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Sample records for mgr site-generated radiological

  1. CLASSIFICATION OF THE MGR SITE WATER SYSTEM

    International Nuclear Information System (INIS)

    J.A. Ziegler

    1999-01-01

    The purpose of this analysis is to document the Quality Assurance (QA) classification of the Monitored Geologic Repository (MGR) site water system structures, systems and components (SSCs) performed by the MGR Safety Assurance Department. This analysis also provides the basis for revision of YMP/90-55Q, Q-List (YMP 1998). The Q-List identifies those MGR SSCs subject to the requirements of DOE/RW-0333P, ''Quality Assurance Requirements and Description'' (QARD) (DOE 1998)

  2. CLASSIFICATION OF THE MGR SITE OPERATIONS SYSTEM

    International Nuclear Information System (INIS)

    J.A. Ziegler

    1999-01-01

    The purpose of this analysis is to document the Quality Assurance (QA) classification of the Monitored Geologic Repository (MGR) site operations system structures, systems and components (SSCs) performed by the MGR Safety Assurance Department. This analysis also provides the basis for revision of YMP/90-55Q, Q-List (YMP 1998). The Q-List identifies those MGR SSCs subject to the requirements of DOE/RW-0333P, ''Quality Assurance Requirements and Description'' (QARD) (DOE 1998)

  3. CLASSIFICATION OF THE MGR SITE LAYOUT SYSTEM

    International Nuclear Information System (INIS)

    S.E. Salzman

    1999-01-01

    The purpose of this analysis is to document the Quality Assurance (QA) classification of the Monitored Geologic Repository (MGR) site layout system structures, systems and components (SSCs) performed by the MGR Safety Assurance Department. This analysis also provides the basis for revision of YMP/90-55Q, Q-List (YMP 1998). The Q-List identifies those MGR SSCs subject to the requirements of DOE/RW-0333P, ''Quality Assurance Requirements and Description'' (QARD) (DOE 1998)

  4. CLASSIFICATION OF THE MGR SITE COMPRESSED AIR SYSTEM

    International Nuclear Information System (INIS)

    J.A. Ziegler

    1999-01-01

    The purpose of this analysis is to document the Quality Assurance (QA) classification of the Monitored Geologic Repository (MGR) site compressed air system structures, systems and components (SSCs) performed by the MGR Safety Assurance Department. This analysis also provides the basis for revision of YMP/90-55Q, Q-List (YMP 1998). The Q-List identifies those MGR SSCs subject to the requirements of DOE/RW-0333P, ''Quality Assurance Requirements and Description'' (QARD) (DOE 1998)

  5. 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

  6. 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

  7. PRELIMINARY SELECTION OF MGR DESIGN BASIS EVENTS

    International Nuclear Information System (INIS)

    Kappes, J.A.

    1999-01-01

    The purpose of this analysis is to identify the preliminary design basis events (DBEs) for consideration in the design of the Monitored Geologic Repository (MGR). For external events and natural phenomena (e.g., earthquake), the objective is to identify those initiating events that the MGR will be designed to withstand. Design criteria will ensure that radiological release scenarios resulting from these initiating events are beyond design basis (i.e., have a scenario frequency less than once per million years). For internal (i.e., human-induced and random equipment failures) events, the objective is to identify credible event sequences that result in bounding radiological releases. These sequences will be used to establish the design basis criteria for MGR structures, systems, and components (SSCs) design basis criteria in order to prevent or mitigate radiological releases. The safety strategy presented in this analysis for preventing or mitigating DBEs is based on the preclosure safety strategy outlined in ''Strategy to Mitigate Preclosure Offsite Exposure'' (CRWMS M andO 1998f). DBE analysis is necessary to provide feedback and requirements to the design process, and also to demonstrate compliance with proposed 10 CFR 63 (Dyer 1999b) requirements. DBE analysis is also required to identify and classify the SSCs that are important to safety (ITS)

  8. CLASSIFICATION OF THE MGR WASTE EMPLACEMENT/RETRIEVAL SYSTEM

    International Nuclear Information System (INIS)

    J.A. Ziegler

    2000-01-01

    The purpose of this analysis is to document the Quality Assurance (QA) classification of the Monitored Geologic Repository (MGR) waste emplacement/retrieved system structures, systems and components (SSCs) performed by the MGR Preclosure Safety and Systems Engineering Section. This analysis also provides the basis for revision of YMP/90-55Q, Q-List (YMP 2000). The Q-List identifies those MGR SSCs subject to the requirements of DOE/RW-0333P, Quality Assurance Requirements and Description (QARD) (DOE 2000). This QA classification incorporates the current MGR design and the results of the ''Design Basis Event Frequency and Dose Calculation for Site Recommendation'' (CRWMS M andO 2000a). The content and technical approach of this analysis is in accordance with the development plan ''QA Classification of MGR Structures, Systems, and Components'' (CRWMS M andO 1999b)

  9. CLASSIFICATION OF THE MGR WASTE HANDLING BUILDING VENTILATION SYSTEM

    International Nuclear Information System (INIS)

    J.A. Ziegler

    2000-01-01

    The purpose of this analysis is to document the Quality Assurance (QA) classification of the Monitored Geologic Repository (MGR) waste handling building ventilation system structures, systems and components (SSCs) performed by the MGR Preclosure Safety and Systems Engineering Section. This analysis also provides the basis for revision of YMP/90-55Q, Q-List (YMP 2000). The Q-List identifies those MGR SSCs subject to the requirements of DOE/RW-0333P, ''Quality Assurance Requirements and Description'' (QARD) (DOE 2000). This QA classification incorporates the current MGR design and the results of the ''Design Basis Event Frequency and Dose Calculation for Site Recommendation'' (CRWMS M andO 2000a) and ''Bounding Individual Category 1 Design Basis Event Dose Calculation to Support Quality Assurance Classification'' (Gwyn 2000)

  10. webMGR: an online tool for the multiple genome rearrangement problem.

    Science.gov (United States)

    Lin, Chi Ho; Zhao, Hao; Lowcay, Sean Harry; Shahab, Atif; Bourque, Guillaume

    2010-02-01

    The algorithm MGR enables the reconstruction of rearrangement phylogenies based on gene or synteny block order in multiple genomes. Although MGR has been successfully applied to study the evolution of different sets of species, its utilization has been hampered by the prohibitive running time for some applications. In the current work, we have designed new heuristics that significantly speed up the tool without compromising its accuracy. Moreover, we have developed a web server (webMGR) that includes elaborate web output to facilitate navigation through the results. webMGR can be accessed via http://www.gis.a-star.edu.sg/~bourque. The source code of the improved standalone version of MGR is also freely available from the web site. Supplementary data are available at Bioinformatics online.

  11. CLASSIFICATION OF THE MGR MUCK HANDLING SYSTEM

    International Nuclear Information System (INIS)

    R. Garrett

    1999-01-01

    The purpose of this analysis is to document the Quality Assurance (QA) classification of the Monitored Geologic Repository (MGR) muck handling system structures, systems and components (SSCs) performed by the MGR Safety Assurance Department. This analysis also provides the basis for revision of YMP/90-55Q, Q-List (YMP 1998). The Q-List identifies those MGR SSCs subject to the requirements of DOE/RW-0333P, ''Quality Assurance Requirements and Description (QARD) (DOE 1998). This QA classification incorporates the current MGR design and the results of the ''Preliminary Preclosure Design Basis Event Calculations for the Monitored Geologic Repository (CRWMS M and O 1998a)

  12. Classification of the MGR Assembly Transfer System

    International Nuclear Information System (INIS)

    S.E. Salzman

    1999-01-01

    The purpose of this analysis is to document the Quality Assurance (QA) classification of the Monitored Geologic Repository (MGR) assembly transfer system structures, systems and components (SSCs) performed by the MGR Safety Assurance Department. This analysis also provides the basis for revision of YMP/90-55Q, Q-List (YMP 1998). The Q-List identifies those MGR SSCs subject to the requirements of DOE/RW-0333P, ''Quality Assurance Requirements and Description'' (QARD) (DOE 1998)

  13. CLASSIFICATION OF THE MGR OFFSITE UTILITIES SYSTEM

    International Nuclear Information System (INIS)

    J.A. Ziegler

    1999-01-01

    The purpose of this analysis is to document the Quality Assurance (QA) classification of the Monitored Geologic Repository (MGR) offsite utilities system structures, systems and components (SSCs) performed by the MGR Safety Assurance Department. This analysis also provides the basis for revision of YMP/90-55Q, Q-List (YMP 1998). The Q-List identifies those MGR SSCs subject to the requirements of DOE/RW-0333P, ''Quality Assurance Requirements and Description'' (QARD) (DOE 1998)

  14. CLASSIFICATION OF THE MGR SUBSURFACE EXCAVATION SYSTEM

    International Nuclear Information System (INIS)

    R. Garrett

    1999-01-01

    The purpose of this analysis is to document the Quality Assurance (QA) classification of the Monitored Geologic Repository (MGR) subsurface excavation system structures, systems and components (SSCs) performed by the MGR Safety Assurance Department. This analysis also provides the basis for revision of YMP/90-55Q, Q-List (YMP 1998). The Q-List identifies those MGR SSCs subject to the requirements of DOE/RW-0333P, ''Quality Assurance Requirements and Description'' (QARD) (DOE 1998)

  15. CLASSIFICATION OF THE MGR SUBSURFACE VENTILATION SYSTEM

    International Nuclear Information System (INIS)

    R.J. Garrett

    1999-01-01

    The purpose of this analysis is to document the Quality Assurance (QA) classification of the Monitored Geologic Repository (MGR) subsurface ventilation system structures, systems and components (SSCs) performed by the MGR Safety Assurance Department. This analysis also provides the basis for revision of YMP/90-55Q, Q-List (YMP 1998). The Q-List identifies those MGR SSCs subject to the requirements of DOE/RW-0333P7 ''Quality Assurance Requirements and Description'' (QARD) (DOE 1998)

  16. CLASSIFICATION OF THE MGR EMERGENCY RESPONSE SYSTEM

    International Nuclear Information System (INIS)

    Zeigler, J.A.

    1999-01-01

    The purpose of this analysis is to document the Quality Assurance (QA) classification of the Monitored Geologic Repository (MGR) emergency response system structures, systems and components (SSCs) performed by the MGR Safety Assurance Department. This analysis also provides the basis for revision of YMP/90-55Q, Q-List (YMP 1998). The Q-List identifies those MGR SSCs subject to the requirements of DOE/RW-0333P7 ''Quality Assurance Requirements and Description'' (QARD) (DOE 1998)

  17. WASTE TREATMENT BUILDING SYSTEM DESCRIPTION DOCUMENT

    Energy Technology Data Exchange (ETDEWEB)

    F. Habashi

    2000-06-22

    The Waste Treatment Building System provides the space, layout, structures, and embedded subsystems that support the processing of low-level liquid and solid radioactive waste generated within the Monitored Geologic Repository (MGR). The activities conducted in the Waste Treatment Building include sorting, volume reduction, and packaging of dry waste, and collecting, processing, solidification, and packaging of liquid waste. The Waste Treatment Building System is located on the surface within the protected area of the MGR. The Waste Treatment Building System helps maintain a suitable environment for the waste processing and protects the systems within the Waste Treatment Building (WTB) from most of the natural and induced environments. The WTB also confines contaminants and provides radiological protection to personnel. In addition to the waste processing operations, the Waste Treatment Building System provides space and layout for staging of packaged waste for shipment, industrial and radiological safety systems, control and monitoring of operations, safeguards and security systems, and fire protection, ventilation and utilities systems. The Waste Treatment Building System also provides the required space and layout for maintenance activities, tool storage, and administrative facilities. The Waste Treatment Building System integrates waste processing systems within its protective structure to support the throughput rates established for the MGR. The Waste Treatment Building System also provides shielding, layout, and other design features to help limit personnel radiation exposures to levels which are as low as is reasonably achievable (ALARA). The Waste Treatment Building System interfaces with the Site Generated Radiological Waste Handling System, and with other MGR systems that support the waste processing operations. The Waste Treatment Building System interfaces with the General Site Transportation System, Site Communications System, Site Water System, MGR

  18. WASTE TREATMENT BUILDING SYSTEM DESCRIPTION DOCUMENT

    International Nuclear Information System (INIS)

    Habashi, F.

    2000-01-01

    The Waste Treatment Building System provides the space, layout, structures, and embedded subsystems that support the processing of low-level liquid and solid radioactive waste generated within the Monitored Geologic Repository (MGR). The activities conducted in the Waste Treatment Building include sorting, volume reduction, and packaging of dry waste, and collecting, processing, solidification, and packaging of liquid waste. The Waste Treatment Building System is located on the surface within the protected area of the MGR. The Waste Treatment Building System helps maintain a suitable environment for the waste processing and protects the systems within the Waste Treatment Building (WTB) from most of the natural and induced environments. The WTB also confines contaminants and provides radiological protection to personnel. In addition to the waste processing operations, the Waste Treatment Building System provides space and layout for staging of packaged waste for shipment, industrial and radiological safety systems, control and monitoring of operations, safeguards and security systems, and fire protection, ventilation and utilities systems. The Waste Treatment Building System also provides the required space and layout for maintenance activities, tool storage, and administrative facilities. The Waste Treatment Building System integrates waste processing systems within its protective structure to support the throughput rates established for the MGR. The Waste Treatment Building System also provides shielding, layout, and other design features to help limit personnel radiation exposures to levels which are as low as is reasonably achievable (ALARA). The Waste Treatment Building System interfaces with the Site Generated Radiological Waste Handling System, and with other MGR systems that support the waste processing operations. The Waste Treatment Building System interfaces with the General Site Transportation System, Site Communications System, Site Water System, MGR

  19. CLASSIFICATION OF THE MGR MAINTENANCE AND SUPPLY SYSTEM

    International Nuclear Information System (INIS)

    J.A. Ziegler

    1999-01-01

    The purpose of this analysis is to document the Quality Assurance (QA) classification of the Monitored Geologic Repository (MGR) maintenance and supply system structures, systems and components (SSCs) performed by the MGR Safety Assurance Department. This analysis also provides the basis for revision of YMP/90-55Q, Q-List (YMP 1998). The Q-List identifies those MGR SSCs subject to the requirements of DOE/RW-0333P, ''Quality Assurance Requirements and Description'' (QARD) (DOE 1998)

  20. MGR External Events Hazards Analysis

    International Nuclear Information System (INIS)

    Booth, L.

    1999-01-01

    The purpose and objective of this analysis is to apply an external events Hazards Analysis (HA) to the License Application Design Selection Enhanced Design Alternative 11 [(LADS EDA II design (Reference 8.32))]. The output of the HA is called a Hazards List (HL). This analysis supersedes the external hazards portion of Rev. 00 of the PHA (Reference 8.1). The PHA for internal events will also be updated to the LADS EDA II design but under a separate analysis. Like the PHA methodology, the HA methodology provides a systematic method to identify potential hazards during the 100-year Monitored Geologic Repository (MGR) operating period updated to reflect the EDA II design. The resulting events on the HL are candidates that may have potential radiological consequences as determined during Design Basis Events (DBEs) analyses. Therefore, the HL that results from this analysis will undergo further screening and analysis based on the criteria that apply during the performance of DBE analyses

  1. CLASSIFICATION OF THE MGR WASTE HANDLING BUILDING ELECTRICAL SYSTEM

    International Nuclear Information System (INIS)

    S.E. Salzman

    1999-01-01

    The purpose of this analysis is to document the Quality Assurance (QA) classification of the Monitored Geologic Repository (MGR) waste handling building electrical system structures, systems and components (SSCs) performed by the MGR Safety Assurance Department. This analysis also provides the basis for revision of YMP/90-55Q, Q-List (YMP 1998). The Q-List identifies those MGR SSCs subject to the requirements of DOE/RW-0333P, ''Quality Assurance Requirements and Description'' (QARD) (DOE 1998)

  2. CLASSIFICATION OF THE MGR OPERATIONS MONITORING AND CONTROL SYSTEM

    International Nuclear Information System (INIS)

    R.J. Garrett

    1999-01-01

    The purpose of this analysis is to document the Quality Assurance (QA) classification of the Monitored Geologic Repository (MGR) Operations Monitoring and Control System structures, systems and components (SSCs) performed by the MGR Safety Assurance Department. This analysis also provides the basis for revision of YMP/90-55Q, Q-List (YMP 1998). The Q-List identifies those MGR SSCs subject to the requirements of DOE/RW-0333P7 ''Quality Assurance Requirements and Description'' (QARD) (DOE 1998)

  3. CLASSIFICATION OF THE MGR NON-FUEL COMPONENTS DISPOSAL CONTAINER SYSTEM

    International Nuclear Information System (INIS)

    J.A. Ziegler

    1999-01-01

    The purpose of this analysis is to document the Quality Assurance (QA) classification of the Monitored Geologic Repository (MGR) non-fuel components disposal container system structures, systems and components (SSCs) performed by the MGR Safety Assurance Department. This analysis also provides the basis for revision of YMP/90-55Q, Q-List (YMP 1998). The Q-List identifies those MGR SSCs subject to the requirements of DOE/RW-0333P, ''Quality Assurance Requirements and Description'' (QARD) (DOE 1998)

  4. CLASSIFICATION OF THE MGR PERFORMANCE CONFIRMATION DATA ACQUISITION/MONITORING SYSTEM

    International Nuclear Information System (INIS)

    J.A. Ziegler

    1999-01-01

    The purpose of this analysis is to document the Quality Assurance (QA) classification of the Monitored Geologic Repository (MGR) performance confirmation data acquisition/monitoring system structures, systems and components (SSCs) performed by the MGR Safety Assurance Department. This analysis also provides the basis for revision of YMP/90-55Q, Q-List (YMF 1998). The Q-List identifies those MGR SSCs subject to the requirements of DOE/RW-0333PY ''Quality Assurance Requirements and Description'' (QARD) (DOE 1998)

  5. CLASSIFICATION OF THE MGR DEFENSE HIGH-LEVEL WASTE DISPOSAL CONTAINER SYSTEM

    International Nuclear Information System (INIS)

    J.A. Ziegler

    1999-01-01

    The purpose of this analysis is to document the Quality Assurance (QA) classification of the Monitored Geologic Repository (MGR) defense high-level waste disposal container system structures, systems and components (SSCs) performed by the MGR Safety Assurance Department. This analysis also provides the basis for revision of YMP/90-55Q, Q-List (YMP 1998). The Q-List identifies those MGR SSCs subject to the requirements of DOE/RW-0333PY ''Quality Assurance Requirements and Description'' (QARD) (DOE 1998)

  6. Posttranslational modification influences the effects of MgrA on norA expression in Staphylococcus aureus.

    Science.gov (United States)

    Truong-Bolduc, Que Chi; Ding, Yanpeng; Hooper, David C

    2008-11-01

    MgrA is a global regulator in Staphylococcus aureus. Differences in the effects of MgrA on norA expression have been reported for different strains, which varied in rsbU, a gene that affects the expression of sigB, which encodes an alternative sigma factor involved in stress responses. We hypothesized that MgrA was modified by sigB-dependent factors that affected its ability to control the expression of the norA efflux pump. Heterologously expressed MgrA purified from Escherichia coli was incubated with crude extracts (CE) from strains RN6390 (rsbU) and SH1000 (rsbU(+)) and tested for binding to the norA promoter. Purified MgrA exhibited greater binding to norA promoter DNA after being incubated with SH1000 CE than MgrA incubated with the RN6390 CE. Phosphorylation of MgrA occurring in cell extracts caused it to lose the ability to bind norA promoter DNA. Overexpression of pknB, encoding a candidate serine/threonine kinase, produced increased phospho-MgrA and led to a fivefold increase in the transcript level of norA for both RN6390 and SH1000, as well as a fourfold increase in the MICs of norfloxacin and ciprofloxacin for these two strains. The levels of expression of pknB in RN6390 and SH1000, however, indicated that additional factors related to rsbU or sigB contribute to the differential regulatory effects of MgrA on norA expression.

  7. The Staphylococcus aureus Global Regulator MgrA Modulates Clumping and Virulence by Controlling Surface Protein Expression.

    Directory of Open Access Journals (Sweden)

    Heidi A Crosby

    2016-05-01

    Full Text Available Staphylococcus aureus is a human commensal and opportunistic pathogen that causes devastating infections in a wide range of locations within the body. One of the defining characteristics of S. aureus is its ability to form clumps in the presence of soluble fibrinogen, which likely has a protective benefit and facilitates adhesion to host tissue. We have previously shown that the ArlRS two-component regulatory system controls clumping, in part by repressing production of the large surface protein Ebh. In this work we show that ArlRS does not directly regulate Ebh, but instead ArlRS activates expression of the global regulator MgrA. Strains lacking mgrA fail to clump in the presence of fibrinogen, and clumping can be restored to an arlRS mutant by overexpressing either arlRS or mgrA, indicating that ArlRS and MgrA constitute a regulatory pathway. We used RNA-seq to show that MgrA represses ebh, as well as seven cell wall-associated proteins (SraP, Spa, FnbB, SasG, SasC, FmtB, and SdrD. EMSA analysis showed that MgrA directly represses expression of ebh and sraP. Clumping can be restored to an mgrA mutant by deleting the genes for Ebh, SraP and SasG, suggesting that increased expression of these proteins blocks clumping by steric hindrance. We show that mgrA mutants are less virulent in a rabbit model of endocarditis, and virulence can be partially restored by deleting the genes for the surface proteins ebh, sraP, and sasG. While mgrA mutants are unable to clump, they are known to have enhanced biofilm capacity. We demonstrate that this increase in biofilm formation is partially due to up-regulation of SasG, a surface protein known to promote intercellular interactions. These results confirm that ArlRS and MgrA constitute a regulatory cascade, and that they control expression of a number of genes important for virulence, including those for eight large surface proteins.

  8. Development of GT-MGR plant power conversion unit design

    International Nuclear Information System (INIS)

    Kostin, V.I.; Kodochigov, N.G.; Belov, S.E.; Vasyaev, A.V.; Golovko, V.F.; Shenoj, A.

    2007-01-01

    The General Atomic Company (USA) and the Pilot Design Bureau for Machine-Building (Russia) are involved in the efforts to design the GT-MGR modular helium cooled reactor and the energy conversion unit with the direct gas turbine cycle. The reactor capacity is equal to 600 MW, it is cooled by helium under 7 MPa pressure. The energy conversion unit consists of a gas turbine, a recuperator, preliminary and intermediate coolers, a generator. The turbine shaft rotation frequency is equal to 4400 rotation/minute. One analyzed the alternate designs of the energy conversion unit to choose its configuration [ru

  9. 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

  10. 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

  11. Phosphorylation of MgrA and its effect on expression of the NorA and NorB efflux pumps of Staphylococcus aureus.

    Science.gov (United States)

    Truong-Bolduc, Que Chi; Hooper, David C

    2010-05-01

    MgrA is a global regulator in Staphylococcus aureus that controls the expression of diverse genes encoding virulence factors and multidrug resistance (MDR) efflux transporters. We identified pknB, which encodes the (Ser/Thr) kinase PknB, in the S. aureus genome. PknB was able to autophosphorylate as well as phosphorylate purified MgrA. We demonstrated that rsbU, which encodes a Ser/Thr phosphatase and is involved in the activation of the SigB regulon, was able to dephosphorylate MgrA-P but not PknB-P. Serines 110 and 113 of MgrA were found to be phosphorylated, and Ala substitutions at these positions resulted in reductions in the level of phosphorylation of MgrA. DNA gel shift binding assays using norA and norB promoters showed that MgrA-P was able to bind the norB promoter but not the norA promoter, a pattern which was the reverse of that for unphosphorylated MgrA. The double mutant MgrA(S110A-S113A) bound to the norA promoter but not the norB promoter. The double mutant led to a 2-fold decrease in norA transcripts and a 2-fold decrease in the MICs of norfloxacin and ciprofloxacin in strain RN6390. Thus, phosphorylation of MgrA results in loss of binding to the norA promoter, but with a gain of the ability to bind the norB promoter. Loss of the ability to phosphorylate MgrA by Ala substitution resulted in increased repression of norA expression and in reductions in susceptibilities to NorA substrates.

  12. 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

  13. 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

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

    International Nuclear Information System (INIS)

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

    1992-10-01

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

  15. 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

  16. 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

  17. Gold(I) Complexes with N-Donor Ligands. 2.(1) Reactions of Ammonium Salts with [Au(acac-kappaC(2))(PR(3))] To Give [Au(NH(3))L](+), [(AuL)(2)(&mgr;(2)-NH(2))](+), [(AuL)(4)(&mgr;(4)-N)](+), or [(AuL)(3)(&mgr;(3)-O)](+). A New and Facile Synthesis of [Au(NH(3))(2)](+) Salts. Crystal Structure of [{AuP(C(6)H(4)OMe-4)(3)}(3)(&mgr;(3)-O)]CF(3)SO(3).

    Science.gov (United States)

    Vicente, José; Chicote, María-Teresa; Guerrero, Rita; Jones, Peter G.; Ramírez De Arellano, M. Carmen

    1997-09-24

    The complexes [Au(acac-kappaC(2))(PR(3))] (acac = acetylacetonate, R = Ph, C(6)H(4)OMe-4) react with (NH(4))ClO(4) to give amminegold(I), [Au(NH(3))(PR(3))]ClO(4), amidogold(I), [(AuPR(3))(2)(&mgr;(2)-NH(2))]ClO(4), or nitridogold(I), [(AuPR(3))(4)(&mgr;(4)-N)]ClO(4), complexes, depending on the reaction conditions. Similarly, [Au(acac-kappaC(2))(PPh(3))] reacts with (NH(3)R')OTf (OTf = CF(3)SO(3)) (1:1) or with [H(3)N(CH(2))(2)NH(2)]OTf (1:1) to give (amine)gold(I) complexes [Au(NH(2)R')(PPh(3))]OTf (R' = Me, C(6)H(4)NO(2)-4) or [(AuPPh(3))(2){&mgr;(2)-H(2)N(CH(2))(2)NH(2)}](OTf)(2), respectively. The ammonium salts (NH(2)R'(2))OTf (R' = Et, Ph) react with [Au(acac-kappaC(2))(PR(3))] (R = Ph, C(6)H(4)OMe-4) (1:2) to give, after hydrolysis, the oxonium salts [(AuPR(3))(3)(&mgr;(3)-O)]OTf (R = Ph, C(6)H(4)OMe-4). When NH(3) is bubbled through a solution of [AuCl(tht)] (tht = tetrahydrothiophene), the complex [Au(NH(3))(2)]Cl precipitates. Addition of [Au(NH(3))(2)]Cl to a solution of AgClO(4) or TlOTf leads to the isolation of [Au(NH(3))(2)]ClO(4) or [Au(NH(3))(2)]OTf, respectively. The crystal structure of [(AuPR(3))(3)(&mgr;(3)-O)]OTf.Me(2)CO (R = C(6)H(4)OMe-4) has been determined: triclinic, space group P&onemacr;, a = 14.884(3) Å, b = 15.828(3) Å, c = 16.061(3) Å, alpha = 83.39(3) degrees, beta = 86.28(3) degrees, gamma = 65.54(3) degrees, R1 (wR2) = 0.0370 (0.0788). The [(AuPR(3))(3)(&mgr;(3)-O)](+) cation shows an essentially trigonal pyramidal array of three gold atoms and one oxygen atom with O-Au-P bond angles of ca. 175 degrees and Au.Au contacts in the range 2.9585(7)-3.0505(14) Å. These cations are linked into centrosymmetric dimers through two short Au.Au [2.9585(7), 3.0919(9) Å] contacts. The gold atoms of the dimer form a six-membered ring with a chair conformation.

