01

    During its existence, 456 nuclear tests were carried out at the Semipalatinsk Test Site - 30 at the ground surface, 86 in the atmosphere and 340 underground. Radioactive fallout from ground surface tests is responsible for the present radiation conditions within the 'Test Field'. The radiation situation in the Degelen Mountains is caused by 209 underground tests carried out in local tunnels. Within the former Test Site there are three large and several small zones to which general access is prohibited for public health reasons: the 'Test Field', the Degelen Mountains, lake Shagan, the rim of the lake, and the adjacent land to the north. The information and characteristics, which have to be included in radiological passport of the former Semipalatinsk Test Site, are discussed along with general information about the Semipalatinsk site, its administrative status, the population distribution throughout the territory, all the economic activities taking place within the territory, the zones and structures representing a radiation hazard, and radiohydrogeological conditions of the test site and the adjacent regions, biogenic conditions (topography, soil, vegetation), wildlife, fauna monitoring, etc. (author)

  9. 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

  10. 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

  11. A Short History of Waste Management at the Hanford Site

    International Nuclear Information System (INIS)

    Gephart, Roy E.

    2010-01-01

    The world's first full-scale nuclear reactors and chemical reprocessing plants built at the Hanford Site in the desert of eastern Washington State produced two-thirds of the plutonium generated in the United States for nuclear weapons. Operating these facilities also created large volumes of radioactive and chemical waste, some of which was released into the environment exposing people who lived downwind and downstream. Hanford now contains the largest accumulation of nuclear waste in the Western Hemisphere. Hanford's last reactor shut down in 1987 followed by closure of the last reprocessing plant in 1990. Today, Hanford's only mission is cleanup. Most onsite radioactive waste and nuclear material lingers inside underground tanks or storage facilities. About half of the chemical waste remains in tanks while the rest persists in the soil, groundwater, and burial grounds. Six million dollars each day, or nearly two billion dollars each year, are spent on waste management and cleanup activities. There is significant uncertainty in how long cleanup will take, how much it will cost, and what risks will remain for future generations. This paper summarizes portions of the waste management history of the Hanford Site published in the book 'Hanford: A Conversation about Nuclear Waste and Cleanup.'

  12. 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

  13. 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.

  14. 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

  15. 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

  16. 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

  17. 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.

  18. 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)

  19. 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.

  20. 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)

  1. History of aerial surveys in response to radiological incidents and accidents

    International Nuclear Information System (INIS)

    Jobst, J.E.

    1986-01-01

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

  2. 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)

  3. 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)

  4. An aerial radiological survey of the Double Track Site and surrounding area. Central Nevada

    International Nuclear Information System (INIS)

    Hendricks, T.J.

    1995-07-01

    An aerial radiological survey of the Double Track Site was conducted in December 1993. An interim report was issued. That report described survey procedures and presented terrestrial exposure rate and wide-area-averaged plutonium isopleth plots. This letter report presents additional plutonium plots and some ''rule-of-thumb'' calculations which should help the reader to properly interpret the data presented. Attached to this report are three isopleth plots produced from the Double Track data. No one processing method provides all the answers regarding a particular surveyed area. Where peak values are most important, isopleth number-sign 1, created from the original unsmoothed data, is the presentation of choice. Isopleth number-sign 2, from smoothed data, is superior for the detection of areas of widespread low-level contamination. Isopleth number-sign 3, also smoothed data, satisfied a particular early mission goal but is not as useful for cleanup operations as the other two

  5. 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

  6. 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

  7. 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

  8. 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

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

    International Nuclear Information System (INIS)

    Lyons, Craig

    2009-01-01

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

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

    International Nuclear Information System (INIS)

    Cindro, M.; Stepisnik, M.; Pinezic, D.; Sinka, D.; Skanata, D.

    2016-01-01

    The work described in this paper was done within the EU funded project 'Upgrading the systems for the on- and off-line monitoring of radioactivity in the environment in Croatia in regular and emergency situations'. The existing system of early warning in case of nuclear accident in Croatia (SPUNN), managed by the State Office for Radiological and Nuclear Safety, includes 33 stations for measuring ambient gamma dose rate (GDR). The aim of the project was to determine appropriate correction factors that will allow the results from this network to be used not only for timely warning in case of nuclear accident but also in routine environmental monitoring to determine the background radiation. Additionally, in the case of fresh deposition due to radioactive contamination, the corrected values are better suited to be used as an input for support systems for decision making in the case of emergency (such as RODOS), as well as for international data exchange (EURDEP) or automatic interpolation and mapping of radiological data (INTAMAP). The response of the individual probes to natural or accidental radiation mostly depends on the geometry or topography, surrounding buildings, vegetation (trees) and the type of soil beneath the detector. In the case of measuring the dose rate, objects such as buildings act as a shield against gamma radiation and limit the field of vision of the detector. If we want to have representative values that can be compared with other measuring sites, it is clear that we need to define standard conditions that each location has to meet. This is true not only for the probes within the same network, but can also be applied more broadly, at the international level, since data exchange mechanisms for GDR data already exist across Europe. The response of each probe is not determined only by the physical features, it is also important to understand the radiological characteristics of the site. Radiological characterization was performed through

  11. 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

  12. 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

  13. 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

  14. 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)

  15. 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.)

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

    Energy Technology Data Exchange (ETDEWEB)

    Ecklund, K.; Share, J.C. [Children' s Hospital Medical Center, Boston, MA (United States). Dept. of Radiology

    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.)

  17. 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

  18. 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

  19. 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

  20. 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

  1. 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

  2. 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

  3. Radiological criteria and methods for remediation of contaminated former mining sites

    International Nuclear Information System (INIS)

    Biesold, H.; Thielen, H.; Weiss, D.

    2001-01-01

    Mining and ore processing have a long history in the New States of Germany, Saxony, Thuringia and Saxony-Anhalt. The ores were often mineralized with uranium and therefore the residues are a radiological hazard to man and environment. Immediately after World War II the Soviet Union started to develop its nuclear capability by mining uranium ores in the occupied zone of East Germany. At the beginning the exploitation was concentrated on former underground mines of silver and other non ferrous ores. Afterwards, new uranium deposits were explored in Saxony and eastern Thuringia. Numerous waste rock piles and tailings ponds of considerable size resulted from these mining activities. Uranium production reached some 220,000 t between 1946 and 1990. After the reunification in 1990, production was finished for economic and other reasons. The German Federal Government was faced with one of the largest ecological, social and economic challenges. In this report an overview is given on kind and amount of the mining residues, the radiation protection criteria, models and data bases used for risk assessment and dose calculation are explained and remediation methods are described. (authors)

  4. Radiological criteria and methods for remediation of contaminated former mining sites

    Energy Technology Data Exchange (ETDEWEB)

    Biesold, H.; Thielen, H. [Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) mbH, Cologne (Germany); Weiss, D. [Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) mbH, Berlin (Germany)

    2001-07-01

    Mining and ore processing have a long history in the New States of Germany, Saxony, Thuringia and Saxony-Anhalt. The ores were often mineralized with uranium and therefore the residues are a radiological hazard to man and environment. Immediately after World War II the Soviet Union started to develop its nuclear capability by mining uranium ores in the occupied zone of East Germany. At the beginning the exploitation was concentrated on former underground mines of silver and other non ferrous ores. Afterwards, new uranium deposits were explored in Saxony and eastern Thuringia. Numerous waste rock piles and tailings ponds of considerable size resulted from these mining activities. Uranium production reached some 220,000 t between 1946 and 1990. After the reunification in 1990, production was finished for economic and other reasons. The German Federal Government was faced with one of the largest ecological, social and economic challenges. In this report an overview is given on kind and amount of the mining residues, the radiation protection criteria, models and data bases used for risk assessment and dose calculation are explained and remediation methods are described. (authors)

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

    International Nuclear Information System (INIS)

    Gonzalez, D.A.

    1986-09-01

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

  6. Notes on the history of the radiological study of Egyptian mummies: from X-rays to new imaging techniques.

    Science.gov (United States)

    Cosmacini, P; Piacentini, P

    2008-08-01

    A few centuries after the practice of mummification was finally abolished in the seventh century A.D., mummies began to capture the collective imagination, exerting a mysterious fascination that continues to this day. From the beginning, the radiological study of Egyptian mummies permitted the collection not only of medical data but also of anthropological and archaeological evidence. The first radiological study of an Egyptian mummy was performed by Flinders Petrie shortly after the discovery of X-rays in 1895, and since then, radiology has never stopped investigating these special patients. By the end of the 1970s, computed tomography (CT) scanning permitted more in-depth studies to be carried out without requiring the mummies to be removed from their cartonnage. CT images can be used to obtain a three-dimensional reconstruction of the mummy that provides important new information, in part thanks to the virtual endoscopy technique known as "fly through". Moreover, starting from CT data and using sophisticated graphics software, one can reconstruct an image of the face of the mummified individual at the time of his or her death. The history of imaging, from its origins until now, from the simplest to the most sophisticated technique, allows us to appreciate why these studies have been, and still are, fundamental in the study of Egyptian mummies.

  7. 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

  8. Spatializing the History of Ecology : Sites, Journeys, Mappings

    NARCIS (Netherlands)

    de Bont, Raf; Lachmund, Jens

    2017-01-01

    Throughout its history, the discipline of ecology has always been profoundly entangled with the history of space and place. On the one hand, ecology is a field science that has thrived on the study of concrete spatial entities, such as islands, forests or rivers. These spaces are the workplaces in

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

    International Nuclear Information System (INIS)

    Miller, M.G.

    1984-12-01

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

  10. 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

  11. Guidelines for radiological performance assessment of DOE low-level radioactive waste disposal sites

    International Nuclear Information System (INIS)

    Case, M.J.; Otis, M.D.

    1988-07-01

    This document provides guidance for conducting radiological performance assessments of Department of Energy (DOE) low-level radioactive waste (LLW) disposal facilities. The guidance is specifically intended to provide the fundamental approach necessary to meet the performance assessment requirements. The document is written for LLW facility operators or other personnel who will manage the performance assessment task. The document is meant to provide guidance for conducting performance assessments in a generally consistent manner at all DOE LLW disposal facilities. The guidance includes a summary of performance objectives to be met by LLW disposal facilities (these objectives are derived from current DOE and other applicable federal regulatory guidelines); specific criteria for an adequate performance assessment and from which a minimum set of required calculations may be determined; recommendations of methods for screening critical components of the analysis system so that these components can be addressed in detail; recommendations for the selection of existing models and the development of site-specific models; recommendations of techniques for comparison of assessment results with performance objectives; and a summary of reporting requirements

  12. 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

  13. Work history and radioprotection practices in relation to cancer incidence and mortality in US radiologic technologists performing nuclear medicine procedures.

    Science.gov (United States)

    Bernier, Marie Odile; Doody, Michele M; Van Dyke, Miriam E; Villoing, Daphné; Alexander, Bruce H; Linet, Martha S; Kitahara, Cari M

    2018-05-02

    Technologists working in nuclear medicine (NM) are exposed to higher radiation doses than most other occupationally exposed populations. The aim of this study was to estimate the risk of cancer in NM technologists in relation to work history, procedures performed and radioprotection practices. From the US Radiologic Technologists cohort study, 72 755 radiologic technologists who completed a 2003-2005 questionnaire were followed for cancer mortality through 31 December 2012 and for cancer incidence through completion of a questionnaire in 2012-2013. Multivariable-adjusted models were used to estimate HRs for total cancer incidence and mortality by history of ever performing NM procedures and frequency of performing specific diagnostic or therapeutic NM procedures and associated radiation protection measures by decade. During follow-up (mean=7.5 years), 960 incident cancers and 425 cancer deaths were reported among the 22 360 technologists who worked with NM procedures. We observed no increased risk of cancer incidence (HR 0.96, 95% CI 0.89 to 1.04) or death (HR 1.05, 95% CI 0.93 to 1.19) among workers who ever performed NM procedures. HRs for cancer incidence but not mortality were higher for technologists who began performing therapeutic procedures in 1960 and later compared with the 1950s. Frequency of performing diagnostic or therapeutic NM procedures and use of radioprotection measures were not consistently associated with cancer risk. No clear associations were observed for specific cancers, but results were based on small numbers. Cancer incidence and mortality were not associated with NM work history practices, including greater frequency of procedures performed. © Article author(s) (or their employer(s) unless otherwise stated in the text of the article) 2018. All rights reserved. No commercial use is permitted unless otherwise expressly granted.

  14. 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)

  15. History of the Hanford Site: 1943-1990

    Energy Technology Data Exchange (ETDEWEB)

    D.W. Harvey

    2000-09-01

    This booklet was developed to highlight the national and international historical events that occurred in association with the development of the Hanford Site. The purpose of the booklet is to increase the awareness Hanford Site employees have of the historical significance of the Site's contributions and missions during the Manhattan Project (1943-1946) and Cold War era (1946-1990). By increasing knowledge and understanding of the Site's unique heritage, it is hoped this publication will help generate an appreciation of the Site's historic buildings and structures, and, thus, instill a sense of ''ownership'' in these buildings. One cannot appreciate the historic significance of a place or building without first knowing its story.

  16. Radiological risk from consuming fish and wildlife to Native Americans on the Hanford Site (USA)

    Energy Technology Data Exchange (ETDEWEB)

    Delistraty, Damon, E-mail: DDEL461@ecy.wa.gov [Washington State Department of Ecology, N. 4601 Monroe, Spokane, WA 99205-1295 (United States); Verst, Scott Van [Washington State Department of Health, Olympia, WA (United States); Rochette, Elizabeth A. [Washington State Department of Ecology, Richland, WA (United States)

    2010-02-15

    Historical operations at the Hanford Site (Washington State, USA) have released a wide array of non-radionuclide and radionuclide contaminants into the environment. As a result of stakeholder concerns, Native American exposure scenarios have been integrated into Hanford risk assessments. Because its contribution to radiological risk to Native Americans is culturally and geographically specific but quantitatively uncertain, a fish and wildlife ingestion pathway was examined in this study. Adult consumption rates were derived from 20 Native American scenarios (based on 12 studies) at Hanford, and tissue concentrations of key radionuclides in fish, game birds, and game mammals were compiled from the Hanford Environmental Information System (HEIS) database for a recent time interval (1995-2007) during the post-operational period. It was assumed that skeletal muscle comprised 90% of intake, while other tissues accounted for the remainder. Acknowledging data gaps, median concentrations of eight radionuclides (i.e., Co-60, Cs-137, Sr-90, Tc-99, U-234, U-238, Pu-238, and Pu-239/240) in skeletal muscle and other tissues were below 0.01 and 1 pCi/g wet wt, respectively. These radionuclide concentrations were not significantly different (Bonferroni P>0.05) on and off the Hanford Site. Despite no observed difference between onsite and offsite tissue concentrations, radiation dose and risk were calculated for the fish and wildlife ingestion pathway using onsite data. With median consumption rates and radionuclide tissue concentrations, skeletal muscle provided 42% of the dose, while other tissues (primarily bone and carcass) accounted for 58%. In terms of biota, fish ingestion was the largest contributor to dose (64%). Among radionuclides, Sr-90 was dominant, accounting for 47% of the dose. At median intake and radionuclide levels, estimated annual dose (0.36 mrem/yr) was below a dose limit of 15 mrem/yr recommended by the United States Environmental Protection Agency (USEPA

  17. 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

  18. 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

  19. 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

  20. 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)

  1. Prospective radiological dose assessment. Amersham plc (Amersham site) variation application December 1998

    International Nuclear Information System (INIS)

    Allott, R.

    2001-01-01

    Amersham plc (previously Nycomed-Amersham plc) submitted an application to the Environment Agency in December 1998 for a variation to their radioactive waste discharge authorisations granted under the Radioactive Substances Act 1993. The application requested a reduction in the discharge limits for certain radionuclides and no change for the remaining radionuclides. Amersham plc undertook a further review of their discharge requirements and submitted a new assessment for revised limits in January 2001. This report provides an assessment of the radiological implications of discharges at these revised limits requested by Amersham plc and the limits proposed by the Agency. It has been prepared by the National Compliance Assessment Service at the request of Thames Region to support their determination of the application. Four candidate critical groups were identified who could be exposed to discharges from the Amersham site: 1) Sewage workers at the Maple Lodge sewage works who might be exposed to external radiation from discharges contained within sewage and inadvertently inhale or ingest sewage. 2) Anglers on the Grand Union Canal who eat a small proportion of their annual catch of freshwater fish, who drink water abstracted solely from the River Colne and eat vegetables irrigated by water from the canal. 3) Persons living closest to site who eat locally produced food. 4) Dog walkers living near to site who eat locally produced food. For continuous discharges at the Agency's proposed annual limits, the highest dose of 160 μSv/y is predicted to be received by infants who live closest to the site and eat locally produced food. Therefore, this has been identified as the critical group. Children and adults living at the same location and eating locally produced food receive doses of 140 μSv/y and 130 μSv/y respectively. The critical group dose is less than the source constraint of 300 μSv/y. The dose is dominated by direct radiation from the site (110 μSv/y) and the

  2. 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)

  3. 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

  4. 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)

  5. Radiological Assessment for the Removal of Legacy BPA Power Lines that Cross the Hanford Site

    International Nuclear Information System (INIS)

    Millsap, William J.; Brush, Daniel J.

    2013-01-01

    This paper discusses some radiological field monitoring and assessment methods used to assess the components of an old electrical power transmission line that ran across the Hanford Site between the production reactors area (100 Area) and the chemical processing area (200 Area). This task was complicated by the presence of radon daughters -- both beta and alpha emitters -- residing on the surfaces, particularly on the surfaces of weathered metals and metals that had been electrically-charged. In many cases, these activities were high compared to the DOE Surface Contamination Guidelines, which were used as guides for the assessment. These methods included the use of the Toulmin model of argument, represented using Toulmin diagrams, to represent the combined force of several strands of evidences, rather than a single measurement of activity, to demonstrate beyond a reasonable doubt that no or very little Hanford activity was present and mixed with the natural activity. A number of forms of evidence were used: the overall chance of Hanford contamination; measurements of removable activity, beta and alpha; 1-minute scaler counts of total surface activity, beta and alpha, using 'background makers'; the beta activity to alpha activity ratios; measured contamination on nearby components; NaI gamma spectral measurements to compare uncontaminated and potentially-contaminated spectra, as well as measurements for the sentinel radionuclides, Am- 241 and Cs-137 on conducting wire; comparative statistical analyses; and in-situ measurements of alpha spectra on conducting wire showing that the alpha activity was natural Po-210, as well as to compare uncontaminated and potentially-contaminated spectra

  6. Radiological Assessment for the Removal of Legacy BPA Power Lines that Cross the Hanford Site

    Energy Technology Data Exchange (ETDEWEB)

    Millsap, William J.; Brush, Daniel J.

    2013-11-13

    This paper discusses some radiological field monitoring and assessment methods used to assess the components of an old electrical power transmission line that ran across the Hanford Site between the production reactors area (100 Area) and the chemical processing area (200 Area). This task was complicated by the presence of radon daughters -- both beta and alpha emitters -- residing on the surfaces, particularly on the surfaces of weathered metals and metals that had been electrically-charged. In many cases, these activities were high compared to the DOE Surface Contamination Guidelines, which were used as guides for the assessment. These methods included the use of the Toulmin model of argument, represented using Toulmin diagrams, to represent the combined force of several strands of evidences, rather than a single measurement of activity, to demonstrate beyond a reasonable doubt that no or very little Hanford activity was present and mixed with the natural activity. A number of forms of evidence were used: the overall chance of Hanford contamination; measurements of removable activity, beta and alpha; 1-minute scaler counts of total surface activity, beta and alpha, using "background makers"; the beta activity to alpha activity ratios; measured contamination on nearby components; NaI gamma spectral measurements to compare uncontaminated and potentially-contaminated spectra, as well as measurements for the sentinel radionuclides, Am- 241 and Cs-137 on conducting wire; comparative statistical analyses; and in-situ measurements of alpha spectra on conducting wire showing that the alpha activity was natural Po-210, as well as to compare uncontaminated and potentially-contaminated spectra.

  7. 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.

  8. 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

  9. Pediatric radiology in the Philadelphia region: a history of pedigrees and legacies

    International Nuclear Information System (INIS)

    Markowitz, Richard I.

    2009-01-01

    The specialty of pediatric radiology in the Philadelphia region has grown and evolved over the past eight decades originating from early ''visiting'' radiologists to Drs. Hope and Kirkpatrick, the ''giants'' of the 1950s and 1960s, to over 40 actively practicing pediatric radiologists. Clinical excellence, commitment to teaching, and advancement of knowledge through research remain the goals and ideals, much as they were many years ago. Philadelphia has been a fertile home and environment for this development, mostly because of outstanding leaders and role models who have trained and influenced generations of pediatric radiologists. The purpose of this article is to tell the story of this growth and development and to explore the intellectual origins, professional ''genealogy,'' and legacies left by those who created this tradition. (orig.)

  10. Pediatric radiology in the Philadelphia region: a history of pedigrees and legacies

    Energy Technology Data Exchange (ETDEWEB)

    Markowitz, Richard I. [University of Pennsylvania School of Medicine, Department of Radiology, Children' s Hospital of Philadelphia, Philadelphia, PA (United States); Children' s Hospital of Philadelphia, Department of Radiology, Philadelphia, PA (United States)

    2009-09-15

    The specialty of pediatric radiology in the Philadelphia region has grown and evolved over the past eight decades originating from early ''visiting'' radiologists to Drs. Hope and Kirkpatrick, the ''giants'' of the 1950s and 1960s, to over 40 actively practicing pediatric radiologists. Clinical excellence, commitment to teaching, and advancement of knowledge through research remain the goals and ideals, much as they were many years ago. Philadelphia has been a fertile home and environment for this development, mostly because of outstanding leaders and role models who have trained and influenced generations of pediatric radiologists. The purpose of this article is to tell the story of this growth and development and to explore the intellectual origins, professional ''genealogy,'' and legacies left by those who created this tradition. (orig.)

  11. Pediatric radiology in the Philadelphia region: a history of pedigrees and legacies.

    Science.gov (United States)

    Markowitz, Richard I

    2009-09-01

    The specialty of pediatric radiology in the Philadelphia region has grown and evolved over the past eight decades originating from early "visiting" radiologists to Drs. Hope and Kirkpatrick, the "giants" of the 1950s and 1960s, to over 40 actively practicing pediatric radiologists. Clinical excellence, commitment to teaching, and advancement of knowledge through research remain the goals and ideals, much as they were many years ago. Philadelphia has been a fertile home and environment for this development, mostly because of outstanding leaders and role models who have trained and influenced generations of pediatric radiologists. The purpose of this article is to tell the story of this growth and development and to explore the intellectual origins, professional "genealogy," and legacies left by those who created this tradition.

  12. Involving stakeholders in radiological protection decision making: recovery history and lessons from the people of Fukushima.

    Science.gov (United States)

    Lazo, T

    2016-12-01

    Between September 2011 and August 2015, the International Commission on Radiological Protection (ICRP) organised a series of 12 stakeholder dialogue workshops with residents of Fukushima Prefecture. Discussions focused on recovery, addressing topics such as protection of children, management of contaminated food, monitoring, and self-help measures. The OECD Nuclear Energy Agency (NEA) supported, and the Committee on Radiation Protection and Public Health (CRPPH) Secretariat attended, all 12 meetings to listen directly to the concerns of affected individuals and draw lessons for CRPPH. To summarise the dialogue results, ICRP organised a final meeting in Date, Japan with the support of NEA and other organisations. The lessons from and utility of the dialogue meetings were praised by dialogue participants and sponsors, and ICRP agreed that some form of dialogue would continue, although with ICRP participation and support rather than leadership. This paper summarises the internationally relevant lessons learned by CRPPH from this important process.

  13. Teaching the History of Astronomy On Site in London

    Science.gov (United States)

    French, Linda M.

    2016-01-01

    In the autumn of 2014, the author had the opportunity to teach a class on the history of astronomy in England as part of a study abroad experience for students at Illinois Wesleyan University. The philosophy of the program is to use the rich cultural environment of London as a setting for active learning. In the classroom, students read and discussed selected works by Ptolemy, Copernicus, Kepler, Galileo, and Herschel. We visited Stonehenge, the Royal Greenwich Observatory, the London Science Museum, the London Monument, and the library of the Royal Astronomical Society. Lessons learned from the experience will be shared.

  14. History of ground motion programs at the Nevada Test Site

    International Nuclear Information System (INIS)

    Banister, J.R.

    1984-01-01

    Some measurements were made in the atmospheric testing era, but the study of ground motion from nuclear tests became of wider interest after the instigation of underground testing. The ground motion generated by underground nuclear test has been investigated for a number of reasons including understanding basic phenomena, operational and safety concerns, yield determination, stimulation of earthquake concerns, and developing methods to aid in treaty verifications. This history of ground motion programs will include discussing early studies, high yield programs, Peaceful Nuclear Explosions tests, and some more recent developments. 6 references, 10 figures

  15. Analysis of the Variability of Classified and Unclassified Radiological Source term Inventories in the Frenchman Flat Area, Nevada test Site

    International Nuclear Information System (INIS)

    Zhao, P.; Zavarin, M.

    2008-01-01

    It has been proposed that unclassified source terms used in the reactive transport modeling investigations at NTS CAUs should be based on yield-weighted source terms calculated using the average source term from Bowen et al. (2001) and the unclassified announced yields reported in DOE/NV-209. This unclassified inventory is likely to be used in unclassified contaminant boundary calculations and is, thus, relevant to compare to the classified inventory. They have examined the classified radionuclide inventory produced by 10 underground nuclear tests conducted in the Frenchman Flat (FF) area of the Nevada Test Site. The goals were to (1) evaluate the variability in classified radiological source terms among the 10 tests and (2) compare that variability and inventory uncertainties to an average unclassified inventory (e.g. Bowen 2001). To evaluate source term variability among the 10 tests, radiological inventories were compared on two relative scales: geometric mean and yield-weighted geometric mean. Furthermore, radiological inventories were either decay corrected to a common date (9/23/1992) or the time zero (t 0 ) of each test. Thus, a total of four data sets were produced. The date of 9/23/1992 was chosen based on the date of the last underground nuclear test at the Nevada Test Site

  16. 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

  17. 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

  18. 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

  19. Challenges in defining a radiologic and hydrologic source term for underground nuclear test centers, Nevada Test Site, Nye County, Nevada

    International Nuclear Information System (INIS)

    Smith, D.K.

    1995-06-01

    The compilation of a radionuclide inventory for long-lived radioactive contaminants residual from nuclear testing provides a partial measure of the radiologic source term at the Nevada Test Site. The radiologic source term also includes potentially mobile short-lived radionuclides excluded from the inventory. The radiologic source term for tritium is known with accuracy and is equivalent to the hydrologic source term within the saturated zone. Definition of the total hydrologic source term for fission and activation products that have high activities for decades following underground testing involves knowledge and assumptions which are presently unavailable. Systematic investigation of the behavior of fission products, activation products and actinides under saturated or Partially saturated conditions is imperative to define a representative total hydrologic source term. This is particularly important given the heterogeneous distribution of radionuclides within testing centers. Data quality objectives which emphasize a combination of measurements and credible estimates of the hydrologic source term are a priority for near-field investigations at the Nevada Test Site

  20. The Monticello, Utah, uranium mill tailings site: A case history

    International Nuclear Information System (INIS)

    Korte, N.E.; Kearl, P.M.; Sewell, J.M.; Fleischhauer, H.L.; Abramiuk, I.N.

    1984-01-01

    A multidisciplinary study was conducted to characterize the potential for contamination from the inactive millsite in Monticello, Utah. Emphasis was given to site geology, hydrology, and geochemistry for two reasons: (1) a perennial stream flows through the tailings area, and (2) a culinary aquifer is overlain by an alluvial aquifer contaminated by the tailings area. Study results indicate that surface-water contamination attributable to the piles exists for approximately 6 km downstream from the site. Contamination also exists in the alluvial aquifer underlying the millsite. Hydrologic studies indicate an active alluvial system, with recharge to the gravels by infiltration through the trailings. Fortunately, water-level and water-quality data, together with the results of a 51-hour pump test, indicate that the Dakota Formation is an effective aquitard, restricting the downward movement of contaminated water to the underlying culinary aquifer

  1. A history of solid waste packaging at the Hanford Site

    International Nuclear Information System (INIS)

    Duncan, D.R.; Weyns-Rollosson, D.I.; Pottmeyer, J.A.; Stratton, T.J.

    1995-02-01

    Since the initiation of the defense materials product mission, a total of more than 600,000 m 3 of radioactive solid waste has been stored or disposed at the US Department of Energy's (DOE) Hanford Site, located in southeastern Washington State. As the DOE complex prepares for its increasing role in environmental restoration and waste remediation, the characterization of buried and retrievably stored waste will become increasingly important. Key to this characterization is an understanding of the standards and specifications to which waste was packaged; the regulations that mandated these standards and specifications; the practices used for handling and packaging different waste types; and the changes in these practices with time

  2. Case history: Vertical barrier wall system for Superfund Site

    International Nuclear Information System (INIS)

    Koelling, M.A.; Kovac, C.P.; Norris, J.E.

    1997-01-01

    Design considerations and construction aspects are presented for the installation of a vertical barrier wall system for the Boeing Company at a Superfund Site near Seattle, WA. The construction was performed during 1996. The vertical barrier wall system included: (1) a soil-bentonite (SB) slurry wall, approximately 670 meters (2200 feet) in length, ranging from 12 to 21 meters (40 to 70 feet) in depth; (2) expansion of a cover system over the area enclosed by the SB wall; and (3) surface drainage improvements. Design and construction of the system addressed requirements of a Consent Decree for the site issued in 1993. The paper discusses the development of the design to meet remedial performance goals of preventing migration of contaminants in the soil/groundwater system and aiding aquifer restoration. Secondly, the paper details installation of the SB wall, highlighting the more significant construction issues, which included excavation of the wall through glacially deposited cobbles/boulders/till as well as addressing the severe elevation changes along the wall alignment. Thirdly, the paper presents Quality Assurance (QA) monitoring and testing performed during the construction phase

  3. 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

  4. Case history update: RCRA waste site remediation by telerobotic methods

    International Nuclear Information System (INIS)

    Yemington, C.R.; Stone, J.

    1992-01-01

    This paper presents a summary of the first 18 months of closure work at the Kerr Hollow Quarry site on the DOE reservation at Oak Ridge, Tennessee. Closure work includes recovery and processing of explosive, toxic and radioactive waste. As of January 1992, more than 10,000 items had been processed and removed from the quarry, exclusively by remotely operated equipment. Drums, buckets, tubing assemblies and other containers are being shredded to react any explosive contents. Concussion and projectiles are controlled by operating the shredder under 30 feet of water. The performance of the shredder, the effectiveness of the approach, production rates and maintenance requirements are addressed in the paper. To avoid exposing personnel to hazards, all work in the restricted area is done remotely. Two remotely operated vehicles were used to clear a pad, set a stand and install the 200-hp shredder. Some materials exposed by shredding are stable in water but react when exposed to air. In addition, radioactive items are mixed in with the other wastes. Safety considerations have therefore led to use of remote techniques for handling and examining materials after recovery. Deteriorated gas cylinders, which may contain pressurized toxic materials, are recovered and handled exclusively by remotely operated equipment. Waste retrieval work at the Kerr Hollow Quarry has proven the capability and cost-effectiveness of remotely operated equipment to deal with a wide variety of hazardous materials in an unstructured waste site environment. A mixture of radioactive materials, toxic chemicals, explosives and asbestos has been found and processed. Remotely operated vehicles have retrieved, sorted and processed more than 10,000 items including drums, buckets, pipe manifolds, gas cylinders and other containers

  5. Radiology clinical synopsis: a simple solution for obtaining an adequate clinical history for the accurate reporting of imaging studies on patients in intensive care units

    International Nuclear Information System (INIS)

    Cohen, Mervyn D.; Alam, Khurshaid

    2005-01-01

    Lack of clinical history on radiology requisitions is a universal problem. We describe a simple Web-based system that readily provides radiology-relevant clinical history to the radiologist reading radiographs of intensive care unit (ICU) patients. Along with the relevant history, which includes primary and secondary diagnoses, disease progression and complications, the system provides the patient's name, record number and hospital location. This information is immediately available to reporting radiologists. New clinical information is immediately entered on-line by the radiologists as they are reviewing images. After patient discharge, the data are stored and immediately available if the patient is readmitted. The system has been in routine clinical use in our hospital for nearly 2 years. (orig.)

