WorldWideScience

Sample records for snf project radiation

  1. Technical Basis - Spent Nuclear Fuels (SNF) Project Radiation and Contamination Trending Program

    International Nuclear Information System (INIS)

    ELGIN, J.C.

    2000-01-01

    This report documents the technical basis for the Spent Nuclear Fuel (SNF) Program radiation and contamination trending program. The program consists of standardized radiation and contamination surveys of the KE Basin, radiation surveys of the KW basin, radiation surveys of the Cold Vacuum Drying Facility (CVD), and radiation surveys of the Canister Storage Building (CSB) with the associated tracking. This report also discusses the remainder of radiological areas within the SNFP that do not have standardized trending programs and the basis for not having this program in those areas

  2. SNF Project Engineering Process Improvement Plan

    International Nuclear Information System (INIS)

    DESAI, S.P.

    2000-01-01

    This plan documents the SNF Project activities and plans to support its engineering process. It describes five SNF Project Engineering initiatives: new engineering procedures, qualification cards process; configuration management, engineering self assessments, and integrated schedule for engineering activities

  3. Spent Nuclear Fuel (SNF) Project Execution Plan

    International Nuclear Information System (INIS)

    LEROY, P.G.

    2000-01-01

    The Spent Nuclear Fuel (SNF) Project supports the Hanford Site Mission to cleanup the Site by providing safe, economic, environmentally sound management of Site spent nuclear fuel in a manner that reduces hazards by staging it to interim onsite storage and deactivates the 100 K Area facilities

  4. Spent Nuclear Fuel (SNF) Project Execution Plan

    Energy Technology Data Exchange (ETDEWEB)

    LEROY, P.G.

    2000-11-03

    The Spent Nuclear Fuel (SNF) Project supports the Hanford Site Mission to cleanup the Site by providing safe, economic, environmentally sound management of Site spent nuclear fuel in a manner that reduces hazards by staging it to interim onsite storage and deactivates the 100 K Area facilities.

  5. SNF project engineering process improvement plan

    International Nuclear Information System (INIS)

    DESAI, S.P.

    1999-01-01

    This Engineering Process Improvement Plan documents the activities and plans to be taken by the SNF Project to support its engineering process and to produce a consolidated set of engineering procedures that are fully compliant with the requirements of HNF-PRO-1819. All new procedures will be issued and implemented by September 30, 1999

  6. Canister storage building compliance assessment SNF project NRC equivalency criteria - HNF-SD-SNF-DB-003

    International Nuclear Information System (INIS)

    BLACK, D.M.

    1999-01-01

    This document presents the Project's position on compliance with the SNF Project NRC Equivalency Criteria - HNF-SD-SNF-DE-003, Spent Nuclear Fuel Project Path Forward Additional NRC Requirements. No non-compliances are shown. The compliance statements have been reviewed and approved by DOE. Open items are scheduled to be closed prior to project completion

  7. SNF project engineering process improvement plan

    International Nuclear Information System (INIS)

    KELMENSON, R.L.

    1999-01-01

    This Engineering Process Improvement Plan documents the activities and plans to be taken by the SNF Project (the Project) to support its engineering process and to produce a consolidated set of engineering procedures that are fully compliant with the requirements of HNF-PRO-1819 (1819). These requirements are imposed on all engineering activities performed for the Project and apply to all life-cycle stages of the Project's systems, structures and components (SSCs). This Plan describes the steps that will be taken by the Project during the transition period to ensure that new procedures are effectively integrated into the Project's work process as these procedures are issued. The consolidated procedures will be issued and implemented by September 30, 1999

  8. Spent Nuclear Fuel (SNF) Project Product Specification

    International Nuclear Information System (INIS)

    PAJUNEN, A.L.

    2000-01-01

    The process for removal of Spent Nuclear Fuel (SNF) from the K Basins has been divided into major sub-systems. The Fuel Retrieval System (FRS) removes fuel from the existing storage canisters, cleans it, and places it into baskets. The multi-canister overpack (MCO) loading system places the baskets into an MCO that has been pre-loaded in a cask. The cask, containing a loaded MCO, is then transferred to the Cold Vacuum Drying (CVD) Facility. After drying at the CVD Facility, the cask, and MCO, are transferred to the Canister Storage Building (CSB), where the MCO is removed from the cask, staged, inspected, sealed (by welding), and stored until a suitable permanent disposal option is implemented. The purpose of this document is to specify the process related characteristics of an MCO at the interface between major process systems. The characteristics are derived from the primary technical documents that form the basis for safety analysis and design calculations. This document translates the calculation assumptions into implementation requirements and describes the method of verifying that the requirement is achieved. These requirements are used to define validation test requirements and describe requirements that influence multiple sub-project safety analysis reports. This product specification establishes limits and controls for each significant process parameter at interfaces between major sub-systems that potentially affect the overall safety and/or quality of the SNF packaged for processing, transport, and interim dry storage. The product specifications in this document cover the SNF packaged in MCOs to be transported throughout the SNF Project. The description of the product specifications are organized in the document as follows: Section 2.0--Summary listing of product specifications at each major sub-system interface. Section 3.0--Summary description providing guidance as to how specifications are complied with by equipment design or processing within a major

  9. Spent Nuclear Fuel (SNF) Project Product Specification

    Energy Technology Data Exchange (ETDEWEB)

    PAJUNEN, A.L.

    2000-12-07

    The process for removal of Spent Nuclear Fuel (SNF) from the K Basins has been divided into major sub-systems. The Fuel Retrieval System (FRS) removes fuel from the existing storage canisters, cleans it, and places it into baskets. The multi-canister overpack (MCO) loading system places the baskets into an MCO that has been pre-loaded in a cask. The cask, containing a loaded MCO, is then transferred to the Cold Vacuum Drying (CVD) Facility. After drying at the CVD Facility, the cask, and MCO, are transferred to the Canister Storage Building (CSB), where the MCO is removed from the cask, staged, inspected, sealed (by welding), and stored until a suitable permanent disposal option is implemented. The purpose of this document is to specify the process related characteristics of an MCO at the interface between major process systems. The characteristics are derived from the primary technical documents that form the basis for safety analysis and design calculations. This document translates the calculation assumptions into implementation requirements and describes the method of verifying that the requirement is achieved. These requirements are used to define validation test requirements and describe requirements that influence multiple sub-project safety analysis reports. This product specification establishes limits and controls for each significant process parameter at interfaces between major sub-systems that potentially affect the overall safety and/or quality of the SNF packaged for processing, transport, and interim dry storage. The product specifications in this document cover the SNF packaged in MCOs to be transported throughout the SNF Project. The description of the product specifications are organized in the document as follows: Section 2.0--Summary listing of product specifications at each major sub-system interface. Section 3.0--Summary description providing guidance as to how specifications are complied with by equipment design or processing within a major

  10. Regulatory practices of radiation safety of SNF transportation in Russia

    International Nuclear Information System (INIS)

    Kuryndina, Lidia; Kuryndin, Anton; Stroganov, Anatoly

    2008-01-01

    This paper overviews current regulatory practices for the assurance of nuclear and radiation safety during railway transportation of SNF on the territory of Russian Federation from NPPs to longterm-storage of reprocessing sites. The legal and regulatory requirements (mostly compliant with IAEA ST-1), licensing procedure for NM transportation are discussed. The current procedure does not require a regulatory approval for each particular shipment if the SNF fully comply with the Rosatom's branch standard and is transported in approved casks. It has been demonstrated that SNF packages compliant with the branch standard, which is knowingly provide sufficient safety margin, will conform to the federal level regulations. The regulatory approval is required if a particular shipment does not comply with the branch standard. In this case, the shipment can be approved only after regulatory review of Applicant's documents to demonstrate that the shipment still conformant to the higher level (federal) regulations. The regulatory review frequently needs a full calculation test of the radiation safety assurance. This test can take a lot of time. That's why the special calculation tools were created in SEC NRS. These tools aimed for precision calculation of the radiation safety parameters by SNF transportation use preliminary calculated Green's functions. Such approach allows quickly simulate any source distribution and optimize spent fuel assemblies placement in cask due to the transport equation property of linearity relatively the source. The short description of calculation tools are presented. Also, the paper discusses foreseen implications related to transportation of mixed-oxide SNF. (author)

  11. SNF fuel retrieval sub project safety analysis document

    International Nuclear Information System (INIS)

    BERGMANN, D.W.

    1999-01-01

    This safety analysis is for the SNF Fuel Retrieval (FRS) Sub Project. The FRS equipment will be added to K West and K East Basins to facilitate retrieval, cleaning and repackaging the spent nuclear fuel into Multi-Canister Overpack baskets. The document includes a hazard evaluation, identifies bounding accidents, documents analyses of the accidents and establishes safety class or safety significant equipment to mitigate accidents as needed

  12. SNF fuel retrieval sub project safety analysis document

    Energy Technology Data Exchange (ETDEWEB)

    BERGMANN, D.W.

    1999-02-24

    This safety analysis is for the SNF Fuel Retrieval (FRS) Sub Project. The FRS equipment will be added to K West and K East Basins to facilitate retrieval, cleaning and repackaging the spent nuclear fuel into Multi-Canister Overpack baskets. The document includes a hazard evaluation, identifies bounding accidents, documents analyses of the accidents and establishes safety class or safety significant equipment to mitigate accidents as needed.

  13. Spent Nuclear Fuel (SNF) Project Design Verification and Validation Process

    International Nuclear Information System (INIS)

    OLGUIN, L.J.

    2000-01-01

    This document provides a description of design verification and validation activities implemented by the Spent Nuclear Fuel (SNF) Project. During the execution of early design verification, a management assessment (Bergman, 1999) and external assessments on configuration management (Augustenburg, 1999) and testing (Loscoe, 2000) were conducted and identified potential uncertainties in the verification process. This led the SNF Chief Engineer to implement corrective actions to improve process and design products. This included Design Verification Reports (DVRs) for each subproject, validation assessments for testing, and verification of the safety function of systems and components identified in the Safety Equipment List to ensure that the design outputs were compliant with the SNF Technical Requirements. Although some activities are still in progress, the results of the DVR and associated validation assessments indicate that Project requirements for design verification are being effectively implemented. These results have been documented in subproject-specific technical documents (Table 2). Identified punch-list items are being dispositioned by the Project. As these remaining items are closed, the technical reports (Table 2) will be revised and reissued to document the results of this work

  14. SNF project's MCO compliance assessment with DOE ''general design criteria,'' order 6430.1A and ''SNF project MCO additional NRC requirements,'' HNF-SD-SNF-DB-005

    International Nuclear Information System (INIS)

    GOLDMANN, L.H.

    1999-01-01

    This document is presented to demonstrate the MCOs compliance to the major design criteria invoked on the MCO. This document is broken down into a section for the MCO's evaluation against DOE Order 6430.1A General Design Criteria sixteen divisions and then the evaluation of the MCO against HNF-SD-SNF-DB-005 ''Spent Nuclear Fuel Project Multi-Canister Overpack Additional NRC Requirements.'' The compliance assessment is presented as a matrix in tabular form. The MCO is the primary container for the K-basin's spent nuclear fuel as it leaves the basin pools and through to the 40 year interim storage at the Canister Storage Building (CSB). The MCO and its components interface with; the K basins, shipping cask and transportation system, Cold Vacuum Drying facility individual process bays and equipment, and CSB facility including the MCO handling machine (MHM), the storage tubes, and the MCO work stations where sampling, welding, and inspection of the MCO is performed. As the MCO is the primary boundary for handling, process, and storage, its main goals are to minimize the spread of its radiological contents to the outside of the MCO and provide for nuclear criticality control. The MCO contains personnel radiation shielding only on its upper end, in the form of a shield plug, where the process interfaces are located. Shielding beyond the shield plug is the responsibility of the using facilities. The design of the MCO and its components is depicted in drawings H-2-828040 through H-2-828075. Not every drawing number in the sequence is used. The first drawing number, H-2-828040, is the drawing index for the MCO. The design performance specification for the MCO is HW-S-0426, and was reviewed and approved by the interfacing design authorities, the safety, regulatory, and operations groups, and the local DOE office. The current revision for the design performance specification is revision 5. The designs of the MCO have been reviewed and approved in a similar way and the reports

  15. SNF sludge treatment system preliminary project execution plan

    International Nuclear Information System (INIS)

    Flament, T.A.

    1998-01-01

    The Fluor Daniel Hanford, Inc. (FDH) Project Director for the Spent Nuclear Fuel (SNF) Project has requested Numatec Hanford Company (NHC) to define how Hanford would manage a new subproject to provide a process system to receive and chemically treat radioactive sludge currently stored in the 100 K Area fuel retention basins. The subproject, named the Sludge Treatment System (STS) Subproject, provides and operates facilities and equipment to chemically process K Basin sludge to meet Tank Waste Remediation System (TWRS) requirements. This document sets forth the NHC management approach for the STS Subproject and will comply with the requirements of the SNF Project Management Plan (HNF-SD-SNFPMP-011). This version of this document is intended to apply to the initial phase of the subproject and to evolve through subsequent revision to include all design, fabrication, and construction conducted on the project and the necessary management and engineering functions within the scope of the subproject. As Project Manager, NHC will perform those activities necessary to complete the STS Subproject within approved cost and schedule baselines and turn over to FDH facilities, systems, and documentation necessary for operation of the STS

  16. Spent Nuclear Fuel (SNF) Project Safety Basis Implementation Strategy

    International Nuclear Information System (INIS)

    TRAWINSKI, B.J.

    2000-01-01

    The objective of the Safety Basis Implementation is to ensure that implementation of activities is accomplished in order to support readiness to move spent fuel from K West Basin. Activities may be performed directly by the Safety Basis Implementation Team or they may be performed by other organizations and tracked by the Team. This strategy will focus on five key elements, (1) Administration of Safety Basis Implementation (general items), (2) Implementing documents, (3) Implementing equipment (including verification of operability), (4) Training, (5) SNF Project Technical Requirements (STRS) database system

  17. Uranium Oxide Rate Summary for the Spent Nuclear Fuel (SNF) Project (OCRWM)

    Energy Technology Data Exchange (ETDEWEB)

    PAJUNEN, A.L.

    2000-09-20

    The purpose of this document is to summarize the uranium oxidation reaction rate information developed by the Hanford Spent Nuclear Fuel (SNF) Project and describe the basis for selecting reaction rate correlations used in system design. The selection basis considers the conditions of practical interest to the fuel removal processes and the reaction rate application during design studies. Since the reaction rate correlations are potentially used over a range of conditions, depending of the type of evaluation being performed, a method for transitioning between oxidation reactions is also documented. The document scope is limited to uranium oxidation reactions of primary interest to the SNF Project processes. The reactions influencing fuel removal processes, and supporting accident analyses, are: uranium-water vapor, uranium-liquid water, uranium-moist air, and uranium-dry air. The correlation selection basis will consider input from all available sources that indicate the oxidation rate of uranium fuel, including the literature data, confirmatory experimental studies, and fuel element observations. Trimble (2000) summarizes literature data and the results of laboratory scale experimental studies. This document combines the information in Trimble (2000) with larger scale reaction observations to describe uranium oxidation rate correlations applicable to conditions of interest to the SNF Project.

  18. Uranium Oxide Rate Summary for the Spent Nuclear Fuel (SNF) Project (OCRWM)

    International Nuclear Information System (INIS)

    PAJUNEN, A.L.

    2000-01-01

    The purpose of this document is to summarize the uranium oxidation reaction rate information developed by the Hanford Spent Nuclear Fuel (SNF) Project and describe the basis for selecting reaction rate correlations used in system design. The selection basis considers the conditions of practical interest to the fuel removal processes and the reaction rate application during design studies. Since the reaction rate correlations are potentially used over a range of conditions, depending of the type of evaluation being performed, a method for transitioning between oxidation reactions is also documented. The document scope is limited to uranium oxidation reactions of primary interest to the SNF Project processes. The reactions influencing fuel removal processes, and supporting accident analyses, are: uranium-water vapor, uranium-liquid water, uranium-moist air, and uranium-dry air. The correlation selection basis will consider input from all available sources that indicate the oxidation rate of uranium fuel, including the literature data, confirmatory experimental studies, and fuel element observations. Trimble (2000) summarizes literature data and the results of laboratory scale experimental studies. This document combines the information in Trimble (2000) with larger scale reaction observations to describe uranium oxidation rate correlations applicable to conditions of interest to the SNF Project

  19. Quality assurance program plan for SNF characterization support project

    International Nuclear Information System (INIS)

    Tanke, J.M.

    1997-01-01

    This Quality Assurance Program Plan (QAPP) provides information on how the Quality Assurance Program is implemented for the Spent Nuclear Fuel Characterization Support Project. This QAPP has been developed specifically for the Spent Nuclear Fuel Characterization Support Project, per Letter of Instruction (LOI) from Duke Engineering and Services Company, letter No. DESH-9655870, dated Nov. 22, 1996. It applies to those items and tasks which affect the completion of activities identified in the work breakdown structure of the Project Management Plan (PMP) and LOI. These activities include installation of sectioning equipment and furnace, surface and subsurface examinations, sectioning for metallography, and element drying and conditioning testing, as well as project related operations within the 327 facility as it relates to the specific activities of this project. General facility activities are covered in other appropriate QA-PPS. In addition, this QAPP supports the related quality assurance activities addressed in CM-2-14, Hazardous Material Packaging and Shipping,1261 and HSRCM-1, Hanford Site Radiological Control Manual. The 327 Building is currently transitioning from being a Pacific Northwest National Laboratory (PNNL) managed facility to a Babcock and Wilcox Hanford Company (BVMC) managed facility. During this transition process existing procedures and documents will be utilized until replaced by BVMC procedures and documents. These documents conform to the requirements found in PNL-MA-70, Quality Assurance Manual and PNL-MA-8 1, Hazardous Materials Shipping Manual. The Quality Assurance Program Index (QAPI) contained in Table 1 provides a matrix which shows how project activities relate to IO CFR 830.120 and 5700.6C criteria. Quality Assurance program requirements will be addressed separate from the requirements specified in this document. Other Hanford Site organizations/companies may be utilized in support of this project and the subject organizations are

  20. Spent Nuclear Fuel (SNF) Project Cold Vacuum Drying (CVD) Facility Operations Manual

    Energy Technology Data Exchange (ETDEWEB)

    IRWIN, J.J.

    2000-02-03

    This document provides the Operations Manual for the Cold Vacuum Drying Facility (CVDF). The Manual was developed in conjunction with HNF-SD-SNF-SAR-002, Safety Analysis Report for the Cold Vacuum Drying Facility, Phase 2, Supporting Installation of the Processing Systems (Garvin 1998) and, the HNF-SD-SNF-DRD-002, 1997, Cold Vacuum Drying Facility Design Requirements, Rev. 3a. The Operations Manual contains general descriptions of all the process, safety and facility systems in the CVDF, a general CVD operations sequence, and has been developed for the spent nuclear fuel project (SNFP) Operations Organization and shall be updated, expanded, and revised in accordance with future design, construction and startup phases of the CVDF until the CVDF final ORR is approved.

  1. Spent Nuclear Fuel (SNF) Project Cold Vacuum Drying (CVD) Facility Operations Manual

    International Nuclear Information System (INIS)

    IRWIN, J.J.

    2000-01-01

    This document provides the Operations Manual for the Cold Vacuum Drying Facility (CVDF). The Manual was developed in conjunction with HNF-SD-SNF-SAR-002, Safety Analysis Report for the Cold Vacuum Drying Facility, Phase 2, Supporting Installation of the Processing Systems (Garvin 1998) and, the HNF-SD-SNF-DRD-002, 1997, Cold Vacuum Drying Facility Design Requirements, Rev. 3a. The Operations Manual contains general descriptions of all the process, safety and facility systems in the CVDF, a general CVD operations sequence, and has been developed for the spent nuclear fuel project (SNFP) Operations Organization and shall be updated, expanded, and revised in accordance with future design, construction and startup phases of the CVDF until the CVDF final ORR is approved

  2. Spent Nuclear Fuel (SNF) Project Design Basis Capacity Study

    International Nuclear Information System (INIS)

    CLEVELAND, K.J.

    2000-01-01

    This study of the design basis capacity of process systems was prepared by Fluor Federal Services for the Spent Nuclear Fuel Project. The evaluation uses a summary level model of major process sub-systems to determine the impact of sub-system interactions on the overall time to complete fuel removal operations. The process system model configuration and time cycle estimates developed in the original version of this report have been updated as operating scenario assumptions evolve. The initial document released in Fiscal Year (FY) 1996 varied the number of parallel systems and transport systems over a wide range, estimating a conservative design basis for completing fuel processing in a two year time period. Configurations modeling planned operations were updated in FY 1998 and FY 1999. The FY 1998 Base Case continued to indicate that fuel removal activities at the basins could be completed in slightly over 2 years. Evaluations completed in FY 1999 were based on schedule modifications that delayed the start of KE Basin fuel removal, with respect to the start of KW Basin fuel removal activities, by 12 months. This delay resulted in extending the time to complete all fuel removal activities by 12 months. However, the results indicated that the number of Cold Vacuum Drying (CVD) stations could be reduced from four to three without impacting the projected time to complete fuel removal activities. This update of the design basis capacity evaluation, performed for FY 2000, evaluates a fuel removal scenario that delays the start of KE Basin activities such that staffing peaks are minimized. The number of CVD stations included in all cases for the FY 2000 evaluation is reduced from three to two, since the scenario schedule results in minimal time periods of simultaneous fuel removal from both basins. The FY 2000 evaluation also considers removal of Shippingport fuel from T Plant storage and transfer to the Canister Storage Building for storage

  3. Spent Nuclear Fuel (SNF) Project Cold Vacuum Drying (CVD) Facility Operations Manual

    International Nuclear Information System (INIS)

    IRWIN, J.J.

    2000-01-01

    The mission of the Spent Nuclear Fuel (SNF) Project Cold Vacuum Drying Facility (CVDF) is to achieve the earliest possible removal of free water from Multi-Canister Overpacks (MCOs). The MCOs contain metallic uranium SNF that have been removed from the 100K Area fuel storage water basins (i.e., the K East and K West Basins) at the US. Department of Energy Hanford Site in Southeastern Washington state. Removal of free water is necessary to halt water-induced corrosion of exposed uranium surfaces and to allow the MCOs and their SNF payloads to be safely transported to the Hanford Site 200 East Area and stored within the SNF Project Canister Storage Building (CSB). The CVDF is located within a few hundred yards of the basins, southwest of the 165KW Power Control Building and the 105KW Reactor Building. The site area required for the facility and vehicle circulation is approximately 2 acres. Access and egress is provided by the main entrance to the 100K inner area using existing roadways. The CVDF will remove free. water from the MCOs to reduce the potential for continued fuel-water corrosion reactions. The cold vacuum drying process involves the draining of bulk water from the MCO and subsequent vacuum drying. The MCO will be evacuated to a pressure of 8 torr or less and backfilled with an inert gas (helium). The MCO will be sealed, leak tested, and then transported to the CSB within a sealed shipping cask. (The MCO remains within the same shipping Cask from the time it enters the basin to receive its SNF payload until it is removed from the Cask by the CSB MCO handling machine.) The CVDF subproject acquired the required process systems, supporting equipment, and facilities. The cold vacuum drying operations result in an MCO containing dried fuel that is prepared for shipment to the CSB by the Cask transportation system. The CVDF subproject also provides equipment to dispose of solid wastes generated by the cold vacuum drying process and transfer process water removed

  4. DESIGN VERIFICATION REPORT SPENT NUCLEAR FUEL (SNF) PROJECT CANISTER STORAGE BUILDING (CSB)

    Energy Technology Data Exchange (ETDEWEB)

    BAZINET, G.D.

    2003-02-12

    The Sub-project W379, ''Spent Nuclear Fuel Canister Storage Building (CSB),'' was established as part of the Spent Nuclear Fuel (SNF) Project. The primary mission of the CSB is to safely store spent nuclear fuel removed from the K Basins in dry storage until such time that it can be transferred to the national geological repository at Yucca Mountain Nevada. This sub-project was initiated in late 1994 by a series of studies and conceptual designs. These studies determined that the partially constructed storage building, originally built as part of the Hanford Waste Vitrification Plant (HWVP) Project, could be redesigned to safely store the spent nuclear fuel. The scope of the CSB facility initially included a receiving station, a hot conditioning system, a storage vault, and a Multi-Canister Overpack (MCO) Handling Machine (MHM). Because of evolution of the project technical strategy, the hot conditioning system was deleted from the scope and MCO welding and sampling stations were added in its place. This report outlines the methods, procedures, and outputs developed by Project W379 to verify that the provided Structures, Systems, and Components (SSCs): satisfy the design requirements and acceptance criteria; perform their intended function; ensure that failure modes and hazards have been addressed in the design; and ensure that the SSCs as installed will not adversely impact other SSCs. The original version of this document was prepared by Vista Engineering for the SNF Project. Revision 1 documented verification actions that were pending at the time the initial report was prepared. Revision 3 of this document incorporates MCO Cover Cap Assembly welding verification activities. Verification activities for the installed and operational SSCs have been completed.

  5. Design Verification Report Spent Nuclear Fuel (SNF) Project Canister Storage Building (CSB)

    Energy Technology Data Exchange (ETDEWEB)

    BAZINET, G.D.

    2001-05-15

    The Sub-project W379, ''Spent Nuclear Fuel Canister Storage Building (CSB),'' was established as part of the Spent Nuclear Fuel (SNF) Project. The primary mission of the CSB is to safely store spent nuclear fuel removed from the K Basins in dry storage until such time that it can be transferred to the national geological repository at Yucca Mountain Nevada. This sub-project was initiated in late 1994 by a series of studies and conceptual designs. These studies determined that the partially constructed storage building, originally built as part of the Hanford Waste Vitrification Plant (HWVP) Project, could be redesigned to safely store the spent nuclear fuel. The scope of the CSB facility initially included a receiving station, a hot conditioning system, a storage vault, and a Multi-Canister Overpack (MCO) Handling Machine (MHM). Because of evolution of the project technical strategy, the hot conditioning system was deleted from the scope and MCO welding and sampling stations were added in its place. This report outlines the methods, procedures, and outputs developed by Project W379 to verify that the provided Structures, Systems, and Components (SSCs): satisfy the design requirements and acceptance criteria; perform their intended function; ensure that failure modes and hazards have been addressed in the design; and ensure that the SSCs as installed will not adversely impact other SSCs. The original version of this document was prepared by Vista Engineering for the SNF Project. Revision 1 documented verification actions that were pending at the time the initial report was prepared. Verification activities for the installed and operational SSCs have been completed. Verification of future additions to the CSB related to the canister cover cap and welding fixture system and MCO Internal Gas Sampling equipment will be completed as appropriate for those components. The open items related to verification of those requirements are noted in section 3

  6. DESIGN VERIFICATION REPORT SPENT NUCLEAR FUEL (SNF) PROJECT CANISTER STORAGE BUILDING (CSB)

    International Nuclear Information System (INIS)

    BAZINET, G.D.

    2003-01-01

    The Sub-project W379, ''Spent Nuclear Fuel Canister Storage Building (CSB),'' was established as part of the Spent Nuclear Fuel (SNF) Project. The primary mission of the CSB is to safely store spent nuclear fuel removed from the K Basins in dry storage until such time that it can be transferred to the national geological repository at Yucca Mountain Nevada. This sub-project was initiated in late 1994 by a series of studies and conceptual designs. These studies determined that the partially constructed storage building, originally built as part of the Hanford Waste Vitrification Plant (HWVP) Project, could be redesigned to safely store the spent nuclear fuel. The scope of the CSB facility initially included a receiving station, a hot conditioning system, a storage vault, and a Multi-Canister Overpack (MCO) Handling Machine (MHM). Because of evolution of the project technical strategy, the hot conditioning system was deleted from the scope and MCO welding and sampling stations were added in its place. This report outlines the methods, procedures, and outputs developed by Project W379 to verify that the provided Structures, Systems, and Components (SSCs): satisfy the design requirements and acceptance criteria; perform their intended function; ensure that failure modes and hazards have been addressed in the design; and ensure that the SSCs as installed will not adversely impact other SSCs. The original version of this document was prepared by Vista Engineering for the SNF Project. Revision 1 documented verification actions that were pending at the time the initial report was prepared. Revision 3 of this document incorporates MCO Cover Cap Assembly welding verification activities. Verification activities for the installed and operational SSCs have been completed

  7. Design Verification Report Spent Nuclear Fuel (SNF) Project Canister Storage Building (CSB)

    International Nuclear Information System (INIS)

    BAZINET, G.D.

    2001-01-01

    The Sub-project W379, ''Spent Nuclear Fuel Canister Storage Building (CSB),'' was established as part of the Spent Nuclear Fuel (SNF) Project. The primary mission of the CSB is to safely store spent nuclear fuel removed from the K Basins in dry storage until such time that it can be transferred to the national geological repository at Yucca Mountain Nevada. This sub-project was initiated in late 1994 by a series of studies and conceptual designs. These studies determined that the partially constructed storage building, originally built as part of the Hanford Waste Vitrification Plant (HWVP) Project, could be redesigned to safely store the spent nuclear fuel. The scope of the CSB facility initially included a receiving station, a hot conditioning system, a storage vault, and a Multi-Canister Overpack (MCO) Handling Machine (MHM). Because of evolution of the project technical strategy, the hot conditioning system was deleted from the scope and MCO welding and sampling stations were added in its place. This report outlines the methods, procedures, and outputs developed by Project W379 to verify that the provided Structures, Systems, and Components (SSCs): satisfy the design requirements and acceptance criteria; perform their intended function; ensure that failure modes and hazards have been addressed in the design; and ensure that the SSCs as installed will not adversely impact other SSCs. The original version of this document was prepared by Vista Engineering for the SNF Project. Revision 1 documented verification actions that were pending at the time the initial report was prepared. Verification activities for the installed and operational SSCs have been completed. Verification of future additions to the CSB related to the canister cover cap and welding fixture system and MCO Internal Gas Sampling equipment will be completed as appropriate for those components. The open items related to verification of those requirements are noted in section 3.1.5 and will be

  8. Design Verification Report Spent Nuclear Fuel (SNF) Project Canister Storage Building (CSB)

    Energy Technology Data Exchange (ETDEWEB)

    BAZINET, G.D.

    2000-11-03

    The Sub-project W379, ''Spent Nuclear Fuel Canister Storage Building (CSB),'' was established as part of the Spent Nuclear Fuel (SNF) Project. The primary mission of the CSB is to safely store spent nuclear fuel removed from the K Basins in dry storage until such time that it can be transferred to the national geological repository at Yucca Mountain Nevada. This sub-project was initiated in late 1994 by a series of studies and conceptual designs. These studies determined that the partially constructed storage building, originally built as part of the Hanford Waste Vitrification Plant (HWVP) Project, could be redesigned to safely store the spent nuclear fuel. The scope of the CSB facility initially included a receiving station, a hot conditioning system, a storage vault, and a Multi-Canister Overpack (MCO) Handling Machine (MHM). Because of evolution of the project technical strategy, the hot conditioning system was deleted from the scope and MCO welding and sampling stations were added in its place. This report outlines the methods, procedures, and outputs developed by Project W379 to verify that the provided Structures, Systems, and Components (SSCs): satisfy the design requirements and acceptance criteria; perform their intended function; ensure that failure modes and hazards have been addressed in the design; and ensure that the SSCs as installed will not adversely impact other SSCs. The original version of this document was prepared by Vista Engineering for the SNF Project. The purpose of this revision is to document completion of verification actions that were pending at the time the initial report was prepared. Verification activities for the installed and operational SSCs have been completed. Verification of future additions to the CSB related to the canister cover cap and welding fixture system and MCO Internal Gas Sampling equipment will be completed as appropriate for those components. The open items related to verification of those

  9. Design Verification Report Spent Nuclear Fuel (SNF) Project Canister Storage Building (CSB)

    International Nuclear Information System (INIS)

    BAZINET, G.D.

    2000-01-01

    The Sub-project W379, ''Spent Nuclear Fuel Canister Storage Building (CSB),'' was established as part of the Spent Nuclear Fuel (SNF) Project. The primary mission of the CSB is to safely store spent nuclear fuel removed from the K Basins in dry storage until such time that it can be transferred to the national geological repository at Yucca Mountain Nevada. This sub-project was initiated in late 1994 by a series of studies and conceptual designs. These studies determined that the partially constructed storage building, originally built as part of the Hanford Waste Vitrification Plant (HWVP) Project, could be redesigned to safely store the spent nuclear fuel. The scope of the CSB facility initially included a receiving station, a hot conditioning system, a storage vault, and a Multi-Canister Overpack (MCO) Handling Machine (MHM). Because of evolution of the project technical strategy, the hot conditioning system was deleted from the scope and MCO welding and sampling stations were added in its place. This report outlines the methods, procedures, and outputs developed by Project W379 to verify that the provided Structures, Systems, and Components (SSCs): satisfy the design requirements and acceptance criteria; perform their intended function; ensure that failure modes and hazards have been addressed in the design; and ensure that the SSCs as installed will not adversely impact other SSCs. The original version of this document was prepared by Vista Engineering for the SNF Project. The purpose of this revision is to document completion of verification actions that were pending at the time the initial report was prepared. Verification activities for the installed and operational SSCs have been completed. Verification of future additions to the CSB related to the canister cover cap and welding fixture system and MCO Internal Gas Sampling equipment will be completed as appropriate for those components. The open items related to verification of those requirements are noted

  10. Design analysis of various transportation package options for BN-350 SNF in terms of nuclear radiation safety in planning for long-terms dry storage

    International Nuclear Information System (INIS)

    Aisabekov, A.Z.; Mukenova, S.A.; Tur, E.S.; Tsyngaev, V.M.

    2004-01-01

    Full text: This effort is performed under the BN-350 reactor facility decommissioning project. One of the project tasks - spent nuclear fuel handling - includes the following: fuel packaging into sealed canisters, transportation of the canisters in multi-seat metallo-concrete containers and placement of the containers for a long-term dry storage. The goal of this effort is to computationally validate nuclear and radiation safety of the SNF containers placed for storage both under normal storage conditions and probable accident situations. The basic unit structure and design configurations are presented: assemblies, canisters, transportation containers. The major factors influencing nuclear and radiation safety are presented: fuel burn-up, enrichment, fabrication tolerance, types of fuel assemblies, configuration of assemblies in the canister and canisters in the container, background of assemblies placed in the reactor and cooling pool. Conditions under which the SNF containers will be stored are described and probable accident situations are listed. Proceeding from the conservatism principle, selection of the assemblies posing the greatest nuclear hazard is validated. A neutron effective multiplication factor is calculated for the SNF containers under the normal storage conditions and for the case of emergency. The effective multiplication factor is shown to be within a standard value of 0.95 in any situation. Based on the experimental data on assembly and canister dose rates, canisters posing the highest radiation threat are selected. Activities of sources and gamma-radiation spectral composition are calculated. Distribution of the dose rate outside the containers both under the normal storage conditions and accident situations are calculated. The results obtained are analyzed

  11. K Basins Spent Nuclear Fuel (SNF) Project Safety Analysis Report for Packaging (SARP) approval plan

    International Nuclear Information System (INIS)

    1995-01-01

    This document delineates the plan for preparation, review, and approval of the K Basins Spent Nuclear Fuel (SNF) Packaging Design Criteria (PDC) document and the on-site Safety Analysis Report for Packaging (SARP). The packaging addressed in these documents is used to transport SNF in a Multi- canister Overpack (MCO) configuration

  12. Design Verification Report Spent Nuclear Fuel (SNF) Project Canister Storage Building (CSB)

    Energy Technology Data Exchange (ETDEWEB)

    PICKETT, W.W.

    2000-09-22

    The Sub-project W379, ''Spent Nuclear Fuel Canister Storage Building (CSB),'' was established as part of the Spent Nuclear Fuel (SNF) Project. The primary mission of the CSB is to safely store spent nuclear fuel removed from the K Basins in dry storage until such time that it can be transferred to the national geological repository at Yucca Mountain Nevada. This sub-project was initiated in late 1994 by a series of studies and conceptual designs. These studies determined that the partially constructed storage building, originally built as part of the Hanford Waste Vitrification Plant (HWVP) Project, could be redesigned to safely store the spent nuclear fuel. The scope of the CSB facility initially included a receiving station, a hot conditioning system, a storage vault, and a Multi-Canister Overpack (MCO) Handling Machine (MHM). Because of evolution of the project technical strategy, the hot conditioning system was deleted from the scope and MCO welding and sampling stations were added in its place. This report outlines the methods, procedures, and outputs developed by Project W379 to verify that the provided Structures, Systems, and Components (SSCs): satisfy the design requirements and acceptance criteria; perform their intended function; ensure that failure modes and hazards have been addressed in the design; and ensure that the SSCs as installed will not adversely impact other SSCs. Because this sub-project is still in the construction/start-up phase, all verification activities have not yet been performed (e.g., canister cover cap and welding fixture system verification, MCO Internal Gas Sampling equipment verification, and As-built verification.). The verification activities identified in this report that still are to be performed will be added to the start-up punchlist and tracked to closure.

  13. Design Verification Report Spent Nuclear Fuel (SNF) Project Canister Storage Building (CSB)

    International Nuclear Information System (INIS)

    PICKETT, W.W.

    2000-01-01

    The Sub-project W379, ''Spent Nuclear Fuel Canister Storage Building (CSB),'' was established as part of the Spent Nuclear Fuel (SNF) Project. The primary mission of the CSB is to safely store spent nuclear fuel removed from the K Basins in dry storage until such time that it can be transferred to the national geological repository at Yucca Mountain Nevada. This sub-project was initiated in late 1994 by a series of studies and conceptual designs. These studies determined that the partially constructed storage building, originally built as part of the Hanford Waste Vitrification Plant (HWVP) Project, could be redesigned to safely store the spent nuclear fuel. The scope of the CSB facility initially included a receiving station, a hot conditioning system, a storage vault, and a Multi-Canister Overpack (MCO) Handling Machine (MHM). Because of evolution of the project technical strategy, the hot conditioning system was deleted from the scope and MCO welding and sampling stations were added in its place. This report outlines the methods, procedures, and outputs developed by Project W379 to verify that the provided Structures, Systems, and Components (SSCs): satisfy the design requirements and acceptance criteria; perform their intended function; ensure that failure modes and hazards have been addressed in the design; and ensure that the SSCs as installed will not adversely impact other SSCs. Because this sub-project is still in the construction/start-up phase, all verification activities have not yet been performed (e.g., canister cover cap and welding fixture system verification, MCO Internal Gas Sampling equipment verification, and As-built verification.). The verification activities identified in this report that still are to be performed will be added to the start-up punchlist and tracked to closure

  14. Spent Nuclear Fuel (SNF) Project Cask and MCO Helium Purge System Design Review Completion Report - Project A.5 and A.6

    International Nuclear Information System (INIS)

    ARD, K.E.

    2000-01-01

    This report documents the results of the design verification performed on the Cask and Multiple Canister Over-pack (MCO) Helium Purge System. The helium purge system is part of the Spent Nuclear Fuel (SNF) Project Cask Loadout System (CLS) at 100K area. The design verification employed the ''Independent Review Method'' in accordance with Administrative Procedure (AP) EN-6-027-01

  15. Preoperational Environmental Survey for the Spent Nuclear Fuel (SNF) Project Facilities

    International Nuclear Information System (INIS)

    MITCHELL, R.M.

    2000-01-01

    This document represents the report for environmental sampling of soil, vegetation, litter, cryptograms, and small mammals at the Spent Nuclear Fuel Project facilities located in 100 K and 200 East Areas in support of the preoperational environmental survey

  16. Preoperational Environmental Survey for the Spent Nuclear Fuel (SNF) Project Facilities

    Energy Technology Data Exchange (ETDEWEB)

    MITCHELL, R.M.

    2000-10-12

    This document represents the report for environmental sampling of soil, vegetation, litter, cryptograms, and small mammals at the Spent Nuclear Fuel Project facilities located in 100 K and 200 East Areas in support of the preoperational environmental survey.

  17. Preoperational Environmental Survey for the Spent Nuclear Fuel (SNF) Project Facilities

    Energy Technology Data Exchange (ETDEWEB)

    MITCHELL, R.M.

    2000-09-28

    This document represents the report for environmental sampling of soil, vegetation, litter, cryptograms, and small mammals at the Spent Nuclear Fuel Project facilities located in 100 K and 200 East Areas in support of the preoperational environmental survey.

  18. The metal and concrete cask for SNF and its radiation protection quality control

    International Nuclear Information System (INIS)

    Shchigolev, N.D.; Golubev, O.M.

    2005-01-01

    The transportation and packing module on the basis of metal and concrete cask for the long-term storage and shipment of the spent nuclear fuel is developed in compliance with the requirements of the national standards and IAEA recommendations. Such wares designed for the NPP and submarine reactors fuel may be remade also for the research ones. A procedure and remote device for the radiation protection control of this cask equally its integrity checks after dynamic testing also is described. (author)

  19. Spent Nuclear Fuel project stage and store K basin SNF in canister storage building functions and requirements. Revision 1

    International Nuclear Information System (INIS)

    Womack, J.C.

    1995-01-01

    This document establishes the functions and requirements baseline for the implementation of the Canister Storage Building Subproject. The mission allocated to the Canister Storage Building Subproject is to provide safe, environmentally sound staging and storage of K Basin SNF until a decision on the final disposition is reached and implemented

  20. Preparation for the Recovery of Spent Nuclear Fuel (SNF) at Andreeva Bay, North West Russia - 13309

    International Nuclear Information System (INIS)

    Field, D.; McAtamney, N.

    2013-01-01

    Andreeva Bay is located near Murmansk in the Russian Federation close to the Norwegian border. The ex-naval site was used to de-fuel nuclear-powered submarines and icebreakers during the Cold War. Approximately 22,000 fuel assemblies remain in three Dry Storage Units (DSUs) which means that Andreeva Bay has one of the largest stockpiles of highly enriched spent nuclear fuel (SNF) in the world. The high contamination and deteriorating condition of the SNF canisters has made improvements to the management of the SNF a high priority for the international community for safety, security and environmental reasons. International Donors have, since 2002, provided support to projects at Andreeva concerned with improving the management of the SNF. This long-term programme of work has been coordinated between the International Donors and responsible bodies within the Russian Federation. Options for the safe and secure management of SNF at Andreeva Bay were considered in 2004 and developed by a number of Russian Institutes with international participation. This consisted of site investigations, surveys and studies to understand the technical challenges. A principal agreement was reached that the SNF would be removed from the site altogether and transported to Russia's reprocessing facility at Mayak in the Urals. The analytical studies provided the information necessary to develop the construction plan for the site. Following design and regulatory processes, stakeholders endorsed the technical solution in April 2007. This detailed the processes, facilities and equipment required to safely remove the SNF and identified other site services and support facilities required on the site. Implementation of this strategy is now well underway with the facilities in various states of construction. Physical works have been performed to address the most urgent tasks including weather protection over one of the DSUs, installation of shielding over the cells, provision of radiation

  1. Preparation for the Recovery of Spent Nuclear Fuel (SNF) at Andreeva Bay, North West Russia - 13309

    Energy Technology Data Exchange (ETDEWEB)

    Field, D.; McAtamney, N. [Nuvia Limited (United Kingdom)

    2013-07-01

    Andreeva Bay is located near Murmansk in the Russian Federation close to the Norwegian border. The ex-naval site was used to de-fuel nuclear-powered submarines and icebreakers during the Cold War. Approximately 22,000 fuel assemblies remain in three Dry Storage Units (DSUs) which means that Andreeva Bay has one of the largest stockpiles of highly enriched spent nuclear fuel (SNF) in the world. The high contamination and deteriorating condition of the SNF canisters has made improvements to the management of the SNF a high priority for the international community for safety, security and environmental reasons. International Donors have, since 2002, provided support to projects at Andreeva concerned with improving the management of the SNF. This long-term programme of work has been coordinated between the International Donors and responsible bodies within the Russian Federation. Options for the safe and secure management of SNF at Andreeva Bay were considered in 2004 and developed by a number of Russian Institutes with international participation. This consisted of site investigations, surveys and studies to understand the technical challenges. A principal agreement was reached that the SNF would be removed from the site altogether and transported to Russia's reprocessing facility at Mayak in the Urals. The analytical studies provided the information necessary to develop the construction plan for the site. Following design and regulatory processes, stakeholders endorsed the technical solution in April 2007. This detailed the processes, facilities and equipment required to safely remove the SNF and identified other site services and support facilities required on the site. Implementation of this strategy is now well underway with the facilities in various states of construction. Physical works have been performed to address the most urgent tasks including weather protection over one of the DSUs, installation of shielding over the cells, provision of radiation

  2. Technical Approach and Plan for Transitioning Spent Nuclear Fuel (SNF) Project Facilities to the Environmental Restoration Program

    International Nuclear Information System (INIS)

    SKELLY, W.A.

    1999-01-01

    This document describes the approach and process in which the 100-K Area Facilities are to be deactivated and transitioned over to the Environmental Restoration Program after spent nuclear fuel has been removed from the K Basins. It describes the Transition Project's scope and objectives, work breakdown structure, activity planning, estimated cost, and schedule. This report will be utilized as a planning document for project management and control and to communicate details of project content and integration

  3. SNF AGING SYSTEM DESCRIPTION DOCUMENT

    International Nuclear Information System (INIS)

    L.L. Swanson

    2005-01-01

    The purpose of this system description document (SDD) is to establish requirements that drive the design of the spent nuclear fuel (SNF) aging system and associated bases, which will allow the design effort to proceed. This SDD will be revised at strategic points as the design matures. This SDD identifies the requirements and describes the system design, as it currently exists, with emphasis on attributes of the design provided to meet the requirements. This SDD is an engineering tool for design control; accordingly, the primary audience and users are design engineers. This SDD is part of an iterative design process. It leads the design process with regard to the flow down of upper tier requirements onto the system. Knowledge of these requirements is essential in performing the design process. The SDD follows the design with regard to the description of the system. The description provided in the SDD reflects the current results of the design process. Throughout this SDD, the term aging cask applies to vertical site-specific casks and to horizontal aging modules. The term overpack is a vertical site-specific cask that contains a dual-purpose canister (DPC) or a disposable canister. Functional and operational requirements applicable to this system were obtained from ''Project Functional and Operational Requirements'' (F andOR) (Curry 2004 [DIRS 170557]). Other requirements that support the design process were taken from documents such as ''Project Design Criteria Document'' (PDC) (BSC 2004 [DES 171599]), ''Site Fire Hazards Analyses'' (BSC 2005 [DIRS 172174]), and ''Nuclear Safety Design Bases for License Application'' (BSC 2005 [DIRS 171512]). The documents address requirements in the ''Project Requirements Document'' (PRD) (Canori and Leitner 2003 [DIRS 166275]). This SDD includes several appendices. Appendix A is a Glossary; Appendix B is a list of key system charts, diagrams, drawings, lists and additional supporting information; and Appendix C is a list of

  4. Commercial SNF Accident Release Fractions

    Energy Technology Data Exchange (ETDEWEB)

    J. Schulz

    2004-11-05

    The purpose of this analysis is to specify and document the total and respirable fractions for radioactive materials that could be potentially released from an accident at the repository involving commercial spent nuclear fuel (SNF) in a dry environment. The total and respirable release fractions are used to support the preclosure licensing basis for the repository. The total release fraction is defined as the fraction of total commercial SNF assembly inventory, typically expressed as an activity inventory (e.g., curies), of a given radionuclide that is released to the environment from a waste form. Radionuclides are released from the inside of breached fuel rods (or pins) and from the detachment of radioactive material (crud) from the outside surfaces of fuel rods and other components of fuel assemblies. The total release fraction accounts for several mechanisms that tend to retain, retard, or diminish the amount of radionuclides that are available for transport to dose receptors or otherwise can be shown to reduce exposure of receptors to radiological releases. The total release fraction includes a fraction of airborne material that is respirable and could result in inhalation doses; this subset of the total release fraction is referred to as the respirable release fraction. Accidents may involve waste forms characterized as: (1) bare unconfined intact fuel assemblies, (2) confined intact fuel assemblies, or (3) canistered failed commercial SNF. Confined intact commercial SNF assemblies at the repository are contained in shipping casks, canisters, or waste packages. Four categories of failed commercial SNF are identified: (1) mechanically and cladding-penetration damaged commercial SNF, (2) consolidated/reconstituted assemblies, (3) fuel rods, pieces, and debris, and (4) nonfuel components. It is assumed that failed commercial SNF is placed into waste packages with a mesh screen at each end (CRWMS M&O 1999). In contrast to bare unconfined fuel assemblies, the

  5. Commercial SNF Accident Release Fractions

    International Nuclear Information System (INIS)

    Schulz, J.

    2004-01-01

    The purpose of this analysis is to specify and document the total and respirable fractions for radioactive materials that could be potentially released from an accident at the repository involving commercial spent nuclear fuel (SNF) in a dry environment. The total and respirable release fractions are used to support the preclosure licensing basis for the repository. The total release fraction is defined as the fraction of total commercial SNF assembly inventory, typically expressed as an activity inventory (e.g., curies), of a given radionuclide that is released to the environment from a waste form. Radionuclides are released from the inside of breached fuel rods (or pins) and from the detachment of radioactive material (crud) from the outside surfaces of fuel rods and other components of fuel assemblies. The total release fraction accounts for several mechanisms that tend to retain, retard, or diminish the amount of radionuclides that are available for transport to dose receptors or otherwise can be shown to reduce exposure of receptors to radiological releases. The total release fraction includes a fraction of airborne material that is respirable and could result in inhalation doses; this subset of the total release fraction is referred to as the respirable release fraction. Accidents may involve waste forms characterized as: (1) bare unconfined intact fuel assemblies, (2) confined intact fuel assemblies, or (3) canistered failed commercial SNF. Confined intact commercial SNF assemblies at the repository are contained in shipping casks, canisters, or waste packages. Four categories of failed commercial SNF are identified: (1) mechanically and cladding-penetration damaged commercial SNF, (2) consolidated/reconstituted assemblies, (3) fuel rods, pieces, and debris, and (4) nonfuel components. It is assumed that failed commercial SNF is placed into waste packages with a mesh screen at each end (CRWMS M andO 1999). In contrast to bare unconfined fuel assemblies, the

  6. Radiation safety for decommissioning projects

    International Nuclear Information System (INIS)

    Ross, A.C.

    1999-01-01

    Decommissioning of redundant nuclear facilities is a growth area in the UK at the present time. NUKEM Nuclear Limited is a leading-edge nuclear decommissioning and waste management contractor (with its own in-house health physics and safety department), working for a variety of clients throughout the UK nuclear industry. NUKEM Nuclear is part of the prestigious, international NUKEM group, a world-class organization specializing in nuclear engineering and utilities technologies. NUKEM Nuclear is involved in a number of large, complex decommissioning projects, both in its own right and as part of consortia. This paper explores the challenges presented by such projects and the interfaces of contractor, client and subcontractors from the point of view of a radiation protection adviser. (author)

  7. Current state of WWER SNF storage in Russia and the perspectives

    International Nuclear Information System (INIS)

    Anisimov, O.; Kozlov, Y.; Razmashkin, N.; Safutin, V.; Tikhonov, N.

    2006-01-01

    In the Russian Federation WWER-440 Spent Nuclear Fuel (SNF) is reprocessed at RT-1 plant near Cheliabinsk. WWER-1000 SNF is supposed to be reprocessed at RT-2 plant, which will be built about 2020. The information on the capacity and fill up level of the at-reactor pools at NPP with WWER reactors considering its modification up to May 2005 is given. The regulatory requirements to all SNF 'wet' storage facilities; the principle design and engineering solutions as well as the complex of measures for radiation safety and the environmental protection of spent fuel storage are presented. WWER-440 SNF management, WWER-1000 SNF management and dry storage of WWER-1000 SNF are discussed. In the conclusion it is noted than neither Russia, nor any other country have the experience of construction of vault-type 'dry' storage facilities of such a capacity to store WWER-1000 SNF (9000 tU). The experience and design solutions approved earlier in creation of other dangerous facilities were used. The calculations were based on conservative assumptions allowing with a large assurance to guarantee the nuclear and radiation safety and the environmental protection. At present, a program is developed for scientific-technical support of the dry storage facility design and operation, aimed at the studies whose results will allow to optimize the taken technical decisions, simplify SNF management technology and, possibly, to reduce the cost of the storage facility itself

  8. SNF AGING SYSTEM DESCRIPTION DOCUMENT

    Energy Technology Data Exchange (ETDEWEB)

    L.L. Swanson

    2005-04-06

    The purpose of this system description document (SDD) is to establish requirements that drive the design of the spent nuclear fuel (SNF) aging system and associated bases, which will allow the design effort to proceed. This SDD will be revised at strategic points as the design matures. This SDD identifies the requirements and describes the system design, as it currently exists, with emphasis on attributes of the design provided to meet the requirements. This SDD is an engineering tool for design control; accordingly, the primary audience and users are design engineers. This SDD is part of an iterative design process. It leads the design process with regard to the flow down of upper tier requirements onto the system. Knowledge of these requirements is essential in performing the design process. The SDD follows the design with regard to the description of the system. The description provided in the SDD reflects the current results of the design process. Throughout this SDD, the term aging cask applies to vertical site-specific casks and to horizontal aging modules. The term overpack is a vertical site-specific cask that contains a dual-purpose canister (DPC) or a disposable canister. Functional and operational requirements applicable to this system were obtained from ''Project Functional and Operational Requirements'' (F&OR) (Curry 2004 [DIRS 170557]). Other requirements that support the design process were taken from documents such as ''Project Design Criteria Document'' (PDC) (BSC 2004 [DES 171599]), ''Site Fire Hazards Analyses'' (BSC 2005 [DIRS 172174]), and ''Nuclear Safety Design Bases for License Application'' (BSC 2005 [DIRS 171512]). The documents address requirements in the ''Project Requirements Document'' (PRD) (Canori and Leitner 2003 [DIRS 166275]). This SDD includes several appendices. Appendix A is a Glossary; Appendix B is a list of key system charts

  9. Spent Nuclear Fuel (SNF) Bounding Drop Support Calculations

    International Nuclear Information System (INIS)

    CHENAULT, D.M.