  18. Mapping the heparin-binding site of the BMP antagonist gremlin by site-directed mutagenesis based on predictive modelling.

    Science.gov (United States)

    Tatsinkam, Arnold Junior; Mulloy, Barbara; Rider, Christopher C

    2015-08-15

    Gremlin is a member of the CAN (cerberus and DAN) family of secreted BMP (bone morphogenetic protein) antagonists and also an agonist of VEGF (vascular endothelial growth factor) receptor-2. It is critical in limb skeleton and kidney development and is re-expressed during tissue fibrosis. Gremlin binds strongly to heparin and heparan sulfate and, in the present study, we sought to investigate its heparin-binding site. In order to explore a putative non-contiguous binding site predicted by computational molecular modelling, we substituted a total of 11 key arginines and lysines located in three basic residue sequence clusters with homologous sequences from cerberus and DAN (differential screening selected gene abberative in neuroblastoma), CAN proteins which lack basic residues in these positions. A panel of six Myc-tagged gremlin mutants, MGR-1-MGR-6 (MGR, mutant gremlin), each containing different combinations of targeted substitutions, all showed markedly reduced affinity for heparin as demonstrated by their NaCl elution on heparin affinity chromatography, thus verifying our predictions. Both MGR-5 and MGR-6 retained BMP-4-binding activity comparable to that of wild-type gremlin. Low-molecular-mass heparin neither promoted nor inhibited BMP-4 binding. Finally, glutaraldehyde cross-linking demonstrated that gremlin forms non-covalent dimers, similar behaviour to that of DAN and also PRDC (protein related to cerberus and DAN), another CAN protein. The resulting dimer would possess two heparin-binding sites, each running along an exposed surface on the second β-strand finger loop of one of the monomers. © 2015 Authors; published by Portland Press Limited.

  19. 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

  20. 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.

  1. 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)

  2. MGR COMPLIANCE PROGRAM GUIDANCE PACKAGE FOR RADIATION PROTECTION EQUIPMENT, INSTRUMENTATION, AND FACILITIES

    International Nuclear Information System (INIS)

    2000-01-01

    This Compliance Program Guidance Package identifies the regulatory guidance and industry codes and standards addressing radiation protection equipment, instrumentation, and support facilities considered to be appropriate for radiation protection at the Monitored Geologic Repository (MGR). Included are considerations relevant to radiation monitoring instruments, calibration, contamination control and decontamination, respiratory protection equipment, and general radiation protection facilities. The scope of this Guidance Package does not include design guidance relevant to criticality monitoring, area radiation monitoring, effluent monitoring, and airborne radioactivity monitoring systems since they are considered to be the topics of specific design and construction requirements (i.e., ''fixed'' or ''built-in'' systems). This Guidance Package does not address radiation protection design issues; it addresses the selection and calibration of radiation monitoring instrumentation to the extent that the guidance is relevant to the operational radiation protection program. Radon and radon progeny monitoring instrumentation is not included in the Guidance Package since such naturally occurring radioactive materials do not fall within the NRC's jurisdiction at the MGR

  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. 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

  5. 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

  6. 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

  7. 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

  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 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)

  10. Nevada Test Site Radiological Control Manual, Revision 1

    International Nuclear Information System (INIS)

    2010-01-01

    Management. The NTS has been the primary location for testing nuclear explosives in the continental United States since 1951. The topographical and geological characteristics of the NTS afford some protection to the inhabitants of the surrounding areas from potential radiation exposure as a result of release of radioactivity or contamination from nuclear testing operations. Historically, testing programs at the NTS have included atmospheric testing in the 1950s and early 1960s; underground testing in drilled, vertical holes and horizontal tunnels; earth-cratering experiments; and open air nuclear reactor and engine testing. Current activities 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 low-level radioactive waste and the handling of radioactive sources. Remediation of contaminated land areas may also result in radiological exposures. The Tenant Organizations (TOs) that are responsible for conducting operations, according to this manual, include National Security Technologies, LLC (NSTec), Defense Threat Reduction Agency, Desert Research Institute, Lawrence Livermore National Laboratory, Los Alamos National Laboratory, Navarro Nevada Environmental Services, LLC, Sandia National Laboratories, and WSI. These organizations operate under this manual only when they are performing activities under the purview of NNSA/NSO. To ensure that the appropriate procedures

  11. Effect of Promoter Region Mutations and mgrA Overexpression on Transcription of norA, Which Encodes a Staphylococcus aureus Multidrug Efflux Transporter

    OpenAIRE

    Kaatz, Glenn W.; Thyagarajan, Rama V.; Seo, Susan M.

    2005-01-01

    NorA is a Staphylococcus aureus multidrug transporter that confers resistance to structurally distinct compounds. The MgrA global regulatory protein is reported to augment norA expression when mgrA is overexpressed from an undefined plasmid-based promoter. Further details about norA regulatory mechanisms are scant. A chromosomal norA::lacZ transcriptional fusion was constructed in different S. aureus strains, and allele replacement was used to define the relevance of promoter region sequences...

  12. 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

  13. Informatics in radiology: RADTF: a semantic search-enabled, natural language processor-generated radiology teaching file.

    Science.gov (United States)

    Do, Bao H; Wu, Andrew; Biswal, Sandip; Kamaya, Aya; Rubin, Daniel L

    2010-11-01

    Storing and retrieving radiology cases is an important activity for education and clinical research, but this process can be time-consuming. In the process of structuring reports and images into organized teaching files, incidental pathologic conditions not pertinent to the primary teaching point can be omitted, as when a user saves images of an aortic dissection case but disregards the incidental osteoid osteoma. An alternate strategy for identifying teaching cases is text search of reports in radiology information systems (RIS), but retrieved reports are unstructured, teaching-related content is not highlighted, and patient identifying information is not removed. Furthermore, searching unstructured reports requires sophisticated retrieval methods to achieve useful results. An open-source, RadLex(®)-compatible teaching file solution called RADTF, which uses natural language processing (NLP) methods to process radiology reports, was developed to create a searchable teaching resource from the RIS and the picture archiving and communication system (PACS). The NLP system extracts and de-identifies teaching-relevant statements from full reports to generate a stand-alone database, thus converting existing RIS archives into an on-demand source of teaching material. Using RADTF, the authors generated a semantic search-enabled, Web-based radiology archive containing over 700,000 cases with millions of images. RADTF combines a compact representation of the teaching-relevant content in radiology reports and a versatile search engine with the scale of the entire RIS-PACS collection of case material. ©RSNA, 2010

  14. RADIATION ACCESS ZONE AND VENTILATION CONFINEMENT ZONE CRITERIA FOR THE MGR SURFACE FACILITIES

    International Nuclear Information System (INIS)

    D. A. Padula

    2000-01-01

    The objectives of this technical report are to: (1) Establish the criteria for Radiation Access Zone (RAZ) designation. (2) Establish the criteria for the Ventilation Confinement Zone (VCZ) designation. The scope will be to formulate the RAZ and VCZ zoning designation for the Monitored Geologic Repository (MGR) surface facilities and to apply the zoning designations to the current Waste Handling Building (WHB), Waste Treatment Building (WTB), and Carrier Preparation Building (CPB) configurations

  15. 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

  16. 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

  17. 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.

  18. Radiological protection for the ANGRA 1 steam generator replacement outage

    International Nuclear Information System (INIS)

    Oliveira, Magno Jose de; Amaral, Marcos Antonio do; Minelli, Edson; Ferreira, William Alves

    2009-01-01

    The Angra 1 Nuclear Power Plant (NPP) is a Westinghouse two-loop plant with net output before its 1P16 Outage of 632 MWe, with the Old Steam Generators (OSG) type model D3, which were replaced by two new Steam Generators with feed water-ring system. Localized in Angra dos Reis, Rio de Janeiro - Brazil, Angra 1 started in commercial operation in 1985 and, from the beginning problems related to corrosion have appeared in the Inconel 600 alloy of the tubes. The corrosion problems indicated the necessity for a strong control of the tubes thicknesses and, after a time, the ELETRONUCLEAR decided to replace the OSG. In 2009, ELETRONUCLEAR initiated in January 24, the actions for the Steam Generators Replacement - SGR. During the SGR process, several controls were applied in field, which made possible to have no radiological accidents, no dose limits exceeded, and permitted to achieve a very good result in terms of Collective Dose. This paper describes the radiological controls applied for the Angra 1 Steam Generator Replacement Outage, the radiological protection team sizing and distribution and the obtained results. (author)

  19. Report generation using digital speech recognition in radiology

    International Nuclear Information System (INIS)

    Vorbeck, F.; Ba-Ssalamah, A.; Kettenbach, J.; Huebsch, P.

    2000-01-01

    The aim of this study was to evaluate whether the use of a digital continuous speech recognition (CSR) in the field of radiology could lead to relevant time savings in generating a report. A CSR system (SP6000, Philips, Eindhoven, The Netherlands) for German was used to transform fluently spoken sentences into text. Two radiologists dictated a total of 450 reports on five radiological topics. Two typists edited those reports by means of conventional typing using a text editor (WinWord 6.0, Microsoft, Redmond, Wash.) installed on an IBM-compatible personal computer (PC). The same reports were generated using the CSR system and the performance of both systems was then evaluated by comparing the time needed to generate the reports and the error rates of both systems. In addition, the error rate of the CSR system and the time needed to create the reports was evaluated. The mean error rate for the CSR system was 5.5 %, and the mean error rate for conventional typing was 0.4 %. Reports edited with the CSR, on average, were generated 19 % faster compared with the conventional text-editing method. However, the amount of error rates and time savings were different and depended on topics, speakers, and typists. Using CSR the maximum time saving achieved was 28 % for the topic sonography. The CSR system was never slower, under any circumstances, than conventional typing on a PC. When compared with a conventional manual typing method, the CSR system proved to be useful in a clinical setting and saved time in generating radiological reports. The amount of time saved, however, greatly depended on the performance of the typist, the speaker, and on stored vocabulary provided by the CSR system. (orig.)

  20. 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)

  1. 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.

  2. 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

  3. 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

  4. WWER-1000/320 steam generator collector rupture. Radiological consequences

    Energy Technology Data Exchange (ETDEWEB)

    Ivanova, A; Sartmadzhiev, A; Balabanov, E [Energoproekt, Sofia (Bulgaria)

    1996-12-31

    A model describing a hypothetical accident with direct release of primary coolant to the atmosphere is proposed. Cover lifting of the primary collector due to a rupture of the fixing bolts leads to a coolant release. The initial and boundary conditions of the accident scenario have been selected to provide for the most unfavorable conditions. The total release of primary coolant during the first 15 min of transient are estimated to 50.8 tons, of these 48.5 t with the initial activity in the primary coolant circuit. Without evacuation or sheltering, after 7 days of exposure, the expected dose at the boundary of the restricted zone is 0.0182 Sv for the whole body and 0.184 Sv for the thyroid gland. The effective equivalent dose on the site would be 0.0521 Sv. As a result of the analysis it is concluded that the steam generator collector rupture is not jeopardizing the core heat removal even with a minimum configuration of ECCS as the cooling is accomplished through the steam generators. The radiological consequences of the accident would be relatively small if an emergency procedure is applied at the 15-th minute of the transient. 1 ref.

  5. 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.

  6. 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

  7. 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

  8. Transportation risk assessment of radioactive wastes generated by the N-Reactor stabilization program at the Hanford Site, Washington

    International Nuclear Information System (INIS)

    Wheeler, T.

    1994-12-01

    The potential radiological and nonradiological risks associated with specific radioactive waste shipping campaigns at the Hanford Site are estimated. The shipping campaigns analyzed are associated with the transportation of wastes from the N-Reactor site at the 200-W Area, both within the Hanford Reservation, for disposal. The analysis is based on waste that would be generated from the N-Reactor stabilization program

  9. 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

  10. 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.

  11. 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

  12. 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

  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. 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

  15. 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

  16. 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

  17. 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

  18. 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

  19. 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.

  20. 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

  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. Evaluation of soluble organic compounds generated by radiological degradation of asphalt

    International Nuclear Information System (INIS)

    Fukumoto, M.; Nishikawa, Y.; Kagawa, A.; Kawamura, K.

    2000-12-01

    The soluble organic compounds generated by radiological degradation of asphalt (γ ray) were confirmed as a part of influence of the bituminized waste degradation in the TRU waste repository. Especially, the influence of the nitrate was focused on. As a result, the concentration of the soluble organic compounds generated by radiological degradation of asphalt (10 MGy, γ ray which is correspond to absorbed dose of asphalt for 1,000,000 years) were lower (each formic acid: about 50 mg/dm 3 , acetic acid: about 30 mg/dm 3 and oxalic acid: about 2 mg/dm 3 ) than that of the formic acid, the acetic acid and the oxalic acid which Valcke et al. had shown (the influence of the organic at the solubility examination which uses Pu and Am). Moreover, the change in the concentration of TOC and the soluble organic compounds (formic acid, acetic acid and oxalic acid) is little under the existence of nitrate ion. That is, the formic acid and acetic acid which can be organic ligands were generated little by oxidative decomposition of asphalt in the process that nitrate ion becomes nitride ion by radiation. The influence of the soluble organic compounds by the radiological degradation of the asphalt (γ ray) on adsorption and solubility by the complexation of radionuclides in the performance assessment can be limited. (author)

  3. 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

  4. Archive of Geosample Data and Information from the Oregon State University (OSU) College of Earth, Ocean and Atmospheric Sciences (CEOAS) Marine Geology Repository (MGR)

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — The Oregon State University Marine Geology Repository (OSU-MGR) is a partner in the Index to Marine and Lacustrine Geological Samples (IMLGS) database, contributing...

  5. 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)

  6. 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

  7. 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)

  8. 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)

  9. 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

  10. 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.

  11. 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

  12. 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.

  13. 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

  14. 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)

  15. 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

  16. 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

  17. 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

  18. 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

  19. 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.

  20. 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)

  1. 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

  2. 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)

  3. Radiological safety aspects of the operation of neutron generators

    International Nuclear Information System (INIS)

    Boggs, R.F.

    1976-01-01

    The purpose of the manual is to provide some basic guidelines to persons with a minimum of training in radiological health or health physics, on some safety aspects of the operation of sealed-tube and Cockcroft-Walton type neutron generators. The manual does not state rules or regulations but presents a description of the most likely hazards. It is relevant to those relatively compact neutron generators which usually operate at less than 150-200 kV for the purpose of producing 14-MeV neutrons. The scope is limited to basic discussions of hazards and measurement techniques. Separate chapters are devoted to the characteristics and use of neutron generators; radiation hazards and safety considerations; radiation monitoring and interpretation of measurements; and requirements for an effective safety programme. Two appendices deal with non-radiation hazards and safety considerations, and with a neutron generator laboratory, respectively. An extensive list of bibliographic references is included

  4. A Planning Tool for Estimating Waste Generated by a Radiological Incident and Subsequent Decontamination Efforts - 13569

    International Nuclear Information System (INIS)

    Boe, Timothy; Lemieux, Paul; Schultheisz, Daniel; Peake, Tom; Hayes, Colin

    2013-01-01

    Management of debris and waste from a wide-area radiological incident would probably constitute a significant percentage of the total remediation cost and effort. The U.S. Environmental Protection Agency's (EPA's) Waste Estimation Support Tool (WEST) is a unique planning tool for estimating the potential volume and radioactivity levels of waste generated by a radiological incident and subsequent decontamination efforts. The WEST was developed to support planners and decision makers by generating a first-order estimate of the quantity and characteristics of waste resulting from a radiological incident. The tool then allows the user to evaluate the impact of various decontamination/demolition strategies on the waste types and volumes generated. WEST consists of a suite of standalone applications and Esri R ArcGIS R scripts for rapidly estimating waste inventories and levels of radioactivity generated from a radiological contamination incident as a function of user-defined decontamination and demolition approaches. WEST accepts Geographic Information System (GIS) shape-files defining contaminated areas and extent of contamination. Building stock information, including square footage, building counts, and building composition estimates are then generated using the Federal Emergency Management Agency's (FEMA's) Hazus R -MH software. WEST then identifies outdoor surfaces based on the application of pattern recognition to overhead aerial imagery. The results from the GIS calculations are then fed into a Microsoft Excel R 2007 spreadsheet with a custom graphical user interface where the user can examine the impact of various decontamination/demolition scenarios on the quantity, characteristics, and residual radioactivity of the resulting waste streams. (authors)

  5. 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)

  6. 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

  7. 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

  8. Membrane-Associated Effects of Glucocorticoid on BACE1 Upregulation and Aβ Generation: Involvement of Lipid Raft-Mediated CREB Activation.

    Science.gov (United States)

    Choi, Gee Euhn; Lee, Sei-Jung; Lee, Hyun Jik; Ko, So Hee; Chae, Chang Woo; Han, Ho Jae

    2017-08-30

    Glucocorticoid has been widely accepted to induce Alzheimer's disease, but the nongenomic effect of glucocorticoid on amyloid β (Aβ) generation has yet to be studied. Here, we investigated the effect of the nongenomic pathway induced by glucocorticoid on amyloid precursor protein processing enzymes as well as Aβ production using male ICR mice and human neuroblastoma SK-N-MC cells. Mice groups exposed to restraint stress or intracerebroventricular injection of Aβ showed impaired cognition, decreased intracellular glucocorticoid receptor (GR) level, but elevated level of membrane GR (mGR). In this respect, we identified the mGR-dependent pathway evoked by glucocorticoid using impermeable cortisol conjugated to BSA (cortisol-BSA) on SK-N-MC cells. Cortisol-BSA augmented the expression of β-site amyloid precursor protein cleaving enzyme 1 (BACE1), the level of C-terminal fragment β of amyloid precursor protein (C99) and Aβ production, which were maintained even after blocking intracellular GR. We also found that cortisol-BSA enhanced the interaction between mGR and Gαs, which colocalized in the lipid raft. The subsequently activated CREB by cortisol-BSA bound to the CRE site of the BACE1 promoter increasing its expression, which was downregulated by inhibiting CBP. Consistently, blocking CBP attenuated cognitive impairment and Aβ production induced by corticosterone treatment or intracerebroventricular injection of Aβ more efficiently than inhibiting intracellular GR in mice. In conclusion, glucocorticoid couples mGR with Gαs and triggers cAMP-PKA-CREB axis dependent on the lipid raft to stimulate BACE1 upregulation and Aβ generation. SIGNIFICANCE STATEMENT Patients with Alzheimer's disease (AD) have been growing sharply and stress is considered as the major environment factor of AD. Glucocorticoid is the primarily responsive factor to stress and is widely known to induce AD. However, most AD patients usually have impaired genomic pathway of glucocorticoid

  9. 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)

  10. Radiological Effluent Technical Specifications (RETS) implementation: Zion Generating Station Units 1 and 2

    International Nuclear Information System (INIS)

    Serrano, W.; Akers, D.W.; Duce, S.W.; Mandler, J.W.; Simpson, F.B.; Young, T.E.

    1985-06-01

    A review of the Radiological Effluent Technical Specifications (RETS) of the Zion Generating Station Units 1 and 2 was performed. The principal review guidelines used were NUREG-0133, ''Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants,'' and Draft 7 of NUREG-0472, Revision 3, ''Radiological Effluent Technical Specifications for Pressurized Water Reactors.'' Draft submittals were discussed with the Licensee by both EG and G and the NRC staff until all items requiring changes to the Technical Specifications were resolved. The Licensee then submitted final proposed RETS to the NRC which were evaluated and found to be in compliance with the NRC review guidelines. The proposed Offsite Dose Calculation Manual was reviewed and generally found to be consistent with the NRC review guidelines. 35 refs., 2 figs., 1 tab

  11. 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.

  12. 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

  13. 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.

  14. Introduction of radiological protection; Pengenalan kepada perlindungan radiologi

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1988-12-31

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

  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 Planning Tool for Estimating Waste Generated by a Radiological Incident and Subsequent Decontamination Efforts - 13569

    Energy Technology Data Exchange (ETDEWEB)

    Boe, Timothy [Oak Ridge Institute for Science and Education, Research Triangle Park, NC 27711 (United States); Lemieux, Paul [U.S. Environmental Protection Agency, Research Triangle Park, NC 27711 (United States); Schultheisz, Daniel; Peake, Tom [U.S. Environmental Protection Agency, Washington, DC 20460 (United States); Hayes, Colin [Eastern Research Group, Inc, Morrisville, NC 26560 (United States)

    2013-07-01

    Management of debris and waste from a wide-area radiological incident would probably constitute a significant percentage of the total remediation cost and effort. The U.S. Environmental Protection Agency's (EPA's) Waste Estimation Support Tool (WEST) is a unique planning tool for estimating the potential volume and radioactivity levels of waste generated by a radiological incident and subsequent decontamination efforts. The WEST was developed to support planners and decision makers by generating a first-order estimate of the quantity and characteristics of waste resulting from a radiological incident. The tool then allows the user to evaluate the impact of various decontamination/demolition strategies on the waste types and volumes generated. WEST consists of a suite of standalone applications and Esri{sup R} ArcGIS{sup R} scripts for rapidly estimating waste inventories and levels of radioactivity generated from a radiological contamination incident as a function of user-defined decontamination and demolition approaches. WEST accepts Geographic Information System (GIS) shape-files defining contaminated areas and extent of contamination. Building stock information, including square footage, building counts, and building composition estimates are then generated using the Federal Emergency Management Agency's (FEMA's) Hazus{sup R}-MH software. WEST then identifies outdoor surfaces based on the application of pattern recognition to overhead aerial imagery. The results from the GIS calculations are then fed into a Microsoft Excel{sup R} 2007 spreadsheet with a custom graphical user interface where the user can examine the impact of various decontamination/demolition scenarios on the quantity, characteristics, and residual radioactivity of the resulting waste streams. (authors)

  17. 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

  18. 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

  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.

    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

  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.

    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

  1. Power plant site evaluation - Douglas Point site. Volume 1, part 2. Final report

    International Nuclear Information System (INIS)

    1977-11-01

    This is part of a series of reports containing an evaluation of the proposed Douglas Point nuclear generating station site located on the Potomac River in Maryland 30 miles south of Washington, DC. This report contains sections on cooling tower air emissions, noise impacts, transmission line effects, radiation from normal releases, site features affecting radiological accidents, and meteorology

  2. 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

  3. 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

  4. 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

  5. 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

  6. 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

  7. 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

  8. 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

  9. 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

  10. 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...

  11. 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

  12. 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.

  13. 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

  14. 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.

  15. A Novel Pentadentate Coordination Mode for the Carbonato Bridge: Synthesis, Crystal Structure, and Magnetic Behavior of (&mgr;(3)-CO(3))[Ni(3)(Medpt)(3)(NCS)(4)], a New Trinuclear Nickel(II) Carbonato-Bridged Complex with Strong Antiferromagnetic Coupling.

    Science.gov (United States)

    Escuer, Albert; Vicente, Ramon; Kumar, Sujit B.; Solans, Xavier; Font-Bardía, Mercé; Caneschi, Andrea

    1996-05-22

    The trinuclear complex (&mgr;(3)-CO(3))[Ni(3)(Medpt)(3)(NCS)(4)] was obtained by reaction of basic solutions of nickel(II), Medpt (bis(3aminopropyl)methylamine) and thiocyanate ligand with atmospheric CO(2) or by simple reaction with carbonate anion. (&mgr;(3)-CO(3))[Ni(3)(Medpt)(3)(NCS)(4)] crystallizes in the triclinic system, space group P&onemacr;, with a = 12.107(5) Å, b = 12.535(7) Å, c = 16.169(9) Å, alpha = 102.69(5) degrees, beta = 92.91(5) degrees, gamma = 118.01(4) degrees, Z = 2, and R = 0.043. The three nickel atoms are asymmetrically bridged by one pentadentate carbonato ligand, which shows a novel coordination mode. The (&mgr;(3)-CO(3))[Ni(3)(Medpt)(3)(NCS)(4)] compound shows a very strong antiferromagnetic coupling. Fit as irregular triangular arrangement gave J(1) = -88.4, J(2) = -57.7, and J(3) = -9.6 cm(-)(1), which is the strongest AF coupling observed to date for Ni(3) compounds. The magnetic behavior of the carbonato bridge is discussed.

  16. 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

  17. 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

  18. 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

  19. Cultivation of university students in radiology using research facilities at KAERI

    Energy Technology Data Exchange (ETDEWEB)

    Shin, Byung Chul [Nuclear Training and Education Center, Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2017-09-15

    The purpose of present research is to offer a specialized educational opportunity for potential users, university students in radiology, by developing specific curriculum on site at KAERI, using HANARO research reactor and National radiation research facilities. The specific items of this research accomplished are: First, Development and operation of various curricula for specific research using HANARO and National radiation research facilities to provide university students with opportunities to use the facilities. Second, Operation of the experiment training programs for university students in radiology to foster next generation specialists. Third, through the on-site experiment training for students in radiology, support future potential experts of the radiation research fields, and broaden the base. A textbook and a teaching aid, a questionnaire have been developed to support the program. 714 university students have completed the courses for radiology experiment from 2006 to 2017. It is hoped that these experiments broaden public awareness and acceptance by the present and potential future utilization of the research reactor and national radiation research facilities, thereby bring positive impacts to policy making.