  6. 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.)

  7. 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.)

  8. Leaching studies of low-level waste as input to radiological assessment at the Drigg disposal site, Cumbria

    International Nuclear Information System (INIS)

    Poulton, J.; Rushbrook, P.E.

    1989-01-01

    Over the period of operation of the low-level waste disposal site at Drigg in Cumbria, several radiological assessments have been carried out. This paper discusses data requirements for such an assessment and in particular describes a project to measure the leaching behaviour of wastes. This project, jointly set up by the staff of BNFL and Environmental Safety Centre at Harwell, began in 1985. The objectives were to determine the processes operating within the waste disposal trenches at Drigg and conditions affecting them. The paper describes the installation and operation of the first of a series of lysimeters designed to simulate conditions in current trenches. (author)

  9. Radiological pathways analysis for spent solvents from the boiler chemical cleaning at the Pickering Nuclear Site

    International Nuclear Information System (INIS)

    Garisto, N.C.; Eslami, Z.; Hodgins, S.; Beaman, T.; Von Svoboda, S.; Marczak, J.

    2006-01-01

    Spent solvents are generated as a result of Boiler Chemical Cleanings (BCC) at CANDU reactor sites. These solutions contain small amount of radioactivity from a number of different sources including: Cut tubes - short sections of boiler tubes are infrequently removed from the boilers for a detailed characterization. These tubes are typically only plugged at the tubesheet allowing the primary side deposits to be exposed to BCC solvents. Tube leaks - primary to secondary side leaks also occur infrequently as a result of tube degradation. Radioactivity from the leaking fluid can consequently be deposited in the sludge on the secondary side of the tubes. Diffusion of tritium - during normal operation of the reactor units, tritium slowly diffuses from the heavy water in the primary heat-transfer system to the light-water coolant on the secondary side. Some of this tritium is retained in the secondary side deposits. The Pickering Nuclear Generating Station (PNGS) would like the flexibility to have several options for handling the spent solvent waste and associated rinse water from BCC. To this end, a radiological pathways analysis was undertaken to determine dose consequences associated with each option. Sample results from this study are included in this paper. The pathways analysis is used in this study to calculate dose to hypothetical receptors including individuals such as truck drivers, incinerator workers, residue (ash) handlers, residents who live near the landfill, inadvertent intruders into the landfill after closure and residents who live near the outfall. This dose is compared to a de minimis dose. A de minimis dose or dose rate represents a level of risk, which is generally accepted as being of no significance. Shipments of spent solvents and rinse water with corresponding doses below de minimis can be sent to conventional (i.e., non-radioactive) landfills for incineration and disposal as the radioactive dose associated with them is much less than natural

  10. 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.

  11. The environmental restoration in the management of radiological accidents with off site consequences

    International Nuclear Information System (INIS)

    Vazquez, C.; Montero, M.; Moraleda, M.; Diaz, J.; Claver, F.; Valles, O.; Rodriguez, N.; Gutierrez, J.

    1998-01-01

    Radiological accidents are among the potential cases of environmental contamination that could have consequences on the health of the population. These accidents, associated with an increase in the level of radiological exposure surpassing the natural background, have been investigated in greater depth than other conventional accidents. This investigation has included the evaluation of their probability, magnitude and consequences in order to establish safety norms. Nevertheless, the social perception of this type of risk appears to be disproportionately high. The development of a comprehensible and adequate standardized system for the evaluation of the radiological risk and the applicability of corrective actions to reduce this type of risk at local level, will undoubtedly contribute to increase the public confidence in the advised options for the restoration of environments contaminated with the long lived radionuclides. This system should consider the local specificity of each contaminated place, and take into account the associated unwanted consequences for each option. This paper presents the first results of a system to help the decision makers in the quantitative evaluation of the radiological risk produced by long lived radionuclides Cs 137, Cs 134 and Sr 90 spread over urban, agricultural and semi-natural environments and the applicable options to reduce it. The evaluation of these applicable options is made considering the reduction of dose that can be reached, the monetary costs and the significant associated secondary effects if there are any. All these factors are integrated for a time period depending on the half-life of the contaminants and on their strength and distribution on the scenario when intervention is being planned. (authors)

  12. 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

  13. Optimizing Travel Time to Outpatient Interventional Radiology Procedures in a Multi-Site Hospital System Using a Google Maps Application.

    Science.gov (United States)

    Mandel, Jacob E; Morel-Ovalle, Louis; Boas, Franz E; Ziv, Etay; Yarmohammadi, Hooman; Deipolyi, Amy; Mohabir, Heeralall R; Erinjeri, Joseph P

    2018-02-20

    The purpose of this study is to determine whether a custom Google Maps application can optimize site selection when scheduling outpatient interventional radiology (IR) procedures within a multi-site hospital system. The Google Maps for Business Application Programming Interface (API) was used to develop an internal web application that uses real-time traffic data to determine estimated travel time (ETT; minutes) and estimated travel distance (ETD; miles) from a patient's home to each a nearby IR facility in our hospital system. Hypothetical patient home addresses based on the 33 cities comprising our institution's catchment area were used to determine the optimal IR site for hypothetical patients traveling from each city based on real-time traffic conditions. For 10/33 (30%) cities, there was discordance between the optimal IR site based on ETT and the optimal IR site based on ETD at non-rush hour time or rush hour time. By choosing to travel to an IR site based on ETT rather than ETD, patients from discordant cities were predicted to save an average of 7.29 min during non-rush hour (p = 0.03), and 28.80 min during rush hour (p travel time when more than one location providing IR procedures is available within the same hospital system.

  14. Radiological guidelines for application to DOE's Formerly Utilized Sites Remedial Action Program. [FUSRAP sites

    Energy Technology Data Exchange (ETDEWEB)

    1983-03-01

    The US Department of Energy has implemented a program to evaluate and, where necessary, take action to protect the public from contamination at sites that were used in the past to process and/or store radioactive materials for the former US Army Corps of Engineers Manhattan Engineer District or the US Atomic Energy Commission. The program is identified as the Formerly Utilized Sites Remedial Action Program (FUSRAP). This document describes methods considered appropriate for the evaluation of health effects that might possible be caused by radioactive contamination at FUSRAP sites. This assessment methodology is applied to a typical site for the purposeof deriving guidelines for the cleanup of contaminated soil. Additional guidance is provided for planning site-specific remedial action that is consistent with the overall objectives of FUSRAP.

  15. 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

  16. 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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2002-07-01

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

  18. 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

  19. 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

  20. Assessment of diffusion tensor image quality across sites and vendors using the American College of Radiology head phantom.

    Science.gov (United States)

    Wang, Zhiyue J; Seo, Youngseob; Babcock, Evelyn; Huang, Hao; Bluml, Stefan; Wisnowski, Jessica; Holshouser, Barbara; Panigrahy, Ashok; Shaw, Dennis W W; Altman, Nolan; McColl, Roderick W; Rollins, Nancy K

    2016-05-08

    The purpose of this study was to explore the feasibility of assessing quality of diffusion tensor imaging (DTI) from multiple sites and vendors using American College of Radiology (ACR) phantom. Participating sites (Siemens (n = 2), GE (n= 2), and Philips (n = 4)) reached consensus on parameters for DTI and used the widely available ACR phantom. Tensor data were processed at one site. B0 and eddy current distortions were assessed using grid line displacement on phantom Slice 5; signal-to-noise ratio (SNR) was measured at the center and periphery of the b = 0 image; fractional anisotropy (FA) and mean diffusivity (MD) were assessed using phantom Slice 7. Variations of acquisition parameters and deviations from specified sequence parameters were recorded. Nonlinear grid line distortion was higher with linear shimming and could be corrected using the 2nd order shimming. Following image registration, eddy current distortion was consistently smaller than acquisi-tion voxel size. SNR was consistently higher in the image periphery than center by a factor of 1.3-2.0. ROI-based FA ranged from 0.007 to 0.024. ROI-based MD ranged from 1.90 × 10-3 to 2.33 × 10-3 mm2/s (median = 2.04 × 10-3 mm2/s). Two sites had image void artifacts. The ACR phantom can be used to compare key qual-ity measures of diffusion images acquired from multiple vendors at multiple sites.

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

    International Nuclear Information System (INIS)

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

    1995-01-01

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

  2. [History of the development of radiodiagnosis at the Russian Research Center of Roentgenology and Radiology: on the occasion of the 90th anniversary of its foundation].

    Science.gov (United States)

    Solodkiĭ, V A; Kotliarov, P M; Nudnov, N V

    2014-01-01

    The paper describes the history of the Russian Research Center of Roentgenology and Radiology set up 90 years ago, the main advances of the researchers of the Institute in roentgenology and radiodiagnosis in historical perspective--from the last century up to the present day. It gives a brief list of the most important procedures and publications on radiodiagnosis, which have been developed and published by the Institute's researchers.

  3. 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

  4. 100 years from the invention of X-rays. From the history of the radiology in Slovakia

    International Nuclear Information System (INIS)

    Kutarna, A.

    1996-01-01

    The survey of the development of radiology after the First World War (after disintegration of Austro-Hungarian Monarchy) as well as after the Second World War in Slovakia is given. Attention is dedicated to the development of radiodiagnostic and radiotherapeutic methods in Slovakia, as well as to personal occupation of the heads of radiologic clinics. In the last decade radiologic working-places and the departments are equipped with modern and efficient techniques. While in the year 1962 a number of the radiologists was about 90 doctors, in the year 1995 a number more than 360 doctors was registered from which are 80 doctors of radiotherapy. A number of radiologic assistants is about 1200. In Slovak hospitals are about 370 departments of radiology and more than 300 radiodiagnostic working-places and 12 departments of radiotherapy. 29 refs

  5. Radiological investigations at the 'Taiga' nuclear explosion site: Site description and in situ measurements

    Energy Technology Data Exchange (ETDEWEB)

    Ramzaev, V., E-mail: V.Ramzaev@mail.ru [Institute of Radiation Hygiene, Mira str. 8, 197101 St.-Petersburg (Russian Federation); Repin, V.; Medvedev, A.; Khramtsov, E.; Timofeeva, M.; Yakovlev, V. [Institute of Radiation Hygiene, Mira str. 8, 197101 St.-Petersburg (Russian Federation)

    2011-07-15

    In the summer of 2009, we performed a field survey of the 'Taiga' peaceful underground nuclear explosion site, the Perm region, Russia (61.30{sup o} N, 56.60{sup o} E). The explosion was carried out by the USSR in 1971. This paper provides an extended summary of the available published data on the 'Taiga' experiment. A detailed description of the site is illustrated by original aerial and ground-level photos. A large artificial lake (700 m long and 350 m wide) currently occupies the central area of the experimental site. The ground lip surrounding the lake is covered by a newly grown mixed forest. In situ measurements, performed in August 2009, revealed elevated levels of the {gamma}-ray dose rate in air on the banks of the lake 'Taiga'. Two hot spots were detected on the eastern bank of the lake. The excess of the {gamma}-ray radiation is attributable to the man-made radionuclides {sup 60}Co and {sup 137}Cs. The current external {gamma}-ray dose rate to a human from the contaminations associated with the 'Taiga' experiment was between 9 and 70 {mu}Sv per week. Periodic monitoring the site is recommended. - Highlights: > We studied a radiation anomaly at the 'Taiga' underground nuclear explosion site. > The anomaly currently has an area of approximately 1 km{sup 2}. > The excess of {gamma}-ray radiation at the site is mainly attributable to {sup 60}Co and {sup 137}Cs. > The external effective dose may currently exceed the negligible value of 10 {mu}Sv y{sup -1}.

  6. Application of an internet web-site of medical images in tele-radiology

    International Nuclear Information System (INIS)

    Wang Weizhong; Wang Hua; Xie Jingxia; Wang Songzhang; Li Xiangdong; Qian Min; Cao Huixia

    2000-01-01

    Objective: To build and Internet web-site of medical images for tele-education and tele-consultation. Methods: Collecting medical images of cases that fulfilled diagnostic standards for teaching and were pathologically proved. The images were digitized using digital camera and scanner. Frontpage 98, Homesite 2.5 and text editors were used for programming. Results: The web site encompasses many useful cases and was update every week. With smart and friendly interface, easy used navigation, the site runs reliably in TCP/IP environment. The site's URL is http://imager.163.net. At present, the site has received about 100 visits per week. Conclusion: The well-designed and programmed internet web site of medical images would be easily acceptable and is going to play an important role in tele-education and tele-consultation

  7. 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.

  8. 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

  9. Formerly utilized MED/AEC sites remedial action program. Radiological survey of the Harshaw Chemical Company, Cleveland, Ohio

    International Nuclear Information System (INIS)

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

    1984-04-01

    During the MED/AEC era, the Harshaw Chemical Company processed large quantities of normal uranium to produce both oxide and fluoride compounds. This work was done under contract to MED and its successor, AEC. Records indicated that at the time the AEC contract was terminated, the facility was decontaminated by Harshaw and released from AEC control in 1960. However, a search of AEC records indicated that documentation was insufficient to determine whether the decontamination work was adequate by current guidelines. Hence, a radiological assessment of the site ws initiated in 1976. The entire grounds and all buildings were surveyed using surface survey instruments to detect surface contamination and radiation detectors to determine general radiation levels. Extensive surface contamination was found throughout the site. While the major contamination was found in Plant C, significant levels of contamination also were found in 16 other buildings and at 32 exterior locations. The contaminating material seemed to be normal uranium exclusively. Air samples were taken at numerous indoor locations throughout the site, but no elevated levels of radon were detected. This was as expected since normal uranium has been separated from radium and hence radon levels are very low. Several soil samples were taken from around the site. Analyses of these samples indicated extensive soil contamination, as well as suspected contamination of the river bed in the vicinity of the plant outfall. Scheduled subsurface investigation of the site, as well as of the river bed and sewer system, have not been conducted. Levels of contamination at this site are significantly above guidelines for release of the site for unrestricted use. 57 figures, 7 tables

  10. Buildings radiological characterization report for the Weldon Spring Site Remedial Action Project, Weldon Spring, Missouri

    International Nuclear Information System (INIS)

    1990-04-01

    This report summarizes radiological characterization data on the Weldon Spring Chemical Plant (WSCP) buildings gathered as part of five previous investigations, and provides a consistent will be used to support future feasibility studies which will determine the best available technologies for ultimate disposition of the buildings and associated equipment. At present no structure or piece of equipment can be released from the WSCP for unrestricted use without further radiation measurements being performed. A final group of equipment and building components contains surface radioactivity levels in excess of DOE guidelines; this group, usually found in buildings housing uranium and/or thorium processing equipment, will require decontamination and comprehensive scanning in order to be considered for unrestricted use release. 9 refs., 44 tabs

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

    International Nuclear Information System (INIS)

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

    1987-01-01

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

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

    International Nuclear Information System (INIS)

    Feimster, E.L.

    1993-09-01

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

  13. 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.)

  14. Data Quality Objectives Summary Report Supporting Radiological Air Surveillance Monitoring for the INL Site

    Energy Technology Data Exchange (ETDEWEB)

    Haney, Thomas Jay [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2015-05-01

    This report documents the Data Quality Objectives (DQOs) developed for the Idaho National Laboratory (INL) Site ambient air surveillance program. The development of the DQOs was based on the seven-step process recommended “for systematic planning to generate performance and acceptance criteria for collecting environmental data” (EPA 2006). The process helped to determine the type, quantity, and quality of data needed to meet current regulatory requirements and to follow U.S. Department of Energy guidance for environmental surveillance air monitoring design. It also considered the current air monitoring program that has existed at INL Site since the 1950s. The development of the DQOs involved the application of the atmospheric dispersion model CALPUFF to identify likely contamination dispersion patterns at and around the INL Site using site-specific meteorological data. Model simulations were used to quantitatively assess the probable frequency of detection of airborne radionuclides released by INL Site facilities using existing and proposed air monitors.

  15. Radiological guidelines for application to DOE's Formerly Utilized Sites Remedial Action Program

    International Nuclear Information System (INIS)

    1983-03-01

    The US Department of Energy has implemented a program to evaluate and, where necessary, take action to protect the public from contamination at sites that were used in the past to process and/or store radioactive materials for the former US Army Corps of Engineers Manhattan Engineer District or the US Atomic Energy Commission. The program is identified as the Formerly Utilized Sites Remedial Action Program (FUSRAP). This document describes methods considered appropriate for the evaluation of health effects that might possible be caused by radioactive contamination at FUSRAP sites. This assessment methodology is applied to a typical site for the purposeof deriving guidelines for the cleanup of contaminated soil. Additional guidance is provided for planning site-specific remedial action that is consistent with the overall objectives of FUSRAP

  16. Sweetgum Response to Nitrogen Fertilization on Sites of Different Quality and Land Use History

    Science.gov (United States)

    D. Andrew Scott; Donald J. Kaczmarek; James A. Burger; Michael B. Kane

    2002-01-01

    Nitrogen (N) fertilizer management in young hardwood plantations is difficult due to our lack of understanding of the site-specific mechanisms that control tree response. Differences in landuse history and soil characteristics can alter the plant response to added N considerably. Foliage biomass, N content, N concentration, resorption, and soil N supply characteristics...

  17. Site descriptions for preliminary radiological assessments of low-level waste repositories

    International Nuclear Information System (INIS)

    Burgess, W.E.; Jones, C.H.; Sumerling, T.J.; Ashton, J.

    1988-07-01

    The environmental contexts of four sites, previously under investigation by UK Nirex Ltd. as potential locations for low-level waste disposal facilities, are described. Information on geographical setting, climate, surface hydrology, land use, agriculture, fisheries, geology and hydrogeology is presented. The geological and hydrogeological data are interpreted with the support of deterministic modelling of groundwater conditions. The routes by which radionuclides may migrate from the site are identified and reduced to 1D statistical descriptions suitable for use in probabilistic risk assessments. Additional data required to improve the assessment of the performance of the site are identified. (author)

  18. Radiologic characterization of the Mexican Hat, Utah, uranium mill tailings remedial action site: Appendix D, Addenda D1--D7

    Energy Technology Data Exchange (ETDEWEB)

    Ludlam, J.R.

    1985-01-01

    This radiologic characterization of the inactive uranium millsite at Mexican Hat, Utah, was conducted by Bendix Field Engineering Corporation foe the US Department of Energy (DOE), Grand Junction Project Office, in response to and in accord with a Statement of Work prepared by the DOE Uranium Mill tailings Remedial Action Project (UMTRAP) Technical Assistance Contractor, Jacobs Engineering Group, Inc. the objective of this project was to determine the horizontal and vertical extent of contamination that exceeds the US Environmental Protection Agency (EPA) standards at the Mexican Hat site. The data presented in this report are required for characterization of the areas adjacent to the Mexican Hat tailings piles and for the subsequent design of cleanup activities. Some on-pile sampling was required to determine the depth of the 15-pCi/g Ra-226 interface in an area where wind and water erosion has taken place.

  19. Assessment of the natural radioactivity and its radiological hazards in prospective ore deposit sites in Southwestern Nigeria

    International Nuclear Information System (INIS)

    Ifeoluwa, O.P.; Obed, R.O. I.

    2014-01-01

    Assessment of the natural radioactivity was conducted in three Southwestern states, Ekiti, Kogi and Kwara in Nigeria spanning over approximately a 9,000 km 2 on earmarked prospective ore deposits sites where thirty six (36) top soil samples were collected then taken to the laboratory for analysis so as to determine and deduce its radiological hazards and health implication prior to exploitation/exploration. The samples collected at 36 locations, mainly undisturbed and virgin lands could determine the annual effective dose (mSv.y -1 ) and the average absorbed dose (nGy/h) for a person living in the rural community along the axis and this was found to be approximately 0.114 mSvy -1 and 93.60±14.4 nGyh -1 respectively. Other health indices are drawn up in the tables found below.

  20. Radiological survey of the former Baker Brothers, Inc. site, 2551--2555 Harleau Place, Toledo, Ohio (BTO001)

    International Nuclear Information System (INIS)

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

    1992-03-01

    At the request of the US Department of Energy (DOE), a team from Oak Ridge National Laboratory conducted investigative radiological surveys at the REMS, Inc., and the Doug Beet Company, 2551-2555 Harleau Place, Toledo, Ohio (BTO001) in 1988. The purpose of the surveys was to determine whether the property was contaminated with radioactive residues, principally 238 U, as a result of work contracted to the Manhattan Engineer District (MED). The survey included gamma scans; directly measured alpha, beta, and gamma radiation levels; transferable contamination levels; and soil, dust, debris, and air sampling for radionuclide analyses. The survey and sampling covered accessible portions of the exterior ground surface, roof, and interiors of buildings. Results of the surveys demonstrated four general areas having radionuclide concentrations in excess of the DOE Formerly Utilized Sites Remedial Action Program criteria for 238 U outdoors and as surface contamination on shelves in one building

  1. An aerial radiological survey of the Double Track Site and surrounding area, Central Nevada. Date of survey: December 1993

    International Nuclear Information System (INIS)

    1995-08-01

    An aerial radiological survey of the Double Track Site was conducted in December 1993. An interim report described survey procedures and presented terrestrial exposure rate and wide-area-averaged plutonium isopleth plots. This letter report presents additional plutonium plots and some rule-of-thumb calculations which should help the reader to properly interpret the data presented. Attached to this report are three isopleth plots produced from the Double Track data. No one processing method provides all the answers regarding a particular surveyed area. Where peak vales are most important, a figure created from the original unsmoothed data is the presentation of choice. A figure from smoothed data is superior for the detection of areas of widespread low-level contamination. A figure , also smoothed data, satisfied a particular early mission goal but is not as useful for cleanup operations as the other two. This last figure is presented for historical completeness only

  2. 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.

  3. Environmental radioactivity and mitigation of radiological impact at legacy uranium sites in Portugal

    International Nuclear Information System (INIS)

    Carvalho, F.

    2014-01-01

    Uranium legacy sites in the country contain large amounts of milling tailings, mining waste, old infrastructures and acid mine drainage with high radioactivity concentrations. Radioactivity surveillance of these sites has been maintained for many years and institutional control kept beyond cessation of Portuguese uranium mining in 2001. A research programme (2003-2006) requested by the government to assess environmental contamination and public health risks in these regions advised implementing environmental remediation measures. A national programme was approved for remediation of abandoned mine sites, including radioactive and non-radioactive mines, that started in 2005 and since has completed significant remediation works in several old uranium mines. One amongst these sites, the Urgeiriça mine and milling site, was re-engineered, tailings were covered, the mine was closed, the area of mine and milling facilities cleaned, and an automated contaminated water treatment plant installed. Environmental radioactivity surveys carried out in this region showed reduced ambient radiation doses, lower radon concentrations in surface air, return to background radioactivity in surface air aerosols, and decrease of radionuclide concentrations in the river receiving water discharges from the mine site, resulting in a reduced radiation exposure to members of the public. Other legacy uranium mines without milling tailings, were mainly remediated for landscape engineering and the adopted solutions included, for example, preservation of non-contaminated ponds for public leisure. Although not completed yet in many sites, the remediation works implemented contributed already to a significant abatement of radiation exposure allowing for safer implementation of activities, such as agriculture and cattle grazing, in the surroundings of legacy sites. Environmental remediation and abatement of radiation exposure contributed to revitalize socio-economic activities of the region and

  4. Site environmental report for Calendar Year 1994 on radiological and nonradiological parameters

    International Nuclear Information System (INIS)

    1995-01-01

    Battelle Memorial Institute's nuclear research facilities are currently being maintained in a surveillance and maintenance (S ampersand M) mode with continual decontamination and decommissioning (D ampersand D) activities being conducted under Department of Energy (DOE) Contract W-7405-ENG-92. These activities are referred to under the Contract as the Battelle Columbus Laboratories Decommissioning Project (BCLDP). Operations referenced in this report are performed in support of S ampersand M and D ampersand D activities. Battelle's King Avenue facility is not considered in this report to the extent that the West Jefferson facility is. The source term at the King Avenue site is a small fraction of the source term at the West Jefferson site. Off site levels of radionuclides that could be attributed to the west Jefferson and King Avenue nuclear operations wereindistinguishable from background levels at specific locations where air, water, and direct radiation measurements were performed. Environmental monitoring continued to demonstrate compliance by Battelle with federal, state and local regulations. Routine, nonradiological activities performed include monitoring liquid effluents and monitoring the ground water system for the West Jefferson North site. Samples of various environmental media including air, water, grass, fish, field and garden crops, sediment and soil were collected from the region surrounding the two sites and analyzed

  5. Radiological criteria for the remediation of sites for spent fuel and radioactive waste storage in the Russian Northwest.

    Science.gov (United States)

    Shandala, N K; Sneve, M K; Titov, A V; Smith, G M; Novikova, N Ya; Romanov, V V; Seregin, V A

    2008-12-01

    In the 1960s, two technical bases of the Northern Fleet were created in Northwest Russia, at Andreeva Bay in the Kola Peninsula and Gremikha village on the coast of the Barents Sea. They maintained nuclear submarines, performing receipt and storage of radioactive waste and spent nuclear fuel, and are now designated sites of temporary storage (STSs). An analysis of the radiation situation at these sites demonstrates that substantial long-term remediation work will be required after the removal of the waste and spent nuclear fuel. Regulatory guidance is under development to support this work. Having in mind modern approaches to guaranteeing radiation safety, the primary regulatory focus is on a justification of dose constraints for determining acceptable residual contamination which might lead to exposure to workers and the public. For these sites, four principal options for remediation have been considered-renovation, conversion, conservation and liquidation. This paper describes a system of recommended dose constraints and derived control levels formulated for each option. The unconditional guarantee of long-term radioecological protection provides the basis for criteria development. Non-exceedance of these dose constraints and control levels implies compliance with radiological protection objectives related to the residual contamination. Dose reduction below proposed dose constraint values must also be carried out according to the optimisation principle. The developed criteria relate to the condition of the facilities and the STS areas after the termination of remediation activities. The proposed criteria for renovation, conversion, conservation and liquidation are entirely within the dose limits adopted in Russia for the management of man-made radiation sources, and are consistent with ICRP recommendations and national practice in other countries. The proposed criteria for STS remediation and new industrial (non-radiation-hazardous) facilities and buildings on

  6. Data Quality Objectives Supporting Radiological Air Emissions Monitoring for the Marine Sciences Laboratory, Sequim Site

    Energy Technology Data Exchange (ETDEWEB)

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

    2012-12-27

    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. The intent of this report is to determine the necessary steps required to ensure that radioactive emissions to the air from the Marine Sciences Laboratory (MSL) headquartered at the Pacific Northwest National Laboratory’s Sequim Marine Research Operations (Sequim Site) on Washington State’s Olympic Peninsula are managed in accordance with regulatory requirements and best practices. The Sequim Site was transitioned in October 2012 from private operation under Battelle Memorial Institute to an exclusive use contract with the U.S. Department of Energy, Office of Science, Pacific Northwest Site Office.

  7. Reconnaissance radiological characterization for the White Point Nike Missile Site, San Pedro, California

    International Nuclear Information System (INIS)

    Espegren, M.L.; Jensen, M.K.; Pierce, G.A.; Smith, S.M.

    1993-01-01

    This report is the result of field work performed at the former White Point Nike Missile Site, San Pedro, California. The Hazardous Waste Remedial Actions Program tasked the Oak Ridge National Laboratory Pollutant Assessments Group in Grand Junction, Colo., with this project. The objective was to determine whether or not radioisotopes possibly associated with past Department of Defense (DOD) operations were present and within accepted background levels. The radiation survey was accomplished by performing three independent radiation surveys, both outdoors and indoors, and random soil sampling. Initially, the site was land surveyed to develop a grid block system. A background radiation investigation was performed out in the San Pedro area

  8. Radiological bioconcentration factors for aquatic, terrestrial, and wetland ecosystems at the Savannah River site

    International Nuclear Information System (INIS)

    Friday, G.P.; Cummins, C.L.; Schwartzman, A.L.

    1996-01-01

    Since the early 1950s, the Savannah River Site (SRS) released over 50 radionuclides into the environment while producing nuclear defense materials. These releases directly exposed aquatic and terrestrial biota to ionizing radiation from surface water, soil, and sediment, and also indirectly by the ingestion of items in the food chain. As part of new missions to develop waste management strategies and identify cost-effective environmental restoration options, knowledge concerning the uptake and distribution of these radionuclides is essential. This report compiles and summarizes site-specific bioconcentration factors for selected radionuclides released at SRS

  9. Radiological bioconcentration factors for aquatic, terrestrial, and wetland ecosystems at the Savannah River site

    Energy Technology Data Exchange (ETDEWEB)

    Friday, G.P.; Cummins, C.L.; Schwartzman, A.L.

    1996-12-31

    Since the early 1950s, the Savannah River Site (SRS) released over 50 radionuclides into the environment while producing nuclear defense materials. These releases directly exposed aquatic and terrestrial biota to ionizing radiation from surface water, soil, and sediment, and also indirectly by the ingestion of items in the food chain. As part of new missions to develop waste management strategies and identify cost-effective environmental restoration options, knowledge concerning the uptake and distribution of these radionuclides is essential. This report compiles and summarizes site-specific bioconcentration factors for selected radionuclides released at SRS.

  10. CNN's evaluation of the radiological monitoring special programs at the sites of nuclear installations

    International Nuclear Information System (INIS)

    Lareyne, O.; Marugan Tovar, I.; Martinez Moreno, M.; Sanz Alduan, M. T.

    2011-01-01

    In 2008, occurred in the Spanish plants various events related to the existence on the sites of the Spanish nuclear facilities or areas dotted with radioactive contamination outside the buildings, events that were reported to the Nuclear Safety Council (CSN) in accordance with the provisions of the regulation, as a result of the analysis of those events, the CSN issued in July 2008, a complementary technique INSTRUCTIONAL requiring the implementation of environmental monitoring programs in outdoor areas within sites nuclear tacilities. First, the CSN nuclear facilities referred to the programs and methodologies intended to perform such monitoring, and, in late 2009, reports of program results.

  11. Plutonium production story at the Hanford site: processes and facilities history

    Energy Technology Data Exchange (ETDEWEB)

    Gerber, M.S., Westinghouse Hanford

    1996-06-20

    This document tells the history of the actual plutonium production process at the Hanford Site. It contains five major sections: Fuel Fabrication Processes, Irradiation of Nuclear Fuel, Spent Fuel Handling, Radiochemical Reprocessing of Irradiated Fuel, and Plutonium Finishing Operations. Within each section the story of the earliest operations is told, along with changes over time until the end of operations. Chemical and physical processes are described, along with the facilities where these processes were carried out. This document is a processes and facilities history. It does not deal with the waste products of plutonium production.

  12. BCLDP site environmental report for calendar year 1997 on radiological and nonradiological parameters

    International Nuclear Information System (INIS)

    Fry, J.