    1999-01-01

    This report evaluates different drop heights, concrete and other impact media to which the transport package and/or the MCO is dropped. A prediction method is derived for estimating the resultant impact factor for determining the bounding drop case for the SNF Project

  10. Serbian SNF Repatriation Operation. Issues, Solving, Lesson

    Energy Technology Data Exchange (ETDEWEB)

    Smirnov, A. [Research and Development Company ' Sosny' , Moscow (Russian Federation)

    2011-07-01

    For now the removal of SNF from RA reactor site (PC NFS, Serbia) is the most time-consuming and technically complicated operation under RRRFR Program. The most efficient techniques and lessons learned from other projects of the RRRFR Program as well as new unique technical decisions were used. Two big challenges were resolved during implementation of Serbian Project: (1) preparation of damaged fuel located in the packages unsuitable for transport, taking into account insufficient infrastructure of RA reactor site and (2) removal of large amount of fuel in one multimodal shipment through several transit countries. The main attention was paid to safety justification of all activities. All approvals were obtained in Russia, Serbia and transit countries. Special canisters were designed for transportation of specific RA reactor fuel (of small dimensions, unidentifiable, damaged due to corrosion). The canister design was selected to be untight - it was the most expedient decision for that case from safety perspective. The technology and a set of equipment were designed for remote removal of the fuel from the existing package (aluminum barrels and reactor channels) and placing of the fuel into the new canisters. After fabrication and assembling of the equipment theoretical and practical training of the personnel was performed. Fuel repackaging took about 5 months. SNF was transported in TUK-19 and SKODA VPVR/M casks. The baskets of large capacity were designed and fabricated for SKODA VPVR/M casks. Special requirements to drying the packages and composition of gaseous medium inside were justified to ensure fire and explosion safety. Specialized ISO-containers and transfer equipment designed under Romanian Project were used together with TUK-19 casks. A forklift and mobile rail system were used to handle SKODA VPVR/M casks under conditions of low capacity of the cranes at the facility. Due to the tight schedule of RRRFR Program as well as geographical peculiarities of RA

  11. SNF shipping cask shielding analysis

    International Nuclear Information System (INIS)

    Johnson, J.O.; Pace, J.V. III.

    1996-01-01

    The Waste Management and Remedial Action Division has planned a modification sequence for storage facility 7827 in the Solid Waste Storage Area (SWSA). The modification cycle is: (1) modify an empty caisson, (2) transfer the spent nuclear fuel (SNF) of an occupied caisson to a hot cell in building 3525 for inspection and possible repackaging, and (3) return the package to the modified caisson in the SWSA. Although the SNF to be moved is in the solid form, it has different levels of activity. Thus, the following 5 shipping casks will be available for the task: the Loop Transport Carrier, the In- Pile Loop LITR HB-2 Carrier, the 6.5-inch HRLEL Carrier, the HFIR Hot Scrap Carrier, and the 10-inch ORR Experiment Removal Shield Cask. This report describes the shielding tasks for the 5 casks: determination of shielding characteristics, any streaming avenues, estimation of thermal limits, and shielding calculational uncertainty for use in the transportation plan

  12. Volumes, Masses, and Surface Areas for Shippingport LWBR Spent Nuclear Fuel in a DOE SNF Canister

    International Nuclear Information System (INIS)

    J.W. Davis

    1999-01-01

    The purpose of this calculation is to estimate volumes, masses, and surface areas associated with (a) an empty Department of Energy (DOE) 18-inch diameter, 15-ft long spent nuclear fuel (SNF) canister, (b) an empty DOE 24-inch diameter, 15-ft long SNF canister, (c) Shippingport Light Water Breeder Reactor (LWBR) SNF, and (d) the internal basket structure for the 18-in. canister that has been designed specifically to accommodate Seed fuel from the Shippingport LWBR. Estimates of volumes, masses, and surface areas are needed as input to structural, thermal, geochemical, nuclear criticality, and radiation shielding calculations to ensure the viability of the proposed disposal configuration

  13. Will the world SNF be reprocessed in Russia?

    International Nuclear Information System (INIS)

    Gagarinski, A.

    2000-01-01

    Russia's possibilities in nuclear fuel reprocessing are well known. RT-1 plant with 400 tons/year in the Chelyabinsk region can provide reprocessing of fuel from Russian and Central European WWER-440 reactors, as well as from transport and research reactors. Former military complex Krasnoyarsk-26 with unique underground installations situated in rock galleries, already has an aqueous facility for storage of 6000 tons of spent nuclear fuel (SNF), half-built plant RT-2 for nuclear fuel reprocessing with 1500 tons/year capacity, as well as the projects of dry storage facility for 30000 tons of SNF and of MOX fuel production plant. Russian nuclear specialists understand well, that the economic efficiency of nuclear fuel reprocessing industry is shown only in case of large-scale production, which would require consolidation of the countries, which develop nuclear energy. They also understand, that Russia has all the possibilities to become one of the centers of such a consolidation and to use these possibilities for the benefit of the country. The idea of foreign nuclear fuel reprocessing (for a long time realized for East and Central European countries, which operate Soviet-design reactors) has existed in the specialists' minds, and sometimes has appeared in the mass media. On the other hand, rehabilitation of territories of nuclear fuel cycle enterprises in Russia continues, including the Karachai lake, which contains 120 million Curie of radioactivity. Unfortunately, Russia simply has no money for complete solution of the problems of radiation military legacy. During discussion of the budget for 2000, the Russian Minatom has made a daring step. A real program, how to find money needed for solving the 'radiation legacy' problem, was proposed. With this purpose, it was proposed to permit storage and further reprocessing of other countries' SNF on Russian territory. It is well known, that another countries' SNF is accepted for reprocessing by UK and France, and Russia

  14. Project Radiation protection, Annual report 1994

    International Nuclear Information System (INIS)

    Ninkovic, M.M.

    1994-12-01

    According to the action plan for the period 1991-1995, the main objective of this project during 1994 was to provide operational basis, methods and procedures for solving the radiation protection problems that might appear under routine working conditions and handling of radiation sources. The aim was also to provide special methods for action in case of accidents that could affect the employed staff and the population. Overall activity was directed to maintaining and providing personnel, instrumentation, and methods for the following special radiation protection measures: operational control of the radiation field and contamination; calibration of the radiation and dosimetry instruments-secondary dosimetry metrology laboratory; instrumentation and measuring systems for radiation protection; control of environmental transfer of radioactive material; medical radiation protection [sr

  15. Radiation exposure modeling and project schedule visualization

    International Nuclear Information System (INIS)

    Jaquish, W.R.; Enderlin, V.R.

    1995-10-01

    This paper discusses two applications using IGRIP (Interactive Graphical Robot Instruction Program) to assist environmental remediation efforts at the Department of Energy (DOE) Hanford Site. In the first application, IGRIP is used to calculate the estimated radiation exposure to workers conducting tasks in radiation environments. In the second, IGRIP is used as a configuration management tool to detect interferences between equipment and personnel work areas for multiple projects occurring simultaneously in one area. Both of these applications have the capability to reduce environmental remediation costs by reducing personnel radiation exposure and by providing a method to effectively manage multiple projects in a single facility

  16. BWR radiation exposure--experience and projection

    International Nuclear Information System (INIS)

    Falk, C.F.; Wilkinson, C.D.; Hollander, W.R.

    1979-01-01

    The BWR/6 Mark III radiation exposures are projected to be about half of those of current average operating experience of 725 man-rem. These projections are said to be realistic and based on current achievements and not on promises of future development. The several BWRs operating with low primary system radiation levels are positive evidence that radiation sources can be reduced. Improvements have been made in reducing the maintenance times for the BWR/6, and further improvements can be made by further attention to cost-effective plant arrangement and layout during detail design to improve accessibility and maintainability of each system and component

  17. Radiation requirements for uranium project approvals

    International Nuclear Information System (INIS)

    Hondros, J.

    2014-01-01

    Uranium mining projects in Australia must receive approval under both state and national laws based on a wide ranging impact assessment of the project. The process may take a number of years and involves multiple levels and parts of government and public consultation and scrutiny. The impact assessment is broad and usually covers; environmental, social, health, public safety and economic aspects. Information provided in the approvals documentation needs to be presented in a credible and understandable manner for all audiences. This means making complex information simpler, while making sure that it maintains its technical integrity. Poorly communicated information, which is overly complex, overly simplified or incomplete, can result in significant delays to the project approval which can potentially impact on project timelines. For uranium projects, along with other projects involving radioactive materials, such as minerals sands and rare earths, radiation and its impacts usually draw a disproportionate amount of both government and public scrutiny compared to other potential impacts and risks. It is therefore of key importance that radiation assessments are properly performed and results clearly presented and communicated with sufficient detail for stakeholders to make informed decisions. It is also important to ensure that the radiation risk is presented in perspective with other risks of the project. This presentation outlines a structure for a radiation impact assessment based on experience from a number of projects in Australia. The structure aims to be clear and simple and ensure the right balance between scientific fact, digestible information and demonstrable competence. (author)

  18. Accelerators for the advanced radiation technology project

    International Nuclear Information System (INIS)

    Maruyama, Michio

    1990-01-01

    Ion beam irradiation facilities are now under construction for the advanced radiation technology (ART) project in Takasaki Radiation Chemistry Research Establishment of (Japan Atomic Energy Research Institute) JAERI. The project is intended to make an effective use of ion beams, especially ion beams, in the research field of radiation application technology. The TIARA (Takasaki Ion Accelerators for Advanced Radiation Application) facilities include four ion accelerators to produce almost all kinds of energetic ions in the periodic table. The facilities are also provided with several advanced irradiation means and act as very powerful accelerator complex for material development. Specifically, this report presents an outline of the ART project, features of TIARA as accelerator facilities dedicated to material development, the AVF cyclotron under construction (Sumitomo Heavy Industries, Ltd., Model 930), tandem accelerator, microbeam, and experimental instruments used. (N.K.)

  19. Security preparation for receipt of SNF from the FRR to the INEEL

    International Nuclear Information System (INIS)

    Dahlquist, Rhonda L.

    1997-01-01

    This paper reports the key security-related activities associated with the Foreign Research Reactors (FRR) shipment. Starting with Transportation of the SNF in the country of origin to the final destination at the INEEL. Methodology for compliance will be addressed. The graded approach and a three-step system will be explained. This paper will be used as part of the planning to support the FRR Project for returning the Asia and European SNF back to the United States. (author)

  20. Security preparation for receipt of SNF from the FRR to the INEEL

    International Nuclear Information System (INIS)

    Dahlquist, R.L.

    1997-01-01

    This paper reports the key security related activities associated with the FRR shipment. Starting with transportation of the SNF in the country of origin to the final destination at the INEEL. Methodology for compliance will be addressed. The graded approach and a three step system will be explained. This paper will be used as part of the planning to support the FRR Project for returning the Asia and European SNF back to the US

  1. Probability of Criticality for MOX SNF

    International Nuclear Information System (INIS)

    P. Gottlieb

    1999-01-01

    The purpose of this calculation is to provide a conservative (upper bound) estimate of the probability of criticality for mixed oxide (MOX) spent nuclear fuel (SNF) of the Westinghouse pressurized water reactor (PWR) design that has been proposed for use. with the Plutonium Disposition Program (Ref. 1, p. 2). This calculation uses a Monte Carlo technique similar to that used for ordinary commercial SNF (Ref. 2, Sections 2 and 5.2). Several scenarios, covering a range of parameters, are evaluated for criticality. Parameters specifying the loss of fission products and iron oxide from the waste package are particularly important. This calculation is associated with disposal of MOX SNF

  2. SWI/SNF complex in disorder

    Science.gov (United States)

    Santen, Gijs W.E.; Kriek, Marjolein; van Attikum, Haico

    2012-01-01

    Heterozygous germline mutations in components of switch/sucrose nonfermenting (SWI/SNF) chromatin remodeling complexes were recently identified in patients with non-syndromic intellectual disability, Coffin-Siris syndrome and Nicolaides-Baraitser syndrome. The common denominator of the phenotype of these patients is severe intellectual disability and speech delay. Somatic and germline mutations in SWI/SNF components were previously implicated in tumor development. This raises the question whether patients with intellectual disability caused by SWI/SNF mutations in the germline are exposed to an increased risk of developing cancer. Here we compare the mutational spectrum of SWI/SNF components in intellectual disability syndromes and cancer, and discuss the implications of the results of this comparison for the patients. PMID:23010866

  3. Spent Nuclear Fuel Project Safety Management Plan

    International Nuclear Information System (INIS)

    Garvin, L.J.

    1996-02-01

    The Spent Nuclear Fuel Project Safety Management Plan describes the new nuclear facility regulatory requirements basis for the Spemt Nuclear Fuel (SNF) Project and establishes the plan to achieve compliance with this basis at the new SNF Project facilities

  4. Technology development for DOE SNF management

    International Nuclear Information System (INIS)

    Hale, D.L.; Einziger, R.E.; Murphy, J.R.

    1995-01-01

    This paper describes the process used to identify technology development needs for the same management of spent nuclear fuel (SNF) in the US Department of Energy (DOE) inventory. Needs were assessed for each of the over 250 fuel types stores at DOE sites around the country for each stage of SNF management--existing storage, transportation, interim storage, and disposal. The needs were then placed into functional groupings to facilitate integration and collaboration among the sites

  5. Radiation Requirements for Uranium Mining Projects

    International Nuclear Information System (INIS)

    Hondros, Jim

    2014-01-01

    Conclusions: • Radiation impact can be complex and confusing; • Aim to be credible and competent; • Process can be straightforward; – Baseline monitoring; – Project emissions; – Impact of emission; – Management measures. • “Tell the story” (what does it all mean)

  6. Online Simulation of Radiation Track Structure Project

    Science.gov (United States)

    Plante, Ianik

    2015-01-01

    Space radiation comprises protons, helium and high charged and energy (HZE) particles. High-energy particles are a concern for human space flight, because they are no known options for shielding astronauts from them. When these ions interact with matter, they damage molecules and create radiolytic species. The pattern of energy deposition and positions of the radiolytic species, called radiation track structure, is highly dependent on the charge and energy of the ion. The radiolytic species damage biological molecules, which may lead to several long-term health effects such as cancer. Because of the importance of heavy ions, the radiation community is very interested in the interaction of HZE particles with DNA, notably with regards to the track structure. A desktop program named RITRACKS was developed to simulate radiation track structure. The goal of this project is to create a web interface to allow registered internal users to use RITRACKS remotely.

  7. Research projects in radiobiology and radiation protection

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1960-04-15

    Of the research projects sponsored by the International Atomic Energy Agency quite a large number are concerned with the biological effects of ionizing radiation. That itself, of course, is a very wide field covering such subjects as the nature and mechanism of radiation damage, genetic mutations, the varying radiosensitivity of different organisms, ways of modifying the natural sensitivity or resistance, and biological and chemical means of protection. In all these branches of enquiry, the Agency has awarded research contracts to scientific institutes or laboratories in different countries

  8. Research projects in radiobiology and radiation protection

    International Nuclear Information System (INIS)

    1960-01-01

    Of the research projects sponsored by the International Atomic Energy Agency quite a large number are concerned with the biological effects of ionizing radiation. That itself, of course, is a very wide field covering such subjects as the nature and mechanism of radiation damage, genetic mutations, the varying radiosensitivity of different organisms, ways of modifying the natural sensitivity or resistance, and biological and chemical means of protection. In all these branches of enquiry, the Agency has awarded research contracts to scientific institutes or laboratories in different countries

  9. The remote methods for radwaste and SNF control

    International Nuclear Information System (INIS)

    Ivanov, O; Stepanov, V; Danilovich, A; Potapov, V

    2017-01-01

    With the examples of developments carried out in the Kurchatov Institute and by the world leaders in the field the presentation considers the devices and methods to obtain remotely information on the distribution of radioactivity in radwaste and SNF. It describes the different types of light portable gamma cameras. The application of scanning spectrometric systems is considers also. The methods of recording UV radiation for detection of alpha contamination with the luminescence of air are presented. We discuss the scope and tasks that can be solved using remote and non-destructive methods. (paper)

  10. New synchrotron radiation facility project. Panel on new synchrotron radiation facility project

    CERN Document Server

    Sato, S; Kimura, Y

    2003-01-01

    The project for constructing a new synchrotron radiation facility dedicated to the science in VUV (or EUV) and Soft X-ray (SX) region has been discussed for these two years at the Panel on New Synchrotron Radiation Facility Project. The Panel together with the Accelerator Design Working Group (WG), Beamline Design WG and Research Program WG suggested to the Ministry of Education, Science, Culture and Sports the construction of a 1.8 GeV electron storage ring suitable for 'Top-Up' operation and beamlines and monochromators designed for undulator radiation. The scientific programs proposed by nationwide scientists are summarized with their requirements of the characteristics of the beam. (author)

  11. Characterization Program Management Plan for Hanford K Basin Spent Nuclear Fuel (SNF) (OCRWM)

    International Nuclear Information System (INIS)

    BAKER, R.B.; TRIMBLE, D.J.

    2000-01-01

    The management plan developed to characterize the K Basin spent nuclear fuel (SNF) and sludge was originally developed for Westinghouse Hanford Company and Pacific Northwest National Laboratory to work together on a program to provide characterization data to support removal, conditioning, and subsequent dry storage of the SNF stored at the Hanford K Basins. The plan also addressed necessary characterization for the removal, transport, and storage of the sludge from the Hanford K Basins. This plan was revised in 1999 (i.e., Revision 2) to incorporate actions necessary to respond to the deficiencies revealed as the result of Quality Assurance surveillances and audits in 1999 with respect to the fuel characterization activities. Revision 3 to this Program Management Plan responds to a Worker Assessment resolution determined in Fical Year 2000. This revision includes an update to current organizational structures and other revisions needed to keep this management plan consistent with the current project scope. The plan continues to address both the SNF and the sludge accumulated at K Basins. Most activities for the characterization of the SNF have been completed. Data validation, Office of Civilian Radioactive Waste Management (OCRWM) document reviews, and OCRWM data qualification are the remaining SNF characterization activities. The transport and storage of K Basin sludge are affected by recent path forward revisions. These revisions require additional laboratory analyses of the sludge to complete the acquisition of required supporting engineering data. Hence, this revision of the management plan provides the overall work control for these remaining SNF and sludge characterization activities given the current organizational structure of the SNF Project

  12. A method for selection of spent nuclear fuel (SNF) transportation route considering socioeconomic cost based on contingent valuation method (CVM)

    International Nuclear Information System (INIS)

    Kim, Young Sik

    2008-02-01

    A transportation of SNF may cause an additional radiation exposure to human beings. It means that the radiological risk should be estimated and managed quantitatively for the public who live near the shipments route. Before the SNF transportation is performed, the route selection is concluded based on the radiological risk estimated with RADTRAN code in existing method generally. It means the existing method for route selection is based only on the radiological health risk but there are not only the impacts related to the radiological health risk but also the socioeconomic impacts related to the cost. In this study, a new method and its numerical formula for route selection on transporting SNF is proposed based on cost estimation because there are several costs in transporting SNF. The total cost consists of radiological health cost, transportation cost, and socioeconomic cost. Each cost is defined properly to the characteristics of SNF transportation and many coefficients and variables describing the meaning of each cost are obtained or estimated through many surveys. Especially to get the socioeconomic cost, contingent valuation method (CVM) is used with a questionnaire. The socioeconomic cost estimation is the most important part of the total cost originated from transporting SNF because it is a very dominant cost in the total cost. The route selection regarding SNF transportation can be supported with the proposed method reasonably and unnecessary or exhausting controversies about the shipments could be avoided

  13. Atmospheric Ionizing Radiation (AIR) Project Review

    Science.gov (United States)

    Singleterry, R. C., Jr.; Wilson, J. W.; Whitehead, A. H.; Goldhagen, P. E.

    1999-01-01

    The National Council on Radiation Protection and Measurement (NCRP) and the National Academy of Science (NAS) established that the uncertainty in the data and models associated with the high-altitude radiation environment could and should be reduced. In response, the National Aeronautics and Space Administration (NASA) and the U.S. Department of Energy Environmental Measurements Laboratory (EML) created the Atmospheric Ionizing Radiation (AIR) Project under the auspices of the High Speed Research (HSR) Program Office at the Langley Research Center. NASA's HSR Program was developed to address the potential of a second-generation supersonic transport. A critical element focussed on the environmental issues, including the threat to crew and passengers posed by atmospheric radiation. Various international investigators were solicited to contribute instruments to fly on an ER-2 aircraft at altitudes similar to those proposed for the High Speed Civil Transport (HSCT). A list of participating investigators, their institutions, and instruments with quantities measured is presented. The flight series took place at solar minimum (radiation maximum) with northern, southern, and east/west flights. The investigators analyzed their data and presented preliminary results at the AIR Workshop in March, 1998. A review of these results are included.

  14. Project Radiation protection East. Status Report, July 1997

    Energy Technology Data Exchange (ETDEWEB)

    Snihs, J.O.; Sundewall, H.; Grapengiesser, S. [STEGRA Consultants (Sweden); Bennerstedt, T. [TeknoTelje (Sweden)

    1997-12-01

    Project Radiation Protection East is a Swedish program for radiation protection work in Central and Eastern Europe. The projects are assessed, planned and performed in close cooperation with partner organizations in the East. Since 1994 radiation protection cooperation concerning the former Soviet Navy training reactors in Paldiski, Estonia, is included in the project. This report presents a summary over some 140 projects, their status, allocated funds and their distribution over countries and project areas. 12 tabs.

  15. White Paper: Multi-purpose canister (MPC) for DOE-owned spent nuclear fuel (SNF)

    International Nuclear Information System (INIS)

    Knecht, D.A.

    1994-04-01

    The paper examines the issue, What are the advantages, disadvantages, and other considerations for using the MPC concept as part of the strategy for interim storage and disposal of DOE-owned SNF? The paper is based in part on the results of an evaluation made for the DOE National Spent Fuel Program by the Waste Form Barrier/Canister Team, which is composed of knowledgeable DOE and DOE-contractor personnel. The paper reviews the MPC and DOE SNF status, provides criteria and other considerations applicable to the issue, and presents an evaluation, conclusions, and recommendations. The primary conclusion is that while most of DOE SNF is not currently sufficiently characterized to be sealed into an MPC, the advantages of standardized packages in handling, reduced radiation exposure, and improved human factors should be considered in DOE SNF program planning. While the design of MPCs for DOE SNF are likely premature at this time, the use of canisters should be considered which are consistent with interim storage options and the MPC design envelope

  16. The Geostationary Earth Radiation Budget Project.

    Science.gov (United States)

    Harries, J. E.; Russell, J. E.; Hanafin, J. A.; Brindley, H.; Futyan, J.; Rufus, J.; Kellock, S.; Matthews, G.; Wrigley, R.; Last, A.; Mueller, J.; Mossavati, R.; Ashmall, J.; Sawyer, E.; Parker, D.; Caldwell, M.; Allan, P. M.; Smith, A.; Bates, M. J.; Coan, B.; Stewart, B. C.; Lepine, D. R.; Cornwall, L. A.; Corney, D. R.; Ricketts, M. J.; Drummond, D.; Smart, D.; Cutler, R.; Dewitte, S.; Clerbaux, N.; Gonzalez, L.; Ipe, A.; Bertrand, C.; Joukoff, A.; Crommelynck, D.; Nelms, N.; Llewellyn-Jones, D. T.; Butcher, G.; Smith, G. L.; Szewczyk, Z. P.; Mlynczak, P. E.; Slingo, A.; Allan, R. P.; Ringer, M. A.

    2005-07-01

    This paper reports on a new satellite sensor, the Geostationary Earth Radiation Budget (GERB) experiment. GERB is designed to make the first measurements of the Earth's radiation budget from geostationary orbit. Measurements at high absolute accuracy of the reflected sunlight from the Earth, and the thermal radiation emitted by the Earth are made every 15 min, with a spatial resolution at the subsatellite point of 44.6 km (north south) by 39.3 km (east west). With knowledge of the incoming solar constant, this gives the primary forcing and response components of the top-of-atmosphere radiation. The first GERB instrument is an instrument of opportunity on Meteosat-8, a new spin-stabilized spacecraft platform also carrying the Spinning Enhanced Visible and Infrared (SEVIRI) sensor, which is currently positioned over the equator at 3.5°W. This overview of the project includes a description of the instrument design and its preflight and in-flight calibration. An evaluation of the instrument performance after its first year in orbit, including comparisons with data from the Clouds and the Earth's Radiant Energy System (CERES) satellite sensors and with output from numerical models, are also presented. After a brief summary of the data processing system and data products, some of the scientific studies that are being undertaken using these early data are described. This marks the beginning of a decade or more of observations from GERB, as subsequent models will fly on each of the four Meteosat Second Generation satellites.

  17. Functional identification of an Arabidopsis snf4 ortholog by screening for heterologous multicopy suppressors of snf4 deficiency in yeast

    DEFF Research Database (Denmark)

    Kleinow, T.; Bhalerao, R.; Breuer, F.

    2000-01-01

    Yeast Snf4 is a prototype of activating gamma-subunits of conserved Snf1/AMPK-related protein kinases (SnRKs) controlling glucose and stress signaling in eukaryotes. The catalytic subunits of Arabidopsis SnRKs, AKIN10 and AKIN11, interact with Snf4 and suppress the snf1 and snf4 mutations in yeast....... By expression of an Arabidopsis cDNA library in yeast, heterologous multicopy snf4 suppressors were isolated. In addition to AKIN10 and AKIN11, the deficiency of yeast snf4 mutant to grown on non-fermentable carbon source was suppressed by Arabidopsis Myb30, CAAT-binding factor Hap3b, casein kinase I, zinc......-finger factors AZF2 and ZAT10, as well as orthologs of hexose/UDP-hexose transporters, calmodulin, SMC1-cohesin and Snf4. Here we describe the characterization of AtSNF4, a functional Arabidopsis Snf4 ortholog, that interacts with yeast Snf1 and specifically binds to the C-terminal regulatory domain...

  18. Scientific projection paper for radiation chemistry

    International Nuclear Information System (INIS)

    Simic, M.G.

    1980-01-01

    Together with radiation physics, an understanding of radiation chemistry is necessary for full appreciation of biological effects of high and low energy radiations, and for the development of prophylactic, therapeutic and potentiating methods and techniques in biological organisms. Areas covered in some detail in this report include: the early chemical events involved in the deposition of radiation energy; the kinetics of free radical and excited state reactions; the application of radiation chemistry to radiation biology; and the availability of instrumentation

  19. The Snf1 Protein Kinase in the Yeast Saccharomyces cerevisiae

    DEFF Research Database (Denmark)

    Usaite, Renata

    2008-01-01

    4 on the regulation of glucose and galactose metabolism, I physiologically characterized Δsnf1, Δsnf4, and Δsnfsnf4 CEN.PK background yeast strains in glucose and glucose-galactose mixture batch cultivations (chapter 2). The results of this study showed that delayed induction of galactose...... that the stable isotope labeling approach is highly reproducible among biological replicates when complex protein mixtures containing small expression changes were analyzed. Where poor correlation between stable isotope labeling and spectral counting was found, the major reason behind the discrepancy was the lack...

  20. Scientific projection paper for radiation chemistry

    International Nuclear Information System (INIS)

    Powers, E.L.

    1980-01-01

    Among all the environmental hazards to which man is exposed, ionizing radiation is the most thoroughly investigated and the most responsibly monitored and controlled. Nevertheless, because of the importance of radiation in modern society from both the hazard as well as the utilitarian standpoints, much more information concerning the biological effects induced and their modification and reversal is required. Together with radiation physics, an understanding of radiation chemistry is necessary for full appreciation of biological effects of high and low energy radiations, and for the development of prophylactic, therapeutic and potentiating methods and techniques in biological organisms

  1. Radiation safety at the West Valley Demonstration Project

    International Nuclear Information System (INIS)

    Hoffman, R.L.

    1997-01-01

    This is a report on the Radiation Safety Program at the West Valley Demonstration Project (WVDP). This Program covers a number of activities that support high-level waste solidification, stabilization of facilities, and decontamination and decommissioning activities at the Project. The conduct of the Program provides confidence that all occupational radiation exposures received during operational tasks at the Project are within limits, standards, and program requirements, and are as low as reasonably achievable

  2. Spent nuclear fuel project product specification

    International Nuclear Information System (INIS)

    PAJUNEN, A.L.

    1999-01-01

    This document establishes the limits and controls for the significant parameters that could potentially affect the safety and/or quality of the Spent Nuclear Fuel (SNF) packaged for processing, transport, and storage. The product specifications in this document cover the SNF packaged in Multi-Canister Overpacks to be transported throughout the SNF Project

  3. Advanced Radiation Protection (ARP): Advanced Radiation Protection Project

    Data.gov (United States)

    National Aeronautics and Space Administration — The project is building the first prototype integrated system to mitigate solar event risk through probabilistic modeling, forecasting, and dose projection. This new...

  4. Project Marna Natural Gamma Radiation MAP

    International Nuclear Information System (INIS)

    Suarez, E.; Fernandez, J.A.

    1997-01-01

    The confusion created by the accident that occurred in one of the Chernobyl reactors in April of 1986 made the general public and governments aware of the need for improved monitoring of environmental radiation levels. The levels of total gamma radiation or total gamma exposure rate over large areas reached values as high as 400 micro Roentgen/hour (mu R/h) and at points exceeded 1000 mu R/h. It should be borne in mind that, depending on the type of geological formations, normal values range from 5 to 30 mu R/h. The IAEA recommended to all countries that natural gamma radiation maps be made available to evaluate the levels of natural gamma radiation and possible increases, and it also indicated its concern that information be standardized. In addition, it stressed the advisability of using data obtained from uranium prospecting. (Author)

  5. FINAL REPORT FOR THE DIII-D RADIATIVE DIVERTOR PROJECT

    International Nuclear Information System (INIS)

    O'NEIL, RC; STAMBAUGH, RD

    2002-01-01

    OAK A271 FINAL REPORT FOR THE DIII-D RADIATIVE DIVERTOR PROJECT. The Radiative Divertor Project originated in 1993 when the DIII-D Five Year Plan for the period 1994--1998 was prepared. The Project Information Sheet described the objective of the project as ''to demonstrate dispersal of divertor power by a factor of then with sufficient diagnostics and modeling to extend the results to ITER and TPX''. Key divertor components identified were: (1) Carbon-carbon and graphite armor tiles; (2) The divertor structure providing a gas baffle and cooling; and (3) The divertor cryopumps to pump fuel and impurities

  6. QED radiative corrections under the SANC project

    International Nuclear Information System (INIS)

    Christova, P.

    2003-01-01

    Automatic calculations of the QED radiative corrections in the framework of the SANC computer system is described. A collection of the computer programs written in FORM3 language is aimed at compiling a database of analytic results to be used to theoretically support the experiments on high-energy accelerators. Presented here is the scheme of automatic analytical calculations of the QED radiative corrections to the fermionic decays of the Z, H and W boson in the framework of the SANC system

  7. DESIGN ANALYSIS FOR THE NAVAL SNF WASTE PACKAGE

    International Nuclear Information System (INIS)

    T.L. Mitchell

    2000-01-01

    The purpose of this analysis is to demonstrate the design of the naval spent nuclear fuel (SNF) waste package (WP) using the Waste Package Department's (WPD) design methodologies and processes described in the ''Waste Package Design Methodology Report'' (CRWMS MandO [Civilian Radioactive Waste Management System Management and Operating Contractor] 2000b). The calculations that support the design of the naval SNF WP will be discussed; however, only a sub-set of such analyses will be presented and shall be limited to those identified in the ''Waste Package Design Sensitivity Report'' (CRWMS MandO 2000c). The objective of this analysis is to describe the naval SNF WP design method and to show that the design of the naval SNF WP complies with the ''Naval Spent Nuclear Fuel Disposal Container System Description Document'' (CRWMS MandO 1999a) and Interface Control Document (ICD) criteria for Site Recommendation. Additional criteria for the design of the naval SNF WP have been outlined in Section 6.2 of the ''Waste Package Design Sensitivity Report'' (CRWMS MandO 2000c). The scope of this analysis is restricted to the design of the naval long WP containing one naval long SNF canister. This WP is representative of the WPs that will contain both naval short SNF and naval long SNF canisters. The following items are included in the scope of this analysis: (1) Providing a general description of the applicable design criteria; (2) Describing the design methodology to be used; (3) Presenting the design of the naval SNF waste package; and (4) Showing compliance with all applicable design criteria. The intended use of this analysis is to support Site Recommendation reports and assist in the development of WPD drawings. Activities described in this analysis were conducted in accordance with the technical product development plan (TPDP) ''Design Analysis for the Naval SNF Waste Package (CRWMS MandO 2000a)

  8. A desk evaluation review of project RAF/9/005 radiation protection development. Project desk evaluation

    International Nuclear Information System (INIS)

    1994-01-01

    The Agency has been assisting member nations through a number of national TC projects in radiation protection and related areas over the years. In addition, a regional project RAF/9/005 - Radiation Protection Development (which is under this review) was approved in 1988, with the aim of assessing existing radiation protection practices in the African Member States in relation to the Agency's new basic safety standards for radiation protection, and to advise Governments on improvements. The project was subsequently extended up to 1994 as an umbrella project to assist all African Member States in the development of appropriate radiation protection services; to co-ordinate the implementation of the relevant national TC projects; and to develop co-operation amongst groups of Member States on a regional and sub-regional basis. Particular emphasis was to be given to manpower development through workshops, seminars and training courses in radiation protection and safety. In parallel thereto, the Agency's Radiation Protection Advisory Teams (RAPATs) visited nineteen African Member States during the period 1986 through 1993, to review and assess their radiation protection activities, identify priorities, and design long-term radiation protection programmes. RAPAT findings and recommendations were considered in drawing up programmes for implementation under project RAF/9/005

  9. Reduction of radiation area project plan

    International Nuclear Information System (INIS)

    1979-08-01

    This plan deals with the overall reduction of outdoor surface radiation areas under Rockwell's jurisdiction. Four basic alternatives are identified which will reduce and/or stabilize radiation areas until long-term disposal decisions are made: (1) continued routine surveillance and maintenance; (2) reduction or elimination of effluent discharges; (3) improved site stabilization; and (4) site removal. The four major transport mechanisms at Hanford that are the primary forces for contamination spread are identified as wind, animal transport, concentration and dispersal by plants, and transport resulting from human activities

  10. Interaction of DOE SNF and Packaging Materials

    International Nuclear Information System (INIS)

    Anderson, P.A.

    1998-01-01

    A sensitivity analysis was conducted to identify and evaluate potential destructive interactions between the materials in US Department of Energy (USDOE) spent nuclear fuels (SNFs) and their storage/disposal canisters. The technical assessment was based on the thermodynamic properties as well as the chemical and physical characteristics of the materials expected inside the canisters. No chemical reactions were disclosed that could feasibly corrode stainless steel canisters to the point of failure. However, the possibility of embrittlement (loss of ductility) of the stainless steel through contact with liquid metal fission products or hydrogen inside the canisters cannot be dismissed. Higher-than-currently-permitted internal gas pressures must also be considered. These results, based on the assessment of two representative 90-year-cooled fuels that are stored at 200C in stainless steel canisters with internal blankets of helium, may be applied to most of the fuels in the USDOE's SNF inventory

  11. Project Management of a personnel radiation records computer system

    International Nuclear Information System (INIS)

    Labenski, T.

    1984-01-01

    Project Management techniques have been used to develop a data base management information system to provide storage and retrieval of personnel radiation and Health Physics records. The system is currently being developed on a Hewlett Packard 1000 Series E Computer with provisions to include plant radiation survey information, radiation work permit information, inventory management for Health Physics supplies and instrumentation, and control of personnel access to radiological controlled areas. The methodologies used to manage the overall project are presented along with selection and management of software vendors

  12. DOE SNF technology development necessary for final disposal

    International Nuclear Information System (INIS)

    Hale, D.L.; Fillmore, D.L.; Windes, W.E.

    1996-01-01

    Existing technology is inadequate to allow safe disposal of the entire inventory of US Department of Energy (DOE) spent nuclear fuel (SNF). Needs for SNF technology development were identified for each individual fuel type in the diverse inventory of SNF generated by past, current, and future DOE materials production, as well as SNF returned from domestic and foreign research reactors. This inventory consists of 259 fuel types with different matrices, cladding materials, meat composition, actinide content, and burnup. Management options for disposal of SNF include direct repository disposal, possible including some physical or chemical preparation, or processing to produce a qualified waste form by using existing aqueous processes or new treatment processes. Technology development needed for direct disposal includes drying, mitigating radionuclide release, canning, stabilization, and characterization technologies. While existing aqueous processing technology is fairly mature, technology development may be needed to apply one of these processes to SNF different than for which the process was originally developed. New processes to treat SNF not suitable for disposal in its current form were identified. These processes have several advantages over existing aqueous processes

  13. Management of environmental and radiation data - the Olympic Dam project

    International Nuclear Information System (INIS)

    Jenkins, B.

    1987-01-01

    In terms of data management the Olympic Dam Project is in a process of transition from investigative studies to operational monitoring. The data management requirements for investigative studies are quite different requirements and indicates the progress taken in this transition, as well as the directions being taken to complete this transition. The environmental and radiation management programs for the Olympic Dam Project have already stored 70 megabytes of data on computer. With the comprehensive monitoring requirements which have been, or are in the process of being established for production operations, the volume of data is increasing. There are six main areas involving environmental and radiation data management: project area environmental monitoring; monitoring of the impact pathway from groundwater extraction for water supply to possible effects on mound springs; radiation levels in the environment; radiation exposures to designated employees; other occupational exposures in the mine; medical records relevant to occupational health

  14. Radiation protection aspects of AECL's retube/refurbishment projects

    International Nuclear Information System (INIS)

    Zhuang, Y.; Boss, C.R.; Pontikakis, N.

    2007-01-01

    In contrast to the construction of a new nuclear reactor, Retube/Refurbishment of nuclear reactors that have been in operation for many years will involve fabrication of a new core in a radiation environment. Careful planning of the radiation protection (RP) program is crucial to ensure the protection of workers and the environment, and the success of the projects. This paper describes the key RP activities currently underway in AECL's Retube/Refurbishment projects, covering RP during retubing tooling and system designs, retubing work planning, retubing operation, and waste transfer and management. The discussion will focus on RP initiatives from engineering design aspects of the projects. (author)

  15. Spent Nuclear Fuel project interface control plan

    International Nuclear Information System (INIS)

    Reilly, M.A.

    1995-01-01

    This implementation process philosophy is in keeping with the ongoing reengineering of the WHC Controlled Manuals to achieve interface control within the SNF Project. This plan applies to all SNF Project sub-project to sub-project, and sub-project to exteranl (both on and off the Hanford Site) interfaces

  16. Radiative-convective equilibrium model intercomparison project

    Science.gov (United States)

    Wing, Allison A.; Reed, Kevin A.; Satoh, Masaki; Stevens, Bjorn; Bony, Sandrine; Ohno, Tomoki

    2018-03-01

    RCEMIP, an intercomparison of multiple types of models configured in radiative-convective equilibrium (RCE), is proposed. RCE is an idealization of the climate system in which there is a balance between radiative cooling of the atmosphere and heating by convection. The scientific objectives of RCEMIP are three-fold. First, clouds and climate sensitivity will be investigated in the RCE setting. This includes determining how cloud fraction changes with warming and the role of self-aggregation of convection in climate sensitivity. Second, RCEMIP will quantify the dependence of the degree of convective aggregation and tropical circulation regimes on temperature. Finally, by providing a common baseline, RCEMIP will allow the robustness of the RCE state across the spectrum of models to be assessed, which is essential for interpreting the results found regarding clouds, climate sensitivity, and aggregation, and more generally, determining which features of tropical climate a RCE framework is useful for. A novel aspect and major advantage of RCEMIP is the accessibility of the RCE framework to a variety of models, including cloud-resolving models, general circulation models, global cloud-resolving models, single-column models, and large-eddy simulation models.

  17. Aspen Forest Cover by Stratum/Plot (SNF)

    Data.gov (United States)

    National Aeronautics and Space Administration — Average percent coverage and standard deviation of each canopy stratum from subplots at each aspen site during the SNF study in the Superior National Forest, Minnesota

  18. Purification and characterization of the three Snf1-activating kinases of Saccharomyces cerevisiae

    OpenAIRE

    Elbing, Karin; McCartney, Rhonda R.; Schmidt, Martin C.

    2006-01-01

    Members of the Snf1/AMPK family of protein kinases are activated by distinct upstream kinases that phosphorylate a conserved threonine residue in the Snf1/AMPK activation loop. Recently, the identities of the Snf1- and AMPK-activating kinases have been determined. Here we describe the purification and characterization of the three Snf1-activating kinases of Saccharomyces cerevisiae. The identities of proteins associated with the Snf1-activating kinases were determined by peptide mass fingerpr...

  19. NASA Space Radiation Risk Project: Overview and Recent Results

    Science.gov (United States)

    Blattnig, Steve R.; Chappell, Lori J.; George, Kerry A.; Hada, Megumi; Hu, Shaowen; Kidane, Yared H.; Kim, Myung-Hee Y.; Kovyrshina, Tatiana; Norman, Ryan B.; Nounu, Hatem N.; hide

    2015-01-01

    The NASA Space Radiation Risk project is responsible for integrating new experimental and computational results into models to predict risk of cancer and acute radiation syndrome (ARS) for use in mission planning and systems design, as well as current space operations. The project has several parallel efforts focused on proving NASA's radiation risk projection capability in both the near and long term. This presentation will give an overview, with select results from these efforts including the following topics: verification, validation, and streamlining the transition of models to use in decision making; relative biological effectiveness and dose rate effect estimation using a combination of stochastic track structure simulations, DNA damage model calculations and experimental data; ARS model improvements; pathway analysis from gene expression data sets; solar particle event probabilistic exposure calculation including correlated uncertainties for use in design optimization.

  20. Spent Nuclear Fuel (SNF) Startup Plan to Operations

    International Nuclear Information System (INIS)

    GREGORY, J.R.

    2000-01-01

    This plan defines the approach that will be used to ensure the transition from initial startup to normal operations of the SNF operations--are performed in a safe, controlled, and deliberate manner. It provides a phased approach that bridges the operations between the completion of the ORR and the return to normal operations. This plan includes management oversight and administrative controls to be implemented and then reduced in a controlled manner until normal operations are authorized by SNF Management

  1. SNF/HLW Transfer System Description Document

    International Nuclear Information System (INIS)

    W. Holt

    2005-01-01

    The purpose of this system description document (SDD) is to establish requirements that drive the design of the spent nuclear fuel (SNF)/high-level radioactive waste (HLW) transfer system and associated bases, which will allow the design effort to proceed to license application. This SDD will be revised at strategic points as the design matures. This SDD identifies the requirements and describes the system design, as it currently exists, with emphasis on attributes of the design provided to meet the requirements. This SDD is an engineering tool for design control. Accordingly, the primary audience and users are design engineers. This SDD is part of an iterative design process. It leads the design process with regard to the flowdown of upper tier requirements onto the system. Knowledge of these requirements is essential in performing the design process. The SDD follows the design with regard to the description of the system. The description provided in this SDD reflects the current results of the design process

  2. The Indiana University proton radiation therapy project

    International Nuclear Information System (INIS)

    Bloch, C.; Derenchuk, V.; Cameron, J.; Fasano, M.; Gilmore, J.; Hashemian, R.; Hornback, N.; Low, D.A.; Morphis, J.; Peterson, C.; Rosselot, D.; Sandison, G.; Shen, R.N.; Shidnia, H.

    1993-01-01

    A fixed horizontal beam line at the Indiana University cyclotron facility (IUCF) has been equipped for proton radiation therapy treatment of head, neck, and brain tumors. The complete system will be commissioned and ready to treat patients early in 1993. IUCF can produce external proton beams from 45 to 200 MeV in energy, which corresponds to a maximum range in water of 26 cm. Beam currents over 100 nA are easily attained, allowing dose rates in excess of 200 cGy/min, even for large fields. Beam spreading systems have been tested which provide uniform fields up to 20 cm in diameter. Range modulation is accomplished with a rotating acrylic device, which provides uniform depth dose distributions from 3 to 18 cm in extent. Tests have been conducted on detectors which monitor the beam position and current, and the dose symmetry. This report discusses those devices, as well as the cyclotron characteristics, measured beam properties, safety interlocks, computerized dose delivery/monitoring system, and future plans. (orig.)

  3. Improving Climate Projections by Understanding How Cloud Phase affects Radiation

    Science.gov (United States)

    Cesana, Gregory; Storelvmo, Trude

    2017-01-01

    Whether a cloud is predominantly water or ice strongly influences interactions between clouds and radiation coming down from the Sun or up from the Earth. Being able to simulate cloud phase transitions accurately in climate models based on observational data sets is critical in order to improve confidence in climate projections, because this uncertainty contributes greatly to the overall uncertainty associated with cloud-climate feedbacks. Ultimately, it translates into uncertainties in Earth's sensitivity to higher CO2 levels. While a lot of effort has recently been made toward constraining cloud phase in climate models, more remains to be done to document the radiative properties of clouds according to their phase. Here we discuss the added value of a new satellite data set that advances the field by providing estimates of the cloud radiative effect as a function of cloud phase and the implications for climate projections.

  4. NREL Solar Radiation Resource Assessment Project: Status and outlook

    Science.gov (United States)

    Renne, D.; Riordan, C.; Maxwell, E.; Stoffel, T.; Marion, B.; Rymes, M.; Wilcox, S.; Myers, D.

    1992-05-01

    This report summarizes the activities and accomplishments of NREL's Solar Radiation Resource Assessment Project during fiscal year 1991. Currently, the primary focus of the SRRAP is to produce a 1961 - 1990 National Solar Radiation Data Base, providing hourly values of global horizontal, diffuse, and direct normal solar radiation at approximately 250 sites around the United States. Because these solar radiation quantities were measured intermittently at only about 50 of these sites, models were developed and applied to the majority of the stations to provide estimates of these parameters. Although approximately 93 percent of the data base consists of modeled data this represents a significant improvement over the SOLMET/ERSATZ 1952 - 1975 data base. The magnitude and importance of this activity are such that the majority of SRRAP human and financial resources were devoted to the data base development. However, in FY 1991 the SRRAP was involved in many other activities, which are reported here. These include the continued maintenance of a solar radiation monitoring network in the southeast United States at six Historically Black Colleges and Universities (HBCU's), the transfer of solar radiation resource assessment technology through a variety of activities, participation in international programs, and the maintenance and operation of NREL's Solar Radiation Research Laboratory.

  5. Project reconversion Service Hospital Radiation Oncology Clinics-Medical School

    International Nuclear Information System (INIS)

    Quarneti, A.; Levaggi, G.

    2004-01-01

    Introduction: The Health Sector operates within the framework of Social Policy and it is therefore one of the ways of distribution of public benefit, like Housing, Education and Social Security. While public spending on health has grown in recent years, its distribution has been uneven and the sector faces funding and management problems. The Service Hospital Radiation Oncology has reduced its health care liavility , lack technological development and unsufficient human resources and training. Aim: developing an inclusive reform bill Service Hospital Radiation Oncology .Material and Methods: This project tends to form a network institutional, introducing concepts of evidence-based medicine, risk models, cost analysis, coding systems, system implementation of quality management (ISO-9000 Standards). Proposes redefining radiotherapy centers and their potential participation in training resource development goals humanos.Promueve scientific research of national interest. Separate strictly administrative function, management and teaching. The project takes into account the characteristics of demand, the need to order it and organize around her, institutional network system and within the Hospital das Clinicas own related services related to Service Hospital Radiation Oncology , Encourages freedom of choice, and confers greater equity in care. The project would managed by the Hospital Clínicas. Conclusions: We believe this proposal identifies problems and opportunities, Service Hospital Radiation Oncology proposes the development of institutional network under one management model

  6. Evaluation of Neutron Poison Materials for DOE SNF Disposal Systems

    International Nuclear Information System (INIS)

    Vinson, D.W.; Caskey, G.R. Jr.; Sindelar, R.L.

    1998-09-01

    Aluminum-based spent nuclear fuel (Al-SNF) from foreign and domestic research reactors is being consolidated at the Savannah River Site (SRS) for ultimate disposal in the Mined Geologic Disposal System (MGDS). Most of the aluminum-based fuel material contains highly enriched uranium (HEU) (more than 20 percent 235U), which challenges the preclusion of criticality events for disposal periods exceeding 10,000 years. Recent criticality analyses have shown that the addition of neutron absorbing materials (poisons) is needed in waste packages containing DOE SNF canisters fully loaded with Al-SNF under flooded and degraded configurations to demonstrate compliance with the requirement that Keff less than 0.95. Compatibility of poison matrix materials and the Al-SNF, including their relative degradation rate and solubility, are important to maintain criticality control. An assessment of the viability of poison and matrix materials has been conducted, and an experimental corrosion program has been initiated to provide data on degradation rates of poison and matrix materials and Al-SNF materials under repository relevant vapor and aqueous environments. Initial testing includes Al6061, Type 316L stainless steel, and A516Gr55 in synthesized J-13 water vapor at 50 degrees C, 100 degrees C, and 200 degrees C and in condensate water vapor at 100 degrees C. Preliminary results are presented herein

  7. Alteration to the SWI/SNF complex in human cancers

    Directory of Open Access Journals (Sweden)

    Vanessa S. Gordon

    2011-12-01

    Full Text Available The SWI/SNF complex is a key catalyst for gene expression and regulates a variety of pathways, many of which have anticancer roles. Its central roles in cellular growth control, DNA repair, differentiation, cell adhesion and development are often targeted, and inactivated, during cancer development and progression. In this review, we will discuss what is known about how SWI/SNF is inactivated, and describe the potential impact of abrogating this complex. BRG1 and BRM are the catalytic subunits which are essential for SWI/SNF function, and thus, it is not surprising that they are lost in a variety of cancer types. As neither gene is mutated when lost, the mechanism of suppression, as well as the impact of potential gene activity restoration, are reviewed.

  8. Radiation technology for sewage sludge treatment: The Argentine project

    International Nuclear Information System (INIS)

    Graino, J.G.

    2001-01-01

    Within the environmental applications of ionizing radiation, disinfection of wastewaters or sewage sludges is one of the most best known. Argentina based the project of a full scale irradiation plant on the gamma irradiation application, utilizing Argentine made Cobalt-60 sources. The design characteristics, process descriptions and costs are included. The research project developed information about the irradiation effects on the sludges with respect to plant performance. For the purpose of oxi-irradiation experiments, a lab-scale pool irradiator was constructed and is described. (author)

  9. Project on 'contaminations - radiation - ecosystems - health' in Russia

    International Nuclear Information System (INIS)

    Botov, N.G.; Kozulin, S.P.; Mironova, N.I.; Dubov, R.I.

    1993-01-01

    This project has two purposes: 1. To determine the influence of the radiation factor among other factors that are increasing human disease and death rate, and are determining industrial impacts to the environment, ecosystems, and people's lives; 2. To ascertain the ecological, medical and social wellbeing of certain contaminated areas in Russia, monitoring and management of radioactive pollution, radioactive waste storage, heavy metals and other contaminants. In our report we present the following: a few experimental data on radioactive contamination; problems of information, experiments and metrology; scientific and technical methods and approaches; financial, equipmental and other needs, that are necessary for successful completion of this Project

  10. CONTAINMENT EVALUATION OF BREACHED AL-SNF FOR CASK TRANSPORT

    International Nuclear Information System (INIS)

    Vinson, D. W.; Sindelar, R. L.; Iyer, N. C.