  20. 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.)

  1. 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

  2. INDUSTRIAL/MILITARY ACTIVITY-INITIATED ACCIDENT SCREENING ANALYSIS

    Energy Technology Data Exchange (ETDEWEB)

    D.A. Kalinich

    1999-09-27

    Impacts due to nearby installations and operations were determined in the Preliminary MGDS Hazards Analysis (CRWMS M&O 1996) to be potentially applicable to the proposed repository at Yucca Mountain. This determination was conservatively based on limited knowledge of the potential activities ongoing on or off the Nevada Test Site (NTS). It is intended that the Industrial/Military Activity-Initiated Accident Screening Analysis provided herein will meet the requirements of the ''Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants'' (NRC 1987) in establishing whether this external event can be screened from further consideration or must be included as a design basis event (DBE) in the development of accident scenarios for the Monitored Geologic Repository (MGR). This analysis only considers issues related to preclosure radiological safety. Issues important to waste isolation as related to impact from nearby installations will be covered in the MGR performance assessment.

  3. 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

  4. 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

  5. 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 ...

  6. 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

  7. 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

  8. Radiological protection challenges at B.N.G. Sellafield

    International Nuclear Information System (INIS)

    Hallard, R.; Anderson, B.; Hutton, E.

    2006-01-01

    The UK Nuclear Industry is in the midst of a period of intense change with the formation of a national body to manage the clean up of Nuclear facilities. Previous owners of nuclear sites have become contractors and the emphasis has switched from production facilities for power or reprocessing to decommissioning and clean up. Many of the older facilities were not designed for decommissioning and now require attention to reduce risks. Sellafield represents a microcosm of the industry with operating and production facilities, waste storage facilities and plants awaiting or undergoing decommissioning. The experience already gained in decommissioning of redundant facilities over the last decade is being used to develop an accelerated response to clean up of the past. The major challenge is to accommodate the changes whilst monitoring and improving Radiological standards and performance. This paper describes a number of issues to which the site must be managed to ensure that the current Radiological performance is maintained and improved. The dose control arrangements for some 6000 radiation workers on the site requires a change in approach as we move towards localised project based systems with an increasingly mobile workforce. Work is proceeding to introduce a new generation of short term dose control equipment with an emphasis on safety culture and management responsibilities for dose control. The achievement and demonstration of ALARP in these circumstances, is being reviewed in situations where timescale, overall risk to public and workforce and exposure to non radiological hazards are factors. Clean up requires more attention to clearance of materials and this aspect has an increasing profile to recognize the need to balance risk and expenditure. The paper will review the current Radiological Protection challenges to the changing Nuclear Industry using the Sellafield site as the prime example and will discuss achievements and areas where further work is necessary

  9. 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

  10. 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

  11. 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.

  12. 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

  13. 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)

  14. 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

  15. 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

  16. 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.''

  17. 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

  18. Radiological hazards of TENORM in precipitated calcium carbonate generated as waste at nitrophosphate fertilizer plant in Pakistan

    Energy Technology Data Exchange (ETDEWEB)

    Javied, Sabiha, E-mail: sabihajavied@yahoo.com [Pakistan Institute of Engineering and Applied Sciences (PIEAS), Nilore 45650, Islamabad (Pakistan); Akhtar, Nasim [Nuclear Institute for Agriculture and Biology (NIAB), Jhang Road, Faisalabad (Pakistan); Tufail, M. [Pakistan Institute of Engineering and Applied Sciences (PIEAS), Nilore 45650, Islamabad (Pakistan)

    2011-08-15

    Highlights: {yields} NORM (naturally occurring radioactive material) in phosphate rock (PR) is converted to TENORM (technologically enhanced naturally occurring radioactive material) as a result of chemical processing of the PR to make phosphate fertilizers. {yields} Precipitated calcium carbonate (PCC) is generated as process waste during nitrophosphate fertilizer production, which contains TENORM. {yields} Activity concentration of the radionuclide in the TENORM was measured using gamma spectrometry and radiological hazard was derived from the measured activities. {yields} Radiological pollution in the environment from TENORM in the PCC has been addressed. {yields} Restricted application of the PCC dose not pose a significant radiological hazard. -- Abstract: The NORM (naturally occurring radioactive material) in phosphate rock is transferred as TENORM (technologically enhanced naturally occurring radioactive material) to phosphatic fertilizers and to the waste generated by the chemical processes. The waste generated at the NP (nitrophosphate) fertilizer plant at Multan in Pakistan is PCC (precipitated calcium carbonate). Thirty samples of the PCC were collected from the heaps of the waste near the fertilizer plant. Activity concentrations of radionuclides in the waste samples were measured by using the technique of gamma ray spectrometry consisting of coaxial type HPGe (high purity germanium) detector coupled with a PC (personal computer) based MCA (multichannel analyzer) through a spectroscopy amplifier. Activity concentrations of {sup 226}Ra, {sup 232}Th and {sup 40}K in the waste samples were determined to be 273 {+-} 23 (173-398), 32 {+-} 4 (26-39) and 56 {+-} 5 (46-66) Bq kg{sup -1} respectively. The activity concentration of {sup 226}Ra in the PCC waste was found to be higher than that in naturally occurring calcium carbonate (limestone and marble) and in worldwide soil. Radiological hazard was estimated from indoor and outdoor exposure to gamma rays from

  19. 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

  20. Alternatives for management of wastes generated by the formerly utilized sites remedial action program and supplement

    International Nuclear Information System (INIS)

    Gilbert, T.L.; Peterson, J.M.; Vocke, R.W.; Alexander, J.K.

    1983-03-01

    Alternatives for disposal or stabilization of the wastes generated by the US Department of Energy's Formerly Utilized Sites Remedial Action Program (FUSRAP) are identified and compared, with emphasis on the long-term aspects. These wastes consist of soil material and rubble containing trace amounts of radionuclides. A detailed pathway analysis for the dose to the maximally exposed individual is carried out using an adaptation of the natural analogue method. Comparisons of the different alternatives, based on the results of the pathway analysis and qualitative cost considerations, indicate that, if the hazard is such that the wastes must be removed and disposed of rather than stabilized in place, disposal by immediate dispersal is preferable to containment, and containment followed by slow planned dispersal is preferable to containment without dispersal. The Supplement presents refinements of work that was reported at the 1982 International Decommissioning Symposium. The new material consists of revisions of the estimates of the predicted potential dose to the maximally exposed individual and a more detailed comparative assessment of the radiological impacts of alternatives for management of wastes generated by the US Department of Energy's Formerly Utilized Sites Remedial Action Program (FUSRAP)

  1. 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)

  2. 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

  3. Development of a real-time radiological dose assessment system

    Energy Technology Data Exchange (ETDEWEB)

    Han, Moon Hee; Lee, Young Bok; Kim, Eun Han; Suh, Kyung Suk; Hwang, Won Tae; Choi, Young Gil

    1997-07-01

    A radiological dose assessment system named FADAS has been developed. This system is necessary to estimated the radiological consequences against a nuclear accident. Mass-consistent wind field module was adopted for the generation of wind field over the whole domain using the several measured wind data. Random-walk dispersion module is used for the calculation of the distribution of radionuclides in the atmosphere. And volume-equivalent numerical integration method has been developed for the assessment of external gamma exposure given from a randomly distributed radioactive materials and a dose data library has been made for rapid calculation. Field tracer experiments have been carried out for the purpose of analyzing the site-specific meteorological characteristics and increasing the accuracy of wind field generation and atmospheric dispersion module of FADAS. At first, field tracer experiment was carried out over flat terrain covered with rice fields using the gas samplers which were designed and manufactured by the staffs of KAERI. The sampled gas was analyzed using gas chromatograph. SODAR and airsonde were used to measure the upper wind. Korean emergency preparedness system CARE was integrated at Kori 4 nuclear power plants in 1995. One of the main functions of CARE is to estimate the radiological dose. The developed real-time dose assessment system FADAS was adopted in CARE as a tool for the radiological dose assessment. (author). 79 refs., 52 tabs., 94 figs.

  4. 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)

  5. 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

  6. NV/YMP radiological control manual, Revision 2

    International Nuclear Information System (INIS)

    Gile, A.L.

    1996-11-01

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

  7. NV/YMP radiological control manual, Revision 2

    Energy Technology Data Exchange (ETDEWEB)

    Gile, A.L. [comp.

    1996-11-01

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

  8. 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

  9. 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

  10. The newsletter 'European Research in Radiological Sciences'

    International Nuclear Information System (INIS)

    Pihet, P.; D'Errico, F.; Doerr, W.; Gruenberger, M.; Schofield, P.

    2004-01-01

    The newsletter 'European Research in Radiological Sciences' is jointly published by the European Late Effects Project Group and the European Radiation Dosimetry Group to disseminate information about research projects and activities carried out under the EURATOM Framework Programme. Since May 2003, the Newsletter is operated interactively from the Internet. The new site uses a dedicated database that automatically generates HTML pages. This system developed at the Univ. of Cambridge provides an innovative approach to improve the dissemination of project information. (authors)

  11. 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 ...

  12. 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.

  13. 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

  14. 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

  15. 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.

  16. Ionizing secondary radiation generated by analog radiological and digital coronary cine angiographic equipment. Influence of external protection devices

    International Nuclear Information System (INIS)

    Ramirez N, Alfredo; Farias Ch, Eric; Silva J, Ana Maria; Leyton L, Fernando; Oyarzun C, Carlos; Ugalde P, Hector; Dussaillant, Gaston; Cumsille G, Angel

    2000-01-01

    Exposure to ionizing radiation is a know hazard of radiological procedures. Aim: to compare the emission of secondary ionizing radiation from two coronary angiographic equipments, one with digital and the other with analog image generation. To evaluate the effectiveness of external radiological protection devices. Material and methods: environmental and fluoroscopy generated radiation in the cephalic region of the patient was measured during diagnostic coronary angiographies. Ionizing radiation generated in anterior left oblique protection (ALO) and anterior right oblique protection (ARO) were measured with and without leaded protections. In 19 patients (group 1), a digital equipment was used and in 21 (group 2), an analog equipment. Results: header radiation for group 1 and 2 was 1194±337 and 364±222 μGray/h respectively (p≤0.001). During fluoroscopy and with leaded protection generated radiation for groups 1 and 2 was 612±947 and 70±61μGray/h respectively (p≤0.001). For ALO projection, generated for groups 1 and 2 was 105±47 and 71±192 μGray/h respectively (p≤0.001). During filming the radiation for ALO projection for groups 1 and 2 was 7252±9569 and 1671±2038 μGray/h respectively (p=0.03). Out of the protection zone, registered radiation during fluoroscopy for groups 1 and 2 was 2800±1741 and 1318±954 μGray/h respectively (p≤0.001); during filming, the figures were 15500±5840 and 18961±10599 μGray/h respectively (NS). Conclusions: digital radiological equipment has a lower level of ionizing radiation emission than the analog equipment

  17. 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

  18. 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.

  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. 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

  1. Conventional radiology and genetic dose

    International Nuclear Information System (INIS)

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

    1992-01-01

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

  2. 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

  3. 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.

  4. 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)

  5. Effective stochastic generator with site-dependent interactions

    Science.gov (United States)

    Khamehchi, Masoumeh; Jafarpour, Farhad H.

    2017-11-01

    It is known that the stochastic generators of effective processes associated with the unconditioned dynamics of rare events might consist of non-local interactions; however, it can be shown that there are special cases for which these generators can include local interactions. In this paper, we investigate this possibility by considering systems of classical particles moving on a one-dimensional lattice with open boundaries. The particles might have hard-core interactions similar to the particles in an exclusion process, or there can be many arbitrary particles at a single site in a zero-range process. Assuming that the interactions in the original process are local and site-independent, we will show that under certain constraints on the microscopic reaction rules, the stochastic generator of an unconditioned process can be local but site-dependent. As two examples, the asymmetric zero-temperature Glauber model and the A-model with diffusion are presented and studied under the above-mentioned constraints.

  6. 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.)

  7. 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)

  8. Non-Destructive Method by Gamma Sampling Measurements for Radiological Characterization of a Steam Generator: Physical and Numerical Modeling for ANIMMA (23-27 June 2013)

    International Nuclear Information System (INIS)

    Auge, G.; Rottner, B.; Dubois, C.

    2013-06-01

    The radiological characterization of a steam generator consists of evaluating the global radiological activity in the tube bundle. In this paper, we present a non-destructive method and the results analysis of the gamma sampling measurements from a sample of U-tubes in the bundle. On site, the implementation of the methodology is fairly easy. But the analysis of the results is more complicated due to the long path of the gamma ray (from 60 Co quite penetrating), and also the heterogeneous activity of U-tubes bundle, which have not the same life cycle. We explain why the periodic spatial arrangement complicates also the analysis. Furthermore, we have taken into account the environment of all tubes measured because of all the external influence activity of others U-tubes (the nearest, the most distant and potential hot spot). A great amount of independent influence coefficient had to be considered (roughly 18 million). Based on a physical and numerical modeling, and using a Cholesky algorithm solving the problem and saving time machine. (authors)

  9. 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

  10. Internet use in radiology: results of a nationwide survey

    Energy Technology Data Exchange (ETDEWEB)

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

    1999-08-01

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

  11. Internet use in radiology: results of a nationwide survey

    International Nuclear Information System (INIS)

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

    1999-01-01

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

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

    International Nuclear Information System (INIS)

    Thome, D.J.

    1995-01-01

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

  13. 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

  14. 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

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

    International Nuclear Information System (INIS)

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

    2018-01-01

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

  16. 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)

  17. 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

  18. Informatics in radiology: automated Web-based graphical dashboard for radiology operational business intelligence.

    Science.gov (United States)

    Nagy, Paul G; Warnock, Max J; Daly, Mark; Toland, Christopher; Meenan, Christopher D; Mezrich, Reuben S

    2009-11-01

    Radiology departments today are faced with many challenges to improve operational efficiency, performance, and quality. Many organizations rely on antiquated, paper-based methods to review their historical performance and understand their operations. With increased workloads, geographically dispersed image acquisition and reading sites, and rapidly changing technologies, this approach is increasingly untenable. A Web-based dashboard was constructed to automate the extraction, processing, and display of indicators and thereby provide useful and current data for twice-monthly departmental operational meetings. The feasibility of extracting specific metrics from clinical information systems was evaluated as part of a longer-term effort to build a radiology business intelligence architecture. Operational data were extracted from clinical information systems and stored in a centralized data warehouse. Higher-level analytics were performed on the centralized data, a process that generated indicators in a dynamic Web-based graphical environment that proved valuable in discussion and root cause analysis. Results aggregated over a 24-month period since implementation suggest that this operational business intelligence reporting system has provided significant data for driving more effective management decisions to improve productivity, performance, and quality of service in the department.

  19. 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

  20. 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

  1. 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.

  2. 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.

  3. Next Generation Nuclear Plant Project Evaluation of Siting a HTGR Co-generation Plant on an Operating Commercial Nuclear Power Plant Site

    International Nuclear Information System (INIS)

    Demick, L.E.

    2011-01-01

    This paper summarizes an evaluation by the Idaho National Laboratory (INL) Next Generation Nuclear Plant (NGNP) Project of siting a High Temperature Gas-cooled Reactor (HTGR) plant on an existing nuclear plant site that is located in an area of significant industrial activity. This is a co-generation application in which the HTGR Plant will be supplying steam and electricity to one or more of the nearby industrial plants.

  4. Next Generation Nuclear Plant Project Evaluation of Siting a HTGR Co-generation Plant on an Operating Commercial Nuclear Power Plant Site

    Energy Technology Data Exchange (ETDEWEB)

    L.E. Demick

    2011-10-01

    This paper summarizes an evaluation by the Idaho National Laboratory (INL) Next Generation Nuclear Plant (NGNP) Project of siting a High Temperature Gas-cooled Reactor (HTGR) plant on an existing nuclear plant site that is located in an area of significant industrial activity. This is a co-generation application in which the HTGR Plant will be supplying steam and electricity to one or more of the nearby industrial plants.

  5. 618-11 Burial Ground USRADS radiological surveys

    International Nuclear Information System (INIS)

    Wendling, M.A.

    1994-01-01

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

  6. 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

  7. 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

  8. 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

  9. Second generation extracorporeal lithotripsy: Whither American radiologic leadership

    International Nuclear Information System (INIS)

    Pfister, R.C.

    1987-01-01

    Extracorporeal shock wave lithotripsy was developed by Dornier Medical Systems, Inc., and West German urologists. In the United States the marketing, training, and operation of these wet-tub units were limited to urologists. New dry-treatment lithotriptors are being developed in various countries, including the United States (Medstone), and will be marketed to radiologists, among others, once approved by the FDA for clinical use; future applications will include gallstones as well as renal calculi. Some of these new lithotripors are radiologically intensive, requiring US or fluroscopic guidance and radiography. Since the stone pulverization process in an image-controlled procedure, the units should be managed by radiologists; this will require supportive leadership from all current radiology department chiefs. This presentation reviews the lithotriptors available

  10. 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)

  11. Aerial radiological survey of the creeks and tributaries near the Rancho Seco Nuclear Generation Station, Clay Station, California. Date of survey: December 1984

    International Nuclear Information System (INIS)

    1986-06-01

    Radiological contamination due to man-made radionuclides was detected using hand-held instruments in the summer of 1984 in the creeks and tributaries near the Rancho Seco Nuclear Generating Station at Clay Station, California. To help determine the extent of the contamination an aerial radiological survey centered over the creeks and tributaries and including the Rancho Seco facility was conducted during the period 3 to 15 December 1984. Radiological contaminants were detected along a 9-mile segment of the system of creeks in the area. These contaminants included cesium-134, cesium-137, and cobalt-60. Radiation measurements away from the contaminated areas were the same as those made during the aerial radiological survey conducted in 1980

  12. 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

  13. 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

  14. 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

  15. Radiological Consequences Analysis for Abnormal Condition on NPPs 1000 MWe by Using Radcon Model

    International Nuclear Information System (INIS)

    Pande Mande Udiyani; Sri Kuntjoro

    2009-01-01

    The operation of NPPs (Nuclear Power Plants) in Indonesia to anticipates rare of energy will generate various challenges, especially about NPPs safety. So installation organizer of nuclear must provide scientific argument to safety NPPs, one of them is by providing document of safety analysis. Calculation of radiological consequences after abnormal condition applies on generic PWR-1000 power reactor. Calculation is done by using program package RadCon (Radiological Consequences Model), with postulate condition is based on DBA (Design Basis Accident). Calculation of dispersion of radionuclide concentration is using PC-COSYMA as input data for RadCon. Simulation for radiological consequences analysis uses by site data sample. Analysis result shows that maximum receiving of internal - externals radiological consequence for short term and long-term below 1 km radius area is below the limit acceptably effective dose for a member of the public as a result of an accident which should not exceed 5 mSv (ICRP 1990). (author)

  16. Waste Handling Equipment Development Test and Evaluation Study

    International Nuclear Information System (INIS)

    R.L. Tome

    1998-01-01

    The purpose of this study is to identify candidate Monitored Geologic Repository (MGR) surface waste handling equipment for development testing. This study will also identify strategies for performing the development tests. Development testing shall be implemented to support detail design and reduce design risks. Development testing shall be conducted to confirm design concepts, evaluate alternative design concepts, show the availability of needed technology, and provide design documentation. The candidate equipment will be selected from MGR surface waste handling equipment that is the responsibility of the Management and Operating Contractor (M and O) Surface Design Department. The equipment identified in this study is based on Viability Assessment (VA) design. The ''Monitored Geologic Repository Test and Evaluation Plan'' (MGR T and EP), Reference 5.1, was used as a basis for this study. The MGR T and EP reflects the extent of test planning and analysis that can be conducted, given the current status of the MGR requirements and latest VA design information. The MGR T and EP supports the appropriate sections in the license application (LA) in accordance with 10 CFR 60.2 1(c)(14). The MGR T and EP describes the following test activities: site characterization to confirm, by test and analysis, the suitability of the Yucca Mountain site for housing a geologic repository; development testing to investigate and document design concepts to reduce risk; qualification testing to verify equipment compliance with design requirements, specifications, and regulatory requirements; system testing to validate compliance with MGR requirements, which include the receipt, handling, retrieval, and disposal of waste; periodic performance testing to verify preclosure requirements and to demonstrate safe and reliable MGR operation; and performance confirmation modeling, testing, and analysis to verify adherence to postclosure regulatory requirements. Development test activities can be

  17. Radiological safety evaluation report for NUWAX-79 exercise

    International Nuclear Information System (INIS)

    King, W.C.

    1979-03-01

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

  18. Radiological evaluation of familial osteopetrosis

    International Nuclear Information System (INIS)

    Moon, Moo Chang; Kang, Shin Wha; Won, Jong Jin; Rhee, Song Joo; Choi, Ki Chul

    1980-01-01

    Authors found 16 patients with benign osteopetrosis out of 62 members of 4 families and analysed these patients clinically, radiologically, hematologically and biochemically at the Department of Radiology, Jeonbug National University Hospital from October 1977 to June 1980. The results are as follows; 1. We obtained that there is evidence of familial tendency in developing osteopetrosis because of the fact that 15 patients (94%) developed in 3 families and more than 2 patients in each family. In genetical point of view we suspected dominant trait of inheritance and could rule out recessive trait because patients were found in successive generations except for one family. There were no consangulneous marriages among the parents of these patients. 2. The majority of patients were adolescent or adult above 10 years of age when the disease was diagnosed. The incidence was identical in both sex. 3. No clinical symptoms and historical abnormalities were found in 11 patients (69%) and 5 patients (31%) showed only mild symptoms. Among 5 patients with clinical symptoms 3 patients showed pathologic fractures. In all 3 patients, fractures occurred only by mild trauma and affected sites were tubular bones and they were transverse type. 4. There were no specific relationship between ABO types and Rh reactions in developing osteopetrosis and no specific findings in hematological, biochemical and routine urinalysis. 5. The only diagnostic finding in most patients were the typical and specific radiological findings

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

    International Nuclear Information System (INIS)

    Thome, D.J.

    1994-01-01

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

  20. 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)

  1. The Radiological Research Accelerator Facility

    International Nuclear Information System (INIS)

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

    1990-07-01

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

  2. 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

  3. Overview of Generation IV (Gen IV) Reactor Designs - Safety and Radiological Protection Considerations

    International Nuclear Information System (INIS)

    Baudrand, Olivier; Blanc, Daniel; Ivanov, Evgeny; Bonneville, Herve; Clement, Bernard; Kissane, Martin; Meignen, Renaud; Monhardt, Daniel; Nicaise, Gregory; Bourgois, Thierry; Bruna, Giovanni; Hache, Georges; Repussard, Jacques

    2012-01-01

    The purpose of this document is to provide an updated overview of specific safety and radiological protection issues for all the reactor concepts adopted by the GIF (Generation IV International Forum), independent of their advantages or disadvantages in terms of resource optimization or long-lived-waste reduction. In particular, this new document attempts to bring out the advantages and disadvantages of each concept in terms of safety, taking into account the Western European Nuclear Regulators' Association (WENRA) statement concerning safety objectives for new nuclear power plants. Using an identical framework for each reactor concept (sodium-cooled fast reactors or SFR, high / very-high temperature helium-cooled reactors of V/HTR, gas-cooled fast reactors or GFR, lead-or lead / bismuth-cooled fast reactors or LFR, molten salt reactors or MSR, and supercritical-water-cooled reactors or SCWR), this summary report provides some general conclusions regarding their safety and radiological protection issues, inspired by WENRA's safety objectives and on the basis of available information. Initial lessons drawn from the events at the Fukushima-Daiichi nuclear power plant in March 2011 have also been taken into account in IRSN's analysis of each reactor concept

  4. 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)

  5. 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)

  6. 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

  7. 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

  8. Mononuclear Amido and Binuclear Imido Zirconium Complexes Supported by Dibenzotetraaza[14]annulene Ligands. X-ray Structure of [(Me(4)taa)Zr(&mgr;-NR)(2)Zr(NHR)(2)] (R = Bu(t) or 2,6-C(6)H(3)Me(2)).

    Science.gov (United States)

    Nikonov, Georgii I.; Blake, Alexander J.; Mountford, Philip

    1997-03-12

    Reaction of 2 equiv of Li[NH-2,6-C(6)H(3)R(2)] with [(Me(4)taa)ZrCl(2)] (Me(4)taaH(2) = tetramethyldibenzotetraaza[14]annulene) gives the bis(amido) derivatives [(Me(4)taa)Zr(NH-2,6-C(6)H(3)R(2))(2)] [R = Pr(i) (1) and Me (2)]. Addition of Me(4)taaH(2) to [Zr(N-2,6-C(6)H(3)Pr(i)(2))(NH-2,6-C(6)H(3)Pr(i)(2))(2)(py)(2)] also affords 1. The reaction of 2 equiv of aryl or alkyl amines H(2)NR with the bis(alkyl) complex [(Me(4)taa)Zr(CH(2)SiMe(3))(2)] is the most versatile method for preparing [(Me(4)taa)Zr(NHR)(2)] (R = 2,6-C(6)H(3)Pr(i)(2), 2,6-C(6)H(3)Me(2), Ph, or Bu(t)). Reaction of 1 equiv of Me(4)taaH(2) with the binuclear complexes [(Bu(t)NH)(2)Zr(&mgr;-NBu(t))(2)Zr(NHBu(t))(2)] or [(py)(HN-2,6-C(6)H(3)Me(2))(2)Zr(&mgr;-N-2,6-C(6)H(3)Me(2))(2)Zr(NH-2,6-C(6)H(3)Me(2))(2)(py)] gives the asymmetrically substituted derivatives [(Me(4)taa)Zr(&mgr;-NR)(2)Zr(NHR)(2)] [R = Bu(t) (6) or 2,6-C(6)H(3)Me(2) (8)], which have been crystallographically characterized.

  9. Assessment of management alternatives for LWR wastes. Volume 8. Cost and radiological impact associated with near-surface disposal of reactor waste (Spanish concept)

    International Nuclear Information System (INIS)

    Alamo Berna, S.; Sanchez Delgado, N.

    1993-01-01

    This report deals with the determination of the cost and the radiological impact associated with a near-surface disposal site (Spanish concept) for low and medium-level radioactive waste generated during operation of a 20 GWe nuclear park composed of LWRs for 30 years. This study is part of an overall theoretical exercise aimed at evaluating a selection of management routes for LWR waste based on economical and radiological criteria

  10. Assessment of management alternatives for LWR wastes. Volume 7. Cost and radiological impact associated with near-surface disposal of reactor waste (French concept)

    International Nuclear Information System (INIS)

    Malherbe, J.