    1998-01-01

    Battelle Memorial Institute currently maintains its retired nuclear research facilities in a surveillance and maintenance (S and M) mode and continues decontamination and decommissioning (D and D) activities. The activities are referred to as the Battelle Columbus Laboratories Decommissioning Project (BCLDP). Operations reference in this report are performed in support of S and M and D and D activities. The majority of this report is devoted to discussion of the West Jefferson facility, because the source term at this facility is larger than the source term at Battelle's King Avenue site. The contamination found at the King Avenue site consists of small amounts of residual radioactive material in solid form, which has become embedded or captured in nearby surfaces such as walls, floors, ceilings, drains, laboratory equipment, and soils. By the end of calendar year (CY) 1997, most remediation activities were completed at the King Avenue site. The contamination found at the West Jefferson site is the result of research and development activities with irradiated materials. During CY 1997, multiple tests at the West Jefferson Nuclear Sciences Area found no isotopes present above the minimum detectable activity (MDA) for air releases or for liquid discharges to Big Darby Creek. Data obtained from downstream sampling locations were statistically indistinguishable from background levels

  13. Final report on the radiological surveys of designated DX firing sites at Los Alamos National Laboratory

    International Nuclear Information System (INIS)

    1996-01-01

    CHEMRAD was contracted by Los Alamos National Laboratory to perform USRADS reg-sign (UltraSonic Ranging And Data System) radiation scanning surveys at designated DX Sites at the Los Alamos National Laboratory. The primary purpose of these scanning surveys was to identify the presence of Depleted Uranium (D-38) resulting from activities at the DX Firing Sites. This effort was conducted to update the most recent surveys of these areas. This current effort was initiated with site orientation on August 12, 1996. Surveys were completed in the field on September 4, 1996. This Executive Summary briefly presents the major findings of this work. The detail survey results are presented in the balance of this report and are organized by Technical Area and Site number in section 2. This organization is not in chronological order. USRADS and the related survey methods are described in section 3. Quality Control issues are addressed in section 4. Surveys were conducted with an array of radiation detectors either mounted on a backpack frame for man-carried use (Manual mode) or on a tricycle cart (RadCart mode). The array included radiation detectors for gamma and beta surface near surface contamination as well as dose rate at 1 meter above grade. The radiation detectors were interfaced directly to an USRADS 2100 Data Pack

  14. 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.)

  15. Facilities and medical care for on-site nuclear power plant radiological emergencies

    International Nuclear Information System (INIS)

    Anon.

    1979-01-01

    The operation of a nuclear power plant introduces risks of injury or accidents that could also result in the exposure of personnel to radiation or radioactive materials. It is important in such an event to have adequate first aid and medical facilities, supplies, equipment, transportation capabilities and trained personnel available to provide necessary care. This standard provides guidance for first aid during an emergency and for initial medical care of those overexposed to penetrating radiation or contaminated with radioactive material or radionuclides. Recommendations cover facilities, supplies, equipment and the extent of care on-site, where first aid and initial care may be provided, and off-site at a local hospital, where further medical and surgical care may be provided. Additional recommendations are also provided for the transportation of patients and the training of personnel. A brief discussion of specialized care is provided in an appendix

  16. Nuclear event time histories and computed site transfer functions for locations in the Los Angeles region

    Science.gov (United States)

    Rogers, A.M.; Covington, P.A.; Park, R.B.; Borcherdt, R.D.; Perkins, D.M.

    1980-01-01

    This report presents a collection of Nevada Test Site (NTS) nuclear explosion recordings obtained at sites in the greater Los Angeles, Calif., region. The report includes ground velocity time histories, as well as, derived site transfer functions. These data have been collected as part of a study to evaluate the validity of using low-level ground motions to predict the frequency-dependent response of a site during an earthquake. For this study 19 nuclear events were recorded at 98 separate locations. Some of these sites have recorded more than one of the nuclear explosions, and, consequently, there are a total of 159, three-component station records. The location of all the recording sites are shown in figures 1–5, the station coordinates and abbreviations are given in table 1. The station addresses are listed in table 2, and the nuclear explosions that were recorded are listed in table 3. The recording sites were chosen on the basis of three criteria: (1) that the underlying geological conditions were representative of conditions over significant areas of the region, (2) that the site was the location of a strong-motion recording of the 1971 San Fernando earthquake, or (3) that more complete geographical coverage was required in that location.

  17. 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

  18. Radiological risk assessment for Al-Twuaitha nuclear site in Iraq

    Energy Technology Data Exchange (ETDEWEB)

    Al Obaidy, Abdul Hameed M.J. [Environmental Research Center, University of Technology, Baghdad (Iraq); Mohammed, Bashair A.R. [Department of Physics, College of Science, University of Baghdad, Baghdad (Iraq); Al Sharaa, Hisham M.J. [Geomatic Engineering Division, University of Technology, Baghdad (Iraq)

    2013-07-01

    In this paper, the contamination level of U, 137Cs, 60Co, 40K and 90Sr from different soil samples of the destroyed nuclear reactor at Al-Tuwaitha site south of Baghdad investigated and four contaminated spots identified. The obtained values of the 40K in soil samples are within normal concentration values and close to the environmental levels. The skewness coefficient for the U series,137Cs and 60Co distribution indicates asymmetric distribution tailing slightly towards higher concentration. However, the activity of U series, 137Cs, 60Co and 90Sr in the soil samples exhibit higher variability and above the regulated environmental levels.

  19. Supplementary radiological measurements at the Maxey Flats radioactive waste burial site, 1976--1977

    International Nuclear Information System (INIS)

    Blanchard, R.L.; Montgomery, D.M.; Kolde, H.E.; Gels, G.L.

    1978-09-01

    Evaporator effluents were investigated further to better define quantities of radionuclides discharged to the atmosphere and improve decontamination factors assigned to the principal radionuclides observed in the evaporator feed: 3 H, 14 C, 60 Co, 137 Cs, 238 Pu, and 239 Pu. On-site measurements included soil sample profiles taken to a maximum depth of 3.5 m from the trench area and from within the main washes east and south of the site. These measurements provided additional information on the near-surface lateral movement of radioactivity. Radiochemical analysis of a test-well sample showed that all measurable radioactivity was associated with the sediment in the well and the highest specific radioactivity was associated with the smaller particles (< 5 μm). Milk and vegetables were again sampled from a number of nearby farms. As previously reported, tritium was the only radionuclide measured in these foods above ambient levels, although concentrations were less than in similar samples collected during the earlier study. 4 figures, 17 tables

  20. 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)

  1. Results of the indoor radiological survey at the W.R. Grace Co., Curtis Bay site, Baltimore, Maryland

    International Nuclear Information System (INIS)

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

    1989-07-01

    The W.R. Grace Company, Davison Chemical Division, conducted developmental research and extraction of thorium from monazite ore at its Curtis Bay facility in Baltimore, Maryland, during the 1950s under contract to the Atomic Energy Commission (AEC). Only one of the numerous buildings on the site was used for these operations. A 1979 aerial survey of the site for the Department of Energy (DOE) indicated that a comprehensive ground survey was required to determine whether or not any contamination remained from the AEC activities in that building. A radiological scoping survey performed later that year for DOE by a team from the Measurement Applications and Development Group of the Health and Safety Research Division, Oak Ridge National Laboratory (ORNL), disclosed surface contamination (alpha) levels in excess of DOE criteria on all five levels of the building. As a result of this finding, two additional surveys were performed in 1986 by ORNL at the request of DOE to evaluate any present or potential health risk. They are detailed in this report. The results of the 1986 surveys revealed several areas having elevated levels of radiation as a result of significant quantities of thorium on some building surfaces such as floors and ceiling beams. Most areas were small spots and in locations of low occupancy; thus, the possibility for significant exposure to workers was judged to be low. To confirm this evaluation, annual radiation exposure estimates for workers frequenting the few, larger contaminated areas on the site were derived using ORNL survey data and occupancy factors provided by the W.R. Grace Company. Estimates ranged from 27 to 41 mrem/yr or a maximum of 41% of the basic dose limit of 100 mrem/yr for members of the general public. 2 refs., 14 figs., 8 tabs

  2. Feedback on the radiological management of a urban site contaminated with tritium

    Energy Technology Data Exchange (ETDEWEB)

    Leprieur, F.; Pierrard, O. [Institut de radioportection et de surete nucleaire - IRSN (France)

    2014-07-01

    Introduction: In November 2010, the IRSN is reached on a rare case of environmental tritium contamination on a site located in an urban area near Paris (Saint-Maur-des-Fosses - dpt 94). This contamination resulted from the presence in an enterprise's premises of an experimental device containing molecular sieve from the Valduc nuclear site, wrongly considered as un-used. First actions: IRSN has quickly performed an initial characterization of tritium contamination in the premises of the company and its close environment. The first results showed the existence of a strong local contamination (tritium activity> 150 000 Bq/m{sup 3} in air) and a important labeling in samples collected in the close vicinity of the company premises (between 1000 and 10000 Bq/kg f.w. in plants, between 500 and 1500 Bq/L in water). These results led IRSN to conduct multiple investigations: - tritium measurements on samples of water, air and plants collected in the area close to the building to know the importance and extent of environmental marking and follow its evolution over time. In this aim, 450 measurements were made between 2010 and 2013; - measurements of tritium in the urine of residents living near the contaminated building: the results showed traces of tritium for some of them but the assessments conducted by the IRSN from these results led to extremely low dosimetry estimates without consequences for the health of these people; - dosimetric evaluations of tritium exposure of employees and visitors of the company contaminated. Informing the public and stakeholders In November 2010, IRSN has collaborated with the mayor to facilitate early interventions in urban areas and in particular to facilitate contacts for access to private property. In this perspective, the IRSN participated in public meetings to explain the cause of this accident and the results of tritium measurements to residents. IRSN also published regularly on its web site briefing notes reflecting the results

  3. Radiological survey of sites around two cement producing factories: WAPCO and PURECHEM, Ewekoro, Southwestern Nigeria

    International Nuclear Information System (INIS)

    Adewole, O.O.; Egunjobi, K. A.

    2011-01-01

    Soil samples were collected around WAPCO at Ewekoro and PURECHEM at Onigbedu, which are both cement producing factories in Ogun State, Nigeria. The natural radioactivity concentrations are the mean absorbed doses of 40 K, 238 U and 232 Th at various selected locations were determined. The mean radionuclide concentration of 40 K, 238 U and 232 Th were 141.6 21.5, 27.5 9.7 and 31.3 11.1 Bq/I for WAPCO factory at selected sites. Also these values were 179.5 28.3, 21.9 7.6 and 31.2 11.7 Bq/I respectively in the same order for PURECHEM factory at selected locations. The survey revealed that the radiation doses due to natural radio nuclides in the environment under investigation are very low and insignificant to cause any serious health problems to the people living in the area.

  4. Geochemical and radiological characterization of soils from former radium processing sites.

    Science.gov (United States)

    Landa, E R

    1984-02-01

    Soil samples were collected from former radium processing sites in Denver, CO, and East Orange, NJ. Particle-size separations and radiochemical analyses of selected samples showed that while the greatest contents of both 226Ra and U were generally found in the finest (less than 45 micron) fraction, the pattern was not always of progressive increase in radionuclide content with decreasing particle size. Leaching tests on these samples showed a large portion of the 226Ra and U to be soluble in dilute hydrochloric acid. Radon-emanation coefficients measured for bulk samples of contaminated soil were about 20%. Recovery of residual uranium and vanadium, as an adjunct to any remedial action program, appears unlikely due to economic considerations.

  5. Results of the radiological survey at the Jessop Steel Company Site, 500 Green Street, Washington, Pennsylvania (JSP001)

    International Nuclear Information System (INIS)

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

    1991-04-01

    At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducted investigative radiological surveys at the Jessop Steel company, 500 Green Street, Washington, Pennsylvania (JSP001) in 1989. The purpose of the surveys was to determine whether the property was contaminated with radioactive residues, principally 238 U, as a result of work contracted to the Atomic Energy Commission. The survey included gamma scans; direct and transferable measurements of alpha and beta-gamma radiation levels; and soil dust, debris, grinding wheel, and air sampling for radionuclide analyses. The survey and sampling covered portions of the exterior ground surface, the roof and gutter section above the saw shop and rolling mill area of building D, and the interiors of buildings A, B, C and D. Results of the survey demonstrated no radionuclide concentrations in excess of the DOE Formerly Utilized Sites Remedial Action Program guidelines for radium, thorium, and uranium. The radionuclide distributions were not significantly different from typical background levels in the Pennsylvania are. 7 refs., 11 figs., 4 tabs

  6. Results of the radiological survey at the former Associate Aircraft Tool and Manufacturing Company site, Fairfield, Ohio (FOH001)

    International Nuclear Information System (INIS)

    Murray, M.E.; Carrier, R.F.; Mathis, R.A.

    1993-03-01

    At the request of the US Department of Energy (DOE), a team from oak Ridge National Laboratory conducted a radiological survey of the former Associate Aircraft Tool and Manufacturing Company facility, Fairfield, Ohio. The survey was performed in July and September 1992. The purpose of the survey was to determine if the facility had become contaminated with residuals containing radioactive materials during the work performed under government contract from February to September, 1956. The survey included gamma scanning over a circumscribed area around and outside of the building, and gamma scanning over most accessible indoor floor surfaces as well as the collection of soil and other samples for radionuclide analyses. Roof trusses were beta-gamma scanned in locations where floor contamination was found. Results of the survey demonstrated radionuclide concentrations in indoor and outdoor samples, and radiation measurements over floor and overhead surfaces, in excess of the DOE Formerly Utilized Sites Remedial Action Program guidelines. Elevated uranium concentrations outdoors were limited to several small, isolated spots. Radiation measurements exceeded guidelines indoors over numerous spots and areas inside the building, mainly in the areas that had been used in the early government work

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

    International Nuclear Information System (INIS)

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

    1993-05-01

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

  8. Results of the radiological survey at the former Alba Craft Laboratory site properties, Oxford, Ohio (OXO001)

    International Nuclear Information System (INIS)

    Murray, M.E.; Brown, K.S.; Mathis, R.A.

    1993-03-01

    At the request of the US Department of Energy (DOE), a team from Oak Ridge National Laboratory conducted a radiological survey at the former Alba Craft Laboratory Site Properties, Oxford, Ohio. The survey was performed in July and September of 1992. The purpose of the survey was to determine whether the property was contaminated with radioactive residues, primarily 238 U, from uranium machining operations conducted for National Lead of Ohio, a prime Atomic Energy Commission contractor. The survey included scan measurement of direct radiation levels inside and outside the former laboratory, outdoors on eight properties adjoining the former laboratory, and the city right-of-way adjacent to the surveyed properties. Radionuclide concentrations were determined in outdoor surface and subsurface soil samples taken from each property and the exterior of the laboratory. Fixed surface residual radioactivity was measured inside the laboratory and outside the building. Air samples were collected, direct exposure was measured, and samples were collected to measure transferable radioactivity inside the building. Results of the survey indicate areas where surface and soil contamination level s are above the DOE guidelines for uncontrolled areas

  9. An aerial radiological survey of the Savannah River Site and surrounding area, Aiken, South Carolina, October--November 1991

    International Nuclear Information System (INIS)

    Vojtech, R.J.

    1993-12-01

    An aerial radiological survey was conducted during the period of October 14 to November 23, 1991, over an area surrounding the United States Department of Energy's Savannah River Site (SRS). The area is situated 15 kilometers south of Aiken, South Carolina. The purpose of the survey was to measure and document the gamma ray environment of the SRS and surrounding areas. Contour maps showing gamma radiation exposure rates at 1 meter above ground level were constructed from the aerial data and overlaid on a United States Geological Survey map of the area. The exposure rates measured within the survey region are generally uniform and typical of natural background. The reported exposure rate values include an estimated cosmic ray contribution. Enhanced exposure rates not attributable to natural background were measured over several areas within the survey region. The manmade radionuclides detected in these areas, cesium-137, cobalt-60, and protactinium-234m, were produced by the reactor operations and material processing conducted at the SRS. The radiation levels produced by these nuclides are consistent with those levels measured during previous SRS aerial surveys. Radionuclide assays of soil samples and pressurized ion chamber measurements were obtained at four locations within the survey boundaries

  10. DEPLOYMENT OF INNOVATIVE CHARACTERIZATION TECHNOLOGIES AND IMPLEMENTATION OF THE MARSSIM PROCESS AT RADIOLOGICALLY CONTAMINATED SITES.

    Energy Technology Data Exchange (ETDEWEB)

    KALB,P.D.; MILIAN,L.; LUCKETT,L.; WATTERS,D.; MILLER,K.M.; GOGOLAK,C.

    2001-05-01

    The success of this Accelerated Site Technology Deployment (ASTD) project is measured on several levels. First, the deployment of this innovative approach using in situ characterization, portable field laboratory measurements, and implementation of MARSSIM was successfully established for all three phases of D and D characterization, i.e., pre-job scoping, on-going disposition of waste, and final status surveys upon completion of the activity. Unlike traditional D and D projects, since the Brookhaven Graphite Research Reactor Decommissioning Project (BGRR-DP) is operating on an accelerated schedule, much of the work is being carried out simultaneously. Rather than complete a full characterization of the facility before D and D work begins, specific removal actions require characterization as the activity progresses. Thus, the need for rapid and cost-effective techniques for characterization is heightened. Secondly, since the approach used for this ASTD project was not thoroughly proven prior to deployment, a large effort was devoted to demonstrating technical comparability to project managers, regulators and stakeholders. During the initial phases, large numbers of replicate samples were taken and analyzed by conventional baseline techniques to ensure that BGRR-DP quality assurance standards were met. ASTD project staff prepared comparisons of data gathered using ISOCS and BetaScint with traditional laboratory methods and presented this information to BGRR-DP staff and regulators from EPA Region II, NYS Department of Environmental Conservation, and the Suffolk County Board of Health. As the results of comparability evaluations became available, approval for these methods was received and the techniques associated with in situ characterization, portable field laboratory measurements, and implementation of MARSSIM were gradually integrated into BGRR-DP procedures.

  11. DEPLOYMENT OF INNOVATIVE CHARACTERIZATION TECHNOLOGIES AND IMPLEMENTATION OF THE MARSSIM PROCESS AT RADIOLOGICALLY CONTAMINATED SITES

    International Nuclear Information System (INIS)

    KALB, P.D.; MILIAN, L.; LUCKETT, L.; WATTERS, D.; MILLER, K.M.; GOGOLAK, C.

    2001-01-01

    The success of this Accelerated Site Technology Deployment (ASTD) project is measured on several levels. First, the deployment of this innovative approach using in situ characterization, portable field laboratory measurements, and implementation of MARSSIM was successfully established for all three phases of D and D characterization, i.e., pre-job scoping, on-going disposition of waste, and final status surveys upon completion of the activity. Unlike traditional D and D projects, since the Brookhaven Graphite Research Reactor Decommissioning Project (BGRR-DP) is operating on an accelerated schedule, much of the work is being carried out simultaneously. Rather than complete a full characterization of the facility before D and D work begins, specific removal actions require characterization as the activity progresses. Thus, the need for rapid and cost-effective techniques for characterization is heightened. Secondly, since the approach used for this ASTD project was not thoroughly proven prior to deployment, a large effort was devoted to demonstrating technical comparability to project managers, regulators and stakeholders. During the initial phases, large numbers of replicate samples were taken and analyzed by conventional baseline techniques to ensure that BGRR-DP quality assurance standards were met. ASTD project staff prepared comparisons of data gathered using ISOCS and BetaScint with traditional laboratory methods and presented this information to BGRR-DP staff and regulators from EPA Region II, NYS Department of Environmental Conservation, and the Suffolk County Board of Health. As the results of comparability evaluations became available, approval for these methods was received and the techniques associated with in situ characterization, portable field laboratory measurements, and implementation of MARSSIM were gradually integrated into BGRR-DP procedures

  12. An aerial radiological survey of Par Pond and associated drainage pathways of the Savannah River Site, Aiken, South Carolina

    International Nuclear Information System (INIS)

    1992-12-01

    The first of a three-phase effort to radiologically monitor the lowering of Par Pond and associated drainage pathways was conducted over three areas of the Savannah River Site (SRS). The areas surveyed during this first phase included Par Pond, the Savannah River swamp from Steel Creek to Little Hell Landing, and Lower Three Runs Creek from the mouth of Lower Three Runs to the Highway 301 Bridge. The first phase was conducted to coincide with the lowering of the water level of Par Pond to an elevation of 190 feet above sea level. Additional surveys were conducted when the water level was at an elevation of 180 feet and prior to refill. The first survey began August 19, 1991, and was completed September 11, 1991. The second survey was conducted in October/November, 1991, during the SRS site-wide survey, and the third survey was conducted in August/September, 1992. Only the Par Pond area itself was surveyed during the third and final phase. The radiation detected over the Creek Plantation portion of the Savannah River swamp and Lower Three Runs areas during the August 1991 survey was consistent with the spatial distribution, quantity, and kinds of radionuclides detected during the 1983 and 1986 surveys. No migration of man-made gamma emitting materials was detected when compared to the prior surveys. The major differences occurred along the Par Pond shoreline where lowered water levels exposed the contaminated pond bed. The activity in the pond bed was attenuated by the water cover prior to the start of the lowering of Par Pond in June 1991. The data collected during each survey were processed in the field and were presented to SRS. A comparison report is being generated after the completion of each survey. A final report will be generated for the three surveys and will include a quantitative comparison of the three surveys in the Par Pond area only

  13. 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

  14. 137Cs Radiological risk estimation of NSD facility at Karawang site by using RESRAD onsite application: effect of cover thickness

    Science.gov (United States)

    Setiawan, B.; Prihastuti, S.; Moersidik, S. S.

    2018-02-01

    The operational of near surface disposal facility during waste packages loading activity into the facility, or in a monitoring activity around disposal facility at Karawang area is predicted to give a radiological risk to radiation workers. The thickness of disposal facility cover system affected the number of radiological risk of workers. Due to this reason, a radiological risk estimation needs to be considered. RESRAD onsite code is applied for this purpose by analyse the individual accepted dose and radiological risk data of radiation workers. The obtained results and then are compared with radiation protection reference in accordance with national regulation. In this case, the data from the experimental result of Karawang clay as host of disposal facility such as Kd value of 137Cs was used. Results showed that the thickness of the cover layer of disposal facility affected to the radiological risk which accepted by workers in a near surface disposal facility.

  15. Geological history and its impact on the rock mechanics properties of the Olkiluoto site

    International Nuclear Information System (INIS)

    Hudson, J.A.; Cosgrove, J.W.

    2006-03-01

    This report is one of three documents with background information for supporting the development of Posiva's future rock mechanics programme. The other two reports are a summary of all the rock mechanics work completed for Posiva before 2005 (Posiva Working Report) and a technical audit of the numerical modeling work that has been conducted previously for Posiva (REC Memo). The purpose of this report is to establish the extent to which the mechanical properties of the rocks at the Olkiluoto site can be estimated from a knowledge of the geological environment. The main information required for rock mechanics studies of the site is a knowledge of the prevailing stress state, the properties of the intact rock, and the properties of the fractures at all scales - from sizes that could form blocks in the tunnel roof up to the major brittle deformation zones that could be influence the location of the ONKALO and the subsequent repository. Thus, the summary of the geological history in Chapter 2 concentrates on these features and we summarise the ductile and brittle deformational tectonic history of the site, with emphasis on the inferred stress states causing the deformations. Then, in Chapter 3, the rock stress, the hierarchy of brittle fracturing, the fracture properties and the mechanical properties of the rock mass are considered in the light of the geological environment. These features provide the baseline knowledge of the host rock from which the logic of the future rock mechanics programme can be developed, based on: the bedrock model; the site investigation results; the requirements for generating the site descriptive model; the prediction-outcome ONKALO studies; and numerically modeling the effects of excavation for design and safety analysis. The implications of this study for the future rock mechanics work are outlined in Chapter 4 with emphasis on the key features for modeling. (orig.)

  16. 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

  17. Pulling History from the Waste Stream: Identification and Collection of Manhattan Project and Cold War Era Artifacts on the Hanford Site

    International Nuclear Information System (INIS)

    Marceau, Thomas E.; Watson, Thomas L.

    2013-01-01

    One man's trash is another man's treasure. Not everything called 'waste' is meant for the refuse pile. The mission of the Curation Program is at direct odds with the remediation objectives of the Hanford Site. While others are busily tearing down and burying the Site's physical structures and their associated contents, the Curation Program seeks to preserve the tangible elements of the Site's history from these structures for future generations before they flow into the waste stream. Under the provisions of a Programmatic Agreement, Cultural Resources staff initiated a project to identify and collect artifacts and archives that have historic or interpretive value in documenting the role of the Hanford Site throughout the Manhattan Project and Cold War Era. The genesis of Hanford's modern day Curation Program, its evolution over nearly two decades, issues encountered, and lessons learned along the way -- particularly the importance of upper management advocacy, when and how identification efforts should be accomplished, the challenges of working within a radiological setting, and the importance of first hand information -- are presented

  18. Pulling History from the Waste Stream: Identification and Collection of Manhattan Project and Cold War Era Artifacts on the Hanford Site

    Energy Technology Data Exchange (ETDEWEB)

    Marceau, Thomas E.; Watson, Thomas L.

    2013-11-13

    One man's trash is another man's treasure. Not everything called "waste" is meant for the refuse pile. The mission of the Curation Program is at direct odds with the remediation objectives of the Hanford Site. While others are busily tearing down and burying the Site's physical structures and their associated contents, the Curation Program seeks to preserve the tangible elements of the Site's history from these structures for future generations before they flow into the waste stream. Under the provisions of a Programmatic Agreement, Cultural Resources staff initiated a project to identify and collect artifacts and archives that have historic or interpretive value in documenting the role of the Hanford Site throughout the Manhattan Project and Cold War Era. The genesis of Hanford's modern day Curation Program, its evolution over nearly two decades, issues encountered, and lessons learned along the way -- particularly the importance of upper management advocacy, when and how identification efforts should be accomplished, the challenges of working within a radiological setting, and the importance of first hand information -- are presented.

  19. Long term radiological effects on plants and animals of a deep geological repository. SR-Site Biosphere

    Energy Technology Data Exchange (ETDEWEB)

    Torudd, Jesper [Facilia AB (Sweden)

    2010-12-15

    This study is part of the safety assessment of the planned repository for spent nuclear fuel in Forsmark, called SR-Site. The purpose of the report is to clarify whether the environment is protected against harmful effects of ionizing radiation after a possible future release of radioactive matter from the planned repository. According to the Swedish Radiation Safety Authority (SSM), biological diversity and sustainable use of biological resources must be protected, and the evaluation should pay special attention to threatened and endemic species as well as economically and culturally valuable species. The report shows the approach to, and results of, calculations of dose rates to organisms other than man. The calculations are based on modelled activity concentrations from a potential future radioactive release, provided by a separate modelling project. Calculations were performed with the ERICA Tool, a software programme developed by an EU research project. In the ERICA Tool, dose rates for site specific organisms (i.e., occurring at the site) were calculated using input data such as size dimensions and masses of organisms, ecosystems and habitats, concentration ratios for the studied elements (i.e. the ratio of accumulated element concentration in the body compared with the element concentration in the surrounding environment) and maximum activity concentrations of radionuclides from the modelled future release. The results are provided in terms of final dose rates for each studied organism. In accordance with rationales of the International Commission of Radiological Protection (ICRP) and the ERICA project, Representative (site-specific) Organisms from the planned site of the future repository were studied. Ideally, the organisms selected would meet the criteria defined by both SSM (species worth protecting) and by ICRP and ERICA (so-called Reference Organisms). Since activity concentrations for a number of radionuclides were missing for some of the studied

  20. Long term radiological effects on plants and animals of a deep geological repository. SR-Site Biosphere

    Energy Technology Data Exchange (ETDEWEB)

    Torudd, Jesper (Facilia AB (Sweden))

    2010-12-15

    This study is part of the safety assessment of the planned repository for spent nuclear fuel in Forsmark, called SR-Site. The purpose of the report is to clarify whether the environment is protected against harmful effects of ionizing radiation after a possible future release of radioactive matter from the planned repository. According to the Swedish Radiation Safety Authority (SSM), biological diversity and sustainable use of biological resources must be protected, and the evaluation should pay special attention to threatened and endemic species as well as economically and culturally valuable species. The report shows the approach to, and results of, calculations of dose rates to organisms other than man. The calculations are based on modelled activity concentrations from a potential future radioactive release, provided by a separate modelling project. Calculations were performed with the ERICA Tool, a software programme developed by an EU research project. In the ERICA Tool, dose rates for site specific organisms (i.e., occurring at the site) were calculated using input data such as size dimensions and masses of organisms, ecosystems and habitats, concentration ratios for the studied elements (i.e. the ratio of accumulated element concentration in the body compared with the element concentration in the surrounding environment) and maximum activity concentrations of radionuclides from the modelled future release. The results are provided in terms of final dose rates for each studied organism. In accordance with rationales of the International Commission of Radiological Protection (ICRP) and the ERICA project, Representative (site-specific) Organisms from the planned site of the future repository were studied. Ideally, the organisms selected would meet the criteria defined by both SSM (species worth protecting) and by ICRP and ERICA (so-called Reference Organisms). Since activity concentrations for a number of radionuclides were missing for some of the studied

  1. Long term radiological effects on plants and animals of a deep geological repository. SR-Site Biosphere

    International Nuclear Information System (INIS)

    Torudd, Jesper

    2010-12-01

    This study is part of the safety assessment of the planned repository for spent nuclear fuel in Forsmark, called SR-Site. The purpose of the report is to clarify whether the environment is protected against harmful effects of ionizing radiation after a possible future release of radioactive matter from the planned repository. According to the Swedish Radiation Safety Authority (SSM), biological diversity and sustainable use of biological resources must be protected, and the evaluation should pay special attention to threatened and endemic species as well as economically and culturally valuable species. The report shows the approach to, and results of, calculations of dose rates to organisms other than man. The calculations are based on modelled activity concentrations from a potential future radioactive release, provided by a separate modelling project. Calculations were performed with the ERICA Tool, a software programme developed by an EU research project. In the ERICA Tool, dose rates for site specific organisms (i.e., occurring at the site) were calculated using input data such as size dimensions and masses of organisms, ecosystems and habitats, concentration ratios for the studied elements (i.e. the ratio of accumulated element concentration in the body compared with the element concentration in the surrounding environment) and maximum activity concentrations of radionuclides from the modelled future release. The results are provided in terms of final dose rates for each studied organism. In accordance with rationales of the International Commission of Radiological Protection (ICRP) and the ERICA project, Representative (site-specific) Organisms from the planned site of the future repository were studied. Ideally, the organisms selected would meet the criteria defined by both SSM (species worth protecting) and by ICRP and ERICA (so-called Reference Organisms). Since activity concentrations for a number of radionuclides were missing for some of the studied

  2. Formerly utilized MED/AEC sites remedial action program: radiological survey of the Building Site 421, United States, Watertown Arsenel, Watertown, MA. Final report

    Energy Technology Data Exchange (ETDEWEB)

    None

    1980-02-01

    This report contains the results of surveys of the current radiological condition of the Building Site 421, United States Arsenal Watertown, Watertown, Massachusetts. Findings of this survey indicate there are four spots involving an area of less than 6000 cm/sup 2/ of identifiable low-level residual radioactivity on the concrete pad which is all that remains of Building Site 421. The largest spot is approximately 5000 cm/sup 2/. The other three spots are 100 cm/sup 2/ or less. The beta-gamma readings at these spots are 8.4 x 10/sup 2/ dis/min-100 cm/sup 2/, 2.2 x 10/sup 5/ dis/min-100 cm/sup 2/, 2.2 x 10/sup 5/ dis/min-100 cm/sup 2/ and 8.5 x 10/sup 4/ dis/min-100 cm/sup 2/. No alpha contamination was found at these locations. Gamma spectral analysis of a chip of contaminated concrete from one of the spots indicates that the contaminant is natural uranium. This contamination is fixed in the concrete and does not present an internal or external exposure hazard under present conditions. A hypothetical hazard analysis under a conservative set of assumed conditions indicates minimal internal hazard. The highest End Window contact reading was 0.09 mR/h. None of the other three spots indicated an elevated direct reading with the End Window Detector. Radon daughter concentrations were determined at three locations on the Building 421 pad. These were 0.00013 WL, 0.00011 WL and 0.00009 WL. According to the Surgeon General's Guidelines found in 10 CFR 712, radon daughter concentrations below 0.03 WL do not require remedial action in structures other than private dwellings and schools. Soil samples taken about the site indicate no elevated levels above the natural background levels in the soil. A gamma spectral analysis of a water sample obtained from the storm sewer line near the Building 421 pad indicates no elevated radioactivity in the sample. It was therefore felt that no contamination is present in this sewer.