    2005-01-01

    Aluminum-based spent nuclear fuel (Al-SNF) from foreign and domestic research reactors (FRR/DRR) is being shipped to the Savannah River Site. To enter the U.S., the cask with loaded fuel must be certified to comply with the requirements in the Title 10 of the U.S. Code of Federal Regulations, Part 71. The requirements include demonstration of containment of the cask with its contents under normal and accident conditions. Al-SNF is subject to corrosion degradation in water storage, and many of the fuel assemblies are ''failed'' or have through-clad damage. A methodology has been developed with technical bases to show that Al-SNF with cladding breaches can be directly transported in standard casks and maintained within the allowable release rates. The approach to evaluate the limiting allowable leakage rate, L R , for a cask with breached Al-SNF for comparison to its test leakage rate could be extended to other nuclear material systems. The approach for containment analysis of Al-SNF follows calculations for commercial spent fuel as provided in NUREG/CR-6487 that adopts ANSI N14.5 as a methodology for containment analysis. The material-specific features and characteristics of damaged Al-SNF (fuel materials, fabrication techniques, microstructure, radionuclide inventory, and vapor corrosion rates) that were derived from literature sources and/or developed in laboratory testing are applied to generate the four containment source terms that yield four separate cask cavity activity densities; namely, those from fines; gaseous fission product species; volatile fission product species; and fuel assembly crud. The activity values, A 2 , are developed per the guidance of 10CFR71. The analysis is performed parametrically to evaluate maximum number of breached assemblies and exposed fuel area for a proposed shipment in a cask with a test leakage rate

  11. Plan for Characterization of K Basin Spent Nuclear Fuel (SNF) and Sludge (OCRWM)

    International Nuclear Information System (INIS)

    TRIMBLE, D.J.

    2000-01-01

    This is an update of the plan for the characterization of spent nuclear fuel (SNF) and sludge stored in the Hanford K West and K East Basins. The purpose of the characterization program is to provide fuel and sludge data in support of the SNF Project in the effort to remove the fuel from the K Basins and place it into dry storage. Characterization of the K Basin fuel and sludge was initiated in 1994 and has been guided by the characterization plans (Abrefah 1994, Lawrence 1995a, Lawrence 1995b) and the characterization program management plan (PMP) (Lawrence 1995c, Lawrence 1998, Trimble 1999). The fuel characterization was completed in 1999. Summaries of these activities were documented by Lawrence (1999) and Suyama (1999). Lawrence (1999) is a summary report providing a road map to the detailed documentation of the fuel characterization. Suyama (1999) provides a basis for the limited characterization sample size as it relates to supporting design limits and the operational safety envelope for the SNF Project. The continuing sludge characterization is guided by a data quality objective (DQO) (Makenas 2000) and a sampling and analysis plan (SAP) (Baker, Welsh and Makenas 2000) The original intent of the characterization program was ''to provide bounding behavior for the fuel'' (Lawrence 1995a). To accomplish this objective, a fuel characterization program was planned that would provide data to augment data from the literature. The program included in-situ examinations of the stored fuel and laboratory testing of individual elements and small samples of fuel (Lawrence 1995a). Some of the planned tests were scaled down or canceled due to the changing needs of the SNF Project. The fundamental technical basis for the process that will be used to place the K Basin fuel into dry storage was established by several key calculations. These calculations characterized nominal and bounding behavior of fuel in Multi-Canister Overpacks (MCOs) during processing and storage

  12. Storage and treatment of SNF of Alfa class nuclear submarines: current status and problems

    International Nuclear Information System (INIS)

    Ignatiev, Sviatoslav; Zabudko, Alexey; Pankratov, Dmitry; Somov, Ivan; Suvorov, Gennady

    2007-01-01

    Available in abstract form only. Full text of publication follows: The current status and main problems associated with storage, defueling and following treatment of spent nuclear fuel (SNF) of Nuclear Submarines (NS) with heavy liquid metal cooled reactors are considered. In the final analysis these solutions could be realized in the form of separate projects to be funded through national and bi- and multilateral funding in the framework of the international collaboration of the Russian Federation on complex utilization of NS and rehabilitation of contaminated objects allocated in the North-West region of Russia. (authors)

  13. Advances in the project about Pin type silicon radiation detectors

    International Nuclear Information System (INIS)

    Ramirez F, J.; Cerdeira, A.; Aceves, M.; Diaz, A.; Estrada, M.; Rosales, P.; Cabal, A.E.; Montano L, M.; Leyva, A.

    1998-01-01

    The obtained advances in the collaboration project ININ-CINVESTAV about development of Pin type semiconductor radiation detectors here are presented. It has been characterized the response to different types of radiation made in CINVESTAV and INAOE. Measurements have been realized with different types of sensitive to charge preamplifiers determining the main characteristics which must be executed to be able to be employed with low capacitance detectors. As applications it has been possible to measure the irradiation time in a mammography machine and X-ray energy spectra have been obtained in the order of 14 KeV, with 4 KeV at ambient temperature. The future actions of project have been indicated and the possible applications of these detectors. (Author)

  14. Prototype Biology-Based Radiation Risk Module Project

    Science.gov (United States)

    Terrier, Douglas; Clayton, Ronald G.; Patel, Zarana; Hu, Shaowen; Huff, Janice

    2015-01-01

    Biological effects of space radiation and risk mitigation are strategic knowledge gaps for the Evolvable Mars Campaign. The current epidemiology-based NASA Space Cancer Risk (NSCR) model contains large uncertainties (HAT #6.5a) due to lack of information on the radiobiology of galactic cosmic rays (GCR) and lack of human data. The use of experimental models that most accurately replicate the response of human tissues is critical for precision in risk projections. Our proposed study will compare DNA damage, histological, and cell kinetic parameters after irradiation in normal 2D human cells versus 3D tissue models, and it will use a multi-scale computational model (CHASTE) to investigate various biological processes that may contribute to carcinogenesis, including radiation-induced cellular signaling pathways. This cross-disciplinary work, with biological validation of an evolvable mathematical computational model, will help reduce uncertainties within NSCR and aid risk mitigation for radiation-induced carcinogenesis.

  15. A User's Guide to the SNF ampersand INEL EIS

    International Nuclear Information System (INIS)

    1995-01-01

    This User's Guide is intended to help you find information in the SNF and INEL EIS (that's short for US Department of Energy Programmatic Spent Nuclear Fuel Management and Idaho National Engineering Laboratory Environmental Restoration and Waste Management Programs Final Environmental Impact Statement). The first section of this Guide gives you a brief overview of the SNF ampersand INEL EIS., The second section is organized to help you find specific information in the Environmental Impact Statement -- whether you're interested in a management alternative, a particular site (such as Hanford), or a discipline (such as land use or water quality)

  16. The Japan Power Demonstration Reactor dismantling project. Radiation control

    International Nuclear Information System (INIS)

    Tomii, Hiroyuki; Seiki, Yoshihiro

    1996-01-01

    In the Japan Power Demonstration Reactor (JPDR) dismantling project, radiation control was performed properly with routine and special monitoring to keep the occupational safety and to collect data necessary for future dismantling of nuclear facilities. This report describes a summary of radiation control in the dismantling activities and some results of parametric analysis on dose equivalent evaluation, and introduces the following knowledge on radiological protection effectiveness of the dismantling systems applied in the project. a) Use of remote dismantling systems was effective in reducing equivalent workplace exposure. b) Utilization of existing facilities as radiation shield or radioactivity containment was effective in reducing workplace exposure, and also in increasing work efficiency. c) Use of underwater cutting systems was useful to minimize air contamination, and to reduce the dose equivalent rate in the working area. d) In the planning of dismantling, it is necessary to optimize the radiation protection by analyzing dismantling work procedures and evaluating radiological features of the dismantling systems applied, including additional work which the systems require brought from such activities. (author)

  17. Health Economics in Radiation Oncology: Introducing the ESTRO HERO project

    International Nuclear Information System (INIS)

    Lievens, Yolande; Grau, Cai

    2012-01-01

    New evidence based regimens and novel high precision technology have reinforced the important role of radiotherapy in the management of cancer. Current data estimate that more than 50% of all cancer patients would benefit from radiotherapy during the course of their disease. Within recent years, the radiotherapy community has become more than conscious of the ever-increasing necessity to come up with objective data to endorse the crucial role and position of radiation therapy within the rapidly changing global oncology landscape. In an era of ever expanding health care costs, proven safety and effectiveness is not sufficient anymore to obtain funding, objective data about cost and cost-effectiveness are nowadays additionally requested. It is in this context that ESTRO is launching the HERO-project (Health Economics in Radiation Oncology), with the overall aim to develop a knowledge base and a model for health economic evaluation of radiation treatments at the European level. To accomplish these objectives, the HERO project will address needs, accessibility, cost and cost-effectiveness of radiotherapy. The results will raise the profile of radiotherapy in the European cancer management context and help countries prioritizing radiotherapy as a highly cost-effective treatment strategy. This article describes the different steps and aims within the HERO-project, starting from evidence on the role of radiotherapy within the global oncology landscape and highlighting weaknesses that may undermine this position.

  18. Health economics in radiation oncology: introducing the ESTRO HERO project.

    Science.gov (United States)

    Lievens, Yolande; Grau, Cai

    2012-04-01

    New evidence based regimens and novel high precision technology have reinforced the important role of radiotherapy in the management of cancer. Current data estimate that more than 50% of all cancer patients would benefit from radiotherapy during the course of their disease. Within recent years, the radiotherapy community has become more than conscious of the ever-increasing necessity to come up with objective data to endorse the crucial role and position of radiation therapy within the rapidly changing global oncology landscape. In an era of ever expanding health care costs, proven safety and effectiveness is not sufficient anymore to obtain funding, objective data about cost and cost-effectiveness are nowadays additionally requested. It is in this context that ESTRO is launching the HERO-project (Health Economics in Radiation Oncology), with the overall aim to develop a knowledge base and a model for health economic evaluation of radiation treatments at the European level. To accomplish these objectives, the HERO project will address needs, accessibility, cost and cost-effectiveness of radiotherapy. The results will raise the profile of radiotherapy in the European cancer management context and help countries prioritizing radiotherapy as a highly cost-effective treatment strategy. This article describes the different steps and aims within the HERO-project, starting from evidence on the role of radiotherapy within the global oncology landscape and highlighting weaknesses that may undermine this position. Copyright © 2012 Elsevier Ireland Ltd. All rights reserved.

  19. Forecasting of Radiation Belts: Results From the PROGRESS Project.

    Science.gov (United States)

    Balikhin, M. A.; Arber, T. D.; Ganushkina, N. Y.; Walker, S. N.

    2017-12-01

    Forecasting of Radiation Belts: Results from the PROGRESS Project. The overall goal of the PROGRESS project, funded in frame of EU Horizon2020 programme, is to combine first principles based models with the systems science methodologies to achieve reliable forecasts of the geo-space particle radiation environment.The PROGRESS incorporates three themes : The propagation of the solar wind to L1, Forecast of geomagnetic indices, and forecast of fluxes of energetic electrons within the magnetosphere. One of the important aspects of the PROGRESS project is the development of statistical wave models for magnetospheric waves that affect the dynamics of energetic electrons such as lower band chorus, hiss and equatorial noise. The error reduction ratio (ERR) concept has been used to optimise the set of solar wind and geomagnetic parameters for organisation of statistical wave models for these emissions. The resulting sets of parameters and statistical wave models will be presented and discussed. However the ERR analysis also indicates that the combination of solar wind and geomagnetic parameters accounts for only part of the variance of the emissions under investigation (lower band chorus, hiss and equatorial noise). In addition, advances in the forecast of fluxes of energetic electrons, exploiting empirical models and the first principles IMPTAM model achieved by the PROGRESS project is presented.

  20. Spent Nuclear Fuel project systems engineering management plan

    International Nuclear Information System (INIS)

    Womack, J.C.

    1995-01-01

    The purpose of the WHC Systems Engineering Management Plan (SEMP) is to describe the systems engineering approach and methods that will be integrated with established WHC engineering practices to enhance the WHC engineering management of the SNF Project. The scope of the SEMP encompasses the efforts needed to manage the WHC implementation of systems engineering on the SNF Project. This implementation applies to, and is tailored to the needs of the SNF project and all its subprojects, including all current and future subprojects

  1. The DIII-D Radiative Divertor Project: Status and plans

    International Nuclear Information System (INIS)

    Smith, J.P.; Baxi, C.B.; Bozek, A.S.

    1996-10-01

    New divertor hardware is being designed and fabricated for the Radiative Divertor modification of the DIII-D tokamak. The installation of the hardware has been separated into two phases, the first phase starting in October of 1996 and the second and final phase, in 1998. The phased approach enables the continuation of the divertor characterization research in the lower divertor while providing pumping for density control in high triangularity, single- or double-null advanced tokamak discharges. When completed, the Radiative Divertor Project hardware will provide pumping at all four strike points of a double-null, high triangularity discharge and provide baffling of the neutral particles from transport back to the core plasma. By puffing neutral gas into the divertor region, a reduction in the heat flux on the target plates will be be demonstrated without a large rise in core density. This reduction in heat flux is accomplished by dispersing the power with radiation in the divertor region. Experiments and modeling have formed the basis for the new design. The capability of the DIII-D cryogenic system is being upgraded as part of this project. The increased capability of the cryogenic system will allow delivery of liquid helium and nitrogen to three new cryopumps. Physics studies on the effects of slot width and length can be accomplished easily with the design of the Radiative Divertor. The slot width can be varied by installing graphite tiles of different geometry. The change in slot length, the distance from the X-point to the target plate, requires relocating the structure vertically and can be completed in about 6-8 weeks. Radiative Divertor diagnostics are being designed to provide comprehensive measurements for diagnosing the divertor. Required diagnostic modifications will be minimal for Phase 1, but extensive for Phase 2 installation. These Phase 2 diagnostics will be required to fully diagnose the high triangularity discharges in the divertor slots

  2. Characterization of FRR SNF in Basin and Dry Storage Systems

    International Nuclear Information System (INIS)

    Brooks, H.M.; Sindelar, R.L.

    1998-09-01

    Since May 1996, over 1700 aluminum-based spent nuclear fuel (A1-SNF) assemblies have been inspected for corrosion and mechanical damage to determine if the cladding had been penetrated as part of the process for acceptance of the fuel at the Savannah River Site (SRS). The results of the release measurements are summarized in this paper

  3. 42 CFR 424.20 - Requirements for posthospital SNF care.

    Science.gov (United States)

    2010-10-01

    ... statements may be signed by— (1) The physician responsible for the case or, with his or her authorization, by a physician on the SNF staff or a physician who is available in case of an emergency and has knowledge of the case; or (2) A nurse practitioner or clinical nurse specialist, neither of whom has a...

  4. Projections onto the Pareto surface in multicriteria radiation therapy optimization.

    Science.gov (United States)

    Bokrantz, Rasmus; Miettinen, Kaisa

    2015-10-01

    To eliminate or reduce the error to Pareto optimality that arises in Pareto surface navigation when the Pareto surface is approximated by a small number of plans. The authors propose to project the navigated plan onto the Pareto surface as a postprocessing step to the navigation. The projection attempts to find a Pareto optimal plan that is at least as good as or better than the initial navigated plan with respect to all objective functions. An augmented form of projection is also suggested where dose-volume histogram constraints are used to prevent that the projection causes a violation of some clinical goal. The projections were evaluated with respect to planning for intensity modulated radiation therapy delivered by step-and-shoot and sliding window and spot-scanned intensity modulated proton therapy. Retrospective plans were generated for a prostate and a head and neck case. The projections led to improved dose conformity and better sparing of organs at risk (OARs) for all three delivery techniques and both patient cases. The mean dose to OARs decreased by 3.1 Gy on average for the unconstrained form of the projection and by 2.0 Gy on average when dose-volume histogram constraints were used. No consistent improvements in target homogeneity were observed. There are situations when Pareto navigation leaves room for improvement in OAR sparing and dose conformity, for example, if the approximation of the Pareto surface is coarse or the problem formulation has too permissive constraints. A projection onto the Pareto surface can identify an inaccurate Pareto surface representation and, if necessary, improve the quality of the navigated plan.

  5. Projections onto the Pareto surface in multicriteria radiation therapy optimization

    International Nuclear Information System (INIS)

    Bokrantz, Rasmus; Miettinen, Kaisa

    2015-01-01

    Purpose: To eliminate or reduce the error to Pareto optimality that arises in Pareto surface navigation when the Pareto surface is approximated by a small number of plans. Methods: The authors propose to project the navigated plan onto the Pareto surface as a postprocessing step to the navigation. The projection attempts to find a Pareto optimal plan that is at least as good as or better than the initial navigated plan with respect to all objective functions. An augmented form of projection is also suggested where dose–volume histogram constraints are used to prevent that the projection causes a violation of some clinical goal. The projections were evaluated with respect to planning for intensity modulated radiation therapy delivered by step-and-shoot and sliding window and spot-scanned intensity modulated proton therapy. Retrospective plans were generated for a prostate and a head and neck case. Results: The projections led to improved dose conformity and better sparing of organs at risk (OARs) for all three delivery techniques and both patient cases. The mean dose to OARs decreased by 3.1 Gy on average for the unconstrained form of the projection and by 2.0 Gy on average when dose–volume histogram constraints were used. No consistent improvements in target homogeneity were observed. Conclusions: There are situations when Pareto navigation leaves room for improvement in OAR sparing and dose conformity, for example, if the approximation of the Pareto surface is coarse or the problem formulation has too permissive constraints. A projection onto the Pareto surface can identify an inaccurate Pareto surface representation and, if necessary, improve the quality of the navigated plan

  6. Study and project of a radiation monitoring system in ships

    International Nuclear Information System (INIS)

    Morgado, Mario Monteiro

    1998-01-01

    In this work we present the project and the development of a radiation detection system for use in ships, called RADINAC. This system was developed to measure the radiation in several points of the ship and to give the dose rates and total dose. The radioactive activity of the sea water is also measured. The project was based on a system developed in the middle of the seventies which is not working due to the lack of some mechanical and electronic components. The RADINAC system was developed in order to nationalize and modernize the old project. The detectors used are plastic scintillator to measure the sea water radioactive activity and ionization chambers to measure the dose rates. The nuclear instrumentation has only three imported items: acquisition data board, picoamperimeter and photomultiplier tube. All the other items are made in Brazil. With regard to the data acquisition, we used the Labwindows software to create the 'virtual instruments' in order to display the data on the computer monitor. (author)

  7. Spent Nuclear Fuel Project Configuration Management Plan

    International Nuclear Information System (INIS)

    Reilly, M.A.

    1995-01-01

    This document is a rewrite of the draft ''C'' that was agreed to ''in principle'' by SNF Project level 2 managers on EDT 609835, dated March 1995 (not released). The implementation process philosphy was changed in keeping with the ongoing reengineering of the WHC Controlled Manuals to achieve configuration management within the SNF Project

  8. The NIOSH Radiation Dose Reconstruction Project: managing technical challenges.

    Science.gov (United States)

    Moeller, Matthew P; Townsend, Ronald D; Dooley, David A

    2008-07-01

    Approximately two years after promulgation of the Energy Employees Occupational Illness Compensation Program Act, the National Institute for Occupational Safety and Health Office of Compensation and Analysis Support selected a contractor team to perform many aspects of the radiation dose reconstruction process. The project scope and schedule necessitated the development of an organization involving a comparatively large number of health physicists. From the initial stages, there were many technical and managerial challenges that required continuous planning, integration, and conflict resolution. This paper identifies those challenges and describes the resolutions and lessons learned. These insights are hopefully useful to managers of similar scientific projects, especially those requiring significant data, technical methods, and calculations. The most complex challenge has been to complete defensible, individualized dose reconstructions that support timely compensation decisions at an acceptable production level. Adherence to applying claimant-favorable and transparent science consistent with the requirements of the Act has been the key to establishing credibility, which is essential to this large and complex project involving tens of thousands of individual stakeholders. The initial challenges included garnering sufficient and capable scientific staff, developing an effective infrastructure, establishing necessary methods and procedures, and integrating activities to ensure consistent, quality products. The continuing challenges include maintaining the project focus on recommending a compensation determination (rather than generating an accurate dose reconstruction), managing the associated very large data and information management challenges, and ensuring quality control and assurance in the presence of an evolving infrastructure. The lessons learned concern project credibility, claimant favorability, project priorities, quality and consistency, and critical

  9. Projection methods for line radiative transfer in spherical media.

    Science.gov (United States)

    Anusha, L. S.; Nagendra, K. N.

    An efficient numerical method called the Preconditioned Bi-Conjugate Gradient (Pre-BiCG) method is presented for the solution of radiative transfer equation in spherical geometry. A variant of this method called Stabilized Preconditioned Bi-Conjugate Gradient (Pre-BiCG-STAB) is also presented. These methods are based on projections on the subspaces of the n dimensional Euclidean space mathbb {R}n called Krylov subspaces. The methods are shown to be faster in terms of convergence rate compared to the contemporary iterative methods such as Jacobi, Gauss-Seidel and Successive Over Relaxation (SOR).

  10. Human projected area factors for detailed direct and diffuse solar radiation analysis

    DEFF Research Database (Denmark)

    Kubaha, K.; Fiala, D.; Toftum, Jørn

    2004-01-01

    Projected area factors for individual segments of the standing and sedentary human body were modelled for both direct and diffuse solar radiation using detailed 3D geometry and radiation models. The local projected area factors with respect to direct short-wave radiation are a function of the solar...

  11. Spent Nuclear Fuel (SNF) Removal Campaign Plan

    International Nuclear Information System (INIS)

    PAJUNEN, A.L.

    2000-01-01

    The overall operation of the Spent Nuclear Fuel Project will include fuel removal, sludge removal, debris removal, and deactivation transition activities. Figure 1-1 provides an overview of the current baseline operating schedule for project sub-systems, indicating that a majority of fuel removal activities are performed over an approximately three-and-one-half year time period. The purpose of this document is to describe the strategy for operating the fuel removal process systems. The campaign plan scope includes: (1) identifying a fuel selection sequence during fuel removal activities, (2) identifying MCOs that are subjected to extra testing (process validation) and monitoring, and (3) discussion of initial MCO loading and monitoring in the Canister Storage Building (CSB). The campaign plan is intended to integrate fuel selection requirements for handling special groups of fuel within the basin (e.g., single pass reactor fuel), process validation activities identified for process systems, and monitoring activities during storage

  12. Report of preliminary investigations on the next-generation large-scale synchrotron radiation facility projects

    International Nuclear Information System (INIS)

    1990-01-01

    The Special Committee for Future Project of the Japanese Society for Synchrotron Radiation Research investigated the construction-projects of the large-scaled synchrotron radiation facilities which are presently in progress in Japan. As a result, the following both projects are considered the very valuable research-project which will carry the development of Japan's next-generation synchrotron radiation science: 1. the 8 GeV synchrotron radiation facilities (SPring-8) projected to be constructed by Japan Atomic Energy Research Institute and the Institute of Physical and Chemical Research under the sponsorship of Science Technology Agency at Harima Science Park City, Hyogo Pref., Japan. 2. The project to utilize the Tristan Main Ring (MR) of the National Laboratory for High Energy Physics as the radiation source. Both projects are unique in research theme and technological approach, and complemental each other. Therefore it has been concluded that both projects should be aided and ratified by the Society. (M.T.)

  13. Upgrading of oil palm wastes by radiation processing - project review

    International Nuclear Information System (INIS)

    Nahrul Khair Alang Md Rashid

    1998-01-01

    Early works on oil palm waste treatment at MINT started in 1984 with the objective of degrading EFB (Empty Fruit Bunches) by radiation. This idea was shared by JAERI that adopted the research project with MINT in 1986 under the Japanese Science and Technology Agency (STA) programme. The results of these preliminary works show that EFB can be degraded using gamma radiation at a dose of ranging from 500 to 1000 kGy - 50 to 100 times higher than what is considered to be the economic dose. It is generally accepted that the economics of radiation treatment process could only be realised if the treatment dose can be kept below 10 kGy, which was incidentally, during the course of this early works, found to be the pasteurisation dose for oil palm by - products. With these information, MINT and JAERI agreed to pursue further research in this area and formulated a bilateral research co-operation in radiation pasteurisation of EFB and subsequent degradation by cellulolytic fungi or mushrooms. The research has the objective of upgrading EFB, which was not considered as suitable for feed due to its known physical properties as coarse and highly fibrous, to animal feed as well as substrate for mushroom cultivation and enzyme production. In addition to the desire to provide an environment friendly method for waste disposal to a growing industry, the possibility of catalysing the development of livestock industry by commercial farming in the process is another motivation for this project. Malaysia is estimated to be only about 40% self-sufficient in beef production. Thus there is great opportunity for the growth and expansion of this industry in Malaysia. However, growth in ruminant population should not result in the alienation of land for pastures. Among the reasons for the lack of interest in livestock production through commercial farming is the unavailability of local feed material which could be cheaper than imported feed grains, particularly maize. Feed is one the main cost

  14. Upgrading of oil palm wastes by radiation processing - project review

    Energy Technology Data Exchange (ETDEWEB)

    Alang Md Rashid, Nahrul Khair [Malaysian Institute for Nuclear Technology Research (MINT), Bangi (Malaysia)

    1998-07-01

    Early works on oil palm waste treatment at MINT started in 1984 with the objective of degrading EFB (Empty Fruit Bunches) by radiation. This idea was shared by JAERI that adopted the research project with MINT in 1986 under the Japanese Science and Technology Agency (STA) programme. The results of these preliminary works show that EFB can be degraded using gamma radiation at a dose of ranging from 500 to 1000 kGy - 50 to 100 times higher than what is considered to be the economic dose. It is generally accepted that the economics of radiation treatment process could only be realised if the treatment dose can be kept below 10 kGy, which was incidentally, during the course of this early works, found to be the pasteurisationdose for oil palm by - products. With these information, MINT and JAERI agreed to pursue further research in this area and formulated a bilateral research co-operation in radiation pasteurisation of EFB and subsequent degradation by cellulolytic fungi or mushrooms. The research has the objective of upgrading EFB, which was not considered as suitable for feed due to its known physical properties as coarse and highly fibrous, to animal feed as well as substrate for mushroom cultivation and enzyme production. In addition to the desire to provide an environment friendly method for waste disposal to a growing industry, the possibility of catalysing the development of livestock industry by commercial farming in the process is another motivation for this project. Malaysia is estimated to be only about 40% self-sufficient in beef production. Thus there is great opportunity for the growth and expansion of this industry in Malaysia. However, growth in ruminant population should not result in the alienation of land for pastures. Among the reasons for the lack of interest in livestock production through commercial farming is the unavailability of local feed material which could be cheaper than imported feed grains, particularly maize. Feed is one the main cost

  15. Purification and characterization of the three Snf1-activating kinases of Saccharomyces cerevisiae.

    Science.gov (United States)

    Elbing, Karin; McCartney, Rhonda R; Schmidt, Martin C

    2006-02-01

    Members of the Snf1/AMPK family of protein kinases are activated by distinct upstream kinases that phosphorylate a conserved threonine residue in the Snf1/AMPK activation loop. Recently, the identities of the Snf1- and AMPK-activating kinases have been determined. Here we describe the purification and characterization of the three Snf1-activating kinases of Saccharomyces cerevisiae. The identities of proteins associated with the Snf1-activating kinases were determined by peptide mass fingerprinting. These kinases, Sak1, Tos3 and Elm2 do not appear to require the presence of additional subunits for activity. Sak1 and Snf1 co-purify and co-elute in size exclusion chromatography, demonstrating that these two proteins form a stable complex. The Snf1-activating kinases phosphorylate the activation loop threonine of Snf1 in vitro with great specificity and are able to do so in the absence of beta and gamma subunits of the Snf1 heterotrimer. Finally, we showed that the Snf1 kinase domain isolated from bacteria as a GST fusion protein can be activated in vitro and shows substrate specificity in the absence of its beta and gamma subunits.

  16. Structure and novel functional mechanism of Drosophila SNF in sex-lethal splicing.

    Directory of Open Access Journals (Sweden)

    Jicheng Hu

    Full Text Available Sans-fille (SNF is the Drosophila homologue of mammalian general splicing factors U1A and U2B'', and it is essential in Drosophila sex determination. We found that, besides its ability to bind U1 snRNA, SNF can also bind polyuridine RNA tracts flanking the male-specific exon of the master switch gene Sex-lethal (Sxl pre-mRNA specifically, similar to Sex-lethal protein (SXL. The polyuridine RNA binding enables SNF directly inhibit Sxl exon 3 splicing, as the dominant negative mutant SNF(1621 binds U1 snRNA but not polyuridine RNA. Unlike U1A, both RNA recognition motifs (RRMs of SNF can recognize polyuridine RNA tracts independently, even though SNF and U1A share very high sequence identity and overall structure similarity. As SNF RRM1 tends to self-associate on the opposite side of the RNA binding surface, it is possible for SNF to bridge the formation of super-complexes between two introns flanking Sxl exon 3 or between a intron and U1 snRNP, which serves the molecular basis for SNF to directly regulate Sxl splicing. Taken together, a new functional model for SNF in Drosophila sex determination is proposed. The key of the new model is that SXL and SNF function similarly in promoting Sxl male-specific exon skipping with SNF being an auxiliary or backup to SXL, and it is the combined dose of SXL and SNF governs Drosophila sex determination.

  17. Sampling and analysis plan for the preoperational environmental survey of the spent nuclear fuel project facilities

    International Nuclear Information System (INIS)

    MITCHELL, R.M.

    1999-01-01

    This sampling and analysis plan will support the preoperational environmental monitoring for construction, development, and operation of the Spent Nuclear Fuel (SNF) Project facilities, which have been designed for the conditioning and storage of spent nuclear fuels; particularly the fuel elements associated with the operation of N-Reactor. The SNF consists principally of irradiated metallic uranium, and therefore includes plutonium and mixed fission products. The primary effort will consist of removing the SNF from the storage basins in K East and K West Areas, placing in multicanister overpacks, vacuum drying, conditioning, and subsequent dry vault storage in the 200 East Area. The primary purpose and need for this action is to reduce the risks to public health and safety and to the environment. Specifically these include prevention of the release of radioactive materials into the air or to the soil surrounding the K Basins, prevention of the potential migration of radionuclides through the soil column to the nearby Columbia River, reduction of occupational radiation exposure, and elimination of the risks to the public and to workers from the deterioration of SNF in the K Basins

  18. The MONIT project: electromagnetic radiation exposure assessment in mobile communications

    International Nuclear Information System (INIS)

    Carla Oliveira; Daniel Sebastiao; Goncalo Carpinteiro; Luis M Correia; Carlos A Fernandes; Afonso Serralha; Nuno Marques

    2006-01-01

    This paper presents the m.o.n.I.T. Project, a risk communication initiative, providing information to the public on exposure to radiation associated to Electromagnetic Fields (E.M.F.), and performing activities of exposure assessment. M.o.n.I.T. is developed within Instituto de Telecomunicacoes (I.T.) Lisbon site at Instituto Superior Tecnico (I.S.T., Technical University of Lisbon, Portugal), which is a non-profit scientific R and D institute with activities in the Telecommunications area. M.o.n.I.T. started in 2004 in the context of an emergent general public concern about possible health hazards caused by radiation from mobile communication antennas, most of the times rooted in misconceptions about the involved aspects, aggravated by the lack of trusty sources of information capable of presenting it in a simple understandable way. An objective evaluation of the risk requires the quantification of E.M.F. levels to which the population is exposed. Systematic information of this type was not openly available in Portugal, and this was one of the gaps that m.o.n.I.T. filled in, by providing results from extensive measurements campaigns performed in public places over the country for a period that presently mounts to three years. The monitoring system is based on a network of autonomous remote probing stations, and also on an extensive E.M.F. sounding program. Measured results are automatically uploaded to a web site for public dissemination (www.lx.it.pt/monit), which includes also other relevant information about E.M.F. for both the general public and the technical community. This paper describes the project structure and activities in Section 2, the automatic monitoring system in Section 3, and a brief analysis of the measured results in Section 4. Finally, some conclusions are presented in Section 5. (authors)

  19. The MONIT project: electromagnetic radiation exposure assessment in mobile communications

    Energy Technology Data Exchange (ETDEWEB)

    Carla Oliveira; Daniel Sebastiao; Goncalo Carpinteiro; Luis M Correia; Carlos A Fernandes [Instituto de Telecomunicacoes/Instituto Superior Tecnico, Technical University of Lisbon (Portugal); Afonso Serralha; Nuno Marques [Magnete Lisbon (Portugal)

    2006-07-01

    This paper presents the m.o.n.I.T. Project, a risk communication initiative, providing information to the public on exposure to radiation associated to Electromagnetic Fields (E.M.F.), and performing activities of exposure assessment. M.o.n.I.T. is developed within Instituto de Telecomunicacoes (I.T.) Lisbon site at Instituto Superior Tecnico (I.S.T., Technical University of Lisbon, Portugal), which is a non-profit scientific R and D institute with activities in the Telecommunications area. M.o.n.I.T. started in 2004 in the context of an emergent general public concern about possible health hazards caused by radiation from mobile communication antennas, most of the times rooted in misconceptions about the involved aspects, aggravated by the lack of trusty sources of information capable of presenting it in a simple understandable way. An objective evaluation of the risk requires the quantification of E.M.F. levels to which the population is exposed. Systematic information of this type was not openly available in Portugal, and this was one of the gaps that m.o.n.I.T. filled in, by providing results from extensive measurements campaigns performed in public places over the country for a period that presently mounts to three years. The monitoring system is based on a network of autonomous remote probing stations, and also on an extensive E.M.F. sounding program. Measured results are automatically uploaded to a web site for public dissemination (www.lx.it.pt/monit), which includes also other relevant information about E.M.F. for both the general public and the technical community. This paper describes the project structure and activities in Section 2, the automatic monitoring system in Section 3, and a brief analysis of the measured results in Section 4. Finally, some conclusions are presented in Section 5. (authors)

  20. Project Radiation Protection East. Swedish cooperation program for radiation protection in Eastern and Central Europe. Status Report, March 1996

    International Nuclear Information System (INIS)

    Snihs, J.O.; Johansson, Mai; Grapengiesser, S.; Bennerstedt, T.

    1996-04-01

    Until now the Swedish program for radiation protection work in central and Eastern europe has been granted 55 MSEK by the Swedish government. The projects are assessed, planned and performed in close cooperation with partner organizations in the East. Since 1994, radiation protection cooperation concerning the former Soviet Navy training reactors in Paldiski, Estonia, is included in Radiation Protection East. The government has granted 8 MSEK for this purpose. This report presents a summary over some 150 projects, their status, allocated funds and their distribution over countries and project areas. The presentation is updated up to March 1996. 7 figs

  1. Some aspects of the development of the Brazilian Synchroton Radiation Project

    International Nuclear Information System (INIS)

    Danon, J.

    1987-01-01

    The history and development of the Brazilian Synchroton Radiation Project are presented. Several aspects of this project may serve as a guide to achieve success in North-South cooperation. (M.W.O.) [pt

  2. Spent Nuclear Fuel (SNF) Cold Vacuum Drying (CVD) Facility Operations Manual; FINAL

    International Nuclear Information System (INIS)

    IRWIN, J.J.

    1999-01-01

    This document provides the Operations Manual for the Cold Vacuum Drying Facility (CVDF). The Manual was developed in conjunction with HNF-553, Spent Nuclear Fuel Project Final Safety Analysis Report Annex B-Cold Vacuum Drying Facility. The HNF-SD-SNF-DRD-002, 1999, Cold Vacuum Drying Facility Design Requirements, Rev. 4, and the CVDF Final Design Report. The Operations Manual contains general descriptions of all the process, safety and facility systems in the CVDF, a general CVD operations sequence and references to the CVDF System Design Descriptions (SDDs). This manual has been developed for the SNFP Operations Organization and shall be updated, expanded, and revised in accordance with future design, construction and startup phases of the CVDF until the CVDF final ORR is approved

  3. Spent Nuclear Fuel (SNF) Cold Vacuum Drying (CVD) Facility Operations Manual

    Energy Technology Data Exchange (ETDEWEB)

    IRWIN, J.J.

    1999-07-02

    This document provides the Operations Manual for the Cold Vacuum Drying Facility (CVDF). The Manual was developed in conjunction with HNF-553, Spent Nuclear Fuel Project Final Safety Analysis Report Annex B--Cold Vacuum Drying Facility. The HNF-SD-SNF-DRD-002, 1999, Cold Vacuum Drying Facility Design Requirements, Rev. 4, and the CVDF Final Design Report. The Operations Manual contains general descriptions of all the process, safety and facility systems in the CVDF, a general CVD operations sequence and references to the CVDF System Design Descriptions (SDDs). This manual has been developed for the SNFP Operations Organization and shall be updated, expanded, and revised in accordance with future design, construction and startup phases of the CVDF until the CVDF final ORR is approved.

  4. Subunits of the Snf1 kinase heterotrimer show interdependence for association and activity.

    Science.gov (United States)

    Elbing, Karin; Rubenstein, Eric M; McCartney, Rhonda R; Schmidt, Martin C

    2006-09-08

    The Snf1 kinase and its mammalian orthologue, the AMP-activated protein kinase (AMPK), function as heterotrimers composed of a catalytic alpha-subunit and two non-catalytic subunits, beta and gamma. The beta-subunit is thought to hold the complex together and control subcellular localization whereas the gamma-subunit plays a regulatory role by binding to and blocking the function of an auto-inhibitory domain (AID) present in the alpha-subunit. In addition, catalytic activity requires phosphorylation by a distinct upstream kinase. In yeast, any one of three Snf1-activating kinases, Sak1, Tos3, or Elm1, can fulfill this role. We have previously shown that Sak1 is the only Snf1-activating kinase that forms a stable complex with Snf1. Here we show that the formation of the Sak1.Snf1 complex requires the beta- and gamma-subunits in vivo. However, formation of the Sak1.Snf1 complex is not necessary for glucose-regulated phosphorylation of the Snf1 activation loop. Snf1 kinase purified from cells lacking the beta-subunits do not contain any gamma-subunit, indicating that the Snf1 kinase does not form a stable alphagamma dimer in vivo. In vitro kinase assays using purified full-length and truncated Snf1 proteins demonstrate that the kinase domain, which lacks the AID, is significantly more active than the full-length Snf1 protein. Addition of purified beta- and gamma-subunits could stimulate the kinase activity of the full-length alpha-subunit but only when all three subunits were present, suggesting an interdependence of all three subunits for assembly of a functional complex.

  5. Radiation environmental impact assessment of radioactive substances of an airport transit storage construction projects

    International Nuclear Information System (INIS)

    Zhang Baozeng; Xia Zitong; Zou Zhaozhuang

    2014-01-01

    Radioactive substances belong to dangerous goods transport aviation. Radioactive substances impoundments construction purpose is to ensure that the radioactive material during transport to transport and the public to achieve full or isolation, the effects of radiation on the human body, property and the environment caused by the control to an acceptable level. According to the relevant national standards and norms, for radiation protection evaluation of project construction of an airport radioactive impoundments, feasibility of the construction project radiation environment. (authors)

  6. Hazard Evaluation for Storage of Spent Nuclear Fuel (SNF) Sludge at the Solid Waste Treatment Facility

    International Nuclear Information System (INIS)

    SCHULTZ, M.V.

    2000-01-01

    As part of the Spent Nuclear Fuel (SNF) storage basin clean-up project, sludge that has accumulated in the K Basins due to corrosion of damaged irradiated N Reactor will be loaded into containers and placed in interim storage. The Hanford Site Treatment Complex (T Plant) has been identified as the location where the sludge will be stored until final disposition of the material occurs. Long term storage of sludge from the K Basin fuel storage facilities requires identification and analysis of potential accidents involving sludge storage in T Plant. This report is prepared as the initial step in the safety assurance process described in DOE Order 5480.23, Nuclear Safety Analysis Reports and HNF-PRO-704, Hazards and Accident Analysis Process. This report documents the evaluation of potential hazards and off-normal events associated with sludge storage activities. This information will be used in subsequent safety analyses, design, and operations procedure development to ensure safe storage. The hazards evaluation for the storage of SNF sludge in T-Plant used the Hazards and Operability Analysis (HazOp) method. The hazard evaluation identified 42 potential hazardous conditions. No hazardous conditions involving hazardous/toxic chemical concerns were identified. Of the 42 items identified in the HazOp study, eight were determined to have potential for onsite worker consequences. No items with potential offsite consequences were identified in the HazOp study. Hazardous conditions with potential onsite worker or offsite consequences are candidates for quantitative consequence analysis. The hazardous conditions with potential onsite worker consequences were grouped into two event categories, Container failure due to overpressure - internal to T Plant, and Spill of multiple containers. The two event categories will be developed into accident scenarios that will be quantitatively analyzed to determine release consequences. A third category, Container failure due to

  7. Supply and Demand for Radiation Oncology in the United States: Updated Projections for 2015 to 2025

    International Nuclear Information System (INIS)

    Pan, Hubert Y.; Haffty, Bruce G.; Falit, Benjamin P.; Buchholz, Thomas A.; Wilson, Lynn D.; Hahn, Stephen M.; Smith, Benjamin D.

    2016-01-01

    Purpose: Prior studies have forecasted demand for radiation therapy to grow 10 times faster than the supply between 2010 and 2020. We updated these projections for 2015 to 2025 to determine whether this imbalance persists and to assess the accuracy of prior projections. Methods and Materials: The demand for radiation therapy between 2015 and 2025 was estimated by combining current radiation utilization rates determined by the Surveillance, Epidemiology, and End Results data with population projections provided by the US Census Bureau. The supply of radiation oncologists was forecast by using workforce demographics and full-time equivalent (FTE) status provided by the American Society for Radiation Oncology (ASTRO), current resident class sizes, and expected survival per life tables from the US Centers for Disease Control. Results: Between 2015 and 2025, the annual total number of patients receiving radiation therapy during their initial treatment course is expected to increase by 19%, from 490,000 to 580,000. Assuming a graduating resident class size of 200, the number of FTE physicians is expected to increase by 27%, from 3903 to 4965. In comparison with prior projections, the new projected demand for radiation therapy in 2020 dropped by 24,000 cases (a 4% relative decline). This decrease is attributable to an overall reduction in the use of radiation to treat cancer, from 28% of all newly diagnosed cancers in the prior projections down to 26% for the new projections. By contrast, the new projected supply of radiation oncologists in 2020 increased by 275 FTEs in comparison with the prior projection for 2020 (a 7% relative increase), attributable to rising residency class sizes. Conclusion: The supply of radiation oncologists is expected to grow more quickly than the demand for radiation therapy from 2015 to 2025. Further research is needed to determine whether this is an appropriate correction or will result in excess capacity.

  8. Supply and Demand for Radiation Oncology in the United States: Updated Projections for 2015 to 2025

    Energy Technology Data Exchange (ETDEWEB)

    Pan, Hubert Y. [Department of Radiation Oncology, The University of Texas MD Anderson Cancer Center, Houston, Texas (United States); Haffty, Bruce G. [Department of Radiation Oncology, Robert Wood Johnson Medical School – University of Medicine and Dentistry of New Jersey, New Brunswick, New Jersey (United States); Falit, Benjamin P. [Radiation Oncology Associates, Lowell, Massachusetts (United States); Buchholz, Thomas A. [Department of Radiation Oncology, The University of Texas MD Anderson Cancer Center, Houston, Texas (United States); Wilson, Lynn D. [Department of Therapeutic Radiology, Yale University School of Medicine, New Haven, Connecticut (United States); Hahn, Stephen M. [Department of Radiation Oncology, The University of Texas MD Anderson Cancer Center, Houston, Texas (United States); Smith, Benjamin D., E-mail: bsmith3@mdanderson.org [Department of Radiation Oncology, The University of Texas MD Anderson Cancer Center, Houston, Texas (United States)

    2016-11-01

    Purpose: Prior studies have forecasted demand for radiation therapy to grow 10 times faster than the supply between 2010 and 2020. We updated these projections for 2015 to 2025 to determine whether this imbalance persists and to assess the accuracy of prior projections. Methods and Materials: The demand for radiation therapy between 2015 and 2025 was estimated by combining current radiation utilization rates determined by the Surveillance, Epidemiology, and End Results data with population projections provided by the US Census Bureau. The supply of radiation oncologists was forecast by using workforce demographics and full-time equivalent (FTE) status provided by the American Society for Radiation Oncology (ASTRO), current resident class sizes, and expected survival per life tables from the US Centers for Disease Control. Results: Between 2015 and 2025, the annual total number of patients receiving radiation therapy during their initial treatment course is expected to increase by 19%, from 490,000 to 580,000. Assuming a graduating resident class size of 200, the number of FTE physicians is expected to increase by 27%, from 3903 to 4965. In comparison with prior projections, the new projected demand for radiation therapy in 2020 dropped by 24,000 cases (a 4% relative decline). This decrease is attributable to an overall reduction in the use of radiation to treat cancer, from 28% of all newly diagnosed cancers in the prior projections down to 26% for the new projections. By contrast, the new projected supply of radiation oncologists in 2020 increased by 275 FTEs in comparison with the prior projection for 2020 (a 7% relative increase), attributable to rising residency class sizes. Conclusion: The supply of radiation oncologists is expected to grow more quickly than the demand for radiation therapy from 2015 to 2025. Further research is needed to determine whether this is an appropriate correction or will result in excess capacity.

  9. [Regulatory supervision and radiation survey in the area of location of former military technical bases].

    Science.gov (United States)

    Shandala, N K; Kiselev, S M; Titov, A V; Seregin, V A; Isaev, D V; Akhromeev, S V; Filonova, A A; Semenova, M P; Gimadova, T I; Aladova, R A; Kosnikov, A S; Shchelkanova, E S; Luk'ianets, A I

    2013-01-01

    Activities related to the rehabilitation of areas and facilities of the temporary storage of spent nuclear fuel and radioactive waste (SNF and RW) at Andreeva Bay and Gremikha on the Kola Peninsula and in the Primorsky Krai in the Russian Far East is an important component of the regulatory functions of the Federal Medical biological Agency (FMBA of Russia). Technical support to the FMBA of Russia in this activity is provided by A.L Burnazyan Federal Medical Biophysical Center Main research interests include evaluation of radiological threats to determine the priority directions of regulation, a detailed analysis of the radiation situation at areas, territories and in vicinity of temporary waste storage facilities, radiation control and environmental monitoring, the development of digital maps and geoinformation systems, project expertise in the field of rehabilitation of PVC including the management of SNF and RW Implementation of these natural, practical and theoretical works is completed by development a set of regulatory documents ensuring adherence to radiation safety for the stuff population and the environment, and the also documents governing the management of SNF and RW waste in the territories of PVC.

  10. Measurements of Fundamental Fluid Physics of SNF Storage Canisters

    Energy Technology Data Exchange (ETDEWEB)

    Condie, Keith Glenn; Mc Creery, Glenn Ernest; McEligot, Donald Marinus

    2001-09-01

    With the University of Idaho, Ohio State University and Clarksean Associates, this research program has the long-term goal to develop reliable predictive techniques for the energy, mass and momentum transfer plus chemical reactions in drying / passivation (surface oxidation) operations in the transfer and storage of spent nuclear fuel (SNF) from wet to dry storage. Such techniques are needed to assist in design of future transfer and storage systems, prediction of the performance of existing and proposed systems and safety (re)evaluation of systems as necessary at later dates. Many fuel element geometries and configurations are accommodated in the storage of spent nuclear fuel. Consequently, there is no one generic fuel element / assembly, storage basket or canister and, therefore, no single generic fuel storage configuration. One can, however, identify generic flow phenomena or processes which may be present during drying or passivation in SNF canisters. The objective of the INEEL tasks was to obtain fundamental measurements of these flow processes in appropriate parameter ranges.

  11. A contingency safe, responsible, economic, increased capacity spent nuclear fuel (SNF) advance fuel cycle

    International Nuclear Information System (INIS)

    Levy, S.

    2008-01-01

    The purpose of this paper is to have an Advanced Light Water (LWR) fuel cycle and an associated development program to provide a contingency plan to the current DOE effort to license once-through spent Light Water Reactor (LWR) fuel for disposition at Yucca Mountain (YM). The intent is to fully support the forthcoming June 2008 DOE submittal to the Nuclear Regulatory Commission (NRC) based upon the latest DOE draft DOE/EIS-0250F-SID dated October 2007 which shows that the latest DOE YM doses would readily satisfy the anticipated NRC and Environmental Protection Agency (EP) standards. The proposed Advance Fuel Cycle can offer potential resolution of obstacles that might arise during the NRC review and, particularly, during the final hearings process to be held in Nevada. Another reason for the proposed concept is that a substantial capacity growth of the YM repository will be necessary to accommodate the SNF of Advance Light Water Reactors (ALWRs) currently under consideration for United States (U.S.) electricity production (1) and the results of the recently issued study by the Electric Power Research Institute (EPRI) to reduce CO 2 emissions (2). That study predicts that by 2030 U.S. nuclear power generation would grow by 64 Gigawatt electrical (GWe) and account for 25.5 percent of the overall U.S. electrical generation. The current annual SNF once-through fuel cycle accumulation would rise from 2000-2100 MT (Metric Tons) to about 3480 MT in 2030 and the total SNF inventory, would reach nearly 500,000 MT by 2100 if U. S. nuclear power continues to grow at 1.1 percent per year after 2030. That last projection does not account for any SNF reduction due to increased fuel burnup or any increased capacity needed 'to establish supply Global Nuclear Energy Partnership (GNEP,) arrangements among nations to provide nuclear fuel and taking back spent fuel for recycling without spreading enrichment and reprocessing technologies' (3). The anticipated capacity of 120 MT

  12. Sp1 and CREB regulate basal transcription of the human SNF2L gene

    International Nuclear Information System (INIS)

    Xia Yu; Jiang Baichun; Zou Yongxin; Gao Guimin; Shang Linshan; Chen Bingxi; Liu Qiji; Gong Yaoqin

    2008-01-01

    Imitation Switch (ISWI) is a member of the SWI2/SNF2 superfamily of ATP-dependent chromatin remodelers, which are involved in multiple nuclear functions, including transcriptional regulation, replication, and chromatin assembly. Mammalian genomes encode two ISWI orthologs, SNF2H and SNF2L. In order to clarify the molecular mechanisms governing the expression of human SNF2L gene, we functionally examined the transcriptional regulation of human SNF2L promoter. Reporter gene assays demonstrated that the minimal SNF2L promoter was located between positions -152 to -86 relative to the transcription start site. In this region we have identified a cAMP-response element (CRE) located at -99 to -92 and a Sp1-binding site at -145 to -135 that play a critical role in regulating basal activity of human SNF2L gene, which were proven by deletion and mutation of specific binding sites, EMSA, and down-regulating Sp1 and CREB via RNAi. This study provides the first insight into the mechanisms that control basal expression of human SNF2L gene

  13. Trehalose-6-phosphate synthesis controls yeast gluconeogenesis downstream and independent of SNF1.

    Science.gov (United States)

    Deroover, Sofie; Ghillebert, Ruben; Broeckx, Tom; Winderickx, Joris; Rolland, Filip

    2016-06-01

    Trehalose-6-P (T6P), an intermediate of trehalose biosynthesis, was identified as an important regulator of yeast sugar metabolism and signaling. tps1Δ mutants, deficient in T6P synthesis (TPS), are unable to grow on rapidly fermentable medium with uncontrolled influx in glycolysis, depletion of ATP and accumulation of sugar phosphates. However, the exact molecular mechanisms involved are not fully understood. We show that SNF1 deletion restores the tps1Δ growth defect on glucose, suggesting that lack of TPS hampers inactivation of SNF1 or SNF1-regulated processes. In addition to alternative, non-fermentable carbon metabolism, SNF1 controls two major processes: respiration and gluconeogenesis. The tps1Δ defect appears to be specifically associated with deficient inhibition of gluconeogenesis, indicating more downstream effects. Consistently, Snf1 dephosphorylation and inactivation on glucose medium are not affected, as confirmed with an in vivo Snf1 activity reporter. Detailed analysis shows that gluconeogenic Pck1 and Fbp1 expression, protein levels and activity are not repressed upon glucose addition to tps1Δ cells, suggesting a link between the metabolic defect and persistent gluconeogenesis. While SNF1 is essential for induction of gluconeogenesis, T6P/TPS is required for inactivation of gluconeogenesis in the presence of glucose, downstream and independent of SNF1 activity and the Cat8 and Sip4 transcription factors. © FEMS 2016. All rights reserved. For permissions, please e-mail: journals.permissions@oup.com.