    1993-01-01

    This report deals with the determination of the cost and the radiological impact associated with a near-surface disposal site (French concept) for low and medium-level radioactive waste generated during operation of a 20 GWe nuclear park composed of LWRs for 30 years. This study is part of an overall theoretical exercise aimed at evaluating a selection of management routes for LWR waste based on economical and radiological criteria

  11. 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

  12. 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

  13. 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

  14. 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.

  15. Exploring the Potential of Generative Adversarial Networks for Synthesizing Radiological Images of the Spine to be Used in In Silico Trials

    Directory of Open Access Journals (Sweden)

    Fabio Galbusera

    2018-05-01

    Full Text Available In silico trials recently emerged as a disruptive technology, which may reduce the costs related to the development and marketing approval of novel medical technologies, as well as shortening their time-to-market. In these trials, virtual patients are recruited from a large database and their response to the therapy, such as the implantation of a medical device, is simulated by means of numerical models. In this work, we propose the use of generative adversarial networks to produce synthetic radiological images to be used in in silico trials. The generative models produced credible synthetic sagittal X-rays of the lumbar spine based on a simple sketch, and were able to generate sagittal radiological images of the trunk using coronal projections as inputs, and vice versa. Although numerous inaccuracies in the anatomical details may still allow distinguishing synthetic and real images in the majority of cases, the present work showed that generative models are a feasible solution for creating synthetic imaging data to be used in in silico trials of novel medical devices.

  16. 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

  17. Teaching Radiology Trainees From the Perspective of a Millennial.

    Science.gov (United States)

    Chen, Po-Hao; Scanlon, Mary H

    2018-06-01

    The millennial generation consists of today's medical students, radiology residents, fellows, and junior staff. Millennials' comfort with immersive technology, high expectations for success, and desire for constant feedback differentiate them from previous generations. Drawing from an author's experiences through radiology residency and fellowship as a millennial, from published literature, and from the mentorship of a long-time radiology educator, this article explores educational strategies that embrace these characteristics to engage today's youngest generation both in and out of the reading room. Copyright © 2018 The Association of University Radiologists. Published by Elsevier Inc. All rights reserved.

  18. NV/YMP RADIOLOGICAL CONTROL MANUAL

    Energy Technology Data Exchange (ETDEWEB)

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

    2004-11-01

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

  19. NV/YMP RADIOLOGICAL CONTROL MANUAL

    International Nuclear Information System (INIS)

    2004-01-01

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

  20. 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.

  1. 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

  2. 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...

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

    International Nuclear Information System (INIS)

    1996-02-01

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

  4. 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

  5. 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.)

  6. The radiological diagnosis of bone tumors

    International Nuclear Information System (INIS)

    Freyschmidt, J.

    1979-01-01

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

  7. Aerial radiological survey of the San Onofre Nuclear Generating Station and surrounding area, San Clemente, California

    International Nuclear Information System (INIS)

    Hilton, L.K.

    1980-12-01

    An airborne radiological survey of an 11 km 2 area surrounding the San Onofre Nuclear Generating Station was made 9 to 17 January 1980. Count rates observed at 60 m altitude were converted to exposure rates at 1 m above the ground and are presented in the form of an isopleth map. Detected radioisotopes and their associated gamma ray exposure rates were consistent with that expected from normal background emitters, except directly over the plant

  8. 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)

  9. 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)

  10. 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.

  11. 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

  12. Options for Steam Generator Decommissioning

    International Nuclear Information System (INIS)

    Krause, Gregor; Amcoff, Bjoern; Robinson, Joe

    2016-01-01

    Selecting the best option for decommissioning steam generators is a key consideration in preparing for decommissioning PWR nuclear power plants. Steam Generators represent a discrete waste stream of large, complex items that can lend themselves to a variety of options for handling, treatment, recycling and disposal. Studsvik has significant experience in processing full size Steam Generators at its metal recycling facility in Sweden, and this paper will introduce the Studsvik steam generator treatment concept and the results achieved to date across a number of projects. The paper will outline the important parameters needed at an early stage to assess options and to help consider the balance between off-site and on-site treatment solutions, and the role of prior decontamination techniques. The paper also outlines the use of feasibility studies and demonstration projects that have been used to help customers prepare for decommissioning. The paper discusses physical, radiological and operational history data, Pro and Contra factors for on- and off-site treatment, the role of chemical decontamination prior to treatment, planning for off-site shipments as well as Studsvik experience This paper has an original focus upon the coming challenges of steam generator decommissioning and potential external treatment capacity constraints in the medium term. It also focuses on the potential during operations or initial shut-down to develop robust plans for steam generator management. (authors)

  13. Features generated for computational splice-site prediction correspond to functional elements

    Directory of Open Access Journals (Sweden)

    Wilbur W John

    2007-10-01

    Full Text Available Abstract Background Accurate selection of splice sites during the splicing of precursors to messenger RNA requires both relatively well-characterized signals at the splice sites and auxiliary signals in the adjacent exons and introns. We previously described a feature generation algorithm (FGA that is capable of achieving high classification accuracy on human 3' splice sites. In this paper, we extend the splice-site prediction to 5' splice sites and explore the generated features for biologically meaningful splicing signals. Results We present examples from the observed features that correspond to known signals, both core signals (including the branch site and pyrimidine tract and auxiliary signals (including GGG triplets and exon splicing enhancers. We present evidence that features identified by FGA include splicing signals not found by other methods. Conclusion Our generated features capture known biological signals in the expected sequence interval flanking splice sites. The method can be easily applied to other species and to similar classification problems, such as tissue-specific regulatory elements, polyadenylation sites, promoters, etc.

  14. 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

  15. 'North-Normandy' radiological report. Methodological report related to continental and marine aquatic compartments

    International Nuclear Information System (INIS)

    Saunier, Jean-Baptiste; Leprieur, Fabrice; Pierrard, Olivier; Bailly Du Bois, Pascal; Boust, Dominique; Wyckaert, Laure; Pinel, Margaux; Sarraza, Manuel; Hamon, Nolwenn; Tetard, Xavier; Fetter, Pierre; Foucher, Eric; Lazard, Coline; Travers-Trolet, Morgane; Verin, Yves; Riviere, Camille; Villette, Frederic

    2015-01-01

    After a recall of the objectives, sampling and analysis strategy, and general methodology of radiological reports, and a general presentation of the radiological report for the 'North-Normandy' region (study framework, geographical scope, demography and activity poles), this report presents the main nuclear installations or sites which use radionuclides of natural or artificial origin: nuclear centres for power production, plants for used fuel processing, storage sites and submerged wastes, Cherbourg naval base, a company of nuclear maintenance (Somanu), industries generating wastes with a reinforced natural radioactivity, and centres of nuclear medicine. The two next chapters describe the characteristics of watersheds, the Channel and North Sea. It presents data acquired by control programmes and radio-ecological studies. The sampling strategies implemented for the continental aquatic environment, and for the coastal and offshore sea environment are described. A synthesis, a planning and perspectives are finally proposed and discussed

  16. Aerial radiological survey of the Waterford Generating Station and surrounding area, Taft, Louisiana. Date of survey: March-April 1982

    International Nuclear Information System (INIS)

    Jaffe, R.J.; Feimster, E.L.

    1984-02-01

    An aerial survey of the Waterford Generating Station near Taft, Louisiana was conducted during the period March 24 through April 7, 1982. The area encompassed a 256-square-kilometer (100-square-mile) area centered on the reactor facilities. Inferred exposure rates were due primarily to naturally occurring gamma-emitting radionuclides and cosmic ray activity (estimated at 3.7 μR/h). The exposure rates varied from 7 to 60 μR/h. Throughout most of the residential/industrial areas, the inferred exposure rate range was 7 to 12 μR/h. Marsh and water-covered areas were less than 7 μR/h. Two areas were encountered which had activity elevated above the typical background: (1) an industrial waste pond located 2 kilometers southeast of the site, and (2) a small area located 5 kilometers southeast of the site on the south bank of the Mississippi River. (A river barge was docked at this location during the survey.) Maximum inferred exposure rates over these areas were 60 and 16 μR/h, respectively. Spectral analysis revealed gamma-emitting radionuclides of the uranium decay chain as the primary contributors to this elevated activity. Ground-based measurements made in several areas were consistent with the aerial data. This was the first aerial radiological survey conducted over this area. 3 references, 9 figures, 3 tables

  17. Radiological objectives and severe accident mitigation strategy for the generation II PWRs in France in the framework of PLE

    International Nuclear Information System (INIS)

    Cenerino, G.; Dubreuil, M.; Raimond, E.; Pichereau, F.

    2012-01-01

    In France, EDF is involved in the construction of a first generation III (Gen III) reactor (European Pressurized Reactor - EPR) on Flamanville site next to two PWRs. Plant Life Extension (PLE) of reactors will consequently lead to simultaneous operation of Gen III and Gen II reactors during a long period of time. As a consequence, EDF was requested by the French Nuclear Safety Authority to prepare a PWR life management program including, in addition to an ageing management of Systems, Structures and Components, a consequent reactor safety enhancement program. The objective was stated to EDF by the French Nuclear Safety Authority: 'the safety objectives of the Gen III reactors should be used as a reference for all studies undertaken in the frame of PLE'. One part of the EDF program deals with additional arrangements able to reduce more drastically the consequences of any accident. The relevance, according to IRSN, of the EDF radiological objectives for Design Basis Accidents, of the new EDF objectives for Severe Accidents (SA) and of the EDF potential modifications for SA mitigation are presented. (author)

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

    International Nuclear Information System (INIS)

    2008-01-01

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

  19. 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

  20. 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.

  1. 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

  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. 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)

  4. 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....

  5. 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

  6. The Radiological Research Accelerator Facility

    International Nuclear Information System (INIS)

    Hall, E.J.

    1992-05-01

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

  7. Radiological imaging in endocrine hypertension

    Directory of Open Access Journals (Sweden)

    Chandan J Das

    2011-01-01

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

  8. 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.

  9. 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

  10. 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

  11. Radiological attacks and accidents. Medical consequences

    International Nuclear Information System (INIS)

    Sakuta, Hidenari

    2007-01-01

    Probability of the occurrence of radiological attacks appears to be elevated after the terrorist attacks against the United States on September 11 in 2001. There are a lot of scenarios of radiological attack: simple radiological device, radiological disperse device (RDD or dirty bomb), attacks against nuclear reactor, improvised nuclear device, and nuclear weapons. Of these, RDD attack is the most probable scenario, because it can be easily made and can generate enormous psychological and economic damages. Radiological incidents are occurring to and fro in the world, including several cases of theft to nuclear facilities and unsuccessful terrorist attacks against them. Recently, a former Russian spy has allegedly been killed using polonium-210. In addition, serious radiological accidents have occurred in Chernobyl, Goiania, and Tokai-mura. Planning, preparation, education, and training exercise appear to be essential factors to cope with radiological attacks and accidents effectively without feeling much anxiety. Triage and psychological first aid are prerequisite to manage and provide effective medial care for mass casualties without inducing panic. (author)

  12. Structuring a cost-effective site characterization

    International Nuclear Information System (INIS)

    Berven, B.A.; Little, C.A.; Swaja, R.E.

    1990-01-01

    Successful chemical and radiological site characterizations are complex activities which require meticulously detailed planning. Each layer of investigation is based upon previously generated information about the site. Baseline historical, physical, geological, and regulatory information is prerequisite for preliminary studies at a site. Preliminary studies then provide samples and measurements which define the identity of potential contaminants and define boundaries around the area to be investigated. The goal of a full site characterization is to accurately determine the extent and magnitude of contaminants and carefully define the site conditions such that the future movements of site contaminants can be assessed for potential exposure to human occupants and/or environmental impacts. Critical to this process is the selection of appropriate measurement and sampling methodology, selection and use of appropriate instrumentation and management/interpretation of site information. Site investigations require optimization between the need of information to maximize the understanding of site conditions and the cost of acquiring that information. 5 refs., 1 tab

  13. 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

  14. 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

  15. TENORM radiological survey of Utica and Marcellus Shale

    International Nuclear Information System (INIS)

    Ying, Leong; O’Connor, Frank

    2013-01-01

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

  16. Effect of magnetic reconnection in stellar plasma

    Science.gov (United States)

    Hammoud, M.; El Eid, M.; Darwish, M.

    2017-06-01

    An important phenomenon in Astrophysics is the process of magnetic reconnection (MGR), which is envisaged to understand the solar flares, coronal mass ejection, interaction of the solar wind with the Earth’s magnetic field (so called geomagnetic storm) and other phenomena. In addition, it plays a role in the formation of stars. MGR involves topological change of a set of magnetic field lines leading to a new equilibrium configuration of lower magnetic energy. The MGR is basically described in the framework of the Maxwell’s equations linked to Navier-Stockes equations. Nevertheless, many details are still not understood. In this paper, we investigate the MGR process in the framework of the Magnetohydrodynamic (MHD) model of a single conducting fluid using a modern powerful computational tool (OpenFOAM). We will show that the MGR process takes place only if resistivity exists. However, despite the high conductivity of the plasma, resistivity becomes effective in a very thin layer generating sharp gradients of the magnetic field, and thus accelerating the reconnection process. The net effect of MGR is that magnetic energy is converted into thermal and kinetic energies leading to heating and acceleration of charged particles. The Sun’s coronal ejection is an example of the MGR process.

  17. Duquesne Light Company 1982 annual radiological environmental report. Volume 2

    International Nuclear Information System (INIS)

    1982-01-01

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

  18. Method of impact evaluation of storage sites for uranium ore tailings

    International Nuclear Information System (INIS)

    Servant, A.C.; Cessac, B.

    2001-11-01

    Mining and ore processing generate liquid effluents and solid waste ( tailings) in important quantities. On fifty years exploitation, 50 millions tons of tailings have been stored on twenty sites in France. From a radiological point of view, the uranium tailings contain only natural radioisotopes, daughters of 238 U and 235 U families and for a low part daughter's of 232 Th family. Their activity stay low to very low, under the ore activity. It decreases very slowly because of the long period of some radionuclides ( 230 Th, 75 000 years, 226 Ra, 1600 years). generally stored on the exploitation site, these tailings constitute a radiological source term of which it is necessary to evaluate the impact on man and environment. At close-down of an uranium ore exploitation site, the operator is required to give to the prefect of his region a file of rehabilitation with the dispositions to take to limit the radiological impact of the storage. It is in this frame that the direction of pollutions and risks prevention (D.P.P.R.) from the Minister of Territory landscaping and the Institute of protection and nuclear safety (I.R.S.N.) established a convention, reference 56/2000, relative to investigations in matter of radiological impact evaluation of uranium tailings storage sites, in order to supply a document allowing to judge the pertinence of the different files made by Cogema in the frame of tailings storage of uranium ore processing. The present document constitutes the report planned at the 3. article ( 3. paragraph) of the convention. It gives the information necessary to the evaluation of impact studies for the sites in question. (N.C.)

  19. Hanford site transuranic waste certification plan

    International Nuclear Information System (INIS)

    GREAGER, T.M.

    1999-01-01

    As a generator of transuranic (TRU) and TRU mixed waste destined for disposal at the Waste Isolation Pilot Plant (WIPP), the Hanford Site must ensure that its TRU waste meets the requirements of U.S. Department of Energy (DOE) Order 5820.2A, ''Radioactive Waste Management, and the Waste Acceptance Criteria for the Waste Isolation Pilot Plant' (DOE 1996d) (WIPP WAC). The WIPP WAC establishes the specific physical, chemical, radiological, and packaging criteria for acceptance of defense TRU waste shipments at WIPP. The WIPP WAC also requires that participating DOE TRU waste generator/treatment/storage sites produce site-specific documents, including a certification plan, that describe their management of TRU waste and TRU waste shipments before transferring waste to WIPP. The Hanford Site must also ensure that its TRU waste destined for disposal at WIPP meets requirements for transport in the Transuranic Package Transporter41 (TRUPACT-11). The U.S. Nuclear Regulatory Commission (NRC) establishes the TRUPACT-I1 requirements in the ''Safety Analysis Report for the TRUPACT-II Shipping Package'' (NRC 1997) (TRUPACT-I1 SARP)

  20. The Radiological Research Accelerator Facility

    International Nuclear Information System (INIS)

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

    1991-05-01

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

  1. The Radiological Research Accelerator Facility

    International Nuclear Information System (INIS)

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

    1993-05-01

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

  2. 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

  3. Results of the radiological survey at 205 Main Street, Lodi, New Jersey (LJ075)

    International Nuclear Information System (INIS)

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

    1989-08-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally 232 Th, derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, 205 Main Street, Lodi, New Jersey (LJ075), was conducted during 1987 and 1988. Results of the survey indicated radioactivity in the range of normal background for the northern New Jersey area. Radiological assessments of soil samples from the site demonstrate no radionuclide concentrations in excess of DOE Formerly Utilized Sites Remedial Action Program criteria. 5 refs., 21 figs., 3 tabs

  4. Comparison of potential radiological impacts of 233U and 239Pu fuel cycles

    International Nuclear Information System (INIS)

    Meyer, H.R.; Little, C.A.; Witherspoon, J.P.; Till, J.E.

    1979-01-01

    Nuclear fuel cycles utilizing 233 U are currently the subject of considerable interest in the United States. This paper focuses on the identification of significant differences between the off-site radiological hazards posed by 232 Th/ 233 U (Th/U) and 238 U/ 239 Pu (U/Pu) fuel cycles, and represents a portion of our involvement in the Nonproliferation Alternative Systems Assessment Program (NASAP), to be used in support of the International Fuel Cycle Evaluation (INFCE). The major contributors to radiological dose are likely to be uranium mining and milling (58.5% of total fuel cycle dose), reprocessing (33.9%), and light-water reactor power generation (7.3%). The remainder of the cycle, including enrichment processes, fuel fabrication, transportation, and waste management, contributes only 0.3% to total estimated fuel cycle dose

  5. 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

  6. Massive radiological releases profoundly differ from controlled releases

    International Nuclear Information System (INIS)

    Pascucci-Cahen, Ludivine; Patrick, Momal

    2013-01-01

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

  7. Westinghouse radiological containment guide

    International Nuclear Information System (INIS)

    Aitken, S.B.; Brown, R.L.; Cantrell, J.R.; Wilcox, D.P.

    1994-03-01

    This document provides uniform guidance for Westinghouse contractors on the implementation of radiological containments. This document reflects standard industry practices and is provided as a guide. The guidance presented herein is consistent with the requirements of the DOE Radiological Control Manual (DOE N 5480.6). This guidance should further serve to enable and encourage the use of containments for contamination control and to accomplish the following: Minimize personnel contamination; Prevent the spread of contamination; Minimize the required use of protective clothing and personal protective equipment; Minimize the generation of waste

  8. Westinghouse radiological containment guide

    Energy Technology Data Exchange (ETDEWEB)

    Aitken, S.B. [Idaho National Engineering Lab., Idaho Falls, ID (United States); Brown, R.L. [Westinghouse Hanford Co., Richland, WA (United States); Cantrell, J.R. [Westinghouse Savannah River Co., Aiken, SC (United States); Wilcox, D.P. [West Valley Nuclear Services Co., Inc., West Valley, NY (United States)

    1994-03-01

    This document provides uniform guidance for Westinghouse contractors on the implementation of radiological containments. This document reflects standard industry practices and is provided as a guide. The guidance presented herein is consistent with the requirements of the DOE Radiological Control Manual (DOE N 5480.6). This guidance should further serve to enable and encourage the use of containments for contamination control and to accomplish the following: Minimize personnel contamination; Prevent the spread of contamination; Minimize the required use of protective clothing and personal protective equipment; Minimize the generation of waste.

  9. Hazardous radiological waste-dental and environmental perspective

    International Nuclear Information System (INIS)

    Tripathi, Anurag

    2014-01-01

    Dental radiology is concerned with maxillo-facial radiological diagnostic procedure. It is meant for patient welfare and to generate diagnostically useful information, which can be utilized for patient welfare. If injudiciously used, it can become a source of harmful effluents and solid waste, which may pose risk to health and environment. Professionals of dental radiology should be aware about their responsibility to dispose such waste in the rightful manner to fulfil their medical pledge and ethics of doing no harm. (author)

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

    International Nuclear Information System (INIS)

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

    1982-02-01

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

  11. 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.

  12. 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

  13. Mobile technology in radiology resident education.

    Science.gov (United States)

    Korbage, Aiham C; Bedi, Harprit S

    2012-06-01

    The authors hypothesized that ownership of a mobile electronic device would result in more time spent learning radiology. Current trends in radiology residents' studying habits, their use of electronic and printed radiology learning resources, and how much of the funds allotted to them are being used toward printed vs electronic education tools were assessed in this study. A survey study was conducted among radiology residents across the United States from June 13 to July 5, 2011. Program directors listed in the Association of Program Directors in Radiology e-mail list server received an e-mail asking for residents to participate in an online survey. The questionnaire consisted of 12 questions and assessed the type of institution, the levels of training of the respondents, and book funds allocated to residents. It also assessed the residents' study habits, access to portable devices, and use of printed and electronic radiology resources. Radiology residents are adopters of new technologies, with 74% owning smart phones and 37% owning tablet devices. Respondents spend nearly an equal amount of time learning radiology from printed textbooks as they do from electronic resources. Eighty-one percent of respondents believe that they would spend more time learning radiology if provided with tablet devices. There is considerable use of online and electronic resources and mobile devices among the current generation of radiology residents. Benefits, such as more study time, may be obtained by radiology programs that incorporate tablet devices into the education of their residents. Copyright © 2012 American College of Radiology. Published by Elsevier Inc. All rights reserved.

  14. Worker radiological protection: occupational medical aspects

    International Nuclear Information System (INIS)

    Cardenas Herrera, Juan; Fernandez Gomez, Isis Maria

    2008-01-01

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

  15. Radiological characterisation on V1 NPP technological systems and buildings - Contamination

    International Nuclear Information System (INIS)

    Hanzel, Richard; Rapant, Tibor; Svitek, Jaroslav

    2012-01-01

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

  16. 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.

  17. 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.

  18. 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

  19. 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)

  20. 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

  1. 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

  2. Challenge of Replacing Obsolete Equipment and Systems on Brownfield Sites

    International Nuclear Information System (INIS)

    Teasdale, St.

    2009-01-01

    The Nuclear Decommissioning Authority (NDA) is responsible for the decommissioning and clean-up of the UK's civil public sector nuclear sites. One of their top priorities is the retrieval of sludge and fuel from the First Generation Magnox Fuel Storage Pond (FGMSP) at Sellafield site which is one of the most complex and compact nuclear sites in the world. The FGMSP plant is currently undergoing a series of major modifications in preparation for the retrievals operations. One of the most challenging modifications undertaken in the facility has been the Control and Surveillance Project which covered replacement of the existing Environmental Monitoring System, this presented the complex challenge of replacing an existing system whilst maintaining full functionality on a live radiological safety system with a constant radiological hazard. The Control and Surveillance Project involved the design, procurement, installation, changeover and commissioning of a new Radiological Surveillance System (alpha, beta and gamma monitoring) along with Building Evacuation Systems within the FGMSP complex to replace the existing obsolete system. This Project was a key enabler to future FGMSP retrievals and decommissioning activities. The project objective was to create and maintain a safe radiological working environment for over 450 personnel working in the plant up to 2020. The Legacy Ponds at Sellafield represent one of the biggest challenges in the civil nuclear clean up portfolio in the UK. Retrieval of sludge and fuel from the First Generation Magnox Fuel Storage Pond (FGMSP), and its safe long term storage is one of the NDA's top priorities. In June 2002 Sellafield Ltd contracted with the ACKtiv Nuclear Joint Venture to progress the risk mitigation, asset restoration and the early enabling works associated with preparation for clean up. Since then significant progress has been made in preparing the facility, and it's support systems, for the clean-up operations. This has been

  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. 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)

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

    International Nuclear Information System (INIS)

    McKinney, S.M.

    1995-04-01

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

  6. 1980 annual radiological environmental report. Volume 2

    International Nuclear Information System (INIS)

    1980-01-01

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

  7. 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

  8. A consequence index approach to identifying radiological sabotage targets

    International Nuclear Information System (INIS)

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

    1988-01-01

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

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

    International Nuclear Information System (INIS)

    Thome, D.J.

    2000-01-01

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

  10. Remedial action at the Acid/Pueblo Canyon site, Los Alamos, New Mexico. Final report

    International Nuclear Information System (INIS)

    1984-10-01

    The Acid/Pueblo Canyon site (TA-45) was designated in 1976 for remedial action under the Formerly Utilized Sites Remedial Action Program (FUSRAP). During the period 1943 to 1964 untreated and treated liquid wastes generated by nuclear weapons research activities at the Los Alamos Scientific Laboratory (LASL) were discharged into the two canyons. A survey of the site conducted by LASL in 1976 to 1977 identified two areas where radiological contamination exceeded criteria levels. The selected remedial action was based on extensive radiological characterization and comprehensive engineering assessments and comprised the excavation and disposal of 390 yd 3 of contaminated soil and rock. This document describes the background to the remedial action, the parties involved in administering and executing it, the chronology of the work, verification of the adequacy of the remedial action, and the cost incurred. 14 references, 5 figures, 5 tables

  11. Results of the radiological survey at 88 East Central Avenue, Maywood, New Jersey (MJ037)

    International Nuclear Information System (INIS)

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

    1989-06-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally 232 Th, derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, 88 East Central Avenue Maywood, New Jersey (MJ037), was conducted during 1988. Results of the survey indicated radioactivity in the range of normal background for the northern New Jersey area. Radiological assessments of soil samples from the site demonstrate no radionuclide concentrations in excess of DOE Formerly Utilized Sites Remedial Action Program criteria. 4 refs., 2 figs., 3 tabs

  12. 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)

  13. The Atmospheric Release Advisory Capability Site Workstation System

    International Nuclear Information System (INIS)

    Foster, K.T.; Sumikawa, D.A.; Foster, C.S.; Baskett, R.L.