  3. Formerly utilized MED/AEC sites remedial action program: radiological survey of the Building Site 421, United States, Watertown Arsenel, Watertown, MA. Final report

    International Nuclear Information System (INIS)

    1980-02-01

    This report contains the results of surveys of the current radiological condition of the Building Site 421, United States Arsenal Watertown, Watertown, Massachusetts. Findings of this survey indicate there are four spots involving an area of less than 6000 cm 2 of identifiable low-level residual radioactivity on the concrete pad which is all that remains of Building Site 421. The largest spot is approximately 5000 cm 2 . The other three spots are 100 cm 2 or less. The beta-gamma readings at these spots are 8.4 x 10 2 dis/min-100 cm 2 , 2.2 x 10 5 dis/min-100 cm 2 , 2.2 x 10 5 dis/min-100 cm 2 and 8.5 x 10 4 dis/min-100 cm 2 . No alpha contamination was found at these locations. Gamma spectral analysis of a chip of contaminated concrete from one of the spots indicates that the contaminant is natural uranium. This contamination is fixed in the concrete and does not present an internal or external exposure hazard under present conditions. A hypothetical hazard analysis under a conservative set of assumed conditions indicates minimal internal hazard. The highest End Window contact reading was 0.09 mR/h. None of the other three spots indicated an elevated direct reading with the End Window Detector. Radon daughter concentrations were determined at three locations on the Building 421 pad. These were 0.00013 WL, 0.00011 WL and 0.00009 WL. According to the Surgeon General's Guidelines found in 10 CFR 712, radon daughter concentrations below 0.03 WL do not require remedial action in structures other than private dwellings and schools. Soil samples taken about the site indicate no elevated levels above the natural background levels in the soil. A gamma spectral analysis of a water sample obtained from the storm sewer line near the Building 421 pad indicates no elevated radioactivity in the sample. It was therefore felt that no contamination is present in this sewer

  4. 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)

  5. HISTORY AND ACCOMPLISHMENTS OF THE US EPA'S SUPERFUND INNOVATIVE TECHNOLOGY EVALUATION (SITE) MONITORING AND MEASUREMENT (MMT) PROGRAM

    Science.gov (United States)

    This manuscript presents the history and evolution of the U.S. Environmental Protection Agency's (EPA) Superfund Innovative Technology Evaluation (SITE) Monitoring and Measurement Technology (MMT) Program. This includes a discussion of how the fundamental concepts of a performanc...

  6. 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

  7. 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

  8. 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 ...

  9. 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

  10. 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

  11. Radiologic findings of anthracofibrosis

    International Nuclear Information System (INIS)

    Yoon, Mi Jin; Ko, Eun Joo; Yoon, Sook Ja; Tien, Kuang Lung; Yoon, Yong Kyu; Lee, Kyung Soo; Kim, Jin Hwan

    1998-01-01

    To evaluate the CT findings of bronchial anthracofibrosis. Fourteen patients with bronchoscopically confirmed anthracofibrosis were involved in this study. CT findings (n=3D12) were retrospectively analysed; the pattern, distri-bution and extent of bronchial and parenchymal abnormalities and additional findings such as mediastinal lymphadenopathy and pleural effusion were assessed. Age, sex, and occupational and disease history were history were also reviewed. Patients were aged between 63 and 95 (mean, 71.3) years, and ten were female. Only one patient had an occupational history, but four had a history of pulmonary tuberculosis. Frequent radiologic findings were bronchial wall thickening(n=3D6), atelectasis(n=3D8), mediastinal lymphad-enopathy(n=3D7) and mass(n=3D4). Other accompanying findings were bronchial wall calcification(n=3D3), consolidation(n=3D2) and pleural effusion(n=3D2). Right upper (n=3D7) and right middle lobe(n=3D7) were the most commonly involved sites, and multifocal involvement (n=3D7) was frequent. Bronchial wall thickening, atelectasis and mediastinal lymphadenopathy were characteristic CT findings of anthracofibrosis. When such findings are noted in older or aged female patients, anthracofibrosis should be included in the differential diagnosis

  12. Radiology today

    International Nuclear Information System (INIS)

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

    1981-01-01

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

  13. Radiological consequence analysis. Report on the work package 10. Preliminary safety analysis for the site Gorleben; Radiologische Konsequenzanalyse. Bericht zum Arbeitspaket 10. Vorlaeufige Sicherheitsanalyse fuer den Standort Gorleben

    Energy Technology Data Exchange (ETDEWEB)

    Larue, Juergen; Baltes, Bruno; Fischer, Heidemarie; Frieling, Gerd; Kock, Ingo; Navarro, Martin; Seher, Holger

    2013-02-15

    Work package 10 of the preliminary safety analysis for the site Gorleben concerns the analysis of release scenarios and the radiological consequences. The report includes the description of the applied methodology, the concept for the mathematical description of scenarios, the variety of scenarios for the radiological consequence analysis with the definition of the reference scenario. The database for the calculation covers geology and hydrology, the final repository concept and the process of the final disposal system. The used models were the one-phase transport model MARINE and the two-phase transport model TOUGH2. The report summarizes the results including an evaluation of the realization of the demonstration concept with respect to solution transport, fluid transport, robustness of the modeling results and analogy discussion to other disposal variants (i.e. borehole disposal and storage of transport or storage casks).

  14. Bonegilla Heritage Park: Contesting and Co-ordinating a Public History Site

    Directory of Open Access Journals (Sweden)

    Alexandra Dellios

    2012-10-01

    Full Text Available Since the 1980s, efforts to publically commemorate the former migrant training and reception centre of Bonegilla, while intermittent, have increased. I am referring to: reunions and anniversaries, state and national heritage listings, the erection of museum displays, temporary and touring exhibitions, the on-site Heritage Park, and forms of popular culture. For the national audience, as well as several ethnic communities, Bonegilla now plays a role in the collective imagination of the post-war period and the migrant journey. Furthermore, the nature of Bonegilla’s public representation has evolved since the late 1980s. Bonegilla has become much more than a place of personal migrant memory, and its previous negative connotations in the public arena have been erased. This public evolution is linked to much wider processes in our national history. This article thus explores the contestation and co-ordination of collective memories—that is, multiple narratives of Bonegilla’s past, which, while in constant dialogue with each other, are framed and sanctioned by the limits of Australian multiculturalism and heritage discourses. While the earliest efforts to commemorate Bonegilla might be typified as ‘participatory’ and vernacular, they might now be described in reference to ‘retrospective commemoration’, in which Bonegilla’s public history is framed by state-sanctioned narratives and other attendant discursive frameworks.

  15. 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.

  16. Digital radiology

    International Nuclear Information System (INIS)

    Dallas, W.J.

    1990-01-01

    Radiology is vital to the life-saving efforts of surgeons and other physicians, but precious time can be lost generating the images and transferring them to and from the operating room. Furthermore, hospitals are straining under the task of storing and managing the deluge of diagnostic films produced every year. A 300-bed hospital generates about 1 gigabyte (8 x 10 9 bits) of picture information every day and is legally bound to hold it for three to seven years--30 years in the case of silicosis or black lung disease, illnesses that may have relevance to future lawsuits. Consequently, hospital warehouses are filling with x-ray film and written reports that are important for analysis of patient histories, for comparison between patients, and for analyzing the progress of disease. Yet only a fraction of the information's potential is being used because access is so complicated. What is more, films are easily lost, erasing valuable medical histories

  17. Solar education combining art, history, science and technology at archaeological sites in Italy

    Energy Technology Data Exchange (ETDEWEB)

    Silvi, C.; Ferro, P. [ISES (Italy); Ceccarini, T. [Educational Section - State Superintendence of Archaeological Monuments in Rome (Italy)

    2004-07-01

    ''Solar Art and Solar Technologies'' and ''Solar Energy by studying Ancient Architecture'' laboratory promoted by ISES ITALIA and the Educational Section of the State Superintendence of Archaeological Monuments in Rome involved from 2000 to 2004 roughly 1000 schoolchildren, 20 teachers and five archaeologists. For its innovative character and its special approach to solar education, the exhibition ''Solar Art and Technologies'' has been acknowledged among the 50 best projects of the ''2001 Energy Globe Award.'' The program has been continuously improved and has broadened its educational reach beyond schoolchildren. The experiences made at the archaeological sites from the energy point of view lead to new research projects and initiatives on solar energy at the archaeological sites during the excavations, while exploring historical sources, and at the involved schools. A seminar on ''Solar energy and the built environment in past civilizations'' will be held at the end of May 2004 to review historical sources and the most recent archaeological discoveries that have relation with solar architecture and technology. The seminar will also address the possible participation of historians and archaeologists in the history sessions planned at ISES 2005 (www.swc2005.org). (orig.)

  18. Investigation of Nonlinear Site Response and Seismic Compression from Case History Analysis and Laboratory Testing

    Science.gov (United States)

    Yee, Eric

    In this thesis I address a series of issues related to ground failure and ground motions during earthquakes. A major component is the evaluation of cyclic volumetric strain behavior of unsaturated soils, more commonly known as seismic compression, from advanced laboratory testing. Another major component is the application of nonlinear and equivalent linear ground response analyses to large-strain problems involving highly nonlinear dynamic soil behavior. These two components are merged in the analysis of a truly unique and crucial field case history of nonlinear site response and seismic compression. My first topic concerns dynamic soil testing for relatively small strain dynamic soil properties such as threshold strains, gammatv. Such testing is often conducted using specialized devices such as dual-specimen simple-shear, as devices configured for large strain testing produce noisy signals in the small strain range. Working with a simple shear device originally developed for large-strain testing, I extend its low-strain capabilities by characterizing noisy signals and utilizing several statistical methods to extract meaningful responses in the small strain range. I utilize linear regression of a transformed variable to estimate the cyclic shear strain from a noisy signal and the confidence interval on its amplitude. I utilize Kernel regression with the Nadaraya-Watson estimator and a Gaussian kernel to evaluate vertical strain response. A practical utilization of these techniques is illustrated by evaluating threshold shear strains for volume change with a procedure that takes into account uncertainties in the measured shear and vertical strains. My second topic concerns the seismic compression characteristics of non-plastic and low-plasticity silty sands with varying fines content (10 ≤ FC ≤ 60%). Simple shear testing was performed on various sand-fines mixtures at a range of modified Proctor relative compaction levels ( RC) and degrees-of-saturation (S

  19. Heat-flow and subsurface temperature history at the site of Saraya (eastern Senegal)

    Science.gov (United States)

    Lucazeau, F.; Rolandone, F.

    2012-08-01

    New temperature measurements from eight boreholes in the West African Craton (WAC) reveal superficial perturbations down to 100 m below the alteration zone. These perturbations are both related to a recent increase in the surface air temperature (SAT) and to the site effects caused by fluid circulations and/or the lower conduction in the alterites. The ground surface temperature (GST), inverted from the boreholes temperatures, increased slowly in the past (~0.4 °C from 1700 to 1940) and then, more importantly, in recent years (~1.5 °C from 1940 to 2010). This recent trend is consistent with the increase of the SAT recorded at two nearby meteorological stations (Tambacounda and Kedougou), and more generally in the Sahel with a coeval rainfall decrease. Site effects are superimposed to the climatic effect and interpreted by advective (circulation of fluids) or conductive (lower conductivity of laterite and of high-porosity sand) perturbations. We used a 1-D finite differences thermal model and a Monte-Carlo procedure to find the best estimates of these site perturbations: all the eight borehole temperature logs can be interpreted with the same basal heat-flow and the same surface temperature history, but with some realistic changes of thermal conductivity and/or fluid velocity. The GST trend observed in Senegal can be confirmed by two previous borehole measurements made in 1983 in other locations of West Africa, the first one in an arid zone of northern Mali and the second one in a sub-humid zone in southern Mali. Finally, the background heat-flow is low (31±2 mW m-2), which makes this part of the WAC more similar with the observations in the southern part (33±8 mW m-2) rather than with those in the northern part and in the Pan-African domains where the surface heat-flow is 15-20 mW m-2 higher.

  20. The effect of extent of site investigation on the estimation of radiological performance and its relevance to the proposed Rock Characterisation Facility at Sellafield

    International Nuclear Information System (INIS)

    Mackay, R.

    1996-01-01

    Proof of Evidence is given by an expert witness on behalf of Greenpeace Ltd as part of their submission to a Planning Inquiry in 1995 hearing the application of UK Nirex Ltd for permission to construct an underground Rock Characterisation Facility (RCF) at a site near Sellafield. The RCF is part of an investigation by Nirex into a suitable site for the disposal of radioactive waste. The evidence concerns the necessity of establishing an adequate hydrogeological model of the site in advance of the construction of the RCF in order to estimate its radiological performance. This detailed examination of Nirex's approach concludes that it is not apparent that a method for demonstrating the adequacy of the conceptual hydrogeological model has been clearly and openly stated so that it may be agreed in advance of construction with an appropriate authority. (1 figure; 1 table, 12 references). (UK)

  1. 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

  2. Results of the independent radiological verification survey at the former Associate Aircraft Tool and Manufacturing Company site, Fairfield, Ohio (FOH001)

    International Nuclear Information System (INIS)

    Rice, D.E.; Murray, M.E.; Brown, K.S.

    1996-01-01

    The former Associate Aircraft Tool and Manufacturing Company site is located at 3550 Dixie Highway, Fairfield, Ohio. Associate Aircraft Tool and Manufacturing Company produced hollow uranium slugs in a machine shop at the site in 1956. The work was performed for National Lead of Ohio in a contract with the Atomic Energy Commission to augment the capacity of the Feed Materials Production Center at Fernald in the development of nuclear energy for defense-related projects. The current occupant of the building, Force Control, operates a multipurpose machine shop. At the request of the US Department of Energy (DOE), a team from Oak Ridge National Laboratory conducted an independent radiological verification survey at the former Associate Aircraft Tool and Manufacturing Company Site, Fairfield, Ohio. The survey was performed from February to May of 1995. The purpose of the survey was to verify that radioactivity from residues of 238 U was remediated to a level below acceptable DOE guidelines levels

  3. 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

  4. Surface radiological investigations of Trench 6 and low-level waste Line Leak Site 7.4b at the Oak Ridge National Laboratory, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

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

    1991-08-01

    A surface radiological investigation of Trench 6 and low-level radioactive waste (LLW) Line Leak Site 7.4b was conducted in July and August 1989 and January 1990 by the Measurement Applications and Development Group, Oak Ridge National Laboratory. The purposes of this survey were (1) to determine the presence, nature, and extent of surface radiological contamination and (2) to recommend interim corrective action to limit human exposures to radioactivity and minimize the potential for contaminant dispersion. Highest surface gamma levels encountered during the survey (39 mR/h) were found just south of the asphalt covering LLW Line Leak Site 7.4b. Elevated surface gamma levels (measuring 28 to 560 μR/h) extended from this area to a width of 100 ft, westward 250 ft, and beyond the survey boundary. Beta-gamma levels up to 17 mrad/h measured on contact with the trunks of trees growing in the area southwest of Trench 6 suggest that three roots are reaching contamination deep within the ground. Since no gamma activity is associated with the trees or their leaves, the elevated beta levels are probably due to the uptake of residual 90 Sr originating from the documented seepage at the Trench 6/Leak Site 7.4b area. Beta activity present in the leaf litter and surface soil indicate that decaying leaves are depositing measurable contaminants on the ground surface. Recommendations for corrective actions are included. 7 refs., 20 figs., 3 tabs

  5. Cardiothoracic radiology

    International Nuclear Information System (INIS)

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

    2005-01-01

    A wealth of cardiothoracic websites exist on the internet. What follows is a list of the higher quality resources currently available which should save you time searching them out for yourself. Many of the sites listed cater for undergraduates and trainee or non-specialist radiologists, nevertheless these may also be of interest to specialists in thoracic radiology, particularly 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 (April 2005)

  6. Analysis and radiological assessment of residues containing NORM materials resulting from earlier activities including modelling of typical industrial residues. Pt. 1. Historical investigation of the radiological relevance of NORM residues and concepts for site identification

    International Nuclear Information System (INIS)

    Reichelt, Andreas; Niedermayer, Matthias; Sitte, Beate; Hamel, Peter Michael

    2007-01-01

    Natural radionuclides are part of the human environment and of the raw materials used. Technical processes may cause their accumulation in residues, and the result will be so-called NORM materials (Naturally occurring radioactive material). The amended Radiation Protection Ordinance (StrlSchV 2001) specifies how the public should be protected, but there are also residues dating back before the issuing of the StrlSchV 2001, the so-called NORM residues. The project intended to assess the risks resulting from these residues. It comprises four parts. Part 1 was for clarification of the radiological relevance of NORM residues and for the development of concepts to detect them. The criterion for their radiological relevance was their activity per mass unit and the material volume accumulated through the centuries. The former was calculated from a wide bibliographic search in the relevant literature on radiation protection, while the mass volume was obtained by a detailed historical search of the consumption of materials that may leave NORM residues. These are, in particular, residues from coal and ore mining and processing. To identify concrete sites, relevant data sources were identified, and a concept for identification of concrete NORM residues was developed on this basis. (orig.) [de

  7. 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.

  8. Preclosure radiological safety analysis for accident conditions of the potential Yucca Mountain Repository: Underground facilities; Yucca Mountain Site Characterization Project

    Energy Technology Data Exchange (ETDEWEB)

    Ma, C.W.; Sit, R.C.; Zavoshy, S.J.; Jardine, L.J. [Bechtel National, Inc., San Francisco, CA (United States); Laub, T.W. [Sandia National Labs., Albuquerque, NM (United States)

    1992-06-01

    This preliminary preclosure radiological safety analysis assesses the scenarios, probabilities, and potential radiological consequences associated with postulated accidents in the underground facility of the potential Yucca Mountain repository. The analysis follows a probabilistic-risk-assessment approach. Twenty-one event trees resulting in 129 accident scenarios are developed. Most of the scenarios have estimated annual probabilities ranging from 10{sup {minus}11}/yr to 10{sup {minus}5}/yr. The study identifies 33 scenarios that could result in offsite doses over 50 mrem and that have annual probabilities greater than 10{sup {minus}9}/yr. The largest offsite dose is calculated to be 220 mrem, which is less than the 500 mrem value used to define items important to safety in 10 CFR 60. The study does not address an estimate of uncertainties, therefore conclusions or decisions made as a result of this report should be made with caution.

  9. Formerly utilized MED/AEC Sites Remedial Action Program. Radiological survey of the former VITRO Rare Metals Plant, Canonsburg, Pennsylvania. Final report. [Plant to extract radium and uranium

    Energy Technology Data Exchange (ETDEWEB)

    None

    1979-06-01

    This 18-acre site was used from 1911 to 1922 to extract radium from carnotite ore, from 1930 to 1942 to extract radium and uranium salts from onsite residues and carnotite ore, and from 1942 to 1957 to recover uranium from various ores and scrap materials. The radiological survey was conducted in two phases, Phase I included measurement of radon and radon daughter concentrations in onsite buildings; concentrations measured in this part of the survey were all above guideline levels. Phase II consisted of measurement of surface contamination levels on the site, external gamma radiation levels at 1 m above surfaces on and near the site, radionuclide concentrations in surface and subsurface soil and water on and near the site, and radon concentrations in air at offsite locations. The results of the second phase of the survey indicate that large quantities of the radioactive wastes generated during radium and uranium recovery operations still remain on the site. Radium-bearing wastes are present in soil beneath or adjacent to each of the buildings on the site and in the top few feet of soil over almost the entire site, with some areas being contaminated to a depth of 16 ft or more. Alpha contamination levels, beta--gamma dose rates, and external gamma radiation levels in some areas of the buildings and outdoors on the site are above current federal guidelines concerning the release of property for unrestricted use. Concentrations of /sup 226/Ra in water in holes drilled on the site are above the maximum permissible concentration (MPC/sub w/). Also, measurements made offsite show that contamination from the site has spread to nearby offsite locations, and that there is significant atmospheric transport of /sup 222/Rn from the site.

  10. 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.

  11. 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...

  12. 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.

  13. 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

  14. Retention of contrast media in the history of radiology. Sequelae of the former use of thorotrast and new challenges

    International Nuclear Information System (INIS)

    Kaick, G. van; Delorme, S.

    2016-01-01

    Detection of gadolinium deposits in patients who have repeatedly been administered intravenous gadolinium chelates have given rise to concern regarding the long-term safety of magnetic resonance imaging (MRI) contrast media. Nevertheless, negative long-term clinical effects have not yet been observed. In some publications parallels have been drawn to the sequelae of thorotrast that was formerly used for arterial angiography. In this article the history of thorotrast use is briefly described and in particular why, despite warnings, this substance was used frequently and worldwide. A brief summary of the results of the German Thorotrast Study revealed that high excess rates were only observed for primary malignant liver tumors after a 15-year or longer latency period and to a lesser degree of leukemias, as well as for severe local complications due to paravascular injections, particularly in the neck region. Based on this historical review, we will venture to take stock of the outcome from the ''success story'' of this contrast agent. (orig.) [de

  15. 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)

  16. Aerial radiological survey of US Department of Energy sites in Ames, Iowa. Date of survey: May 1977

    International Nuclear Information System (INIS)

    1979-07-01

    An aerial radiological survey to measure terrestrial gamma radiation was carried out over five areas totaling 10 km 2 within the town of Ames, Iowa. Gamma ray data were measured over Ames Laboratory, several sections of downtown Ames, and the surrounding area. This was accomplished by flying parallel east-west lines 61 m apart. Processed data indicated that three areas showed increased activity levels of at least twice average background: the reactor, the waste treatment area, and a small area near the airport runway

  17. Survey of Radiological and Chemical Contaminants in the Near-Shore Environment at the Hanford Site 300 Area

    International Nuclear Information System (INIS)

    Patton, Gregory W.; Van Verst, Scott P.; Tiller, Brett L.; Antonio, Ernest J.; Poston, Ted M.

    2003-01-01

    This updates the original report by correcting some errors and adding new information. This assessment of the 300 Area was completed to identify any contamination present and determine if it could present a risk to humans and plant and animal life. The assessment characterized the radiological and chemical conditions existing in the near-shore environment of the Columbia River at the 300 Area by collecting water, biota, and sediment samples and measuring radiation levels during a time when the effects of riverbank spring discharges and groundwater upwelling into the river was likely to be present

  18. Laenderyggens degeneration og radiologi

    DEFF Research Database (Denmark)

    Jacobsen, Steffen; Gosvig, Kasper Kjaerulf; Sonne-Holm, Stig

    2006-01-01

    and significant relationships between radiological findings and subjective symptoms have both been notoriously difficult to identify. The lack of consensus on clinical criteria and radiological definitions has hampered the undertaking of properly executed epidemiological studies. The natural history of LBP...... is cyclic: exacerbations relieved by asymptomatic periods. New imaging modalities, including the combination of MR imaging and multiplanar 3-D CT scans, have broadened our awareness of possible pain-generating degenerative processes of the lumbar spine other than disc degeneration....

  19. Formerly utilized MED/AEC sites remedial action program. Radiological survey of the Seaway Industrial Park, Tonawanda, New York. Final report

    International Nuclear Information System (INIS)

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

    1978-05-01

    The results of a radiological survey of the Seaway Industrial Park, Tonawanda, New York, are presented in this report. The site is adjacent to the former Haist property, which was used to receive residues from uranium processing during the period 1944--46. In 1974 approximately 6000 yd 3 of this residue was transported to Seaway, where it was used as landfill. The survey was undertaken to determine radiation levels and the extent of radioactive materials on the Seaway property, as well as the extent of movement of radioactive residues by natural means such as surface run-off. The survey included measurement of: external gamma radiation on and near the site; beta-gamma radiation at the surface in the most contaminated areas; radium and uranium concentrations in the soil; concentrations of radium, uranium, and thorium in water samples collected from the drainage areas; and radium concentrations in mud samples taken from the drainage areas. The results indicate that the residues on the site do not pose any immediate health hazards. However, potential health hazards could result from some uses of the site. In particular, if buildings were to be built in certain areas on the site, significant concentrations of radon daughters could develop in these structures. 16 figs, 3 tables

  20. The history of the Gorleben site as a basis for the long-term behavior of a barrier system

    International Nuclear Information System (INIS)

    Jaritz, W.

    1994-01-01

    The following processes that took place during the development of the Gorleben salt dome and their mutual relationships are examined and correlated with the geological time scale: Tectonics and epirogenesis, eustatic changes, chemical and mineralogical changes in the salt formation, halokinetic history, subsurface solution at the top of the salt dome, history of formation of the cap rock, sedimentation and erosion above the salt dome and the glacial impact on the site. A prediction of the evolution of the salt dome in the near geological future can be derived from consideration of each of these factors. (orig.) [de

  1. Radiological Risk Assessments for Occupational Exposure at Fuel Fabrication Facility in AlTuwaitha Site Baghdad – Iraq by using RESRAD Computer Code

    Science.gov (United States)

    Ibrahim, Ziadoon H.; Ibrahim, S. A.; Mohammed, M. K.; Shaban, A. H.

    2018-05-01

    The purpose of this study is to evaluate the radiological risks for workers for one year of their activities at Fuel Fabrication Facility (FFF) so as to make the necessary protection to prevent or minimize risks resulted from these activities this site now is under the Iraqi decommissioning program (40). Soil samples surface and subsurface were collected from different positions of this facility and analyzed by gamma rays spectroscopy technique High Purity Germanium detector (HPGe) was used. It was found out admixture of radioactive isotopes (232Th 40K 238U 235U137Cs) according to the laboratory results the highest values were (975758) for 238U (21203) for 235U (218) for 232Th (4046) for 40K and (129) for 137Cs in (Bqkg1) unit. The annual total radiation dose and risks were estimated by using RESRAD (onsite) 70 computer code. The highest total radiation dose was (5617μSv/year) in area that represented by soil sample (S7) and the radiological risks morbidity and mortality (118E02 8661E03) respectively in the same area

  2. Status of the Real-time On-line Decision Support (RODOS) system for off-site emergency management after nuclear and radiological accidents

    International Nuclear Information System (INIS)

    Raskov, W.; Ehrhardt, J.; Landman, C.; Pasler-Sauer, J.

    2006-01-01

    Under the auspices of its EURATOM Research Framework Programmes, the European Commission (EC) has supported the development of the comprehensive decision support system RODOS (Real-time On-line Decision Support) for off-site emergency management after nuclear accidents for more than a decade. Many national research programmes, research institutes and industrial collaborators contributed to the project, in particular the German Ministry of Environment, Nature Conservation and Reactor Safety (B MU). The RODOS system can be applied to accidental releases into the atmosphere and various aquatic environments within and across Europe. It provides coherent support before, during and after such a release to assist analysis of the situation and decision making about short and long-term countermeasures for mitigating the consequences with respect to health, the environment, and the economy. Appropriate interfaces exist with local and national radiological monitoring data systems, meteorological measurements and forecasts, and for the adaptation to local, regional and national conditions in Europe. Within the European Integrated Project EURANOS of the sixth Framework Programme, the RODOS system is being enhanced, among others, for radiological emergencies such as dirty bombs attacks, transport accidents and satellite crashes by extensions of the nuclide list, the source term characteristics and the atmospheric dispersion model

  3. EPA Enforcement and Compliance History Online: Hazardous Waste Sites Data Set

    Data.gov (United States)

    U.S. Environmental Protection Agency — The Enforcement and Compliance History Online (ECHO) data sets have been compiled for access to larger sets of national data to ensure that ECHO meets your data...

  4. Radiological English

    Energy Technology Data Exchange (ETDEWEB)

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

    2007-07-01

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

  5. Radiological English

    International Nuclear Information System (INIS)

    Ribes, R.; Ros, P.R.

    2007-01-01

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

  6. 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

  7. Laenderyggens degeneration og radiologi

    DEFF Research Database (Denmark)

    Jacobsen, Steffen; Gosvig, Kasper Kjaerulf; Sonne-Holm, Stig

    2006-01-01

    Low back pain (LBP) is one of the most common conditions, and at the same time one of the most complex nosological entities. The lifetime prevalence is approximately 80%, and radiological features of lumbar degeneration are almost universal in adults. The individual risk factors for LBP and signi......Low back pain (LBP) is one of the most common conditions, and at the same time one of the most complex nosological entities. The lifetime prevalence is approximately 80%, and radiological features of lumbar degeneration are almost universal in adults. The individual risk factors for LBP...... and significant relationships between radiological findings and subjective symptoms have both been notoriously difficult to identify. The lack of consensus on clinical criteria and radiological definitions has hampered the undertaking of properly executed epidemiological studies. The natural history of LBP...

  8. Radiological survey of the low-level radioactive waste burial site at the Palos Forest Preserve, Illinois

    International Nuclear Information System (INIS)

    Hayes, K.A.

    1982-01-01

    Two landfill sites containing low-level radioactive waste material, Site A and Plot M, are located 14 miles southwest of Chicago, Illinois in the Palos Forest Preserve. Site A is the former location of the Argonne National Laboratory. Buried at Site A in 1956 were the dismantled reactor shells, building walls, and cooling towers from three of the world's first nuclear reactors. Plot M was used from 1943 to 1949 for burial of low-level radioactive wastes derived from Site A operations and from the University of Chicago Metallurgical Laboratory. Tritiated water was detected in 1973 in some of the Forest Preserve picnic wells located 500 to 1000 yards north of Plot M. An extensive surveillance program was initiated in 1976 to: (1) study the elevated tritium content of some picnic wells and its observed seasonal fluctuations, (2) establish if other radionuclides buried in Plot M or remaining at Site A have migrated, (3) establish the rate of groundwater movement in the glacial till and underlying dolomite aquifer, (4) determine the tritium content of the till and aquifer, and (5) predict future tritium levels in the well water. Several test wells were installed in the soil and dolomite bedrock to monitor radioactivity in groundwater, measure water levels, and provide other geohydrological information. Tritium has migrated from the Plot M burial trenches into the surrounding drift. The tritium plume, the contaminated zone in the drift in which tritium concentrations exceed 10 nanocuries per liter of water (nCi/L), has migrated at least 165 feet horizontally northward and 130 feet vertically downward to the bedrock surface. Small amounts of other radionuclides - uranium, plutonium, and strontium-90 - have been found in boreholes beneath the concrete cap covering Plot M, but not in the subsoil outside of the Plot. The radionuclide concentrations found to date are too low to result in any measureable radiation exposure to the public

  9. Radiology fundamentals

    CERN Document Server

    Singh, Harjit

    2011-01-01

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

  10. RSVP radiology

    International Nuclear Information System (INIS)

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

    1990-01-01

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

  11. Radiological environmental dose assessment methods and compliance dose results for 2015 operations at the Savannah River Site

    International Nuclear Information System (INIS)

    Jannik, G. T.; Dixon, K. L.

    2016-01-01

    This report presents the environmental dose assessment methods and the estimated potential doses to the offsite public from 2015 Savannah River Site (SRS) atmospheric and liquid radioactive releases. Also documented are potential doses from special-case exposure scenarios - such as the consumption of deer meat, fish, and goat milk.

  12. Radiological environmental dose assessment methods and compliance dose results for 2015 operations at the Savannah River Site

    Energy Technology Data Exchange (ETDEWEB)

    Jannik, G. T. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Dixon, K. L. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

    2016-09-01

    This report presents the environmental dose assessment methods and the estimated potential doses to the offsite public from 2015 Savannah River Site (SRS) atmospheric and liquid radioactive releases. Also documented are potential doses from special-case exposure scenarios - such as the consumption of deer meat, fish, and goat milk.