  14. Human error prediction and countermeasures based on CREAM in spent nuclear fuel (SNF) transportation

    International Nuclear Information System (INIS)

    Kim, Jae San

    2007-02-01

    Since the 1980s, in order to secure the storage capacity of spent nuclear fuel (SNF) at NPPs, SNF assemblies have been transported on-site from one unit to another unit nearby. However in the future the amount of the spent fuel will approach capacity in the areas used, and some of these SNFs will have to be transported to an off-site spent fuel repository. Most SNF materials used at NPPs will be transported by general cargo ships from abroad, and these SNFs will be stored in an interim storage facility. In the process of transporting SNF, human interactions will involve inspecting and preparing the cask and spent fuel, loading the cask onto the vehicle or ship, transferring the cask as well as storage or monitoring the cask. The transportation of SNF involves a number of activities that depend on reliable human performance. In the case of the transport of a cask, human errors may include spent fuel bundle misidentification or cask transport accidents among others. Reviews of accident events when transporting the Radioactive Material (RAM) throughout the world indicate that human error is the major causes for more than 65% of significant events. For the safety of SNF transportation, it is very important to predict human error and to deduce a method that minimizes the human error. This study examines the human factor effects on the safety of transporting spent nuclear fuel (SNF). It predicts and identifies the possible human errors in the SNF transport process (loading, transfer and storage of the SNF). After evaluating the human error mode in each transport process, countermeasures to minimize the human error are deduced. The human errors in SNF transportation were analyzed using Hollnagel's Cognitive Reliability and Error Analysis Method (CREAM). After determining the important factors for each process, countermeasures to minimize human error are provided in three parts: System design, Operational environment, and Human ability

  15. Co-evolution of SNF spliceosomal proteins with their RNA targets in trans-splicing nematodes.

    Science.gov (United States)

    Strange, Rex Meade; Russelburg, L Peyton; Delaney, Kimberly J

    2016-08-01

    Although the mechanism of pre-mRNA splicing has been well characterized, the evolution of spliceosomal proteins is poorly understood. The U1A/U2B″/SNF family (hereafter referred to as the SNF family) of RNA binding spliceosomal proteins participates in both the U1 and U2 small interacting nuclear ribonucleoproteins (snRNPs). The highly constrained nature of this system has inhibited an analysis of co-evolutionary trends between the proteins and their RNA binding targets. Here we report accelerated sequence evolution in the SNF protein family in Phylum Nematoda, which has allowed an analysis of protein:RNA co-evolution. In a comparison of SNF genes from ecdysozoan species, we found a correlation between trans-splicing species (nematodes) and increased phylogenetic branch lengths of the SNF protein family, with respect to their sister clade Arthropoda. In particular, we found that nematodes (~70-80 % of pre-mRNAs are trans-spliced) have experienced higher rates of SNF sequence evolution than arthropods (predominantly cis-spliced) at both the nucleotide and amino acid levels. Interestingly, this increased evolutionary rate correlates with the reliance on trans-splicing by nematodes, which would alter the role of the SNF family of spliceosomal proteins. We mapped amino acid substitutions to functionally important regions of the SNF protein, specifically to sites that are predicted to disrupt protein:RNA and protein:protein interactions. Finally, we investigated SNF's RNA targets: the U1 and U2 snRNAs. Both are more divergent in nematodes than arthropods, suggesting the RNAs have co-evolved with SNF in order to maintain the necessarily high affinity interaction that has been characterized in other species.

  16. Reconstruction of the yeast Snf1 kinase regulatory network reveals its role as a global energy regulator

    Science.gov (United States)

    Usaite, Renata; Jewett, Michael C; Oliveira, Ana Paula; Yates, John R; Olsson, Lisbeth; Nielsen, Jens

    2009-01-01

    Highly conserved among eukaryotic cells, the AMP-activated kinase (AMPK) is a central regulator of carbon metabolism. To map the complete network of interactions around AMPK in yeast (Snf1) and to evaluate the role of its regulatory subunit Snf4, we measured global mRNA, protein and metabolite levels in wild type, Δsnf1, Δsnf4, and Δsnfsnf4 knockout strains. Using four newly developed computational tools, including novel DOGMA sub-network analysis, we showed the benefits of three-level ome-data integration to uncover the global Snf1 kinase role in yeast. We for the first time identified Snf1's global regulation on gene and protein expression levels, and showed that yeast Snf1 has a far more extensive function in controlling energy metabolism than reported earlier. Additionally, we identified complementary roles of Snf1 and Snf4. Similar to the function of AMPK in humans, our findings showed that Snf1 is a low-energy checkpoint and that yeast can be used more extensively as a model system for studying the molecular mechanisms underlying the global regulation of AMPK in mammals, failure of which leads to metabolic diseases. PMID:19888214

  17. Radiation protection planning for the international FAIR project

    International Nuclear Information System (INIS)

    Fehrenbacher, G.; Belousov, A.; Conrad, I.

    2015-01-01

    FAIR (=Facility for AntiProton and Ion Research) is an international accelerator facility which will be built near the GSI site in Darmstadt, where protons and heavy ion beams can be accelerated in a synchrotron to energies up to 30 GeV/nucleon with intensities partially up to 1E13/sec. The accelerated particles will be used for experiments in atomic, nuclear and plasma physics as well as for radiation biology and medicine and materials research. The radiation protection planning focuses on the estimation of radiation fields produced by heavy ions and its shielding. As examples, the radiation protection planning for the heavy ion synchrotron SIS100 as well as for two experiment caves are presented. Moreover, further important topics in this radiation protection planning are the estimation of the distribution and production of radionuclides in media and the handling before disposal.

  18. Spent nuclear fuel project technical databook

    International Nuclear Information System (INIS)

    Reilly, M.A.

    1998-01-01

    The Spent Nuclear Fuel (SNF) project technical databook provides project-approved summary tables of selected parameters and derived physical quantities, with nominal design and safety basis values. It contains the parameters necessary for a complete documentation basis of the SNF Project technical and safety baseline. The databook is presented in two volumes. Volume 1 presents K Basins SNF related information. Volume 2 (not yet available) will present selected sludge and water information, as it relates to the sludge and water removal projects. The values, within this databook, shall be used as the foundation for analyses, modeling, assumptions, or other input to SNF project safety analyses or design. All analysis and modeling using a parameter available in this databook are required to use and cite the appropriate associated value, and document any changes to those values (i.e., analysis assumptions, equipment conditions, etc). Characterization and analysis efforts are ongoing to validate, or update these values

  19. Spent nuclear fuel project technical databook

    Energy Technology Data Exchange (ETDEWEB)

    Reilly, M.A.

    1998-07-22

    The Spent Nuclear Fuel (SNF) project technical databook provides project-approved summary tables of selected parameters and derived physical quantities, with nominal design and safety basis values. It contains the parameters necessary for a complete documentation basis of the SNF Project technical and safety baseline. The databook is presented in two volumes. Volume 1 presents K Basins SNF related information. Volume 2 (not yet available) will present selected sludge and water information, as it relates to the sludge and water removal projects. The values, within this databook, shall be used as the foundation for analyses, modeling, assumptions, or other input to SNF project safety analyses or design. All analysis and modeling using a parameter available in this databook are required to use and cite the appropriate associated value, and document any changes to those values (i.e., analysis assumptions, equipment conditions, etc). Characterization and analysis efforts are ongoing to validate, or update these values.

  20. SNF Interim Storage Canister Corrosion and Surface Environment Investigations

    International Nuclear Information System (INIS)

    Bryan, Charles R.; Enos, David G.

    2015-01-01

    This progress report describes work being done at Sandia National Laboratories (SNL) to assess the localized corrosion performance of container/cask materials used in the interim storage of spent nuclear fuel (SNF). Of particular concern is stress corrosion cracking (SCC), by which a through-wall crack could potentially form in a canister outer wall over time intervals that are shorter than possible dry storage times. In order for SCC to occur, three criteria must be met. A corrosive environment must be present on the canister surface, the metal must susceptible to SCC, and sufficient tensile stress to support SCC must be present through the entire thickness of the canister wall. SNL is currently evaluating the potential for each of these criteria to be met.

  1. SNF Interim Storage Canister Corrosion and Surface Environment Investigations

    Energy Technology Data Exchange (ETDEWEB)

    Bryan, Charles R. [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States); Enos, David G. [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States)

    2015-09-01

    This progress report describes work being done at Sandia National Laboratories (SNL) to assess the localized corrosion performance of container/cask materials used in the interim storage of spent nuclear fuel (SNF). Of particular concern is stress corrosion cracking (SCC), by which a through-wall crack could potentially form in a canister outer wall over time intervals that are shorter than possible dry storage times. In order for SCC to occur, three criteria must be met. A corrosive environment must be present on the canister surface, the metal must susceptible to SCC, and sufficient tensile stress to support SCC must be present through the entire thickness of the canister wall. SNL is currently evaluating the potential for each of these criteria to be met.

  2. Potential dispositioning flowsheets for ICPP SNF and wastes

    Energy Technology Data Exchange (ETDEWEB)

    Olson, A.L. [ed.; Anderson, P.A.; Bendixsen, C.L. [and others

    1995-11-01

    The Idaho Chemical Processing Plant (ICPP), located at the Idaho National Laboratory (INEL), has reprocessed irradiated nuclear fuels for the US Department of Energy (DOE) since 1953. This activity resulted mainly in the recovery of uranium and the management of the resulting wastes. The acidic radioactive high-level liquid waste was routinely stored in stainless steel tanks and then calcined to form a dry granular solid. The calcine is stored in stainless steel bins that are housed in underground concrete vaults. In April 1992, the DOE discontinued the practice of reprocessing irradiated nuclear fuels. This decision has left a legacy of 1.8 million gallons of radioactive liquid wastes (1.5 million gallons of radioactive sodium-bearing liquid wastes and 0.3 million gallons of high-level liquid waste), 3800 cubic meters of calcine waste, and 289 metric tons of heavy metal within unprocessed spent nuclear fuel (SNF) left in inventory at the ICPP. The nation`s radioactive waste policy has been established by the Nuclear Waste Policy Act (NWPA), which requires the final disposal of SNF and radioactive waste in accordance with US Environmental Protection Agency (EPA) and Nuclear Regulatory Commission (NRC) standards. In accordance with these regulations and other legal agreements between the State of Idaho and the DOE, the DOE must, among other requirements, (1) complete a final Environmental Impact Statement by April 30, 1995, (2) evaluate and test sodium-bearing waste pre-treatment technologies, (3) select the sodium-bearing and calcine waste pre-treatment technology, if necessary, by June 1, 1995, and (4) select a technology for converting calcined waste into an appropriate disposal form by June 1, 1995.

  3. Potential dispositioning flowsheets for ICPP SNF and wastes

    International Nuclear Information System (INIS)

    Olson, A.L.; Anderson, P.A.; Bendixsen, C.L.

    1995-11-01

    The Idaho Chemical Processing Plant (ICPP), located at the Idaho National Laboratory (INEL), has reprocessed irradiated nuclear fuels for the US Department of Energy (DOE) since 1953. This activity resulted mainly in the recovery of uranium and the management of the resulting wastes. The acidic radioactive high-level liquid waste was routinely stored in stainless steel tanks and then calcined to form a dry granular solid. The calcine is stored in stainless steel bins that are housed in underground concrete vaults. In April 1992, the DOE discontinued the practice of reprocessing irradiated nuclear fuels. This decision has left a legacy of 1.8 million gallons of radioactive liquid wastes (1.5 million gallons of radioactive sodium-bearing liquid wastes and 0.3 million gallons of high-level liquid waste), 3800 cubic meters of calcine waste, and 289 metric tons of heavy metal within unprocessed spent nuclear fuel (SNF) left in inventory at the ICPP. The nation's radioactive waste policy has been established by the Nuclear Waste Policy Act (NWPA), which requires the final disposal of SNF and radioactive waste in accordance with US Environmental Protection Agency (EPA) and Nuclear Regulatory Commission (NRC) standards. In accordance with these regulations and other legal agreements between the State of Idaho and the DOE, the DOE must, among other requirements, (1) complete a final Environmental Impact Statement by April 30, 1995, (2) evaluate and test sodium-bearing waste pre-treatment technologies, (3) select the sodium-bearing and calcine waste pre-treatment technology, if necessary, by June 1, 1995, and (4) select a technology for converting calcined waste into an appropriate disposal form by June 1, 1995

  4. Main Principles of the Perspective System of SNF Management in Russia - 13333

    International Nuclear Information System (INIS)

    Baryshnikov, Mikhail

    2013-01-01

    For the last several years the System of the Spent Nuclear Fuel management in Russia was seriously changed. The paper describes the main principles of the changes and the bases of the Perspective System of SNF Management in Russia. Among such the bases there are the theses with the interesting names like 'total knowledge', 'pollutant pays' and 'pay and forget'. There is also a brief description of the modern Russian SNF Management Infrastructure. And an outline of the whole System. The System which is - in case of Russia - is quite necessary to adjust SNF accumulation and to utilize the nuclear heritage. (authors)

  5. Radiation control in the core shroud replacement project of Fukushima-Daiichi NPS Unit no.2

    International Nuclear Information System (INIS)

    Kokubun, Yasunori; Haraguchi, Kazuyuki; Yoshizawa, Yuji; Yamada, Yasuo

    2000-01-01

    In Fukushima-Daiichi NPS Unit no.2, the core shroud replacement was made following that of Unit no.3. This project involves replacement of wide-ranging equipment, with the project extending over a long period of time. This was expected to increase the dose equivalent of workers. Accordingly, various measures to lower the dose equivalent were planned and implemented. We outline radiation controls implemented during the project period. The shroud replacement project was a preventive maintenance project which consisted of replacing the core shroud and other internals with those less susceptible to stress corrosion cracking. Problems related to radiation control during the replacement project of Unit no.3 the year before last were summarized. We studied, planned, and implemented measures to be reflected in the project for Unit no.2. This was done to lower the dose equivalent as much as possible while paying due attention to safety and economy. For radiation control during the project for Unit no.2, experiments with Unit no.3 were fully exploited and any effective measures taken at that time were adopted in this project. Problems pointed out after that project with Unit no.3 resulted in new or improved measures being taken with Unit no.2. Measures taken over from the project with Unit no.3; a. Daily analysis of difference between expected and actual dose equivalents b. Dose reduction measures, chemical decontamination, temporary shield, flushing, etc.; New or improved measures; a. Dose reduction measures: Mechanical removal of radiation sources, strengthening of shield, etc.; b. Automatic remote control system; c. Use of new protective devices. With measures implemented as described above, the dose equivalent during shroud replacement of Unit no.2 was reduced by about 30% when compared with that (11.5 persons · Sv) in the case of Unit no.3. Implemented radiation controls will be checked and reviewed in future for reflection in projects with other units. (author)

  6. Combined equations for estimating global solar radiation: Projection of radiation field over Japan under global warming conditions by statistical downscaling

    International Nuclear Information System (INIS)

    Iizumi, T.; Nishimori, M.; Yokozawa, M.

    2008-01-01

    For this study, we developed a new statistical model to estimate the daily accumulated global solar radiation on the earth's surface and used the model to generate a high-resolution climate change scenario of the radiation field in Japan. The statistical model mainly relies on precipitable water vapor calculated from air temperature and relative humidity on the surface to estimate seasonal changes in global solar radiation. On the other hand, to estimate daily radiation fluctuations, the model uses either a diurnal temperature range or relative humidity. The diurnal temperature range, calculated from the daily maximum and minimum temperatures, and relative humidity is a general output of most climate models, and pertinent observation data are comparatively easy to access. The statistical model performed well when estimating the monthly mean value, daily fluctuation statistics, and regional differences in the radiation field in Japan. To project the change in the radiation field for the years 2081 to 2100, we applied the statistical model to the climate change scenario of a high-resolution Regional Climate Model with a 20-km mesh size (RCM20) developed at the Meteorological Research Institute based on the Special Report for Emission Scenario (SRES)-A2. The projected change shows the following tendency: global solar radiation will increase in the warm season and decrease in the cool season in many areas of Japan, indicating that global warming may cause changes in the radiation field in Japan. The generated climate change scenario for the radiation field is linked to long-term and short-term changes in air temperature and relative humidity obtained from the RCM20 and, consequently, is expected to complement the RCM20 datasets for an impact assessment study in the agricultural sector

  7. The Pocketable Electronic Devices in Radiation Oncology (PEDRO) Project

    DEFF Research Database (Denmark)

    De Bari, Berardino; Franco, P.; Niyazi, Maximilian

    2016-01-01

    ) members of the national radiation or clinical oncology associations of the countries involved in the study. The 15 items investigated diffusion of MEDs (smartphones and/or tablets), their impact on daily clinical activity, and the differences perceived by participants along time. Results: A total of 386...... in young professionals working in radiation oncology. Looking at these data, it is important to verify the consistency of information found within apps, in order to avoid potential errors eventually detrimental for patients. “Quality assurance” criteria should be specifically developed for medical apps...

  8. Hermite- Padé projection to thermal radiative and variable ...

    African Journals Online (AJOL)

    The combined effect of variable thermal conductivity and radiative heat transfer on steady flow of a conducting optically thin viscous fluid through a channel with sliding wall and non-uniform wall temperatures under the influence of an externally applied homogeneous magnetic field are analyzed in the present study.

  9. Channeling-radiation project for Department of Energy

    International Nuclear Information System (INIS)

    Marshall, Paul

    1999-01-01

    To demonstrate the feasibility of producing and utilizing a channeling-radiation beam at a typical medical electron accelerator. The experiment consisted of two distinct stages, designing and assembling an extension to the existing beam line and running the experiment using silicon and diamond crystals

  10. SERI Solar Radiation Resource Assessment Project: Fiscal Year 1990 Annual Progress Report

    Energy Technology Data Exchange (ETDEWEB)

    Riordan, C; Maxwell, E; Stoffel, T; Rymes, M; Wilcox, S

    1991-07-01

    The purpose of the Solar Radiation Resource Project is to help meet the needs of the public, government, industry, and utilities for solar radiation data, models, and assessments as required to develop, design, deploy, and operate solar energy conversion systems. The project scientists produce information on the spatial (geographic), temporal (hourly, daily, and seasonal), and spectral (wavelength distribution) variability of solar radiation at different locations in the United States. Resources committed to the project in FY 1990 supported about four staff members, including part-time administrative support. With these resources, the staff must concentrate on solar radiation resource assessment in the United States; funds do not allow for significant efforts to respond to a common need for improved worldwide data. 34 refs., 21 figs., 6 tabs.

  11. European dimension of the implementation of the IAEA TC model project 'Upgrading radiation protection infrastructure'

    International Nuclear Information System (INIS)

    Sabol, J.

    2001-01-01

    A comprehensive evaluation carried out by the IAEA during the period 1984-1995 showed that eleven countries in Europe -- Albania, Armenia, Belarus, Bosnia and Herzegovina, Cyprus, Estonia, Georgia, Latvia, Lithuania, the Republic of Moldova, The Former Yugoslav Republic (TFYR) of Macedonia -- did not have a satisfactory system for radiation protection and the safety of radiation sources in accordance with the recommended international requirements. During the past four years, these countries have been participating in a Model Project aimed at upgrading radiation protection infrastructure in the Europe region with special emphasis on the establishment of an effective legal framework for adequate regulatory control of radiation sources and facilities. This paper analyses the results accomplished in the implementation of this project. It presents the main objectives, based on the present achievements for a follow-up programme to be carried out in participating and also in some other Member States with insufficient national infrastructures for assuring adequate safety in nuclear and radiation technologies. (author)

  12. A biotechnological project with a gamma radiation source of 100,000 Ci

    International Nuclear Information System (INIS)

    Lombardo, J.H.; Smolko, E.E.

    1990-01-01

    A project for the production of radiovaccines and other bio-medical products is presented which includes a radiation facility provided with a gamma ray source equivalent to 100,000 Ci of Co-60. The whole process incorporates novel basic features in virus production and inactivation steps. The former is carried out in animals previously subjected to immunodepression through electromagnetic radiation. The latter is obtained at low temperatures by using either electromagnetic or particle radiations. A vaccine manufacture process is shown to illustrate the utilization of ionizing radiations to obtain a foot and mouth disease virus (FMDV) vaccine with good antigenic quality and low cost. (author)

  13. The application and development on radiation monitoring microcomputer management system in design of a certain project

    International Nuclear Information System (INIS)

    Zhang Hongyou

    1993-01-01

    A scheme of a radiation monitoring system with a RMMMS (Radiation Monitoring Microcomputer Management System) has been designed for the first time in the radiation protection design of a certain nuclear projection undertaken by the BINE (Beijing Institute of Nuclear Engineering). Meanwhile, we accepted the research task of the RMMMS that can manage 40 monitoring channel. The key factors of radiation monitors, microcomputer, information management and systematic design method are considered in the development of the RMMMS. This paper presents briefly the scheme and functions of the RMMMS

  14. Technical, economical and legal aspects of repatriation of Russian-origin research reactor SNF to Russia

    International Nuclear Information System (INIS)

    Smirnov, A.; Kanashov, B.; Efarov, S.; Lebedev, A.; Kolupaev, D.

    2005-01-01

    The aim of the report is to find some principal decisions to implement an Agreement between the Governments of the Russian Federation and the USA on repatriation of the research reactor spent nuclear fuel (RR SNF) to the Russian Federation. The report presents some ideas and approaches to the transportation of the Russian-origin RR SNF from the technical, economical and legal viewpoints. The report summarizes the Russian experience and possibilities to fulfill the program under the Agreement. Some decisions are proposed related to application of the international transportation experience and the most advanced technologies for the RR SNF handling. At present, there is no any unified SNF transportation technology that is capable to implement the transportation program schedule set by the Agreement. The decision is in the comprehensive approach as well as in the development of mobile and flexible schemes and in implementation of parallel and combined shipments. (author)

  15. An assessment of KW Basin radionuclide activity when opening SNF canisters

    International Nuclear Information System (INIS)

    Bergmann, D.W.; Mollerus, F.J.; Wray, J.L.

    1995-01-01

    N Reactor spent fuel is being stored in sealed canisters in the KW Basin. Some of the canisters contain damaged fuel elements. There is the potential for release of Cs 137, Kr 85, H3, and other fission products and transuranics (TRUs) when canisters are opened. Canister opening is required to select and transfer fuel elements to the 300 Area for examination as part of the Spent Nuclear Fuel (SNF) Characterization program. This report estimates the amount of radionuclides that can be released from Mark II spent nuclear fuel (SNF) canisters in KW Basin when canisters are opened for SNF fuel sampling as part of the SNF Characterization Program. The report also assesses the dose consequences of the releases and steps that can be taken to reduce the impacts of these releases

  16. Evaluation of Test Methodologies for Dissolution and Corrosion of Al-SNF

    International Nuclear Information System (INIS)

    Wiersma, B.J.; Mickalonis, J.I.; Louthan, M.R.

    1998-09-01

    The performance of aluminum-based spent nuclear fuel (Al-SNF) in the repository will differ from that of the commercial nuclear fuels and the high level waste glasses. The program consists of evaluating three test methods

  17. Role and future subjects of support project 'research activity on radiation etc. by high school students'

    International Nuclear Information System (INIS)

    Iimoto, Takeshi; Fujimoto, Noboru; Nakamura, Takashi

    2014-01-01

    This is a report of the project of MEXT(The Ministry of Education, Culture, Sports, Science and Technology) to support high school students researching radiation etc. This subject research consists of an exchange meeting, independence research, and a presentation meeting of the results. Media introduced the project and this was a very reputable project. However, regrettably this support project was broken off in the business year of 2012. In this document, the outline of the support project for seven years is introduced and the possibility of future deployment is discussed. (author)

  18. Legal precedents regarding use and defensibility of risk assessment in Federal transportation of SNF and HLW

    International Nuclear Information System (INIS)

    Bentz, E.J. Jr.; Bentz, C.B.; O'Hora, T.D.; Chen, S.Y.

    1997-01-01

    Risk assessment has become an increasingly important and essential tool in support of Federal decision-making regarding the handling, storage, disposal, and transportation of spent nuclear fuel (SNF) and high-level radioactive waste (HLW). This paper analyzes the current statutory and regulatory framework and related legal precedents with regard to SNF and HLW transportation. The authors identify key scientific and technical issues regarding the use and defensibility of risk assessment in Federal decision-making regarding anticipated shipments

  19. Enhanced amino acid utilization sustains growth of cells lacking Snf1/AMPK

    DEFF Research Database (Denmark)

    Nicastro, Raffaele; Tripodi, Farida; Guzzi, Cinzia

    2015-01-01

    when grown with glucose excess. We show that loss of Snf1 in cells growing in 2% glucose induces an extensive transcriptional reprogramming, enhances glycolytic activity, fatty acid accumulation and reliance on amino acid utilization for growth. Strikingly, we demonstrate that Snf1/AMPK-deficient cells...... remodel their metabolism fueling mitochondria and show glucose and amino acids addiction, a typical hallmark of cancer cells....

  20. Role of Snf3 in glucose homeostasis of Saccharomyces cerevisiae (review)

    DEFF Research Database (Denmark)

    Kielland-Brandt, Morten

    signal pathways in directions opposite to those caused by extracellular nutrients (6,7), a phenomenon predicted to contribute to intracellular nutrient homeostasis. Although significant, the influence of intracellular leucine on signaling from Ssy1 is relatively modest (6), whereas the conditions...... with enhanced intracellular glucose concentrations (7) caused a strong decrease in signaling from Snf3, suggesting an important role of Snf3 in intracellular glucose homeostasis. Strategies for studies of this role will be discussed....

  1. Complexon Solutions in Freon for Decontamination of Solids and SNF Treatment

    International Nuclear Information System (INIS)

    Kamachev, V.; Shadrin, A.; Murzin, A.

    2008-01-01

    Full text of publication follows: The possibility of using complexon solutions in supercritical and compressed carbon dioxide for decontamination of solid surfaces and for spent nuclear fuel (SNF) treatment was demonstrated in the works of Japanese, Russian and American researchers. The obtained data showed that the use of complexon solutions in carbon dioxide sharply decreases the volume of secondary radioactive wastes because it can be easily evaporated, purified and recycled. Moreover, high penetrability of carbon dioxide allows decontamination of surfaces with complex shape. However, one of the disadvantages of carbon dioxide is its high working pressure (10-20 MPa for supercritical CO 2 and 7 MPa for compressed CO 2 ). Moreover, in case of SNF treatment, carbon dioxide solvent will be contaminated with 14 C, which in the course of SNF dissolution in CO 2 containing TBP*HNO 3 adduct stage will be oxidized into CO 2 . These main disadvantages can be eliminated by using complexon solutions in ozone-friendly Freon HFC-134a for decontamination and SNF treatment. Our experimental data for real contaminated materials showed that the decontamination factor for complexon solutions in liquid Freon HFC-134a at 1,2 MPa and 25 deg. C is close to that attained in carbon dioxide. Moreover, the possibility of SNF treatment in Freon HFC-134a was demonstrated in trials using real SNF and its imitators. (authors)

  2. Scientific projection paper on biologic effects of ionizing radiation

    International Nuclear Information System (INIS)

    Matanoski, G.

    1980-01-01

    There is widespread knowledge about the effects of radiation in human populations but the studies have had some limitations which have left gaps in our knowledge. Most populations have had exposure to high doses with little information on the effect of dose rate. The characteristics of the populations have been restricted by the location of the disaster, the occupational limitations, or the basic risks associated with the under-lying disease for which radiation was given. All doses have been estimated and such values are subject to marked variability particularly when they rely on sources of data such as hospital records. The biological data although extensive have several deficits in information. Which are the sites in which cancer is produced by irradiation and what are the cell types which are produced. The sensitivity of various tissues and organs are not similar and it is important to rank them according to susceptibility. This has been done in the past but the results are not complete for all cell types and organs. The temporal patterns for tumor development, the latent period, the period of expressed excess, the life-time risks need to be defined more precisely for the cancers. Many populations have not been followed long enough to express the complete risk

  3. Project SIMORAC: a wireless system for radiation monitoring in emergencies

    International Nuclear Information System (INIS)

    Gomez, D.; Serrano, J. L.; Cabrera, E.; Barbaran, J.; Llopis, L.; Diaz, M.

    2013-01-01

    The SIMORAC project includes a new system for Radiological monitoring using wireless sensor networks (RSIs), without infrastructure planning in emergency situations for a rapidly deployable by air or land, with the aim of providing a tool emergency teams capable of offering a real time x-ray map within the radius of action of an accident. Communication of quality at a great distance, resistance to weather, long autonomy and possibility of aerial deployment are some of the features of SIMORAC.

  4. Proceedings of the public meeting to address a proposed federal radiation research agenda. Volume 2. Science projection papers

    International Nuclear Information System (INIS)

    1980-03-01

    Separate abstracts were prepared for the 14 science projection papers presented at a public meeting on March 10-11, 1980 to address a proposed federal radiation research agenda into the biological effects of ionizing radiation

  5. IPRT polarized radiative transfer model intercomparison project - Three-dimensional test cases (phase B)

    Science.gov (United States)

    Emde, Claudia; Barlakas, Vasileios; Cornet, Céline; Evans, Frank; Wang, Zhen; Labonotte, Laurent C.; Macke, Andreas; Mayer, Bernhard; Wendisch, Manfred

    2018-04-01

    Initially unpolarized solar radiation becomes polarized by scattering in the Earth's atmosphere. In particular molecular scattering (Rayleigh scattering) polarizes electromagnetic radiation, but also scattering of radiation at aerosols, cloud droplets (Mie scattering) and ice crystals polarizes. Each atmospheric constituent produces a characteristic polarization signal, thus spectro-polarimetric measurements are frequently employed for remote sensing of aerosol and cloud properties. Retrieval algorithms require efficient radiative transfer models. Usually, these apply the plane-parallel approximation (PPA), assuming that the atmosphere consists of horizontally homogeneous layers. This allows to solve the vector radiative transfer equation (VRTE) efficiently. For remote sensing applications, the radiance is considered constant over the instantaneous field-of-view of the instrument and each sensor element is treated independently in plane-parallel approximation, neglecting horizontal radiation transport between adjacent pixels (Independent Pixel Approximation, IPA). In order to estimate the errors due to the IPA approximation, three-dimensional (3D) vector radiative transfer models are required. So far, only a few such models exist. Therefore, the International Polarized Radiative Transfer (IPRT) working group of the International Radiation Commission (IRC) has initiated a model intercomparison project in order to provide benchmark results for polarized radiative transfer. The group has already performed an intercomparison for one-dimensional (1D) multi-layer test cases [phase A, 1]. This paper presents the continuation of the intercomparison project (phase B) for 2D and 3D test cases: a step cloud, a cubic cloud, and a more realistic scenario including a 3D cloud field generated by a Large Eddy Simulation (LES) model and typical background aerosols. The commonly established benchmark results for 3D polarized radiative transfer are available at the IPRT website (http

  6. Analysis on environmental impact of radiation from metallurgical project for rare metals

    International Nuclear Information System (INIS)

    Xia Zitong; Zhang Baozeng

    2012-01-01

    Rare metals are the composition of many high-property metal materials, which has a wide range of uses in the field of national defense advanced science technology. Since Ta-Nb material is associated radioactive mineral resources, and it contains high radionuclide, resulting in some radioactive indicators in process and workplace of the Ta-Nb smelting projects were significantly higher than that of the surrounding environmental radiation background. Based on the analysis of Ta-Nb smelting projects, the major sources of pollution were identified. and the possible radiation impact of the project was analyzed and evaluated, corrective measures on the process layout were also proposed, and reasonable suggestions of how to optimize the radiation protection were made. (authors)

  7. ITEM Project: Risk Communication on Exposure to Electromagnetic Radiation from Mobile Communications

    International Nuclear Information System (INIS)

    Oliveira, Carla; Carpinteiro, Goncalo; Correia, Luis M.; Fernandes, Carlos A.; Serralha, Afonso; Marques, Nuno

    2004-01-01

    The ITEM Project is a pioneer project in Portugal, providing public information on exposure to electromagnetic radiation, essentially due to mobile communication systems. The motivation, the main goals and the Project description are presented in this paper, as well as the website that provides the public dissemination of results and further significant information (www.lx.it.pt/item). This site provides information on different issues related to exposure to radiation, namely results of measurement campaigns conducted by a team on several locations in Portugal, and results of continuous measurements performed by autonomous stations located in public places in collaboration with municipal authorities. The global overview of the results from the measurement campaigns carried out up to present shows that all the analysed locations are in compliance with the radiation thresholds, i.e., all the electric field measured values are below the most restrictive threshold established at European level. (author)

  8. Amino acid residues involved in ligand preference of the Snf3 transporter-like sensor in Saccharomyces cerevisiae

    DEFF Research Database (Denmark)

    Dietvorst, J.; Karhumaa, Kaisa; Kielland-Brandt, Morten

    2010-01-01

    /preferences of Snf3. The ability of cells to sense sugars in vivo was monitored by following the degradation of the Mth1 protein, :ill earl., event ill the signal pathway. Our study reveals that Snf3. ill addition to glucose. also senses fructose and mannose, as well as the glucose analogues 2-deoxyglucose, 3-O......-methylglucoside and 6-deoxyglucose. The signalling proficiency of a non-phosphorylatable analogue strongly supports the notion that sensing through Snf3 does not require sugar phosphorylation. Sequence comparisons of Snf3 to glucose transporters indicated amino acid residues possibly involved in sensing of sugars other...... than glucose. By site-specific mutagenesis of the structural gene, roles of specific residues in Snf3 could he established. Change of isoleucine-374 to valine ill transmembrane segment 7 of Snf3 partially abolished sensing of fructose mannose. while mutagenesis causing it change of phenylalanine-462 (4...

  9. INCA project for investigation of primary cosmic radiation spectrum

    International Nuclear Information System (INIS)

    Aleksandrov, K.V.; Erlykin, A.D.; Zhdanov, G.B.

    2002-01-01

    The scientific purposes of the INCA project and application of the ionization-neutron calorimeter for direct measurements of the cosmic rays spectrum and composition in the knee area and the primary electrons spectrum by 10 14 - 10 13 eV are discussed. The new effective method for the primary electrons and protons separation with the complex rejection coefficient of 10 -5 - 10 -6 is proposed for studying the primary electrons spectrum by E e > 1 TeV. The experimental and calculation data are in good agreement [ru

  10. Radiation processing project at the Institute of Nuclear Energy Research

    International Nuclear Information System (INIS)

    Tsai, C.M.; Fu, Y.K.; Yang, Y.H.; Chen, Y.T.; Wei, Y.H.; Lee, K.P.; Wang, Y.K.

    1981-01-01

    The utilization of scientific approach to preserve and sterilize the agricultural products has long been studied since 1954 and was adopted by several countries gradually since 1958. Starting from July 1977 this Institute began to study the preservation of potatoes and onions with reference to sprout inhibition which is discussed and its economical aspect is evaluated. The design concept of a megacurie 60 Co irradiator at this Institute is illustrated. The progress of construction work for the irradiator and the safety device in particular are reported. Current research project on the preservation of agricultural products in this Institute is presented. (author)

  11. Status of burnup credit for transport of SNF in the United States

    International Nuclear Information System (INIS)

    Parks, C.V.; Wagner, J.C.

    2004-01-01

    Allowing credit for the reduction in reactivity associated with fuel depletion can enable more cost-effective, higher-density storage, transportation, and disposal of spent nuclear fuel (SNF) while maintaining a subcritical margin sufficient to establish an adequate safety basis. This paper reviews the current status of burnup credit applied to the design and transport of SNF casks in the United States. The existing U.S. regulatory guidance on burnup credit is limited to pressurized-water-reactor (PWR) fuel and to allowing credit only for actinides in the SNF. By comparing loading curves against actual SNF discharge data for U.S. reactors, the potential benefits that can be realized using the current regulatory guidance with actinide-only burnup credit are illustrated in terms of the inventory allowed in high-capacity casks and the concurrent reduction in SNF shipments. The additional benefits that might be realized by extending burnup credit to credit for select fission products are also illustrated. The curves show that, although fission products in SNF provide a small decrease in reactivity compared with actinides, the additional negative reactivity causes the SNF inventory acceptable for transportation to increase from roughly 30% to approximately 90% when fission products are considered. A savings of approximately $150M in transport costs can potentially be realized for the planned inventory of the repository. Given appropriate experimental data to support code validation, a realistic best-estimate analysis of burnup credit that includes validated credit for fission products is the enhancement that will yield the most significant impact on future transportation plans

  12. Fall 2015 NASA Internship, and Space Radiation Health Project

    Science.gov (United States)

    Patience, Luke

    2015-01-01

    This fall, I was fortunate enough to have been able to participate in an internship at NASA's Lyndon B. Johnson Space Center. I was placed into the Human Health & Performance Directorate, where I was specifically tasked to work with Dr. Zarana Patel, researching the impacts of cosmic level radiation on human cells. Using different laboratory techniques, we were able to examine the cells to see if any damage had been done due to radiation exposure, and if so, how much damage was done. Cell culture samples were exposed at different doses, and fixed at different time points so that we could accumulate a large pool of quantifiable data. After examining quantifiable results relative to the impacts of space radiation on the human body at the cellular and chromosomal level, researchers can defer to different areas of the space program that have to do with astronaut safety, and research and development (extravehicular mobility unit construction, vehicle design and construction, etc.). This experience has been very eye-opening, and I was able to learn quite a bit. I learned some new laboratory techniques, and I did my best to try and learn new ways to balance such a hectic work and school schedule. I also learned some very intimate thing about working at NASA; I learned that far more people want to watch you succeed, rather than watch you fail, and I also learned that this is a place that is alive with innovators and explorers - people who have a sole purpose of exploring space for the betterment of humanity, and not for any other reason. It's truly inspiring. All of these experiences during my internship have impacted me in a really profound way, so much that my educational and career goals are completely different than when I started. I started out as a biotechnology major, and I discovered recently toward the end of the internship, that I don't want to work in a lab, nor was I as enthralled by biological life sciences as a believed myself to be. Taking that all into

  13. Pre operational background radiation monitoring around Kudankulam Nuclear Power Project site - a decade long experience

    International Nuclear Information System (INIS)

    Vijayakumar, B.; George, Thomas; Sundara Rajan, P.; Selvi, B.S.; Balamurugan, M.; Pandit, G.G.; Ravi, P.M.; Tripathi, R.M.

    2014-01-01

    Pre-operational environmental background radiation monitoring around nuclear power plants is very important to understand baseline values existing in the site and also to identify any hot spots of naturally occurring high background radiation areas and their sources. These baseline measurements will act as a benchmark for future comparison after the reactors go into operation. The radiation measurements are continued during the operational phase of the plant and the results are compared to see whether there is any impact of the operation of the plant on the environment. A comprehensive background radiation monitoring plan has been in vogue at site from 2004 to meet this objective. This paper describes the different monitoring strategies adopted around Kudankulam Nuclear Power Project site and throws light on the pre operational background radiation levels in the environment

  14. "Intelligent Ensemble" Projections of Precipitation and Surface Radiation in Support of Agricultural Climate Change Adaptation

    Science.gov (United States)

    Taylor, Patrick C.; Baker, Noel C.

    2015-01-01

    Earth's climate is changing and will continue to change into the foreseeable future. Expected changes in the climatological distribution of precipitation, surface temperature, and surface solar radiation will significantly impact agriculture. Adaptation strategies are, therefore, required to reduce the agricultural impacts of climate change. Climate change projections of precipitation, surface temperature, and surface solar radiation distributions are necessary input for adaption planning studies. These projections are conventionally constructed from an ensemble of climate model simulations (e.g., the Coupled Model Intercomparison Project 5 (CMIP5)) as an equal weighted average, one model one vote. Each climate model, however, represents the array of climate-relevant physical processes with varying degrees of fidelity influencing the projection of individual climate variables differently. Presented here is a new approach, termed the "Intelligent Ensemble, that constructs climate variable projections by weighting each model according to its ability to represent key physical processes, e.g., precipitation probability distribution. This approach provides added value over the equal weighted average method. Physical process metrics applied in the "Intelligent Ensemble" method are created using a combination of NASA and NOAA satellite and surface-based cloud, radiation, temperature, and precipitation data sets. The "Intelligent Ensemble" method is applied to the RCP4.5 and RCP8.5 anthropogenic climate forcing simulations within the CMIP5 archive to develop a set of climate change scenarios for precipitation, temperature, and surface solar radiation in each USDA Farm Resource Region for use in climate change adaptation studies.

  15. Sewage sludge pasteurization by gamma radiation: A Canadian demonstration project — 1988-91

    Science.gov (United States)

    Swinwood, Jean F.; Wilson, Bruce K.

    Nordion International Inc. and a Canadian city, in cooperation with the Federal & Provincial Ministries of the Environment, began a project in 1988 to construct and operate a commercial-scale sewage sludge pasteurization facility using gamma radiation technology. The facility is scheduled to begin operations in 1991. This paper discusses the objectives and scope of the project, the design of the irradiation system, and the plans to market the pasteurized sludge as a high-value, organic soil conditioner and fertilizer.

  16. Wongabel Rhabdovirus Accessory Protein U3 Targets the SWI/SNF Chromatin Remodeling Complex

    Science.gov (United States)

    Joubert, D. Albert; Rodriguez-Andres, Julio; Monaghan, Paul; Cummins, Michelle; McKinstry, William J.; Paradkar, Prasad N.; Moseley, Gregory W.

    2014-01-01

    ABSTRACT Wongabel virus (WONV) is an arthropod-borne rhabdovirus that infects birds. It is one of the growing array of rhabdoviruses with complex genomes that encode multiple accessory proteins of unknown function. In addition to the five canonical rhabdovirus structural protein genes (N, P, M, G, and L), the 13.2-kb negative-sense single-stranded RNA (ssRNA) WONV genome contains five uncharacterized accessory genes, one overlapping the N gene (Nx or U4), three located between the P and M genes (U1 to U3), and a fifth one overlapping the G gene (Gx or U5). Here we show that WONV U3 is expressed during infection in insect and mammalian cells and is required for efficient viral replication. A yeast two-hybrid screen against a mosquito cell cDNA library identified that WONV U3 interacts with the 83-amino-acid (aa) C-terminal domain of SNF5, a component of the SWI/SNF chromatin remodeling complex. The interaction was confirmed by affinity chromatography, and nuclear colocalization was established by confocal microscopy. Gene expression studies showed that SNF5 transcripts are upregulated during infection of mosquito cells with WONV, as well as West Nile virus (Flaviviridae) and bovine ephemeral fever virus (Rhabdoviridae), and that SNF5 knockdown results in increased WONV replication. WONV U3 also inhibits SNF5-regulated expression of the cytokine gene CSF1. The data suggest that WONV U3 targets the SWI/SNF complex to block the host response to infection. IMPORTANCE The rhabdoviruses comprise a large family of RNA viruses infecting plants, vertebrates, and invertebrates. In addition to the major structural proteins (N, P, M, G, and L), many rhabdoviruses encode a diverse array of accessory proteins of largely unknown function. Understanding the role of these proteins may reveal much about host-pathogen interactions in infected cells. Here we examine accessory protein U3 of Wongabel virus, an arthropod-borne rhabdovirus that infects birds. We show that U3 enters the

  17. Debris Removal Project K West Canister Cleaning System Performance Specification

    International Nuclear Information System (INIS)

    FARWICK, C.C.

    1999-01-01

    Approximately 2,300 metric tons Spent Nuclear Fuel (SNF) are currently stored within two water filled pools, the 105 K East (KE) fuel storage basin and the 105 K West (KW) fuel storage basin, at the U.S. Department of Energy, Richland Operations Office (RL). The SNF Project is responsible for operation of the K Basins and for the materials within them. A subproject to the SNF Project is the Debris Removal Subproject, which is responsible for removal of empty canisters and lids from the basins. Design criteria for a Canister Cleaning System to be installed in the KW Basin. This documents the requirements for design and installation of the system

  18. The Bridge Project: improving heart failure care in skilled nursing facilities.

    Science.gov (United States)

    Boxer, Rebecca S; Dolansky, Mary A; Frantz, Megan A; Prosser, Regina; Hitch, Jeanne A; Piña, Ileana L

    2012-01-01

    Rehospitalization rates and transitions of care for patients with heart failure (HF) continue to be of prominent importance for hospital systems around the United States. Skilled nursing facilities (SNF) are pivotal sites for transition especially for older adults. The purpose of this study was to evaluate in SNF both the (1) current state of HF management (HF admissions, protocols, and staff knowledge) and (2) the acceptability and effect of a HF staff educational program. Four SNF participated in the project, 2 the first year and 2 the second year. SNF were surveyed by discipline as to HF disease management techniques. Staff were evaluated on HF knowledge and confidence in pre- and post-HF disease management training. All-cause rehospitalization rates ranged from 18% to 43% in the 2 SNF evaluated. Overall, there was a lack of identification and tracking of HF patients in all the SNF. There were no HF-specific disease management protocols at any SNF and staff had limited knowledge of HF care. Staff pre and post test scores indicated an improvement in both staff knowledge and confidence in HF management after receiving training. The lack of identification and tracking of patients with HF limits SNF ability to care for patients with HF. HF education for staff is likely important to effective HF management in the SNF. Copyright © 2012 American Medical Directors Association, Inc. Published by Elsevier Inc. All rights reserved.

  19. Extracellular Matrix-Regulated Gene Expression RequiresCooperation of SWI/SNF and Transcription Factors

    Energy Technology Data Exchange (ETDEWEB)

    Xu, Ren; Spencer, Virginia A.; Bissell, Mina J.

    2006-05-25

    Extracellular cues play crucial roles in the transcriptional regulation of tissue-specific genes, but whether and how these signals lead to chromatin remodeling is not understood and subject to debate. Using chromatin immunoprecipitation (ChIP) assays and mammary-specific genes as models, we show here that extracellular matrix (ECM) molecules and prolactin cooperate to induce histone acetylation and binding of transcription factors and the SWI/SNF complex to the {beta}- and ?-casein promoters. Introduction of a dominant negative Brg1, an ATPase subunit of SWI/SNF complex, significantly reduced both {beta}- and ?-casein expression, suggesting that SWI/SNF-dependent chromatin remodeling is required for transcription of mammary-specific genes. ChIP analyses demonstrated that the ATPase activity of SWI/SNF is necessary for recruitment of RNA transcriptional machinery, but not for binding of transcription factors or for histone acetylation. Coimmunoprecipitation analyses showed that the SWI/SNF complex is associated with STAT5, C/EBP{beta}, and glucocorticoid receptor (GR). Thus, ECM- and prolactin-regulated transcription of the mammary-specific casein genes requires the concerted action of chromatin remodeling enzymes and transcription factors.

  20. SNF5 is an essential executor of epigenetic regulation during differentiation.

    Science.gov (United States)

    You, Jueng Soo; De Carvalho, Daniel D; Dai, Chao; Liu, Minmin; Pandiyan, Kurinji; Zhou, Xianghong J; Liang, Gangning; Jones, Peter A

    2013-04-01

    Nucleosome occupancy controls the accessibility of the transcription machinery to DNA regulatory regions and serves an instructive role for gene expression. Chromatin remodelers, such as the BAF complexes, are responsible for establishing nucleosome occupancy patterns, which are key to epigenetic regulation along with DNA methylation and histone modifications. Some reports have assessed the roles of the BAF complex subunits and stemness in murine embryonic stem cells. However, the details of the relationships between remodelers and transcription factors in altering chromatin configuration, which ultimately affects gene expression during cell differentiation, remain unclear. Here for the first time we demonstrate that SNF5, a core subunit of the BAF complex, negatively regulates OCT4 levels in pluripotent cells and is essential for cell survival during differentiation. SNF5 is responsible for generating nucleosome-depleted regions (NDRs) at the regulatory sites of OCT4 repressed target genes such as PAX6 and NEUROG1, which are crucial for cell fate determination. Concurrently, SNF5 closes the NDRs at the regulatory regions of OCT4-activated target genes such as OCT4 itself and NANOG. Furthermore, using loss- and gain-of-function experiments followed by extensive genome-wide analyses including gene expression microarrays and ChIP-sequencing, we highlight that SNF5 plays dual roles during differentiation by antagonizing the expression of genes that were either activated or repressed by OCT4, respectively. Together, we demonstrate that SNF5 executes the switch between pluripotency and differentiation.

  1. SNF5 is an essential executor of epigenetic regulation during differentiation.

    Directory of Open Access Journals (Sweden)

    Jueng Soo You

    2013-04-01

    Full Text Available Nucleosome occupancy controls the accessibility of the transcription machinery to DNA regulatory regions and serves an instructive role for gene expression. Chromatin remodelers, such as the BAF complexes, are responsible for establishing nucleosome occupancy patterns, which are key to epigenetic regulation along with DNA methylation and histone modifications. Some reports have assessed the roles of the BAF complex subunits and stemness in murine embryonic stem cells. However, the details of the relationships between remodelers and transcription factors in altering chromatin configuration, which ultimately affects gene expression during cell differentiation, remain unclear. Here for the first time we demonstrate that SNF5, a core subunit of the BAF complex, negatively regulates OCT4 levels in pluripotent cells and is essential for cell survival during differentiation. SNF5 is responsible for generating nucleosome-depleted regions (NDRs at the regulatory sites of OCT4 repressed target genes such as PAX6 and NEUROG1, which are crucial for cell fate determination. Concurrently, SNF5 closes the NDRs at the regulatory regions of OCT4-activated target genes such as OCT4 itself and NANOG. Furthermore, using loss- and gain-of-function experiments followed by extensive genome-wide analyses including gene expression microarrays and ChIP-sequencing, we highlight that SNF5 plays dual roles during differentiation by antagonizing the expression of genes that were either activated or repressed by OCT4, respectively. Together, we demonstrate that SNF5 executes the switch between pluripotency and differentiation.

  2. Identification of multiple distinct Snf2 subfamilies with conserved structural motifs.

    Science.gov (United States)

    Flaus, Andrew; Martin, David M A; Barton, Geoffrey J; Owen-Hughes, Tom

    2006-01-01

    The Snf2 family of helicase-related proteins includes the catalytic subunits of ATP-dependent chromatin remodelling complexes found in all eukaryotes. These act to regulate the structure and dynamic properties of chromatin and so influence a broad range of nuclear processes. We have exploited progress in genome sequencing to assemble a comprehensive catalogue of over 1300 Snf2 family members. Multiple sequence alignment of the helicase-related regions enables 24 distinct subfamilies to be identified, a considerable expansion over earlier surveys. Where information is known, there is a good correlation between biological or biochemical function and these assignments, suggesting Snf2 family motor domains are tuned for specific tasks. Scanning of complete genomes reveals all eukaryotes contain members of multiple subfamilies, whereas they are less common and not ubiquitous in eubacteria or archaea. The large sample of Snf2 proteins enables additional distinguishing conserved sequence blocks within the helicase-like motor to be identified. The establishment of a phylogeny for Snf2 proteins provides an opportunity to make informed assignments of function, and the identification of conserved motifs provides a framework for understanding the mechanisms by which these proteins function.

  3. Mechanisms of regulation of SNF1/AMPK/SnRK1 protein kinases

    Science.gov (United States)

    Crozet, Pierre; Margalha, Leonor; Confraria, Ana; Rodrigues, Américo; Martinho, Cláudia; Adamo, Mattia; Elias, Carlos A.; Baena-González, Elena

    2014-01-01

    The SNF1 (sucrose non-fermenting 1)-related protein kinases 1 (SnRKs1) are the plant orthologs of the budding yeast SNF1 and mammalian AMPK (AMP-activated protein kinase). These evolutionarily conserved kinases are metabolic sensors that undergo activation in response to declining energy levels. Upon activation, SNF1/AMPK/SnRK1 kinases trigger a vast transcriptional and metabolic reprograming that restores energy homeostasis and promotes tolerance to adverse conditions, partly through an induction of catabolic processes and a general repression of anabolism. These kinases typically function as a heterotrimeric complex composed of two regulatory subunits, β and γ, and an α-catalytic subunit, which requires phosphorylation of a conserved activation loop residue for activity. Additionally, SNF1/AMPK/SnRK1 kinases are controlled by multiple mechanisms that have an impact on kinase activity, stability, and/or subcellular localization. Here we will review current knowledge on the regulation of SNF1/AMPK/SnRK1 by upstream components, post-translational modifications, various metabolites, hormones, and others, in an attempt to highlight both the commonalities of these essential eukaryotic kinases and the divergences that have evolved to cope with the particularities of each one of these systems. PMID:24904600

  4. DAF-16 employs the chromatin remodeller SWI/SNF to promote stress resistance and longevity.

    Science.gov (United States)

    Riedel, Christian G; Dowen, Robert H; Lourenco, Guinevere F; Kirienko, Natalia V; Heimbucher, Thomas; West, Jason A; Bowman, Sarah K; Kingston, Robert E; Dillin, Andrew; Asara, John M; Ruvkun, Gary

    2013-05-01

    Organisms are constantly challenged by stresses and privations and require adaptive responses for their survival. The forkhead box O (FOXO) transcription factor DAF-16 (hereafter referred to as DAF-16/FOXO) is a central nexus in these responses, but despite its importance little is known about how it regulates its target genes. Proteomic identification of DAF-16/FOXO-binding partners in Caenorhabditis elegans and their subsequent functional evaluation by RNA interference revealed several candidate DAF-16/FOXO cofactors, most notably the chromatin remodeller SWI/SNF. DAF-16/FOXO and SWI/SNF form a complex and globally co-localize at DAF-16/FOXO target promoters. We show that specifically for gene activation, DAF-16/FOXO depends on SWI/SNF, facilitating SWI/SNF recruitment to target promoters, to activate transcription by presumed remodelling of local chromatin. For the animal, this translates into an essential role for SWI/SNF in DAF-16/FOXO-mediated processes, in particular dauer formation, stress resistance and the promotion of longevity. Thus, we give insight into the mechanisms of DAF-16/FOXO-mediated transcriptional regulation and establish a critical link between ATP-dependent chromatin remodelling and lifespan regulation.