    1993-01-01

    The Atmospheric Release Advisory Capability (ARAC) is a centralized emergency response service that assesses the consequences that may result from an atmospheric release of toxic material. ARAC was developed by the Lawrence Livermore National Laboratory (LLNL) for the Departments of Energy (DOE) and Defense (DOD) and responds principally to radiological accidents. ARAC provides radiological health and safety guidance to decision makers in the form of computer-generated estimates of the effects of an actual, or potential release of radioactive material into the atmosphere. Upon receipt of the release scenario, the ARAC assessment staff extracts meteorological, topographic, and geographic data from resident world-wide databases for use in complex, three-dimensional transport and diffusion models. These dispersion models generate air concentration (or dose) and ground deposition contour plots showing estimates of the contamination patterns produced as the toxic material is carried by the prevailing winds. To facilitate the ARAC response to a release from specific DOE and DOD sites and to provide these sites with a local emergency response tool, a remote Site Workstation System (SWS) is being placed at various ARAC-supported facilities across the country.. This SWS replaces the existing antiquated ARAC Site System now installed at many of these sites. The new system gives users access to complex atmospheric dispersion models that may be run either by the ARAC staff at LLNL, or (in a later phase of the system) by site personnel using the computational resources of the SWS. Supporting this primary function are a variety of SWS-resident supplemental capabilities that include meteorological data acquisition, manipulation of release-specific databases, computer-based communications, and the use of a simpler Gaussian trajectory puff model that is based on Environmental Protection Agency's INPUFF code

  14. Waste Minimization via Radiological Hazard Reduction

    International Nuclear Information System (INIS)

    Stone, K.A.; Coffield, T.; Hooker, K.L.

    1998-01-01

    The Savannah River Site (SRS), a 803 km 2 U.S. Department of Energy (DOE) facility in south-western South Carolina, incorporates pollution prevention as a fundamental component of its Environmental Management System. A comprehensive pollution prevention program was implemented as part of an overall business strategy to reduce waste generation and pollution releases, minimize environmental impacts, and to reduce future waste management and pollution control costs. In fiscal years 1995 through 1997, the Site focused on implementing specific waste reduction initiatives identified while benchmarking industry best practices. These efforts resulted in greater than $25 million in documented cost avoidance. While these results have been dramatic to date, the Site is further challenged to maximize resource utilization and deploy new technologies and practices to achieve further waste reductions. The Site has elected to target a site-wide reduction of contaminated work spaces in fiscal year 1998 as the primary source reduction initiative. Over 120,900 m 2 of radiologically contaminated work areas (approximately 600 separate inside areas) exist at SRS. Reduction of these areas reduces future waste generation, minimizes worker exposure, and reduces surveillance and maintenance costs. This is a major focus of the Site's As Low As Reasonably Achievable (ALARA) program by reducing sources of worker exposure. The basis for this approach was demonstrated during 1997 as part of a successful Enhanced Work Planning pilot conducted at several specific contamination areas at SRS. An economic-based prioritization process was utilized to develop a model for prioritizing areas to reclaim. In the H-Canyon Separation facility, over 3,900 m 2 of potentially contaminated area was rolled back to a Radiation Buffer Area. The facility estimated nearly 420 m 3 of low level radioactive waste will be avoided each year, and overall cost savings and productivity gains will reach approximately $1

  15. 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)

  16. 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)

  17. 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)

  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. Environmental Radiological Impact of Nuclear Power. Monitoring and Control Programs

    International Nuclear Information System (INIS)

    Ramos, L. M.

    2000-01-01

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

  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. 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.)

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

    International Nuclear Information System (INIS)

    NSTec Environmental Restoration

    2007-01-01

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

  3. 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

  4. A survey of radiology reporting practices in veterinary teaching hospitals

    International Nuclear Information System (INIS)

    Adams, W.M.

    1998-01-01

    Radiologists from 28 veterinary schools and one private teaching hospital responded to a survey questionnaire focused on diagnostic image reporting. Radiologists at 26 hospitals generated a hard copy report on essentially all imaging studies performed. At 25 hospitals, radiologists dictated and transcriptionists typed all or most reports; radiologists at two institutions typed all or some of their reports. At five hospitals, preliminary and/or final handwritten reports were generated. The range of reports generated per day was <10 to 40 per radiologist on duty. Seven respondents generated reports as films came from the processor and another 12 routinely generated reports the day the studies were completed. Clinician access to a processed report averaged 2 to 4 days after study was completed (reported range: several hours to 7 or more days). Fifteen responding radiologists personally mounted films from storage jackets for a majority of their reporting. Fourteen respondents generated reports from films mounted on motorized or stationary viewers. Nineteen respondents generated reports in a busy viewing area where they were frequently interrupted. Radiologists' impression of clinician and resident satisfaction regarding availability of radiology reports was that they were satisfied or very satisfied at 15 of the 29 hospitals. Five respondents reported that clinicians and residents were not concerned about availability of processed radiology reports. Thirteen radiologists were planning to change their reporting method within the next 2 years. The change most frequently sought (12 respondents) was to decrease turn-around time of reports. Ten radiologists indicated an interest in trying a voice recognition dictation system. The most common reasons given for not planning any changes in radiology reporting in the next 2 years were: limited number of radiologists (8) and 1 ''satisfied as is'' (7). Turn-around of radiology reports at these veterinary institutions averaged 2

  5. Site release in the decommissioning of nuclear installations

    International Nuclear Information System (INIS)

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

    2008-01-01

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

  6. 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

  7. Radiological consequence analysis with HEU and LEU fuels

    Energy Technology Data Exchange (ETDEWEB)

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

    1984-01-01

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

  8. Radiological consequence analysis with HEU and LEU fuels

    International Nuclear Information System (INIS)

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

    1984-01-01

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

  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. 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

  11. 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)

  12. 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.

  13. American College of Radiology-American Brachytherapy Society practice parameter for electronically generated low-energy radiation sources.

    Science.gov (United States)

    Devlin, Phillip M; Gaspar, Laurie E; Buzurovic, Ivan; Demanes, D Jeffrey; Kasper, Michael E; Nag, Subir; Ouhib, Zoubir; Petit, Joshua H; Rosenthal, Seth A; Small, William; Wallner, Paul E; Hartford, Alan C

    This collaborative practice parameter technical standard has been created between the American College of Radiology and American Brachytherapy Society to guide the usage of electronically generated low energy radiation sources (ELSs). It refers to the use of electronic X-ray sources with peak voltages up to 120 kVp to deliver therapeutic radiation therapy. The parameter provides a guideline for utilizing ELS, including patient selection and consent, treatment planning, and delivery processes. The parameter reviews the published clinical data with regard to ELS results in skin, breast, and other cancers. This technical standard recommends appropriate qualifications of the involved personnel. The parameter reviews the technical issues relating to equipment specifications as well as patient and personnel safety. Regarding suggestions for educational programs with regard to this parameter,it is suggested that the training level for clinicians be equivalent to that for other radiation therapies. It also suggests that ELS must be done using the same standards of quality and safety as those in place for other forms of radiation therapy. Copyright © 2017 American Brachytherapy Society and American College of Radiology. Published by Elsevier Inc. All rights reserved.

  14. Federal Radiological Monitoring and Assessment Center Phased Response Operations

    International Nuclear Information System (INIS)

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

    1999-01-01

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

  15. Federal Radiological Monitoring and Assessment Center: Phase I Response

    International Nuclear Information System (INIS)

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

    1999-01-01

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

  16. Assessment of SRS radiological liquid and airborne contaminants and pathways

    International Nuclear Information System (INIS)

    Jannik, G.T.

    1997-04-01

    This report compiles and documents the radiological critical-contaminant/critical-pathway analysis performed for SRS. The analysis covers radiological releases to the atmosphere and to surface water, which are the principal media that carry contaminants off site. During routine operations at SRS, limited amounts of radionuclides are released to the environment through atmospheric and/or liquid pathways. These releases potentially result in exposure to offsite people. Though the groundwater beneath an estimated 5 to 10 percent of SRS has been contaminated by radionuclides, there is no evidence that groundwater contaminated with these constituents has migrated offsite (Arnett, 1996). Therefore, with the notable exception of radiological source terms originating from shallow surface water migration into site streams, onsite groundwater was not considered as a potential exposure pathway to offsite people

  17. 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.)

  18. 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

  19. Radiological re-survey results at 130 West Central Avenue, Maywood, New Jersey (MJ029)

    International Nuclear Information System (INIS)

    Murray, M.E.; Johnson, C.A.

    1994-01-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from 1916 to 1959. During the early years of operation, MCW stored wastes and residues in low-lying areas west of the processing facilities and consequently some of the residuals containing radioactive materials migrated offsite to the surrounding area. Subsequently, the U.S. Department of Energy (DOE), designated for remedial action the old MCW property and several vicinity properties. Additionally, in 1984, the property at 130 West Central Ave., Maywood, New Jersey and properties in its vicinity were included as a decontamination research and development project under the DOE Formerly Utilized Sites Remedial Action Program. In 1987 and 1988, at the request of DOE, ORNL conducted a radiological survey on this property. A second radiological survey by ORNL was conducted on this property in May, 1993 at the request of DOE after an ad hoc radiological survey, requested by a new property owner and conducted by Bechtel National, Inc. (BNI), identified some contamination not previously found by ORNL. The purpose of the survey was to determine if residuals from the old MCW were present on the property, and if so, if any radiological elements present were above guidelines. A certified civil survey was requisitioned by ORNL to determine actual property boundaries before beginning the radiological survey. The radiological re-survey included a surface gamma scan and the collection of a large number of soil samples for radionuclide analyses

  20. Radiological Research Accelerator Facility

    International Nuclear Information System (INIS)

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

    1986-01-01

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

  1. Biological Treatment of Petroleum in Radiologically Contaminated Soil

    Energy Technology Data Exchange (ETDEWEB)

    BERRY, CHRISTOPHER

    2005-11-14

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

  2. Results of the radiological survey at 142 West Central Avenue, Maywood, New Jersey (MJ041)

    International Nuclear Information System (INIS)

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

    1989-06-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally 232 Th, derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, 142 West Central Avenue, Maywood, New Jersey (MJ041), was conducted during 1988. Results of the survey indicated scattered radiation or ''shine'' from a storage pile, located off the property, containing residual radioactive material. Lead-shielded measurements showed radioactivity in the range of normal background for the northern New Jersey area. Radiological assessments of soil samples from the site demonstrate no radionuclide concentrations in excess of DOE Formerly Utilized Sites Remedial Action Program criteria. 4 refs., 8 figs., 3 tabs

  3. 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

  4. 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.)

  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. www.PedRad.info, the first bilingual case-oriented publication platform for pediatric radiology

    International Nuclear Information System (INIS)

    Hirsch, Wolfgang; Paetzel, Martina; Talanow, Roland

    2005-01-01

    On the Internet, there are few pediatric radiology databases. The most important and complete Web site is PediatricRadiology.com, which provides many radiological links but does not have its own database. We present an Internet project called PedRad.info (also known as Kinderradiologie-Online). The open-source, case-oriented publication platform publishes validated pediatric radiology findings on the Internet. A comparable on-line program, even for adult radiology, does not exist, so this tool is a pioneer in the area of Web-based information technology for medical and radiological communities. (orig.)

  7. 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

  8. Study on the operational guides of the off-site emergency management center

    International Nuclear Information System (INIS)

    Park, Won Jong; Han, S. J.; Oh, K. H.

    2005-01-01

    The emergency response organizational groups and roles of Off-site Emergency Management Center was proposed to respond in case of radiological emergency. Development of implementing procedures of Off-site Emergency Management Center in case of radiological emergency to improve effective co-operation and rapid response in radiological emergency. Establishment of 'The Ordinance of Operation of residence radiological emergency office of the Minister of Science and Technology' and announced by the Minister of Science and Technology. The Implementing procedures of Off-site Emergency Management Center and 'The Ordinance of Operation of residence radiological emergency office of the Minister of Science and Technology' can be provide guidelines in case of emergency

  9. 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

  10. 200-UP-2 operable unit radiological surveys

    International Nuclear Information System (INIS)

    Wendling, M.A.

    1994-01-01

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

  11. 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

  12. Mobilization suited for each radiological emergency

    International Nuclear Information System (INIS)

    Chambrette, V.

    2013-01-01

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

  13. Information related to low-level mixed waste inventory, characteristics, generation, and facility assessment for treatment, storage, and disposal alternatives considered in the U.S. Department of Energy Waste Management Programmatic Environmental Impact Statement

    International Nuclear Information System (INIS)

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

    1996-12-01

    This report was prepared to support the analysis of risks and costs associated with the proposed treatment of low-level mixed waste (LLMW) under management of the US Department of Energy (DOE). The various waste management alternatives for treatment of LLMW have been defined in the DOE's Office of Waste Management Programmatic Environmental Impact Statement. This technical memorandum estimates the waste material throughput expected at each proposed LLMW treatment facility and analyzes potential radiological and chemical releases at each DOE site resulting from treatment of these wastes. Models have been developed to generate site-dependent radiological profiles and waste-stream-dependent chemical profiles for these wastes. Current site-dependent inventories and estimates for future generation of LLMW have been obtained from DOE's 1994 Mixed Waste Inventory Report (MWIR-2). Using treatment procedures developed by the Mixed Waste Treatment Project, the MWIR-2 database was analyzed to provide waste throughput and emission estimates for each of the different waste types assessed in this report. Uncertainties in the estimates at each site are discussed for waste material throughputs and radiological and chemical releases

  14. Information related to low-level mixed waste inventory, characteristics, generation, and facility assessment for treatment, storage, and disposal alternatives considered in the U.S. Department of Energy Waste Management programmatic environmental impact statement

    International Nuclear Information System (INIS)

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

    1995-04-01

    This report was prepared to support the analysis of risks and costs associated with the proposed treatment of low-level mixed waste (LLMW) under management of the U.S. Department of Energy (DOE). The various waste management alternatives for treatment of LLMW have been defined in the DOE's Office of Waste Management Programmatic Environmental Impact Statement. This technical memorandum estimates the waste material throughput expected at each proposed LLMW treatment facility and analyzes potential radiological and chemical releases at each DOE site resulting from treatment of these wastes. Models have been developed to generate site-dependent radiological profiles and waste-stream-dependent chemical profiles for these wastes. Current site-dependent inventories and estimates for future generation of LLMW have been obtained from DOE's 1994 Mixed Waste Inventory Report (MWIR-2). Using treatment procedures developed by the Mixed Waste Treatment Project, the MWIR-2 database was analyzed to provide waste throughput and emission estimates for each of the different waste types assessed in this report. Uncertainties in the estimates at each site are discussed for waste material throughputs and radiological and chemical releases

  15. National radiological emergency response to the Fukushima Daiichi Nuclear Power Plant accident

    International Nuclear Information System (INIS)

    Dela Rosa, Alumanda M.

    2011-01-01

    The Fukushima nuclear power plant accident occurred on March 11, 2011, when two natural disasters of unprecedented strengths, an earthquake with magnitude 9 followed one hour later by a powerful tsunami struck northeastern Japan and felled the external power supply and the emergency diesel generators of the Fukushima Daiichi nuclear power station, resulting in a loss of coolant accident. There were core meltdowns in three nuclear reactors with the release of radioactivity estimated to be 1/10 of what was released to the environment during the Chernobyl nuclear power plant accident in April 1986. The Fukushima nuclear accident tested the capability of the Philippine Nuclear Research Institute (PNRI) and the National Disaster Risk Reduction and Management Council (NDRRMC) in responding to such radiological emergency as a nuclear power plant accident. The PNRI and NDRRMC activated the RADPLAN for possible radiological emergency. The emergency response was calibrated to the status of the nuclear reactors on site and the environmental monitoring undertaken around the site and off-site, including the marine environment. This orchestrated effort enabled the PNRI and the national agencies concerned to reassure the public that the nuclear accident does not have a significant impact on the Philippines, both on the health and safety of the people and on the safety of the environment. National actions taken during the accident will be presented. The role played by the International Atomic Energy Agency as the central UN agency for nuclear matters will be discussed. (author)

  16. Results of the radiological survey at 90 Orchard Place Maywood, New Jersey (MJ023)

    International Nuclear Information System (INIS)

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

    1989-10-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally 233 Th, derived from the MCW site. The surveys typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, 90 Orchard Place, Maywood, New Jersey (MJ023), was conducted during 1987. While some radiological measurements taken at 90 Orchard Place were slightly greater than typical background levels encountered in the northern New Jersey area, no radionuclide concentrations nor radiation levels exceeded the applicable federal criteria. Based on the survey data it is recommended that this site be eliminated from consideration for inclusion in the DOE remedial action program. 5 refs., 2 figs., 3 tabs

  17. 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)

  18. Digital image information systems in radiology

    International Nuclear Information System (INIS)

    Greinacher, C.F.C.; Luetke, B.; Seufert, G.

    1987-01-01

    About 25% of all patient examinations are performed digitally in a today's radiological department. A computerized system is described that supports generation, transport, interpretation and archiving of digital radiological images (Picture Archiving and Communication System PACS). The technical features concerning image communication via local area networks, image storage on magnetic and optical media and digital workstations for image display and manipulation are described. A structured system architecture is introduced. It allows flexible adaption to individual organizations and minimizes the requirements of the communication network. (orig.) [de

  19. Multihospital Occurrence of Pan-Resistant Klebsiella pneumoniae Sequence Type 147 with an ISEcp1-Directed blaOXA-181 Insertion in the mgrB Gene in the United Arab Emirates.

    Science.gov (United States)

    Sonnevend, Ágnes; Ghazawi, Akela; Hashmey, Rayhan; Haidermota, Aliasgher; Girgis, Safinaz; Alfaresi, Mubarak; Omar, Mohammed; Paterson, David L; Zowawi, Hosam M; Pál, Tibor

    2017-07-01

    The emergence of pan-resistant Klebsiella pneumoniae strains is an increasing concern. In the present study, we describe a cluster of 9 pan-resistant K. pneumoniae sequence type 147 (ST147) isolates encountered in 4 patients over nearly 1 year in 3 hospitals of the United Arab Emirates (UAE). The isolates exhibited highly similar genotypes. All produced chromosomally encoded OXA-181, and the majority also produced the NDM-5 carbapenemase. As with the previously described single isolate from the UAE, MS6671, the mgrB was disrupted by a functional, IS Ecp1 -driven bla OXA-181 insertion causing resistance to carbapenems. The mutation was successfully complemented with an intact mgrB gene, indicating that it was responsible for colistin resistance. bla NDM-5 was located within a resistance island of an approximately 100-kb IncFII plasmid carrying ermB , mph (A), bla TEM-1B , rmtB , bla NDM-5 , sul1 , aadA2 , and dfrA12 resistance genes. Sequencing this plasmid (pABC143-NDM) revealed that its backbone was nearly identical to that of plasmid pMS6671E from which several resistance genes, including bla NDM-5 , had been deleted. More extensive similarities of the backbone and the resistance island were found between pABC143C-NDM and the bla NDM-5 -carrying IncFII plasmids of two K. pneumoniae ST147 isolates from South Korea, one of which was colistin resistant, and both also produced OXA-181. Notably, one of these strains was isolated from a patient transferred from the UAE. Our data show that this pan-resistant clone has an alarming capacity to maintain itself over an extended period of time and is even likely to be transmitted internationally. Copyright © 2017 American Society for Microbiology.

  20. Potential release scenario and radiological consequence evaluation of mineral resources at WIPP

    International Nuclear Information System (INIS)

    Little, M.S.

    1982-05-01

    This report has reviewed certain of the natural resources which may be found at the site of the nuclear waste repository being considered for southeastern New Mexico, and discussed the scenarios which have been used to estimate the radiological consequences from the mining of these resources several hundred years after the radioactive waste has been emplaced. It has been concluded that the radiological consequences of the mining of potash or hydrocarbons (mostly natural gas) are probably bounded by the consequences of hydrologic breach scenarios already considered by the US Department of Energy, and by reports of EEG. These studies conclude that the resultant doses would not constitute a significant threat to public health. This report also evaluates the radiological consequences of solution mining of halite at the WIPP site. Although such mining in the Delaware Basin and particularly at the WIPP site, is not likely at the present time, significant economic, social or climatic changes a few hundred years after emplacement may make these resources more attractive. The DOE did not consider such mining at the site credible

  1. 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.

  2. Results of the radiological survey at West Hunter Avenue Firehall, Maywood, New Jersey (MJ027)

    International Nuclear Information System (INIS)

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

    1990-03-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally 232 Th, derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, West Hunter Avenue Firehall, Maywood, New Jersey (MJ027), was conducted during 1987. 4 refs., 3 tabs

  3. Pseudo-random-number generators and the square site percolation threshold.

    Science.gov (United States)

    Lee, Michael J

    2008-09-01

    Selected pseudo-random-number generators are applied to a Monte Carlo study of the two-dimensional square-lattice site percolation model. A generator suitable for high precision calculations is identified from an application specific test of randomness. After extended computation and analysis, an ostensibly reliable value of p_{c}=0.59274598(4) is obtained for the percolation threshold.

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

    International Nuclear Information System (INIS)

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

    1991-10-01

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

  5. Radiological-dose assessments of atolls in the northern Marshall Islands

    International Nuclear Information System (INIS)

    Robison, W.L.

    1983-04-01

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

  6. Annual Site Environmental Report for Calendar Years 2005-2006

    International Nuclear Information System (INIS)

    Finley, Virginia L.

    2010-01-01

    Contained in the following report are data for radioactivity in the environment collected and analyzed by Princeton Plasma Physics Laboratory's Princeton Environmental, Analytical, and Radiological Laboratory (PEARL). The PEARL is located on-site and is certified for analyzing radiological and non-radiological parameters through the New Jersey Department of Environmental Protection's Laboratory Certification Program, Certification Number 12471. Non-radiological surface and ground water samples are analyzed by NJDEP certified subcontractor laboratories - QC, Inc. and Accutest Laboratory. To the best of our knowledge, these data, as contained in the 'Annual Site Environmental Report for 2005 and 2006,' are documented and certified to be correct.

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

    International Nuclear Information System (INIS)

    MCKINNEY, S.M.

    1998-01-01

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

  8. 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)

  9. Pediatric radiology for medical-technical radiology assistants/radiologists

    International Nuclear Information System (INIS)

    Oppelt, Birgit

    2010-01-01

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

  10. Computer assisted radiology

    International Nuclear Information System (INIS)

    Lemke, H.U.; Jaffe, C.C.; Felix, R.

    1993-01-01

    The proceedings of the CAR'93 symposium present the 126 oral papers and the 58 posters contributed to the four Technical Sessions entitled: (1) Image Management, (2) Medical Workstations, (3) Digital Image Generation - DIG, and (4) Application Systems - AS. Topics discussed in Session (1) are: picture archiving and communication systems, teleradiology, hospital information systems and radiological information systems, technology assessment and implications, standards, and data bases. Session (2) deals with computer vision, computer graphics, design and application, man computer interaction. Session (3) goes into the details of the diagnostic examination methods such as digital radiography, MRI, CT, nuclear medicine, ultrasound, digital angiography, and multimodality imaging. Session (4) is devoted to computer-assisted techniques, as there are: computer assisted radiological diagnosis, knowledge based systems, computer assisted radiation therapy and computer assisted surgical planning. (UWA). 266 figs [de

  11. Results of the radiological survey at the property at Main Street and Highway 46, Lodi, New Jersey (LJ074)

    International Nuclear Information System (INIS)

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

    1989-09-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally 232 Th, derived from the MCW site. The survey typically includes direct measurements of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site located at the intersection of Main Street and Highway 46, Lodi, New Jersey (LJ074), was conducted during 1987. While some radiological measurements taken at the vacant lot at the intersection of Main Street and Highway 46 were greater than background levels typically encountered in the northern New Jersey area, no radiation levels nor radionuclide concentrations exceeded the applicable DOE criteria. The survey results demonstrate that the radiological condition of this property conforms to DOE guidelines for remedial action. 4 refs., 5 figs., 3 tabs

  12. 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.

  13. Privacy and Generation Y: Applying Library Values to Social Networking Sites

    Science.gov (United States)

    Fernandez, Peter

    2010-01-01

    Librarians face many challenges when dealing with issues of privacy within the mediated space of social networking sites. Conceptually, social networking sites differ from libraries on privacy as a value. Research about Generation Y students, the primary clientele of undergraduate libraries, can inform librarians' relationship to this important…

  14. Final report: survey and removal of radioactive surface contamination at environmental restoration sites, Sandia National Laboratories/New Mexico. Volume 1

    International Nuclear Information System (INIS)

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

    1997-09-01

    This report describes the survey and removal of radioactive surface contamination at Sandia's Environmental Restoration (ER) sites. Radiological characterization was performed as a prerequisite to beginning the Resource Conservation and Recovery Act (RCRA) corrective action process. The removal of radioactive surface contamination was performed in order to reduce potential impacts to human health and the environment. The predominant radiological contaminant of concern was depleted uranium (DU). Between October 1993 and November 1996 scanning surface radiation surveys, using gamma scintillometers, were conducted at 65 sites covering approximately 908 acres. A total of 9,518 radiation anomalies were detected at 38 sites. Cleanup activities were conducted between October 1994 and November 1996. A total of 9,122 anomalies were removed and 2,072 waste drums were generated. The majority of anomalies not removed were associated with a site that has subsurface contamination beyond the scope of this project. Verification soil samples (1,008 total samples) were collected from anomalies during cleanup activities and confirm that the soil concentration achieved in the field were far below the target cleanup level of 230 pCi/g of U-238 (the primary constituent of DU) in the soil. Cleanup was completed at 21 sites and no further radiological action is required. Seventeen sites were not completed since cleanup activities wee precluded by ongoing site activity or were beyond the original project scope

  15. Final report: survey and removal of radioactive surface contamination at environmental restoration sites, Sandia National Laboratories/New Mexico. Volume 1

    Energy Technology Data Exchange (ETDEWEB)

    Lambert, K.A.; Mitchell, M.M. [Brown and Root Environmental, Albuquerque, NM (United States); Jean, D. [MDM/Lamb, Inc., Albuquerque, NM (United States); Brown, C. [Environmental Dimensions, Inc., Albuquerque, NM 87109 (United States); Byrd, C.S. [Sandia National Labs., Albuquerque, NM (United States)

    1997-09-01

    This report describes the survey and removal of radioactive surface contamination at Sandia`s Environmental Restoration (ER) sites. Radiological characterization was performed as a prerequisite to beginning the Resource Conservation and Recovery Act (RCRA) corrective action process. The removal of radioactive surface contamination was performed in order to reduce potential impacts to human health and the environment. The predominant radiological contaminant of concern was depleted uranium (DU). Between October 1993 and November 1996 scanning surface radiation surveys, using gamma scintillometers, were conducted at 65 sites covering approximately 908 acres. A total of 9,518 radiation anomalies were detected at 38 sites. Cleanup activities were conducted between October 1994 and November 1996. A total of 9,122 anomalies were removed and 2,072 waste drums were generated. The majority of anomalies not removed were associated with a site that has subsurface contamination beyond the scope of this project. Verification soil samples (1,008 total samples) were collected from anomalies during cleanup activities and confirm that the soil concentration achieved in the field were far below the target cleanup level of 230 pCi/g of U-238 (the primary constituent of DU) in the soil. Cleanup was completed at 21 sites and no further radiological action is required. Seventeen sites were not completed since cleanup activities wee precluded by ongoing site activity or were beyond the original project scope.