  13. Corrective Action Investigation Plan for Corrective Action Unit 576: Miscellaneous Radiological Sites and Debris Nevada National Security Site, Nevada, Revision 0

    Energy Technology Data Exchange (ETDEWEB)

    Matthews, Patrick [Navarro, Las Vegas, NV (United States)

    2016-12-01

    Corrective Action Unit (CAU) 576 is located in Areas 2, 3, 5, 8, and 9 of the Nevada National Security Site, which is approximately 65 miles northwest of Las Vegas, Nevada. CAU 576 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 576, which comprises the following corrective action sites (CASs): 00-99-01, Potential Source Material; 02-99-12, U-2af (Kennebec) Surface Rad-Chem Piping; 03-99-20, Area 3 Subsurface Rad-Chem Piping; 05-19-04, Frenchman Flat Rad Waste Dump ; 09-99-08, U-9x (Allegheny) Subsurface Rad-Chem Piping; 09-99-09, U-9its u24 (Avens-Alkermes) Surface Contaminated Flex Line 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 (CADD).

  14. 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.

  15. 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

  16. History of Tree Growth Declines Recorded in Old Trees at Two Sacred Sites in Northern China.

    Science.gov (United States)

    Li, Yan; Zhang, Qi-Bin

    2017-01-01

    Old forests are an important component in sacred sites, yet they are at risk of growth decline from ongoing global warming and increased human activities. Growth decline, characterized by chronic loss of tree vigor, is not a recent phenomenon. Knowledge of past occurrence of declines is useful for preparing conservation plans because it helps understand if present day forests are outside the natural range of variation in tree health. We report a dendroecological study of growth decline events in the past two centuries at two sacred sites, Hengshan and Wutaishan, in Shanxi province of northern China. Tree rings collected at both sites show distinct periods of declining growth evident as narrow rings. These occurred in the 1830s in both sites, in the 1920s in Wutaishan and in the 2000s in Hengshan. By comparing the pattern of grow declines at the two sites, we hypothesize that resistance of tree growth to external disturbances is forest size dependent, and increased human activity might be a factor additional to climatic droughts in causing the recent strong growth decline at Hengshan Park. Despite these past declines, the forests at both sites have high resilience to disturbances as evidenced by the ability of trees to recover their growth rates to levels comparable to the pre-decline period. Managers should consider reducing fragmentation and restoring natural habitat of old forests, especially in areas on dry sites.

  17. History of Tree Growth Declines Recorded in Old Trees at Two Sacred Sites in Northern China

    Directory of Open Access Journals (Sweden)

    Yan Li

    2017-11-01

    Full Text Available Old forests are an important component in sacred sites, yet they are at risk of growth decline from ongoing global warming and increased human activities. Growth decline, characterized by chronic loss of tree vigor, is not a recent phenomenon. Knowledge of past occurrence of declines is useful for preparing conservation plans because it helps understand if present day forests are outside the natural range of variation in tree health. We report a dendroecological study of growth decline events in the past two centuries at two sacred sites, Hengshan and Wutaishan, in Shanxi province of northern China. Tree rings collected at both sites show distinct periods of declining growth evident as narrow rings. These occurred in the 1830s in both sites, in the 1920s in Wutaishan and in the 2000s in Hengshan. By comparing the pattern of grow declines at the two sites, we hypothesize that resistance of tree growth to external disturbances is forest size dependent, and increased human activity might be a factor additional to climatic droughts in causing the recent strong growth decline at Hengshan Park. Despite these past declines, the forests at both sites have high resilience to disturbances as evidenced by the ability of trees to recover their growth rates to levels comparable to the pre-decline period. Managers should consider reducing fragmentation and restoring natural habitat of old forests, especially in areas on dry sites.

  18. Applications of SLAR in nuclear power plant siting: A case history

    Science.gov (United States)

    Siegal, B. S.

    1980-01-01

    Over 10,000 square km of side-looking airborne radar (SLAR) imagery was obtained and analyzed for the siting of the first nuclear power plant in the Republic of the Philippines. The imagery was obtained using the Motorola APS/AN-94D (X-band) real aperture system as part of an overall remote sensing program to site and evaluate potential site regions. Analysis of SLAR images, in conjunction with LANDSAT, color, black and white, and thermal infrared images, provided basic information on structure, relative geochronology, stratigraphy, geomorphology, and ground water, which facilitated field operations and data synthesis.

  19. Development of a methodology for post closure radiological risk analysis of underground waste repositories. Illustrative assessment of the Harwell site

    International Nuclear Information System (INIS)

    Gralewski, Z.A.; Kane, P.; Nicholls, D.B.

    1987-06-01

    A probabilistic risk analysis (pra) is demonstrated for a number of ground water mediated release scenarios at the Harwell Site for a hypothetical repository at a depth of about 150 metres. This is the second stage of development of an overall risk assessment methodology. A procedure for carrying out multi-scenario assessment using available probabilistic risk assessment (pra) models is presented and a general methodology for combining risk contributions is outlined. Appropriate levels of model complexity in pra are discussed. Modelling requirements for the treatment of multiple simultaneous pathways and of site evolution are outlined. Further developments of pra systems are required to increase the realism of both the models and their mode of application, and hence to improve estimates of risk. (author)

  20. American National Standard: for facilities and medical care for on-site nuclear-power-plant radiological emergencies

    International Nuclear Information System (INIS)

    Anon.

    1979-01-01

    This standard provides guidance for first aid during an emergency and for initial medical care of those persons on-site who are overexposed to penetrating radiation (irradiated). It also provides guidance for medical care of persons contaminated with radioactive material or radionuclides who may also be irradiated or injured as a result of an accident at a nuclear power plant. It provides recommendations for facilities, supplies, equipment, and the extent of care both on-site where first aid and initial care may be provided and off-site at a local hospital where further medical and surgical care may be provided. This initial care continues until either the patient is released or admitted, or referred to another, possibly distant, medical center for definitive care. Recommendations are also provided for the transportation of patients and the training of personnel. Recommendations for specialized care are considered to be beyond the scope of this standard on emergency medical care; however, since emergency and specialized care are related, a brief discussion of specialized care is provided in the Appendix

  1. Radiology illustrated. Pediatric radiology

    Energy Technology Data Exchange (ETDEWEB)

    Kim, In-One (ed.) [Seoul National Univ. College of Medicine (Korea, Republic of). Dept. of Radiology

    2014-11-01

    Depicts characteristic imaging findings of common and uncommon diseases in the pediatric age group. Will serve as an ideal diagnostic reference in daily practice. Offers an excellent teaching aid, with numerous high-quality illustrations. This case-based atlas presents images depicting the findings typically observed when imaging a variety of common and uncommon diseases in the pediatric age group. The cases are organized according to anatomic region, covering disorders of the brain, spinal cord, head and neck, chest, cardiovascular system, gastrointestinal system, genitourinary system, and musculoskeletal system. Cases are presented in a form resembling teaching files, and the images are accompanied by concise informative text. The goal is to provide a diagnostic reference suitable for use in daily routine by both practicing radiologists and radiology residents or fellows. The atlas will also serve as a teaching aide and a study resource, and will offer pediatricians and surgeons guidance on the clinical applications of pediatric imaging.

  2. The Wahluke (North) Slope of the Hanford Site: History and present challenges

    International Nuclear Information System (INIS)

    Gerber, M.S.

    1996-01-01

    The Hanford Site was founded in early 1943 for the top secret government mission of producing plutonium for the world's first atomic weapons. A great deal of land was needed, both to separate various Site facilities from each other, and to provide buffer zones for safety and security purposes. In total, 640 square miles were occupied by the original Hanford Site and its buffer zones. Much of this land had been earmarked for inclusion in the Columbia Basin Irrigation Project (CBP). After World War II ended, a series of national decisions led to a long-term mission for the Hanford Site, and area residents learned that the Site lands they had hoped to farm would be withheld from agricultural production for the foreseeable future. A long set of negotiations commenced between the federal management agency responsible for Hanford (the Atomic Energy Commission -- AEC), and the Bureau of Reclamation (BOR), Department of the Interior that managed the CBP. Some lands were turned back to agriculture, and other compromises made, in the Site's far northern buffer lands known as the Wahluke Slope, during the 1950s. In the mid-1960s, further negotiations were about to allow farming on lands just north of the Columbia River, opposite Hanford's reactors, when studies conducted by the BOR found drainage barriers to irrigation. As a result of these findings, two wildlife refuges were created on that land in 1971. Today, after the Hanford Site plutonium production mission has ended and as Site cleanup goes forward, the possibility of total release of Wahluke Slope lands from the control of the Department of Energy (DOE -- a successor agency to the AEC) is under discussion. Such discussion encompasses not just objective and clearly visible criteria, but it resurrects historical debates about the roles of farming and government presence in the Columbia Basin

  3. 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

  4. Siting history and current construction status of disposal facility for low and intermediate level radioactive waste in Korea

    International Nuclear Information System (INIS)

    Sakai, Akihiro; Kikuchi, Saburo; Maruyama, Masakatsu

    2008-01-01

    Korean government decided disposal site for low and intermediate level radioactive waste (LILW), which is located at coastal area near the Wolsong nuclear power plants in Gyeong-Ju city in December. 2005, based on the result of votes of residents in four candidate sites. Since then, Korea Hydro and Nuclear Power Co., Ltd (KHNP), which is the management company of the LILW disposal facility, has carried out the preparation for construction of disposal facility and its licensing process. At the first phase, 100 thousand drums in 200 liter are planned to be disposed of in the rock cavern type disposal facility located at the depth from 80m to 130m below the sea level, and finally 800 thousand drums in 200 liter are planned to be disposed of in the site. This report shows the history of siting for the LILW disposal, the outline of design of disposal facility and current status of its construction, based on the information which was obtained mainly during our visit to the disposal site in Korea. (author)

  5. Formerly utilized MED/AEC sites remedial action program. Radiological survey of the former Horizons, Inc., metal handling facility, Cleveland, Ohio. Final report

    International Nuclear Information System (INIS)

    Leggett, R.W.; Cottrell, W.D.; Shinpaugh, W.H.; Doane, R.W.; Haywood, F.F.; Johnson, W.M.

    1979-02-01

    The results of a radiological survey of the former Horizons, Inc., metal handling facility in Cleveland, Ohio, are presented in this report. During the 1940's and early 1950's, two of the three buildings on this site (Buildings B and C) were used for the production of granular thorium metal. The survey included measurements related to the following: fixed and transferable alpha and beta-gamma contamination levels on the surfaces in Buildings B and C and on the roofs of these buildings; external gamma radiation levels at 1 m above the floors and grounds on and near the property; radionuclide concentrations in soil, water, and other materials collected from surfaces and drains inside Buildings B and C, from beneath the floor in Building C, and from outdoor locations on and near the site; and thoron ( 220 Rn) daughter concentrations in the air in Buildings B and C. Elevated concentrations of 232 Th, 228 Ra, 228 Th, and 230 Th were found in some samples. Alpha and beta-gamma contamination levels exceeded applicable guideline limits in some areas of Buildings B and C. External gamma radiation levels, approximately 10 times the average background level, were measured at isolated points in and near Building B. Thorium B ( 212 Pb) concentrations in air in Building B were near the Radioactivity Concentration Guide (RCG) level. Most of the elevated radiation levels were found indoors in areas presently used for storage. Outdoors on and near the site, significant radiation levels were found only near the east wall of Building B

  6. Imaging and radiology

    Science.gov (United States)

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

  7. Chronicle of pediatric radiology

    International Nuclear Information System (INIS)

    Benz-Bohm, Gabriele; Richter, Ernst

    2012-01-01

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

  8. Development of the radiological protection focus in the site, design and construction of the nuclear power plant in Cuba

    International Nuclear Information System (INIS)

    Rodriguez R, J.M.

    1996-01-01

    The first nuclear station in Cuba NPP Juragua, at present in analysis for starting again the construction, under a multinational economic association, had had as main architect/engineer organization the Design Institute for Nuclear Power Stations of St. Petersburg (former LIAEP). Active participation of Cuban radiation protection specialist of Energoproyecto in the Juragua Project began at the beginning of the site selection works and continued in the design and construction stages up till now, and simultaneously our specialists have been acting as a counterpart of soviet designers, responsible for the general design of the station. Furthermore, some additional works in compliance with the latest safety requirements and the best international practices, which are described, as well as ongoing and planned work were performed. (author). 11 refs., 3 figs

  9. Campaign of complementary investigation on the old mining site of Saint-Pierre (Cantal) 2. part of the relative expertise at the radiological situation of the site

    International Nuclear Information System (INIS)

    2007-01-01

    The C.L.I. of Saint-Pierre which was held on May 19., 2006 in Mauriac (Cantal) confirmed the program of additional investigations to be collectively led by the I.R.S.N. and the C.R.I.I.R.A.D. on Saint Pierre site. Main directions are the following ones: realize additional analyses on the drainages of water; measure the external exposure on 14 plots of land; measure the flux of radon at the ground level and radon inside houses; realize investigations on the food chain. The present report reports campaigns of sampling realized by the I.R.S.N. in 2006 as well as analyses led in its laboratories. (N.C.)

  10. White ash (Fraxinus americana) decline and mortality: the role of site nutrition and stress history

    Science.gov (United States)

    Alejandro A. Royo; Kathleen S. Knight

    2012-01-01

    Over the past century, white ash (Fraxinus americana) populations throughout its range have deteriorated as a result of declining tree health and increased mortality rates. Although co-occurring factors including site nutritional deficiencies and punctuated stress events (e.g., defoliations, drought) are hypothesized to trigger white ash decline,...

  11. Comparison of the regulatory models assessing off-site radiological dose due to the routine releases of tritium

    International Nuclear Information System (INIS)

    Hwang, W. T.; Kim, E. H.; Han, M. H.; Choi, Y. H.; Lee, H. S.; Lee, C. W.

    2005-01-01

    Methodologies of NEWTRIT model, NRC model and AIRDOS-EPA model, which are off-site dose assessment models for regulatory compliance from routine releases of tritium into the environment, were investigated. Using the domestic data, if available, the predictive results of the models were compared. Among them, recently developed NEWTRIT model considers only doses from organically bounded tritium (OBT) due to environmental releases of tritiated water (HTO). A total dose from all exposure pathways predicted from AIRDOS-EPA model was 1.03 and 2.46 times higher than that from NEWTRIT model and NRC model, respectively. From above result, readers should not have an understanding that a predictive dose from NRC model may be underestimated compared with a realistic dose. It is because of that both mathematical models and corresponding parameter values for regulatory compliance are based on the conservative assumptions. For a dose by food consumption predicted from NEWTRIT model, the contribution of OBT was nearly equivalent to that of HTO due to relatively high consumption of grains in Korean. Although a total dose predicted from NEWTRIT model is similar to that from AIRDOS-EPA model, NEWTRIT model may be have a meaning in the understanding of phenomena for the behavior of HTO released into the environment

  12. Survey, Settlement, and Population History at the Ancient Maya Site of Pacbitun, Belize

    DEFF Research Database (Denmark)

    Healy, Paul F.; Helmke, Christophe G.B.; Awe, Jaime J.

    2007-01-01

    Survey and excavations of mounds on the outskirts of the site of Pacbitun in western Belize provide insights to the ancient Maya settlement pattern at this medium-sized regional center. This research employed two methods: analysis of structural remains from four separate 1000 m transect surveys...... to have been about 5000-6000 persons. This population estimate is compared with several coeval lowland Maya centers, and found to be reasonable for a medium-sized, Late Classic Maya center....

  13. History and stabilization of the Plutonium Finishing Plant (PFP) complex, Hanford Site

    Energy Technology Data Exchange (ETDEWEB)

    Gerber, M.S., Fluor Daniel Hanford

    1997-02-18

    The 231-Z Isolation Building or Plutonium Metallurgy Building is located in the Hanford Site`s 200 West Area, approximately 300 yards north of the Plutonium Finishing Plant (PFP) (234-5 Building). When the Hanford Engineer Works (HEW) built it in 1944 to contain the final step for processing plutonium, it was called the Isolation Building. At that time, HEW used a bismuth phosphate radiochemical separations process to make `AT solution,` which was then dried and shipped to Los Alamos, New Mexico. (AT solution is a code name used during World War II for the final HEW product.) The process was carried out first in T Plant and the 224-T Bulk Reduction Building and B Plant and the 224-B Bulk Reduction Building. The 224-T and -B processes produced a concentrated plutonium nitrate stream, which then was sent in 8-gallon batches to the 231-Z Building for final purification. In the 231-Z Building, the plutonium nitrate solution underwent peroxide `strikes` (additions of hydrogen peroxide to further separate the plutonium from its carrier solutions), to form the AT solution. The AT solution was dried and shipped to the Los Alamos Site, where it was made into metallic plutonium and then into weapons hemispheres.` The 231-Z Building began `hot` operations (operations using radioactive materials) with regular runs of plutonium nitrate on January 16, 1945.

  14. Effects of zinc and female aging on nymphal life history in a grasshopper from polluted sites.

    Science.gov (United States)

    Augustyniak, Maria; Babczyńska, Agnieszka; Kozłowski, Michał; Sawczyn, Tomasz; Augustyniak, Michał

    2008-01-01

    Insect reproduction is influenced by various factors, including food quality and quantity, temperature, population density and female age. Contamination, including heavy metals, may disturb reproductive processes. The aim of this work was to assess interactions between effects of aging in female Chorthippus brunneus and environmental pollution on their reproduction measured in number of laid eggs. We also compared basic developmental parameters (number of hatchlings, body mass, embryonic developmental rate) in grasshopper nymphs additionally exposed to zinc during diapause. Aging grasshoppers from heavily polluted areas (Olkusz and Szopienice) lay significantly fewer eggs than insects from the reference site (Pilica). Zinc application caused the decrease in hatching success and duration of embryogenesis in insects from each site. This suggests a cumulative effect of female age, pollutants and additional stressing factors. The intensity of this process differed between populations. In insects from the reference site, it was shown in a moderate degree. In insects from Szopienice, an additional stressor exerted a weaker effect than in insects from Pilica. In grasshoppers from Olkusz, we found the strongest decrease of hatching percentage and increase in duration of embryogenesis after zinc intoxication. This may indicate that the population from Olkusz exists at the limit of its energetic abilities.

  15. Formerly utilized MED/AEC sites remedial action program: radiological survey of the former Simonds Saw and Steel Co., Lockport, New York. Final report

    International Nuclear Information System (INIS)

    1979-11-01

    Results of a radiological survey of the former Simonds Saw and Steel Company (current name of this facility is Guterl Special Steel Corporation), Lockport, New York, are presented in this report. During the period 1948 to 1956, this company handled large quantities of uranium metal and smaller quantities of thorium metal in rolling mill operations. The survey included measurement of residual alpha and beta-gamma radiation levels in the rolling mill building and forging shop; external gamma radiation in the same area; uranium, radium, and thorium in soil samples taken from beneath removable floor plates in the rolling mill area and from other parts of the site; radon and radon daughter concentrations in the rolling mill building; and contamination in drainage paths leading from the buildings and grounds. Elevated concentrations of uranium were found in soil samples taken from beneath the floor plates within 40 ft of the 16-inch rolling mill. Beta-gamma radiation levels were greater than 1 mrad/hr at the locations having the highest concentrations of uranium. External gamma radiation levels were above the background level in a few small isolated areas in the rolling mill building. The 16-inch rolling mill showed elevated alpha and beta contamination levels in several areas

  16. Radiological dose assessment for the decontaminated concrete removed from 183-H solar evaporation basins at the Hanford site, Richland, Washington

    International Nuclear Information System (INIS)

    Kamboj, S.; Faillace, E.; Yu, C.

    1997-01-01

    Potential maximum radiation dose rates over a 1,000-year time horizon were calculated for exposure to the decontaminated concrete removed from the 183-H Solar Evaporation Basins at the Hanford Site, Richland, Washington. The RESRAD computer code, Version 5.62, which implements the methodology described in the US Department of Energy's manual for developing residual radioactive material guidelines, was used in this evaluation. Currently, the concrete is not being used. Four potential exposure scenarios were developed for the land area where the decontaminated concrete will be stored. In Scenario A industrial use of the land is assumed; in Scenario B recreational use of the land is assumed; in Scenario C residential use of the land is assumed; and in Scenario D (a plausible but unlikely land-use scenario), the presence of a subsistence farmer in the immediate vicinity of the land is assumed. For Scenarios A and B, water used for drinking is assumed to be surface water from the Columbia River; for Scenarios C and D, groundwater drawn from a well located at the downgradient edge of the storage area is the only source of water for drinking, irrigation, and raising livestock. Conservative parameters values were used to estimate the radiation doses. The results of the evaluation indicate that the US Department of Energy's dose limit of 100 mrem/yr would not be exceeded for any of the scenarios analyzed. The potential maximum dose rates for Scenarios A, B, C, and D are 0.75, 0.022, 29, 29 mrem/yr, respectively. An uncertainty analysis was performed to determine which parameters have the greatest impact on the estimated doses. The doses in Scenarios C and D were found to be very sensitive to the magnitude of the irrigation rate

  17. History of dams at the Department of Energy's Savannah River Site, Aiken, South Carolina

    International Nuclear Information System (INIS)

    Jones, M.P.; Wilson, C.B.

    1995-01-01

    Since the production of nuclear material at SRS for weapons required large quantities of cooling water, a series of canals, dikes, and dams were constructed to provide conveyance systems and reservoirs. This paper presents a brief overview of the history of the construction of the dams and dikes. Attention is given to the use of asphaltic concrete for 30 years (and its maintenance and repair) to line the banks of dikes and the upstream slopes of dams to prevent erosion and possible failure. The ability of asphaltic concrete in preventing dam/dike failure was proven. Benefits and drawbacks to the use of this material are discussed based on the extensive experience at SRS

  18. Dental radiology

    International Nuclear Information System (INIS)

    Bhaskar, S.N.

    1982-01-01

    The book presents the radiological manifestations of the maxillodental region in a suitable manner for fast detection and correct diagnosing of diseases of the teeth, soft tissue, and jaws. Classification therefore is made according to the radiological manifestations of the diseases and not according to etiology. (orig./MG) [de

  19. Assessment of radiological risk parameters associated with some selected rivers around oil mineral producing sites in Abia State, Nigeria due to gross alpha and beta radiations

    International Nuclear Information System (INIS)

    Enyinna, Paschal Ikenna; Uzochukwu, Francis C.

    2016-01-01

    The study of gross alpha and beta radiation in environmental components and water bodies in particular is very crucial to the environmental, radiation and medical Physicist as this helps to promote good water quality and environmental hygiene. This research work understudied the radiological risk parameters due to gross alpha and beta radiations associated with three selected rivers around crude oil production sites in Abia State, Nigeria. Gross alpha and beta activities were computed for the three rivers based on analytical measurements carried out using a well-calibrated IN-20 model gas-flow proportional counter. Radiological risk parameters were computed from the activity concentrations which included; annual effective dose equivalent of radiation from ingested water (AEDE), annual gonadal dose equivalent (AGDE), and excess lifetime cancer risk (ELCR). The mean of the total AEDE due to the sum of alpha and beta radiations for the three rivers are 0.868 ± 0.221 mSv/y, 1.008 ± 0.156 mSv/y, and 0.917 ± 0.214 mSv/y; and are above the World Health Organization (WHO) permissible limit of 0.1 mSv/y. The mean of the total AGDE are 4.048 ± 1.063 mSv/y, 4.756 ± 0.739 mSv/y, and 4.295 ± 1.026 mSv/y; and are above the world average limit of 0.3 mSv/y. The mean of the total ELCR are (3.038 ± 0.774) X 10"-"3, (3.529 ± 0.547) X 10"-"3, and (3.210 ± 0.748) X 10"-"3; and are above the world average limit of 0.29 X 10"-"3. Most values of ELCR computed in this work are >6.0 X 10"-"4 estimated to be the risk of fatal and weighted nonfatal health conditions over a lifetime (70 years) derived from the radiation dose of 0.1 mSv/y (WHO permissible limit for drinking water). Drinking water from these surveyed sources could impact negatively on the end users. (author)

  20. 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

  1. Handbook of radiologic procedures

    International Nuclear Information System (INIS)

    Hedgcock, M.

    1986-01-01

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

  2. 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

  3. Engineered materials characterization report for the Yucca Mountain Site Characterization Project. Volume 1, Introduction, history, and current candidates

    International Nuclear Information System (INIS)

    Van Konynenburg, R.A.; McCright, R.D.; Roy, A.K.; Jones, D.A.

    1995-08-01

    The purpose of the Yucca Mountain Site Characterization Project is to evaluate Yucca Mountain for its suitability as a potential site for the nation's first high-level nuclear waste repository. As part of this effort, Lawrence Livermore National Laboratory (LLNL) has been occupied for a number of years with developing and evaluating the performance of waste packages for the potential repository. In recent years this work has been carried out under the guidance of and in collaboration with the Management and Operating contractor for the Civilian Radioactive Waste Management System, TRW Environmental Safety Systems, Inc., which in turn reports to the Office of Civilian Radioactive Waste Management of the US Department of Energy. This report summarizes the history of the selection and characterization of materials to be used in the engineered barrier system for the potential repository at Yucca Mountain, describes the current candidate materials, presents a compilation of their properties, and summarizes available corrosion data and modeling. The term ''engineered materials'' is intended to distinguish those materials that are used as part of the engineered barrier system from the natural, geologic materials of the site

  4. 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)

  5. 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)

  6. 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

  7. Radiological optimization

    International Nuclear Information System (INIS)

    Zeevaert, T.

    1998-01-01

    Radiological optimization is one of the basic principles in each radiation-protection system and it is a basic requirement in the safety standards for radiation protection in the European Communities. The objectives of the research, performed in this field at the Belgian Nuclear Research Centre SCK-CEN, are: (1) to implement the ALARA principles in activities with radiological consequences; (2) to develop methodologies for optimization techniques in decision-aiding; (3) to optimize radiological assessment models by validation and intercomparison; (4) to improve methods to assess in real time the radiological hazards in the environment in case of an accident; (5) to develop methods and programmes to assist decision-makers during a nuclear emergency; (6) to support the policy of radioactive waste management authorities in the field of radiation protection; (7) to investigate existing software programmes in the domain of multi criteria analysis. The main achievements for 1997 are given

  8. MEMO radiology

    International Nuclear Information System (INIS)

    Wagner-Manslau, C.

    1989-01-01

    This radiology volume is a concise handbook of imaging techniques, nuclear medicine, and radiation therapy, albeit that the main emphasis is on classic radiology. It offers, for instance, a survey of radiological findings for the most frequent pathological conditions, many overviews of differential diagnosis, a glossary of the technical bases of radiology and so forth. The contents are divided into the following chapters: Physical and biological bases; skeleton; thorax with the subdivisions lungs, heart, mediastinum, and pleura; gastrointestinal tract with the subsections esophagus, small and large intestine; liver; biliary tract; pancreas; retroperitoneal space; kidney; suprarenal glands; bladder; blood vessels, lymph nodes, spleen; mammary glands; female genitals; prostate and scrotum, epididymis and seminal vesicle. (orig./MG) With 23 figs [de

  9. Formerly utilized MED/AEC sites remedial action program. Radiological survey of Eckhart Hall, the University of Chicago, Chicago, Illinois, September 14, 1976-March 22, 1977

    International Nuclear Information System (INIS)

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

    1982-05-01

    A comprehensive radiological survey was conducted at the Eckhart Hall at the University of Chicago, Chicago, Illinois. General radiochemistry and/or physics research was performed at this facility during the MED/AEC era in the 1940s. The building is now used as laboratories, offices, and classrooms. Survey measurements included alpha and beta-gamma contamination determinations, both fixed and removable; beta-gamma exposure readings at contact and at 1 m (3 ft); estimates of radon-daughter concentrations in the air; and determination of concentrations of 137 Cs, the 232 Th decay chain, the 226 Ra decay chain, and uranium in the soil on the site. Thirteen spots of contamination were found to be fixed to or under existing surfaces and not readily available for transfer to other locations. Under current use conditions, the potential for radiation exposure to occupants of this building from these sources of contamination is remote. Concentrations of radon daughters in the air of the building were less than the limit of 0.01 Working Level (WL) above background. No long-lived radionuclides were detected in any air sample. Concentrations of radionuclides in soil samples collected around the facility indicated background levels. The presumed maximum potential internal radiation 50-year dose commitments from inhalation/ingestion of contamination remaining from MED/AEC activities were calculated to be less than 25% of the appropriate annual standards for an individual in an uncontrolled area. Remedial measures such as stabilization of the contamination in place would be applicable as a short-term measure. In order to reduce the risk in the event that building modifications take place in the future, health physics procedures and coverage are recommended. The long-term solution would involve decontamination by removal of the radioactive residues

  10. Methodological improvement and extension of scope of the guide to the radiological examination and evaluation of contaminated former mining sites. Final report

    International Nuclear Information System (INIS)

    2005-01-01

    G.E.O.S. Freiberg Ingenieurgesellschaft mbH have been requested in a letter from the Federal Radiation Protection Office dated 15 September 2006 - AG 3.1 StSch - to submit a quote on the topic of ''Methodological improvement and extension of scope of the guide to the radiological examination and evaluation of contaminated former mining sites''. In response to this request Part A of this guide is to be extended by a section on microbiology or, more specifically, on processes in tailings and sedimentation plants that could be induced by microorganisms. Up until now the guide only considered chemical and geochemical processes in the modelling and evaluation of the release of radionuclides from tailings. However, in view of the possibility of microbiological processes occurring in tailings, as for example in the presence of pyrite, one must also reckon with microbiological influences on radionuclide release. the following tasks and problems will therefore be addressed: Do the recommendations given in the guide also apply if microbiological influences are considered? Is it also necessary to consider microbiological issues in the examination and modelling of radionuclide transport via groundwater? What parameters need to be measured and assessed if decisions on rehabilitation measures for tailings must also be based on microbiological aspects? Which examination methods should be used to measure the required parameters efficiently and reliably? Is there anything particular that needs to be considered in studying the involvement of microbiological processes in the release of radionuclides from industrial sedimentation plants? The recommendations given in the guide with respect to the treatment of the water pathway should be reviewed with regard to any amendments or supplementations they might require from the microbiological viewpoint. It should also be investigated whether microbiological studies and measurements are required for the guide's further development. The

  11. Radiological hazards

    International Nuclear Information System (INIS)

    Hamilton, M.

    1984-01-01

    The work of the (United Kingdom) National Radiological Protection Board is discussed. The following topics are mentioned: relative contributions to genetically significant doses of radiation from various sources; radon gas in non-coal mines and in dwelling houses; effects of radiation accidents; radioactive waste disposal; radiological protection of the patient in medicine; microwaves, infrared radiation and cataracts; guidance notes for use with forthcoming Ionising Radiations Regulations; training courses; personal dosimetry service; work related to European Communities. (U.K.)

  12. 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.

  13. A radiological dose assessment for the Port Hope conversion facility

    International Nuclear Information System (INIS)

    Garisto, N.C.; Cooper, F.; Janes, A.; Stager, R.; Peters, R.

    2011-01-01

    The Port Hope Conversion Facility (PHCF) receives uranium trioxide for conversion to uranium hexafluoride (UF 6 ) or uranium dioxide (UO 2 ). The PHCF Site has a long history of industrial use. A Radiological Dose Assessment was undertaken as part of a Site Wide Risk Assessment. This assessment took into account all possible human receptors, both workers and members of the public. This paper focuses on a radiological assessment of dose to members of the public. The doses to members of the public from terrestrial pathways were added to the doses from aquatic pathways to obtain overall dose to receptors. The benchmark used in the assessment is 1 mSv/y. The estimated doses related to PHCF operations are much lower than the dose limit. (author)

  14. Radiological protection

    International Nuclear Information System (INIS)

    Azorin N, J.; Azorin V, J. C.