  5. DAF-16/FOXO employs the chromatin remodeller SWI/SNF to promote stress resistance and longevity

    Science.gov (United States)

    Riedel, Christian G.; Dowen, Robert H.; Lourenco, Guinevere F.; Kirienko, Natalia V.; Heimbucher, Thomas; West, Jason A.; Bowman, Sarah K.; Kingston, Robert E.; Dillin, Andrew; Asara, John M.; Ruvkun, Gary

    2013-01-01

    Organisms are constantly challenged by stresses and privations and require adaptive responses for their survival. The transcription factor DAF-16/FOXO is central nexus in these responses, but despite its importance little is known about how it regulates its target genes. Proteomic identification of DAF-16/FOXO binding partners in Caenorhabditis elegans and their subsequent functional evaluation by RNA interference (RNAi) revealed several candidate DAF-16/FOXO cofactors, most notably the chromatin remodeller SWI/SNF. DAF-16/FOXO and SWI/SNF form a complex and globally colocalize at DAF-16/FOXO target promoters. We show that specifically for gene-activation, DAF-16/FOXO depends on SWI/SNF, facilitating SWI/SNF recruitment to target promoters, in order to activate transcription by presumed remodelling of local chromatin. For the animal, this translates into an essential role of SWI/SNF for DAF-16/FOXO-mediated processes, i.e. dauer formation, stress resistance, and the promotion of longevity. Thus we give insight into the mechanisms of DAF-16/FOXO-mediated transcriptional regulation and establish a critical link between ATP-dependent chromatin remodelling and lifespan regulation. PMID:23604319

  6. Fundamental remote sensing science research program. Part 1: Scene radiation and atmospheric effects characterization project

    Science.gov (United States)

    Murphy, R. E.; Deering, D. W.

    1984-01-01

    Brief articles summarizing the status of research in the scene radiation and atmospheric effect characterization (SRAEC) project are presented. Research conducted within the SRAEC program is focused on the development of empirical characterizations and mathematical process models which relate the electromagnetic energy reflected or emitted from a scene to the biophysical parameters of interest.

  7. Measuring radiation damage dynamics by pulsed ion beam irradiation: 2016 project annual report

    Energy Technology Data Exchange (ETDEWEB)

    Kucheyev, Sergei O. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

    2017-01-04

    The major goal of this project is to develop and demonstrate a novel experimental approach to access the dynamic regime of radiation damage formation in nuclear materials. In particular, the project exploits a pulsed-ion-beam method in order to gain insight into defect interaction dynamics by measuring effective defect interaction time constants and defect diffusion lengths. For Year 3, this project had the following two major milestones: (i) the demonstration of the measurement of thermally activated defect-interaction processes by pulsed ion beam techniques and (ii) the demonstration of alternative characterization techniques to study defect dynamics. As we describe below, both of these milestones have been met.

  8. High Density Radiation Shielding Concretes for Hot Cells of 99mTc Project

    International Nuclear Information System (INIS)

    Sakr, K.

    2006-01-01

    High density concrete [more than 3.6 ton/m 3 (3.6x10 3 kg/m 3 )] was prepared to be used as a radiation shielding concrete (RSC) for hot-cells in gel technetium project at inshas to attenuate gamma radiation emitted from radioactive sources. different types of concrete were prepared by mixing local mineral aggregates mainly gravel and ilmenite . iron shots were added to the concrete mixture proportion as partial replacement of heavy aggregates to increase its density. the physical properties of prepared concrete in both plastic and hardened phases were investigated. compressive strength and radiation attenuation of gamma rays were determined. Results showed that ilmenite concrete mixed with iron shots had the highest density suitable to be use as RSC according to the chinese hot cell design requirements. Recommendations to avoid some technical problems of manufacturing radiation shielding concrete were maintained

  9. Conditions With High Intracellular Glucose Inhibit Sensing Through Glucose Sensor Snf3 in Saccharomyces cerevisiae

    DEFF Research Database (Denmark)

    Karhumaa, Kaisa; Wu, B.Q.; Kielland-Brandt, Morten

    2010-01-01

    as for amino acids. An alternating-access model of the function of transporter-like sensors has been previously suggested based on amino acid sensing, where intracellular ligand inhibits binding of extracellular ligand. Here we studied the effect of intracellular glucose on sensing of extracellular glucose...... through the transporter-like sensor Snf3 in yeast. Sensing through Snf3 was determined by measuring degradation of Mth1 protein. High intracellular glucose concentrations were achieved by using yeast strains lacking monohexose transporters which were grown on maltose. The apparent affinity...... of extracellular glucose to Snf3 was measured for cells grown in non-fermentative medium or on maltose. The apparent affinity for glucose was lowest when the intracellular glucose concentration was high. The results conform to an alternating-access model for transporter-like sensors. J. Cell. Biochem. 110: 920...

  10. Regulatory Experiences from Effective Step-wise Implementation of the SNF Disposal in Finland

    International Nuclear Information System (INIS)

    Hämäläinen, K.

    2016-01-01

    Finland is one of the foremost countries in the world in developing a disposal solution for spent nuclear fuel (SNF). The Construction License Application (CLA) for the Olkiluoto SNF encapsulation and disposal facility was submitted by Posiva, the implementer, to the authorities at the end of 2012 and the Government is expected to decide about the license during autumn 2015. In 1983 the Government made a strategy decision on the objectives and target time schedule for the research, development and technical planning of nuclear waste management. Decision included the milestones for site selection, submittal of construction license and start of disposal operations.

  11. Mutations affecting components of the SWI/SNF complex cause Coffin-Siris syndrome.

    Science.gov (United States)

    Tsurusaki, Yoshinori; Okamoto, Nobuhiko; Ohashi, Hirofumi; Kosho, Tomoki; Imai, Yoko; Hibi-Ko, Yumiko; Kaname, Tadashi; Naritomi, Kenji; Kawame, Hiroshi; Wakui, Keiko; Fukushima, Yoshimitsu; Homma, Tomomi; Kato, Mitsuhiro; Hiraki, Yoko; Yamagata, Takanori; Yano, Shoji; Mizuno, Seiji; Sakazume, Satoru; Ishii, Takuma; Nagai, Toshiro; Shiina, Masaaki; Ogata, Kazuhiro; Ohta, Tohru; Niikawa, Norio; Miyatake, Satoko; Okada, Ippei; Mizuguchi, Takeshi; Doi, Hiroshi; Saitsu, Hirotomo; Miyake, Noriko; Matsumoto, Naomichi

    2012-03-18

    By exome sequencing, we found de novo SMARCB1 mutations in two of five individuals with typical Coffin-Siris syndrome (CSS), a rare autosomal dominant anomaly syndrome. As SMARCB1 encodes a subunit of the SWItch/Sucrose NonFermenting (SWI/SNF) complex, we screened 15 other genes encoding subunits of this complex in 23 individuals with CSS. Twenty affected individuals (87%) each had a germline mutation in one of six SWI/SNF subunit genes, including SMARCB1, SMARCA4, SMARCA2, SMARCE1, ARID1A and ARID1B.

  12. Snf2 family gene distribution in higher plant genomes reveals DRD1 expansion and diversification in the tomato genome.

    Science.gov (United States)

    Bargsten, Joachim W; Folta, Adam; Mlynárová, Ludmila; Nap, Jan-Peter

    2013-01-01

    As part of large protein complexes, Snf2 family ATPases are responsible for energy supply during chromatin remodeling, but the precise mechanism of action of many of these proteins is largely unknown. They influence many processes in plants, such as the response to environmental stress. This analysis is the first comprehensive study of Snf2 family ATPases in plants. We here present a comparative analysis of 1159 candidate plant Snf2 genes in 33 complete and annotated plant genomes, including two green algae. The number of Snf2 ATPases shows considerable variation across plant genomes (17-63 genes). The DRD1, Rad5/16 and Snf2 subfamily members occur most often. Detailed analysis of the plant-specific DRD1 subfamily in related plant genomes shows the occurrence of a complex series of evolutionary events. Notably tomato carries unexpected gene expansions of DRD1 gene members. Most of these genes are expressed in tomato, although at low levels and with distinct tissue or organ specificity. In contrast, the Snf2 subfamily genes tend to be expressed constitutively in tomato. The results underpin and extend the Snf2 subfamily classification, which could help to determine the various functional roles of Snf2 ATPases and to target environmental stress tolerance and yield in future breeding.

  13. Reconstruction of the yeast Snf1 kinase regulatory network reveals its role as a global energy regulator

    DEFF Research Database (Denmark)

    Usaite, Renata; Jewett, Michael Christopher; Soberano de Oliveira, Ana Paula

    2009-01-01

    Highly conserved among eukaryotic cells, the AMP-activated kinase (AMPK) is a central regulator of carbon metabolism. To map the complete network of interactions around AMPK in yeast (Snf1) and to evaluate the role of its regulatory subunit Snf4, we measured global mRNA, protein and metabolite...

  14. Snf2 family gene distribution in higher plant genomes reveals DRD1 expansion and diversification in the tomato genome.

    Directory of Open Access Journals (Sweden)

    Joachim W Bargsten

    Full Text Available As part of large protein complexes, Snf2 family ATPases are responsible for energy supply during chromatin remodeling, but the precise mechanism of action of many of these proteins is largely unknown. They influence many processes in plants, such as the response to environmental stress. This analysis is the first comprehensive study of Snf2 family ATPases in plants. We here present a comparative analysis of 1159 candidate plant Snf2 genes in 33 complete and annotated plant genomes, including two green algae. The number of Snf2 ATPases shows considerable variation across plant genomes (17-63 genes. The DRD1, Rad5/16 and Snf2 subfamily members occur most often. Detailed analysis of the plant-specific DRD1 subfamily in related plant genomes shows the occurrence of a complex series of evolutionary events. Notably tomato carries unexpected gene expansions of DRD1 gene members. Most of these genes are expressed in tomato, although at low levels and with distinct tissue or organ specificity. In contrast, the Snf2 subfamily genes tend to be expressed constitutively in tomato. The results underpin and extend the Snf2 subfamily classification, which could help to determine the various functional roles of Snf2 ATPases and to target environmental stress tolerance and yield in future breeding.

  15. Spent nuclear fuel project product specification

    International Nuclear Information System (INIS)

    Pajunen, A.L.

    1998-01-01

    Product specifications are limits and controls established for each significant parameter that potentially affects safety and/or quality of the Spent Nuclear Fuel (SNF) packaged for transport to dry storage. The product specifications in this document cover the spent fuel packaged in MultiCanister Overpacks (MCOs) to be transported throughout the SNF Project. The SNF includes N Reactor fuel and single-pass reactor fuel. The FRS removes the SNF from the storage canisters, cleans it, and places it into baskets. The MCO loading system places the baskets into MCO/Cask assembly packages. These packages are then transferred to the Cold Vacuum Drying (CVD) Facility. After drying at the CVD Facility, the MCO cask packages are transferred to the Canister Storage Building (CSB), where the MCOs are removed from the casks, staged, inspected, sealed (by welding), and stored until a suitable permanent disposal option is implemented. The key criteria necessary to achieve these goals are documented in this specification

  16. Interim report on the special research project 'exposure to environmental radiation due to nuclear facilities'

    International Nuclear Information System (INIS)

    1981-03-01

    This special research project was started in 1978 as five-year plan. The purposes are to clarify the aspect of radiation exposure in human bodies due to the radioactive substances brought into the environment regarding the utilization of atomic energy, its mechanism and various factors affecting it, and to contribute to the evaluation of exposure dose, the reduction of radiation exposure, the conditions of locating nuclear facilities and the improvement of the method of disposing radioactive wastes. In addition to the fields treated in the previous special research project, the experimental research concerning the metabolism of environmental radioactive nuclides in bodies, namely the problem of the peculiarity of radioactive nuclide kinetics in infants and fetuses different from adults and the possibility of causing the changes in the intake and metabolism of nuclides in foods by the difference in their states of existence, was newly included. Also the research concerning the method of evaluating the absorbed dose in human organs at the time of irradiation outside and inside bodies in a new subject. Accordingly, this special research project is composed of (1) the research concerning the radionuclide kinetics in the environment, (2) the research concerning the radionuclide kinetics in bodies, (3) the research concerning the measurement and evaluation of dose absorbed in internal organs due to environmental radiation, and (4) the research concerning the monitoring of low level environmental radiation. The results obtained so far are reported. (Kako, I.)

  17. Monitoring Space Radiation Hazards with the Responsive Environmental Assessment Commercially Hosted (REACH) Project

    Science.gov (United States)

    Mazur, J. E.; Guild, T. B.; Crain, W.; Crain, S.; Holker, D.; Quintana, S.; O'Brien, T. P., III; Kelly, M. A.; Barnes, R. J.; Sotirelis, T.

    2017-12-01

    The Responsive Environmental Assessment Commercial Hosting (REACH) project uses radiation dosimeters on a commercial satellite constellation in low Earth orbit to provide unprecedented spatial and time sampling of space weather radiation hazards. The spatial and time scales of natural space radiation environments coupled with constraints for the hosting accommodation drove the instrumentation requirements and the plan for the final orbital constellation. The project has delivered a total of thirty two radiation dosimeter instruments for launch with each instrument containing two dosimeters with different passive shielding and electronic thresholds to address proton-induced single-event effects, vehicle charging, and total ionizing dose. There are two REACH instruments currently operating with four more planned for launch by the time of the 2017 meeting. Our aim is to field a long-lived system of highly-capable radiation detectors to monitor the hazards of single-event effects, total ionizing dose, and spacecraft charging with maximized spatial coverage and with minimal time latency. We combined a robust detection technology with a commercial satellite hosting to produce a new demonstration for satellite situational awareness and for other engineering and science applications.

  18. The Palaeoclimate and Terrestrial Exoplanet Radiative Transfer Model Intercomparison Project (PALAEOTRIP: experimental design and protocols

    Directory of Open Access Journals (Sweden)

    C. Goldblatt

    2017-11-01

    Full Text Available Accurate radiative transfer calculation is fundamental to all climate modelling. For deep palaeoclimate, and increasingly terrestrial exoplanet climate science, this brings both the joy and the challenge of exotic atmospheric compositions. The challenge here is that most standard radiation codes for climate modelling have been developed for modern atmospheric conditions and may perform poorly away from these. The palaeoclimate or exoclimate modeller must either rely on these or use bespoke radiation codes, and in both cases rely on either blind faith or ad hoc testing of the code. In this paper, we describe the protocols for the Palaeoclimate and Terrestrial Exoplanet Radiative Transfer Model Intercomparison Project (PALAEOTRIP to systematically address this. This will compare as many radiation codes used for palaeoclimate or exoplanets as possible, with the aim of identifying the ranges of far-from-modern atmospheric compositions in which the codes perform well. This paper describes the experimental protocol and invites community participation in the project through 2017–2018.

  19. Development of Graphical User Interface for ARRBOD (Acute Radiation Risk and BRYNTRN Organ Dose Projection)

    Science.gov (United States)

    Kim, Myung-Hee; Hu, Shaowen; Nounu, Hatem N.; Cucinotta, Francis A.

    2010-01-01

    The space radiation environment, particularly solar particle events (SPEs), poses the risk of acute radiation sickness (ARS) to humans; and organ doses from SPE exposure may reach critical levels during extra vehicular activities (EVAs) or within lightly shielded spacecraft. NASA has developed an organ dose projection model using the BRYNTRN with SUMDOSE computer codes, and a probabilistic model of Acute Radiation Risk (ARR). The codes BRYNTRN and SUMDOSE, written in FORTRAN, are a Baryon transport code and an output data processing code, respectively. The ARR code is written in C. The risk projection models of organ doses and ARR take the output from BRYNTRN as an input to their calculations. BRYNTRN code operation requires extensive input preparation. With a graphical user interface (GUI) to handle input and output for BRYNTRN, the response models can be connected easily and correctly to BRYNTRN in friendly way. A GUI for the Acute Radiation Risk and BRYNTRN Organ Dose (ARRBOD) projection code provides seamless integration of input and output manipulations, which are required for operations of the ARRBOD modules: BRYNTRN, SUMDOSE, and the ARR probabilistic response model. The ARRBOD GUI is intended for mission planners, radiation shield designers, space operations in the mission operations directorate (MOD), and space biophysics researchers. The ARRBOD GUI will serve as a proof-of-concept example for future integration of other human space applications risk projection models. The current version of the ARRBOD GUI is a new self-contained product and will have follow-on versions, as options are added: 1) human geometries of MAX/FAX in addition to CAM/CAF; 2) shielding distributions for spacecraft, Mars surface and atmosphere; 3) various space environmental and biophysical models; and 4) other response models to be connected to the BRYNTRN. The major components of the overall system, the subsystem interconnections, and external interfaces are described in this

  20. Isotope detectors and radiation detectors for test reliability techniqui. A preliminary project

    International Nuclear Information System (INIS)

    Christell, R.

    1977-03-01

    A survey is done of small and simple components for use as detectors for ionizing radiation, as well as different methods and components producing images of radiation fields based on position sensitive detectors. The investigation has resulted in a system for detection of stones in wood. In a second project isotope excited x ray fluorescence has been used for analysis of material resulting from wear of mechanical components. A facility for analysis has been built and test analysis has been performed. Methods for continous wear control with possibility to forecast breakdowns have been investigated. (K.K.)

  1. Study of the feasibility of distributed cathodic arc as a plasma source for development of the technology for plasma separation of SNF and radioactive wastes

    Energy Technology Data Exchange (ETDEWEB)

    Amirov, R. Kh.; Vorona, N. A.; Gavrikov, A. V.; Liziakin, G. D.; Polistchook, V. P.; Samoylov, I. S.; Smirnov, V. P.; Usmanov, R. A., E-mail: ravus46@yandex.ru; Yartsev, I. M. [Russian Academy of Sciences, Joint Institute for High Temperatures (Russian Federation)

    2015-12-15

    One of the key problems in the development of plasma separation technology is designing a plasma source which uses condensed spent nuclear fuel (SNF) or nuclear wastes as a raw material. This paper covers the experimental study of the evaporation and ionization of model materials (gadolinium, niobium oxide, and titanium oxide). For these purposes, a vacuum arc with a heated cathode on the studied material was initiated and its parameters in different regimes were studied. During the experiment, the cathode temperature, arc current, arc voltage, and plasma radiation spectra were measured, and also probe measurements were carried out. It was found that the increase in the cathode heating power leads to the decrease in the arc voltage (to 3 V). This fact makes it possible to reduce the electron energy and achieve singly ionized plasma with a high degree of ionization to fulfill one of the requirements for plasma separation of SNF. This finding is supported by the analysis of the plasma radiation spectrum and the results of the probe diagnostics.

  2. Coordinated research project on radiation sterilization and decontamination of pharmaceuticals and pharmaceutical raw materials. CRP report

    International Nuclear Information System (INIS)

    2005-01-01

    Radiation processing is a very convenient tool for imparting desirable effects in materials and it has been an area of enormous interest in the last few decades. Radiation processing of synthetic and natural polymers for improving their characteristics is largely used in laboratory and industrial scale. Radiation sterilization is a well developed and established technology for many products. It is especially useful for the treatment of pharmaceuticals due to flexibility of radiation processing to be carried out at any desired temperature, sterilizability of mixed products in kits, offering simultaneous sterilization and modification of polymer based formulations. The success of radiation technology for processing of synthetic and natural polymers and treatment of pharmaceuticals has been based, to a large extent, on empirical knowledge. But now, the applications of natural polymers are being sought in knowledge-demanding areas such as pharmacy and biotechnology. Reliable analytical methods are being developed for controlling of degradation effects of radiation on polymers. Procedures and chemical formulations are being investigated enhancing or preventing degradation effects depending on the desired application of the process. The Coordinated Research Project (CRP) on the use of radiation processing for sterilization or decontamination of pharmaceuticals and pharmaceutical raw materials has been completed in 2002. The overall objective of the CRP was to coordinate the research and development programmes carried out in different countries in use of radiation processing for sterilization or decontamination of pharmaceuticals and pharmaceutic raw materials. It has been concluded that in addition to well known advantages of radiation sterilization being a well developed and established technology requiring the control of only one parameter, dose, to achieve sterilization; it is especially useful for the treatment of pharmaceuticals due to flexibility of radiation

  3. Coordinated research project on radiation sterilization and decontamination of pharmaceuticals and pharmaceutical raw materials. CRP report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-07-01

    Radiation processing is a very convenient tool for imparting desirable effects in materials and it has been an area of enormous interest in the last few decades. Radiation processing of synthetic and natural polymers for improving their characteristics is largely used in laboratory and industrial scale. Radiation sterilization is a well developed and established technology for many products. It is especially useful for the treatment of pharmaceuticals due to flexibility of radiation processing to be carried out at any desired temperature, sterilizability of mixed products in kits, offering simultaneous sterilization and modification of polymer based formulations. The success of radiation technology for processing of synthetic and natural polymers and treatment of pharmaceuticals has been based, to a large extent, on empirical knowledge. But now, the applications of natural polymers are being sought in knowledge-demanding areas such as pharmacy and biotechnology. Reliable analytical methods are being developed for controlling of degradation effects of radiation on polymers. Procedures and chemical formulations are being investigated enhancing or preventing degradation effects depending on the desired application of the process. The Coordinated Research Project (CRP) on the use of radiation processing for sterilization or decontamination of pharmaceuticals and pharmaceutical raw materials has been completed in 2002. The overall objective of the CRP was to coordinate the research and development programmes carried out in different countries in use of radiation processing for sterilization or decontamination of pharmaceuticals and pharmaceutic raw materials. It has been concluded that in addition to well known advantages of radiation sterilization being a well developed and established technology requiring the control of only one parameter, dose, to achieve sterilization; it is especially useful for the treatment of pharmaceuticals due to flexibility of radiation

  4. Differential Roles of the Glycogen-Binding Domains of β Subunits in Regulation of the Snf1 Kinase Complex▿

    Science.gov (United States)

    Mangat, Simmanjeet; Chandrashekarappa, Dakshayini; McCartney, Rhonda R.; Elbing, Karin; Schmidt, Martin C.

    2010-01-01

    Members of the AMP-activated protein kinase family, including the Snf1 kinase of Saccharomyces cerevisiae, are activated under conditions of nutrient stress. AMP-activated protein kinases are heterotrimeric complexes composed of a catalytic α subunit and regulatory β and γ subunits. In this study, the role of the β subunits in the regulation of Snf1 activity was examined. Yeasts express three isoforms of the AMP-activated protein kinase consisting of Snf1 (α), Snf4 (γ), and one of three alternative β subunits, either Sip1, Sip2, or Gal83. The Gal83 isoform of the Snf1 complex is the most abundant and was analyzed in the greatest detail. All three β subunits contain a conserved domain referred to as the glycogen-binding domain. The deletion of this domain from Gal83 results in a deregulation of the Snf1 kinase, as judged by a constitutive activity independent of glucose availability. In contrast, the deletion of this homologous domain from the Sip1 and Sip2 subunits had little effect on Snf1 kinase regulation. Therefore, the different Snf1 kinase isoforms are regulated through distinct mechanisms, which may contribute to their specialized roles in different stress response pathways. In addition, the β subunits are subjected to phosphorylation. The responsible kinases were identified as being Snf1 and casein kinase II. The significance of the phosphorylation is unclear since the deletion of the region containing the phosphorylation sites in Gal83 had little effect on the regulation of Snf1 in response to glucose limitation. PMID:19897735

  5. Differential roles of the glycogen-binding domains of beta subunits in regulation of the Snf1 kinase complex.

    Science.gov (United States)

    Mangat, Simmanjeet; Chandrashekarappa, Dakshayini; McCartney, Rhonda R; Elbing, Karin; Schmidt, Martin C

    2010-01-01

    Members of the AMP-activated protein kinase family, including the Snf1 kinase of Saccharomyces cerevisiae, are activated under conditions of nutrient stress. AMP-activated protein kinases are heterotrimeric complexes composed of a catalytic alpha subunit and regulatory beta and gamma subunits. In this study, the role of the beta subunits in the regulation of Snf1 activity was examined. Yeasts express three isoforms of the AMP-activated protein kinase consisting of Snf1 (alpha), Snf4 (gamma), and one of three alternative beta subunits, either Sip1, Sip2, or Gal83. The Gal83 isoform of the Snf1 complex is the most abundant and was analyzed in the greatest detail. All three beta subunits contain a conserved domain referred to as the glycogen-binding domain. The deletion of this domain from Gal83 results in a deregulation of the Snf1 kinase, as judged by a constitutive activity independent of glucose availability. In contrast, the deletion of this homologous domain from the Sip1 and Sip2 subunits had little effect on Snf1 kinase regulation. Therefore, the different Snf1 kinase isoforms are regulated through distinct mechanisms, which may contribute to their specialized roles in different stress response pathways. In addition, the beta subunits are subjected to phosphorylation. The responsible kinases were identified as being Snf1 and casein kinase II. The significance of the phosphorylation is unclear since the deletion of the region containing the phosphorylation sites in Gal83 had little effect on the regulation of Snf1 in response to glucose limitation.

  6. NASA GeneLab Project: Bridging Space Radiation Omics with Ground Studies.

    Science.gov (United States)

    Beheshti, Afshin; Miller, Jack; Kidane, Yared; Berrios, Daniel; Gebre, Samrawit G; Costes, Sylvain V

    2018-04-13

    Accurate assessment of risks of long-term space missions is critical for human space exploration. It is essential to have a detailed understanding of the biological effects on humans living and working in deep space. Ionizing radiation from galactic cosmic rays (GCR) is a major health risk factor for astronauts on extended missions outside the protective effects of the Earth's magnetic field. Currently, there are gaps in our knowledge of the health risks associated with chronic low-dose, low-dose-rate ionizing radiation, specifically ions associated with high (H) atomic number (Z) and energy (E). The NASA GeneLab project ( https://genelab.nasa.gov/ ) aims to provide a detailed library of omics datasets associated with biological samples exposed to HZE. The GeneLab Data System (GLDS) includes datasets from both spaceflight and ground-based studies, a majority of which involve exposure to ionizing radiation. In addition to detailed information on radiation exposure for ground-based studies, GeneLab is adding detailed, curated dosimetry information for spaceflight experiments. GeneLab is the first comprehensive omics database for space-related research from which an investigator can generate hypotheses to direct future experiments, utilizing both ground and space biological radiation data. The GLDS is continually expanding as omics-related data are generated by the space life sciences community. Here we provide a brief summary of the space radiation-related data available at GeneLab.

  7. Project, construction and calibration of parallel plate ionization chambers for x-radiation

    International Nuclear Information System (INIS)

    Albuquerque, M.P.P.

    1989-01-01

    Two pairs of parallel-plate ionization chambers were projected and constructed. In each pair one of the chambers has a collecting electrode and a guard ring made of graphite and the other, of aluminium. The difference between both pairs is that in only one case screws were used to fix the chamber components. The chambers are made of Lucite with aluminized Mylar entrance windows; they have circular form and are unsealed. All chamber components are easily available. The main chamber characteristics were determined, applying the tests of current leakage, repetitively and long term stability. The energy and angular dependence, and the polarity effect were also studied, obtaining the saturation curves and determining the build-up effect for gamma radiation detection. The chambers were calibrated with low and intermediate energy X-radiation, gamma radiation of sup(60)Co an sup(137)Cs, and beta radiation of sup(90)Sr + sup(90)Y. The obtained results show the viability of utilization of these chambers in radiation dosimetry and the results were compared with those of imported commercial ionization chambers of the secondary standard type. The great difference between the energy dependence of the chambers according to the collecting electrode material, allowed the formation of a Tandem system (constituted by a chamber pair A, C), for the determination of the effective energy and the exposure rate in air of unknown X-radiation fields, in the case of low intermediate energy ranges. (author)

  8. Synchrotron radiation sources and condensers for projection x-ray lithography

    International Nuclear Information System (INIS)

    Murphy, J.B.; MacDowell, A.A.; White, D.L.; Wood, O.R. II

    1992-01-01

    The design requirements for a compact electron storage ring that could be used as a soft x-ray source for projection lithography are discussed. The design concepts of the x-ray optics that are required to collect and condition the radiation in divergence, uniformity and direction to properly illuminate the mask and the particular x-ray projection camera used are discussed. Preliminary designs for an entire soft x-ray projection lithography system using an electron storage ring as a soft X-ray source are presented. It is shown that by combining the existing technology of storage rings with large collection angle condensers, a powerful and reliable source of 130 Angstrom photons for production line projection x-ray lithography is possible

  9. Low dose radiation effects: an integrative european approach (Risc-Rad Project) coordinated by the Cea

    International Nuclear Information System (INIS)

    Sabatier, L.

    2006-01-01

    RISC-RAD (Radiosensitivity of Individuals and Susceptibility to Cancer induced by ionizing Radiations) is an Integrated Project funded by the European Commission under 6. Framework Programme / EURATOM. RISC-RAD started on 1. January 2004 for a duration of four years. Coordinated by Cea (Dr Laure Sabatier), it involves 11 European countries (Austria, Denmark, Finland, France, Germany, Ireland, Italy, the Netherlands, Spain, Sweden and the United Kingdom) and 29 research institutions. Objectives: Exposures to low and protracted doses of ionizing radiation are very frequent in normal living environment, at work places, in industry and in medicine. Effects of these exposures on human health cannot be reliably assessed by epidemiological methods, nor is thoroughly understood by biologists. RISC-RAD project proposes to help bridging the gap of scientific knowledge about these effects. To achieve this goal, a necessary key step is to understand the basic mechanisms by which radiation induces cancer. Studying this multistage process in an integrated way, the project offers a new biological approach characterised by and clear-cut and objective-driven scientific policy: the project is focused on the effects of low doses (less than 100 mSv) and protracted doses of radiation. It aims at identifying new parameters that take into account the differences in radiation responses between individuals. A group of modelers works closely with the experimental teams in order to better quantify the risks associated with low and protracted doses. Research work is divided into five work packages interacting closely with each other. WP1 is dedicated to DNA damage. Ionizing Radiation (IR) produce a broad spectrum of base modifications and DNA strand breaks of different kinds, among which double-strand breaks and 'clustered damage' which is thought to be a major feature in biological effectiveness of IR. The aim of Work Package 1 is to improve understanding of the initial DNA damage induced by

  10. Projection of radiation-induced cancer risks across time and populations

    International Nuclear Information System (INIS)

    Muirhead, C.R.

    1991-01-01

    Various methods can be used to project the risks of radiation-induced cancer estimated in cohort studies beyond the period of follow-up and to other populations. The choice of risk projection model is reviewed based on data from studies such as those of the Japanese atomic bomb survivors and UK ankylosing spondylitis patients given X ray therapy. Risk estimates applicable to a UK population are calculated on the basis of various models, including those developed by the BEIR V Committee. It is emphasised that the continued follow-up of populations such as the Japanese atomic bomb survivors is of great importance in estimating lifetime risks. (author)

  11. Sampling strategy for a large scale indoor radiation survey - a pilot project

    International Nuclear Information System (INIS)

    Strand, T.; Stranden, E.

    1986-01-01

    Optimisation of a stratified random sampling strategy for large scale indoor radiation surveys is discussed. It is based on the results from a small scale pilot project where variances in dose rates within different categories of houses were assessed. By selecting a predetermined precision level for the mean dose rate in a given region, the number of measurements needed can be optimised. The results of a pilot project in Norway are presented together with the development of the final sampling strategy for a planned large scale survey. (author)

  12. Non-targeted effects of ionising radiation (note). A new European integrated project, 2006-2010

    International Nuclear Information System (INIS)

    Salomaa, S.; Wright, E.G.; Hildebrandt, G.; Kadhim, M.; Little, M.P.; Prise, K.M.; Belyakov, O.V.

    2007-01-01

    Complete text of publication follows. The general objectives of the NOTE project are: (1) to investigate the mechanisms of nontargeted effects, in particular, bystander effects, genomic instability and adaptive response; (2) to investigate if and how non-targeted effects modulate the cancer risk in the low dose region, and whether they relate to protective or harmful functions; (3) to investigate if ionising radiation can cause non-cancer diseases or beneficial effects at low and intermediate doses; (4) to investigate individual susceptibility and other factors modifying non-targeted responses; (5) to assess the relevance of non-targeted effects for radiation protection and to set the scientific basis for a modern, more realistic, radiation safety system; (6) to contribute to the conceptualisation of a new paradigm in radiation biology that would cover both the classical direct (DNA-targeted) and non-targeted (indirect) effects. The NOTE brings together 19 major European and Canadian groups involved in the discovery, characterisation and mechanistic investigation of non-targeted effects of ionising radiation in cellular, tissue and animal models. The NOTE research activities are organised in six work packages. Four work packages (WPs 2-5) are problem-oriented, focussing on major questions relevant for the scientific basis of the system of radiation protection: WP2 Mechanisms of non-targeted effects, WP3 Non-cancer diseases, WP4 Factors modifying non-targeted responses, WP5 Modelling of non-targeted effects. The integration activities provided by WP6 strengthen the collaboration by supporting the access to infrastructures, mobility and training. WP7 provides dissemination and exploitation activities in the form of workshops and a public website. Managerial activities (WP1) ensure the organisation and structures for decision making, monitoring of progress, knowledge management and efficient flow of information and financing. Coordinator of the NOTE project is Prof

  13. Development of radiation resistant magnets for JHF/J-PARC project

    CERN Document Server

    Tanaka, K H; Takahashi, H; Agari, K; Toyoda, A; Sato, Y; Minakawa, M; Noumi, H; Yamanoi, Y; Ieiri, M; Katoh, Y; Yamada, Y; Suzuki, Y; Takasaki, M; Birumachi, T; Tsukuda, S; Saitoh, Y; Saitô, N; Yahata, K; Kato, K; Tanaka, H; 10.1109/TASC.2004.829681

    2004-01-01

    A series of the R&D works on the radiation resistant magnets for the Japan Hadron Facility (JHF) project has been continued at the High Energy Accelerator Research Organization (KEK). The JHF is a high- energy part of the Japanese high intensity Particle Accelerator Research Complex (J-PARC), which is Japanese next-generation high- intensity accelerator project. The main JHF accelerator is the 50 GeV proton synchrotron and will provide high intensity 15 mu A proton beam for various nuclear and particle physics experiments. This time, the actual sized completely-inorganic radiation-resistant quadrupole magnet, designed for the 50 GeV proton beam transportation, was manufactured successfully by using mineral insulation magnet cable (MIC). The assembling procedure and the test results are presented in this issue. (8 refs).

  14. Radiation safety study for conventional facility and siting pre project phase of International Linear Collider

    International Nuclear Information System (INIS)

    Sanami, Toshiya; Ban, Syuichi; Sasaki, Shin-ichi

    2015-01-01

    The International Linear Collider (ILC) is a proposed high-energy collider consisting of two linear accelerators, two dumping rings, electron and positron sources, and a single colliding hall with two detectors. The total length and CMS energy of the ILC will be 31 km and 500 GeV, respectively (and 50 km and 1 TeV after future upgrade). The design of the ILC has entered the pre-project phase, which includes site-dependent design. Radiation safety design for the ILC is on-going as a part of conventional facility and siting activities of the pre-project phase. The thickness of a central wall of normal concrete is designed to be 3.5 m under a pessimistic assumption of beam loss. The beam loss scenario is under discussion. Experience and knowledge relating to shielding design and radiation control operational work at other laboratories are required. (authors)

  15. Acute Radiation Risk and BRYNTRN Organ Dose Projection Graphical User Interface

    Science.gov (United States)

    Cucinotta, Francis A.; Hu, Shaowen; Nounu, Hateni N.; Kim, Myung-Hee

    2011-01-01

    The integration of human space applications risk projection models of organ dose and acute radiation risk has been a key problem. NASA has developed an organ dose projection model using the BRYNTRN with SUM DOSE computer codes, and a probabilistic model of Acute Radiation Risk (ARR). The codes BRYNTRN and SUM DOSE are a Baryon transport code and an output data processing code, respectively. The risk projection models of organ doses and ARR take the output from BRYNTRN as an input to their calculations. With a graphical user interface (GUI) to handle input and output for BRYNTRN, the response models can be connected easily and correctly to BRYNTRN. A GUI for the ARR and BRYNTRN Organ Dose (ARRBOD) projection code provides seamless integration of input and output manipulations, which are required for operations of the ARRBOD modules. The ARRBOD GUI is intended for mission planners, radiation shield designers, space operations in the mission operations directorate (MOD), and space biophysics researchers. BRYNTRN code operation requires extensive input preparation. Only a graphical user interface (GUI) can handle input and output for BRYNTRN to the response models easily and correctly. The purpose of the GUI development for ARRBOD is to provide seamless integration of input and output manipulations for the operations of projection modules (BRYNTRN, SLMDOSE, and the ARR probabilistic response model) in assessing the acute risk and the organ doses of significant Solar Particle Events (SPEs). The assessment of astronauts radiation risk from SPE is in support of mission design and operational planning to manage radiation risks in future space missions. The ARRBOD GUI can identify the proper shielding solutions using the gender-specific organ dose assessments in order to avoid ARR symptoms, and to stay within the current NASA short-term dose limits. The quantified evaluation of ARR severities based on any given shielding configuration and a specified EVA or other mission

  16. Contribution of the ARCAL XX/IAEA project to improvement of radiation safety in medical practices

    International Nuclear Information System (INIS)

    Medina Gironzini, E.

    2001-01-01

    The objectives of the ARCAL XX Project: 'Guidelines on Control of Radiation Sources' (1997-2000) are to promote an effective control of the radiation sources used in medicine, industrial and research applications, harmonising and updating existing procedures within Latin American, adopting the International Basic Safety Standards, in order to avoid unnecessary expositions limiting the probability of accidents occurrence. Nine countries participate with experts in the development of guidelines based in the regional experience. The guidelines contain Radiological Safety Requirements, Guide for Authorisation Application and Inspections Procedures. At this moment, there are guidelines for Radiotherapy, Nuclear Medicine and Diagnostic Radiology. The implementation of these guidelines will improve the effectiveness of regulatory control of radiation sources in Latin American and the radiological protection in aspects of occupational, medical, public and potential exposure. This document presents the experience in the development of these guidelines and their contribution for elaborating national regulations in medical practices. (author) [es

  17. Methodology of fuel cycles long-term safety assessment of SNF/HLW geological disposal

    International Nuclear Information System (INIS)

    Pritrsky, J.

    2008-02-01

    Methodology for the long-term safety assessment of nuclear fuel cycles is given in the presented doctoral thesis. The aim of work was to develop a geological repository model for disposal of spent nuclear fuel (SNF) and high level waste (HLW) using an appropriate software code able to calculate the influence of partitioning and transmutation in advanced fuel cycles. The first step in this process was specifying of indicators which can be used to quantify the radiological impact of each fuel cycle. Indicators such as annual effective dose and radiotoxicity of inventory have been quantitatively analysed to determine the potential risk and radiological consequences associated with production of SNF/HLW. Advanced fuel types bring a number of advantages in comparison to uranium oxide fuel UO 2 used worldwide nowadays in terms of safety improvement due to minor actinides transmutation and non-proliferation aspects as well. Within the scope of work, three different fuel cycles are compared from the point of view of long-term safety of deep geological repository. The first considered fuel cycle is the currently used open fuel cycle (UOX) which uses only U-FA (Uranium Fuel Assembly). The second assessed cycle is a closed fuel cycle (MOX) with MOX-FA (Mixed OXides Fuel Assembly) and the third considered one is a partially closed fuel cycle (IMF) with IMC-FA (Inert Matrix Combined Fuel Assembly). Description and input data of advanced fuel cycles have been gained by participation in the EC project RED-IMPACT. Results were calculated using code AMBER, which is a flexible software tool that allows building dynamic compartmental models to represent the migration and fate of contaminants in a system, for example in the surface and sub-surface environment. Contaminants in solid, liquid and gaseous phases can be considered. AMBER gives the user the flexibility to define any number of compartments; any number of contaminants and associated decays; deterministic, probabilistic and

  18. Methodology of fuel cycles long-term safety assessment of SNF/HLW geological disposal

    International Nuclear Information System (INIS)

    Pritrsky, J.

    2008-01-01

    Methodology for the long-term safety assessment of nuclear fuel cycles is given in the presented doctoral thesis. The aim of work was to develop a geological repository model for disposal of spent nuclear fuel (SNF) and high level waste (HLW) using an appropriate software code able to calculate the influence of partitioning and transmutation in advanced fuel cycles. The first step in this process was specifying of indicators which can be used to quantify the radiological impact of each fuel cycle. Indicators such as annual effective dose and radiotoxicity of inventory have been quantitatively analysed to determine the potential risk and radiological consequences associated with production of SNF/HLW. Advanced fuel types bring a number of advantages in comparison to uranium oxide fuel UO 2 used worldwide nowadays in terms of safety improvement due to minor actinides transmutation and non-proliferation aspects as well. Within the scope of work, three different fuel cycles are compared from the point of view of long-term safety of deep geological repository. The first considered fuel cycle is the currently used open fuel cycle (UOX) which uses only U-FA (Uranium Fuel Assembly). The second assessed cycle is a closed fuel cycle (MOX) with MOX-FA (Mixed OXides Fuel Assembly) and the third considered one is a partially closed fuel cycle (IMF) with IMC-FA (Inert Matrix Combined Fuel Assembly). Description and input data of advanced fuel cycles have been gained by participation in the EC project RED-IMPACT. Results were calculated using code AMBER, which is a flexible software tool that allows building dynamic compartmental models to represent the migration and fate of contaminants in a system, for example in the surface and sub-surface environment. Contaminants in solid, liquid and gaseous phases can be considered. AMBER gives the user the flexibility to define any number of compartments; any number of contaminants and associated decays; deterministic, probabilistic and

  19. Assessment results of the Indonesian TRIGA SNF to be shipped to INEEL

    International Nuclear Information System (INIS)

    Jefimoff, J.; Robb, A.K.; Wendt, K.M.; Syarip, I.; Alfa, T.

    1997-01-01

    This paper describes the Training, Research, Isotope, General Atomics (TRIGA) spent nuclear fuel (SNF) examination performed by technical personnel from the Idaho National Engineering and Environmental Laboratory (INEEL) at the Bandung and Yogyakarta research reactor facilities in Indonesia. The examination was required before the SNF would be accepted for transportation to and storage at the INEEL. This paper delineates the Initial Preparations prior to the Indonesian foreign research reactor (FRR) fuel examination. The technical basis for the examination, the TRIGA SNF Acceptance Criteria, and the physical condition required for transportation, receipt and storage of the TRIGA SNF at the INEEL is explained. In addition to the initial preparations, preparation descriptions of the Work Plan For TRIGA Fuel Examination, the Underwater Examination Equipment used, and personnel Examination Team Training are included. Finally, the Fuel Examination and Results of the aluminum and stainless steel clad TRIGA fuel examination have been summarized. Lessons learned from all the activities completed to date is provided in an addendum. The initial preparations included: (1) coordination between the INEEL, FRR or Badan Tenaga Atom Nasional (BATAN), DOE-HQ, and the US State Department and Embassy; (2) incorporating Savannah River Site (SRS) FRR experience and lessons learned; (3) collecting both FRR facility and spent fuel data, and issuing a radionuclide report (Radionuclide Mass Inventory, Activity, Decay Heat, and Dose Rate Parametric Data for TRIGA Spent Nuclear Fuels) needed for transportation and fuel acceptance at the INEEL; and (4) preexamination work at the research reactor for the fuel examination

  20. Criticality Potential of Waste Packages Containing DOE SNF Affected by Igneous Intrusion

    International Nuclear Information System (INIS)

    D.S. Kimball; C.E. Sanders

    2006-01-01

    The Department of Energy (DOE) is currently preparing an application to submit to the U.S. Nuclear Regulatory Commission for a construction authorization for a monitored geologic repository. The repository will contain spent nuclear fuel (SNF) and defense high-level waste (DHLW) in waste packages placed in underground tunnels, or drifts. The primary objective of this paper is to perform a criticality analysis for waste packages containing DOE SNF affected by a disruptive igneous intrusion event in the emplacement drifts. The waste packages feature one DOE SNF canister placed in the center and surrounded by five High-Level Waste (HLW) glass canisters. The effective neutron multiplication factor (k eff ) is determined for potential configurations of the waste package during and after an intrusive igneous event. Due to the complexity of the potential scenarios following an igneous intrusion, finding conservative and bounding configurations with respect to criticality requires some additional considerations. In particular, the geometry of a slumped and damaged waste package must be examined, drift conditions must be modeled over a range of parameters, and the chemical degradation of DOE SNF and waste package materials must be considered for the expected high temperatures. The secondary intent of this calculation is to present a method for selecting conservative and bounding configurations for a wide range of end conditions

  1. Evaluation of Radionuclide Release from Aluminum-Based SNF in Basin Storage

    International Nuclear Information System (INIS)

    Sindelar, R.L.; Burke, S.D.; Howell, J.P.

    1998-09-01

    This report provides an evaluation of the release rates of radionuclides from breached A1-SNF assemblies and evaluates the effect of direct storage of breached fuel at a conservative upper bound reference condition on the SRS basin water activity levels

  2. Duo_2-Steel cermet manufacturing technology for PWR Spent Nuclear Fuel (SNF) casks

    International Nuclear Information System (INIS)

    Siti Alimah; Budiarto

    2005-01-01

    Assessment of DUO_2-Steel cermet manufacturing technology for PWR SNF casks has been done. DUO_2-Steel cermet consisting of DUO_2 particulates and other particulates, embedded in a steel matrix. Cermet SNF casks have the potential for superior performance compared with casks constructed of other materials. The addition of DUO_2 ceramic particulates can increase SNF cask capacity, improve of repository performance and disposal of excess depleted uranium as potential waste. Two sets of cermet manufacturing technologies are casting and powder metallurgy. Three casting methods are infusion casting, traditional casting and centrifugal casting. While for powder metallurgy methods there are traditional method and new method. DUO_2-Steel cermet have traditionally been produced by powder metallurgy methods. The production of a cask, however, presents special requirements: the manufacture of an annular object with weights up to 100 tons, and methods are being not to manufacture a cermet of this size and geometry. A new powder metallurgy method, is a method for manufacturing cermet for PWR SNF cask. This powder metallurgy techniques have potentials low costs and provides greater freedom In the design of the cermet cask by allowing variable cermet properties. (author)

  3. Public health response to radiation emergencies and the role of the Helsinki Project Office

    International Nuclear Information System (INIS)

    Baverstock, Keith F.

    1997-01-01

    This paper focuses on the public health element of nuclear emergency preparedness, defined as the mitigation of the long-term effects of radiation on exposed populations, as opposed to dealing with the health consequences of an exposure in an individual (termed medical aspects). The paper also approaches to the role of the Helsinki Project Office which is concerned with the protection of public health through effective response to nuclear emergencies, and falling into two categories, namely contingency planning or preparedness, and response

  4. Assessment of global cloud datasets from satellites: Project and database initiated by the GEWEX radiation panel

    OpenAIRE

    Stubenrauch , C.J.; Rossow , W.B.; Kinne , S.; Ackerman , S.; Cesana , G.; Chepfer , H.; Di Girolamo , L.; Getzewich , B.; Guignard , A.; Heidinger , A.; Maddux , B.C.; Menzel , W.P.; Minnis , P.; Pearl , C.; Platnick , S.

    2013-01-01

    International audience; The Global Energy and Water Cycle Experiment (GEWEX) Radiation Panel initiated the GEWEX Cloud Assessment in 2005 to compare available, global, long-term cloud data products with the International Satellite Cloud Climatology Project (ISCCP). The GEWEX Cloud Assessment database included cloud properties retrieved from different satellite sensor measurements, taken at various local times and over various time periods. The relevant passive satellite sensors measured radia...

  5. Overview of Graphical User Interface for ARRBOD (Acute Radiation Risk and BRYNTRN Organ Dose Projection)

    Science.gov (United States)

    Kim, Myung-Hee Y.; Hu, Shaowen; Nounu, Hatem N.; Cucinotta, Francis A.

    2010-01-01

    Solar particle events (SPEs) pose the risk of acute radiation sickness (ARS) to astronauts, because organ doses from large SPEs may reach critical levels during extra vehicular activities (EVAs) or lightly shielded spacecraft. NASA has developed an organ dose projection model of Baryon transport code (BRYNTRN) with an output data processing module of SUMDOSE, and a probabilistic model of acute radiation risk (ARR). BRYNTRN code operation requires extensive input preparation, and the risk projection models of organ doses and ARR take the output from BRYNTRN as an input to their calculations. With a graphical user interface (GUI) to handle input and output for BRYNTRN, these response models can be connected easily and correctly to BRYNTRN in a user friendly way. The GUI for the Acute Radiation Risk and BRYNTRN Organ Dose (ARRBOD) projection code provides seamless integration of input and output manipulations required for operations of the ARRBOD modules: BRYNTRN, SUMDOSE, and the ARR probabilistic response model. The ARRBOD GUI is intended for mission planners, radiation shield designers, space operations in the mission operations directorate (MOD), and space biophysics researchers. Assessment of astronauts organ doses and ARS from the exposure to historically large SPEs is in support of mission design and operation planning to avoid ARS and stay within the current NASA short-term dose limits. The ARRBOD GUI will serve as a proof-of-concept for future integration of other risk projection models for human space applications. We present an overview of the ARRBOD GUI product, which is a new self-contained product, for the major components of the overall system, subsystem interconnections, and external interfaces.

  6. The internet radiation oncology journal club - a multi-institutional collaborative education project

    International Nuclear Information System (INIS)

    Goldsmith, Brian J.; Donaldson, Sarah S.; Mendenhall, William M.; Recht, Abram; Hoppe, Richard T.; Grigsby, Perry W.; Turrisi, Andrew T.; Tepper, Joel E.; Roach, Mack; Larson, David A.; Withers, H. Rodney; Purdy, James A.

    1997-01-01

    Purpose/Objective: The high volume of literature publication in radiation oncology poses a substantial selection and reading challenge. Busy health care providers may, from time to time, fail to identify and read important papers, resulting in delays in improvement of practice standards. Residency training programs have historically used journal clubs as a solution to this education challenge. In June 1995, radiation oncologists and scientists from nine institutions began the Internet Radiation Oncology Journal Club (IROJC) - a pilot project created to improve radiation oncology education worldwide by identifying noteworthy literature and stimulating an internet-based forum for literature discussion. Materials and Methods: The IROJC is a free-of-charge, moderated e-mailing list hosted by BIOSCI - a set of electronic communication forums used by biological scientists worldwide. Eleven radiation oncologists and scientists with internationally-recognized subspecialty expertise serve as IROJC editors. Each month, editors select noteworthy contemporary literature for inclusion. Selected references, often accompanied by editorial comments, are transmitted over the internet to IROJC readers. Readers request subscription by sending an e-mail message to biosci-server at net.bio.net, with 'subscribe radoncjc' in the body of the message. A website (www.bio.net/hypermail/RADIATION-ONCOLOGY), which includes an archive of back issues, is also available. Results: By February 1997, the IROJC's email-format enrollment numbered more than 670 readers from over 14 countries, its website was browsed by an average of 25 unique readers per week, and both figures were increasing steadily. An exciting online dialogue of literature- and practice-based comments and questions had emerged with increasing readership participation. Conclusion: Our pilot experience with the IROJC project has been promising. The observed increase in enrollment, website use, and readership discourse suggests

  7. The provision of Technical Co-operation: The model project for upgrading radiation protection infrastructure

    International Nuclear Information System (INIS)

    Barretto, P.M.C.

    2001-01-01

    The paper describes the IAEA's systematic effort to address the inadequate situation in many of its Member States with regard to radiation protection and safety. For this effort a special project was created and implemented in the past five years to create or strengthen existing radiation protection infrastructure in 52 countries where such infrastructure was non-existent or not appropriate for the type of practice involved. The implementation of this project focused on the development of qualified human resources, assistance for introduction of appropriate legislation and equipment for inspection and analysis. Workplans were tailored to the individual needs of each participating country and the elements of these workplans were grouped into five milestones -- regulatory framework, occupational exposure control, medical exposure control, public exposure control, and emergency preparedness and response capabilities. By the end of 2000 more than 70% of the participating countries had radiation protection laws promulgated and a regulatory authority established; 46% had regulations adopted and 42% had a system of notification, authorization and control of radiation sources operational. During the five years of implementation, 555 fellows received individual training, another 2278 participated in training courses, over 1000 expert missions were fielded and equipment worth about US $6 million was provided. The total cost was over US $17 million. (author)

  8. Projected requirements for radiation oncologists and trainees in Australia and New Zealand to 2007

    International Nuclear Information System (INIS)

    Morgan, G.; Wigg, D.; Childs, J.