  16. Hydrological modeling using a multi-site stochastic weather generator

    Science.gov (United States)

    Weather data is usually required at several locations over a large watershed, especially when using distributed models for hydrological simulations. In many applications, spatially correlated weather data can be provided by a multi-site stochastic weather generator which considers the spatial correl...

  17. Radiological mapping of Mumbai-Arakkonam rail route

    International Nuclear Information System (INIS)

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

    2018-01-01

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

  18. Cursory radiological assessment: Battelle Columbus Laboratory Decommissioning and Decontamination Project

    International Nuclear Information System (INIS)

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

    1988-10-01

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

  19. Site-optimization of wind turbine generators

    Energy Technology Data Exchange (ETDEWEB)

    Wolff, T.J. de; Thillerup, J. [Nordtank Energy Group, Richmond, VA (United States)

    1997-12-31

    The Danish Company Nordtank is one of the pioneers within the wind turbine industry. Since 1981 Nordtank has installed worldwide more than 2500 wind turbine generators with a total name plate capacity that is exceeding 450 MW. The opening up of new and widely divergent markets has demanded an extremely flexible approach towards wind turbine construction. The Nordtank product range has expanded considerable in recent years, with the main objective to develop wind energy conversion machines that can run profitable in any given case. This paper will describe site optimization of Nordtank wind turbines. Nordtank has developed a flexible design concept for its WTGs in the 500/750 kW range, in order to offer the optimal WTG solution for any given site and wind regime. Through this flexible design, the 500/750 turbine line can adjust the rotor diameter, tower height and many other components to optimally fit the turbine to each specific project. This design philosophy will be illustrated with some case histories of recently completed projects.

  20. Radiological control guide for decommissioning of the TRIGA mark-2, 3

    International Nuclear Information System (INIS)

    Lee, Bong Jae

    2000-08-01

    The purpose of radiological control for TRIGA mark-2, 3 research reactors and facilities at the KAERI Seoul site, which are to be decommissioned, is in minimizing the radiation exposure for workers and in preventing the release of the radioactive materials to the environment. In order to accomplish these goal, the radiological control guide will be prepared during the decommissioning activities. Therefore, it is expected that this technical report can be used in preparing radiological control guide for safety decommissioning of the TRIGA mark-2, 3

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

    International Nuclear Information System (INIS)

    Mueller, P.G.

    2000-01-01

    During the 1960's and 70's the expanded use of nuclear materials to generate electricity, to provide medical benefits, and for research purposes continued to grow in the United States. While substantial effort went into constructing plants and facilities and providing for a number of redundant backup systems for safety purposes, little effort went into the development of emergency response plans for possible major radiological accidents. Unfortunately, adequate plans and procedures had not been developed to co-ordinate either state or federal emergency response assets and personnel should a major radiological accident occur. This situation became quite evident following the Three Mile Island Nuclear Reactor accident in 1979. An accident of that magnitude had not been adequately prepared for and Pennsylvania's limited emergency radiological resources and capabilities were quickly exhausted. Several federal agencies with statutory responsibilities for emergency response, including the U.S. Environmental Protection Agency (EPA), U.S. Department of Energy (DOE), Federal Emergency Management Agency (FEMA), Nuclear Regulatory Commission (NRC), and others provided extensive assistance and support during the accident. However, the assistance was not fully co-ordinated nor controlled. Following the Three Mile Island incident 13 federal agencies worked co-operatively to develop an agreement called the Federal Radiological Emergency Response Plan (FRERP). Signed in November 1985, this plan delineated the statutory responsibilities and authorities of each federal agency signatory to the FRERP. In the event of a major radiological accident, the FRERP would be activated to ensure that a co-ordinated federal emergency response would be available to respond to any major radiological accident scenario. The FRERP encompasses a wide variety of radiological accidents, not just those stemming from nuclear power plants. Activation of the FRERP could occur from major accidents involving

  2. 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

  3. Results of the radiological survey at 14 Saint Ann Place, Rochelle Park, New Jersey (MJ032)

    International Nuclear Information System (INIS)

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

    1990-03-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally 232 Th, derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, 14 Saint Ann Place, Rochelle Park, New Jersey (MJ032), was conducted during 1987. 4 refs., 3 tabs

  4. Annual Site Environmental Report for Calendar Years 2005-2006

    Energy Technology Data Exchange (ETDEWEB)

    Virginia L. Finley

    2010-01-25

    Contained in the following report are data for radioactivity in the environment collected and analyzed by Princeton Plasma Physics Laboratory's Princeton Environmental, Analytical, and Radiological Laboratory (PEARL). The PEARL is located on-site and is certified for analyzing radiological and non-radiological parameters through the New Jersey Department of Environmental Protection's Laboratory Certification Program, Certification Number 12471. Non-radiological surface and ground water samples are analyzed by NJDEP certified subcontractor laboratories - QC, Inc. and Accutest Laboratory. To the best of our knowledge, these data, as contained in the "Annual Site Environmental Report for 2005 and 2006," are documented and certified to be correct.

  5. Assessment of radiological properties of wastes from urban decontamination procedures

    International Nuclear Information System (INIS)

    Da Silva, D.N.G.; Guimarães, J.R.D.; Rochedo, E.R.R.; Rochedo, P.R.R.; De Luca, C.

    2015-01-01

    One important activity associated to urban areas contaminated from accidental releases to the atmosphere of nuclear power plants is the management of radioactive wastes generated from decontamination procedures. This include the collection, conditioning, packing, transport and temporary/final disposition. The final destination is defined usually through a political decision. Thus, transport of packed radioactive wastes shall depend on decisions not just under the scope of radiological protection issues. However, the simulations performed to assess doses for the public and decontamination workers allows the estimate of radiological aspects related to the waste generated and these characteristics may be included in a multi-criteria decision tool aiming to support, under the radiological protection point of view, the decision-making process on post-emergency procedures. Important information to decision makers are the type, amount and activity concentration of wastes. This work describes the procedures to be included in the urban area model to account for the assessment of qualitative and quantitative description of wastes. The results will allow the classification of different procedures according to predefined criteria that shall then feed the multi-criteria assessment tool, currently under development, considering basic radiological protection aspects of wastes generated by the different available cleanup procedures on typical tropical urban environments. (authors)

  6. Estimation of dose challenge in radiological exams policontuses patients in public hospital in Santiago with digital radiology equipment

    International Nuclear Information System (INIS)

    Diaz-Munoz Ihmaidan, Gabriela

    2012-01-01

    lonizing radiation is always present in our natural environment and with the development of new technologies in diagnostic radiology we have elevated the exposure to radiation with an increased dose to both patient and professionals. This is of great importance for secondary stochastic effects that could be generated by exposure to ionizing radiation. There are different x-ray entrance dose studies in patients with radiological examinations in conventional radiology equipment, but not in trauma patients examinated with digital radiology equipment where there is a supposed greater exposure to radiation because of the increase of the number of radiological examinations requested. This study determined the doses received by trauma patients in a direct digital x ray equipment (in a ER in Santiago, Chile) and see if the doses are within the ones recommended by international societies. We used thermoluminescent crystals which were first properly calibrated and located in the center of the radiation beam. The results obtained show that using good practice we can obtain acceptable dose levels, independently of the digital equipment used where it is presumed that could give a higher dose of ionizing radiation exposure than conventional x-ray equipment

  7. 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

  8. New nuclear build and evolving radiological protection challenges

    International Nuclear Information System (INIS)

    Lazo, T.

    2010-01-01

    Many trends and indicators suggest that the use of nuclear power for generating electricity will increase, perhaps significantly, in the coming 10 to 20 years and beyond. Any such expansion will not take place in a static scientific or social context, but rather in the midst of ongoing changes in many relevant fields, radiological protection, radioactive waste management and nuclear safety to name a few. Regarding radiological protection, this evolution can be characterised in many different ways, but can conveniently be described as having scientific and socially driven aspects. These may well pose challenges to radiological protection (RP) policy, regulation and application in the future

  9. 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.

  10. Application of computers in a radiological survey program

    International Nuclear Information System (INIS)

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

    1984-01-01

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

  11. Radiological Final Status Survey of the Hammond Depot, Hammond, Indiana

    International Nuclear Information System (INIS)

    Vitkus, T.J.

    2008-01-01

    ORISE conducted extensive scoping, characterization, and final status surveys of land areas and structures at the DNSC's Hammond Depot located in Hammond, Indiana in multiple phases during 2005, 2006 and 2007. This report provides a detailed discussion of the radiological survey planning, survey implementation, remediation, and the results for these activities supporting the conclusion that radioactive contamination previously identified at the Hammond Depot (HD) has been reduced to levels such that the site may be released without radiological restrictions. The objective of the radiological final status survey (FSS) was to obtain the data necessary to demonstrate compliance with the U.S. Nuclear Regulatory Commission (NRC)-approved site-specific derived concentration guideline levels (DCGLs) for both structural surfaces and outdoor areas (ORISE 2006a and NRC 2007). The DCGLs were modeled such that any residual licensed material would not exceed the NRC's basic dose limit for license termination of 25 millirem per year (mrem/y)

  12. Radiological Worker Training: Radiological Worker 2 study guides

    International Nuclear Information System (INIS)

    1992-10-01

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

  13. Aerial radiological survey of the Rancho Seco Nuclear Generating Station, Clay Station, California, 18 January 1980 to 1 February 1980

    International Nuclear Information System (INIS)

    1980-11-01

    An airborne radiological survey of 260 km 2 area centered over the Rancho Seco Nuclear Generating Station was made 18 January through 1 February 1980. Detected radioisotopes and their associated gamma ray exposure rates were consistent with that expected from normal background emitters, except directly over the station. Count rates observed at 90 m altitude were converted to exposure rates at 1 m above the ground and are presented in the form of an isopleth map

  14. 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)

  15. Radiological clerkships as a critical curriculum component in radiology education

    International Nuclear Information System (INIS)

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

    2011-01-01

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

  16. Results of the radiological survey at 9 Redstone Lane, Lodi, New Jersey (LJ069)

    International Nuclear Information System (INIS)

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

    1989-07-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process waste and residues associated with the production and refining of thorium and thorium compounds from monozite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Areas residents used the sandlike waste from this thorium extraction process mixed with teas and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigate radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally 232 Th, derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, 9 Redstone Lane, Lodi, New Jersey (LJ069), was conducted during 1987. Measurements at the private property located at 9 Redstone Lane indicate slightly elevated gamma exposure rates in association with cinder-like material observed in logging holes. These elevated levels result from naturally occurring radioactivity present in such substances as ashes and cinders. They are not related to the deposit of residues from processing operations at the MCW site. All other radiological findings conform to the guidelines established by the DOE for the Maywood, New Jersey, area remedial action plan. 4 refs., 3 figs., 3 tabs

  17. 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

  18. Optimization aspects of the ARAC real-time radiological emergency response system

    International Nuclear Information System (INIS)

    Taylor, S.S.; Sullivan, T.J.

    1985-07-01

    The Atmospheric Release Advisory Capability (ARAC) project at the Lawrence Livermore National Laboratory responds to radiological emergencies throughout the Continental United States. Using complex three-dimensional dispersion models to account for the effects of complex meteorology and regional terrain, ARAC simulates the release of radioactive materials and provides dispersion, deposition, and dose calculations that are displayed over local geographic features for use by authorities at the accident/release site. ARAC's response is ensured by a software system that (1) makes optimal use of dispersion models, (2) minimizes the time required to provide projections, and (3) maximizes the fault-tolerance of the system. In this paper we describe ARAC's goals and functionality and the costs associated with its development and use. Specifically, we address optimizations in ARAC notifications, meteorological data collection, the determination of site- and problem-specific parameters, the generation of site-specific topography and geography, the running of models, and the distribution of ARAC products. We also discuss the backup features employed to ensure ARAC's ability to respond

  19. Customer adoption of small-scale on-site power generation

    Energy Technology Data Exchange (ETDEWEB)

    Siddiqui, Afzal S.; Marnay, Chris; Hamachi, Kristina S.; Rubio, F. Javier

    2001-04-01

    The electricity supply system is undergoing major regulatory and technological change with significant implications for the way in which the sector will operate (including its patterns of carbon emissions) and for the policies required to ensure socially and environmentally desirable outcomes. One such change stems from the rapid emergence of viable small-scale (i.e., smaller than 500 kW) generators that are potentially competitive with grid delivered electricity, especially in combined heat and power configurations. Such distributed energy resources (DER) may be grouped together with loads in microgrids. These clusters could operate semi-autonomously from the established power system, or macrogrid, matching power quality and reliability more closely to local end-use requirements. In order to establish a capability for analyzing the effect that microgrids may have on typical commercial customers, such as office buildings, restaurants, shopping malls, and grocery stores, an economic mod el of DER adoption is being developed at Berkeley Lab. This model endeavors to indicate the optimal quantity and type of small on-site generation technologies that customers could employ given their electricity requirements. For various regulatory schemes and general economic conditions, this analysis produces a simple operating schedule for any installed generators. Early results suggest that many commercial customers can benefit economically from on-site generation, even without considering potential combined heat and power and reliability benefits, even though they are unlikely to disconnect from the established power system.

  20. Customer adoption of small-scale on-site power generation

    International Nuclear Information System (INIS)

    Siddiqui, Afzal S.; Marnay, Chris; Hamachi, Kristina S.; Rubio, F. Javier

    2001-01-01

    The electricity supply system is undergoing major regulatory and technological change with significant implications for the way in which the sector will operate (including its patterns of carbon emissions) and for the policies required to ensure socially and environmentally desirable outcomes. One such change stems from the rapid emergence of viable small-scale (i.e., smaller than 500 kW) generators that are potentially competitive with grid delivered electricity, especially in combined heat and power configurations. Such distributed energy resources (DER) may be grouped together with loads in microgrids. These clusters could operate semi-autonomously from the established power system, or macrogrid, matching power quality and reliability more closely to local end-use requirements. In order to establish a capability for analyzing the effect that microgrids may have on typical commercial customers, such as office buildings, restaurants, shopping malls, and grocery stores, an economic mod el of DER adoption is being developed at Berkeley Lab. This model endeavors to indicate the optimal quantity and type of small on-site generation technologies that customers could employ given their electricity requirements. For various regulatory schemes and general economic conditions, this analysis produces a simple operating schedule for any installed generators. Early results suggest that many commercial customers can benefit economically from on-site generation, even without considering potential combined heat and power and reliability benefits, even though they are unlikely to disconnect from the established power system

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

    Science.gov (United States)

    Chew, Felix S

    2002-11-01

    page of the Web site provided the schedule, faculty names, attendance and grading policies, course overview, and links to individual tutorials. The pages for individual tutorials included educational objectives, glossary of radiology terminology relevant to the subject, lecture slides and handouts, and teaching cases. All students had laptop computers and access to the academic network, but did not use them during the actual tutorial sessions. Implementation of the radiology clerkship required extensive negotiation with directors of other clerkships so that students could be released from their other responsibilities in order to attend the radiology tutorials. The radiology clerkship format has proven to be complex in its administration, with faculty and students on different schedules commuting to the radiology lecture hall from various locations. Extensive use of e-mail and communication via the Web site have been instrumental in reminding faculty and students of upcoming sessions. Preliminary evaluations have indicated that students liked the radiology sessions and learned a great deal, but disliked the scheduling and the lack of continuity. An evaluation of the curriculum and its components is ongoing.

  2. 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.

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

    International Nuclear Information System (INIS)

    Mckinney, S.M.

    1997-01-01

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

  4. Nuclear power plant site evaluation using site population-meterology factor

    International Nuclear Information System (INIS)

    Rho, B.H.; Kang, C.H.

    1982-01-01

    In this paper, as a site evaluation technique, SPNF(Site Population Neteorology Factor) which is modified from SPF(Site Population Factor) of the USNRC model, is defined from site population and meteorology data in order to consider the radiological impacts to the population at large from the atmospheric dispersion of the radioactive effluents released during routine plant operation as well as accidental conditions. The SPMF model proved its propriety from the comparison of SPMF and SPF for Kori site. The relative suitability of Korean sites to the U.S. sites have been also examined using SPF. (Author)

  5. Cancer incidence among radiologic technologists and nurses in Lithuania

    International Nuclear Information System (INIS)

    Smerdokiene, V.

    2000-01-01

    The retrospective cohort study of 'Cancer incidence among persons, working at ionizing radiation environment' was performed. The cohort consisted of 2034 persons (13.82% males and 86.18% females). Among them 475 were radiologists (doctors), 868 - radiologic technologists (all of them females) and 470 nurses (cleaners in radiology departments). The members of the cohort were followed -up retrospectively from 01.01.1978 until 31.12.1977. Standard Incidence Ratio for all cancers in the cohort of female radiologic technologists was 1,31 [0,90-1,85], of female nurses -1,99 [1,26-2,99]. The size of cohorts and follow-up period were too small for site - specific analysis of cancer incidence. (author)

  6. Text Simplification Using Consumer Health Vocabulary to Generate Patient-Centered Radiology Reporting: Translation and Evaluation.

    Science.gov (United States)

    Qenam, Basel; Kim, Tae Youn; Carroll, Mark J; Hogarth, Michael

    2017-12-18

    Radiology reporting is a clinically oriented form of documentation that reflects critical information for patients about their health care processes. Realizing its importance, many medical institutions have started providing radiology reports in patient portals. The gain, however, can be limited because of medical language barriers, which require a way for customizing these reports for patients. The open-access, collaborative consumer health vocabulary (CHV) is a terminology system created for such purposes and can be the basis of lexical simplification processes for clinical notes. The aim of this study was to examine the comprehensibility and suitability of CHV in simplifying radiology reports for consumers. This was done by characterizing the content coverage and the lexical similarity between the terms in the reports and the CHV-preferred terms. The overall procedure was divided into the following two main stages: (1) translation and (2) evaluation. The translation process involved using MetaMap to link terms in the reports to CHV concepts. This is followed by replacing the terms with CHV-preferred terms using the concept names and sources table (MRCONSO) in the Unified Medical Language System (UMLS) Metathesaurus. In the second stage, medical terms in the reports and general terms that are used to describe medical phenomena were selected and evaluated by comparing the words in the original reports with the translated ones. The evaluation includes measuring the content coverage, investigating lexical similarity, and finding trends in missing concepts. Of the 792 terms selected from the radiology reports, 695 of them could be mapped directly to CHV concepts, indicating a content coverage of 88.5%. A total of 51 of the concepts (53%, 51/97) that could not be mapped are names of human anatomical structures and regions, followed by 28 anatomical descriptions and pathological variations (29%, 28/97). In addition, 12 radiology techniques and projections represented

  7. Overview of Generation IV (Gen IV) Reactor Designs - Safety and Radiological Protection Considerations. Published on September 24, 2012

    International Nuclear Information System (INIS)

    Couturier, Jean; Bruna, Giovanni; Baudrand, Olivier; Blanc, Daniel; Ivanov, Evgeny; Bonneville, Herve; Clement, Bernard; Kissane, Martin; Meignen, Renaud; Monhardt, Daniel; Nicaise, Gregory; Bourgois, Thierry; Hache, Georges

    2012-01-01

    The purpose of this document is to provide an updated overview of specific safety and radiological protection issues for all the reactor concepts adopted by the GIF (Generation IV International Forum), independent of their advantages or disadvantages in terms of resource optimization or long-lived-waste reduction. In particular, this new document attempts to bring out the advantages and disadvantages of each concept in terms of safety, taking into account the Western European Nuclear Regulators' Association (WENRA) statement concerning safety objectives for new nuclear power plants. Using an identical framework for each reactor concept (sodium-cooled fast reactors or SFR, high / very-high temperature helium-cooled reactors of V/HTR, gas-cooled fast reactors or GFR, lead-or lead / bismuth-cooled fast reactors or LFR, molten salt reactors or MSR, and supercritical-water-cooled reactors or SCWR), this summary report provides some general conclusions regarding their safety and radiological protection issues, inspired by WENRA's safety objectives and on the basis of available information. Initial lessons drawn from the events at the Fukushima-Daiichi nuclear power plant in March 2011 have also been taken into account in IRSN's analysis of each reactor concept

  8. Evaluation of Absorbents for Compatibility with Site Generated Hazardous and Mixed Liquid Wastes

    International Nuclear Information System (INIS)

    Oji, L.N.

    2002-01-01

    SRS Solid Waste requested SRTC to perform a literature-based evaluation of sorbents, which are compatible with hazardous mixed waste being generated on site. Polypropylene-based materials and ground corn cob (Toxi-dry), because of their compatibility with the Consolidated Incinerator Facility (CIF) process, are the only two spill stabilization agents which are recommended for use on site (IS manual, Waste Acceptance Criteria 3.18). While ensuring minimal potential for undesired reactions between spills and spill control agents, Solid Waste wants to increase the number of site approved absorbents to give waste generators more flexibility in choosing liquid spill immobilization agents

  9. Industrial Sites Project Establishment of Final Action Levels

    International Nuclear Information System (INIS)

    Boehlecke, Robert F.

    2006-01-01

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

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

    International Nuclear Information System (INIS)

    1993-09-01

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

  11. Federal Radiological Monitoring and Assessment Center Analytical Response

    International Nuclear Information System (INIS)

    Nielsen, E.C.

    2003-01-01

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

  12. Environmental radiological studies downstream from Rancho Seco Nuclear Power Generating Station

    International Nuclear Information System (INIS)

    Noshkin, V.E.; Wong, K.M.; Eagle, R.J.; Dawson, J.W.; Brunk, J.L.; Jokela, T.A.

    1985-01-01

    This report summarizes the information compiled in 1984 while assessing the environmental impact of radionuclides in aquatic releases from the Rancho Seco Nuclear Power Generating Station. Gamma-emitting radionuclides discharged since 1981 are found in many of the dietary components derived from the creeks receiving the effluent wastewater. Some soils and crops are found to contain radionuclides that originate from the contaminated water that was transferred to land during the irrigation season. 134 Cs and 137 Cs are the primary gamma-emitting radionuclides detected in the edible flesh of fish from the creeks. Concentrations in the flesh of fish decreased exponentially with distance from the plant. No significant differences in the 137 Cs activity were found between male and female fish of equal size, but concentrations may vary in fish of different size, with the season and diet. 21% of the total 137 Cs and 134 Cs discharged between 1981 and 1984 is associated with the creek sediments to a distance of 27 km from the plant. Fractions of the missing inventory have been transferred to land during the irrigation season or to downstream regions more distant than 27 km from the plant. The radiocesium content of the sediments in 1984 decreased significantly in a downstream direction, much in the same manner as concentrations decreased in fish. Radioactivity originating from the plant was not above detection limits in any terrestrial food item sampled beyond 6.5 km from the plant. Based on the usage factors provided by individuals interviewed in a 1984 survey, the fish and aquatic-organism ingestion pathway contributed the largest radiological dose to humans utilizing products contaminated with the radionuclides in the liquid wastes discharged from the Rancho Seco Nuclear Power Generating Station in 1984

  13. Radiological design criteria for fusion power test facilities

    International Nuclear Information System (INIS)

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

    1982-01-01

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

  14. Radiation Protection in Paediatric Radiology

    International Nuclear Information System (INIS)

    2012-01-01

    Over the past decade and a half, special issues have arisen regarding the protection of children undergoing radiological examinations. These issues have come to the consciousness of a gradually widening group of concerned professionals and the public, largely because of the natural instinct to protect children from unnecessary harm. Some tissues in children are more sensitive to radiation and children have a long life expectancy, during which significant pathology can emerge. The instinct to protect children has received further impetus from the level of professional and public concern articulated in the wake of media responses to certain publications in the professional literature. Many institutions have highlighted the need to pay particular attention to the special problems of protecting paediatric patients. The International Commission on Radiological Protection has noted it and the IAEA's General Safety Requirements publication, Radiation Protection and Safety of Radiation Sources: International Basic Safety Standards (BSS), requires it. This need has been endorsed implicitly in the advisory material on paediatric computed tomography scanning issued by bodies such as the US Food and Drug Administration and the National Cancer Institute in the United States of America, as well as by many initiatives taken by other national and regional radiological societies and professional bodies. A major part of patient exposure, in general, and paediatric exposure, in particular, now arises from practices that barely existed two decades ago. For practitioners and regulators, it is evident that this innovation has been driven both by the imaging industry and by an ever increasing array of new applications generated and validated in the clinical environment. Regulation, industrial standardization, safety procedures and advice on best practice lag (inevitably) behind industrial and clinical innovations. This Safety Report is designed to consolidate and provide timely advice on

  15. Federal Radiological Monitoring and Assessment Center. The analytical response

    International Nuclear Information System (INIS)

    Nielsen, E.C.

    2005-01-01

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

  16. 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

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

    International Nuclear Information System (INIS)

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

    1997-01-01

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

  18. Nevada National Security Site Radiation Protection Program

    Energy Technology Data Exchange (ETDEWEB)

    Managers' Council, Radiological Control

    2018-03-12

    This is a shared document required by 10 CFR 835 for all contractors conducting radiological work at the Nevada National Security Site. Please record the Author as "Radiological Control Managers' Council" for consistency with previous RPPs and Rad Con Manuals.