    2010-01-01

    This work is directed to all those people related with the exercise of the radiological protection and has the purpose of providing them a base of knowledge in this discipline so that they can make decisions documented on technical and scientist factors for the protection of the personnel occupationally exposed, the people in general and the environment during the work with ionizing radiations. Before de lack of a text on this matter, this work seeks to cover the specific necessities of our country, providing a solid presentation of the radiological protection, included the bases of the radiations physics, the detection and radiation dosimetry, the radiobiology, the normative and operational procedures associates, the radioactive wastes, the emergencies and the transport of the radioactive material through the medical and industrial applications of the radiations, making emphasis in the relative particular aspects to the radiological protection in Mexico. The book have 16 chapters and with the purpose of supplementing the given information, are included at the end four appendixes: 1) the radioactive waste management in Mexico, 2-3) the Mexican official standards related with the radiological protection, 4) a terms glossary used in radiological protection. We hope this book will be of utility for those people that work in the investigation and the applications of the ionizing radiations. (Author)

  15. 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.

  16. 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

  17. Status of the RODOS system for off-site emergency management after nuclear and radiological accidents and its enhancement under the EURANOS project

    International Nuclear Information System (INIS)

    Raskob, W.

    2007-01-01

    Full text: Under the auspices of its Euratom Research Framework Programmes, the European Commission (EC) has supported the development of the RODOS (Real-time On-line Decision Support) system for off-site emergency management after nuclear accidents for more than a decade. Significant additional funds have been provided by many national RTD programmes, research institutes and industrial collaborators. In particular, the German Ministry of Environment, Nature Conservation and Reactor Safety (BMU) financially contributed to the project with emphasis on early emergency response. As a result of these collaborative actions, a comprehensive decision support system (RODOS) has been developed which can be applied generally within and across Europe. The current version of the system has been, or is being, installed in national emergency centres in several European countries for (pre-operational) use (Germany, Finland, Spain, Portugal, Austria, the Netherlands, Poland, Hungary, Slovakia, Ukraine, Slovenia, and the Czech Republic). Installation is foreseen or under consideration in Switzerland, Greece, Romania, Bulgaria, and Russia within the next few years. RODOS provides coherent support at all stages of an accident (i.e., before, during and after a release), including the long term management and restoration of contaminated areas. The system is able to support decisions about the introduction of a wide range of potentially useful countermeasures (e.g., sheltering and evacuation of people, distribution of iodine tablets, food restrictions, agricultural countermeasures, relocation, decontamination, restoration, etc.) mitigating the consequences of an accident with respect to health, the environment, and the economy. It can be applied to accidental releases into the atmosphere and into various aquatic environments. Appropriate interfaces exist with local and national radiological monitoring data, meteorological measurements and forecasts, and for adaptation to local, regional

  18. Observing Site Histories

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — Detailed reports prepared for the Midwestern Regional Climate Center under the auspices of the Climate Database Modernization Program. The goal of each report is to...

  19. 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

  20. Postoperative radiology

    International Nuclear Information System (INIS)

    Burhenne, H.J.

    1989-01-01

    This paper reports on the importance of postoperative radiology. Most surgical procedures on the alimentary tract are successful, but postoperative complications remain a common occurrence. The radiologist must be familiar with a large variety of possible surgical complications, because it is this specialty that is most commonly called on to render a definitive diagnosis. The decision for reoperation, for instance, is usually based on results from radiologic imaging techniques. These now include ultrasonography, CT scanning, needle biopsy, and interventional techniques in addition to contrast studies and nuclear medicine investigation

  1. Late Pliocene History of Mediterranean Outflow Water in the Gulf of Cadiz (IODP Expedition 339, Site U1389)

    Science.gov (United States)

    Grunert, P.; Balestra, B.; Flores, J. A.; Sierro, F. J.; García Gallardo, Á.; Piller, W. E.; Aubry, M. P.

    2014-12-01

    The opening and closure of ocean gateways play an important role amongst climate forcing mechanisms: surface and deep-water circulation are altered, and hence global heat transport. An important component of North Atlantic circulation patterns is the warm and saline Mediterranean Outflow Water (MOW) that enters the North Atlantic via the Gibraltar Strait. Its onset and early history after the opening of the Gibraltar Strait at 5.3 Ma are poorly constrained and its impact on oceanography and climate in the Pliocene are largely unexplored. Current research efforts in the scope of projects funded by the Austrian Science Fund (FWF-P25831-N29) and the Max Kade Foundation aim to improve our knowledge about this early phase of MOW. Research focuses on Sites U1387C (upper Miocene-lower Pliocene; ~5.8-3.8 Myrs) and U1389E (middle-upper Pliocene; ~3.7-2.8) drilled during IODP Expedition 339 in the northern Gulf of Cádiz close to the source area of MOW. At IODP Site U1389E, a 280m-thick sequence of upper Pliocene contourites is studied to reconstruct MOW behavior and potential paleoceanographic and paleoclimatic feedback mechanisms during the Mid-Pliocene Thermal Optimum. Currently, a reliable age model is developed for the studied interval based on bio-, chemo-, and cyclostratigraphy. Several biostratigraphic datums have been identified from analyses of calcareous nannoplankton and planktic foraminifera which indicate a depositional age between 3.65 Ma and 2.87 Ma. In some intervals of the record a further refinement of the age model at the millenial scale is complicated by poor recovery. However, preliminary results from high-resolution geochemical analyses of the bulk sediment (TOC, CaCO3 and S) and shells of the planktic foraminifer Globigerinoides ruber (δ18O, δ13C) reveal distinct cyclic patterns in several well recovered intervals. Based on an average sedimentation rate of ~25cm/ka, these cycles most likely reflect precessional forcing. Current paleoceanographic

  2. Petrogenesis and depositional history of felsic pyroclastic rocks from the Melka Wakena archaeological site-complex in South central Ethiopia

    Science.gov (United States)

    Resom, Angesom; Asrat, Asfawossen; Gossa, Tegenu; Hovers, Erella

    2018-06-01

    The Melka Wakena archaeological site-complex is located at the eastern rift margin of the central sector of the Main Ethiopian Rift (MER), in south central Ethiopia. This wide, gently sloping rift shoulder, locally called the "Gadeb plain" is underlain by a succession of primary pyroclastic deposits and intercalated fluvial sediments as well as reworked volcaniclastic rocks, the top part of which is exposed by the Wabe River in the Melka Wakena area. Recent archaeological survey and excavations at this site revealed important paleoanthropological records. An integrated stratigraphic, petrological, and major and trace element geochemical study has been conducted to constrain the petrogenesis of the primary pyroclastic deposits and the depositional history of the sequence. The results revealed that the Melka Wakena pyroclastic deposits are a suite of mildly alkaline, rhyolitic pantellerites (ash falls, pumiceous ash falls and ignimbrites) and slightly dacitic ash flows. These rocks were deposited by episodic volcanic eruptions during early to middle Pleistocene from large calderas along the Wonji Fault Belt (WFB) in the central sector of the MER and from large silicic volcanic centers at the eastern rift shoulder. The rhyolitic ash falls, pumiceous ash falls and ignimbrites have been generated by fractional crystallization of a differentiating basaltic magma while the petrogenesis of the slightly dacitic ash flows involved some crustal contamination and assimilation during fractionation. Contemporaneous fluvial activities in the geomorphologically active Gadeb plain deposited overbank sedimentary sequences (archaeology bearing conglomerates and sands) along meandering river courses while a dense network of channels and streams have subsequently down-cut through the older volcanic and sedimentary sequences, redepositing the reworked volcaniclastic sediments further downstream.

  3. 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

  4. Radiological protection in interventional radiology

    International Nuclear Information System (INIS)

    Padovani, R.

    2001-01-01

    Interventional radiology (IR) reduces the need for many traditional interventions, particularly surgery, so reducing the discomfort and risk for patients compared with traditional systems. IR procedures are frequently performed by non-radiologist physicians, often without the proper radiological equipment and sufficient knowledge of radiation protection. Levels of doses to patients and staff in IR vary enormously. A poor correlation exists between patient and staff dose, and large variations of dose are reported for the same procedure. The occurrence of deterministic effects in patients is another peculiar aspect of IR owing to the potentially high skin doses of some procedures. The paper reviews the use of IR and the radiological protection of patients and staff, and examines the need for new standards for IR equipment and the training of personnel. (author)

  5. 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

  6. Pediatric radiology

    International Nuclear Information System (INIS)

    Benz-Bohm, G.

    1997-01-01

    Pediatric radiology is an important subsection of diagnostic radiology involving specific difficulties, but unfortunately is quite too often neglected as a subject of further education and training. The book therefore is not intended for specialists in the field, but for radiologists wishing to plunge deeper into the matter of pediatric radiology and to acquire a sound, basic knowledge and information about well-proven modalities, the resulting diagnostic images, and interpretation of results. The book is a compact guide and a helpful source of reference and information required for every-day work, or in special cases. With patients who are babies or children, the challenges are different. The book offers all the information needed, including important experience from pediatric hospital units that may be helpful in diagnostic evaluation, information about specific dissimilarities in anatomy and physiology which affect the imaging results, hints for radiology planning and performance, as well as information about the various techniques and their indication and achievements. The book presents a wide spectrum of informative and annotated images. (orig./CB) [de

  7. Radiologic considerations

    International Nuclear Information System (INIS)

    Judge, L.O.

    1987-01-01

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

  8. Formerly utilized MED/AEC sites remedial action program post-remedial-action radiological survey of Kent Chemical Laboratory, the University of Chicago, Chicago, IL

    International Nuclear Information System (INIS)

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

    1983-05-01

    A comprehensive radiological assessment of Kent Laboratory was conducted during September 1977, by the ANL Radiological Survey Group to determine if any radioactive contamination remained. The results of the assessment indicated the need for remedial action. Since 1977, the University has decontaminated this laboratory building, and in May 1983, the Department of Energy requested the ANL Radiological Survey Group to conduct a post-remedial-action survey. All the contaminated areas identified during the 1977 assessment were rechecked. Contamination remained in six of the rooms. Further decontamination of these areas was conducted by university personnel, and as a result, these areas are now free of contamination. However, a contaminated clay pipe in the attic remained. The clay pipe has since been removed and disposed of as solid radioactive waste. During the post-remedial-action survey, six soil samples were collected from excavation trenches dug in Rooms 1 and 2 as part of the University's remedial action efforts. Also, four sludge samples were taken from below the manhole covers in the basement of Kent Chemical Laboratory to assess the radiological condition of the sewer system. A radiological assessment of the sewer system had not been accomplished during the 1977 survey as per program direction. Radiochemical (fluorometric) and gamma-spectral analyses indicated that eight out of ten soil and sludge samples contained levels of radioactivity above expected background concentrations. The soil has since been further excavated. The building is now free of radioactive contamination in excess of background levels; however, the sewers do contain radioactive materials above background levels since contamination was found at appropriate access points. 6 references, 16 figures, 7 tables

  9. Radiologic findings of dwarfism

    Energy Technology Data Exchange (ETDEWEB)

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

    1981-06-15

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

  10. Radiologic findings of dwarfism

    International Nuclear Information System (INIS)

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

    1981-01-01

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

  11. Lessons learned in radiology

    International Nuclear Information System (INIS)

    Goodenough, D.J.

    2001-01-01

    The paper reviews aspects of the history of radiology with the goal of identifying lessons learned, particularly in the area of radiological protection of the patient in diagnostic and interventional radiology, nuclear medicine and radiotherapy. It is pointed out that since the days of Roentgen there has been a need not only to control and quantify the amount of radiation reaching the patient but also to optimize the imaging process to offer the greatest diagnostic benefit within allowable levels of patient dose. To this end, in diagnostic radiology, one finds the development of better films, X rays tubes, grids, screens and processing techniques, while in fluoroscopy, one sees the increased luminance of calcium tungstate. In interventional radiology, one finds an improvement in catheterization techniques and contrast agents. In nuclear medicine, the development of tracer techniques into modern cameras and isotopes such as technetium can be followed. In radiotherapy, one sees the early superficial X rays and radium sources gradually replaced with radon seeds, supervoltage, 60 Co and today's linear accelerators. Along with the incredible advances in imaging and therapeutic technologies comes the growing realization of the potential danger of radiation and the need to protect the patient (as well as physicians, ancillary personnel and the general population) from unnecessary radiation. The important lesson learned is that we must walk a tightrope, balancing the benefits and risks of any technology utilizing radiation to produce the greatest benefits at the lowest acceptable risk. The alternative techniques using non-ionizing radiation will have to be considered as part of the general armamentarium for medical imaging whenever radiation consequences are unacceptable. (author)

  12. 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

  13. Chest radiology

    International Nuclear Information System (INIS)

    Reed, J.C.

    1990-01-01

    This book is a reference in plain chest film diagnosis provides a thorough background in the differential diagnosis of 22 of the most common radiologic patterns of chest disease. Each chapter is introduced with problem cases and a set of questions, followed by a tabular listing of the appropriate differential considerations. The book emphasizes plain films, CT and some MR scans are integrated to demonstrate how these modalities enhance the work of a case

  14. History of the 185-/189-D thermal hydraulics laboratory and its effects on reactor operations at the Hanford Site

    International Nuclear Information System (INIS)

    Gerber, M.S.

    1994-09-01

    The 185-D deaeration building and the 189-D refrigeration building were constructed at Hanford during 1943 and 1944. Both buildings were constructed as part of the influent water cooling system for D reactor. The CMS studies eliminated the need for 185-D function. Early gains in knowledge ended the original function of the 189-D building mission. In 1951, 185-D and 189-D were converted to a thermal-hydraulic laboratory. The experiments held in the thermal-hydraulic lab lead to historic changes in Hanford reactor operations. In late 1951, the exponential physics experiments were moved to the 189-D building. In 1958, new production reactor experiments were begun in 185/189-D. In 1959, Plutonium Recycle Test Reactor experiments were added to the 185/189-D facility. By 1960, the 185/189-D thermal hydraulics laboratory was one of the few full service facilities of its type in the nation. During the years 1961--1963 tests continued in the facility in support of existing reactors, new production reactors, and the Plutonium Recycle Test Reactor. In 1969, Fast Flux Test Facility developmental testings began in the facility. Simulations in 185/189-D building aided in the N Reactor repairs in the 1980's. In 1994 the facility was nominated to the National Register of Historic Places, because of its pioneering role over many years in thermal hydraulics, flow studies, heat transfer, and other reactor coolant support work. During 1994 and 1995 it was demolished in the largest decontamination and decommissioning project thus far in Hanford Site history

  15. Late Neolithic vegetation history at the pile-dwelling site of Palù di Livenza (northeastern Italy

    Science.gov (United States)

    Pini, Roberta

    2004-12-01

    The Late Neolithic pile-dwelling of Palù di Livenza yielded archaeological remains typical of the Square Mouth Pottery and Lagozza Cultures. A palynological investigation reveals important changes in the vegetation due to anthropogenic pressure. Between ca. 6590 and 5960 cal. yr BP, dense oak wood forests with deciduous Quercus, Fagus and Corylus extended around the mire, with no signs of human impact. The establishment of the pile-dwelling, dated to ca. 5960 cal. yr BP, led to a strong reduction of forests, reclamation of wetlands, and expansion of herbaceous communities, with cultivated species, infestant weeds, nitrophilous and ruderal herbs, pastures and meadows. According to AMS dates and previous archaeological chronologies, the pile-dwelling persisted for about 700 years (from ca. 5960 to 5260 cal. yr BP). The history of the pile-dwelling after ca. 5260 cal. yr BP cannot be reconstructed because of recent contamination of the top part of the section. Rarefaction analysis was applied to estimate changes of palynological richness through time: the highest E(Tn) (between 56 and 69 taxa) are contemporaneous with the local development of the pile-dwelling. The comparison of pollen data with archaeobotanical evidence indicates that Fragaria vesca, Malus sylvestris, Papaver somniferum and Physalis alkekengi were gathered at some distance from the site and that Linum usitatissimum is strongly under-represented in pollen samples. Crop cultivation can be estimated for a radius of several hundred metres around the mire. Palù di Livenza is significant in the context of Neolithic archaeobotany of northern Italy and neighbouring countries. Copyright

  16. Infantile abuse: Radiological diagnosis

    Directory of Open Access Journals (Sweden)

    Ana Teresa Araujo Reyes

    2006-08-01

    Full Text Available Infantile abuse is a frequent problem, that must be suspected to bediagnosed, the children victims of infantile abuse can present anytype of injury, nevertheless there are associated injuries common toan inferred trauma that constitute radiological patterns highly specific for abuse, among them are the metafisial injuries, posterior costal fractures and first costal arc fractures, fractures of the toracolumbar region, fractures without apparent explanation, fractures in different stage of evolution, subdural hematoma, subarachnoid hemorrhage, intraparenquimatose contusion and diffuse axonal injury, which combined with the history of the trauma, the age, the development of mental abilities, as well as the mechanism guides the injury diagnose.

  17. Radiological diagnosis of fractures

    International Nuclear Information System (INIS)

    Finlay, D.B.L.; Allen, M.J.

    1984-01-01

    This book is about radiology of fractures. While it contains sections of clinical features it is not intended that readers should rely entirely upon these for the diagnosis and management of the injured patient. As in the diagnosis and treatment of all medical problems, fracture management must be carried out in a logical step-by-step fashion - namely, history, examination, investigation, differential diagnosis, diagnosis and then treatment. Each section deals with a specific anatomical area and begins with line drawings of the normal radiographs demonstrating the anatomy. Accessory views that may be requested, and the indications for these, are included. Any radiological pitfalls for the area in general are then described. The fractures in adults are then examined in turn, their radiological features described, and any pitfalls in their diagnosis discussed. A brief note of important clinical findings is included. A brief mention is made of pediatric fractures which are of significance and their differences to the adult pattern indicated. Although fractures can be classified into types with different characteristics, in life every fracture is individual. Fractures by and large follow common patterns, but many have variations

  18. 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

  19. 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)

  20. Evaluation of sexual history-based screening of anatomic sites for chlamydia trachomatis and neisseria gonorrhoeae infection in men having sex with men in routine practice

    Directory of Open Access Journals (Sweden)

    Jansen Casper L

    2011-07-01

    Full Text Available Abstract Background Sexually transmitted infection (STI screening programmes are implemented in many countries to decrease burden of STI and to improve sexual health. Screening for Chlamydia trachomatis and Neisseria gonorrhoeae has a prominent role in these protocols. Most of the screening programmes concerning men having sex with men (MSM are based on opportunistic urethral testing. In The Netherlands, a history-based approach is used. The aim of this study is to evaluate the protocol of screening anatomic sites for C. trachomatis and N. gonorrhoeae infection based on sexual history in MSM in routine practice in The Netherlands. Methods All MSM visiting the clinic for STI in The Hague are routinely asked about their sexual practice during consulting. As per protocol, tests for urogenital, oropharyngeal and anorectal infection are obtained based on reported site(s of sexual contact. All consultations are entered into a database as part of the national STI monitoring system. Data of an 18 months period were retrieved from this database and analysed. Results A total of 1455 consultations in MSM were registered during the study period. The prevalence of C. trachomatis and N. gonorrhoeae per anatomic site was: urethral infection 4.0% respectively and 2.8%, oropharynx 1.5% and 4.2%, and anorectum 8.2% and 6.0%. The majority of chlamydia cases (72% involved a single anatomic site, which was especially manifest for anorectal infections (79%, while 42% of gonorrhoea cases were single site. Twenty-six percent of MSM with anorectal chlamydia and 17% with anorectal gonorrhoea reported symptoms of proctitis; none of the oropharyngeal infections were symptomatic. Most cases of anorectal infection (83% and oropharyngeal infection (100% would have remained undiagnosed with a symptom-based protocol. Conclusions The current strategy of sexual-history based screening of multiple anatomic sites for chlamydia and gonorrhoea in MSM is a useful and valid guideline

  1. Diagnostic radiology 1987

    International Nuclear Information System (INIS)

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

    1987-01-01

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

  2. Pediatric radiology

    International Nuclear Information System (INIS)

    Silverman, F.N.

    1982-01-01

    A literature review with 186 references of diagnostic pediatric radiology, a speciality restricted to an age group rather than to an organ system or technique of examination, is presented. In the present chapter topics follow the basic organ system divisions with discussions of special techniques within these divisions. The diagnosis of congenital malformations, infectious diseases and neoplasms are a few of the topics discussed for the head and neck region, the vertebrae, the cardiovascular system, the respiratory system, the gastrointestinal tract, the urinary tract, and the skeleton

  3. Radiological effects

    International Nuclear Information System (INIS)

    Anon.

    1978-01-01

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

  4. Pediatric radiology

    International Nuclear Information System (INIS)

    Kirkpatrick, J.A. Jr.

    1985-01-01

    Computed tomography has made possible the excellent and basic work having to do with the characteristics of the trachea, its caliber, shape, and length in children. Another group of articles has to do with interventional pediatric radiology. This year there were a number of articles of which only a sample is included, dealing with therapeutic procedures involving drainage of abscesses, angioplasty, nephrostomy, therapeutic embolization, and the removal of esophageal foreign bodies. Obviously, there is no reason to think that techniques developed for the adult may not be applicable to the infant or child; also, there is no reason to believe that processes peculiar to the child should not be amenable to intervention, for instance, use of embolization of hepatic hemangioma and transluminal balloon valvuloplasty for pulmonary valvular stenosis. Among the reports and reviews, the author would add that sonography remains a basic imaging technique in pediatric radiology and each year its application broadens. For example, there is an excellent article having to do with sonography of the neonatal and infant hip and evaluation of the inferior vena cava and the gallbladder. Nuclear medicine continues to play a significant role in diagnosis, which is featured in two articles concerned with problems of the hip

  5. Radiological malpractice

    International Nuclear Information System (INIS)

    Bauer, G.

    1987-01-01

    As medico-legal statistics show, compared with other branches of medicine, cases of liability of the radiologist or his assistants are relatively rare. The duty to exercise due care as set out in Paragraph 6 of the Austrian penal code or Paragraph 276 of the German civil code, respectively, provide a basic rule of law also for radiology. Due to the risk inherent in the investigation method, incidents in angiography cannot be totally excluded. Therefore, it is of utmost importance that all steps be taken with regard to staff, equipment and drugs to be able to deal with any complications and incidents that may arise. The courts of law require the employer to produce strongest exonerating evidence to prove that the duty to exercise due care in the selection and supervision of the assistants has been duly fulfilled. For the practical execution of radiological investigations of the digestive tract, also the RTA is responsible; her liability when performing an irrigoscopy is particularly great, as perforation of the intestine is often lethal. The introduction of the rectal tube into the vagina by mistake, with resultant injury or death of the patient, will regularly lead to conviction under penal law. (orig.) [de

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

    International Nuclear Information System (INIS)

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

    1996-04-01

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

  7. RESRAD: an analysis method of the exposure via to ionizing radiation, used on radiological risk assessment in sites with problems of soil contamination

    International Nuclear Information System (INIS)

    Oliveira Loureiro, C. de; Yu, C.

    1995-01-01

    A microcomputer program, denominated RESRAD, was presented and described as an analytical tool to perform pathway analysis and radiological risk assessment. Nine exposure pathways are implemented in the code. They are the following: external radiation; dust inhalation; inhalation of radon; and, ingestion of plant, meat, milk, water, aquatic food, and soil. The U.S. Department of Energy (US-DOE) has recommended the use of RESRAD, as a radiological risk assessment package, for completing the pathway analysis needed to derive specific soil-guidelines and to support the ALARA evaluation. Since its conception, the RESRAD code has been continuously improved and updated to accommodate comments and suggestions from its users and to incorporate new features to improve its capability and flexibility. Version 5.0 consolidates the last major RESRAD updates. The package is intentionally user-friendly and operates with a menu system from which the user can access the data input screens, run the RESRAD calculations and view the output. (author). 4 refs, 1 fig, 1 tab

  8. Innovate the Teaching of Taiwaness History: An Application of Multimedia Distance Learning—A Web-site Construction Sample of Shih Hsin University

    Directory of Open Access Journals (Sweden)

    Shaw-Fong Lee

    2004-03-01

    Full Text Available Traditionally, the teaching of history course mostly utilizes face to face instruction and oral presentation. Along with the development of educational technology, the teaching methods could be more various such as using internet and multimedia. Literature reviews also indicate that using internet and multimedia may improve the effect of learning and teaching. This paper explores the development of a web-based instructional system for the course of Taiwanese History at Shih Hsin University.The result and the product of this development project is the web site, http://distance.shu.edu.tw/taiwan/list.htm. The content of the web-site includes instructional materials such as animations, videos, pictures, texts, historical maps, and so on. The developmental methods used in this project use curriculum design, survey, interview, review of literatures and focus group discussion.[Article content in Chinese

  9. Procedures in diagnostic radiology

    International Nuclear Information System (INIS)

    Doyle, T.; Hare, W.S.C.; Thomson, K.; Tess, B.

    1989-01-01

    This book outlines the various procedures necessary for the successful practice of diagnostic radiology. Topics covered are: general principles, imaging of the urinary and gastrointestinal tracts, vascular radiology, arthrography, and miscellaneous diagnostic radiologic procedures

  10. Radiological Characterization Technical Report on Californium-252 Sealed Source Transuranic Debris Waste for the Off-Site Source Recovery Project at Los Alamos National Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Feldman, Alexander [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2014-04-24

    This document describes the development and approach for the radiological characterization of Cf-252 sealed sources for shipment to the Waste Isolation Pilot Plant. The report combines information on the nuclear material content of each individual source (mass or activity and date of manufacture) with information and data on the radionuclide distributions within the originating nuclear material. This approach allows for complete and accurate characterization of the waste container without the need to take additional measurements. The radionuclide uncertainties, developed from acceptable knowledge (AK) information regarding the source material, are applied to the summed activities in the drum. The AK information used in the characterization of Cf-252 sealed sources has been qualified by the peer review process, which has been reviewed and accepted by the Environmental Protection Agency.

  11. 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)

  12. 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

  13. 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

  14. Radiologic protection in dental radiology

    International Nuclear Information System (INIS)

    Pacheco Jimenez, R.E.; Bermudez Jimenez, L.A.

    2000-01-01

    With this work and employing the radioprotection criterion, the authors pretend to minimize the risks associated to this practice; without losing the quality of the radiologic image. Odontology should perform the following criterions: 1. Justification: all operation of practice that implies exposition to radiations, should be reweighed, through an analysis of risks versus benefits, with the purpose to assure, that the total detriment will be small, compared to resultant benefit of this activity. 2. Optimization: all of the exposures should be maintained as low as reasonable possible, considering the social and economic factors. 3. Dose limit: any dose limit system should be considered as a top condition, nota as an admissible level. (S. Grainger)

  15. 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

  16. Total filmless digital radiology service

    International Nuclear Information System (INIS)

    Mun, S.K.; Goeringer, F.; Benson, H.; Horii, S.C.

    1989-01-01

    The completion of a comprehensive picture archiving and communication system (PACS) at Georgetown University Hospital has allowed us to identify a number of technical, administrative, personnel, and operational issues that will affect a total digital radiology service. With a hospital-wide digital imaging network system, computer simulation of communications and storage options, and economic modeling, we have developed a feasibility study and implementation strategy for the smooth transition to a nearly filmless radiology service over the next several years. This paper describes the technical and operational requirements for various database operations, workstations (used in diagnosis, review, and education), and communications. Site and installation planning, personnel training, and transition operations are discussed

  17. Radiological protection in dentistry

    Energy Technology Data Exchange (ETDEWEB)

    Holliday, B

    1974-01-01

    Information that would allow an assessment of the standard of radiological protection in dentistry in the United Kingdom is sparse. The National Radiological Protection Board (previously the Radiological Protection Service) has provided a monitoring and advisory service to dentists for many years but very limited use has been made of this service. In a recent survey, 114 dentists were visited in representative practices in South East England and it was established that only 6.5% of dentists in general practice do not use radiography as an adjunct to their practice (Smith, 1969). In the 88 x-ray sets which were examined, 24% had less than the recommended thickness of aluminium filtration, while 25% had a fixed field size which was larger than necessary for dental radiography; in addition, 27% of the timers were found to have an error of greater than 20% in repetition of the pre-set exposure time. The exposure rate at the cone tip of a dental x-ray unit is generally in the range 1 to 4 R/s. A fault in the timer unit coupled with a failure on the part of the dentist to notice that x-rays are being generated (normally indicated by a red warning light) would rapidly lead to excessive exposure of the patient. Furthermore, a dentist continually holding films in the mouth of his patient would certainly incur a dose well in excess of the permissible hand dose, assuming anaverage work load for the x-ray equipment. Three case histories are given to illustrate the type of hazard that might arise from faulty equipment or bad operating technique.

  18. Feasibility study to combine the evaluation of radiological and chemical-toxicological effects of old contaminated sites; Machbarkeitsstudie zur Verknuepfung der Bewertung radiologischer und chemisch-toxischer Wirkungen von Altlasten

    Energy Technology Data Exchange (ETDEWEB)

    Jacob, P; Proehl, G [Gesellschaft fuer Strahlen- und Umweltforschung mbH Muenchen, Neuherberg (Germany). Inst. fuer Strahlenschutz; Schneider, K; Voss, J U [FoBiG Forschungs- und Beratungsinstitut Gefahrstoffe GmbH, Freiburg im Breisgau (Germany)

    1997-08-01

    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{sup 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.) [Deutsch] In den Gebieten des ehemaligen Uranbergbaus der Bundeslaender Sachsen, Thueringen und Sachsen-Anhalt treten neben den radioaktiven Kontaminationen auch andere Schadstoffe, insbesondere Schwermetalle, auf. Fuer ionisierende Strahlung und fuer chemische Noxen existieren unabhaengig voneinander entwickelte Bewertungssysteme zum Schutz vor Gesundheitsgefahren und Empfehlungen zum Umgang mit kontaminierten Standorten. Vor diesem Hintergrund forderte die 9. Umweltministerkonferenz - Ost am 17./18. Juni 1993 eine `Verknuepfung der radiologischen und konventionellen Altlastenbewertung`. Ob diese Verknuepfung moeglich ist und in welcher Weise diese vorgenommen werden kann, ist bisher nicht untersucht worden. Diese Machbarkeitsstudie unternimmt eine Bestandsaufnahme von Uebereinstimmungen und Unterschieden der beiden bestehenden Bewertungssysteme fuer Kontaminationen mit Radionukliden und mit chemisch-toxischen Stoffen und zeigt einen Weg auf zur Verinheitlichung der

  19. Radiologically detectable musculoskeletal involvement in systemic lupus erythematosus

    International Nuclear Information System (INIS)

    Jimenez, M. M.; Manjon, P.; Diaz de Bustamante, T.; Galindo, M.; Buj, M. J.; Cabezudo, J.

    2000-01-01

    We show a wide spectrum of musculoskeletal involvement in systemic lupus erythematosus (SLE) that can be detected by radiological examination. We determined the indications of different imaging techniques in the diagnosis and follow-up of this disease. We reviewed the clinical and radiological histories of 37 patients diagnosed as having SLE on the basis of serological and musculoskeletal criteria. We assessed the personal data of each patient, the association of the disease with autoimmune processes, serology, treatment and radiological findings using plain X ray, ultrasound, computed tomography (CT) and magnetic resonance (MR). Of the 37 cases reviewed, only ten presented changes in one or more of the imaging studies performed. the most common radiological finding was symmetric poly arthritis located at different sites. Other signs included avascular necrosis (late and early), inflammation and tendon and/or ligament rupture, nonerosive deforming arthropathies , soft tissue calcifications and arthritis (staphylococcal and tuberculous). A direct correlation was established between the anticardiolipin antibody titer, steroid doses and avascular necrosis. In SLE, radiologically detectable osteoarticular lesions are uncommon. Symmetric polyarthritis is the earliest lesion and that occurring most frequently. Other signs do not appear as often, with the exception of osteonecrosis, which usually occurs late. It developed early and was unusually aggressive in two youths with elevated anticardiolipin antibody titers and substantial systemic involvement in our series. The contributions of ultrasound and MR in the assessment of musculoskeletal involvement in SLE are especially relevant in the study of inflammations and tendon rupture and in the management of avascular necrosis, respectively. (Author) 17 refs

  20. Current radiology. Volume 5

    International Nuclear Information System (INIS)

    Wilson, G.H.; Hanafee, W.N.