    2000-01-01

    Workloads in radiation oncology facilities in Australia and New Zealand have been increasing steadily for many years and it is anticipated that this trend will continue. In the present paper the projected number of radiation oncologists required to meet this demand to the year 2007 are estimated, along with the number of trainees required. The estimates are based on data from regular surveys by the Royal Australian and New Zealand College of Radiologists (RANZCR) for the years 1988-97 (inclusive). From these surveys profiles of numbers, age and gender of specialists and trainees are documented together with increases from the training programme and losses from retirement. It is concluded that if the current trainee numbers are increased by 12 in Australia and two in New Zealand, there will be approximately 10 radiation oncologists per million of population by the year 2007. This number is considered appropriate vue the anticipated increase in demands and complexity of treatment. Because projections too far forward are unreliable, careful monitoring of progress is essential to obtain the appropriate balance between requirement and supply. Comparisons are made with other estimates of needs including the 1998 Australian Medical Workforce Advisory Committee (AMWAC) Report and the New Zealand Clinical Agency Workforce Project Report in 1997. Copyright (1999) Blackwell Science Pty Ltd

  9. The NASA Radiation Interuniversity Science and Engineering(RaISE) Project: A Model for Inter-collaboration and Distance Learning in Radiation Physics and Nuclear Engineering

    Science.gov (United States)

    Denkins, Pamela S.; Saganti, P.; Obot, V.; Singleterry, R.

    2006-01-01

    This viewgraph document reviews the Radiation Interuniversity Science and Engineering (RaISE) Project, which is a project that has as its goals strengthening and furthering the curriculum in radiation sciences at two Historically Black Colleges and Universities (HBCU), Prairie View A&M University and Texas Southern University. Those were chosen in part because of the proximity to NASA Johnson Space Center, a lead center for the Space Radiation Health Program. The presentation reviews the courses that have been developed, both in-class, and on-line.

  10. NASA GeneLab Project: Bridging Space Radiation Omics with Ground Studies

    Science.gov (United States)

    Beheshti, Afshin; Miller, Jack; Kidane, Yared H.; Berrios, Daniel; Gebre, Samrawit G.; Costes, Sylvain V.

    2018-01-01

    Accurate assessment of risk factors for long-term space missions is critical for human space exploration: therefore it is essential to have a detailed understanding of the biological effects on humans living and working in deep space. Ionizing radiation from Galactic Cosmic Rays (GCR) is one of the major risk factors factor that will impact health of astronauts on extended missions outside the protective effects of the Earth's magnetic field. Currently there are gaps in our knowledge of the health risks associated with chronic low dose, low dose rate ionizing radiation, specifically ions associated with high (H) atomic number (Z) and energy (E). The GeneLab project (genelab.nasa.gov) aims to provide a detailed library of Omics datasets associated with biological samples exposed to HZE. The GeneLab Data System (GLDS) currently includes datasets from both spaceflight and ground-based studies, a majority of which involve exposure to ionizing radiation. In addition to detailed information for ground-based studies, we are in the process of adding detailed, curated dosimetry information for spaceflight missions. GeneLab is the first comprehensive Omics database for space related research from which an investigator can generate hypotheses to direct future experiments utilizing both ground and space biological radiation data. In addition to previously acquired data, the GLDS is continually expanding as Omics related data are generated by the space life sciences community. Here we provide a brief summary of space radiation related data available at GeneLab.

  11. Human Error Prediction and Countermeasures based on CREAM in Loading and Storage Phase of Spent Nuclear Fuel (SNF)

    International Nuclear Information System (INIS)

    Kim, Jae San; Kim, Min Su; Jo, Seong Youn

    2007-01-01

    With the steady demands for nuclear power energy in Korea, the amount of accumulated SNF has inevitably increased year by year. Thus far, SNF has been on-site transported from one unit to a nearby unit or an on-site dry storage facility. In the near future, as the amount of SNF generated approaches the capacity of these facilities, a percentage of it will be transported to another SNF storage facility. In the process of transporting SNF, human interactions involve inspecting and preparing the cask and spent fuel, loading the cask, transferring the cask and storage or monitoring the cask, etc. So, human actions play a significant role in SNF transportation. In analyzing incidents that have occurred during transport operations, several recent studies have indicated that 'human error' is a primary cause. Therefore, the objectives of this study are to predict and identify possible human errors during the loading and storage of SNF. Furthermore, after evaluating human error for each process, countermeasures to minimize human error are deduced

  12. Snf1 Phosphorylates Adenylate Cyclase and Negatively Regulates Protein Kinase A-dependent Transcription in Saccharomyces cerevisiae.

    Science.gov (United States)

    Nicastro, Raffaele; Tripodi, Farida; Gaggini, Marco; Castoldi, Andrea; Reghellin, Veronica; Nonnis, Simona; Tedeschi, Gabriella; Coccetti, Paola

    2015-10-09

    In eukaryotes, nutrient availability and metabolism are coordinated by sensing mechanisms and signaling pathways, which influence a broad set of cellular functions such as transcription and metabolic pathways to match environmental conditions. In yeast, PKA is activated in the presence of high glucose concentrations, favoring fast nutrient utilization, shutting down stress responses, and boosting growth. On the contrary, Snf1/AMPK is activated in the presence of low glucose or alternative carbon sources, thus promoting an energy saving program through transcriptional activation and phosphorylation of metabolic enzymes. The PKA and Snf1/AMPK pathways share common downstream targets. Moreover, PKA has been reported to negatively influence the activation of Snf1/AMPK. We report a new cross-talk mechanism with a Snf1-dependent regulation of the PKA pathway. We show that Snf1 and adenylate cyclase (Cyr1) interact in a nutrient-independent manner. Moreover, we identify Cyr1 as a Snf1 substrate and show that Snf1 activation state influences Cyr1 phosphorylation pattern, cAMP intracellular levels, and PKA-dependent transcription. © 2015 by The American Society for Biochemistry and Molecular Biology, Inc.

  13. Cloud radiative effects and changes simulated by the Coupled Model Intercomparison Project Phase 5 models

    Science.gov (United States)

    Shin, Sun-Hee; Kim, Ok-Yeon; Kim, Dongmin; Lee, Myong-In

    2017-07-01

    Using 32 CMIP5 (Coupled Model Intercomparison Project Phase 5) models, this study examines the veracity in the simulation of cloud amount and their radiative effects (CREs) in the historical run driven by observed external radiative forcing for 1850-2005, and their future changes in the RCP (Representative Concentration Pathway) 4.5 scenario runs for 2006-2100. Validation metrics for the historical run are designed to examine the accuracy in the representation of spatial patterns for climatological mean, and annual and interannual variations of clouds and CREs. The models show large spread in the simulation of cloud amounts, specifically in the low cloud amount. The observed relationship between cloud amount and the controlling large-scale environment are also reproduced diversely by various models. Based on the validation metrics, four models—ACCESS1.0, ACCESS1.3, HadGEM2-CC, and HadGEM2-ES—are selected as best models, and the average of the four models performs more skillfully than the multimodel ensemble average. All models project global-mean SST warming at the increase of the greenhouse gases, but the magnitude varies across the simulations between 1 and 2 K, which is largely attributable to the difference in the change of cloud amount and distribution. The models that simulate more SST warming show a greater increase in the net CRE due to reduced low cloud and increased incoming shortwave radiation, particularly over the regions of marine boundary layer in the subtropics. Selected best-performing models project a significant reduction in global-mean cloud amount of about -0.99% K-1 and net radiative warming of 0.46 W m-2 K-1, suggesting a role of positive feedback to global warming.

  14. Application of isotopes and radiation to increasing agricultural production - Phase 2. Indonesia. Project findings and recommendations

    International Nuclear Information System (INIS)

    1992-01-01

    This Phase 2 Project was primarily aimed at consolidating the advances made during the previous phase, formulating practical agricultural technologies which can be adopted by farmers, disseminating and applying these technologies, and enhancing the capability of the Centre for Application of Isotopes and Radiation (CAIR) to conduct agricultural research using nuclear and related techniques. Outputs generated by this project were generally in accordance with those anticipated in the Project Document. Some outputs have been transferred to the target beneficiaries (farmers) through existing systems of extension, in co-operation with the main implementing agency (BATAN). Other outputs have potential for further assessment, and may lead to practical applications in future. The rest remain as important contributions to scientific knowledge. The project has been managed to assure sustainability after project termination. A strong indication of such sustainability is evident in the on-going research and development work at CAIR and the adoption of transferred technologies by the end-users. To keep up with rapid global advancements in bio-science and technology, a new project on application of nuclear and related techniques in agricultural bio-science and technology would be needed in relation to the second long-term phase of the national development programmes. (author)

  15. Glucose de-repression by yeast AMP-activated protein kinase SNF1 is controlled via at least two independent steps.

    Science.gov (United States)

    García-Salcedo, Raúl; Lubitz, Timo; Beltran, Gemma; Elbing, Karin; Tian, Ye; Frey, Simone; Wolkenhauer, Olaf; Krantz, Marcus; Klipp, Edda; Hohmann, Stefan

    2014-04-01

    The AMP-activated protein kinase, AMPK, controls energy homeostasis in eukaryotic cells but little is known about the mechanisms governing the dynamics of its activation/deactivation. The yeast AMPK, SNF1, is activated in response to glucose depletion and mediates glucose de-repression by inactivating the transcriptional repressor Mig1. Here we show that overexpression of the Snf1-activating kinase Sak1 results, in the presence of glucose, in constitutive Snf1 activation without alleviating glucose repression. Co-overexpression of the regulatory subunit Reg1 of the Glc-Reg1 phosphatase complex partly restores glucose regulation of Snf1. We generated a set of 24 kinetic mathematical models based on dynamic data of Snf1 pathway activation and deactivation. The models that reproduced our experimental observations best featured (a) glucose regulation of both Snf1 phosphorylation and dephosphorylation, (b) determination of the Mig1 phosphorylation status in the absence of glucose by Snf1 activity only and (c) a regulatory step directing active Snf1 to Mig1 under glucose limitation. Hence it appears that glucose de-repression via Snf1-Mig1 is regulated by glucose via at least two independent steps: the control of activation of the Snf1 kinase and directing active Snf1 to inactivating its target Mig1. © 2014 FEBS.

  16. The Montbeliard Radiation Protection Pilot Project: a global approach of radiation protection addressing occupational, public and patient exposures at the level of a large urban community

    International Nuclear Information System (INIS)

    Schieber, Caroline; Lochard, Jacques; Badajoz, Coralie; Bataille, Celine; Croueail, Pascal; Klein, Didier; Klopfenstein, Jean-Francois; Makovicka, Libor

    2008-01-01

    The Montbeliard Radiation Protection Pilot Project started in March 2004, at the initiative of the Inter- City Council of the Montbeliard Country in cooperation with CEPN. It aims at improving the radiation protection of the inhabitants of the Montbeliard Country in the various exposure situations which can be potentially encountered on the territory (hospital, dwellings, environment,...) as well as at promoting the creation of a pole of competence in the field of radiation protection in the Montbeliard Country. The project relies on the involvement of all relevant stakeholders at the local, national and international level. This paper provides with a quick insight of the project organisation, followed by a synthetic description of the main achievements of the various project areas. (author)

  17. Reports on radiation protection R and D projects of the Federal Ministry of the Interior in the year 1983

    International Nuclear Information System (INIS)

    1984-10-01

    The volume presents separate reports set up by the contractors or donees for documentation of the progress achieved within the framework of the various projects. The reports inform about the project purpose, work performed, results obtained, and further activities and goals. The full-text reports are preceeded by four different lists showing the report titles arranged according to terms of the radiation protection thesaurus, to project packages, to project numbers, and to an alphabetical subject index. (orig./HP) [de

  18. Plant Responses to Increased UV-B Radiation: A Research Project

    Science.gov (United States)

    DAntoni, H. L.; Skiles, J. W.; Armstrong, R.; Coughlan, J.; Daleo, G.; Mayoral, A.; Lawless, James G. (Technical Monitor)

    1994-01-01

    Ozone decrease implies more ultraviolet-B (UV-B) radiation reaching the surface of the Earth. Increased UV-B radiation triggers responses by living organisms. Despite the large potential impacts on vegetation, little is known about UV-B effects on terrestrial ecosystems. Long-term ecological studies are needed to quantify the effects of increased UV radiation on terrestrial ecosystems, asses the risks, and produce reliable data for prediction. Screening pigments are part of one of the protective mechanism in plants. Higher concentrations of screening pigments in leaves may be interpreted as a response to increased UV radiation. If the screening effect is not sufficient, important molecules will be disturbed by incoming radiation. Thus, genetics, photosynthesis, growth, plant and leaf shape and size, and pollen grains may be affected. This will have an impact on ecosystem dynamics, structure and productivity. It is necessary to monitor selected terrestrial ecosystems to permit detection and interpretation of changes attributable to global climate change and depleted ozone shield. The objectives of this project are: (1) To identify and measure indicators of the effects of increased solar UV-B radiation on terrestrial plants; (2) to select indicators with the greatest responses to UV-B exposure; (3) to test, adapt or create ecosystem models that use the information gathered by this project for prediction and to enhance our understanding of the effects of increased UV-B radiation on terrestrial ecosystems. As a first step to achieve these objectives we propose a three-year study of forest and steppe vegetation on the North slope of the Brooks Range (within the Arctic circle, in Alaska), in the Saguaro National Monument (near Tucson, Arizona) and in the forests and steppes of Patagonia (Argentina). We selected (1) vegetation north of the Polar Circle because at 70N there is 8% risk of plant damage due to increased UV-B radiation; (2) the foothills of Catalina Mountains

  19. Proposal of experimental facilities for studies of nuclear data and radiation engineering in the Intense Proton Accelerator Project

    CERN Document Server

    Baba, M; Nagai, Y; Ishibashi, K

    2003-01-01

    A proposal is given on the facilities and experiments in the Intense Proton Accelerator Project (J-PARC) relevant to the nuclear data and radiation engineering, nuclear astrophysics, nuclear transmutation, accelerator technology and space technology and so on. (3 refs).

  20. Spent Nuclear Fuel Project technical baseline document. Fiscal year 1995: Volume 1, Baseline description

    International Nuclear Information System (INIS)

    Womack, J.C.; Cramond, R.; Paedon, R.J.

    1995-01-01

    This document is a revision to WHC-SD-SNF-SD-002, and is issued to support the individual projects that make up the Spent Nuclear Fuel Project in the lower-tier functions, requirements, interfaces, and technical baseline items. It presents results of engineering analyses since Sept. 1994. The mission of the SNFP on the Hanford site is to provide safety, economic, environmentally sound management of Hanford SNF in a manner that stages it to final disposition. This particularly involves K Basin fuel, although other SNF is involved also

  1. Monte Carlo simulations for the space radiation superconducting shield project (SR2S).

    Science.gov (United States)

    Vuolo, M; Giraudo, M; Musenich, R; Calvelli, V; Ambroglini, F; Burger, W J; Battiston, R

    2016-02-01

    Astronauts on deep-space long-duration missions will be exposed for long time to galactic cosmic rays (GCR) and Solar Particle Events (SPE). The exposure to space radiation could lead to both acute and late effects in the crew members and well defined countermeasures do not exist nowadays. The simplest solution given by optimized passive shielding is not able to reduce the dose deposited by GCRs below the actual dose limits, therefore other solutions, such as active shielding employing superconducting magnetic fields, are under study. In the framework of the EU FP7 SR2S Project - Space Radiation Superconducting Shield--a toroidal magnetic system based on MgB2 superconductors has been analyzed through detailed Monte Carlo simulations using Geant4 interface GRAS. Spacecraft and magnets were modeled together with a simplified mechanical structure supporting the coils. Radiation transport through magnetic fields and materials was simulated for a deep-space mission scenario, considering for the first time the effect of secondary particles produced in the passage of space radiation through the active shielding and spacecraft structures. When modeling the structures supporting the active shielding systems and the habitat, the radiation protection efficiency of the magnetic field is severely decreasing compared to the one reported in previous studies, when only the magnetic field was modeled around the crew. This is due to the large production of secondary radiation taking place in the material surrounding the habitat. Copyright © 2016 The Committee on Space Research (COSPAR). Published by Elsevier Ltd. All rights reserved.

  2. Evaluation of the WIPP Project`s compliance with the EPA radiation protection standards for disposal of transuranic waste

    Energy Technology Data Exchange (ETDEWEB)

    Neill, R.H.; Chaturvedi, L.; Rucker, D.F.; Silva, M.K.; Walker, B.A.; Channell, J.K.; Clemo, T.M. [Environmental Evaluation Group, Albuquerque, NM (United States)]|[Environmental Evaluation Group, Carlsbad, NM (United States)

    1998-03-01

    The US Environmental Protection Agency`s (EPA) proposed rule to certify that the Waste Isolation Pilot Plant (WIPP) meets compliance with the long-term radiation protection standards for geologic repositories (40CFR191 Subparts B and C), is one of the most significant milestones to date for the WIPP project in particular, and for the nuclear waste issue in general. The Environmental Evaluation Group (EEG) has provided an independent technical oversight for the WIPP project since 1978, and is responsible for many improvements in the location, design, and testing of various aspects of the project, including participation in the development of the EPA standards since the early 1980s. The EEG reviewed the development of documentation for assessing the WIPP`s compliance by the Sandia National Laboratories following the 1985 promulgation by EPA, and provided many written and verbal comments on various aspects of this effort, culminating in the overall review of the 1992 performance assessment. For the US Department of Energy`s (DOE) compliance certification application (CCA), the EEG provided detailed comments on the draft CCA in March, 1996, and additional comments through unpublished letters in 1997 (included as Appendices 8.1 and 8.2 in this report). Since the October 30, 1997, publication of the EPA`s proposed rule to certify WIPP, the EEG gave presentations on important issues to the EPA on December 10, 1997, and sent a December 31, 1997 letter with attachments to clarify those issues (Appendix 8.3). The EEG has raised a number of questions that may have an impact on compliance. In spite of the best efforts by the EEG, the EPA reaction to reviews and suggestions has been slow and apparently driven by legal considerations. This report discusses in detail the questions that have been raised about containment requirements. Also discussed are assurance requirements, groundwater protection, individual protection, and an evaluation of EPA`s responses to EEG`s comments.

  3. Thermal properties and phase transition in the fluoride, (NH4)3SnF7

    International Nuclear Information System (INIS)

    Kartashev, A.V.; Gorev, M.V.; Bogdanov, E.V.; Flerov, I.N.; Laptash, N.M.

    2016-01-01

    Calorimetric, dilatometric and differential thermal analysis studies were performed on (NH 4 ) 3 SnF 7 for a wide range of temperatures and pressures. Large entropy (δS 0 =22 J/mol K) and elastic deformation (δ(ΔV/V) 0 =0.89%) jumps have proven that the Pa-3↔Pm-3m phase transition is a strong first order structural transformation. A total entropy change of ΔS 0 =32.5 J/mol K is characteristic for the order–disorder phase transition, and is equal to the sum of entropy changes in the related material, (NH 4 ) 3 TiF 7 , undergoing transformation between the two cubic phases through the intermediate phases. Hydrostatic pressure decreases the stability of the high temperature Pm-3m phase in (NH 4 ) 3 SnF 7 , contrary to (NH 4 ) 3 TiF 7 , characterised by a negative baric coefficient. The effect of experimental conditions on the chemical stability of (NH 4 ) 3 SnF 7 was observed. - Graphical abstract: Strong first order structural transformation Pa-3↔Pm-3m in (NH 4 ) 3 SnF 7 is associated with very large total entropy change of ΔS 0 =32.5 J/mol K characteristic for the ordering processes and equal to the sum of entropy changes in the related (NH 4 ) 3 TiF 7 undergoing transformation between the same two cubic phases through the intermediate phases. - Highlights: • (NH 4 ) 3 SnF 7 undergoes strong first order Pa-3↔Pm-3m phase transition. • Anomalous behaviour of ΔC p and ΔV/V exists far below phase transition temperature. • Structural distortions are accompanied by huge total entropy change ΔS≈Rln50. • High pressure strongly increases the stability of Pa-3 phase in (NH 4 ) 3 SnF 7 . • Entropy of the Pa-3↔Pm-3m phase transition does not depend on pressure.

  4. Development of the ENVI simulator to estimate Korean SNF flow and its cost - 16060

    International Nuclear Information System (INIS)

    Hwang, Yongsoo; Miller, Ian

    2009-01-01

    This paper describes an integrated model developed by the Korean Atomic Energy Research Institute (KAERI) to simulate options for managing spent nuclear fuel (SNF) in South Korea. A companion paper (Hwang and Miller, 2009) describes a performance assessment model to address the long-term safety of alternative geological disposal options for different waste streams. The model addresses alternative concepts for storage, transportation, and processing of SNF of different types (Candu, PWR), leading up to permanent disposal in geological repositories. It uses the GoldSim software to simulate the logistics of the associated activities, including the associated capital and operating costs. The model's results allow direct comparison of alternative waste management concepts, and predict the sizes and timings of different facilities required. Future versions of the model will also address the uncertainties associated with the different system components in order to provide risk-based assessments. (authors)

  5. The FORO Project on Safety Culture in Organizations, Facilities and Activities With Sources of Ionizing Radiation

    International Nuclear Information System (INIS)

    Bomben, A. M.; Ferro Fernández, R.; Arciniega Torres, J.; Ordoñez Gutiérrez, E.; Blanes Tabernero, A.; Cruz Suárez, R.; Da Silva Silveira, C.; Perera Meas, J.; Ramírez Quijada, R.; Videla Valdebenito, R.

    2016-01-01

    The aim of this paper is to present the Ibero-American Forum of Nuclear and Radiological Regulatory Authorities’ (FORO) Project on Safety Culture in organizations, facilities and activities with sources of ionizing radiation developed by experts from the Regulatory Authorities of Argentina, Brazil, Chile, Cuba, Spain, Mexico, Peru and Uruguay, under the scientific coordination of the International Atomic Energy Agency (IAEA). Taking into account that Safety Culture problems have been widely recognised as one of the major contributors to many radiological events, several international and regional initiatives are being carried out to foster and develop a strong Safety Culture. One of these initiatives is the two-year project sponsored by the FORO with the purpose to prepare a document to allow its member states understanding, promoting and achieving a higher level of Safety Culture.

  6. Final report on the Project Research 'Assessment of Human Exposure to Environmental Radiation'

    International Nuclear Information System (INIS)

    1989-03-01

    This is the final report of the Project Research, 'Assessment of Human Exposure to Environmental Radiation', which has been conducted during the period 1983-1988. With the objective of assessing risk of environmental radioactivity to the population, the Project was divided into the following five research groups: (1) research for establishing calculation models and parameters in transfer of radionuclides from crop species through the human body; (2) research for analyzing transfer of radionuclides in the ocean and their contributions to exposure doses in the human body; (3) research for surveying accuracy of exposure models for the external body and respiratory organ and the influential factors; (4) research for determining uptake and biokinetics of radionuclides in the body; and (5) research for estimating and evaluating physical and physiological characteristics of reference Japanese man and the populaltion doses. Effluents from nuclear power plants and reprocessing plants were regarded as radionuclide sources in the water and atmosphere. (N.K.)

  7. 327 SNF fuel return to K-Basin quality process plan

    International Nuclear Information System (INIS)

    Ham, J.E.

    1998-01-01

    The B and W Hanford Company's (BWHC) 327 Facility, in the 300 Area of the Hanford Site, contains Spent Nuclear Fuel (SNF) single fuel element canisters (SFEC) and fuel remnant canisters (FRC) which are to be returned to K-Basin. Seven shipments of up to six fuel canisters will be loaded into the CNS 1-13G Cask and transported to 105-KE

  8. A SWI/SNF Chromatin Remodelling Protein Controls Cytokinin Production through the Regulation of Chromatin Architecture

    KAUST Repository

    Jé gu, Teddy; Domenichini, Sé verine; Blein, Thomas; Ariel, Federico; Christ, Auré lie; Kim, SoonKap; Crespi, Martin; Boutet-Mercey, Sté phanie; Mouille, Gré gory; Bourge, Mickaë l; Hirt, Heribert; Bergounioux, Catherine; Raynaud, Cé cile; Benhamed, Moussa

    2015-01-01

    Chromatin architecture determines transcriptional accessibility to DNA and consequently gene expression levels in response to developmental and environmental stimuli. Recently, chromatin remodelers such as SWI/SNF complexes have been recognized as key regulators of chromatin architecture. To gain insight into the function of these complexes during root development, we have analyzed Arabidopsis knock-down lines for one sub-unit of SWI/SNF complexes: BAF60. Here, we show that BAF60 is a positive regulator of root development and cell cycle progression in the root meristem via its ability to down-regulate cytokinin production. By opposing both the deposition of active histone marks and the formation of a chromatin regulatory loop, BAF60 negatively regulates two crucial target genes for cytokinin biosynthesis (IPT3 and IPT7) and one cell cycle inhibitor (KRP7). Our results demonstrate that SWI/SNF complexes containing BAF60 are key factors governing the equilibrium between formation and dissociation of a chromatin loop controlling phytohormone production and cell cycle progression.

  9. A SWI/SNF Chromatin Remodelling Protein Controls Cytokinin Production through the Regulation of Chromatin Architecture

    KAUST Repository

    Jégu, Teddy

    2015-10-12

    Chromatin architecture determines transcriptional accessibility to DNA and consequently gene expression levels in response to developmental and environmental stimuli. Recently, chromatin remodelers such as SWI/SNF complexes have been recognized as key regulators of chromatin architecture. To gain insight into the function of these complexes during root development, we have analyzed Arabidopsis knock-down lines for one sub-unit of SWI/SNF complexes: BAF60. Here, we show that BAF60 is a positive regulator of root development and cell cycle progression in the root meristem via its ability to down-regulate cytokinin production. By opposing both the deposition of active histone marks and the formation of a chromatin regulatory loop, BAF60 negatively regulates two crucial target genes for cytokinin biosynthesis (IPT3 and IPT7) and one cell cycle inhibitor (KRP7). Our results demonstrate that SWI/SNF complexes containing BAF60 are key factors governing the equilibrium between formation and dissociation of a chromatin loop controlling phytohormone production and cell cycle progression.

  10. Assessment of new radiation oncology technology and treatments in radiation oncology the ANROTAT project and collection of IMRT specific data

    International Nuclear Information System (INIS)

    Haworth, A.; Corry, J.; Kron, T.; Duchesne, G.; Ng, M.; Burmeister, B.

    2010-01-01

    Full text: Medical physicists (MP) are familiar with assessing new radiation oncology technology and treatments ( ROT A T) for their own departments but are not usually involved in providing advice to government for funding these technologies. This paper describes the role of the MP within the Commonwealth Government Department of Health and Aging initiative to develop a generic framework for assessment of ROTAT and the collection of data to support Med care Benefits Scheme (MBS) funding of IMRT. The clinical trials group TROG is developing a generic framework for the assessment of NROTAT. This will be tested and data collected to support applications for MBS funding of IMRT and IGRT. The tumour sites of nasopharynx, post-prostatectomy and anal canal have been selected to represent sites that are commonly, occasionally and rarely treated with IMRT respectively. Site selection for data collection will represent a broad range of clinical practices. Data quality is assured through TROG QA procedures and will include dosimetry audits. The final report will assess the clinical efficacy, cost effectiveness and safety of IMRT compared to 3DCRT. Existing clinical trial protocols form the basis for data collection and surrogate endpoints are being developed. Key publications have been identified that correlate specific dose-volume histogram parameters with clinical end-points, recognising limitations of these data in the 1MRT setting. Engagement of MPs within this project will help ensure collection of high quality data that ultimately aims to secure appropriate funding to ensure our patients receive best clinical care. (author)

  11. Poly(ADP-ribosyl)ation links the chromatin remodeler SMARCA5/SNF2H to RNF168-dependent DNA damage signaling

    DEFF Research Database (Denmark)

    Smeenk, G.; Wiegant, W.W.; Luijsterburg, M.S.

    2013-01-01

    Ionizing radiation (IR)-induced DNA double-strand breaks (DSBs) arising in native chromatin elicit an RNF8/RNF168-dependent ubiquitylation response, which triggers the recruitment of various repair factors. Precisely how this response is regulated in the context of chromatin remains largely...... unexplored. Here, we show that SMARCA5/SNF2H, the catalytic subunit of ISWI chromatin remodeling complexes, is recruited to DSBs in a poly(ADP-ribose) polymerase 1 (PARP1)-dependent manner. Remarkably, PARP activity, although dispensable for the efficient spreading of νH2AX into damaged chromatin......, selectively promotes spreading of SMARCA5, the E3 ubiquitin ligase RNF168, ubiquitin conjugates and the ubiquitin-binding factors RAD18 and the RAP80-BRCA1 complex throughout DSB-flanking chromatin. This suggests that PARP regulates the spatial organization of the RNF168-driven ubiquitin response to DNA...

  12. Functions and requirements for K Basin SNF characterization shipping

    International Nuclear Information System (INIS)

    Bergmann, D.W.

    1994-01-01

    This document details the plan for the shipping of fuel samples from the K Basins to the 300 Area for characterization. The fuel characterization project will evaluate the Hanford defense production fuel (N-Reactor and Single Pass Reactor) to support interim storage, transportation and final disposition. A limited number of fuel samples will be transported to a laboratory for analysis. It is currently estimated that 20 shipments of fuel per year for approximately 3 years (could be as long as 5 years) will be transported to the laboratory for analysis. Based on the NRC certificate of compliance each shipment is limited to 500 equivalent grams of 235 U. In practical terms this will limit shipments to three outer elements or two assemblies of any type of N-Reactor or SPR fuel. Case by case determination of broken fuel will be made based on the type of fuel and maximum potential fissile content

  13. Radiation

    International Nuclear Information System (INIS)

    2013-01-01

    The chapter one presents the composition of matter and atomic theory; matter structure; transitions; origin of radiation; radioactivity; nuclear radiation; interactions in decay processes; radiation produced by the interaction of radiation with matter

  14. Emergency Management and Radiation Monitoring in Nuclear and Radiological Accidents. Summary Report on the NKS Project EMARAD

    International Nuclear Information System (INIS)

    Lahtinen, J.

    2006-04-01

    In order to manage various nuclear or radiological emergencies the authorities must have pre-prepared plans. The purpose of the NKS project EMARAD (Emergency Management and Radiation Monitoring in Nuclear and Radiological Accidents) was to produce and gather various data and information that could be useful in drawing up emergency plans and radiation monitoring strategies. One of the specific objectives of the project was to establish a www site that would contain various radiation-threat and radiation-monitoring related data and documents and that could be accessed by all Nordic countries. Other important objectives were discussing various factors affecting measurements in an emergency, efficient use of communication technology and disseminating relevant information on such topics as urban dispersion and illicit use of radiation. The web server is hosted by the Radiation and Nuclear Safety Authority (STUK) of Finland. The data stored include pre-calculated consequence data for nuclear power plant accidents as well as documents and presentations describing e.g. general features of monitoring strategies, the testing of the British urban dispersion model UDM and the scenarios and aspects related to malicious use of radiation sources and radioactive material. As regards the last item mentioned, a special workshop dealing with the subject was arranged in Sweden in 2005 within the framework of the project. (au)

  15. Emergency Management and Radiation Moni-toring in Nuclear and Radiological Accidents. Summary Report on the NKS Project EMARAD

    Energy Technology Data Exchange (ETDEWEB)

    Lahtinen, J [Radiation and Nuclear Safety Authority (STUK) (Finland)

    2006-04-15

    In order to manage various nuclear or radiological emergencies the authorities must have pre-prepared plans. The purpose of the NKS project EMARAD (Emergency Management and Radiation Monitoring in Nuclear and Radiological Accidents) was to produce and gather various data and information that could be useful in drawing up emergency plans and radiation monitoring strategies. One of the specific objectives of the project was to establish a www site that would contain various radiation-threat and radiation-monitoring related data and documents and that could be accessed by all Nordic countries. Other important objectives were discussing various factors affecting measurements in an emergency, efficient use of communication technology and disseminating relevant information on such topics as urban dispersion and illicit use of radiation. The web server is hosted by the Radiation and Nuclear Safety Authority (STUK) of Finland. The data stored include pre-calculated consequence data for nuclear power plant accidents as well as documents and presentations describing e.g. general features of monitoring strategies, the testing of the British urban dispersion model UDM and the scenarios and aspects related to malicious use of radiation sources and radioactive material. As regards the last item mentioned, a special workshop dealing with the subject was arranged in Sweden in 2005 within the framework of the project. (au)

  16. Spent Nuclear Fuel Project Canister Storage Building Functions and Requirements

    International Nuclear Information System (INIS)

    KLEM, M.J.

    2000-01-01

    In 1998, a major change in the technical strategy for managing Multi Canister Overpacks (MCO) while stored within the Canister Storage Building (CSB) occurred. The technical strategy is documented in Baseline Change Request (BCR) No. SNF-98-006, Simplified SNF Project Baseline (MCO Sealing) (FDH 1998). This BCR deleted the hot conditioning process initially adopted for the Spent Nuclear Fuel Project (SNF Project) as documented in WHC-SD-SNF-SP-005, Integrated Process Strategy for K Basins Spent Nuclear Fuel (WHC 199.5). In summary, MCOs containing Spent Nuclear Fuel (SNF) from K Basins would be placed in interim storage following processing through the Cold Vacuum Drying (CVD) facility. With this change, the needs for the Hot Conditioning System (HCS) and inerting/pressure retaining capabilities of the CSB storage tubes and the MCO Handling Machine (MHM) were eliminated. Mechanical seals will be used on the MCOs prior to transport to the CSB. Covers will be welded on the MCOs for the final seal at the CSB. Approval of BCR No. SNF-98-006, imposed the need to review and update the CSB functions and requirements baseline documented herein including changing the document title to ''Spent Nuclear Fuel Project Canister Storage Building Functions and Requirements.'' This revision aligns the functions and requirements baseline with the CSB Simplified SNF Project Baseline (MCO Sealing). This document represents the Canister Storage Building (CSB) Subproject technical baseline. It establishes the functions and requirements baseline for the implementation of the CSB Subproject. The document is organized in eight sections. Sections 1.0 Introduction and 2.0 Overview provide brief introductions to the document and the CSB Subproject. Sections 3.0 Functions, 4.0 Requirements, 5.0 Architecture, and 6.0 Interfaces provide the data described by their titles. Section 7.0 Glossary lists the acronyms and defines the terms used in this document. Section 8.0 References lists the

  17. Supporting project on international education and training in cooperated program for Radiation Technology with World Nuclear University

    Energy Technology Data Exchange (ETDEWEB)

    Yoo, Byung Duk; Nam, Y. M.; Noh, S. P.; Shin, J. Y. [KAERI, Daejeon (Korea, Republic of)

    2010-08-15

    The objective is promote national status and potential of Nuclear radiation industry, and take a world-wide leading role in radiation industry, by developing and hosting the first WNU Radiation Technology School. RI School (World Nuclear University Radioisotope School) is the three-week program designed to develop and inspire future international leaders in the field of radioisotope for the first time. The project would enable promote abilities of radioactive isotopes professions, and to build the human network with future leaders in the world-wide nuclear and radiation field. Especially by offering opportunity to construct human networks between worldwide radiation field leaders of next generation, intangible assets and pro-Korean human networks are secured among international radiation industry personnel. This might enhance the power and the status of Korean radiation industries, and establish the fundamental base for exporting of radiation technology and its products. We developed the performance measurement method for the school. This shows that 2010 WNU RI School was the first training program focusing on the radioisotope and very useful program for the participants in view of knowledge management and strengthening personal abilities. Especially, the experiences and a human network with world-wide future-leaders in radiation field are most valuable asset. It is expected that the participants could this experience and network developed in the program as a stepping stone toward the development of Korea's nuclear and radiation industry.

  18. Supporting project on international education and training in cooperated program for Radiation Technology with World Nuclear University

    International Nuclear Information System (INIS)

    Yoo, Byung Duk; Nam, Y. M.; Noh, S. P.; Shin, J. Y.

    2010-08-01

    The objective is promote national status and potential of Nuclear radiation industry, and take a world-wide leading role in radiation industry, by developing and hosting the first WNU Radiation Technology School. RI School (World Nuclear University Radioisotope School) is the three-week program designed to develop and inspire future international leaders in the field of radioisotope for the first time. The project would enable promote abilities of radioactive isotopes professions, and to build the human network with future leaders in the world-wide nuclear and radiation field. Especially by offering opportunity to construct human networks between worldwide radiation field leaders of next generation, intangible assets and pro-Korean human networks are secured among international radiation industry personnel. This might enhance the power and the status of Korean radiation industries, and establish the fundamental base for exporting of radiation technology and its products. We developed the performance measurement method for the school. This shows that 2010 WNU RI School was the first training program focusing on the radioisotope and very useful program for the participants in view of knowledge management and strengthening personal abilities. Especially, the experiences and a human network with world-wide future-leaders in radiation field are most valuable asset. It is expected that the participants could this experience and network developed in the program as a stepping stone toward the development of Korea's nuclear and radiation industry

  19. Radiation protection system installation for the accelerator production of tritium/low energy demonstration accelerator project (APT/LEDA)

    CERN Document Server

    Wilmarth, J E; Tomei, T L

    2000-01-01

    The APT/LEDA personnel radiation protection system installation was accomplished using a flexible, modular proven system which satisfied regulatory orders, project design criteria, operational modes, and facility requirements. The goal of providing exclusion and safe access of personnel to areas where prompt radiation in the LEDA facility is produced was achieved with the installation of a DOE-approved Personnel Access Control System (PACS). To satisfy the facility configuration design, the PACS, a major component of the overall radiation safety system, conveniently provided five independent areas of personnel access control. Because of its flexibility and adaptability the Los-Alamos Neutron- Science-Center-(LANSCE)-designed Radiation Security System (RSS) was efficiently configured to provide the desired operational modes and satisfy the APT/LEDA project design criteria. The Backbone Beam Enable (BBE) system based on the LANSCE RSS provided the accelerator beam control functions with redundant, hardwired, ta...

  20. Radiation analysis for a generic centralized interim storage facility

    International Nuclear Information System (INIS)

    Gillespie, S.G.; Lopez, P.; Eble, R.G.

    1997-01-01

    This paper documents the radiation analysis performed for the storage area of a generic Centralized Interim Storage Facility (CISF) for commercial spent nuclear fuel (SNF). The purpose of the analysis is to establish the CISF Protected Area and Restricted Area boundaries by modeling a representative SNF storage array, calculating the radiation dose at selected locations outside the storage area, and comparing the results with regulatory radiation dose limits. The particular challenge for this analysis is to adequately model a large (6000 cask) storage array with a reasonable amount of analysis time and effort. Previous analyses of SNF storage systems for Independent Spent Fuel Storage Installations at nuclear plant sites (for example in References 5.1 and 5.2) had only considered small arrays of storage casks. For such analyses, the dose contribution from each storage cask can be modeled individually. Since the large number of casks in the CISF storage array make such an approach unrealistic, a simplified model is required

  1. Radiation Therapy Infrastructure and Human Resources in Low- and Middle-Income Countries: Present Status and Projections for 2020

    Energy Technology Data Exchange (ETDEWEB)

    Datta, Niloy R., E-mail: niloyranjan.datta@ksa.ch [Centre for Radiation Oncology, Kantonsspital Aarau - Kantonsspital Baden, Kantonsspital Aarau, Aarau (Switzerland); Samiei, Massoud [Consultancy Practice, Vienna (Austria); Bodis, Stephan [Centre for Radiation Oncology, Kantonsspital Aarau - Kantonsspital Baden, Kantonsspital Aarau, Aarau, Switzerland, and Department of Radiation Oncology, University Hospital Zurich (Switzerland)

    2014-07-01

    Purpose: Radiation therapy, a key component of cancer management, is required in more than half of new cancer patients, particularly in low- and middle-income countries (LMICs). The projected rise in cancer incidence over the next decades in LMICs will result in an increasing demand for radiation therapy services. Considering the present cancer incidence and that projected for 2020 (as listed in GLOBOCAN), we evaluated the current and anticipated needs for radiation therapy infrastructure and staffing by 2020 for each of the LMICs. Methods and Materials: Based on World Bank classification, 139 countries fall in the category of LMICs. Details of teletherapy, radiation oncologists, medical physicists, and radiation therapy technologists were available for 84 LMICs from the International Atomic Energy Agency–Directory of Radiotherapy Centres (IAEA-DIRAC) database. Present requirements and those for 2020 were estimated according to recommendations from the IAEA and European Society for Radiotherapy and Oncology (ESTRO-QUARTS). Results: Only 4 of the 139 LMICs have the requisite number of teletherapy units, and 55 (39.5%) have no radiation therapy facilities at present. Patient access to radiation therapy in the remaining 80 LMICs ranges from 2.3% to 98.8% (median: 36.7%). By 2020, these 84 LMICs would additionally need 9169 teletherapy units, 12,149 radiation oncologists, 9915 medical physicists, and 29,140 radiation therapy technologists. Moreover, de novo radiation therapy facilities would have to be considered for those with no services. Conclusions: Twelve pragmatic steps are proposed for consideration at national and international levels to narrow the gap in radiation therapy access. Multipronged and coordinated action from all national and international stakeholders is required to develop realistic strategies to curb this impending global crisis.

  2. Radiation Therapy Infrastructure and Human Resources in Low- and Middle-Income Countries: Present Status and Projections for 2020

    International Nuclear Information System (INIS)

    Datta, Niloy R.; Samiei, Massoud; Bodis, Stephan

    2014-01-01

    Purpose: Radiation therapy, a key component of cancer management, is required in more than half of new cancer patients, particularly in low- and middle-income countries (LMICs). The projected rise in cancer incidence over the next decades in LMICs will result in an increasing demand for radiation therapy services. Considering the present cancer incidence and that projected for 2020 (as listed in GLOBOCAN), we evaluated the current and anticipated needs for radiation therapy infrastructure and staffing by 2020 for each of the LMICs. Methods and Materials: Based on World Bank classification, 139 countries fall in the category of LMICs. Details of teletherapy, radiation oncologists, medical physicists, and radiation therapy technologists were available for 84 LMICs from the International Atomic Energy Agency–Directory of Radiotherapy Centres (IAEA-DIRAC) database. Present requirements and those for 2020 were estimated according to recommendations from the IAEA and European Society for Radiotherapy and Oncology (ESTRO-QUARTS). Results: Only 4 of the 139 LMICs have the requisite number of teletherapy units, and 55 (39.5%) have no radiation therapy facilities at present. Patient access to radiation therapy in the remaining 80 LMICs ranges from 2.3% to 98.8% (median: 36.7%). By 2020, these 84 LMICs would additionally need 9169 teletherapy units, 12,149 radiation oncologists, 9915 medical physicists, and 29,140 radiation therapy technologists. Moreover, de novo radiation therapy facilities would have to be considered for those with no services. Conclusions: Twelve pragmatic steps are proposed for consideration at national and international levels to narrow the gap in radiation therapy access. Multipronged and coordinated action from all national and international stakeholders is required to develop realistic strategies to curb this impending global crisis

  3. Radiation and temperature effects on electronic components investigated under the CSTI high capacity power project

    International Nuclear Information System (INIS)

    Schwarze, G.E.; Niedra, J.M.; Frasca, A.J.; Wieserman, W.R.

    1993-01-01

    The effects of nuclear radiation and high temperature environments must be fully known and understood for the electronic components and materials used in both the Power Conditioning and Control subsystem and the reactor Instrumentation and Control subsystem of future high capacity nuclear space power systems. This knowledge is required by the designer of these subsystems in order to develop highly reliable, long-life power systems for future NASA missions. A review and summary of the experimental results obtained for the electronic components and materials investigated under the power management element of the CSTI high capacity power project will be presented in this paper: (1) Neutron, gamma ray, and temperature effects on power semiconductor switches, (2) Temperature and frequency effects on soft magnetic materials; and (3) Temperature effects on rare-earth permanent magnets

  4. Problems studied within the state research project New Methods of Nondestructive Materials Testing Using Ionizing Radiation

    International Nuclear Information System (INIS)

    Mysak, F.; Strba, J.

    1979-01-01

    A state research project is described divided into ten subprojects, viz.: New trends of ionizing radiation detection using television technology in nondestructive testing; the application of accelerators for thick-walled product testing; the atlas of butt welds of medium thicknesses; the application of radioanalytical methods in testing the wear of gearboxes and other components of instrument parts; multielemental analyses of combustion engine wear using radionuclides; the application of radioisotope methods in research into wear of antifriction bearings of trucks and railway cars; the application of radionuclides in assessing corrosion resistance of steels and corrosion protection systems; the application of radionuclide methods in improving the quality of high-grade steel production; the selection and testing of radionuclide instruments for building production control, intermediate and acceptance checks; and radioisotope methods for building machine and equipment control. (M.S.)

  5. Radiation and temperature effects on electronic components investigated under the CSTI High Capacity Power Project

    International Nuclear Information System (INIS)

    Shwarze, G.E.; Wieserman, W.R.

    1994-01-01

    The effects of nuclear radiation and high temperature environments must be fully known and understood for the electronic components and materials used in both the Power Conditioning and Control subsystem and the reactor Instrumentation and Control subsystem of future high capacity nuclear space power systems. This knowledge is required by the designer of these subsystems in order to develop highly reliable, long-life power systems for future NASA missions. A review and summary of the experimental results obtained for the electronic components and materials investigated under the power management element of the CSTI high capacity power project will be presented in this paper: (1) Neutron, gamma ray, and temperature effects on power semiconductor switches, (2) Temperature and frequency effects on soft magnetic materials; and (3) Temperature effects on rare earth permanent magnets

  6. Facility Effluent Monitoring Plan for the Spent Nuclear Fuel (SNF) Project

    International Nuclear Information System (INIS)

    HUNACEK, G.S.

    2000-01-01

    A facility effluent monitoring plan is required by the US. Department of Energy in DOE Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. This document was prepared using the specific guidelines identified in Westinghouse Hanford Company (WHC)-EP-0438-1, ''A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans'', and assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements. This facility effluent monitoring plan is the third revision to the original annual report. This document is reviewed annually even if there are no operational changes, and it is updated as necessary

  7. Spent Nuclear Fuel (SNF) Project Canister Storage Building (CSB) Process Flow Diagram Mass Balance Calculations

    International Nuclear Information System (INIS)

    KLEM, M.J.

    2000-01-01

    The purpose of these calculations is to develop the material balances for documentation of the Canister Storage Building (CSB) Process Flow Diagram (PFD) and future reference. The attached mass balances were prepared to support revision two of the PFD for the CSB. The calculations refer to diagram H-2-825869

  8. Spent Nuclear Fuel (SNF) Project Multi Canister Overpack (MCO) Process Flow Diagram Mass Balance Calculations

    International Nuclear Information System (INIS)

    KLEM, M.J.

    2000-01-01

    The purpose of this calculation document is to develop the bases for the material balances of the Multi-Canister Overpack (MCO) Level 1 Process Flow Diagram (PFD). The attached mass balances support revision two of the PFD for the MCO and provide future reference

  9. Spent Nuclear Fuel (SNF) project Integrated Safety Management System phase I and II Verification Review Plan

    International Nuclear Information System (INIS)

    CARTER, R.P.

    1999-01-01

    The U.S. Department of Energy (DOE) commits to accomplishing its mission safely. To ensure this objective is met, DOE issued DOE P 450.4, Safety Management System Policy, and incorporated safety management into the DOE Acquisition Regulations ([DEAR] 48 CFR 970.5204-2 and 90.5204-78). Integrated Safety Management (ISM) requires contractors to integrate safety into management and work practices at all levels so that missions are achieved while protecting the public, the worker, and the environment. The contractor is required to describe the Integrated Safety Management System (ISMS) to be used to implement the safety performance objective

  10. Spent Nuclear Fuel (SNF) project Integrated Safety Management System phase I and II Verification Review Plan

    Energy Technology Data Exchange (ETDEWEB)

    CARTER, R.P.

    1999-11-19

    The U.S. Department of Energy (DOE) commits to accomplishing its mission safely. To ensure this objective is met, DOE issued DOE P 450.4, Safety Management System Policy, and incorporated safety management into the DOE Acquisition Regulations ([DEAR] 48 CFR 970.5204-2 and 90.5204-78). Integrated Safety Management (ISM) requires contractors to integrate safety into management and work practices at all levels so that missions are achieved while protecting the public, the worker, and the environment. The contractor is required to describe the Integrated Safety Management System (ISMS) to be used to implement the safety performance objective.

  11. CITON involvement in CETRAD project on 'Education and training in radiation protection and radioactive waste'

    International Nuclear Information System (INIS)

    Comsa, Olivia; Meglea, Claudia; Banutoiu, Marina; Paraschiva, M. V.; Meglea, S.

    2003-01-01

    Within the European Community and world-wide there is extensive experience in the principles and practice of radiation protection and radioactive waste management. Nuclear skills and capabilities have grown and evolved since the inception of nuclear technology in the 1940s. However, with the current stagnation of the nuclear industry it is increasingly acknowledged that the skills and expertise held by the generation who grew up with nuclear technology are being passed on to new generations of experts. This poses a significant risk to the community who will need to manage nuclear liabilities for long times into the future in order to protect future society from radiological hazards. Notwithstanding that the state of the art in nuclear waste management is undoubtedly high in many organizations, it is very clear that there is continuous need for the provision of education and training in this area. The various training and education programmes throughout Europe are at different stages of development. There is undoubtedly a need for harmonization of the numerous programmes and there would be great benefit to countries at early stages of development due to the learning experiences from the more developed organizations. The objective of CETRAD is to develop proposals for structuring and delivering both education and training in the management of the geological disposal of long-lived radioactive waste and radiation protection across Europe. This proposal is seen as a forerunner of a more comprehensive pan-European Network in this area, which it is planned, will emerge from this work. The project activities will be carried out in two phases. Phase 1 will involve national evaluations of both the needs for education and training and the existing infrastructure and resources in the field of radiation protection and radioactive waste management. Phase 2 will involve development of specific proposals for education and training based on the needs identified in Phase 1. (authors)

  12. The Midwest Proton Radiation Institute project at the Indiana University Cyclotron Facility

    Energy Technology Data Exchange (ETDEWEB)

    Anferov, V; Broderick, B; Collins, J C; Friesel, D L; Jenner, D; Jones, W P; Katuin, J; Klein, S B; Starks, W; Self, J; Schreuder, N [IUCF, Bloomington, Indiana 47408 (United States)

    2001-12-12

    The IUCF cyclotrons ceased delivering particle beams for physics research and became dedicated medical proton beam accelerators in 1999. Removal of the beam lines and nuclear research facilities associated with the cyclotrons to make room for the new medical beam delivery systems was completed in October, 2000. A new achromatic beam line was completed, extending from the main stage cyclotron and ending at a temporary research platform. This beam line is being commissioned during ongoing applied research. The achromatic line will deliver 0.5 {mu}A of 205 MeV protons from which the treatment room technician may draw current at any time via fast switching, laminated magnets located at the entrances to the energy selection systems upstream of each of the treatment rooms. Three treatment rooms are planned, one containing two fixed horizontal lines and two gantry rooms. The cyclotrons will also support full time research in radiation effects, single event upset, radiation biology and pre-clinical research. This contribution describes the status of the medical construction project.

  13. International panoram and Spanish contribution to the dissemination and evaluation of reference data for the ionizing radiations: Project BANDRRI

    International Nuclear Information System (INIS)

    Los Arcos, J.M.; Gonzalez, A.; Bailador, A.; Gonzalez, A.; Sanchez, E.; Gorostiza, C.; Ortiz, F.

    1998-01-01

    The present work shows the international panorama of the diverse sources of reference data commonly used in the environment of the radiations ionizantes, as well as the organized Spanish contribution recently around the project of the database of Reference for the radiations ionizantes (BANDRRI), developed jointly by the Unit of Metrology of Ionizing Radiations (UMRI) of the center of Environmental and Technological Investigations (CIEMAT), clerk of the Ministry of Industry and Spanish Energy, the University of Education to Distance and the Address of Computer science of the CIEMAT

  14. Review of Research Projects on Qualitative and Quantitative Effects of Radiation on Haematopoietic Tissue in Man and Experimental Animal

    Energy Technology Data Exchange (ETDEWEB)

    Hilberg, A. W. [Division of Radiological Health, Department of Health, Education and Welfare, Rockville, MD (United States)

    1967-07-15

    By way of introduction to a review of Research Projects of the Division of Radiological Health concerned with effects of radiation on the haematopoietic tissue in man and the experimental animal, I should like first to discuss briefly the organization of research. Our research is organized into three major disciplines: (1) Epidemiology, (2) Radiation biology, and (3) Environmental sciences. Briefly, epidemiology is concerned with studies, of populations and effects of radiation in.man; radiation biology is concerned with effects in the experimental animal under controlled situations and also concerned with basic research in cellular and sub-cellular effects; and environmental science is concerned with transport mechanisms in the biosphere and how these mechanisms may operate and be interrupted to reduce radiation hazard to man.