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

    International Nuclear Information System (INIS)

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

    1995-07-01

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

  20. Description of the Formerly Utilized Sites Remedial Action Program

    International Nuclear Information System (INIS)

    1980-09-01

    The background and the results to date of the Department of Energy program to identify and evaluate the radiological conditions at sites formerly utilized by the Corps of Engineers' Manhattan Engineer District (MED) and the US Atomic Energy Commission (AEC) are summarized. The sites of concern were federally, privately, and institutionally owned and were used primarily for research, processing, and storage of uranium and thorium ores, concentrates, or residues. Some sites were subsequently released for other purposes without radiological restriction. Surveys have been conducted since 1974 to document radiological conditions at such sites. Based on radiological surveys, sites are identified in this document that require, or are projected to require, remedial action to remove potential restrictions on the use of the property due to the presence of residual low-level radioactive contamination. Specific recommendations for each site will result from more detailed environmental and engineering surveys to be conducted at those sites and, if necessary, an environmental impact assessment or environmental impact statement will be prepared. Section 3.0 describes the current standards and guidelines now being used to conduct remedial actions. Current authority of the US Department of Energy (DOE) to proceed with remedial actions and the new authority required are summarized. A plan to implement the Formerly Utilized Sites Remedial Action Program (FUSRAP) in accordance with the new authority is presented, including the objectives, scope, general approach, and a summary schedule. Key issues affecting schedule and cost are discussed

  1. Description of the Formerly Utilized Sites Remedial Action Program

    Energy Technology Data Exchange (ETDEWEB)

    1980-09-01

    The background and the results to date of the Department of Energy program to identify and evaluate the radiological conditions at sites formerly utilized by the Corps of Engineers' Manhattan Engineer District (MED) and the US Atomic Energy Commission (AEC) are summarized. The sites of concern were federally, privately, and institutionally owned and were used primarily for research, processing, and storage of uranium and thorium ores, concentrates, or residues. Some sites were subsequently released for other purposes without radiological restriction. Surveys have been conducted since 1974 to document radiological conditions at such sites. Based on radiological surveys, sites are identified in this document that require, or are projected to require, remedial action to remove potential restrictions on the use of the property due to the presence of residual low-level radioactive contamination. Specific recommendations for each site will result from more detailed environmental and engineering surveys to be conducted at those sites and, if necessary, an environmental impact assessment or environmental impact statement will be prepared. Section 3.0 describes the current standards and guidelines now being used to conduct remedial actions. Current authority of the US Department of Energy (DOE) to proceed with remedial actions and the new authority required are summarized. A plan to implement the Formerly Utilized Sites Remedial Action Program (FUSRAP) in accordance with the new authority is presented, including the objectives, scope, general approach, and a summary schedule. Key issues affecting schedule and cost are discussed.

  2. 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.

  3. Developing standard transmission system for radiology reporting including key images

    International Nuclear Information System (INIS)

    Kim, Seon Chil

    2007-01-01

    Development of hospital information system and Picture Archiving Communication System is not new in the medical field, and the development of internet and information technology are also universal. In the course of such development, however, it is hard to share medical information without a refined standard format. Especially in the department of radiology, the role of PACS has become very important in interchanging information with other disparate hospital information systems. A specific system needs to be developed that radiological reports are archived into a database efficiently. This includes sharing of medical images. A model is suggested in this study in which an internal system is developed where radiologists store necessary images and transmit them is the standard international clinical format, Clinical Document Architecture, and share the information with hospitals. CDA document generator was made to generate a new file format and separate the existing storage system from the new system. This was to ensure the access to required data in XML documents. The model presented in this study added a process where crucial images in reading are inserted in the CDA radiological report generator. Therefore, this study suggests a storage and transmission model for CDA documents, which is different from the existing DICOM SR. Radiological reports could be better shared, when the application function for inserting images and the analysis of standard clinical terms are completed

  4. 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....

  5. Sampling on radiological protection training in diagnostic radiology

    International Nuclear Information System (INIS)

    Gaona, E.

    2001-01-01

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

  6. Radiological Tenckhoff catheter insertion for peritoneal dialysis: A cost-effective approach.

    Science.gov (United States)

    Lee, James; Mott, Nigel; Mahmood, Usman; Clouston, John; Summers, Kara; Nicholas, Pauline; Gois, Pedro Henrique França; Ranganathan, Dwarakanathan

    2018-04-01

    Radiological insertion of Tenckhoff catheters can be an alternative option for peritoneal dialysis access creation, as compared to surgical catheter insertion. This study will review the outcomes and complications of radiological Tenckhoff catheter insertion in a metropolitan renal service and compare costs between surgical and radiological insertion. Data were collected prospectively for all patients who had a Tenckhoff catheter insertion for peritoneal dialysis (PD) under radiological guidance at our hospital from May 2014 to November 2016. The type of catheter used and complications, including peri-catheter leak, exit site infection and peritonitis were reviewed. Follow-up data were also collected at points 3, 6 and 12 months from catheter insertion. Costing data were obtained from Queensland Health Electronic Reporting System (QHERS) data, average staff salaries and consumable contract price lists. In the 30-month evaluation period, 70 catheters were inserted. Two patients had an unsuccessful procedure due to the presence of abdominal adhesions. Seven patients had an episode of peri-catheter leak, and four patients had an exit site infection following catheter insertion. Peritonitis was observed in nine patients during the study period. The majority of patients (90%) remained on peritoneal dialysis at 3-month follow-up. The average costs of surgical and radiological insertion were noted to be AUD$7788.34 and AUD$1597.35, respectively. Radiological Tenckhoff catheter insertion for peritoneal dialysis appears to be an attractive and cost-effective option given less waiting periods for the procedure, the relatively low cost of insertion and comparable rates of complications. © 2017 The Royal Australian and New Zealand College of Radiologists.

  7. Radiological decontamination, survey, and statistical release method for vehicles

    International Nuclear Information System (INIS)

    Goodwill, M.E.; Lively, J.W.; Morris, R.L.

    1996-06-01

    Earth-moving vehicles (e.g., dump trucks, belly dumps) commonly haul radiologically contaminated materials from a site being remediated to a disposal site. Traditionally, each vehicle must be surveyed before being released. The logistical difficulties of implementing the traditional approach on a large scale demand that an alternative be devised. A statistical method for assessing product quality from a continuous process was adapted to the vehicle decontamination process. This method produced a sampling scheme that automatically compensates and accommodates fluctuating batch sizes and changing conditions without the need to modify or rectify the sampling scheme in the field. Vehicles are randomly selected (sampled) upon completion of the decontamination process to be surveyed for residual radioactive surface contamination. The frequency of sampling is based on the expected number of vehicles passing through the decontamination process in a given period and the confidence level desired. This process has been successfully used for 1 year at the former uranium millsite in Monticello, Utah (a cleanup site regulated under the Comprehensive Environmental Response, Compensation, and Liability Act). The method forces improvement in the quality of the decontamination process and results in a lower likelihood that vehicles exceeding the surface contamination standards are offered for survey. Implementation of this statistical sampling method on Monticello projects has resulted in more efficient processing of vehicles through decontamination and radiological release, saved hundreds of hours of processing time, provided a high level of confidence that release limits are met, and improved the radiological cleanliness of vehicles leaving the controlled site

  8. A radiological legacy. Radioactive residues of the Cold War period

    International Nuclear Information System (INIS)

    Gonzalez, A.J.

    1998-01-01

    A dominating feature of the historical period known as the Cold War was the large-scale production and testing, of nuclear weapons. These military activities brought with them an unprecedented generation of radioactive substances. A fraction of these 'Cold War residues' ended up in the atmosphere and were dispersed throughout the world. Some remained in relatively isolated states in underground geological environments at the production or test site. Others have contaminated areas at times accessible to humans. Augmenting this picture are other scenes of a Cold War legacy. Large amounts of radioactive waste and byproducts are in storage from the production of weapons material. At some point, they are expected to be converted to peaceful applications or sent for final disposal. Over the past decade, the IAEA has been asked to play a greater role in helping countries address this Cold War legacy. A number of scientific assessments of radiological situations created by the Cold War have been carried out by experts convened by the IAEA - at nuclear test sites, nuclear production facilities, and waste dumping sites. This edition of the IAEA Bulletin highlights these cooperative activities in the context of international developments and concerns

  9. Radiological impact assessment in Bagjata uranium deposit: a case study

    International Nuclear Information System (INIS)

    Sarangi, A.K.; Bhowmik, S.C.; Jha, V.N.

    2007-01-01

    The uranium ore mining facility, in addition to the desirable product, produces wastes in the form of environmental releases or effluents to air, water and soil. The toxicological and other (non-radiological) effects are generally addressed in EIA/EMP studies as per MOEF guidelines. Since the uranium ore is radioactive, it is desirable to conduct a study on radiological effects considering the impacts of radiological releases to the environment. Before undertaking the commercial mining operations at Bagjata uranium deposit in the Singhbhum east district of Jharkhand, pre-operational radiological base line data were generated and a separate study on radiological impact on various environmental matrices was conducted in line with the International Atomic Energy Agency's laid out guidelines. The paper describes the philosophy of such studies and the findings that helped in formulating a separate environmental management plan. (author)

  10. Entrepreneurial Women in Radiology: Role Models of Success.

    Science.gov (United States)

    Anzai, Yoshimi; Meltzer, Carolyn C; DeStigter, Kristen K; Destounis, Stamatia; Pawley, Barbara K; Oates, M Elizabeth

    2016-11-01

    Radiology is undeniably male dominated. Alongside surgery and orthopedic surgery, academic radiology ranks near the bottom in having the lowest proportion of full-time female faculty members. Despite many efforts to recruit talented women, the pipeline entering the radiologic disciplines continues to flow at a trickle. One factor is the relative lack of role models for female medical students. Entrepreneurial women in radiology can lead the field with their innovation and creativity, courage, and commitment. In this article, the authors highlight two entrepreneurial female radiologists who shared their success stories at the American Association for Women Radiologists' session at the 2015 ACR annual meeting. Their successes underscore the potential for such women to serve as role models to female medical students and even college undergraduates. Despite the gender gap in radiology, the field has yielded some exceptional women who can take on challenges, overcome barriers and assume risks, create strategies and processes to operationalize their visions, secure funding, and expand their enterprises to make sustainable impacts both at home and abroad. As we move toward more patient- and family-centered care models and become increasingly visible to diverse populations, there is no better time for female leaders in radiology to inspire the next generation to join our essential and rewarding specialty. Copyright © 2016 American College of Radiology. Published by Elsevier Inc. All rights reserved.

  11. The radiological accident in Yanango

    International Nuclear Information System (INIS)

    2000-01-01

    The use of nuclear technologies has fostered new, more effective and efficient medical procedures and has substantially improved diagnostic and therapeutic capabilities. However, in order that the benefits of the use of ionizing radiation outweigh the potential hazards posed by this medium, it is important that radiation protection and safety standards be established to govern every aspect of the application of ionizing radiation. Adherence to these standards needs to be maintained through effective regulatory control, safe operational procedures and a safety culture that is shared by all. Occasionally, established safety procedures are violated and serious radiological consequences ensue. The radiological accident described in this report, which took place in Lilo, Georgia, was a result of such an infraction. Sealed radiation sources had been abandoned by a previous owner at a site without following established regulatory safety procedures, for example by transferring the sources to the new owner or treating them as spent material and conditioning them as waste. As a consequence, 11 individuals at the site were exposed for a long period of time to high doses of radiation which resulted inter alia in severe radiation induced skin injuries. Although at the time of the accident Georgia was not an IAEA Member State and was not a signatory of the Convention on Assistance in the Case of a Nuclear Accident or Radiological Emergency, the IAEA still provided assistance to the Government of Georgia in assessing the radiological situation, while the World Health Organization (WHO) assisted in alleviating the medical consequences of the accident. The two organizations co-operated closely from the beginning, following the request for assistance by the Georgian Government. The IAEA conducted the radiological assessment and was responsible for preparing the report. The WHO and its collaborating centres within the Radiation Emergency Medical Preparedness and Assistance Network

  12. 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

  13. Nevada Test Site Environmental Report 2004

    International Nuclear Information System (INIS)

    BECHTEL NEVADA

    2005-01-01

    The ''Nevada Test Site Environmental Report 2004'' was prepared by Bechtel Nevada (BN) to meet the information needs of the public and the requirements and guidelines of the U.S. Department of Energy (DOE) for annual site environmental reports. This Executive Summary presents the purpose of the document, the major programs conducted at the Nevada Test Site (NTS), NTS key environmental initiatives, radiological releases and potential doses to the public resulting from site operations, a summary of non-radiological releases, implementation status of the NTS Environmental Management System, and significant environmental accomplishments. Much of the content of this Executive Summary is also presented in a separate stand-alone pamphlet titled ''Nevada Test Site Environmental Report Summary 2004''. It was produced this year to provide a more cost-effective and wider distribution of a hardcopy summary of the ''Nevada Test Site Environmental Report 2004'' to interested DOE stakeholders

  14. American Society for Therapeutic Radiology and Oncology (ASTRO) Emerging Technology Committee Report on Electronic Brachytherapy

    International Nuclear Information System (INIS)

    Park, Catherine C.; Yom, Sue S.; Podgorsak, Matthew B.; Harris, Eleanor; Price, Robert A.; Bevan, Alison; Pouliot, Jean; Konski, Andre A.; Wallner, Paul E.

    2010-01-01

    The development of novel technologies for the safe and effective delivery of radiation is critical to advancing the field of radiation oncology. The Emerging Technology Committee of the American Society for Therapeutic Radiology and Oncology appointed a Task Group within its Evaluation Subcommittee to evaluate new electronic brachytherapy methods that are being developed for, or are already in, clinical use. The Task Group evaluated two devices, the Axxent Electronic Brachytherapy System by Xoft, Inc. (Fremont, CA), and the Intrabeam Photon Radiosurgery Device by Carl Zeiss Surgical (Oberkochen, Germany). These devices are designed to deliver electronically generated radiation, and because of their relatively low energy output, they do not fall under existing regulatory scrutiny of radioactive sources that are used for conventional radioisotope brachytherapy. This report provides a descriptive overview of the technologies, current and future projected applications, comparison of competing technologies, potential impact, and potential safety issues. The full Emerging Technology Committee report is available on the American Society for Therapeutic Radiology and Oncology Web site.

  15. 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).

  16. 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

  17. A Site Selection Model for a Straw-Based Power Generation Plant with CO2 Emissions

    Directory of Open Access Journals (Sweden)

    Hao Lv

    2014-10-01

    Full Text Available The decision on the location of a straw-based power generation plant has a great influence on the plant’s operation and performance. This study explores traditional theories for site selection. Using integer programming, the study optimizes the economic and carbon emission outcomes of straw-based power generation as two objectives, with the supply and demand of straw as constraints. It provides a multi-objective mixed-integer programming model to solve the site selection problem for a straw-based power generation plant. It then provides a case study to demonstrate the application of the model in the decision on the site selection for a straw-based power generation plant with a Chinese region. Finally, the paper discusses the result of the model in the context of the wider aspect of straw-based power generation.

  18. From NIMBY to YIMBY: How generators can support siting LLRW disposal facilities

    International Nuclear Information System (INIS)

    Hoffman, J.P.

    1995-01-01

    The most frequently head complaint about siting low-level radioactive waste disposal facilities is the NIMBY (Not In My Back Yard) syndrome. The producers or generators of this waste can help move public opinion form NIMBY to YIMBY (YES exclamation point In MY Back Yard exclamation point). Generators of low-level radioactive waste often believe it is the responsibility of other organizations to site disposal facilities for the waste, and that their role is to assure the technical aspects of the facility, such as acceptability criteria for the various waste forms, are clearly defined. In reality, generators, using a properly designed and effectively implemented communications plan, can be the most effective advocates for siting a facility. The communications plan must include the following elements: an objective focusing on the importance of generators becoming vocal and active; clearly defined and crafted key messages; specifically defined and targeted audiences for those messages; and speaker training which includes how to communicate with hostile or concerned audiences about a subject they perceive as very risky. Generators must develop coalitions with other groups and form a grassroots support organization. Finally, opportunities must be developed to deliver these messages using a variety of means. Written materials should be distributed often to keep the need for disposal capability in the public's mind. Can we get from NIMBY to YIMBY? It is difficult, but doable--especially with support from the people who make the waste in the first place

  19. Savannah River Site RCRA Facility Investigation plan: Road A Chemical Basin

    International Nuclear Information System (INIS)

    1989-06-01

    The nature of wastes disposed of at the Road A Chemical Basin (RACB) is such that some degree of soil contamination is probable. Lead has also been detected in site monitoring wells at concentrations above SRS background levels. A RCRA Facility Investigation (RFI) is proposed for the RACB and will include a ground penetrating radar (GPR) survey, collection and chemical and radiological analyses of soil cores, installation of groundwater monitoring wells, collection and chemical and radiological analyses of groundwater samples, and collection of chemical and radiological analyses of surface water and sediment samples. Upon completion of the proposed RFI field work and chemical and radiological analyses, and RFI report should be prepared to present conclusions on the nature and extent of contamination at the site, and to make recommendations for site remediation. If contamination is detected at concentrations above SRS background levels, a receptor analysis should be done to evaluate potential impacts of site contamination on nearby populations

  20. Radioactive Waste Management Complex low-level waste radiological performance assessment

    Energy Technology Data Exchange (ETDEWEB)

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

    1994-04-01

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

  1. Radioactive Waste Management Complex low-level waste radiological performance assessment

    International Nuclear Information System (INIS)

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

    1994-04-01

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

  2. Results of the radiological survey at 17 John Street, Lodi, New Jersey

    International Nuclear Information System (INIS)

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

    1989-12-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally 232 Th, derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, 17 John Street, Lodi, New Jersey (LJ088), was conducted during 1988. 5 refs., 2 figs., 3 tabs

  3. Results of the radiological survey at 60 Orchard Place, Maywood, New Jersey

    International Nuclear Information System (INIS)

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

    1989-11-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated waste were also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally 232 Th, derived from the MCW site. The survey typically includes a direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, 60 Orchard Place, Maywood, New Jersey (MJ048), was conducted during 1988. 4 refs., 2 figs., 3 tabs

  4. 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 ...

  5. 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.

  6. Natural Language Processing in Radiology: A Systematic Review.

    Science.gov (United States)

    Pons, Ewoud; Braun, Loes M M; Hunink, M G Myriam; Kors, Jan A

    2016-05-01

    Radiological reporting has generated large quantities of digital content within the electronic health record, which is potentially a valuable source of information for improving clinical care and supporting research. Although radiology reports are stored for communication and documentation of diagnostic imaging, harnessing their potential requires efficient and automated information extraction: they exist mainly as free-text clinical narrative, from which it is a major challenge to obtain structured data. Natural language processing (NLP) provides techniques that aid the conversion of text into a structured representation, and thus enables computers to derive meaning from human (ie, natural language) input. Used on radiology reports, NLP techniques enable automatic identification and extraction of information. By exploring the various purposes for their use, this review examines how radiology benefits from NLP. A systematic literature search identified 67 relevant publications describing NLP methods that support practical applications in radiology. This review takes a close look at the individual studies in terms of tasks (ie, the extracted information), the NLP methodology and tools used, and their application purpose and performance results. Additionally, limitations, future challenges, and requirements for advancing NLP in radiology will be discussed. (©) RSNA, 2016 Online supplemental material is available for this article.

  7. Interactive, Computer-Based Training Program for Radiological Workers

    International Nuclear Information System (INIS)

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

    2000-01-01

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

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

    International Nuclear Information System (INIS)

    Tipton, W.J.

    1977-10-01

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

  9. 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.

  10. Radiologic science students' perceptions of parental involvement.

    Science.gov (United States)

    DuBose, Cheryl; Barymon, Deanna; Vanderford, Virginia; Hensley, Chad; Shaver, Gary

    2014-01-01

    A new generation of students is in the classroom, and they are not always alone. Helicopter parents, those who hover around the student and attempt to ease life's challenges, are accompanying the students to radiologic science programs across the nation. To determine radiologic science students' perception regarding their parents' level of involvement in their lives. A survey focused on student perceptions of parental involvement inside and outside of the academic setting was completed by 121 radiologic science students at 4 institutional settings. The analysis demonstrates statistically significant relationships between student sex, age, marital status, and perceived level of parental involvement. In addition, as financial support increases, students' perception of the level of parental involvement also increases. Radiologic science students want their parents to be involved in their higher education decisions. Research indicates that students with involved parents are more successful, and faculty should be prepared for increased parental involvement in the future. Radiologic science students perceive their parents to be involved in their academic careers. Ninety-five percent of respondents believe that the financial support of their parent or parents contributes to their academic success. Sixty-five percent of participants are content with their parents' current level of involvement, while 11% wish their parents were more involved in their academic careers.

  11. 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

  12. 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.)

  13. 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.)

  14. 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

  15. Procedures manual for the ORNL Radiological Survey Activities (RASA) Program

    International Nuclear Information System (INIS)

    Myrick, T.E.; Berven, B.A.; Cottrell, W.D.; Goldsmith, W.A.; Haywood, F.F.

    1987-04-01

    The portion of the radiological survey program performed by ORNL is the subject of this Procedures Manual. The RASA group of the Health and Safety Research Division (HASRD) at ORNL is responsible for the planning, conducting, and reporting of the results of radiological surveys at specified sites and associated vicinity properties. The results of these surveys are used by DOE in determining the need for and extent of remedial actions. Upon completion of the necessary remedial actions, the ORNL-RASA group or other OOS contractor may be called upon to verify the effectiveness of the remedial action. Information from these postremedial action surveys is included as part of the data base used by DOE in certifying a site for unrestricted use

  16. 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)

  17. Procedures manual for the ORNL Radiological Survey Activities (RASA) Program

    Energy Technology Data Exchange (ETDEWEB)

    Myrick, T.E.; Berven, B.A.; Cottrell, W.D.; Goldsmith, W.A.; Haywood, F.F.

    1987-04-01

    The portion of the radiological survey program performed by ORNL is the subject of this Procedures Manual. The RASA group of the Health and Safety Research Division (HASRD) at ORNL is responsible for the planning, conducting, and reporting of the results of radiological surveys at specified sites and associated vicinity properties. The results of these surveys are used by DOE in determining the need for and extent of remedial actions. Upon completion of the necessary remedial actions, the ORNL-RASA group or other OOS contractor may be called upon to verify the effectiveness of the remedial action. Information from these postremedial action surveys is included as part of the data base used by DOE in certifying a site for unrestricted use.

  18. Results of the independent radiological verification survey at 4400 Piehl Road, Ottawa Lake, Michigan (BTO002)

    Energy Technology Data Exchange (ETDEWEB)

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

    1996-04-01

    At the request of the US Department of Energy (DOE), a team from Oak Ridge National Laboratory (ORNL) conducted an independent radiological verification survey at Ottawa Lake, Michigan. The survey was performed in November and December of 1994. The purpose of the survey was to verify that the site was remediated to levels below the DOE guidelines for FUSRAP sites. Results of the independent radiological verification survey at Ottawa Lake, Michigan confirm that the residual uranium contamination at the site is below DOE FUSRAP guidelines for unrestricted use.

  19. Soils radiological characterization under a nuclear facility - 59046

    International Nuclear Information System (INIS)

    Aubonnet, Emilie; Dubot, Didier

    2012-01-01

    Nowadays, nuclear industry is facing a crucial need in establishing radiological characterization for the appraisal and the monitoring of any remediation work. Regarding its experience in this domain, the French Alternative Energies and Atomic Energy Commission (CEA) of Fontenay-aux- Roses, established an important feedback and developed over the last 10 years a sound methodology for radiological characterization. This approach is based on several steps: - historical investigations; - assumption and confirmation of the contamination; - surface characterization; - in-depth characterization; - rehabilitation objectives; - remediation process. The amount of measures, samples and analysis is optimized for data processing using geo-statistics. This approach is now used to characterize soils under facilities. The paper presents the radiological characterization of soils under a facility basement. This facility has been built after the first generation of nuclear facilities, replacing a plutonium facility which has been dismantled in 1960. The presentation details the different steps of radiological characterization from historical investigations to optimization of excavation depths, impact studies and contaminated volumes. (authors)

  20. Malaysian experiences in radiological safety assessment on norm wastes

    International Nuclear Information System (INIS)

    Syed Hakimi Sakuma Syed Ahmad; Khairuddin Mohamad Kontol

    2000-01-01

    Radiological Impact Assessments (RIAs) on proposed disposal sites for NORM wastes were performed in Malaysia. Analysis results were used to derive site specific guidelines for allowable residual concentrations of radionuclides in soil, calculation of doses and risks. Appropriate use scenarios and site specific parameters were used as much as possible so as to be realistic so that will reasonably ensure that individual dose limits and or constraints will be achieved. Disposals were performed to fulfil Atomic Energy Licensing Board of Malaysia (AELB) requirements for which the operator must carry out a radiological impact assessment. This is to demonstrate that no member of public will be exposed to more than 1 mSv/year from all activities. Fatal cancer risk factor is 5x10 -2 per man.Sv. Radionuclides of main concern are radium-226 and radium-228 which are considered as toxic. Sensitivity and uncertainty analyses were performed to show that the parameters used as input into the computer model were justified so as to improve confidence of the public and the AELB in respect of the results of the analysis. Case study to determine a proposed near surface disposal site for treated oil sludge was described. (author)

  1. Building 773-A, Lab F003 Glovebox Project Radiological Design Summary Report

    International Nuclear Information System (INIS)

    Gaul, W.C.

    2003-01-01

    Engineering Standards present the radiological design criteria and requirements, which must be satisfied for all SRS facility designs. The radiological design criteria and requirements specified in the standard are based on the Code of Federal Regulations, DOE Orders, Site manuals, other applicable standards, and various DOE guides and handbooks. This report contains top-level requirements for the various areas of radiological protection for workers. For the purposes of demonstrating compliance with these requirements, the designer must examine the requirement for the design and either incorporate or provide a technical justification as to why the requirement is not incorporated. This document reports a radiological design review for the STREAK lab glovebox upgrades of inlet ventilation, additional mechanical and electrical services, new glovebox instrumentation and alarms. This report demonstrates that the gloveboxes meet the radiological design requirements of Engineering Standards

  2. United States Department of Energy radiological emergency response programme - a national capability

    International Nuclear Information System (INIS)

    Gordon-Hagerty, L.E.

    1993-01-01

    In order to respond to a radiological emergency, the United States Department of Energy (USDOE) maintains seven emergency response assets and capabilities in support of a radiological emergency of any proportion within the continental United States and abroad. The seven emergency response assets and capabilities include: Accident Response Group; Aerial Measuring Systems; Atmospheric Release Advisory Capability; Federal Radiological Monitoring and Assessment Center; Nuclear Emergency Search Team; Radiation Emergency Assistance Center/Training Site; and Radiological Assistance Program. Presently, USDOE maintains the most comprehensive national radiological emergency response assets in the United States, capable of dealing with any type of emergency involving nuclear materials. In all, the Department's assets are available to support any type of accident/incident involving radioactive materials in coordination with other United States Federal agencies, as well as state and local governments, as required. (author)

  3. 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

  4. Savannah River Site environmental report for 1993 summary pamphlet

    International Nuclear Information System (INIS)

    Karapatakis, L.