    1984-01-01

    This book contains 10 selections. They are: Nuclear Magnetic Resonance Imaging, Interventional Vascular Radiology, Genitourinary Radiology, Skeletal Radiology, Digital Subtraction Angiography, Neuroradiology, Computed Tomographic Evaluation of Degenerative Diseases of the Lumbar Spine, The Lung, Otolaringology and Opthalmology, and Pediatric Radiology: Cranial, Facial, Cervical, Vertebral, and Appendicular

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

    International Nuclear Information System (INIS)

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

    1982-05-01

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

  2. Evaluation of critical pathways, radionuclides, and remedial measures for reducing the radiological dose to returning populations at a former nuclear test site

    Energy Technology Data Exchange (ETDEWEB)

    Robison, W. L., LLNL

    1997-11-01

    Bikini Island, the major residence island at Bikini Atoll, was contaminated with radioactive fallout as a result of the BRAVO test conducted on March 1, 1954. We have identified the critical radionuclides and supplied radiological data needed to develop dose estimates for all possible exposure pathways. These estimates show that the major dose to returning populations would result from ingestion of cesium-137 (137 Cs) in locally grown terrestrial foods where the predicted population average effective dose exceeds current federal guidelines. Consequently, we designed several long-term field experiments to develop and evaluate methods to reduce the 137 Cs content in locally grown foods.This paper gives a general outline of the remediation experiments with a more detailed description of a preferred combined option. Our comparative evaluation on various remedial methods show that the combined option--potassium treatment of the entire islands with limited excavation of soil in village an d housing areas--will be effective in reducing the dose to about 10% of pretreatment levels, and offers very significant benefits with respect to adverse environmental impacts as well as savings in overall costs, time, and required expert resources.

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

    International Nuclear Information System (INIS)

    L.K. Roe

    2001-01-01

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

  4. Development of the re-engineered European decision support system for off-site nuclear and radiological emergencies - JRODOS. Application to air pollution transport modelling

    International Nuclear Information System (INIS)

    Ievdin, I.; Treebushny, D.; Raskob, W.; Zheleznyak, M.

    2008-01-01

    Full text: The European decision support system for nuclear and radiological emergencies RODOS includes a set of numerical models simulating the transport of radionuclides in the environment, estimating potential doses to the public and simulating and evaluating the efficiency of countermeasures. The re-engineering of the RODOS system using the Java technology has started recently which will allow to apply the new system called JRODOS on nearly any computational platform running Java virtual machine. Modern software development approaches were used for the JRODOS system architecture and implementation: distributed system design (client, management server, computational server), geo-database utilization, plug-in model structure and OpenMI-like compatibility to support seamless model inter-connection. Stable open source components such as an ORM solution (Hibernate), an OpenGIS component (Geotools) and a charting/reporting component (JFree, Pentaho) were utilized to optimize the development effort and allow a fast completion of the project. The architecture of the system is presented and illustrated for the atmospheric dispersion module ALSMC (Atmospheric Local Scale Model Chain) performing calculations of atmospheric pollution transport and the corresponding acute doses and dose rates. The example application is based on a synthetic scenario of a release from a nuclear power plant located in Europe. (author)

  5. Radiology of the esophagus

    International Nuclear Information System (INIS)

    Huepscher, D.N.

    1988-01-01

    Before the radiologist can decide on his approach to the examination, he needs clinical information and a short relevant medical history of the patient. These aspects are considered in Chapter 1. Chapter 2 covers the 'standard' examination of the esophagus, the contrast media, the relative values of the single contrast, mucosal relief and double contrast studies, the various techniques used to obtain double contrast films and, finally, several of the drugs administered during the examination. Since in cases of aspecific dysphagia the entire esophagus - including the pharynx - must be examined, this stepchild of the radiological examination is the focus of attention in Chapter 3 while an overview of the anatomy, physiology, roentgen anatomy and roentgen physiology of the esophageal body is presented in Chapter 4. Congenital abnormalities, displacement and impressions, diverticula, foreign bodies, perforation and tumors are considered in more detail in Chapters 5 to 10, respectively. The value of computed tomography for the staging of esophageal cancer is discussed in Chapter 11. Chapter 12 is devoted to the highly diversified spectrum of abnormalities of the esophageal wall. Disturbed motility is the subject of Chapter 13. In Chapter 14 the hiatal hernia, gastroesophageal reflux and its results are discussed in a somewhat broader context. In Chapter 15 the radiological aspects of the postoperative esophagus are described. (orig./MG)

  6. 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.

  7. RA radiological characterization database application

    International Nuclear Information System (INIS)

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

    2005-01-01

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

  8. 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

  9. Geology and History of Water-Containment Ponds at U12n, U12t, and U12e Tunnels, Rainier Mesa, Nevada National Security Site

    International Nuclear Information System (INIS)

    Huckins-Gang, H.; Townsend, M.

    2011-01-01

    Tunnels constructed in Rainier Mesa at the Nevada National Security Site (formerly Nevada Test Site) intersected water-producing areas (perched well above the regional groundwater system) during mining and drilling. There was enough overall sustained flow from three of the tunnel complexes (U12n, U12t, and U12e, also known as N-Tunnel, T-Tunnel, and E-Tunnel), that ponds were constructed in drainages below the portals to contain the discharged water. Water flow has now been blocked from N-Tunnel and T-Tunnel, and the ponds there are dry; however, E-Tunnel continues to produce water. The Underground Test Area Sub-Project of the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office is examining the possibility that contaminants from the tunnel complexes may be able to reach the regional groundwater flow system. Because some radiologically contaminated water was conveyed to these ponds, the ponds have been viewed as a potential source of groundwater contamination (in addition to the tunnel complexes themselves but part of the same hydrologic source term). Although the regional water table is very deep (greater than 305 meters [1,000 feet]) beneath the pond locations, some of the ponds were constructed on carbonate rocks, which some scientists think might provide a 'fast path' to the regional groundwater system. This report describes the geology and hydrologic conditions in the area of these three sets of tunnel ponds to aid in determining whether the ponds should be modeled as sources of contaminant migration. Data concerning the locations of the ponds, the volume of effluent discharged, and the concentration of tritium and other radionuclides in the water have been compiled from published and unpublished sources and included also.

  10. 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.

  11. 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

  12. Regional Radiological Security Partnership in Southeast Asia - Increasing the Sustainability of Security Systems at the Site-Level by Using a Model Facility Approach

    International Nuclear Information System (INIS)

    Chamberlain, Travis L.; Dickerson, Sarah; Ravenhill, Scott D.; Murray, Allan; Morris, Frederic A.; Herdes, Gregory A.

    2009-01-01

    In 2004, Australia, through the Australian Nuclear Science and Technology Organisation (ANSTO), created the Regional Security of Radioactive Sources (RSRS) project and partnered with the U.S. Department of Energy's Global Threat Reduction Initiative (GTRI) and the International Atomic Energy Agency (IAEA) to form the Southeast Asian Regional Radiological Security Partnership (RRSP). The intent of the RRSP is to cooperate with countries in Southeast Asia to improve the security of their radioactive sources. This Southeast Asian Partnership supports objectives to improve the security of high risk radioactive sources by raising awareness of the need and developing national programs to protect and control such materials, improve the security of such materials, and recover and condition the materials no longer in use. The RRSP has utilized many tools to meet those objectives including: provision of physical protection upgrades, awareness training, physical protection training, regulatory development, locating and recovering orphan sources, and most recently - development of model security procedures at a model facility. This paper discusses the benefits of establishing a model facility, the methods employed by the RRSP, and three of the expected outcomes of the Model Facility approach. The first expected outcome is to increase compliance with source security guidance materials and national regulations by adding context to those materials, and illustrating their impact on a facility. Second, the effectiveness of each of the tools above is increased by making them part of an integrated system. Third, the methods used to develop the model procedures establishes a sustainable process that can ultimately be transferred to all facilities beyond the model. Overall, the RRSP has utilized the Model Facility approach as an important tool to increase the security of radioactive sources, and to position facilities and countries for the long term secure management of those sources.

  13. Thermal history of the multi-well experiment (MWX) site, Piceance Creek Basin, Northwestern Colorado, derived from fission-track analysis

    International Nuclear Information System (INIS)

    Kelley, S.A.; Blackwell, D.D.

    1990-01-01

    Fission-track analysis of apatite and zircon from 19 depth intervals in two drill holes at the MWX site in the Piceance Creek Basin, Colorado, is used to determine the burial and subsequent cooling history of the Upper Cretaceous Mesaverde Group and the Paleocene Wasatch Formation. The fission-track data, as well as available temperature, vitrinite reflectance, and geological information, indicate that the sampled sediments attained maximum burial at approximately 10 Ma, with maximum temperatures in the 150-200 0 C range. After 10 Ma the sediments began to cool during erosion related to the downcutting of the Colorado River, which lies just to the north of the MWX site. The heat flow in this area has remained relatively constant for the past 10 Ma. (author)

  14. Inflammatory myofibroblastic tumor of maxilla showing sarcomatous change in an edentulous site with a history of tooth extraction following periodontitis: A case report with discussion.

    Science.gov (United States)

    Biniraj, K R; Janardhanan, Mahija

    2014-05-01

    Inflammatory myofibroblastic tumor (IMT) is a rare tumor of uncertain origin with variable biological behavior ranging from reactive lesions to highly aggressive malignancy. Oral IMTs are extremely rare and only 25 cases had been reported so far. A case of IMT with sarcomatous transformation in an extraction site with a history of tooth extraction following tooth mobility of an upper left molar tooth is presented here. The tooth was extracted following a complaint of gingival swelling and mobility of tooth. Though malignant transformation in IMTs had been documented in the extra oral sites, wide search of associated literature suggests, this is the first case of oral IMT showing malignant change associated with gingiva. The case report attempts to highlight the variant possibilities of tooth mobility other than periodontitis and the importance of assessing the primary cause of such conditions.

  15. Development of a methodology for post closure radiological risk analysis of underground waste repositories. Illustrative assessment of the Harwell site. V.1

    International Nuclear Information System (INIS)

    Gralewski, Z.A.; Kane, P.; Nicholls, D.B.

    1987-06-01

    A probabilistic risk analysis (pra) is demonstrated for a number of ground water mediated release scenarios at the Harwell Site for a hypothetical repository at a depth of about 150 metres. This is the second stage of development of an overall risk assessment methodology. A procedure for carrying out multi-scenario assessment using available probabilistic risk assessment (pra) models is presented and a general methodology for combining risk contributions is outlined. Appropriate levels of model complexity in pra are discussed. Modelling requirements for the treatment of multiple simultaneous pathways and of site evolution are outlined. Further developments of pra systems are required to increase the realism of both the models and their mode of application, and hence to improve estimates of risk. (author)

  16. 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

  17. 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.

  18. Radiological design criteria

    International Nuclear Information System (INIS)

    Selby, J.M.; Andersen, B.V.; Carter, L.A.; Waite, D.A.

    1977-01-01

    Many new nuclear facilities are unsatisfactory from a radiation protection point of view, particularly when striving to maintain occupational exposure as low as practicable 'ALAP'. Radiation protection is achieved through physical protective features supplemented by administrative controls. Adequate physical protective feature should be achieved during construction so that supplemental administrative controls may be kept simple and workable. Many nuclear facilities fall short of adequate physical protective features, thus, remedial and sometimes awkward administrative procedures are required to safely conduct work. In reviewing the various handbooks, reports and regulations which deal with radiation protection, it may be noted that there is minimal radiological design guidance for application to nuclear facilities. A set of criteria or codes covering functional areas rather than specific nuclear facility types is badly needed. The following are suggested as functional areas to be considered: characterization of the Facility; siting and access; design exposure limits; layout (people and materials flow); ventilation and effluent control; radiation protection facilities and systems. The application of such radiological design criteria early in the design process would provide some assurance that nuclear facilities will be safe, flexible, and efficient with a minimum of costly retrofitting or administrative restrictions. Criteria which we have found helpful in these functional areas is discussed together with justification for adoption of such criteria and identification of problems which still require solution

  19. Sexual Harassment in Radiology.

    Science.gov (United States)

    Camargo, Aline; Liu, Li; Yousem, David M

    2017-08-01

    To gauge the prevalence of sexual harassment (SH) and to understand the issues regarding its disclosure among radiologists. A questionnaire on ethics and SH was sent by e-mail to 1,569 radiologists and radiology trainees in an institutional database maintained for continuing medical education purposes on three separate occasions between September 17 and October 31, 2016. The link to the survey was also posted on social media sites via the authors' divisional and institutional accounts on Facebook, Twitter, Instagram, and Aunt Minnie, as well as on ACR and RSNA web blogs. Overall, 9.75% (39 of 400) respondents stated they had suffered SH, with more female (22 of 90 = 24.4%) than male victims (11 of 249 = 4.4%) (P school graduates (119 of 220 = 54.1%) were less likely than graduates from outside the United States (37 of 48 = 77.1%). Of 401 respondents to questions on SH, 28.7% (n = 115), including more women (38 of 91 = 41.8%) than men (61 of 249 = 24.5%) (P = .002), said they had witnessed SH. By percentage responding, female radiologists are more frequently victims and witnesses of sexual harassment but are less likely to report such cases. Steps need to be taken to eliminate a culture that leads radiologists to tolerate SH without addressing it. Copyright © 2017 American College of Radiology. Published by Elsevier Inc. All rights reserved.

  20. 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

  1. Fermilab History and Archives Project | Home

    Science.gov (United States)

    Special Events Early Users Meetings (1979 - 1989) The Tevatron Natural History Discoveries Technology Site Fermilab History and Archives Project Fermilab History and Archives Project Fermi National Accelerator Laboratory Home About the Archives History & Archives Online Request Contact Us Site Index

  2. Surface formation, preservation, and history of low-porosity crusts at the WAIS Divide site, West Antarctica

    Science.gov (United States)

    Fegyveresi, John M.; Alley, Richard B.; Muto, Atsuhiro; Orsi, Anaïs J.; Spencer, Matthew K.

    2018-01-01

    Observations at the West Antarctic Ice Sheet (WAIS) Divide site show that near-surface snow is strongly altered by weather-related processes such as strong winds and temperature fluctuations, producing features that are recognizable in the deep ice core. Prominent glazed surface crusts develop frequently at the site during summer seasons. Surface, snow pit, and ice core observations made in this study during summer field seasons from 2008-2009 to 2012-2013, supplemented by automated weather station (AWS) data with short- and longwave radiation sensors, revealed that such crusts formed during relatively low-wind, low-humidity, clear-sky periods with intense daytime sunshine. After formation, such glazed surfaces typically developed cracks in a polygonal pattern likely from thermal contraction at night. Cracking was commonest when several clear days occurred in succession and was generally followed by surface hoar growth; vapor escaping through the cracks during sunny days may have contributed to the high humidity that favored nighttime formation of surface hoar. Temperature and radiation observations show that daytime solar heating often warmed the near-surface snow above the air temperature, contributing to upward mass transfer, favoring crust formation from below, and then surface hoar formation. A simple surface energy calculation supports this observation. Subsequent examination of the WDC06A deep ice core revealed that crusts are preserved through the bubbly ice, and some occur in snow accumulated during winters, although not as commonly as in summertime deposits. Although no one has been on site to observe crust formation during winter, it may be favored by greater wintertime wind packing from stronger peak winds, high temperatures and steep temperature gradients from rapid midwinter warmings reaching as high as -15 °C, and perhaps longer intervals of surface stability. Time variations in crust occurrence in the core may provide paleoclimatic information

  3. Formerly utilized MED/AEC sites Remedial Action Program: radiological survey of the Bayo Canyon, Los Alamos, New Mexico. Final report

    International Nuclear Information System (INIS)

    Mayfield, D.L.; Stoker, A.K.; Ahlquist, A.J.

    1979-06-01

    A portion of Bayo Canyon, located in Los Alamos County in north-central New Mexico, was used between 1944 and 1961 as a site for experiments employing conventional high explosives in conjunction with research on nuclear weapons development. Radiochemistry operations conducted at the site resulted in the generation of liquid and solid radioactive wastes, which were disposed into subsurface pits and leaching fields. The site was decommissioned by 1963. The resurvey utilized information from a number of routine and special environmental surveillance studies as well as extensive new instrumental measurements, soil sampling, and radiochemical analyses. Results showed that residual surface contamination due to 90 Sr averaged about 1.4 pCi/g or approximately 3 times the level attributable to worldwide fallout. Surface uranium averaged about 4.9 μg/g or about 1.5 times the amount naturally present in the volcanic-derived soils of the area. Subsurface contamination associated with the former waste disposal locations is largely confined within a total area of about 10,000 m 2 and down to depths of about 5 m. Of 378 subsurface samples, fewer than 12% exceeded 13 pCi/g of gross beta activity, which is comparable to the upper range of activities for uncontaminated local soils. Health physics interpretation of the data indicates that the present population of Los Alamos living on mesas adjacent to Bayo Canyon is not receiving any incremental radiation doses due to the residual contamination. Potential future land uses of Bayo Canyon include development of a residential area

  4. Development of a computer code system for selecting off-site protective action in radiological accidents based on the multiobjective optimization method

    International Nuclear Information System (INIS)

    Ishigami, Tsutomu; Oyama, Kazuo

    1989-09-01

    This report presents a new method to support selection of off-site protective action in nuclear reactor accidents, and provides a user's manual of a computer code system, PRASMA, developed using the method. The PRASMA code system gives several candidates of protective action zones of evacuation, sheltering and no action based on the multiobjective optimization method, which requires objective functions and decision variables. We have assigned population risks of fatality, injury and cost as the objective functions, and distance from a nuclear power plant characterizing the above three protective action zones as the decision variables. (author)

  5. Evaluation of environmental radiological impact of {sup 137} Cs repository area, site of Abadia de Goias, using the RESRAD model; Avaliacao do impacto radiologico ambiental na area do repositorio de {sup 137} Cs, em Abadia de Goias, utilizando o modelo RESRAD

    Energy Technology Data Exchange (ETDEWEB)

    Oliveira Loureiro, C. de [Minas Gerais Univ., Belo Horizonte, MG (Brazil). Escola de Engenharia; Aquino Branco, O.E. de [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN), Belo Horizonte, MG (Brazil)

    1995-12-31

    Radiological impacts under a conservative approach were assessed for the final deposition of {sup 137} Cs at the repository site of Abadia de Goias, in the State of Goias. This site was selected as the definitive storage location for the wastes generated in the radiological accident occurred in the definitive storage location for the wastes generated in the radiological accident occurred in the nearby city of Goiania, in September of 1987. The wastes are composed of various different materials, with an estimated radioactive inventory of about 1250 Ci of {sup 137} Cs, and will be deposited definitively in a repository box of concrete with a volume of 3900 m{sup 3} approximately. A conservative approach was considered in this study and the contaminated zone was simplified as an isotropic block of soil, of 3900 m{sup 3} of volume, containing 1250 Ci of {sup 137} Cs homogeneously distributed within the whole volume. Several potential exposure scenarios were considered for the assessment of the future radiological impacts predicted at the repository site, depending on the level of institutional control maintained at the site, its future use, the time spent at the site and the sources of food. A comparative analysis of the resulting radiological impacts from all these future potential scenarios was performed using a microcomputer program named RESRAD. The simulated results indicated that the external exposure to gamma radiation, directly from the contaminated soil, is the most significant exposure pathway. The maximum predicted annual dose was below 7 mrem. (author). 5 refs, 6 figs, 3 tabs.

  6. 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

  7. Integrated Geophysical and Aerial Sensing Methods for Archaeology: A Case History in the Punic Site of Villamar (Sardinia, Italy

    Directory of Open Access Journals (Sweden)

    Carlo Piga

    2014-11-01

    Full Text Available In this paper, the authors present a recent integrated survey carried out on an archaeological urban site, generally free of buildings, except some temporary structures related to excavated areas where multi-chamber tombs were found. The two methods used to investigate this site were thermal infrared and ground penetrating radar (GPR. The thermography was carried out with the sensor mounted under a helium balloon simultaneously with a photographic camera. In order to have a synthetic view of the surface thermal behavior, a simplified version of the existing night thermal gradient algorithm was applied. By this approach, we have a wide extension of thermal maps due to the balloon oscillation, because we are able to compute the maps despite collecting few acquisition samples. By the integration of GPR and the thermal imaging, we can evaluate the depth of the thermal influence of possible archaeological targets, such as buried Punic tombs or walls belonging to the succeeding medieval buildings, which have been subsequently destroyed. The thermal anomalies present correspondences to the radar time slices obtained from 30 to 50 cm. Furthermore, by superimposing historical aerial pictures on the GPR and thermal imaging data, we can identify these anomalies as the foundations of the destroyed buildings.

  8. Polyphase serpentinization history of Mariana forearc mantle: observations on the microfabric of ultramafic clasts from ODP Leg 195, Site 1200

    Science.gov (United States)

    Kahl, Wolf-Achim; Jöns, Niels; Bach, Wolfgang; Klein, Frieder

    2013-04-01

    In the forearc of the Mariana subduction zone system, a number of seamounts form from extrusion of blueschist and serpentine mud. Ocean Drilling Program Leg 195 drilled the South Chamorro seamount, where ultramafic clasts occur within the mud matrix. These clasts show a complex serpentinization history, which bears the potential for tracking the alteration history during uplift and cooling of mantle wedge rocks to the seafloor. Moreover, the microfabrics of the highly serpentinized harzburgite and dunite clasts exhibit evidence for multiple fracturing events in the forearc mantle. These, in turn, lead to fluid influx and varied styles of serpentinization of harzburgite and dunite. The serpentinized ultramafic clasts exhibit a variety of microfabrics that range from virtually undeformed to strongly deformed samples. Pervasively serpentinized harzburgites feature either an equigranular fabric of serpentinized olivine and orthopyroxene crystals, or different vein generations related to multiple stages of serpentinization. Several types of fluid pathways in harzburgites are present: (i) veins containing brucite and iron oxides, developed linearly without marked conformance with the rock fabric. In places, these veins developed mm-cm wide halos with finger-shaped serpentinization fronts. Veins of type (i) are either developed as syntaxial veins from a single crack-seal event with large magnetite crystals growing from one wall to the other (as confirmed with high-resolution X-ray microtomography), or formed by multiple fluid events. (ii) serpentine veins that encompass regions of marginally serpentinized, microgranular olivine and large orthopyroxene crystals. (iii) extensional serpentine veins (known as "Frankenstein" type). In the clasts studied, their occurrence is restricted to the halo region of type (i) veins. (iv) as a late-stage feature, extensional veins documenting multiple crack-seal events can be present in the serpentinites (either in undeformed regions with

  9. Screening for renal insufficiency following ESUR (European Society of Urogenital Radiology) guidelines with on-site creatinine measurements in an outpatient setting

    International Nuclear Information System (INIS)

    Ledermann, H.P.; Mengiardi, B.; Schmid, A.; Froehlich, J.M.

    2010-01-01

    To report the results and implications for workflow following introduction of ESUR guidelines to screen for potential renal insufficiency (RI) in private practice with on-site creatinine measurements. A total of 1,766 consecutive outpatients scheduled for contrast-enhanced CT (CECT) completed the ESUR questionnaire enquiring about kidney disease, renal surgery, proteinuria, diabetes mellitus, hypertension, gout or use of nephrotoxic drugs. Patients with positive risk factors underwent on-site creatinine measurement and calculation of estimated glomerular filtration rate (eGFR). Attending radiologists adapted subsequent imaging depending on renal function and presence of risk factors. One or more ESUR risk factors were present in 796 (45.1%) patients, including hypertension (37.7%), nephrotoxic medication (21.3%), diabetes mellitus (8.0%), proteinuria (3.9%), renal disease (4.1%), gout (3.1%) and renal surgery (2.6%). Pre-procedural creatinine measurements revealed severe RI (eGFR -1 1.73 m -2 ) in 10 (1.3%) and moderate RI (eGFR 30-59 ml min -1 1.73 m -2 ) in 106 (13.8%). Imaging work-up was adapted in 132 (16.6%) as follows: reduction of contrast material dose (n = 85), CT without contrast (n = 40), changeover to MRI (n = 3) or scintigraphy (n = 4). Screening for RI following ESUR guidelines requires creatinine measurements in nearly half of outpatients scheduled for CECT and reveals moderate to severe renal impairment in 6.6%. (orig.)

  10. Film and History.

    Science.gov (United States)

    Schaber, Robin L.

    2002-01-01

    Provides an annotated bibliography of Web sites that focus on using film to teach history. Includes Web sites in five areas: (1) film and education; (2) history of cinema; (3) film and history resources; (4) film and women; and (5) film organizations. (CMK)

  11. Impact of radiation history, gender and age on bone quality in sites for orthodontic skeletal anchorage device placement.

    Science.gov (United States)

    Konermann, A; Appel, T; Wenghoefer, M; Sirokay, S; Dirk, C; Jäger, A; Götz, W

    2015-05-01

    Stability of orthodontic miniscrew implants is prerequisite to their success and durability in orthodontic treatment. As investigations revealed a positive correlation of miniscrew stability to periimplant bone quality, it has been the aim of this study to analyze the bone structure of resection preparations of human mandibles histologically by investigating the samples according to age, gender and exposure to radiotherapy. Inflammation- and tumor-free alveolar bone sections from human mandibles (n = 31) with previously diagnosed carcinoma, chronic osteomyelitis or cysts were analyzed histomorphologically and histomorphometrically as to the dimension of trabeculae in cancellous areas. Group A investigated the impact of a history of radiation therapy, group B of gender and group C contrasted biopsies from individuals aging under 60 or over 60 years. Statistics were performed using the Kruskal-Wallis-test. Radiation, gender and age did not significantly influence bone density. The mean bone density averaged 40.7 ± 15.0% of spongiosa for the total collective with a median age of 58.4 years ± 14.7 years. Our findings provide new information on bone quality, thus contributing to a more precise evaluation of the parameters affecting and those not affecting miniscrew implant stability. On the basis of these results, the formulation of clinical guidelines for risk assessment of therapeutic approaches in patients prior to insertion of orthodontic skeletal anchorage devices seems to be conceivable. Copyright © 2014 Elsevier GmbH. All rights reserved.

  12. Formerly utilized MED/AEC sites remedial action program. Radiological survey of Universal Cyclopes, Inc., Titusville, Plant (formerly Vulcan Crucible Steel Company, Aliquippa, Pennsylvania, May 2-8, 1978)

    International Nuclear Information System (INIS)

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

    1982-05-01

    A radiological survey was conducted at the Universal Cyclops, Inc. Titusville Plant (formerly Vulcan Crucible Steel Company), in Aliquippa, Pennsylvania, to determine the location and quantities of any radioactive materials remaining on the site as a result of MED/AEC activities in the late 1940s. This facility was used for rolling uranium billets during the MED/AEC era. The survey included measurements of alpha and beta-gamma contamination, both fixed and removable; beta-gamma exposure readings at contact and at 1 m (3 ft) above the floor or ground level; and measurements of the concentrations of radon daughters in air and concentrations of 137 Cs, the 232 Th decay chain, the 226 Ra decay chain, and uranium in the soil on the site. Fourteen spots of contamination exceeded the allowable limits for natural uranium. Under current use conditions, the potential for radiation exposure of occupants of the building from these sources of contamination is remote. Concentrations of radon daughters were below the 0.01 WL limit. Calculated radon concentrations based on the radon-daughter determinations ranged from 0.11 to 0.27 pCi/l. The concentration guide for 222 Rn in uncontrolled areas is 3 pCi/l. Analysis of soil samples from the site indicated elevated concentrations of uranium (15.1 +- 0.7 to 109.0 +- 5.5 pCi/g) at one sampling location near the building. There currently are no regulatory limits for uranium concentration in soil, but, a proposed guide value is pCi/g. After evaluation of results of the survey, it was concluded that although some areas of the Universal Cyclops facility are contaminated, these areas do not pose a significant risk to the present occupants of the building. Nonetheless, in a few cases the contamination does exceed accepted guidelines. Remedial measures are indicated to bring the contaminated areas within the guidelines

  13. 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

  14. Surface formation, preservation, and history of low-porosity crusts at the WAIS Divide site, West Antarctica

    Directory of Open Access Journals (Sweden)

    J. M. Fegyveresi

    2018-01-01

    Full Text Available Observations at the West Antarctic Ice Sheet (WAIS Divide site show that near-surface snow is strongly altered by weather-related processes such as strong winds and temperature fluctuations, producing features that are recognizable in the deep ice core. Prominent glazed surface crusts develop frequently at the site during summer seasons. Surface, snow pit, and ice core observations made in this study during summer field seasons from 2008–2009 to 2012–2013, supplemented by automated weather station (AWS data with short- and longwave radiation sensors, revealed that such crusts formed during relatively low-wind, low-humidity, clear-sky periods with intense daytime sunshine. After formation, such glazed surfaces typically developed cracks in a polygonal pattern likely from thermal contraction at night. Cracking was commonest when several clear days occurred in succession and was generally followed by surface hoar growth; vapor escaping through the cracks during sunny days may have contributed to the high humidity that favored nighttime formation of surface hoar. Temperature and radiation observations show that daytime solar heating often warmed the near-surface snow above the air temperature, contributing to upward mass transfer, favoring crust formation from below, and then surface hoar formation. A simple surface energy calculation supports this observation. Subsequent examination of the WDC06A deep ice core revealed that crusts are preserved through the bubbly ice, and some occur in snow accumulated during winters, although not as commonly as in summertime deposits. Although no one has been on site to observe crust formation during winter, it may be favored by greater wintertime wind packing from stronger peak winds, high temperatures and steep temperature gradients from rapid midwinter warmings reaching as high as −15 °C, and perhaps longer intervals of surface stability. Time variations in crust occurrence in the core may provide

  15. 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

  16. Radiological impact of exposure to radon-thoron and their progeny present in the environment of fly ash dumping site in Faridabad (Haryana)

    International Nuclear Information System (INIS)

    Gupta, Nitin; Kant, Krishan; Garg, Maneesha

    2013-01-01

    Radon-Thoron and their Progeny monitoring was carried out in dwellings near fly ash dumping sites in Faridabad (Haryana), as it is very important from health and hygiene point of view of the occupants. For the measurements, the track etch technique was used. The dosimeter employed for the measurement consisted of twin chamber systems with LR-115 Type II SSNTDs placed on the two sides of the central partition inside the cup and a bare film placed outside it. The detectors were exposed in the mixed field of radon-thoron in the environment of dwellings. The detectors were placed in about 100 dwellings and the choice of the dwelling was random. The value of PAEC, radon concentration, annual exposure, annual effective dose in the dwellings near fly ash dumping sites in District Faridabad (Haryana) varied from 1.34 mWL to 14.05 mWL with an average value of (4.95 0.85) mWL, 12.41 Bqm -3 to 129.91 Bqm -3 with an average value of (45.77 7.87) Bqm -3 , 0.55 10 -1 WLM to 5.83 10 -1 WLM with an average value of (2.04 0.28) 10 -1 WLM and 0.21 mSv to 2.23 mSv with an average value of (0.79 0.13) mSv. The value of PAEC, thoron concentration, annual exposure, annual effective dose in the dwellings near fly ash dumping sites in District Faridabad (Haryana) varied from 1.34 mWL to 14.0 SmWL with an average value of (4.95 0.85) mWL, 1.16 Bq/m 3 to 65.08 Bq/m 3 with an average value of (32.77 7.87) Bqm -3 , 0.55 10 -1 WLM to 5.83 10 -1 WLM with an average value of (2.04 0.28) 10 -1 WLM and 0.21 mSv to 2.23 mSv with an average value of (0.79 0.13) mSv. The measurements indicate that the radon concentration was below the safety levels (action levels) as recommended by various regulatory bodies. The maximum value of 129.91 Bqm -3 was found in a cave inside a temple, where there was no ventilation. The different values of radon concentrations are due to different ventilation conditions and house structures. The radon concentration was found to decrease with the increase in distance of the

  17. Screening for renal insufficiency following ESUR (European Society of Urogenital Radiology) guidelines with on-site creatinine measurements in an outpatient setting

    Energy Technology Data Exchange (ETDEWEB)

    Ledermann, H.P.; Mengiardi, B.; Schmid, A. [IMAMED Radiologie Nordwest, Basel (Switzerland); Froehlich, J.M. [Guerbet AG, Medical Affairs, Zurich (Switzerland); University of Bern, Radiology Department, Bern (Switzerland)

    2010-08-15

    To report the results and implications for workflow following introduction of ESUR guidelines to screen for potential renal insufficiency (RI) in private practice with on-site creatinine measurements. A total of 1,766 consecutive outpatients scheduled for contrast-enhanced CT (CECT) completed the ESUR questionnaire enquiring about kidney disease, renal surgery, proteinuria, diabetes mellitus, hypertension, gout or use of nephrotoxic drugs. Patients with positive risk factors underwent on-site creatinine measurement and calculation of estimated glomerular filtration rate (eGFR). Attending radiologists adapted subsequent imaging depending on renal function and presence of risk factors. One or more ESUR risk factors were present in 796 (45.1%) patients, including hypertension (37.7%), nephrotoxic medication (21.3%), diabetes mellitus (8.0%), proteinuria (3.9%), renal disease (4.1%), gout (3.1%) and renal surgery (2.6%). Pre-procedural creatinine measurements revealed severe RI (eGFR < 30 ml min{sup -1} 1.73 m{sup -2}) in 10 (1.3%) and moderate RI (eGFR 30-59 ml min{sup -1} 1.73 m{sup -2}) in 106 (13.8%). Imaging work-up was adapted in 132 (16.6%) as follows: reduction of contrast material dose (n = 85), CT without contrast (n = 40), changeover to MRI (n = 3) or scintigraphy (n = 4). Screening for RI following ESUR guidelines requires creatinine measurements in nearly half of outpatients scheduled for CECT and reveals moderate to severe renal impairment in 6.6%. (orig.)