  15. A Green Approach to SNF Reprocessing: Are Common Household Reagents the Answer?

    International Nuclear Information System (INIS)

    Peper, Shane M.; McNamara, Bruce K.; O'Hara, Matthew J.; Douglas, Matthew

    2008-01-01

    It has been discovered that UO2, the principal component of spent nuclear fuel (SNF), can efficiently be dissolved at room temperature using a combination of common household reagents, namely hydrogen peroxide, baking soda, and ammonia. This rather serendipitous discovery opens up the possibility, for the first time, of considering a non-acidic process for recycling U from SNF. Albeit at the early stages of development, our unconventional dissolution approach possesses many attractive features that could make it a reality in the future. With dissolution byproducts of water and oxygen, our approach poses a minimal threat to the environment. Moreover, the use of common household reagents to afford actinide oxide dissolution suggests a certain degree of economic favorability. With the use of a ''closed'' digestion vessel as a reaction chamber, our approach has substantial versatility with the option of using either aqueous or gaseous reactant feeds or a combination of both. Our approach distinguishes itself from all existing reprocessing technologies in two important ways. First and foremost, it is an alkaline rather than an acidic process, using mild non-corrosive chemicals under ambient conditions to effect actinide separations. Secondly, it does not dissolve the entire SNF matrix, but rather selectively solubilizes U and other light actinides for subsequent separation, resulting in potentially faster head-end dissolution and fewer downstream separation steps. From a safeguards perspective, the use of oxidizing alkaline solutions to effect actinide separations also potentially offers a degree of inherent proliferation resistance, by allowing the U to be selectively removed from the remaining dissolver solution while keeping Pu grouped with the other minor actinides and fission products. This paper will describe the design and general experimental setup of a 'closed' digestion vessel for performing uranium oxide dissolutions under alkaline conditions using gaseous

  16. A Green Approach to SNF Reprocessing: Are Common Household Reagents the Answer?

    Energy Technology Data Exchange (ETDEWEB)

    Peper, Shane M.; McNamara, Bruce K.; O' Hara, Matthew J.; Douglas, Matthew

    2008-04-03

    It has been discovered that UO2, the principal component of spent nuclear fuel (SNF), can efficiently be dissolved at room temperature using a combination of common household reagents, namely hydrogen peroxide, baking soda, and ammonia. This rather serendipitous discovery opens up the possibility, for the first time, of considering a non-acidic process for recycling U from SNF. Albeit at the early stages of development, our unconventional dissolution approach possesses many attractive features that could make it a reality in the future. With dissolution byproducts of water and oxygen, our approach poses a minimal threat to the environment. Moreover, the use of common household reagents to afford actinide oxide dissolution suggests a certain degree of economic favorability. With the use of a “closed” digestion vessel as a reaction chamber, our approach has substantial versatility with the option of using either aqueous or gaseous reactant feeds or a combination of both. Our approach distinguishes itself from all existing reprocessing technologies in two important ways. First and foremost, it is an alkaline rather than an acidic process, using mild non-corrosive chemicals under ambient conditions to effect actinide separations. Secondly, it does not dissolve the entire SNF matrix, but rather selectively solubilizes U and other light actinides for subsequent separation, resulting in potentially faster head-end dissolution and fewer downstream separation steps. From a safeguards perspective, the use of oxidizing alkaline solutions to effect actinide separations also potentially offers a degree of inherent proliferation resistance, by allowing the U to be selectively removed from the remaining dissolver solution while keeping Pu grouped with the other minor actinides and fission products. This paper will describe the design and general experimental setup of a “closed” digestion vessel for performing uranium oxide dissolutions under alkaline conditions using

  17. Downregulation of SWI/SNF chromatin remodeling factor subunits modulates cisplatin cytotoxicity

    International Nuclear Information System (INIS)

    Kothandapani, Anbarasi; Gopalakrishnan, Kathirvel; Kahali, Bhaskar; Reisman, David; Patrick, Steve M.

    2012-01-01

    Chromatin remodeling complex SWI/SNF plays important roles in many cellular processes including transcription, proliferation, differentiation and DNA repair. In this report, we investigated the role of SWI/SNF catalytic subunits Brg1 and Brm in the cellular response to cisplatin in lung cancer and head/neck cancer cells. Stable knockdown of Brg1 and Brm enhanced cellular sensitivity to cisplatin. Repair kinetics of cisplatin DNA adducts revealed that downregulation of Brg1 and Brm impeded the repair of both intrastrand adducts and interstrand crosslinks (ICLs). Cisplatin ICL-induced DNA double strand break repair was also decreased in Brg1 and Brm depleted cells. Altered checkpoint activation with enhanced apoptosis as well as impaired chromatin relaxation was observed in Brg1 and Brm deficient cells. Downregulation of Brg1 and Brm did not affect the recruitment of DNA damage recognition factor XPC to cisplatin DNA lesions, but affected ERCC1 recruitment, which is involved in the later stages of DNA repair. Based on these results, we propose that SWI/SNF chromatin remodeling complex modulates cisplatin cytotoxicity by facilitating efficient repair of the cisplatin DNA lesions. -- Highlights: ► Stable knockdown of Brg1 and Brm enhances cellular sensitivity to cisplatin. ► Downregulation of Brg1 and Brm impedes the repair of cisplatin intrastrand adducts and interstrand crosslinks. ► Brg1 and Brm deficiency results in impaired chromatin relaxation, altered checkpoint activation as well as enhanced apoptosis. ► Downregulation of Brg1 and Brm affects recruitment of ERCC1, but not XPC to cisplatin DNA lesions.

  18. Problems and solutions of the spent nuclear fuel (SNF) at Kozloduy NPP

    International Nuclear Information System (INIS)

    Jordanov, J.

    2003-01-01

    There are two options concerning spent nuclear fuel: to return it back to Russia for reprocessing or to store it on the site until we decide what to do with it. In both options prior to the shutting down of each reactor the Spent Fuel Pool thereto should be vacated (the filling in of the equipment at present is illustrated) and the Spent Fuel Storage Facility (SFSF) should also be vacated after the stop of the last nuclear facility on the site in order to be reequipped for permanent storage of the highly active wastes which will be returned in the country, if we submit the fuel for reprocessing; or of SNF, if we decide to leave them ultimately in Bulgaria. The difference is mainly in the quantities which will permanently remain here, respectively the volumes required for their storage and the funds necessary for the implementation of the processes. The pool volumes filling in both variants is also illustrated and the SFSF will be filled by 2008, if no fuel is transported.Costs of the SNF transport to Russia and investment costs of dry storage of SNF from pools 1 - 4 are present. The costs are visibly lower compared to those in the case of return of the fuel. However, these are only investments for construction and equipment of the buildings and storage containers. The costs related to their servicing are not included, and it should be taken into account that in approximately 50 years we will have to seek solution for their permanent storage. Despite the material costs to be incurred now for the implementation of the option with the return of the fuel, this is the more worthy way to resolve the problem. In accordance with the ethic principles in the nuclear energy, the burdens arising as a result of the use of nuclear facilities should be covered by the generation consuming the benefits from it

  19. The SNF2-family member Fun30 promotes gene silencing in heterochromatic loci.

    Directory of Open Access Journals (Sweden)

    Ana Neves-Costa

    2009-12-01

    Full Text Available Chromatin regulates many key processes in the nucleus by controlling access to the underlying DNA. SNF2-like factors are ATP-driven enzymes that play key roles in the dynamics of chromatin by remodelling nucleosomes and other nucleoprotein complexes. Even simple eukaryotes such as yeast contain members of several subfamilies of SNF2-like factors. The FUN30/ETL1 subfamily of SNF2 remodellers is conserved from yeasts to humans, but is poorly characterized. We show that the deletion of FUN30 leads to sensitivity to the topoisomerase I poison camptothecin and to severe cell cycle progression defects when the Orc5 subunit is mutated. We demonstrate a role of FUN30 in promoting silencing in the heterochromatin-like mating type locus HMR, telomeres and the rDNA repeats. Chromatin immunoprecipitation experiments demonstrate that Fun30 binds at the boundary element of the silent HMR and within the silent HMR. Mapping of nucleosomes in vivo using micrococcal nuclease demonstrates that deletion of FUN30 leads to changes of the chromatin structure at the boundary element. A point mutation in the ATP-binding site abrogates the silencing function of Fun30 as well as its toxicity upon overexpression, indicating that the ATPase activity is essential for these roles of Fun30. We identify by amino acid sequence analysis a putative CUE motif as a feature of FUN30/ETL1 factors and show that this motif assists Fun30 activity. Our work suggests that Fun30 is directly involved in silencing by regulating the chromatin structure within or around silent loci.

  20. Current status of development in dry pyro-electrochemical technology of SNF reprocessing

    International Nuclear Information System (INIS)

    Bychkov, A.V.; Skiba, O.V.; Kormilitsyn, M.V.

    2004-01-01

    The technology of SNF management in molten salts currently developed by a group of institutes headed by RIAR has had several stages of development: - basic research of uranium, plutonium and main FP properties (investigation and reprocessing of different kinds of SNF in 1960 - 1970); - development of the equipment and implementation of the pyro-electrochemical technology of granulated UPu fuel production. Development of the vibro-packing method and in-pile testing of vibro-packed fuel pins with granulated fuel as the most 'logical' continuation of reprocessing: implementation of the technology for BOR-60 and BN-600 (1980 - 1990); - development of closed fuel cycle elements. Checking of the technology using batches of SNF. In-pile tests. Feasibility study of the closed fuel cycle (CFC). Study of application of the technology to other objects (transmutation; nitride, cermet and other fuels) (1980 - 1990). The current status of the research is the following: - Basic research. Properties of uranium, plutonium, thorium, and neptunium in chloride melts have been studied in much detail. The data on physical chemistry and electrochemistry of the main FP is enough for understanding the processes. Detailed studies of americium, curium, and technetium chemistry are the essential investigation directions; - Engineering development. The technology and equipment bases have been developed for the processes of oxide fuel reprocessing and fabrication. The technology was checked using 5500 kg of pure fuel from different reactors and 20 kg of irradiated BN-350 and BOR-60 fuel. The bases of the technology have been provided and the feasibility study has been carried out for a full-scale plant of BN-800 CFC; - Industrial application: Since the technology is highly prepared, the activities on industrial application of U-Pu fuel are now underway. The BOR-60 reactor uses fuel obtained by the dry method, the design of the facility for implementation of CFC reactors is being developed. 9

  1. Confirmation of an ARID2 defect in SWI/SNF-related intellectual disability.

    Science.gov (United States)

    Van Paemel, Ruben; De Bruyne, Pauline; van der Straaten, Saskia; D'hondt, Marleen; Fränkel, Urlien; Dheedene, Annelies; Menten, Björn; Callewaert, Bert

    2017-11-01

    We present a 4-year-old girl with delayed neuromotor development, short stature of prenatal onset, and specific behavioral and craniofacial features harboring an intragenic deletion in the ARID2 gene. The phenotype confirmed the major features of the recently described ARID2-related intellectual disability syndrome. However, our patient showed overlapping features with Nicolaides-Baraitser syndrome and Coffin-Siris syndrome, providing further arguments to reclassify these disorders as "SWI/SNF-related intellectual disability syndromes." © 2017 Wiley Periodicals, Inc.

  2. Radionuclide Inventories for DOE SNF Waste Stream and Uranium/Thorium Carbide Fuels

    International Nuclear Information System (INIS)

    K.L. Goluoglu

    2000-01-01

    The objective of this calculation is to generate radionuclide inventories for the Department of Energy (DOE) spent nuclear fuel (SNF) waste stream destined for disposal at the potential repository at Yucca Mountain. The scope of this calculation is limited to the calculation of two radionuclide inventories; one for all uranium/thorium carbide fuels in the waste stream and one for the entire waste stream. These inventories will provide input in future screening calculations to be performed by Performance Assessment to determine important radionuclides

  3. OPEN RADIATION: a collaborative project for radioactivity measurement in the environment by the public

    Science.gov (United States)

    Bottollier-Depois, Jean-François; Allain, E.; Baumont, G.; Berthelot, N.; Clairand, I.; Couvez, C.; Darley, G.; Henry, B.; Jolivet, T.; Laroche, P.; Lebau-Livé, A.; Lejeune, V.; Miss, J.; Monange, W.; Quéinnec, F.; Richet, Y.; Simon, C.; Trompier, F.; Vayron, F.

    2017-09-01

    After the Fukushima accident, initiatives emerged from the public to carry out themselves measurements of the radioactivity in the environment with various devices, among which smartphones, and to share data and experiences through collaborative tools and social networks. Such measurements have two major interests, on the one hand, to enable each individual of the public to assess his own risk regarding the radioactivity and, on the other hand, to provide "real time" data from the field at various locations, especially in the early phase of an emergency situation, which could be very useful for the emergency management. The objective of the OPENRADIATION project is to offer to the public the opportunity to be an actor for measurements of the radioactivity in the environment using connected dosimetric applications on smartphones. The challenge is to operate such a system on a sustainable basis in peaceful time and be useful in case of emergency. In "peaceful situation", this project is based on a collaborative approach with the aim to get complementary data to the existing ones, to consolidate the radiation background, to generate alerts in case of problem and to provide education & training and enhanced pedagogical approaches for a clear understanding of measures for the public. In case of emergency situation, data will be available "spontaneously" from the field in "real time" providing an opportunity for the emergency management and the communication with the public. … The practical objective is i) to develop a website centralising data from various systems/dosimeters, providing dose maps with raw and filtered data and creating dedicated areas for specific initiatives and exchanges of data and ii) to develop a data acquisition protocol and a dosimetric application using a connected dosimeter with a bluetooth connection. This project is conducted within a partnership between organisms' representative of the scientific community and associations to create links

  4. Radionuclide migration at sites of temporary storage of SNF and RW in North-West Russia - Contribution to regulatory development

    International Nuclear Information System (INIS)

    Sneve, M.K.; Shandala, N.K.; Orlova, E.I.; Titov, A.V.; Kochetkov, O.A.; Smith, G.M.; Barraclough, I.M.

    2007-01-01

    Two technical bases of the Northern Fleet were created in the Russian northwest in the 1960s at Andreeva in the Kola Bay and Gremikha village on the coast of the Barents Sea. They maintained nuclear submarines, performing receipt and storage of radioactive waste and spent nuclear fuel. No further stored material was received after 1985. These technical bases have since been re-categorised as sites of temporary storage. It is necessary to note that, during the storage of RW and SNF, certain conditions arose which resulted in failure of the storage barrier system, resulting in release of radionuclides. Remediation activities at the site focus on reduction of major risks associated with most hazardous radioactive source terms. In addition, the long term management of the sites includes consideration of how to remediate contaminated areas, not only because they affect continuing work at the site, but also because this work will influence final radiological status of the sites. The optimum approach to remediation will be affected by how quickly radionuclides could move, both during the remediation works and, so far as any residual activity is concerned, after the works are completed. Present investigations reported here are directed to determination of sorption-desorption parameters of radionuclides in the studied areas, which will affect their underground migration, with the purpose of accounting for regional peculiarities in optimization process of the STSs remediation. The work is being carried out by the TSO State Research Centre - Institute of Biophysics, of Russian Federation, with assistance from western experts. The work forms part of a regulatory collaboration programme on-going between the Norwegian Radiation Protection Authority and the Federal Medical-Biological Agency which is designed to support the development of norms and standards to be applied in the remediation of these sites of temporary storage. (author)

  5. Interrelation of technologies for RW preparation and sites for final isolation of the wastes from pyrochemical processing of SNF

    Energy Technology Data Exchange (ETDEWEB)

    Gupalo, V.S.; Chistyakov, V.N. [JSC - Design-Prospecting and Scientific-Research Institute of Industrial Technology -, Kashirskoye Highway, 33, Moscow 115409 (Russian Federation); Kormilitsyn, M.V.; Kormilitsyna, L.A. [JSC - State Scientific Center - Research Institute of Atomic Reactors -, Ulyanovsk region, Dimitrovgrad - 10, 433510 (Russian Federation)

    2013-07-01

    For the justification of engineering solutions and practical testing of the radiochemical component of the perspective nuclear power complex with on-site variant of nuclear fuel cycle (NFC), it is planned to establish a multi-functional research-development complex (MFCRC) for radiochemical processing of spent nuclear fuels (SNF) from fast reactors. MFCRC is being established at the NIIAR site, it comprises technological process lines, where innovation pyro-electrochemical and hydrometallurgical technologies are realized, with an option for closing the inter-chain material flows for testing the combined radiochemically converted materials. The technological flowchart for processing at the MFCRC is subdivided into 3 segments: -) complex of the lead operations for dismantling the fuel elements (FE) and fuel assemblies (FA), -) pyrochemical extraction flowchart for processing SNF, and -) hydrometallurgical flowchart for processing SNF. The engineered solutions for the management and disposition of the radioactive wastes from MFCRC are reviewed.

  6. Proceedings of the symposium on the joint research project between JAERI and Universities. Status and perspective of the advanced radiation technology project

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-06-01

    This report describes the Proceedings of the Symposium on the Joint Research Project between JAERI and Universities -Status and Perspective of the Advanced Radiation Technology Project-, held at Tokyo on January 27, 1999. After a series of conferences which had been held at the second or third year to present the main activities of this unique collaborative project system, the symposium was particularly focused on critical reviewing of the project and on its future. The scientific papers presented were the recent achievements in the themes: 1) nuclear spectroscopy and nuclear materials science with an isotope separator on-line; 2) radiation shielding and nuclear data for use of accelerators; 3) materials analysis methods using ion beams; 4) microstructure in polymer materials irradiated with ions; 5) effects of transmutation products in fusion-reactor materials; 6) physiological study of plants using positron-emitting isotopes. The new theme titled 'Development and application of micro PIXE analysis in the atmospheric pressure' was proposed. Eight panelists discussed the future of the project. The 17 papers are indexed individually. (J.P.N.)

  7. Mammography with and without radiolucent positioning sheets : Comparison of projected breast area, pain experience, radiation dose and technical image quality

    NARCIS (Netherlands)

    Timmers, Janine; ten Voorde, Marloes; van Engen, Ruben E.; van Landsveld-Verhoeven, Cary; Pijnappel, Ruud; Droogh-de Greve, Kitty; den Heeten, Gerard J.; Broeders, Mireille J. M.

    2015-01-01

    Purpose: To compare projected breast area, image quality, pain experience and radiation dose between mammography performed with and without radiolucent positioning sheets. Methods: 184 women screened in the Dutch breast screening programme (May-June 2012) provided written informed consent to have

  8. Mammography with and without radiolucent positioning sheets: Comparison of projected breast area, pain experience, radiation dose and technical image quality

    NARCIS (Netherlands)

    Timmers, Janine; ten Voorde, Marloes; van Engen, Ruben E.; van Landsveld-Verhoeven, Cary; Pijnappel, Ruud; Droogh-de Greve, Kitty; den Heeten, Gerard J.; Broeders, Mireille J. M.

    2015-01-01

    To compare projected breast area, image quality, pain experience and radiation dose between mammography performed with and without radiolucent positioning sheets. 184 women screened in the Dutch breast screening programme (May-June 2012) provided written informed consent to have one additional image

  9. Breast compression and radiation dose in two different mammographic oblique projections: 45 and 60 deg

    International Nuclear Information System (INIS)

    Brnic, Zoran; Hebrang, Andrija

    2001-01-01

    Introduction: Standard mammography includes two views, craniocaudal and medio-lateral oblique. Depending on patient's body constitution, central beam angle in mediolateral oblique projection may vary, with 45 deg. being suitable for the majority of patients in routine daily practice. With continuous improvement in X-ray technology and radiographers' training, the risk of radiation induced cancerogenesis is considerably reduced and acceptable when compared to benefit. However, the risk still exists, being cumulative and directly related to absorbed glandular dose. There is no minimal dose of radiation which is absolutely harmless, and every effort to reduce the dose is welcome. In this retrospective study two different angles (45 vs. 60 deg.) of mediolateral oblique view were compared according to radiation dose and efficacy of breast compression. Patients and methods: In 52 women, additional 60 deg. oblique films were done after craniocaudal and mediolateral oblique 45 deg.-films, with the same kVp and positioning technique. Breast thickness, time-current products (mA s) and absorbed doses were compared between 45 deg. - and 60 deg.-films. Subgroups of women with large, small, prominent and pendulous breasts were analyzed separately, following the same methodology as for the whole group. Results: mA s were 11.5% lower and compression 7% better with an angle of 60 deg. than with 45 deg. In the subgroup of women with small breasts, mA s values were 13% lower and compression 9% better with 60 deg. than with 45 deg., while in the subgroup with large breasts, mA s were 9% lower and compression 5% better. In the subgroup of patients with pendulous breasts, mA s values were 12% lower and compression 10% better with 60 deg. than with 45 deg., while in the subgroup with prominent breasts, mA s values were 4% lower and compression 3% better. Absorbed glandular dose was estimated to be approximately 20% lower when an oblique mammogram was done with 60 deg. instead of 45 deg

  10. Preliminary results of radiation monitoring near uranium mines in Namibia EJOLT Project (DRAFT version)

    International Nuclear Information System (INIS)

    Chareyron, Bruno

    2012-01-01

    As a part of the EJOLT (Environmental Justice Organizations Liability and Trade) project, EARTHLIFE Namibia and CRIIRAD (Commission for Independent Research and Information about Radiation) have organised visits in areas located in the vicinity of uranium mines in Namibia In the course of an on site mission carried out between September 22 and October 2 2011, scientists from the CRIIRAD laboratory took radiation measurements in situ, and collected 14 samples of top soil, 13 samples of surface sediments of the Swakop, Gawib and Khan rivers, 11 underground water samples in the alluvium of Swakop, and Khan rivers and tap water from Arandis city, and one sample of asparagus. Solid samples have been analysed at the CRIIRAD laboratory in France (measurements performed by HpGe gamma spectrometry) and water samples have been monitored for main chemicals by LDA 26 laboratory in France and for radium 226 and radon 222 at the CRIIRAD laboratory. Some of the preliminary findings are summarised in this report: 1 - The dose rate measured by CRIIRAD on the parking of Roessing mine is about 6 times above natural background value (0.9 μSv/h compared to 0.15 μSv/h); 2 - The management of waste rock dumps needs to be improved: Some waste rocks are dumped on the banks of Khan river (at the intersection with Dome Gorge) without fencing and confinement. The radiological impact of this activity has to be studied in detail but preliminary measurements show various impacts on the environment; 3 - The finest fraction of the radioactive tailings dumped on Roessing tailings dam is blown away by the wind and contaminates the surrounding environment; 4 - The high uranium concentration in underground water collected downstream Roessing uranium mine in the Khan river and Swakop river alluvium raises the question of the origin of this uranium

  11. Preliminary results of radiation monitoring near uranium mines in Namibia EJOLT Project (DRAFT version)

    Energy Technology Data Exchange (ETDEWEB)

    Chareyron, Bruno

    2012-04-05

    As a part of the EJOLT (Environmental Justice Organizations Liability and Trade) project, EARTHLIFE Namibia and CRIIRAD (Commission for Independent Research and Information about Radiation) have organised visits in areas located in the vicinity of uranium mines in Namibia In the course of an on site mission carried out between September 22 and October 2 2011, scientists from the CRIIRAD laboratory took radiation measurements in situ, and collected 14 samples of top soil, 13 samples of surface sediments of the Swakop, Gawib and Khan rivers, 11 underground water samples in the alluvium of Swakop, and Khan rivers and tap water from Arandis city, and one sample of asparagus. Solid samples have been analysed at the CRIIRAD laboratory in France (measurements performed by HpGe gamma spectrometry) and water samples have been monitored for main chemicals by LDA 26 laboratory in France and for radium 226 and radon 222 at the CRIIRAD laboratory. Some of the preliminary findings are summarised in this report: 1 - The dose rate measured by CRIIRAD on the parking of Roessing mine is about 6 times above natural background value (0.9 {mu}Sv/h compared to 0.15 {mu}Sv/h); 2 - The management of waste rock dumps needs to be improved: Some waste rocks are dumped on the banks of Khan river (at the intersection with Dome Gorge) without fencing and confinement. The radiological impact of this activity has to be studied in detail but preliminary measurements show various impacts on the environment; 3 - The finest fraction of the radioactive tailings dumped on Roessing tailings dam is blown away by the wind and contaminates the surrounding environment; 4 - The high uranium concentration in underground water collected downstream Roessing uranium mine in the Khan river and Swakop river alluvium raises the question of the origin of this uranium

  12. The international project of radiation and hydrochemical investigation and monitoring of general Caspian rivers

    International Nuclear Information System (INIS)

    Passell, H.D.; Barber, D.S.; Kadyrzhanov, K.K; Solodukhin, V.P.; Chernykh, E.E.; Arutyunyan, R.V.; Valyaev, A.N.; Kadik, A.A.; Stepanetts, O.V; Vernadsky, V.I.; Alizade, A.A.; Gutiev, I.S.; Mamedov, R.F.; Nadareishvili, K.S.; Chkhartishvili, A.G.; Tsitskishvili, M.S.; Chubaryan, E. V; Gevorgyan, R.G.; Puskyulyan, K.I.

    2005-01-01

    Full text: The scientific community of six countries (USA, Kazakhstan, Russia, Georgia, Armenia, and Azerbaijan) has developed the ecological project 'Joint International Researches and Creation of the General System of Radiation and Hydro-chemical Monitoring of Rivers of the Caspian Sea Basin.' The purpose of this project is to investigate and characterized contamination by radionuclides and toxic and chemically hazardous elements and create a valid system of radiation and hydro-chemical monitoring of the main river basins of the Caspian region: the Volga, Ural, Emba and Kura. The basins of these rivers cover large parts of Europe and Asia, including parts of Russia, West Kazakhstan and the South Caucasus and including territories of Georgia, Armenia and Azerbaijan. The total area of the basins of these rivers exceeds combined area of such large European states as France, Spain and Germany, and comprises 1631 sq. km. All these rivers are the main life-supporting water arteries for the region's inhabitants, a population that comprises tens of millions of people Also, the outlets of these rivers determine the condition of the aquatic environment of the Caspian Sea. The ecological condition of the aquatic environment of all the rivers of the Caspian Sea is to a great extent due to contamination, the main components of which are anthropogenic radioactive elements, heavy metals and oil products. At present, information about contamination levels of these rivers is not known and is occasionally contradictory. In this connection there is an obvious need of qualified investigation of contamination levels and its character in the basins of these rivers and in creating a common monitoring system to assess the quality of the aquatic environment. The present project is devoted to this matter. 1. The project provides for the following main tasks: 1. Wide-ranging investigation of the level and character of contamination by radionuclides and toxic elements of the river basins

  13. A novel Snf2 protein maintains trans-generational regulatory states established by paramutation in maize.

    Directory of Open Access Journals (Sweden)

    Christopher J Hale

    2007-10-01

    Full Text Available Paramutations represent heritable epigenetic alterations that cause departures from Mendelian inheritance. While the mechanism responsible is largely unknown, recent results in both mouse and maize suggest paramutations are correlated with RNA molecules capable of affecting changes in gene expression patterns. In maize, multiple required to maintain repression (rmr loci stabilize these paramutant states. Here we show rmr1 encodes a novel Snf2 protein that affects both small RNA accumulation and cytosine methylation of a proximal transposon fragment at the Pl1-Rhoades allele. However, these cytosine methylation differences do not define the various epigenetic states associated with paramutations. Pedigree analyses also show RMR1 does not mediate the allelic interactions that typically establish paramutations. Strikingly, our mutant analyses show that Pl1-Rhoades RNA transcript levels are altered independently of transcription rates, implicating a post-transcriptional level of RMR1 action. These results suggest the RNA component of maize paramutation maintains small heterochromatic-like domains that can affect, via the activity of a Snf2 protein, the stability of nascent transcripts from adjacent genes by way of a cotranscriptional repression process. These findings highlight a mechanism by which alleles of endogenous loci can acquire novel expression patterns that are meiotically transmissible.

  14. Progress in realization of the state policy in RW and SNF Management in the Russian Federation

    International Nuclear Information System (INIS)

    Borzunov, Andrey I.

    1999-01-01

    The basic infrastructure at the majority of the enterprises for management of radioactive waste (RW) and spent nuclear fuel (SNF) built in Russia in the 1960s and 1970s are now morally and technically obsolete and require reconstruction. As stated in this presentation, the most complicated problem is the shortage of financial resources, and International support is very important. The presentation is organised in sections discussing (1) the problem, (2) basic aspects of the State policy in this field, (3) the federal institutions in charge, (4) the principles upon which the State policy is grounded, (5) the main objectives of the RW and SNF management in Russia, (6) the federal programme: Radioactive wastes and spent nuclear materials management, their disposal and burial for the period 1996-2005, (7) plans for impending solution of the problems of the Northern and Pacific regions of Russia, (8) some top priority work of Minatom, (9) measures planned at the Russian power plants, (10) some basic results so far, (11) international co-operation

  15. Coffin-Siris syndrome is a SWI/SNF complex disorder.

    Science.gov (United States)

    Tsurusaki, Y; Okamoto, N; Ohashi, H; Mizuno, S; Matsumoto, N; Makita, Y; Fukuda, M; Isidor, B; Perrier, J; Aggarwal, S; Dalal, A B; Al-Kindy, A; Liebelt, J; Mowat, D; Nakashima, M; Saitsu, H; Miyake, N; Matsumoto, N

    2014-06-01

    Coffin-Siris syndrome (CSS) is a congenital disorder characterized by intellectual disability, growth deficiency, microcephaly, coarse facial features, and hypoplastic or absent fifth fingernails and/or toenails. We previously reported that five genes are mutated in CSS, all of which encode subunits of the switch/sucrose non-fermenting (SWI/SNF) ATP-dependent chromatin-remodeling complex: SMARCB1, SMARCA4, SMARCE1, ARID1A, and ARID1B. In this study, we examined 49 newly recruited CSS-suspected patients, and re-examined three patients who did not show any mutations (using high-resolution melting analysis) in the previous study, by whole-exome sequencing or targeted resequencing. We found that SMARCB1, SMARCA4, or ARID1B were mutated in 20 patients. By examining available parental samples, we ascertained that 17 occurred de novo. All mutations in SMARCB1 and SMARCA4 were non-truncating (missense or in-frame deletion) whereas those in ARID1B were all truncating (nonsense or frameshift deletion/insertion) in this study as in our previous study. Our data further support that CSS is a SWI/SNF complex disorder. © 2013 John Wiley & Sons A/S. Published by John Wiley & Sons Ltd.

  16. Progress in realization of the state policy in RW and SNF Management in the Russian Federation

    Energy Technology Data Exchange (ETDEWEB)

    Borzunov, Andrey I

    1999-07-01

    The basic infrastructure at the majority of the enterprises for management of radioactive waste (RW) and spent nuclear fuel (SNF) built in Russia in the 1960s and 1970s are now morally and technically obsolete and require reconstruction. As stated in this presentation, the most complicatedproblem is the shortage of financial resources, and International support is very important. The presentation is organised in sections discussing (1) the problem, (2) basic aspects of the State policy in this field, (3) the federal institutions in charge, (4) the principles upon which the State policy is grounded, (5) the main objectives of the RW and SNF management in Russia, (6) the federal programme: Radioactive wastes and spent nuclear materials management, their disposal and burial for the period 1996-2005, (7) plans for impending solution of the problems of the Northern and Pacific regions of Russia, (8) some top priority work of Minatom, (9) measures planned at the Russian power plants, (10) some basic results so far, (11) international co-operation.

  17. Revitalized citizen projects for Fukushima's radiation and nuclear disaster issues and introduction of the integrated programs relative to radiation education, exercise guidance, and development support at Tokushima University

    International Nuclear Information System (INIS)

    Sakama, Minoru; Nakayama, Shintaro; Saze, Takuya

    2017-01-01

    As for the purpose of this project, 'Revitalized Residential Projects for Fukushima's Radiological and Nuclear Disaster Issues at Tokushima University', the organization of the special mission which is constructed in staffs with volunteer sprits at universities and research facilities have collaborated together with elementary and junior high school teachers and the local government at the revitalized areas in Fukushima. They have built and practiced the new learning education model to bring up the children in there who are not defeated by uneasiness and the rumor of the radiation pollutions relative to the nuclear disaster of Fukushima Dai-ichi Nuclear Power Plant. For children carrying the future only at Fukushima but also in Japan, we bring up hope and the smile of them by coordinating their education to feed the resistance from an early stage to every rumor. By carrying on it we have set up with an integrated goal of getting that we can breed vitality and relief of the whole local community. Our radiation hazard support team at Tokushima University worked on urgent radiation exposure screening at Fukushima from the beginning of earthquake disaster. We had worked on support activities such as the radiation protection education, and also made efforts for the uneasiness reduction of citizens and reducing burdens on the local government. Until now we have kept up with working on the medium-and-long term trials of uneasiness reductions due to radiation properties and radiation hazards for local inhabitants and staffs such as any companies and the local government through practicing these programs, civilian learning society, staff learning society, learning society and counselling for mother and the child, radiation measurement, decontamination advice, and radioactivity measurement support, in particular, at Shirakawa City located as the doorway city of Tohoku area. This report introduces an outline of collaborated programs that we have developed in this project

  18. Spent Nuclear Fuel Project document control and Records Management Program Description

    International Nuclear Information System (INIS)

    MARTIN, B.M.

    2000-01-01

    The Spent Nuclear Fuel (SNF) Project document control and records management program, as defined within this document, is based on a broad spectrum of regulatory requirements, Department of Energy (DOE) and Project Hanford and SNF Project-specific direction and guidance. The SNF Project Execution Plan, HNF-3552, requires the control of documents and management of records under the auspices of configuration control, conduct of operations, training, quality assurance, work control, records management, data management, engineering and design control, operational readiness review, and project management and turnover. Implementation of the controls, systems, and processes necessary to ensure compliance with applicable requirements is facilitated through plans, directives, and procedures within the Project Hanford Management System (PHMS) and the SNF Project internal technical and administrative procedures systems. The documents cited within this document are those which directly establish or define the SNF Project document control and records management program. There are many peripheral documents that establish requirements and provide direction pertinent to managing specific types of documents that, for the sake of brevity and clarity, are not cited within this document

  19. Spent Nuclear Fuel Project Document Management Plan

    International Nuclear Information System (INIS)

    Connor, M.D.; Harizison, G.L.; Rice, W.C.

    1995-12-01

    The SNF Project Document Management Plan identifies and describes the currently available systems and processes for implementing and maintaining an effective document control and records management program. This program governs the methods by which documents are generated, released, distributed, maintained current, retired, and ultimately disposed

  20. Emergency monitoring strategy and radiation measurements document of the NKS project emergency management and radiation monitoring in nuclear and radiological accidents (EMARAD)

    Energy Technology Data Exchange (ETDEWEB)

    Lahtinen, J. [Radiation and Nuclear Safety Authority (STUK) (Finland)

    2006-04-15

    This report is one of the deliverables of the NKS Project Emergency management and radiation monitoring in nuclear and radiological accidents (EMARAD) (20022005). The project and the overall results are briefly described in the NKS publication 'Emergency Management and Radiation Monitoring in Nuclear and Radiological Accidents. Summary Report on the NKS Project EMARAD' (NKS-137, April 2006). In a nuclear or radiological emergency, all radiation measurements must be performed efficiently and the results interpreted correctly in order to provide the decision-makers with adequate data needed in analysing the situation and carrying out countermeasures. Managing measurements in different situations in a proper way requires the existence of pre-prepared emergency monitoring strategies. Preparing a comprehensive yet versatile strategy is not an easy task to perform because there are lots of different factors that have to be taken into account. The primary objective of this study was to discuss the general problematics concerning emergency monitoring strategies and to describe a few important features of an efficient emergency monitoring system as well as factors affecting measurement activities in practise. Some information concerning the current situation in the Nordic countries has also been included. (au)

  1. Emergency monitoring strategy and radiation measurements. Working document of the NKS project emergency management and radiation monitoring in nuclear and radiological accidents (EMARAD)

    International Nuclear Information System (INIS)

    Lahtinen, J.

    2006-04-01

    This report is one of the deliverables of the NKS Project Emergency management and radiation monitoring in nuclear and radiological accidents (EMARAD) (20022005). The project and the overall results are briefly described in the NKS publication 'Emergency Management and Radiation Monitoring in Nuclear and Radiological Accidents. Summary Report on the NKS Project EMARAD' (NKS-137, April 2006). In a nuclear or radiological emergency, all radiation measurements must be performed efficiently and the results interpreted correctly in order to provide the decision-makers with adequate data needed in analysing the situation and carrying out countermeasures. Managing measurements in different situations in a proper way requires the existence of pre-prepared emergency monitoring strategies. Preparing a comprehensive yet versatile strategy is not an easy task to perform because there are lots of different factors that have to be taken into account. The primary objective of this study was to discuss the general problematics concerning emergency monitoring strategies and to describe a few important features of an efficient emergency monitoring system as well as factors affecting measurement activities in practise. Some information concerning the current situation in the Nordic countries has also been included. (au)

  2. Contributions of projected land use to global radiative forcing ascribed to local sources

    Science.gov (United States)

    Ward, D. S.; Mahowald, N. M.; Kloster, S.

    2013-12-01

    With global demand for food expected to dramatically increase and put additional pressures on natural lands, there is a need to understand the environmental impacts of land use and land cover change (LULCC). Previous studies have shown that the magnitude and even the sign of the radiative forcing (RF) of biogeophysical effects from LULCC depends on the latitude and forest ecology of the disturbed region. Here we ascribe the contributions to the global RF by land-use related anthropogenic activities to their local sources, organized on a grid of 1.9 degrees latitude by 2.5 degrees longitude. We use RF estimates for the year 2100, using five future LULCC projections, computed from simulations with the National Center for Atmospheric Research Community Land Model and Community Atmosphere Models and additional offline analyses. Our definition of the LULCC RF includes changes to terrestrial carbon storage, methane and nitrous oxide emissions, atmospheric chemistry, aerosol emissions, and surface albedo. We ascribe the RF to gridded locations based on LULCC-related emissions of relevant trace gases and aerosols, including emissions from fires. We find that the largest contributions to the global RF in year 2100 from LULCC originate in the tropics for all future scenarios. In fact, LULCC is the largest tropical source of anthropogenic RF. The LULCC RF in the tropics is dominated by emissions of CO2 from deforestation and methane emissions from livestock and soils. Land surface albedo change is rarely the dominant forcing agent in any of the future LULCC projections, at any location. By combining the five future scenarios we find that deforested area at a specific tropical location can be used to predict the contribution to global RF from LULCC at that location (the relationship does not hold as well in the extratropics). This information could support global efforts like REDD (Reducing Emissions from Deforestation and Forest Degradation), that aim to reduce greenhouse gas

  3. Alpha-risk: a European project on the quantification of risks associated with multiple radiation exposures

    International Nuclear Information System (INIS)

    Laurier, D.; Monchaux, G.; Tirmarche, M.; Darby, S.; Cardis, E.; Binks, K.; Hofmann, W.; Muirhead, C.

    2006-01-01

    The Alpha-Risk research project is being conducted within the Sixth European Framework Programme (EC-FP6, 2005 -2008). It aims to improve the quantification of risks associated with multiple exposures, taking into account the contribution of different radionuclides and external exposure using specific organ dose calculations. The Alpha-Risk Consortium involves 18 partners from 9 countries, and is coordinated by the IRSN. Its composition allows a multidisciplinary collaboration between researchers in epidemiology, dosimetry, statistics, modelling and risk assessment. Alpha-Risk brings together major epidemiological studies in Europe, which are able to evaluate long-term health effects of internal exposure from radionuclides. It includes large size cohort and case-control studies, with accurate registration of individual annual exposures: uranium miner studies, studies on lung cancer and indoor radon exposure, and studies of lung cancer and leukaemia among nuclear workers exposed to transuranic nuclides (mainly uranium and plutonium), for whom organ doses will be reconstructed individually. The contribution of experts in dosimetry will allow the calculation of organ doses in presence of multiple exposures (radon decay products, uranium dust and external gamma exposure). Expression of the risk per unit organ dose will make it possible to compare results with those from other populations exposed to external radiation. The multidisciplinary approach of Alpha-Risk promotes the development of coherent and improved methodological approaches regarding risk modelling. A specific work - package is dedicated to the integration of results and their use for risk assessment, especially for radon. Alpha-Risk will contribute to a better understanding of long-term health risks following chronic low doses from internal exposures. The project also has the great potential to help resolve major public health concerns about the effects of low and/or protracted exposures, especially

  4. Using an Ongoing Study of Terrestrial Plant Response to Ultraviolet Radiation in Project ALERT

    Science.gov (United States)

    Condon, Estelle; Skiles, J. W.; Seitz, Jeffery C.; Dantoni, Hector L.

    1998-01-01

    The ALERT (Augmented Learning Environment for Renewable Teaching) Project is a cooperative California-based program with two main partners: California State University (CSU) geoscience and education departments and two NASA Centers, the Jet Propulsion Laboratory (JPL) in Pasadena and the Ames Research Center (ARC) in Mountain View. This paper presents an example of how a NASA research effort can be used in the undergraduate classroom. A study, now in the fourth year, subjects test plants to exposures of varying solar ultraviolet (UV) radiation (280 - 340 nm); a full solar UV exposure, a solar UV exposure less about 14% of ambient UV flux, and a UV-blocked regime. This experiment is simple in that only modest amounts of expense are required yet it is elegant since only one variable, UV-flux is involved. The experiment lends itself to teaching several of the Earth Sciences because it uses information from botany, taxonomy, and ecology. Aspects of physics are inherent in the study since portions of the electromagnetic spectrum are studied. Further, since only one of many variables are manipulated, UV flux, the study demonstrates how the scientific method is used in formulating and testing hypotheses. Based on the ALERT experience this summer, this study will be implemented at a CSU campus with the expectation that it will serve as a pedagogical tool and where it will involve students in actual research.

  5. Measurements and radiation tests on scintillating fibres for the LHCb SciFi project

    CERN Document Server

    Joram, Christian; Shatalov, Pavel

    2014-01-01

    This note describes a number of measurements and a radiation test performed on the baseline fibre of the LHCb SciFi upgrade project. These include measurements of the optical attenuation length - globally and wavelength resolved -, measurements of the photoelectric yield, and finally the assessment of the impact of proton irradiation on these quantities. The fibres were irradiated at the CERN PS with 24 GeV/c protons up to a fluence of 7•10$^{13}$ p/cm$^2$ equivalent to an ionizing dose of about 22 kGy. Measurements on the fibres, in particular in view of possible recovery effects, are still ongoing and the report is expected to be updated in the coming months. This report is meant as backup document for the LHCb internal SciFi review in February 2013. It had to be produced in a short available time. Missing information will be added and style as well as formatting will be improved in the forthcoming version.

  6. Off-site radiation exposure review project: computer-aided surface interpolation and graphical display

    International Nuclear Information System (INIS)

    Foley, T.A. Jr.

    1981-08-01

    This report presents the implementation of an iterative procedure that solves the following bivariate interpolation problem: Given N distinct points in the plane (x/sub i/, y/sub i/) and N real numbers Z/sub i/, construct a function F(x,y) that satisfies F(x/sub i/, y/sub i/) = Z/sub i/, for i = 1, ..., N. This problem can be interpreted as fitting a surface through N points in three dimensional space. The application of primary concern to the Offsite Radiation Exposure Review Project is the characterization of the radionuclide activity resulting from nuclear tests. Samples of activity were measured at various locations. The location of the sample point is represented by (x/sub i/, y/sub i/), and the magnitude of the reading is represented by Z/sub i/. The method presented in this report is constructed to be efficient on large data sets, stable on the large variations of the Z/sub i/ magnitudes, and capable of smoothly filling in areas that are void of data. This globally defined icode was initiateminednitial shock but to two later eriological invaders are Staphylococcus albus, Beta-hemolytic Streptococcus e to the same general semiclassical treatment

  7. Solar energy R + D programme, 1979-1983. Project F: solar radiation data

    Energy Technology Data Exchange (ETDEWEB)

    1981-01-01

    Individual presentations report work in the following areas: production of test reference years for model simulation of solar systems and components; global radiation atlas for horizontal surfaces; radiation data on inclined surfaces; intensity thresholds and cumulative frequency curves; useful energy output from solar collectors; network comparison of pyranometers; measurements of turbidity, spectral radiation, etc.; satellite data. (LEW)

  8. Hydroacoustic measurements of the radiated noise from Wave Energy Converters in the Lysekil project and project WESA

    OpenAIRE

    Haikonen, Kalle; Sundberg, Jan; Leijon, Mats

    2013-01-01

    Field measurements of the hydroacoustic noise from Wave Energy Converters (WECs) in the Lysekil project at Uppsala University and the Project WESA (joint effort between Uppsala University (Lead Partner), Ålands Teknikkluster r.f. and University of Turku) are presented. Anthropogenic noise is increasing in the oceans world wide and wave energy conversion may contribute to this noise, but to what extent? The main objective in this study is to examine the noise from full scale operating WECs in ...

  9. Correlation between scatter radiation dose at the height of the operators eye and dose to patient for different angiographies projections

    Energy Technology Data Exchange (ETDEWEB)

    Leyton, F.; Nogueira, M. S.; Da Silva, T. A. [Centro de Desenvolvimento da Tecnologia Nuclear / CNEN, Post-graduation in Sciences and Technology of Radiations, Minerals and Materials, Pte. Antonio Carlos No. 6627, Belo Horizonte 31270-901, Minas Gerais (Brazil); Gubolino, L.; Pivetta, M. R. [Hospital dos Fornecedores de Cana de Piracicaba, Av. Barao de Valenca 616, 13405-233 Piracicaba (Brazil); Ubeda, C., E-mail: leyton.fernando@gmail.com [Tarapaca University, Health Sciences Faculty, Radiological Sciences Center, Av. Gral. Velasquez 1775, 1000007 Arica, Arica and Parinacota (Chile)

    2015-10-15

    Cases of radiation induced cataract among cardiology professionals have been reported in studies. In view of evidence of radiation injuries, the ICRP recommends limiting the radiation dose to the lens to 20 mSv per year for occupational exposure. The aim of this works was to report scattered radiation doses at the height of the operators eye in an interventional cardiology facility from procedures performed without use of radiation protection devices, correlated with different angiographic projections and operational modes. Measurements were made in a cardiac laboratory with an angiography X-ray system GE equipped with flat-panel detector. PMMA plates of 30 x 30 x 5 cm were used to simulate a patient with a thickness of 20 cm. Two fluoroscopy modes (low and normal, 15 frame/s), cine mode 15 frame/s. Four angiographic projections anterior posterior (Ap), lateral (Lat), left anterior oblique caudal (spider) and left anterior oblique cranial (Lao-45/cra-30) and a cardiac protocol for patient between 70 to 90 kg was used. Measurements of phantom entrance doses rate and scatter doses rate were performed with two Unfors Xi plus. The detector measuring scatter radiation was positioned at the usual distance of the cardiologists eyes during working conditions (1 m from the isocenter and 1.7 m from the floor). There is a good linear correlation between the kerma-area product and scatter dose at the lens. An experimental correlation factor of 2.3; 12.0; 12.2 and 17.6 μSv/Gy cm{sup 2} were found for the Ap, Lao/cra, spider and Lat projections, respectively. The entrance dose of PMMA for fluoroscopy low, medium and cine was 13, 39 and 282 mGy/min, respectively to Ap. (Author)

  10. Correlation between scatter radiation dose at the height of the operators eye and dose to patient for different angiographies projections

    International Nuclear Information System (INIS)

    Leyton, F.; Nogueira, M. S.; Da Silva, T. A.; Gubolino, L.; Pivetta, M. R.; Ubeda, C.

    2015-10-01

    Cases of radiation induced cataract among cardiology professionals have been reported in studies. In view of evidence of radiation injuries, the ICRP recommends limiting the radiation dose to the lens to 20 mSv per year for occupational exposure. The aim of this works was to report scattered radiation doses at the height of the operators eye in an interventional cardiology facility from procedures performed without use of radiation protection devices, correlated with different angiographic projections and operational modes. Measurements were made in a cardiac laboratory with an angiography X-ray system GE equipped with flat-panel detector. PMMA plates of 30 x 30 x 5 cm were used to simulate a patient with a thickness of 20 cm. Two fluoroscopy modes (low and normal, 15 frame/s), cine mode 15 frame/s. Four angiographic projections anterior posterior (Ap), lateral (Lat), left anterior oblique caudal (spider) and left anterior oblique cranial (Lao-45/cra-30) and a cardiac protocol for patient between 70 to 90 kg was used. Measurements of phantom entrance doses rate and scatter doses rate were performed with two Unfors Xi plus. The detector measuring scatter radiation was positioned at the usual distance of the cardiologists eyes during working conditions (1 m from the isocenter and 1.7 m from the floor). There is a good linear correlation between the kerma-area product and scatter dose at the lens. An experimental correlation factor of 2.3; 12.0; 12.2 and 17.6 μSv/Gy cm 2 were found for the Ap, Lao/cra, spider and Lat projections, respectively. The entrance dose of PMMA for fluoroscopy low, medium and cine was 13, 39 and 282 mGy/min, respectively to Ap. (Author)

  11. Development of a cryogenic EOS capability for the Z Pulsed Radiation Source: Goals and accomplishments of FY97 LDRD project

    International Nuclear Information System (INIS)

    Hanson, D.L.; Johnston, R.R.; Asay, J.R.