    1994-01-01

    This pamphlet summarizes the impact of 1993 Savannah River Site operations on the environment and the off-site public. It includes an overview of site operations; the basis for radiological and nonradiological monitoring; 1993 radiological releases and the resulting dose to the off-site population; and results of the 1993 nonradiological program. The Savannah River Site Environmental Report for 1993 describes the findings of the environmental monitoring program for 1993. The report contains detailed information about site operations,the environmental monitoring and surveillance programs, monitoring and surveillance results, environmental compliance activities, and special programs. The report is distributed to government officials, members of the US Congress, universities, government facilities, environmental and civic groups, the news media, and interested individuals

  5. Nevada Test Site Environmental Report 2004

    Energy Technology Data Exchange (ETDEWEB)

    BECHTEL NEVADA

    2005-10-01

    The ''Nevada Test Site Environmental Report 2004'' was prepared by Bechtel Nevada (BN) to meet the information needs of the public and the requirements and guidelines of the U.S. Department of Energy (DOE) for annual site environmental reports. This Executive Summary presents the purpose of the document, the major programs conducted at the Nevada Test Site (NTS), NTS key environmental initiatives, radiological releases and potential doses to the public resulting from site operations, a summary of non-radiological releases, implementation status of the NTS Environmental Management System, and significant environmental accomplishments. Much of the content of this Executive Summary is also presented in a separate stand-alone pamphlet titled ''Nevada Test Site Environmental Report Summary 2004''. It was produced this year to provide a more cost-effective and wider distribution of a hardcopy summary of the ''Nevada Test Site Environmental Report 2004'' to interested DOE stakeholders.

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

    International Nuclear Information System (INIS)

    Doyle, J.F. III.

    1986-01-01

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

  7. Radiological anatomy - evaluation of integrative education in radiology.

    Science.gov (United States)

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

    2013-09-01

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

  8. Analysis of the Radiology Reports from Radiology Clinics

    International Nuclear Information System (INIS)

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

    2009-01-01

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

  9. Radiology and the Internet: A systematic review of patient information resources

    Energy Technology Data Exchange (ETDEWEB)

    Smart, James M; Burling, David

    2001-11-01

    AIM: To determine whether the internet is a useful resource for patients seeking information on radiological procedures. MATERIALS AND METHODS: A systematic search of the world wide web was performed by means of four general search engines (AltaVista, Yahoo{exclamation_point}, Infoseek and Excite). Twenty-eight suitable patient-directed websites on arteriography were identified for analysis. The value of this material was measured by establishing inclusion or exclusion of a number of factors relating to the procedure. Readability of the materials was evaluated using the Flesch reading ease score. RESULTS: Advice on preparation was included in 21 (75%) sites. Contraindications were found in 16 (57%) sites, risks in 6 (21%) and aftercare in 25 (89%). Result availability was discussed in 15 (54%) sites, with links to other radiology sites in 13 (46%). Visual aids were used in 6 (21%) sites and a contact address found in 27 (96%). Mean Flesch reading ease score was 57, with 46% of sites below the preferred minimum of 60. CONCLUSIONS: Few sites provide the range of information a patient needs before arriving for a procedure. In addition, the readability of the material on these sites is frequently set at a level incomprehensible to patients with lower levels of literacy. Smart, J.M. and Burling, D. (2001)

  10. Radiology and the Internet: A systematic review of patient information resources

    International Nuclear Information System (INIS)

    Smart, James M.; Burling, David

    2001-01-01

    AIM: To determine whether the internet is a useful resource for patients seeking information on radiological procedures. MATERIALS AND METHODS: A systematic search of the world wide web was performed by means of four general search engines (AltaVista, Yahoo!, Infoseek and Excite). Twenty-eight suitable patient-directed websites on arteriography were identified for analysis. The value of this material was measured by establishing inclusion or exclusion of a number of factors relating to the procedure. Readability of the materials was evaluated using the Flesch reading ease score. RESULTS: Advice on preparation was included in 21 (75%) sites. Contraindications were found in 16 (57%) sites, risks in 6 (21%) and aftercare in 25 (89%). Result availability was discussed in 15 (54%) sites, with links to other radiology sites in 13 (46%). Visual aids were used in 6 (21%) sites and a contact address found in 27 (96%). Mean Flesch reading ease score was 57, with 46% of sites below the preferred minimum of 60. CONCLUSIONS: Few sites provide the range of information a patient needs before arriving for a procedure. In addition, the readability of the material on these sites is frequently set at a level incomprehensible to patients with lower levels of literacy. Smart, J.M. and Burling, D. (2001)

  11. NNSA/NV Consequence Management Capabilities for Radiological Emergency Response

    International Nuclear Information System (INIS)

    Bowman, D. R.

    2002-01-01

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

  12. Radiological criteria for underground nuclear tests

    International Nuclear Information System (INIS)

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

    1981-04-01

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

  13. Radiological criteria for underground nuclear tests

    Energy Technology Data Exchange (ETDEWEB)

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

    1981-04-01

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

  14. Waste generation and pollution prevention progress fact sheet: Nevada Test Site

    International Nuclear Information System (INIS)

    1994-01-01

    The Nevada Test Site is responsible for maintaining nuclear testing capability, supporting science-based Stockpile Stewardship experiments, maintaining nuclear agency response capability, applying environmental restoration techniques to areas affected by nuclear testing, managing low-level and mixed radioactive waste, investigating demilitarization technologies, investigating counter- proliferation technologies, supporting work-for-others programs and special Department of Defense activities, operating a hazardous materials spill test center, and providing for the commercial development of the site. This fact sheet provides information on routine waste generation and projected reduction by waste type. Also, materials recycled by the Nevada Test Site in 1994 are listed

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

    Science.gov (United States)

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

    2017-10-01

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

  16. 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

  17. e-Learning applications for radiological protection training

    International Nuclear Information System (INIS)

    Gonzalez, F.; Gomez-Arguello, B.; Callejo, J. L.

    2003-01-01

    The unattended training, through e-learning platforms, offers advantages in comparison with the traditional attended training, such as, freedom to study when, where and how the trance desires, the student is learning customization, a continuous self evaluation of the learning process and the rhythm of study, etc. To explore the possibilities of the radiological protection training in a WEB site, a first application for External Workers has been developed. The high number of students, their geographical dispersion and their different level of knowledge and experience arise attended training limitations in this area. In this article, the WEB course Basic Radiological Protection is presented and the results, preliminarily conclusions and lesson learnt are analysed. (Author) 7 refs

  18. 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

  19. Evaluation of radiological teaching programs in the Internet

    International Nuclear Information System (INIS)

    Seitz, J.; Schubert, S.; Voelk, M.; Scheibl, K.; Paetzel, C.; Schreyer, A.; Djavidani, B.; Feuerbach, S.; Strotzer, M.

    2003-01-01

    Evaluation of web based training programs,which can be contacted from the homepages of radiological departments of German universities.Material and method From june 2000 to january 2002 the 75 web based training programs of 57 providers,which can be contacted from the web pages of the radiological departments of german universities were evaluated in a prospective study.A medical student experienced in using the world wide web examined each training program three times in an interval of six months using the following criteria: availability of the web sites,target group,kind of training program,contents and structure and the technical solution. 51 of the 57 the homepages were fully available at each visit. 64 of the 75 web based training programs which could be connected from these sites were available at all three visitis.One program was only partially available at one spot check. 8 of the 75 programs were designed for physicians and medically trained personal, 23 were made for medical students and 44 addressed both target groups (partially more than once mentioned).The number of the presented cases ranged between one single and 3700. In 31 of 75 training programs links to other teaching files were found.A complete presentation of cases was presented by 48 of the 75 web sites.5 of the 75 web sites offered physiological images for comparison. In 20 training programs the pathological changes were optically marked in the x-ray images.A logical and didactical structure was found in 24 teaching files, 14 gave the possibility to check the learning results.No provider made use of the possibility to pass credits to the students or physicians acount with regard to official training programs. Multimedia techniques were used in 15 training programs.43 sites used data reduced preview images (thumbnails).The latest update of the site is mentioned in 55 of the 75 web sites. 19 of 57 providers had either no possibility of contact or did not answer to an e-mail. From the homepages

  20. Analysis of long-term impacts of TRU waste remaining at generator/storage sites for No Action Alternative 2

    International Nuclear Information System (INIS)

    Buck, J.W.; Bagaasen, L.M.; Bergeron, M.P.; Streile, G.P.

    1997-09-01

    This report is a supplement to the Waste Isolation Pilot Plant Disposal-Phase Final Supplemental Environmental Impact Statement (SEIS-II). Described herein are the underlying information, data, and assumptions used to estimate the long-term human-health impacts from exposure to radionuclides and hazardous chemicals in transuranic (TRU) waste remaining at major generator/storage sites after loss of institutional control under No Action Alternative 2. Under No Action Alternative 2, TRU wastes would not be emplaced at the Waste Isolation Pilot Plant (WIPP) but would remain at generator/storage sites in surface or near-surface storage. Waste generated at smaller sites would be consolidated at the major generator/storage sites. Current TRU waste management practices would continue, but newly generated waste would be treated to meet the WIPP waste acceptance criteria. For this alternative, institutional control was assumed to be lost 100 years after the end of the waste generation period, with exposure to radionuclides and hazardous chemicals in the TRU waste possible from direct intrusion and release to the surrounding environment. The potential human-health impacts from exposure to radionuclides and hazardous chemicals in TRU waste were analyzed for two different types of scenarios. Both analyses estimated site-specific, human-health impacts at seven major generator/storage sites: the Hanford Site (Hanford), Idaho National Engineering and Environmental Laboratory (INEEL), Lawrence Livermore National Laboratory (LLNL), Los Alamos National Laboratory (LANL), Oak Ridge National Laboratory (ORNL), Rocky Flats Environmental Technology Site (RFETS), and Savannah River Site (SRS). The analysis focused on these seven sites because 99 % of the estimated TRU waste volume and inventory would remain there under the assumptions of No Action Alternative 2

  1. Generation, on-site storage; handling and processing of industrial waste of Tehran

    International Nuclear Information System (INIS)

    Abduli, M.A.

    1997-01-01

    This paper describes out the present status of generation, on-site handling, processing and storage of industrial waste in Tehran. In this investigation, 67 large scale factories of different industrial groups were randomly selected. Above cited functional elements of these factories were surveyed. In this investigation a close contact with each factory was required, thus a questionnaire was prepared and distributed among these factories. The relationship between daily weight of the industrial waste (Y) and number of employer of each factory (x) is found to be Y=547.4 + 0.58 x. The relationship between daily volume of industrial waste (V), and daily weight of waste generated in each factory (Y) can be described by V=1.56 + 0.00078 Y. About 68% of the factories have their own interim storage site and the rest of the factories do not possess any on-site storage facility

  2. 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

  3. Radiological emergency response - a functional approach

    International Nuclear Information System (INIS)

    Chowdhury, Prosanta

    1997-01-01

    The radiological emergency response program in the State of Louisiana is discussed. The improved approach intends to maximize the efficiency for both nuclear power plant and radiological emergency response as a whole. Several broad-based components are identified: cluster of 'nodes' are generated for each component; these 'nodes' may be divided into 'sub-nodes' which will contain some 'attributes'; 'relational bonds' among the 'attributes' will exist. When executed, the process begins and continues with the 'nodes' assuming a functional and dynamic role based on the nature and characteristics of the 'attributes'. The typical response based on stand-alone elements is eliminated; overlapping of functions is avoided, and is produced a well-structure and efficient organization

  4. Radiological aerial monitoring in a nuclear emergency

    International Nuclear Information System (INIS)

    Shin, Hyeongki; Kim, Juyoul; Jung, Gunhyo

    2008-01-01

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

  5. 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.)

  6. 2000 RSNA annual oration in diagnostic radiology: The future of interventional radiology.

    Science.gov (United States)

    Becker, G J

    2001-08-01

    Origins in imaging, procedural emphasis, and dependence on innovation characterize interventional radiology, which will continue as the field of image-guided minimally invasive therapies. A steady supply of innovators will be needed. Current workforce shortages demand that this problem be addressed and in an ongoing fashion. Interventional radiology's major identity problem will require multiple corrective measures, including a name change. Diagnostic radiologists must fully embrace the concept of the dedicated interventionalist. Interspecialty turf battles will continue, especially with cardiologists and vascular surgeons. To advance the discipline, interventional radiologists must remain involved in cutting-edge therapies such as endograft repair of aortic aneurysms and carotid stent placement. As the population ages, interventionalists will experience a shift toward a greater emphasis on cancer treatment. Political agendas and public pressure will improve access to care and result in managed health care reforms. Academic centers will continue to witness a decline in time and resources available to pursue academic missions. The public outcry for accountability will result in systems changes aimed at reducing errors and process changes in the way physicians are trained, certified, and monitored. Evidence-based medicine will be the watchword of this century. Interventional radiology will maintain its role through development of methods for delivery of genes, gene products, and drugs to specific target sites; control of angiogenesis and other biologic processes; and noninvasive image-guided delivery of various forms of energy for ablation.

  7. Radiologic evaluation of colorectal cancer

    International Nuclear Information System (INIS)

    Lee, Young Joong; Kang, Hee Tae; Kim, Jong Deok; Rhee, Hak Song

    1984-01-01

    The incidence of colorectal cancer of Korea is much lower than that of Western countries, but has shown a tendency to a slight increase recently. Barium enema is the most valuable, noninvasive and inexpensive method available to evaluate the size, shape and site of colorectal cancer. The authors reviewed and radiologically classified barium enema studies of 232 cases of colorectal cancer from Aug. 1967 to July 1982 at Presbyterian Medical Center, Jeonju, Confirmed clinically, operatively and pathologically. The results were as follows; 1. The ratio of male and female was 1.3:1, and youngest was 13 year-old and the oldest 86 year-old. 2. The peak incidence occurred from 5th to 7th decades, accounting for 78% of all cases (181/232), and there was a relatively high incidence of the disease in patients below 30 years of age at 7.8% (18/232). 3. Rectum and rectosigmoid region are the most frequently involved regions (127/232:54.8%). 4. The positivity of barium enema examination was 4.0% (232/5807), and its accuracy was 96.5% (224/232). 5. The radiologic findings were classified into 4 groups, and they were annular encircling 62.9% (146/232). polypoid fungating 26.8% (62/232), infiltrating 8.6% (20/232), and primary ulcerating 1.7% (4/232) in order of frequency. 6. The linear length of the cancer ranged from 1.5 Cm to 15 Cm, and the average length was 5.5 Cm. 7. There was no statistical correlation between the length of lesion, the site, and the radiologic findings, and stages of the lesion (P:0.750-0.250). 8. The majority of colorectal cancers was adenocarcinoma (217/232:93.6%)

  8. A virtual environment for simulation of radiological accidents

    International Nuclear Information System (INIS)

    Silva, Tadeu Augusto de Almeida; Farias, Oscar Luiz Monteiro de

    2013-01-01

    A virtual environment is a computer environment, representative of a subset of the real world, and where models of the real world entities, process and events are included in a virtual (three-dimensional) space. Virtual environments are ideal tools for simulation of certain critical processes, such as radiological accidents, where human beings or properties can suffer irreversible or long term damages. Radiological accidents are characterized by the significant exposure to radiation of specialized workers and general public. The early detection of a radiological accident and the determination of its possible extension are essential factors for the planning of prompt answers and emergency actions. This paper proposes the integration of georeferenced representation of the three-dimensional space and agent-based models, with the objective to construct virtual environments that have the capacity to simulate radiological accidents. The three-dimensional georeferenced representations of space candidates are: 1) the spatial representation of traditional geographical information systems (GIS); 2) the representation adopted by Google Maps®. Adding agents to these spatial representations allow us to simulate radiological accidents, quantify the doses received by members of the public, obtain a possible spatial distribution of people contaminated, estimate the number of contaminated individuals, estimate the impact on the health-network, estimate environmental impacts, generate exclusion zones, build alternative scenarios and train staff to deal with radiological accidents. (author)

  9. A virtual environment for simulation of radiological accidents

    Energy Technology Data Exchange (ETDEWEB)

    Silva, Tadeu Augusto de Almeida, E-mail: tedsilva@ird.gov.br [Instituto de Radioprotecao e Dosimetria (IRD/CNEN-RJ), Rio de Janeiro, RJ (Brazil); Farias, Oscar Luiz Monteiro de, E-mail: fariasol@eng.uerj.br [Universidade do Estado do Rio de Janeiro (UERJ), Rio de Janeiro, RJ (Brazil)

    2013-07-01

    A virtual environment is a computer environment, representative of a subset of the real world, and where models of the real world entities, process and events are included in a virtual (three-dimensional) space. Virtual environments are ideal tools for simulation of certain critical processes, such as radiological accidents, where human beings or properties can suffer irreversible or long term damages. Radiological accidents are characterized by the significant exposure to radiation of specialized workers and general public. The early detection of a radiological accident and the determination of its possible extension are essential factors for the planning of prompt answers and emergency actions. This paper proposes the integration of georeferenced representation of the three-dimensional space and agent-based models, with the objective to construct virtual environments that have the capacity to simulate radiological accidents. The three-dimensional georeferenced representations of space candidates are: 1) the spatial representation of traditional geographical information systems (GIS); 2) the representation adopted by Google Maps®. Adding agents to these spatial representations allow us to simulate radiological accidents, quantify the doses received by members of the public, obtain a possible spatial distribution of people contaminated, estimate the number of contaminated individuals, estimate the impact on the health-network, estimate environmental impacts, generate exclusion zones, build alternative scenarios and train staff to deal with radiological accidents. (author)

  10. Nevada Test Site Environmental Report 2003

    Energy Technology Data Exchange (ETDEWEB)

    Bechtel Nevada

    2004-10-01

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

  11. 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

  12. Cost-benefit analysis for U.S. NRC proposed radiological criteria for decommissioning

    International Nuclear Information System (INIS)

    Meck, R.A.

    1995-01-01

    The U.S. Nuclear Regulatory Commission prepared cost-benefit analyses in support of the proposed regulation on radiological criteria for decommissioning. These analyses have been published in the Draft Generic Environmental Impact Statement (GEIS), NUREG-1496, and in the Draft Regulatory Analysis (RA). The method used was to first list the reasonable regulatory alternatives that could be considered. Second, for each regulatory alternative, we analyzed and compared the costs and the incremental radiological and non-radiological impacts to workers and members of the public. The regulatory alternatives for unrestricted use of a site that were analyzed and compared were: no regulatory change; a uniform risk based on total effective dose equivalent (TEDE); use of 'best' available technology; and returning the level of radioactivity attributable to licensed activity to background levels. The analyses were performed for ten types of reference facilities, and each facility was evaluated at low, medium, and high levels of contamination. The reference facilities included: reactors; various uranium and non-fuel cycle facilities; and independent spent fuel storage installations. Since both the radiological and non-radiological benefits were considered, the benefits of the various alternatives were measured in terms of 'Estimated Mortalities Averted.' Conclusions supported by the analyses were that a risk limit, expressed as a 15 mrem/y dose, is reasonable both as a level for protecting public health and safety and with regard to its cost-benefit effects. Further reductions on a site-specific application of the ALARA principle are also supported in the context of accounting for both the radiological and non-radiological effects in both the short and long terms. Restricted release is also supported when the same level of protection is provided in decommissioning those facilities that cannot reasonably meet the unrestricted release criteria. (J.P.N.)

  13. The teaching of Radiological Protection in actual society

    International Nuclear Information System (INIS)

    Lorenzo, Nestor Pedro de

    1996-01-01

    The use more and more frequent of radiations in different areas of the daily life generate a growing necessity of competent professionals and technicians qualified in Health Physics. The teaching of the Radiological Protection does not limit only to the instruction in scientists topics that quality to the professionals in the resolution of problems or the application of techniques, must qualified also the students in the diffusion of the own problems of the radiological protection. The content of different courses of radiological protection given in the Instituto Bailer's ( a join between the National University of Cuyo and the National Commission of Atomic Energy) guided to different groups of students or professionals are also introduced. Finally, some of the examples used in order to clarify practical situations are shown. (author)

  14. Elimination of a ligand gating site generates a supersensitive olfactory receptor.

    Science.gov (United States)

    Sharma, Kanika; Ahuja, Gaurav; Hussain, Ashiq; Balfanz, Sabine; Baumann, Arnd; Korsching, Sigrun I

    2016-06-21

    Olfaction poses one of the most complex ligand-receptor matching problems in biology due to the unparalleled multitude of odor molecules facing a large number of cognate olfactory receptors. We have recently deorphanized an olfactory receptor, TAAR13c, as a specific receptor for the death-associated odor cadaverine. Here we have modeled the cadaverine/TAAR13c interaction, exchanged predicted binding residues by site-directed mutagenesis, and measured the activity of the mutant receptors. Unexpectedly we observed a binding site for cadaverine at the external surface of the receptor, in addition to an internal binding site, whose mutation resulted in complete loss of activity. In stark contrast, elimination of the external binding site generated supersensitive receptors. Modeling suggests this site to act as a gate, limiting access of the ligand to the internal binding site and thereby downregulating the affinity of the native receptor. This constitutes a novel mechanism to fine-tune physiological sensitivity to socially relevant odors.

  15. WIPP site and vicinity geological field trip

    International Nuclear Information System (INIS)

    Chaturvedi, L.

    1980-10-01

    The Environmental Evaluation Group (EEG) is conducting an assessment of the radiological health risks to people from the Waste Isolation Pilot Plant (WIPP). As a part of this work, EEG is making an effort to improve the understanding of those geological issues concerning the WIPP site which may affect the radiological consequences of the proposed repository. One of the important geological issues to be resolved is the timing and the nature of the dissolution processes which may have affected the WIPP site. EEG organized a two-day conference of geological scientists, titled Geotechnical Considerations for Radiological Hazard Assessment of WIPP on January 17-18, 1980. During this conference, it was realized that a field trip to the site would further clarify the different views on the geological processes active at the site. The field trip of June 16-18, 1980 was organized for this purpose. This report provides a summary of the field trip activities along with the participants post field trip comments. Important field stops are briefly described, followed by a more detailed discussion of critical geological issues. The report concludes with EEG's summary and recommendations to the US Department of Energy for further information needed to more adequately resolve concerns for the geologic and hydrologic integrity of the site

  16. 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)

  17. 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

  18. Draft environmental impact statement. High-level waste repository site suitability criteria

    International Nuclear Information System (INIS)

    1978-01-01

    The purpose of HLWRSSC is to present guidelines which will help in the development of safe waste management schemes. Current regulations require solidification of all high-level waste within 5 years of their generation and transfer to a Federal waste repository within 10 years. Development of the proposed HLWRSSC is part of the overall NRC program to close the ''back end'' of the commercial LWR fuel cycle. In this document, the need for the HLWRSSC is reviewed, and the national energy policy, the need for electrical energy, and the nuclear fuel cycle are discussed. Considerations for HLWRSSC are presented, including the nature of the repository, important site-related factors, and radiological risk assessment methodology. Radiological and nonradiological environment impacts associated with the HLWRSSC are defined. Alternatives to the criteria are presented, and the cost-benefit-risk evaluation is reviewed

  19. Health literacy in vascular and interventional radiology: a comparative analysis of online patient education resources.

    Science.gov (United States)

    Hansberry, David R; Kraus, Carl; Agarwal, Nitin; Baker, Stephen R; Gonzales, Sharon F

    2014-08-01

    The Internet is frequently accessed by patients as a resource for medical knowledge. However, the provided material is typically written at a level well above the recommended 7th grade level. A clear understanding of the capabilities, limitations, risks, and benefits of interventional radiology by patients, both current and prospective, is hindered when the textual information offered to the public is pitched at a level of sophistication too high for general comprehension. In January 2013, all 25 patient education resources from the Cardiovascular and Interventional Radiology Society of Europe (CIRSE) Web site ( http://www.cirse.org ) and all 31 resources from the Society of Interventional Radiology (SIR) Web site ( http://www.sirweb.org ) were analyzed for their specific level of readability using ten quantitative scales: Flesch Reading Ease, Flesch-Kincaid Grade Level, Simple Measure of Gobbledygook, Gunning fog index, New Fog Count, Coleman-Liau index, FORCAST formula, Fry graph, Raygor Readability Estimate, and New Dale-Chall. Collectively, the patient education resources on the CIRSE Web site are written at the 12.3 grade level, while the resources on the SIR Web site are written at the 14.5 grade level. Educational health care materials available on both the CIRSE and the SIR Web sites are presented in language in the aggregate that could be too difficult for many lay people to fully understand. Given the complex nature of vascular and interventional radiology, it may be advantageous to rewrite these educational resources at a lower reading level to increase comprehension.

  20. A summary of radiological waste disposal practices in the United States and the United Kingdom - 16379

    International Nuclear Information System (INIS)

    Maranville, Victoria M.; McGrath, Richard

    2009-01-01

    A systematic review of near-surface repositories for radioactive waste in the United States (US) was conducted. The main focus of the review consisted of a literature search of available documents and other published sources on low level radioactive waste (LLRW) disposal practices, remediation of LLRW sites in the US, and public participation for remediation efforts of near-surface radiological waste disposal sites in the US. This review was undertaken to provide background information in support of work by the United Kingdom's (UK) Low Level Waste Repository (LLWR) and to aid in optimizing the future management of this site. The review contained a summary of the US and UK radiological waste classification requirements including a discussion of the waste types, disposal requirements, and the differences between US and UK disposal practices. A regulatory overview and evolution of regulatory requirements in the US is presented. The UK regulatory environment is also discussed and contrasted to the US process. The public participation, as part of the US regulatory process, is provided and the mechanism for stakeholder identification and involvement is detailed. To demonstrate how remediation of radiologically impacted sites is implemented in the US, existing US case studies, in which remediation activities were carried out, were reviewed. The following information was compiled: type of wastes disposed of to US shallow ground facilities [with comparison with UK classifications], facility designs (with special emphasis on those directly comparable to the subsurface conditions in the UK), and deficiencies identified in operation or in demonstrating safe post closure; and processes and difficulties in remedial actions encountered at the selected sites. Stakeholder involvement is discussed within the case studies. Publicly available information related to radiological waste management and disposal practices were reviewed. Two sites are presented in this publication for