  18. 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.)

  19. Radiological diagnostics in hyperparathyroidism

    International Nuclear Information System (INIS)

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

    1991-01-01

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

  20. 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.

  1. Soil Radiological Characterisation Methodology

    International Nuclear Information System (INIS)

    Attiogbe, Julien; Aubonnet, Emilie; De Maquille, Laurence; De Moura, Patrick; Desnoyers, Yvon; Dubot, Didier; Feret, Bruno; Fichet, Pascal; Granier, Guy; Iooss, Bertrand; Nokhamzon, Jean-Guy; Ollivier Dehaye, Catherine; Pillette-Cousin, Lucien; Savary, Alain

    2014-12-01

    This report presents the general methodology and best practice approaches which combine proven existing techniques for sampling and characterisation to assess the contamination of soils prior to remediation. It is based on feedback of projects conducted by main French nuclear stakeholders involved in the field of remediation and dismantling (EDF, CEA, AREVA and IRSN). The application of this methodology will enable the project managers to obtain the elements necessary for the drawing up of files associated with remediation operations, as required by the regulatory authorities. It is applicable to each of the steps necessary for the piloting of remediation work-sites, depending on the objectives targeted (release into the public domain, re-use, etc.). The main part describes the applied statistical methodology with the exploratory analysis and variogram data, identification of singular points and their location. The results obtained permit assessment of a mapping to identify the contaminated surface and subsurface areas. It stakes the way for radiological site characterisation since the initial investigations from historical and functional analysis to check that the remediation objectives have been met. It follows an example application from the feedback of the remediation of a contaminated site on the Fontenay aux Roses facility. It is supplemented by a glossary of main terms used in the field from different publications or international standards. This technical report is a support of the ISO Standard ISO ISO/TC 85/SC 5 N 18557 'Sampling and characterisation principles for soils, buildings and infrastructures contaminated by radionuclides for remediation purposes'. (authors) [fr

  2. Radiological contribution to skeletal changes in systemic mastocytosis - urticaria pigmentosa

    Energy Technology Data Exchange (ETDEWEB)

    Schratter, M.; Canigiani, G.; Schoenbauer, C.; Mach, K.

    1983-11-01

    Three patients are demonstrated suffering from systemic mastocytosis with skin and skeletal involvement. History, clinical and radiological results are reported. After a brief analysis of the pathogenetic mechanism, the radiological findings on the skeletal system in systemic mastocytosis are discussed. Finally, roentgenological differential diagnosis of the osseous lesions is explained.

  3. 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.

  4. 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

  5. Radiology systems architecture.

    Science.gov (United States)

    Deibel, S R; Greenes, R A

    1996-05-01

    This article focuses on the software requirements for enterprise integration in radiology. The needs of a future radiology systems architecture are examined, both at a concrete functional level and at an abstract system-properties level. A component-based approach to software development is described and is validated in the context of each of the abstract system requirements for future radiology computing environments.

  6. NOAA History - Main Page

    Science.gov (United States)

    NOAA History Banner gold bar divider home - takes you to index page about the site contacts noaa americas science and service noaa legacy 1807 - 2007 NOAA History is an intrinsic part of the history of Initiative scroll divider More NOAA History from Around the Nation scroll divider drawing of a tornado NOAA

  7. 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.

  8. Effect of pruning history on growth and dry mass partitioning of jatropha on a plantation site in Madagascar

    International Nuclear Information System (INIS)

    Rajaona, Arisoa M.; Brueck, Holger; Asch, Folkard

    2011-01-01

    While technical aspects of oil processing of seeds of jatropha are under intensive investigation, comparably little is known about the performance of jatropha in the field. We investigated the effects of water availability (rainfed versus irrigated) and pruning-induced differences in plant stature on growth, biomass partitioning, and canopy size at a plantation site in Madagascar in 2010. Plants of different pruning types differed in trunk height (43 versus 29 cm) and primary branches total length (171 versus 310 cm). The two pruning types had effects on dry mass formation and leaf area projection (LAP) during the vegetation period. Trees which had a shorter trunk and longer lateral branches produced more biomass and had a higher LAP. Total dry mass formation varied from 489 to 912 g m −2 and LAP from 3.26 to 7.37. Total aboveground biomass increased from 2.3 ± 0.5 to 4.89 ± 1.4 kg tree −1 and from 4.6 ± 1.8 to 8.9 ± 1.0 kg tree −1 for the pruning types with shorter and longer lateral branches, respectively. Growth of twigs and leaves was positively correlated with total length of branches. Relative dry mass allocation to branches, twigs and leaves, length of twigs per cm of branches and specific leaf area (13.57 ± 0.72 m 2 kg −1 ) were not affected by pruning and water supply. Trees with shorter branches had higher LAD. Results indicate that pruning type should be considered as a management tool to optimize biomass production. Detailed studies on effects of canopy size and shape on radiation interception and growth are required to improve the productivity of jatropha. -- Highlights: ▶ Correlation between branch length and newly formed twigs and leaves. ▶ Comparison of LAI and leaf area density in the field. ▶ Twigs per unit length of branches.

  9. Decision Strategy: Radiological Evaluations: Air

    Energy Technology Data Exchange (ETDEWEB)

    Sohier, A

    2000-07-01

    The objectives of SCK-CEN's R and D programme on off-site emergency management are (1) to improve methods to assess in real time the radiological impact to the population and the environment during a nuclear emergency; (2) to support and advise the Belgian authorities on specific problems concerning existing and potential hazards from exposure to ionising radiation in normal and accidental conditions; (3) to organise training courses on off-site emergency response to nuclear accidents. Main achievements in 1999 are reported on.

  10. Decision Strategy: Radiological Evaluations: Air

    International Nuclear Information System (INIS)

    Sohier, A.

    2000-01-01

    The objectives of SCK-CEN's R and D programme on off-site emergency management are (1) to improve methods to assess in real time the radiological impact to the population and the environment during a nuclear emergency; (2) to support and advise the Belgian authorities on specific problems concerning existing and potential hazards from exposure to ionising radiation in normal and accidental conditions; (3) to organise training courses on off-site emergency response to nuclear accidents. Main achievements in 1999 are reported on

  11. Radiology and fine art.

    Science.gov (United States)

    Marinković, Slobodan; Stošić-Opinćal, Tatjana; Tomić, Oliver

    2012-07-01

    The radiologic aesthetics of some body parts and internal organs have inspired certain artists to create specific works of art. Our aim was to describe the link between radiology and fine art. We explored 13,625 artworks in the literature produced by 2049 artists and found several thousand photographs in an online image search. The examination revealed 271 radiologic artworks (1.99%) created by 59 artists (2.88%) who mainly applied radiography, sonography, CT, and MRI. Some authors produced radiologic artistic photographs, and others used radiologic images to create artful compositions, specific sculptures, or digital works. Many radiologic artworks have symbolic, metaphoric, or conceptual connotations. Radiology is clearly becoming an original and important field of modern art.

  12. Soft tissue Burkitt's lymphoma: radiological findings

    International Nuclear Information System (INIS)

    Garcia-Barredo, R.; Fernandez Echevarria, M.A.; Riego, M. del; Canga, A.

    1998-01-01

    An unusual case is reported of a soft tissue mass in the lower extremity, without bone involvement, in an 85-year-old woman; the histopathological diagnosis was Burkitt's lymphoma. Pertinent clinical history, histological examination, and imaging procedures allowed early diagnosis. To our knowledge, the radiological findings in Burkitt's lymphoma with this unusual clinical presentation have not been described previously. (orig.)

  13. Late Pleistocene Age Model for Site U1460, Perth Basin, SW Australian Shelf: Implications for Leeuwin Current History

    Science.gov (United States)

    Christensen, B. A.; Takayanagi, H.; Petrick, B.; Ishiwa, T.; Henderiks, J.; Groeneveld, J.; Mamo, B. L.; De Vleeschouwer, D.; Auer, G.; Deik, H.; Fulthorpe, C.; Gallagher, S. J.; McHugh, C.; Reuning, L.; Yokoyama, Y.

    2017-12-01

    The Leeuwin Current (LC) exerts an important control on modern Australian climate, but its onset is not well defined. The LC is the only southward flowing eastern boundary current. Driven by a pressure gradient set up in the Indonesian Throughflow, its warm waters support reefs to 29°S. It is seasonally controlled south of the Western Cape. Determination of the onset of the LC was a major objective of IODP Expedition 356. Expedition 356 drilling on the western Australian margin provides an opportunity to explore depositional patterns and timing in the region influenced by the current. Site U1460 was drilled in 214.5 m w.d. (Gallagher et al., 2017). Integrated calcareous nannofossil and planktonic foraminiferal biostratigraphy places the upper 86.5 m firmly within the late Pleistocene. However, the glacial- interglacial stratigraphy is uncertain because of the complexity of this shelfal depositional environment. Here we present a likely late Pleistocene stratigraphy based on integrated geochemical and paleontological datasets. A benthic foraminifer (Uvigerina peregrina) stable isotope record provides the foundation for the age model and the data are supported by SST estimates based on Tex86 and alkenones. Our age model places MIS 16 between 104 and 99 m-CSF-A, followed by an expanded MIS 15 section (99 - 50 m-CSF-A). We correlate the interval from 50 - 5 m-CSF-A with MIS 14 to MIS 8, with the largest magnitude glacial events (MIS 12, MIS 6) either condensed or represented as depositional hiatuses. A Recent 14C date at 0.34 mbsf constrains the interval from 2 - 0.5 m-CSF-A to MIS 4-3, which is in good agreement with the base of common Emiliania huxleyi (0.09 Ma) at 2.13 m-CSF-A. Thus MIS 5 is equivalent to the interval from 5 to 2 m-CSF-A. The expanded MIS 15 section follows a geometric change from slope to prograding shelf. It is associated with a shift to infaunal benthic foraminiferal assemblages, abundant sponge spicules, and a reduction in CaCO3%, suggesting

  14. Occupational radiological protection in diagnostic radiology

    International Nuclear Information System (INIS)

    Mota, H.C.

    1983-01-01

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

  15. 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

  16. 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

  17. Surgical site infections

    African Journals Online (AJOL)

    Surgical site infections (SSIs) are a worldwide problem that has ... deep tissue is found on clinical examination, re-opening, histopathological or radiological investigation ..... Esposito S, Immune system and SSI, Journal of Chemotherapy, 2001.

  18. Cardiac radiology: centenary review.

    Science.gov (United States)

    de Roos, Albert; Higgins, Charles B

    2014-11-01

    During the past century, cardiac imaging technologies have revolutionized the diagnosis and treatment of acquired and congenital heart disease. Many important contributions to the field of cardiac imaging were initially reported in Radiology. The field developed from the early stages of cardiac imaging, including the use of coronary x-ray angiography and roentgen kymography, to nowadays the widely used echocardiographic, nuclear medicine, cardiac computed tomographic (CT), and magnetic resonance (MR) applications. It is surprising how many of these techniques were not recognized for their potential during their early inception. Some techniques were described in the literature but required many years to enter the clinical arena and presently continue to expand in terms of clinical application. The application of various CT and MR contrast agents for the diagnosis of myocardial ischemia is a case in point, as the utility of contrast agents continues to expand the noninvasive characterization of myocardium. The history of cardiac imaging has included a continuous process of advances in our understanding of the anatomy and physiology of the cardiovascular system, along with advances in imaging technology that continue to the present day.

  19. Site operations

    International Nuclear Information System (INIS)

    House, W.B.; Ebenhack, D.G.

    1989-01-01

    This chapter is a discussion of the management and operations practices used at the Barnwell Waste Management Facility in Barnwell, SC. The following topics are discussed: (1) Waste receiving and inspection, including manifest and certificates of compliance, radiological surveys, disposition of nonconforming items, and decontamination and disposition of secondary waste streams; (2) Waste disposal, including Title 10 CFR 61 requirements, disposal area evaluations, shipment offloading, container emplacement, and radiation protection; (3) Trench closure, including trench backfilling, trench capping, and permanent markers; (4) Site maintenance and stabilization, including trench maintenance, surface water management, and site closure activities; (5) Site monitoring programs, including operational monitoring, and environmental monitoring program; (6) Personnel training and qualifications, including basic training program, safety training program, special skills training, and physical qualifications; (7) Records management, including waste records, personnel training records, personnel dosimetry records, site monitoring records, trench qualification and construction records, and site drawings and stabilization records; (8) Site security; (9) Emergency response plans; and (10) Quality assurance

  20. Report writing in skeletal radiology

    International Nuclear Information System (INIS)

    Rowe, L.J.; Yochum, T.R.

    1987-01-01

    The formulation of reports in clinical practice is a standard method of documentation of a patient's history, examination findings, therapeutic regime, and prognosis, as well as other important features. In the practice of producing and interpreting diagnostic radiographs, report writing also serves a number of important roles, which include providing an accurate means of recording findings in instances of 1) medicolegal circumstances; 2) a standard for comparison with previous or later examinations; 3) a permanent record if the radiographs are lost or not immediately available for perusal; 4) communication with other practitioners and health professionals; and 5) expediating the treatment regime by providing a resume of important indications and contraindictions for therapy. In the radiological literature there is a distinct lack of material on report writing and very little as to what would be considered a standard style. Consequently, radiological reporting has increasingly become a subjective, personalized procedure, with each individual modifying the report according to previous training, experience, and needs. It is the purpose of this chapter to provide basic guidelines on the mechanisms of formulating adequate standardized reports in radiological examinations of the skeletal system

  1. Fifty years of radiological protection

    International Nuclear Information System (INIS)

    2007-01-01

    On 21 March 1957, the Steering Committee for Nuclear Energy of the Organisation for European Economic Co-operation established the Working Party on Public Health and Safety. From this early date onwards, radiological protection formed a central part of the work of what was to become the OECD Nuclear Energy Agency. Now, 50 years later, the Committee on Radiation Protection and Public Health (CRPPH) has commissioned this historical review of half a century of work and accomplishments. Over this period, the key topics in radiological protection have been identified, debated and addressed by the CRPPH. This report brings this history to life, presenting the major questions in the context of their time, and of the personalities who worked to address them. The developments and views of the past condition how we are able to assess and manage radiological risks today, as well as how we may adjust to challenges that will or could emerge in the coming years. This heritage is thus an important element for the CRPPH to consider as it looks forward to its next 50 years of accomplishments. (author)

  2. 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)

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

    DEFF Research Database (Denmark)

    Andersen, Poul Erik

    2011-01-01

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

  4. 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)

  5. Socioeconomic trends in radiology

    International Nuclear Information System (INIS)

    Barneveld Binkhuysen, F.H.

    1998-01-01

    For radiology the socioeconomic environment is a topic of increasing importance. In addition to the well-known important scientific developments in radiology such as interventional MRI, several other major trends can be recognized: (1) changes in the delivery of health care, in which all kinds of managed care are developing and will influence the practice of radiology, and (2) the process of computerization and digitization. The socioeconomic environment of radiology will be transformed by the developments in managed care, teleradiology and the integration of information systems. If radiologists want to manage future radiology departments they must have an understanding of the changes in the fields of economics and politics that are taking place and that will increasingly influence radiology. Some important and recognizable aspects of these changes will be described here. (orig.)

  6. The global threat reduction initiative's radiological security cooperation with Russia - 59361

    International Nuclear Information System (INIS)

    Blanchard, Tiffany A.; Abramson, William J.; Russell, James W. Jr.; Roberts, Catherine K.

    2012-01-01

    The United States (U.S.) Department of Energy (DOE) / National Nuclear Security Administration's (NNSA) Global Threat Reduction Initiative (GTRI) supports both U.S. and international threat reduction goals by securing vulnerable nuclear and radiological material located at civilian sites throughout the world. GTRI's approach to reducing the threat posed by vulnerable, high-activity radioactive sources includes removing and disposing of orphan or disused radioactive sources; implementing physical security upgrades at civilian sites containing radioactive sources; and establishing a cooperative sustainability program at sites to ensure that upgrades are maintained. For many years GTRI has collaborated successfully with the Russian Federation and international partners to improve radiological security in Russia. This paper provides a synopsis of GTRI's accomplishments and cooperation with Russia in the following areas: 1.) recovering and disposing of orphan and disused radioactive sources, 2.) recovering and disposing of radioisotope thermoelectric generators (RTGs), and 3.) providing physical security upgrades at civilian sites that contain vulnerable radiological material. The success of GTRI's program to secure radiological material in the Russian Federation over the past decade is due largely to the hard work, technical expertise, and tenacity of the U.S. laboratory teams and the Russian partner organizations with whom GTRI has worked. GTRI plans to continue building on this history of cooperation in order to recover and secure additional, vulnerable radioactive sources in locations throughout Russia. GTRI also is committed to sustainability efforts so that facilities in Russia receiving physical protection equipment and training are prepared to eventually assume responsibility for those security upgrades. In the years to come, GTRI will combine financial support with capacity building to enhance Russia's domestic programs to address these challenges. Through

  7. Radiological Emergency Response Data

    Data.gov (United States)

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

  8. Radiological evaluation of dysphagia

    Energy Technology Data Exchange (ETDEWEB)

    Ott, D.J.; Gelfand, D.W.; Wu, W.C.; Chen, Y.M.

    1986-11-21

    Dysphagia is a common complaint in patients presenting for radiological or endoscopic examination of the esophagus and is usually due to functional or structural abnormalities of the esophageal body or esophagogastric region. The authors review the radiological evaluation of the esophagus and esophagogastric region in patients with esophageal dysphagia and discuss the roentgenographic techniques used, radiological efficacy for common structural disorders, and evaluation of esophageal motor function. Comparison is made with endoscopy in assessing dysphagia, with the conclusion that the radiological examination be used initially in patients with this complaint.

  9. Machine Learning and Radiology

    Science.gov (United States)

    Wang, Shijun; Summers, Ronald M.

    2012-01-01

    In this paper, we give a short introduction to machine learning and survey its applications in radiology. We focused on six categories of applications in radiology: medical image segmentation, registration, computer aided detection and diagnosis, brain function or activity analysis and neurological disease diagnosis from fMR images, content-based image retrieval systems for CT or MRI images, and text analysis of radiology reports using natural language processing (NLP) and natural language understanding (NLU). This survey shows that machine learning plays a key role in many radiology applications. Machine learning identifies complex patterns automatically and helps radiologists make intelligent decisions on radiology data such as conventional radiographs, CT, MRI, and PET images and radiology reports. In many applications, the performance of machine learning-based automatic detection and diagnosis systems has shown to be comparable to that of a well-trained and experienced radiologist. Technology development in machine learning and radiology will benefit from each other in the long run. Key contributions and common characteristics of machine learning techniques in radiology are discussed. We also discuss the problem of translating machine learning applications to the radiology clinical setting, including advantages and potential barriers. PMID:22465077

  10. Radiological evaluation of dysphagia

    International Nuclear Information System (INIS)

    Ott, D.J.; Gelfand, D.W.; Wu, W.C.; Chen, Y.M.

    1986-01-01

    Dysphagia is a common complaint in patients presenting for radiological or endoscopic examination of the esophagus and is usually due to functional or structural abnormalities of the esophageal body or esophagogastric region. The authors review the radiological evaluation of the esophagus and esophagogastric region in patients with esophageal dysphagia and discuss the roentgenographic techniques used, radiological efficacy for common structural disorders, and evaluation of esophageal motor function. Comparison is made with endoscopy in assessing dysphagia, with the conclusion that the radiological examination be used initially in patients with this complaint

  11. Machine learning and radiology.

    Science.gov (United States)

    Wang, Shijun; Summers, Ronald M

    2012-07-01

    In this paper, we give a short introduction to machine learning and survey its applications in radiology. We focused on six categories of applications in radiology: medical image segmentation, registration, computer aided detection and diagnosis, brain function or activity analysis and neurological disease diagnosis from fMR images, content-based image retrieval systems for CT or MRI images, and text analysis of radiology reports using natural language processing (NLP) and natural language understanding (NLU). This survey shows that machine learning plays a key role in many radiology applications. Machine learning identifies complex patterns automatically and helps radiologists make intelligent decisions on radiology data such as conventional radiographs, CT, MRI, and PET images and radiology reports. In many applications, the performance of machine learning-based automatic detection and diagnosis systems has shown to be comparable to that of a well-trained and experienced radiologist. Technology development in machine learning and radiology will benefit from each other in the long run. Key contributions and common characteristics of machine learning techniques in radiology are discussed. We also discuss the problem of translating machine learning applications to the radiology clinical setting, including advantages and potential barriers. Copyright © 2012. Published by Elsevier B.V.

  12. Reconstructing Southern Greenland Ice Sheet History During the Plio-Pleistocene Intensification of Northern Hemisphere Glaciation: Insights from IODP Site U1307

    Science.gov (United States)

    Blake-Mizen, K. R.; Hatfield, R. G.; Carlson, A. E.; Walczak, M. H.; Stoner, J. S.; Xuan, C.; Lawrence, K. T.; Bailey, I.

    2017-12-01

    Should it melt entirely, the Greenland Ice Sheet (GrIS) has the potential to raise global sea-level by 7 metres. With the Arctic continuing to warm at a remarkable rate, to better understand how the GrIS will respond to future anthropogenically-induced climate change we must constrain its natural variability in the geological past. In this regard, much uncertainty exists surrounding its pre-Quaternary history; particularly during the mid-Piacenzian warm period (mPWP; 3.3-3.0 Ma) - widely considered an analogue for near-future equilibrium climate with modern atmospheric CO2 levels and elevated temperatures relative to today - and the late Pliocene/early Pleistocene onset of widespread Northern Hemisphere glaciation (NHG, 2.7 Ma). GrIS reconstructions for these intervals have been largely hampered by a lack of well-dated, high-resolution records from suitable sites. To address this, we present new high-resolution, multi-proxy records from IODP Site U1307, a North Atlantic marine sediment core recovered from the Eirik Drift just south of Greenland. Generation of a new high-resolution relative palaeointensity (RPI)-based age-model - representing the first of its kind for high-latitude sediments deposited during NHG - has enabled strong orbital age control. Our ice-rafted debris (IRD) record confirms a 2.72 Ma initiation of major southern GrIS marine-terminating glaciations, which appear to persist even through interglacial periods up to at least 2.24 Ma. XRF-scanning and IRD evidence suggests, however, that an ephemeral ice-cap of likely considerable size persisted on southern Greenland prior to the mPWP. These data, together with the analysed provenance of individual IRD, indicate marine-based GrIS margins extended southward over the NHG interval and only occurred on Greenland's southern tip from 2.7 Ma. Despite a large increase in the deposition of GrIS-derived IRD from this time, bulk sedimentation rates and magnetic grain-size dropped significantly, implying that

  13. Long Term Hydrological (Radiological) Site Monitoring Data

    Data.gov (United States)

    U.S. Environmental Protection Agency — Quality Data Asset includes all current and historical data on the quality of water with regard to the presence of water pollutants of all kinds regulated by the...

  14. Radiological aspect of pancreatic pseudocysts

    International Nuclear Information System (INIS)

    Chung, Tae Sub; Lim, Sue Jin; Yoo, Hyung Sik; Suh, Jung Ho; Park, Chang Yun

    1982-01-01

    Pancreatic pseudocyst occurs as a complication of pancreatitis or trauma, which results in the escape of pancreatitis enzymes from the parenchyma or ductal system of pancreas. At that time, serum amylase may have retuned to normal level, and the patient may be subjectively asymptomatic. In this phase, the radiologic findings are relatively greater significance than laboratory data. In the conventional radiologic study, pancreatic pseudocyst have been frequently confused with other retroperitoneal mass, but recently with clinical application of ultrasound and CT scan, more accurate diagnosis can be obtained. The brief results are as follows: 1. Male to female ratio was 3 : 2 in 15 patients. Incidence was more common in young adult age. Most frequent symptom was epigastric pain, and which was noted in 11 cases of patients. 7 cases of patients had past history of abdominal trauma and past history of pancreatitis was only in 1 case. Most common laboratory findings was leukocytosis in 8 cases of patients and elevated serum amylase was also noted in 7 cases. 2. In each 5 cases of patients, plain chest roentgenologic evidence of left side pleural effusion and hemidiaphragm elevation were observed. 3. On flat abdomen film, soft mass shadow was visualized in 8 cases of patients. On UGI series, evidence of retrogastric space widening was observed in 11 cases of patients. 4. The location of pseudocyst is mainly in body and tail of pancrease in 11 cases of patients. 5. More accureable diagnosis can be obtained through application of ultrasound and CT scan

  15. How Secure Is Your Radiology Department? Mapping Digital Radiology Adoption and Security Worldwide.

    Science.gov (United States)

    Stites, Mark; Pianykh, Oleg S

    2016-04-01

    Despite the long history of digital radiology, one of its most critical aspects--information security--still remains extremely underdeveloped and poorly standardized. To study the current state of radiology security, we explored the worldwide security of medical image archives. Using the DICOM data-transmitting standard, we implemented a highly parallel application to scan the entire World Wide Web of networked computers and devices, locating open and unprotected radiology servers. We used only legal and radiology-compliant tools. Our security-probing application initiated a standard DICOM handshake to remote computer or device addresses, and then assessed their security posture on the basis of handshake replies. The scan discovered a total of 2774 unprotected radiology or DICOM servers worldwide. Of those, 719 were fully open to patient data communications. Geolocation was used to analyze and rank our findings according to country utilization. As a result, we built maps and world ranking of clinical security, suggesting that even the most radiology-advanced countries have hospitals with serious security gaps. Despite more than two decades of active development and implementation, our radiology data still remains insecure. The results provided should be applied to raise awareness and begin an earnest dialogue toward elimination of the problem. The application we designed and the novel scanning approach we developed can be used to identify security breaches and to eliminate them before they are compromised.

  16. Annual report 1999 of the German Commission on Radiological Protection (SSK), and a survey of the history of the SSK in the past 25 years. With explanations on the objectives, functions, and history of the SKK, complete lists of recommendations, statements, and publications

    International Nuclear Information System (INIS)

    Gumprecht, D.; Heller, H.

    2000-01-01

    The report begins with an introduction explaining the objectives, functions and composition of the SSK. The main areas and aspects of work in 1999 are addressed and the reports, recommendations or statements prepared by the six committees of the SSK are presented. The areas of work of the committees are: radiation protection and health physics, radioecology, radiological protection in health care, radiological engineering, emergency preparedness, and non-ionizing radiation. (orig./CB) [de

  17. Streamlining interventional radiology admissions: The role of the interventional radiology clinic and physician's assistant

    International Nuclear Information System (INIS)

    White, R.I. Jr.; Rizer, D.M.; Shuman, K.; White, E.J.; Adams, P.; Doyle, K.; Kinnison, M.

    1987-01-01

    During a 5-year period (1982-1987), 376 patients were admitted to an interventional radiology service where they were managed by the senior physician and interventional radiology fellows. Sixty-eight percent of patients were admitted for angioplasty and 32% for elective embolotherapy/diagnostic angiography. A one-half-day, twice weekly interventional radiology clinic and employment of a physician's assistant who performed preadmission history and physicals and wrote orders accounted, in part, for a decrease in hospital stay length from 3.74 days (1982-1983) to 2.41 days (1986-1987). The authors conclude that use of the clinic and the physician's assistant streamlines patient flow and the admitting process and is partially responsible for a decreased length of stay for patients admitted to an interventional radiology service

  18. MARSAME Radiological Release Report for Archaeological Artifacts Excavated from Area L

    Energy Technology Data Exchange (ETDEWEB)

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

    2016-06-03

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

  19. Optimal layout of radiological environment monitoring based on TOPSIS method

    International Nuclear Information System (INIS)

    Li Sufen; Zhou Chunlin

    2006-01-01

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

  20. Radiological protection report 2016

    International Nuclear Information System (INIS)

    2017-06-01

    on the basis of international recommendations. ENSI uses inspections and comparative measurements to ensure that the necessary calibrated radiological protection measurement equipment is available and that it is used for its intended purpose in order to determine correct values. For this purpose, it operates a test centre accredited to ISO 17025. The network operated by ENSI for automatically monitoring the dose rate in the vicinity of nuclear power plants measures dose rates in the vicinity of nuclear power stations all year round and 24 hours a day. The 10-minute, hourly and daily mean rates measured can be viewed on ENSI's web site in real time. This monitoring network serves to secure evidence for the authorities and in dealings with the public. No local increases in dose rates that could be attributed to discharges from nuclear power plants were detected in the reporting year. Sporadic, locally high measurements are due to fluctuations in natural background radiation, e.g. after rainfall. The programme JRODOS (Java-based Realtime Online DecisiOn Support system) has been used since the beginning of 2016 to model atmospheric spread and calculate the dose, should an event occur. JRODOS allows the direct use of 3D weather forecast data from the COSMO-1 model routinely used by MeteoSwiss with a grid size of 1 km. The COSMO-1 model supplies forecasts stretching up to 24 hours into the future with high spatial and temporal resolution. In order to reflect the small scale structure of the Swiss countryside and that of southern Germany, JRODOS uses the very high resolution elevation model from the Swiss Federal Office of Topography. This means that together with the aerial radiometric equipment, there are invaluable, precise instruments available at all times for making current assessments (diagnoses) as well as forecasts of the radiological situation. In the reporting year, all thresholds contained in the Federal Ordinance on radiation protection were met. There