    1998-03-01

    Experimental cryogenic capabilities are essential for the study of ICF high-gain target and weapons effects issues involving dynamic materials response at low temperatures. This report describes progress during the period 2/97-11/97 on the FY97 LDRD project ''Cryogenic EOS Capabilities on Pulsed Radiation Sources (Z Pinch)''. The goal of this project is the development of a general purpose cryogenic target system for precision EOS and shock physics measurements at liquid helium temperatures on the Z accelerator Z-pinch pulsed radiation source. Activity during the FY97 LDRD phase of this project has focused on development of a conceptual design for the cryogenic target system based on consideration of physics, operational, and safety issues, design and fabrication of principal system components, construction and instrumentation of a cryogenic test facility for off-line thermal and optical testing at liquid helium temperatures, initial thermal testing of a cryogenic target assembly, and the design of a cryogenic system interface to the Z pulsed radiation source facility. The authors discuss these accomplishments as well as elements of the project that require further work

  12. Correlation between scatter radiation dose at height of operator's eye and dose to patient for different angiographic projections

    International Nuclear Information System (INIS)

    Leyton, Fernando; Nogueira, Maria S.; Gubolino, Luiz A.; Pivetta, Makyson R.; Ubeda, Carlos

    2016-01-01

    Studies have reported cases of radiation-induced cataract among cardiology professionals. In view of the evidence of epidemiological studies, the ICRP recommends a new threshold for opacities and a new radiation dose to eye lens limit of 20 mSv per year for occupational exposure. The aim of this paper is to report scattered radiation doses at the height of the operator's eye in an interventional cardiology facility without considering radiation protection devices and to correlate these values with different angiographic projections and operational modes. Measurements were taken in a cardiac laboratory with an angiography X-ray system equipped with flat-panel detector. PMMA plates of 30×30×5 cm were used with a thickness of 20 cm. Measurements were taken in two fluoroscopy modes (low and normal, 15 pulses/s) and in cine mode (15 frames/s). Four angiographic projections were used: anterior posterior; lateral; left anterior oblique caudal (spider); and left anterior oblique cranial, with a cardiac protocol for patients weighing between 70 and 90 kg. Measurements of phantom entrance dose rate and scatter dose rate were performed with two Unfors Xi plus detectors. The detector measuring scatter radiation was positioned at the usual distance of the cardiologist's eyes during working conditions. There is a good linear correlation between the kerma area product and scatter dose at the lens. Experimental correlation factors of 2.3, 12.0, 12.2 and 17.6 μSv/Gy cm2 were found for different projections. PMMA entrance dose rates for low and medium fluoroscopy and cine modes were 13, 39 and 282 mGy/min, respectively, for AP projection. - Highlights: • A method is presented to estimate the scatter radiation dose at operator eye height. • The method allows estimating scatter radiation dose measuring ambient dose equivalent. • Operator could exceed threshold for lens opacities if protection tools are not used. • There is a good linear correlation between kerma

  13. Calculation Method for the Projection of Future Spent Nuclear Fuel Discharges

    International Nuclear Information System (INIS)

    B. McLeod

    2002-01-01

    This report describes the calculation method developed for the projection of future utility spent nuclear fuel (SNF) discharges in regard to their timing, quantity, burnup, and initial enrichment. This projection method complements the utility-supplied RW-859 data on historic discharges and short-term projections of SNF discharges by providing long-term projections that complete the total life cycle of discharges for each of the current U.S. nuclear power reactors. The method was initially developed in mid-1999 to update the SNF discharge projection associated with the 1995 RW-859 utility survey (CRWMS M and O 1996). and was further developed as described in Rev. 00 of this report (CRWMS M and O 2001a). Primary input to the projection of SNF discharges is the utility projection of the next five discharges from each nuclear unit, which is provided via the revised final version of the Energy Information Administration (EIA) 1998 RW-859 utility survey (EIA 2000a). The projection calculation method is implemented via a set of Excel 97 spreadsheets. These calculations provide the interface between receipt of the utility five-discharge projections that are provided in the RW-859 survey, and the delivery of projected life-cycle SNF discharge quantities and characteristics in the format requisite for performing logistics analysis to support design of the Civilian Radioactive Waste Management System (CRWMS). Calculation method improvements described in this report include the addition of a reactor-specific maximum enrichment-based discharge burnup limit. This limit is the consequence of the enrichment limit, currently 5 percent. which is imposed as a Nuclear Regulatory Commission (NRC) license condition on nuclear fuel fabrication plants. In addition, the calculation method now includes the capability for projecting future nuclear plant power upratings, consistent with many such recent plant uprates and the prospect of additional future uprates. Finally. this report

  14. Demonstrating the Feasibility of Molten Aluminum for Destroying Polymeric Encapsulants in SNF-Bearing Metallographic Mounts. Final Technical Report

    International Nuclear Information System (INIS)

    Dan Stout; Scott Ploger

    2004-01-01

    DOE-owned spent nuclear fuel (SNF) rods have been cross sectioned and mounted for metallography throughout the history of nuclear reactors. Many hundreds of these ''met mounts'' have accumulated in storage across the DOE complex. However, because of potential hydrogen generation from radiolysis of the polymeric encapsulants, the met mounts are problematic for eventual disposal in a geologic repository

  15. Fanconi anemia protein, FANCA, associates with BRG1, a component of the human SWI/SNF complex.

    Science.gov (United States)

    Otsuki, T; Furukawa, Y; Ikeda, K; Endo, H; Yamashita, T; Shinohara, A; Iwamatsu, A; Ozawa, K; Liu, J M

    2001-11-01

    Fanconi anemia (FA) is a genetic disorder that predisposes to hematopoietic failure, birth defects and cancer. We identified an interaction between the FA protein, FANCA and brm-related gene 1 (BRG1) product. BRG1 is a subunit of the SWI/SNF complex, which remodels chromatin structure through a DNA-dependent ATPase activity. FANCA was demonstrated to associate with the endogenous SWI/SNF complex. We also found a significant increase in the molecular chaperone, glucose-regulated protein 94 (GRP94) among BRG1-associated factors isolated from a FANCA-mutant cell line, which was not seen in either a normal control cell line or the mutant line complemented by wild-type FANCA. Despite this specific difference, FANCA did not appear to be absolutely required for in vitro chromatin remodeling. Finally, we demonstrated co-localization in the nucleus between transfected FANCA and BRG1. The physiological action of FANCA on the SWI/SNF complex remains to be clarified, but our work suggests that FANCA may recruit the SWI/SNF complex to target genes, thereby enabling coupled nuclear functions such as transcription and DNA repair.

  16. Chromatin-remodeling SWI/SNF complex regulates coenzyme Q6 synthesis and a metabolic shift to respiration in yeast.

    Science.gov (United States)

    Awad, Agape M; Venkataramanan, Srivats; Nag, Anish; Galivanche, Anoop Raj; Bradley, Michelle C; Neves, Lauren T; Douglass, Stephen; Clarke, Catherine F; Johnson, Tracy L

    2017-09-08

    Despite its relatively streamlined genome, there are many important examples of regulated RNA splicing in Saccharomyces cerevisiae Here, we report a role for the chromatin remodeler SWI/SNF in respiration, partially via the regulation of splicing. We find that a nutrient-dependent decrease in Snf2 leads to an increase in splicing of the PTC7 transcript. The spliced PTC7 transcript encodes a mitochondrial phosphatase regulator of biosynthesis of coenzyme Q 6 (ubiquinone or CoQ 6 ) and a mitochondrial redox-active lipid essential for electron and proton transport in respiration. Increased splicing of PTC7 increases CoQ 6 levels. The increase in PTC7 splicing occurs at least in part due to down-regulation of ribosomal protein gene expression, leading to the redistribution of spliceosomes from this abundant class of intron-containing RNAs to otherwise poorly spliced transcripts. In contrast, a protein encoded by the nonspliced isoform of PTC7 represses CoQ 6 biosynthesis. Taken together, these findings uncover a link between Snf2 expression and the splicing of PTC7 and establish a previously unknown role for the SWI/SNF complex in the transition of yeast cells from fermentative to respiratory modes of metabolism. © 2017 by The American Society for Biochemistry and Molecular Biology, Inc.

  17. Standardization of Fat:SNF ratio of milk and addition of sprouted wheat fada (semolina) for the manufacture of halvasan.

    Science.gov (United States)

    Chaudhary, Apurva H; Patel, H G; Prajapati, P S; Prajapati, J P

    2015-04-01

    Traditional Indian Dairy Products such as Halvasan are manufactured in India using an age old practice. For manufacture of such products industrially, a standard formulation is required. Halvasan is a region specific, very popular heat desiccated milk product but has not been studied scientifically. Fat and Solids-not-fat (SNF) plays an important role in physico-chemical, sensory, textural characteristics and also the shelf life of any milk sweet. Hence for process standardization of Halvasan manufacture, different levels of Fat:SNF ratios i.e. 0.44, 0.55, 0.66 and 0.77 of milk were studied so that an optimum level yielding best organoleptic characteristics in final product can be selected. The product was made from milk standardized to these ratios of Fat:SNF and the product was manufactured as per the method tentatively employed on the basis of characterization of market samples of the product in laboratory. Based on the sensory results obtained, a Fat:SNF ratio of 0.66 for the milk has been selected. In the similar way, for standardizing the rate of addition of fada (semolina); 30, 40, 50 and 60 g fada (semolina) per kg of milk were added and based on the sensory observations, the level of fada (semolina) addition @50 gm/kg of milk was adjudged the best for Halvasan manufacture and hence selected.

  18. Process Evaluation of a Quality Improvement Project to Decrease Hospital Readmissions From Skilled Nursing Facilities.

    Science.gov (United States)

    Meehan, Thomas P; Qazi, Daniel J; Van Hoof, Thomas J; Ho, Shih-Yieh; Eckenrode, Sheila; Spenard, Ann; Pandolfi, Michelle; Johnson, Florence; Quetti, Deborah

    2015-08-01

    To describe and evaluate the impact of quality improvement (QI) support provided to skilled nursing facilities (SNFs) by a Quality Improvement Organization (QIO). Retrospective, mixed-method, process evaluation of a QI project intended to decrease preventable hospital readmissions from SNFs. Five SNFs in Connecticut. SNF Administrators, Directors of Nursing, Assistant Directors of Nursing, Admissions Coordinators, Registered Nurses, Certified Nursing Assistants, Receptionists, QIO Quality Improvement Consultant. QIO staff provided training and technical assistance to SNF administrative and clinical staff to establish or enhance QI infrastructure and implement an established set of QI tools [Interventions to Reduce Acute Care Transfers (INTERACT) tools]. Baseline SNF demographic, staffing, and hospital readmission data; baseline and follow-up SNF QI structure (QI Committee), processes (general and use of INTERACT tools), and outcome (30-day all-cause hospital readmission rates); details of QIO-provided training and technical assistance; QIO-perceived barriers to quality improvement; SNF leadership-perceived barriers, accomplishments, and suggestions for improvement of QIO support. Success occurred in establishing QI Committees and targeting preventable hospital readmissions, as well as implementing INTERACT tools in all SNFs; however, hospital readmission rates decreased in only 2 facilities. QIO staff and SNF leaders noted the ongoing challenge of engaging already busy SNF staff and leadership in QI activities. SNF leaders reported that they appreciated the training and technical assistance that their institutions received, although most noted that additional support was needed to bring about improvement in readmission rates. This process evaluation documented mixed clinical results but successfully identified opportunities to improve recruitment of and provision of technical support to participating SNFs. Recommendations are offered for others who wish to conduct

  19. Planning research on the next strategical project through the trend analysis on radiation fusion technology, industry and policy

    International Nuclear Information System (INIS)

    Kim, Dong Sub; Choi, Jae Hak; Kim, Tak Hyun

    2013-01-01

    Ο The planning research for establish a detailed implementation strategy to serve as small, but a strong institution leading national radiation research and resolving the pending issues related to using radiation - Now is a time when it needs a implementation strategy to achieve it's unique mission as the sole radiation-specialized research institute leading to promote the radiation industry. Ο The main background of this study is to build the planning of a new paradigm for research and development to cope with the changing domestic and international environment for sustainable growth - As the domestic regional radiation field is getting more competitive and the cooperative group expands, it needs to adapt to the global trend such as technology convergence and acceleration etc.. - The need for establish basic database to make a new strategy in order to narrow the technology gap in the radiation fusion technology comparing to the developed country and cope with emerging country's advancement in technology Ο The use to build basic database to spearhead the project and set aside a budget effectively - It's to be used as a reference to set aside a budget through planning strategy industry field to forecast the industrial demand and variation of the future policy and create blue ocean and niche markets

  20. Receipt capability for foreign research reactor (FRR) spent nuclear fuel (SNF) at the Savannah River Site (SRS)

    International Nuclear Information System (INIS)

    Clark, William D. Jr.

    1997-01-01

    The United Stated Department of Energy began implementation of the ten year FRR SNF return policy in May, 1996. Seventeen months into the thirteen year return program, four shipments have been made, returning 863 assemblies of aluminum clad SNF to SRS. Five additional shipments containing over 1,200 assemblies are scheduled in fiscal year 1998. During negotiation of contracts with various reactor operators, it has become apparent that many facilities wish to delay the return of their SNF until the latter part of the program. This has raised concern on the part of the DOE that insufficient receipt capability will exist during the last three to five years of the program to ensure the return of all of the SNF. To help quantify this issue and ensure that it is addressed early in the program, a computer simulation model has been developed at SRS to facilitate the planning, scheduling, and analysis of SNF shipments to be received from offsite facilities. The simulation model, called OFFSHIP, greatly reduces the time and effort required to analyze the complex global transportation system that involves dozens of reactor facilities, multiple casks and fuel types, and time-dependent SNF inventories. OFFSHIP allows the user to input many variables including priorities, cask preferences, shipping date preferences, turnaround times, and regional groupings. User input is easily managed using a spreadsheet format and the output data is generated in a spreadsheet format to facilitate detailed analysis and prepare graphical results. The model was developed in Microsoft Visual Basic for Applications and runs native in Microsoft Excel. The receipt schedules produced by the model have been compared to schedules generated manually with consistent results. For the purposes of this presentation, four scenarios have been developed. The 'Base Case' accounts for those countries/facilities that DOE believes may not participate in the return program. The three additional scenarios look at the

  1. Field studies on long term ecosystem consequences of ionising radiation and chemical pollutants (EANOR Project)

    Energy Technology Data Exchange (ETDEWEB)

    Oughton, D. [Centre for Environmental Radioactivity - CERAD (Norway); Evseeva, T. [Institute of Biology RAS (Russian Federation); Erenturk, S. [Istanbul Technical University (Turkey)

    2014-07-01

    Chernobyl and other nuclear accidents have demonstrated that high levels of ionizing radiation can result in impacts on plants and animals, however little is known about the long-term effects of chronic exposure on biodiversity or other population and ecosystem level effects. The issue of ecological impact has been addressed after the Fukushima accident, which has raised questions about the impacts of radioactivity not only on human health, but also on wildlife. The overall aim of the EANOR project (2012-2015) is to assess the impacts of chronic exposure to enhanced radioactivity and chemical pollutants by studying the diversity of plant and soil invertebrate populations at two field sites. The first is a radium contaminated site in the Vodny area of the Komi Republic, Russia. Between 1931 and 1956, this was the main location of Soviet radium production. Wastes from the industry caused contamination of the environment, leading to high levels of radionuclides, heavy metals and rare-earth elements in the surroundings. The prolonged exposure of the ecosystem, combined with relatively low human activities, makes the site an excellent field laboratory for investigating the long-term effects of pollution. The second site is metal mining (Fe, Au, Ag, Mn, Mo, Cu, Pb and Zn) and industrial area on the Eastern Black Sea Region, Turkey, having elevated levels of both heavy metals and radionuclides for many decades. Eastern Black Sea Region is a mountainous area covered with dense forests, where numerous rivers and torrents flow through gorges and is characterized by heavy rainfall, humid summers, and mild winters. Based on these conditions, the region is rich in biological diversity. Joint field expeditions have been carried out in 2012 and 2013 with the objective of documenting levels of radionuclides and other chemical contaminants in soils and organisms, and assessing plant and soil invertebrate biodiversity. Measurement of a range of biomarkers, including soil meta

  2. The Arabidopsis SWI/SNF protein BAF60 mediates seedling growth control by modulating DNA accessibility

    KAUST Repository

    Jégu, Teddy

    2017-06-15

    Plant adaptive responses to changing environments involve complex molecular interplays between intrinsic and external signals. Whilst much is known on the signaling components mediating diurnal, light, and temperature controls on plant development, their influence on chromatin-based transcriptional controls remains poorly explored.In this study we show that a SWI/SNF chromatin remodeler subunit, BAF60, represses seedling growth by modulating DNA accessibility of hypocotyl cell size regulatory genes. BAF60 binds nucleosome-free regions of multiple G box-containing genes, opposing in cis the promoting effect of the photomorphogenic and thermomorphogenic regulator Phytochrome Interacting Factor 4 (PIF4) on hypocotyl elongation. Furthermore, BAF60 expression level is regulated in response to light and daily rhythms.These results unveil a short path between a chromatin remodeler and a signaling component to fine-tune plant morphogenesis in response to environmental conditions.

  3. FY17 Status Report: Research on Stress Corrosion Cracking of SNF Interim Storage Canisters.

    Energy Technology Data Exchange (ETDEWEB)

    Schindelholz, Eric John [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Bryan, Charles R. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Alexander, Christopher L. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2017-09-01

    This progress report describes work done in FY17 at Sandia National Laboratories (SNL) to assess the localized corrosion performance of container/cask materials used in the interim storage of spent nuclear fuel (SNF). Of particular concern is stress corrosion cracking (SCC), by which a through-wall crack could potentially form in a canister outer wall over time intervals that are shorter than possible dry storage times. Work in FY17 refined our understanding of the chemical and physical environment on canister surfaces, and evaluated the relationship between chemical and physical environment and the form and extent of corrosion that occurs. The SNL corrosion work focused predominantly on pitting corrosion, a necessary precursor for SCC, and process of pit-to-crack transition; it has been carried out in collaboration with university partners. SNL is collaborating with several university partners to investigate SCC crack growth experimentally, providing guidance for design and interpretation of experiments.

  4. The Arabidopsis SWI/SNF protein BAF60 mediates seedling growth control by modulating DNA accessibility

    KAUST Repository

    Jé gu, Teddy; Veluchamy, Alaguraj; Ramirez Prado, Juan Sebastian; Rizzi-Paillet, Charley; Perez, Magalie; Lhomme, Anaï s; Latrasse, David; Coleno, Emeline; Vicaire, Serge; Legras, Sté phanie; Jost, Bernard; Rougé e, Martin; Barneche, Fredy; Bergounioux, Catherine; Crespi, Martin; Mahfouz, Magdy M.; Hirt, Heribert; Raynaud, Cé cile; Benhamed, Moussa

    2017-01-01

    Plant adaptive responses to changing environments involve complex molecular interplays between intrinsic and external signals. Whilst much is known on the signaling components mediating diurnal, light, and temperature controls on plant development, their influence on chromatin-based transcriptional controls remains poorly explored.In this study we show that a SWI/SNF chromatin remodeler subunit, BAF60, represses seedling growth by modulating DNA accessibility of hypocotyl cell size regulatory genes. BAF60 binds nucleosome-free regions of multiple G box-containing genes, opposing in cis the promoting effect of the photomorphogenic and thermomorphogenic regulator Phytochrome Interacting Factor 4 (PIF4) on hypocotyl elongation. Furthermore, BAF60 expression level is regulated in response to light and daily rhythms.These results unveil a short path between a chromatin remodeler and a signaling component to fine-tune plant morphogenesis in response to environmental conditions.

  5. Vertical Drop of the Naval SNF Long Waste Package On Unyielding Surface

    International Nuclear Information System (INIS)

    S. Mastilovic

    2006-01-01

    The purpose of this calculation is to determine the structural response of a Naval SNF (Spent Nuclear Fuel) Long Waste Package (WP) subjected to 2 m-vertical drop on unyielding surface (US). The scope of this document is limited to reporting the calculation results in terms of maximum stress intensities. This calculation is associated with the waste package design; calculation is performed by the Waste Package Design group. AP-3.12Q, Revision 0, ICN 0, Calculations, is used to perform the calculation and develop the document. The finite element calculation is performed by using the commercially available ANSYS Version (V) 5.4 finite element code. The result of this calculation is provided in terms of maximum stress intensities

  6. Candida albicans Swi/Snf and Mediator Complexes Differentially Regulate Mrr1-Induced MDR1 Expression and Fluconazole Resistance.

    Science.gov (United States)

    Liu, Zhongle; Myers, Lawrence C

    2017-11-01

    Long-term azole treatment of patients with chronic Candida albicans infections can lead to drug resistance. Gain-of-function (GOF) mutations in the transcription factor Mrr1 and the consequent transcriptional activation of MDR1 , a drug efflux coding gene, is a common pathway by which this human fungal pathogen acquires fluconazole resistance. This work elucidates the previously unknown downstream transcription mechanisms utilized by hyperactive Mrr1. We identified the Swi/Snf chromatin remodeling complex as a key coactivator for Mrr1, which is required to maintain basal and induced open chromatin, and Mrr1 occupancy, at the MDR1 promoter. Deletion of snf2 , the catalytic subunit of Swi/Snf, largely abrogates the increases in MDR1 expression and fluconazole MIC observed in MRR1 GOF mutant strains. Mediator positively and negatively regulates key Mrr1 target promoters. Deletion of the Mediator tail module med3 subunit reduces, but does not eliminate, the increased MDR1 expression and fluconazole MIC conferred by MRR1 GOF mutations. Eliminating the kinase activity of the Mediator Ssn3 subunit suppresses the decreased MDR1 expression and fluconazole MIC of the snf2 null mutation in MRR1 GOF strains. Ssn3 deletion also suppresses MDR1 promoter histone displacement defects in snf2 null mutants. The combination of this work with studies on other hyperactive zinc cluster transcription factors that confer azole resistance in fungal pathogens reveals a complex picture where the induction of drug efflux pump expression requires the coordination of multiple coactivators. The observed variations in transcription factor and target promoter dependence of this process may make the search for azole sensitivity-restoring small molecules more complicated. Copyright © 2017 American Society for Microbiology.

  7. Influence of the rate of conversion of HT and HTO on projected radiation doses from release of molecular tritium

    International Nuclear Information System (INIS)

    Jacobs, D.G.; Easterly, C.E.; Phillips, J.E.

    1979-01-01

    Releases of tritium in the past have been largely in the form of tritiated water, and the projected radiation doses could be estimated by assuming tritium behaviour to parallel that of water. There is increasing interest in potential releases of tritium in the form of HT because of significant recent advances in fusion reactor research. Several recent studies have shown that bacteria containing the enzyme hydrogenase can catalyse the conversion of HT to HTO at rates several orders of magnitude faster than the rates measured in atmospheric systems. Rates of conversion in the soil have been combined with estimates of rates of permeation of HT into the soil and with global and local models depicting tritium transport and cycling. The results suggest that for the expected conversion rates, the impact on projected radiation doses should be relatively minor. (author)

  8. Assessment results of the South Korea TRIGA SNF to be shipped to INEEL

    International Nuclear Information System (INIS)

    Cole, C.M.; Dirk, W.J.; Cottam, R.E.; Paik, S.T.

    1997-01-01

    This paper describes the Training, Research, Isotope, General Atomics (TRIGA) spent nuclear fuel (SNF) examination at the Seoul and the Taejon Research Reactor Facilities in South Korea. The examination was required before the SNF would be accepted for transportation and storage at the INEEL. The results of the aluminum and stainless steel clad TRIGA fuel examination have been summarized. A description of the examination team training, the examination work plan and examination equipment is also included. This paper also explains the technical basis for the examination and physical condition criteria used to determine what, if any, additional packaging would be required for transportation and for the receipt and storage of the fuel at the INEEL. This paper delineates the preparation activities prior to the fuel examinations and includes (1) collecting spent fuel data; (2) preparatory work by the Korean Atomic Energy Research Institute (KAERI) for fuel examination: (3) preparation of a radionuclide report, Radionuclide Mass Inventory, Activity, Decay Heat, and Dose Rate Parametric Data for TRIGA Spent Nuclear Fuels needed to provide input data for transportation and fuel acceptance at the Idaho National Engineering and Environmental Laboratory (INEEL); (4) gathering FRR Facility data; and (5) coordination between the INEEL and KAERI. Included, are the unanticipated conditions encountered in the unloading of fuel from the dry storage casks in Taejon in preparation for examination, a description of the damaged condition of the fuel removed from the casks, and the apparent cause of the damages. Lessons learned from all the activities are also addressed. A brief description of the preparatory work for the shipment of the spent fuel from Korea to INEEL is included

  9. Assessment results of the South Korea TRIGA SNF to be shipped to INEEL

    International Nuclear Information System (INIS)

    Cole, Charles M.; Dirk, Willam J.; Cottam, Russel E.; Paik, Sam T.

    1997-01-01

    This paper describes the Training, Research, Isotope, General Atomics (TRIGA) spent nuclear fuel (SNF) examination at the Seoul and the Taejon Research Reactor Facilities in South Korea. The examination was required before the SNF would be accepted for transportation and storage at the INEEL. The results of the aluminum and stainless steel clad TRIGA fuel examination have been summarized. A description of the examination team training, the examination work plan and examination equipment is also included. This paper also explains the technical basis for the examination and physical condition criteria used to determine what, if any, additional packaging (canning) would be required for transportation and for the receipt and storage of the fuel at the INEEL. This paper delineates the preparation activities prior to the fuel examinations and includes (1) collecting spent fuel data; (2) preparatory work by the Korean Atomic Energy Research Institute (KAERI) for fuel examination: (3) preparation of a radionuclide report, 'Radionuclide Mass Inventory, Activity, Decay Heat, and Dose Rate Parametric Data for TRIGA Spent Nuclear Fuels' needed to provide input data for transportation and fuel acceptance at the Idaho National Engineering and Environmental Laboratory (INEEL); (4) gathering FRR Facility data; (5) preparation of Appendix A; (6) and coordination between the INEEL and KAERI. Included, are the unanticipated conditions encountered in the unloading of fuel from the dry storage casks in Taejon in preparation for examination, a description of the damaged condition of the fuel removed from the casks, and the apparent cause of the damages. Lessons learned from all the activities are also addressed. A brief description of the preparatory work for the shipment of the spent fuel from Korea to INEEL is included. (author)

  10. JCCRER Project 2.3 -- Deterministic effects of occupational exposure to radiation. Phase 1: Feasibility study; Final report

    Energy Technology Data Exchange (ETDEWEB)

    Okladnikova, N.; Pesternikova, V.; Sumina, M. [Inst. of Biophysics, Ozyorsk (Russian Federation)] [and others

    1998-12-01

    Phase 1 of Project 2.3, a short-term collaborative Feasibility Study, was funded for 12 months starting on 1 February 1996. The overall aim of the study was to determine the practical feasibility of using the dosimetric and clinical data on the MAYAK worker population to study the deterministic effects of exposure to external gamma radiation and to internal alpha radiation from inhaled plutonium. Phase 1 efforts were limited to the period of greatest worker exposure (1948--1954) and focused on collaboratively: assessing the comprehensiveness, availability, quality, and suitability of the Russian clinical and dosimetric data for the study of deterministic effects; creating an electronic data base containing complete clinical and dosimetric data on a small, representative sample of MAYAK workers; developing computer software for the testing of a currently used health risk model of hematopoietic effects; and familiarizing the US team with the Russian diagnostic criteria and techniques used in the identification of Chronic Radiation Sickness.

  11. JCCRER Project 2.3 - Deterministic effects of occupational exposure to radiation. Phase 1: Feasibility study. Final report

    International Nuclear Information System (INIS)

    Okladnikova, N.; Pesternikova, V.; Sumina, M.

    1998-01-01

    Phase 1 of Project 2.3, a short-term collaborative Feasibility Study, was funded for 12 months starting on 1 February 1996. The overall aim of the study was to determine the practical feasibility of using the dosimetric and clinical data on the MAYAK worker population to study the deterministic effects of exposure to external gamma radiation and to internal alpha radiation from inhaled plutonium. Phase 1 efforts were limited to the period of greatest worker exposure (1948--1954) and focused on collaboratively: assessing the comprehensiveness, availability, quality, and suitability of the Russian clinical and dosimetric data for the study of deterministic effects; creating an electronic data base containing complete clinical and dosimetric data on a small, representative sample of MAYAK workers; developing computer software for the testing of a currently used health risk model of hematopoietic effects; and familiarizing the US team with the Russian diagnostic criteria and techniques used in the identification of Chronic Radiation Sickness

  12. The constructive solution of the Greifswald linear accelerator 'Neptun 10 p' project from the point of view of radiation protection

    International Nuclear Information System (INIS)

    Schmidt, W.; Waag, V.; Nadrowitz, R.; Wendorff, W.

    1981-01-01

    In 1981 the linear accelerator 'Neptun 10 p' will be mounted at the Radiological Clinic of the University of Greifswald. Its place will be an irradiation room which is equipped for a radiation of 1.33 MeV. The strengthening of walls and celling, which is necessary for 9 MeV bremsstrahlung and 10 MeV electron radiation, can only be realized by a self-supporting lead-steel construction for reasons of the distance to the neighbouring house and of the connected conditions of foundation as well as of the load capacity of the existing construction of the roof. As in the eighties similar problems are to be expected in other radiological hospitals of the GDR the constructive solution of the Greifswald linear accelerator project and connected problems of the radiation protection are represented. (author)

  13. Strengthening of an advanced automated radiation laboratory. Hungary. Terminal report project findings and recommendations

    International Nuclear Information System (INIS)

    1992-01-01

    An Advanced Automated Radiation Laboratory was completed; the hardware and software bases are now suitable for up-to-date kinetical measurements in radiation chemistry and technology both for Hungarian experts and for specialists from abroad. It would be possible and useful e.g. to organize further training courses in the field of radiation chemistry and technology by the IAEA and/or the UNDP, as well as to send fellows from developing countries for practical research work or other purposes (TCDC)

  14. Overview of research in radiation biology and protective measures in the Manhattan Project during the war years, 1942-1946

    International Nuclear Information System (INIS)

    Friedell, H.L.

    The objecitve was to present a cohesive view of the general biological research program associated with the Manhattan Project. The material is arrangd in chronological order. Each of the major research sites is identified and the general nature of their research program indicated. A section is devoted to the question of the various radiation limits which were used in the operational approach to hazard controls

  15. EXPERIENCE SANITARY-EPIDEMIOLOGICAL EXAMINATION PROJECT OF PLACING A SOURCE OF IONIZING RADIATION (GENERATING IN HEALTH CARE INSTITUTIONS

    Directory of Open Access Journals (Sweden)

    I. A. Rakitin

    2015-01-01

    Full Text Available The article reviews the results of long-term sanitary-epidemiological examination of projects of placing of ionizing radiation (generating sources in health care institutions of Saint-Petersburg. The majority among the placed sources presented for examination was X-ray diagnostic units and sets – 35.7%, dentist X-rays – 39.4% and fluorography units – 10.8%. Mammography units and computer tomographs made 6.7% each, accelerants – 0.7%.The most frequent reasons of primary refusals to accept design documentation were: absence of calculations of protection against all placed diagnostic X-ray devices (23.6% – at placing of diagnostic X-ray sets, 16.2% – at placing of dentist devices, absence of the upper floors layouts (26.5% – at placing of dentist X-rays and absence of permitting documentation for X-ray devices (at placing of dentist X-ray devices – 22.2%.At carrying out of design activity of special importance is creation of medical and technical projects which were absent in 22.9% of presented projects and in 34.6% were replaced with technical projects. Significant drawbacks of the projects were ignoring the necessity to consider the distance from the personnel workplaces and the width of technical passes (34.0%. That was caused by the absence of corresponding documentation from suppliers of equipment for X-ray rooms.At calculation of protection against X-ray radiation in 11.3% of projects of placing X-ray diagnostic devices (sets and in 7.7% of projects of placing dentist X-ray devices, radiation directivity factors (N were determined incorrectly.Of importance is the issue of adequate choice of building and finishing materials. In 50.0% of projects of placing of diagnostic X-ray devices (sets and 37.6% of projects of placing dentist X-ray devices there were no sanitary-epidemiological conclusions regarding the building and finishing materials to confirming their feasibility for healthcare institutions.Analysis of the main stages

  16. The pathway by which the yeast protein kinase Snf1p controls acquisition of sodium tolerance is different from that mediating glucose regulation.

    Science.gov (United States)

    Ye, Tian; Elbing, Karin; Hohmann, Stefan

    2008-09-01

    It recently became apparent that the highly conserved Snf1p protein kinase plays roles in controlling different cellular processes in the yeast Saccharomyces cerevisiae, in addition to its well-known function in glucose repression/derepression. We have previously reported that Snf1p together with Gis4p controls ion homeostasis by regulating expression of ENA1, which encodes the Ena1p Na(+) extrusion system. In this study we found that Snf1p is rapidly phosphorylated when cells are exposed to NaCl and this phosphorylation is required for the role of Snf1p in Na(+) tolerance. In contrast to activation by low glucose levels, the salt-induced phosphorylation of Snf1p promoted neither phosphorylation nor nuclear export of the Mig1p repressor. The mechanism that prevents Mig1p phosphorylation by active Snf1p under salt stress does not involve either hexokinase PII or the Gis4p regulator. Instead, Snf1p may mediate upregulation of ENA1 expression via the repressor Nrg1p. Activation of Snf1p in response to glucose depletion requires any of the three upstream protein kinases Sak1p, Tos3p and Elm1p, with Sak1p playing the most prominent role. The same upstream kinases were required for salt-induced Snf1p phosphorylation, and also under these conditions Sak1p played the most prominent role. Unexpectedly, however, it appears that Elm1p plays a dual role in acquisition of salt tolerance by activating Snf1p and in a presently unknown parallel pathway. Together, these results indicate that under salt stress Snf1p takes part in a different pathway from that during glucose depletion and this role is performed together as well as in parallel with its upstream kinase Elm1p. Snf1p appears to be part of a wider functional network than previously anticipated and the full complexity of this network remains to be elucidated.

  17. Projection of needs for gamma radiation sources and other radioisotopes and assessment of alternatives for providing radiation sources

    Energy Technology Data Exchange (ETDEWEB)

    Ross, W.A.; Jensen, G.A.; Clark, L.L.; Eakin, D.E.; Jarrett, J.H.; Katayama, Y.B.; McKee, R.W.; Morgan, L.G.; Nealey, S.M.; Platt, A.M.; Tingey, G.L.

    1989-06-01

    Pacific Northwest Laboratory reviewed the projected uses and demands for a variety of nuclear byproducts. Because the major large-scale near-term demand is for gamma irradiation sources, this report concentrates on the needs for gamma sources and evaluates the options for providing the needed material. Projections of possible growth in the irradiation treatment industry indicate that there will be a need for 180 to 320 MCi of /sup 60/Co (including /sup 137/Cs equivalent) in service in the year 2000. The largest current and projected use of gamma irradiation is for the sterilization of medical devices and disposable medical supplies. Currently, 40% of US disposable medical products are treated by irradiation, and within 10 years it is expected that 90% will be treated in this manner. Irradiation treatment of food for destruction of pathogens or parasites, disinfestation, or extension of allowable storage periods is estimated to require an active inventory of 75 MCi of /sup 60/Co-equivalent gamma source in about a decade. 90 refs., 7 figs., 25 tabs.

  18. Projection of needs for gamma radiation sources and other radioisotopes and assessment of alternatives for providing radiation sources

    International Nuclear Information System (INIS)

    Ross, W.A.; Jensen, G.A.; Clark, L.L.

    1989-06-01

    Pacific Northwest Laboratory reviewed the projected uses and demands for a variety of nuclear byproducts. Because the major large-scale near-term demand is for gamma irradiation sources, this report concentrates on the needs for gamma sources and evaluates the options for providing the needed material. Projections of possible growth in the irradiation treatment industry indicate that there will be a need for 180 to 320 MCi of 60 Co (including 137 Cs equivalent) in service in the year 2000. The largest current and projected use of gamma irradiation is for the sterilization of medical devices and disposable medical supplies. Currently, 40% of US disposable medical products are treated by irradiation, and within 10 years it is expected that 90% will be treated in this manner. Irradiation treatment of food for destruction of pathogens or parasites, disinfestation, or extension of allowable storage periods is estimated to require an active inventory of 75 MCi of 60 Co-equivalent gamma source in about a decade. 90 refs., 7 figs., 25 tabs

  19. Quality Assurance Program Plan for Project W-379: Spent Nuclear Fuels Canister Storage Building Projec

    International Nuclear Information System (INIS)

    Duncan, D.W.

    1995-01-01

    This document describes the Quality Assurance Program Plan (QAPP) for the Spent Nuclear Fuels (SNF) Canister Storage Building (CSB) Project. The purpose of this QAPP is to control project activities ensuring achievement of the project mission in a safe, consistent and reliable manner

  20. Dosimetry for radiation processing. Final report of the co-ordinated research project on characterization and evaluation of high dose dosimetry techniques for quality assurance in radiation processing

    International Nuclear Information System (INIS)

    2000-06-01

    In many Member States the use of large cobalt-60 gamma ray facilities and electron beam accelerators with beam energies from about 0.1 to 10 MeV for industrial processing continues to increase. For these processes, quality assurance relies on the application of well established dosimetry systems and procedures. This is especially the case for health regulated processes, such as the radiation sterilization of health care products, and the irradiation of food to eliminate pathogenic organisms or to control insect pests. A co-ordinated research project (CRP) was initiated by the IAEA in June 1995. Research contracts and research agreements in areas of high dose dosimetry were initiated to meet these challenges. The major goals of this CRP were to investigate the parameters that influence the response of dosimeters and to develop reference and transfer dosimetry techniques, especially for electron beams of energy less than 4 MeV and for high energy X ray sources (up to 5 MV). These will help to unify the radiation measurements performed by different radiation processing facilities and other high dose dosimetry users in Member States and encourage efforts to obtain traceability to primary and secondary standards laboratories. It will also aim to strengthen and expand the present International Dose Assurance Service (IDAS) provided by the IAEA

  1. Radiation protection research projects. Programme report 2013. Summary of results from recent research projects of the BMU's Applied Research Programme carried out under the responsibility of the German Office of Radiation Protection (BfS); Strahlenschutzforschung. Programmreport 2013. Bericht ueber das vom Bundesamt fuer Strahlenschutz fachlich begleitete und administrativ umgesetzte Forschungsprogramm Strahlenschutz des Bundesministeriums fuer Umwelt, Naturschutz, Bau und Reaktorsicherheit

    Energy Technology Data Exchange (ETDEWEB)

    Schmitt-Hannig, Annemarie; Goedde, Ralph; Loebke-Reinl, Angelika; Hachenberger, Claudia; Trugenberger-Schnabel, Angela (comps.)

    2014-09-15

    On behalf of the Federal Ministry for the Environment, Nature Conservation, Building and Nuclear Safety (BMUB) the Federal Office for Radiation Protection (BfS) awards research grants for projects in the field of radiation protection. The findings of these projects serve as decision aiding information in the development of radiation protection regulations as well as in the fulfilment of specific tasks in the field of radiation protection. Planning, technical and administrative preparation, awarding of contracts, general support as well as the technical evaluation of research and study projects are tasks of the Federal Office for Radiation Protection. This report provides information on preliminary (in the form of status reports) and, where applicable, final results of radiation protection projects within the BMUB's Environmental Research Plan for the year 2013.

  2. Radiation protection research projects. Programme report 2010. Summary of results from recent research projects of the BMU's Applied Research Programme carried out under the responsibility of the German Office of Radiation Protection (BfS); Strahlenschutzforschung. Programmreport 2010. Bericht ueber das vom Bundesamt fuer Strahlenschutz fachlich begleitete und administrativ umgesetzte Forschungsprogramm Strahlenschutz des Bundesministeriums fuer Umwelt, Naturschutz und Reaktorsicherheit

    Energy Technology Data Exchange (ETDEWEB)

    Bernhard-Stroel, Claudia; Goedde, Ralph; Hachenberger, Claudia; Loebke-Reinl, Angelika; Schmitt-Hannig, Annemarie

    2011-11-15

    On behalf of the Ministry for the Environment, Nature Conservation and Nuclear Safety (BMU) the Federal Office for Radiation Protection (BfS) awards research grants for projects in the field of radiation protection. The findings of these projects serve as decision aiding information in the development of radiation protection regulations as well as in the fulfilment of specific tasks in the field of radiation protection. Planning, technical and administrative preparation, awarding of contracts, general support as well as the technical evaluation of research and study projects are tasks of the Federal Office for Radiation Protection. This report provides information on preliminary and, where applicable, final results (in the form of status reports) of radiation protection projects within the BMU's Environmental Research Plan for the year 2010. (orig.)

  3. Radiation protection research projects. Programme report 2012. Summary of results from recent research projects of the BMU's Applied Research Programme carried out under the responsibility of the German Office of Radiation Protection (BfS); Strahlenschutzforschung. Programmreport 2012. Bericht ueber das vom Bundesamt fuer Strahlenschutz fachlich begleitete und administrativ umgesetzte Forschungsprogramm Strahlenschutz des Bundesministeriums fuer Umwelt, Naturschutz und Reaktorsicherheit

    Energy Technology Data Exchange (ETDEWEB)

    Bernhard-Stroel, Claudia; Goedde, Ralph; Hachenberger, Claudia; Loebke-Reinl, Angelika; Schmitt-Hannig, Annemarie; Trugenberger-Schnabel, Angela

    2013-12-15

    On behalf of the Ministry for the Environment, Nature Conservation and Nuclear Safety (BMU) the Federal Office for Radiation Protection (BfS) awards research grants for projects in the field of radiation protection. The findings of these projects serve as decision aiding information in the development of radiation protection regulations as well as in the fulfilment of specific tasks in the field of radiation protection. Planning, technical and administrative preparation, awarding of contracts, general support as well as the technical evaluation of research and study projects are tasks of the Federal Office for Radiation Protection. This report provides information on preliminary (in the form of status reports) and, where applicable, final results of radiation protection projects within the BMU's Environmental Research Plan for the year 2012.

  4. Radiation chemistry at the Metallurgical Laboratory, Manhattan Project, University of Chicago (1942-1947) and the Argonne National Laboratory, Argonne, IL (1947-1984)

    International Nuclear Information System (INIS)

    Gordon, S.

    1989-01-01

    The events in radiation chemistry which occurred in the Manhattan Project Laboratory and Argonne National Laboratory during World War II are reviewed. Research programmes from then until the present day are presented, with emphasis on pulse radiolysis studies. (UK)

  5. Final report on the project research 'assessment of radiation exposure of the public to radioactivities related to the environment and food chain'. April 1988 - March 1992

    International Nuclear Information System (INIS)

    1994-03-01

    This publication is the collection of the reports on the project research 'Assessment of Radiation Exposure of the Public to Radioactivities Related to the Environment and Food Chain'. The 16 of the reports are indexed individually. (J.P.N.)

  6. Comparison of the response of various TLDs to cosmic radiation and ion beams: Current results of the HAMLET project

    International Nuclear Information System (INIS)

    Bilski, P.; Berger, T.; Hajek, M.; Reitz, G.

    2011-01-01

    HAMLET is an European Commission research project aiming at optimal scientific exploitation of the data produced within the space experiment MATROSHKA. During phase 1 of this experiment a human phantom equipped with several thousands of radiation detectors (mainly TLDs) was exposed outside the International Space Station for 1.5 years. Besides the measurements realized in Earth orbit, the HAMLET project includes also a ground-based program of intercomparison of detector response to high-energy ion beams. Within the paper, the relative response of main glow-curve peaks of various TLDs (mostly based on LiF) used in frame of the MATROSHKA experiment by three laboratories (DLR Cologne, ATI Vienna and IFJ Krakow) for radiation in space and several ion beams, has been compared. For LiF:Mg,Ti detectors a very good agreement between results obtained by the three laboratories was observed, both for space and accelerator-based exposures. This should be considered a remarkable result, taking into account that the studied TLDs originated from six different batches, manufactured by two producers exploiting different production techniques and were processed by three laboratories, using significantly different protocols (annealing, readout, calibration, glow-curve analysis). Another type of TL detectors, LiF:Mg,Cu,P, was found to show response to cosmic radiation lower than that of LiF:Mg,Ti by 5%–18%.

  7. WE-AB-303-09: Rapid Projection Computations for On-Board Digital Tomosynthesis in Radiation Therapy

    International Nuclear Information System (INIS)

    Iliopoulos, AS; Sun, X; Pitsianis, N; Yin, FF; Ren, L

    2015-01-01

    Purpose: To facilitate fast and accurate iterative volumetric image reconstruction from limited-angle on-board projections. Methods: Intrafraction motion hinders the clinical applicability of modern radiotherapy techniques, such as lung stereotactic body radiation therapy (SBRT). The LIVE system may impact clinical practice by recovering volumetric information via Digital Tomosynthesis (DTS), thus entailing low time and radiation dose for image acquisition during treatment. The DTS is estimated as a deformation of prior CT via iterative registration with on-board images; this shifts the challenge to the computational domain, owing largely to repeated projection computations across iterations. We address this issue by composing efficient digital projection operators from their constituent parts. This allows us to separate the static (projection geometry) and dynamic (volume/image data) parts of projection operations by means of pre-computations, enabling fast on-board processing, while also relaxing constraints on underlying numerical models (e.g. regridding interpolation kernels). Further decoupling the projectors into simpler ones ensures the incurred memory overhead remains low, within the capacity of a single GPU. These operators depend only on the treatment plan and may be reused across iterations and patients. The dynamic processing load is kept to a minimum and maps well to the GPU computational model. Results: We have integrated efficient, pre-computable modules for volumetric ray-casting and FDK-based back-projection with the LIVE processing pipeline. Our results show a 60x acceleration of the DTS computations, compared to the previous version, using a single GPU; presently, reconstruction is attained within a couple of minutes. The present implementation allows for significant flexibility in terms of the numerical and operational projection model; we are investigating the benefit of further optimizations and accurate digital projection sub

  8. WE-AB-303-09: Rapid Projection Computations for On-Board Digital Tomosynthesis in Radiation Therapy

    Energy Technology Data Exchange (ETDEWEB)

    Iliopoulos, AS; Sun, X [Duke University, Durham, NC (United States); Pitsianis, N [Aristotle University of Thessaloniki (Greece); Duke University, Durham, NC (United States); Yin, FF; Ren, L [Duke University Medical Center, Durham, NC (United States)

    2015-06-15

    Purpose: To facilitate fast and accurate iterative volumetric image reconstruction from limited-angle on-board projections. Methods: Intrafraction motion hinders the clinical applicability of modern radiotherapy techniques, such as lung stereotactic body radiation therapy (SBRT). The LIVE system may impact clinical practice by recovering volumetric information via Digital Tomosynthesis (DTS), thus entailing low time and radiation dose for image acquisition during treatment. The DTS is estimated as a deformation of prior CT via iterative registration with on-board images; this shifts the challenge to the computational domain, owing largely to repeated projection computations across iterations. We address this issue by composing efficient digital projection operators from their constituent parts. This allows us to separate the static (projection geometry) and dynamic (volume/image data) parts of projection operations by means of pre-computations, enabling fast on-board processing, while also relaxing constraints on underlying numerical models (e.g. regridding interpolation kernels). Further decoupling the projectors into simpler ones ensures the incurred memory overhead remains low, within the capacity of a single GPU. These operators depend only on the treatment plan and may be reused across iterations and patients. The dynamic processing load is kept to a minimum and maps well to the GPU computational model. Results: We have integrated efficient, pre-computable modules for volumetric ray-casting and FDK-based back-projection with the LIVE processing pipeline. Our results show a 60x acceleration of the DTS computations, compared to the previous version, using a single GPU; presently, reconstruction is attained within a couple of minutes. The present implementation allows for significant flexibility in terms of the numerical and operational projection model; we are investigating the benefit of further optimizations and accurate digital projection sub

  9. Radiation protection and quality assurance in diagnostic radiology - an IAEA coordinated research project in Asia and Eastern Europe

    International Nuclear Information System (INIS)

    Oresegun, Modupe; LeHeron, J.; Maccia, C.; Padovani, R.; Vano, E.

    1999-01-01

    The International Atomic Energy Agency currently has two parallel Coordinated Research Projects (CRP) running in Asia and Eastern Europe. The main objective of the CRPs is to raise the level of awareness in participating countries about the need for radiation protection for patients undergoing diagnostic radiology procedures. This is to be achieved by first assessing the status quo in a sample of hospitals and X-ray rooms in each participating country. A program of optimization of radiation protection for patients is then introduced by means of a comprehensive quality assurance program and the implementation of appropriate dose reduction methods, taking into account clinical requirements for diagnostically acceptable images. Patient dose assessment and image quality assessment are to be performed both before and after the introduction of the quality assurance program. The CRP is divided into two phases - the first is concerned with conventional radiography, while the second involves fluoroscopy and computed tomography. The CRP is still running, restricting the scope of this paper to a discussion of the approach being taken with the project. The project will be completed in 1998, with analysis to follow

  10. Radiation protection and quality assurance in diagnostic radiology - an IAEA coordinated research project in Asia and Eastern Europe

    Energy Technology Data Exchange (ETDEWEB)

    Oresegun, Modupe [International Atomic Energy Agency, Vienna (Austria); LeHeron, J. [National Radiation Laboratory, Christchurch (New Zealand); Maccia, C. [Centre d' Assurance de qualite des Applications Technologiques dans le Domaine de la Sante, Bourg-la-Reine (France); Padovani, R. [Instituto di Fisica Sanitaria, Udine (Italy); Vano, E. [Medical Physics Group, Radiology Department, Complutense University, Madrid (Spain)

    1999-01-01

    The International Atomic Energy Agency currently has two parallel Coordinated Research Projects (CRP) running in Asia and Eastern Europe. The main objective of the CRPs is to raise the level of awareness in participating countries about the need for radiation protection for patients undergoing diagnostic radiology procedures. This is to be achieved by first assessing the status quo in a sample of hospitals and X-ray rooms in each participating country. A program of optimization of radiation protection for patients is then introduced by means of a comprehensive quality assurance program and the implementation of appropriate dose reduction methods, taking into account clinical requirements for diagnostically acceptable images. Patient dose assessment and image quality assessment are to be performed both before and after the introduction of the quality assurance program. The CRP is divided into two phases - the first is concerned with conventional radiography, while the second involves fluoroscopy and computed tomography. The CRP is still running, restricting the scope of this paper to a discussion of the approach being taken with the project. The project will be completed in 1998, with analysis to follow.

  11. Radiations

    International Nuclear Information System (INIS)

    Pujol Mora, J.

    1999-01-01

    The exposition to ionizing radiations is a constant fact in the life of the human being and its utilization as diagnostic and therapeutic method is generalized. However, it is notorious how as years go on, the fear to the ionizing radiation seems to persist too, and this fact is not limited to the common individual, but to the technical personnel and professional personnel that labors with them same. (S. Grainger) [es

  12. Radiation

    International Nuclear Information System (INIS)

    Davidson, J.H.

    1986-01-01

    The basic facts about radiation are explained, along with some simple and natural ways of combating its ill-effects, based on ancient healing wisdom as well as the latest biochemical and technological research. Details are also given of the diet that saved thousands of lives in Nagasaki after the Atomic bomb attack. Special comment is made on the use of radiation for food processing. (U.K.)

  13. Training activities on radiation protection in nuclear medicine in the frame of the EURATOM FP7 collaborative project MADEIRA

    International Nuclear Information System (INIS)

    Giussani, Augusto; Mattsson, Sören; Mikuž, Marko; Cantone, Marie Claire; Hoeschen, Christoph

    2011-01-01

    MADEIRA was a Collaborative Project cofunded by the European Commission through the EURATOM Seventh Research Framework Programme. It was structured into four scientific work packages, and its aim was to optimize the efficacy and safety of 3D functional imaging in nuclear medicine and thereby to reduce the radiation exposures of the patients while keeping or even improving the quality of the diagnostic information. Additionally, a fifth work package was dedicated to training and dissemination activities, including the organization of specific training courses, as well as research exchange programs for young scientists. This manuscript summarizes the experience gained during the Training Courses, in particular the one devoted to aspects of radiation protection in nuclear medicine.

  14. ABI1 and PP2CA Phosphatases Are Negative Regulators of Snf1-Related Protein Kinase1 Signaling in Arabidopsis

    OpenAIRE

    Rodrigues, A.; Adamo, M.; Crozet, P.; Margalha, L.; Confraria, A.; Martinho, C.; Elias, A.; Rabissi, A.; Lumbreras, V.; Gonzalez-Guzman, M.; Antoni, R.; Rodriguez, P. L.; Baena-Gonzalez, E.

    2013-01-01

    Plant survival under environmental stress requires the integration of multiple signaling pathways into a coordinated response, but the molecular mechanisms underlying this integration are poorly understood. Stress-derived energy deprivation activates the Snf1-related protein kinases1 (SnRK1s), triggering a vast transcriptional and metabolic reprogramming that restores homeostasis and promotes tolerance to adverse conditions. Here, we show that two clade A type 2C protein phosphatases (PP2Cs),...

  15. Biallelic germline and somatic mutations in malignant mesothelioma: multiple mutations in transcription regulators including mSWI/SNF genes.

    Science.gov (United States)

    Yoshikawa, Yoshie; Sato, Ayuko; Tsujimura, Tohru; Otsuki, Taiichiro; Fukuoka, Kazuya; Hasegawa, Seiki; Nakano, Takashi; Hashimoto-Tamaoki, Tomoko

    2015-02-01

    We detected low levels of acetylation for histone H3 tail lysines in malignant mesothelioma (MM) cell lines resistant to histone deacetylase inhibitors. To identify the possible genetic causes related to the low histone acetylation levels, whole-exome sequencing was conducted with MM cell lines established from eight patients. A mono-allelic variant of BRD1 was common to two MM cell lines with very low acetylation levels. We identified 318 homozygous protein-damaging variants/mutations (18-78 variants/mutations per patient); annotation analysis showed enrichment of the molecules associated with mammalian SWI/SNF (mSWI/SNF) chromatin remodeling complexes and co-activators that facilitate initiation of transcription. In seven of the patients, we detected a combination of variants in histone modifiers or transcription factors/co-factors, in addition to variants in mSWI/SNF. Direct sequencing showed that homozygous mutations in SMARCA4, PBRM1 and ARID2 were somatic. In one patient, homozygous germline variants were observed for SMARCC1 and SETD2 in chr3p22.1-3p14.2. These exhibited extended germline homozygosity and were in regions containing somatic mutations, leading to a loss of BAP1 and PBRM1 expression in MM cell line. Most protein-damaging variants were heterozygous in normal tissues. Heterozygous germline variants were often converted into hemizygous variants by mono-allelic deletion, and were rarely homozygous because of acquired uniparental disomy. Our findings imply that MM might develop through the somatic inactivation of mSWI/SNF complex subunits and/or histone modifiers, including BAP1, in subjects that have rare germline variants of these transcription regulators and/or transcription factors/co-factors, and in regions prone to mono-allelic deletion during oncogenesis. © 2014 UICC.

  16. The HAW-Project. Test disposal of highly radioactive radiation sources in the Asse salt mine. Final report

    International Nuclear Information System (INIS)

    Rothfuchs, T.; Cuevas, C. de las; Donker, H.; Feddersen, H.K.; Garcia-Celma, A.; Gies, H.; Goreychi, M.; Graefe, V.; Heijdra, J.; Hente, B.; Jockwer, N.; LeMeur, R.; Moenig, J.; Mueller, K.; Prij, J.; Regulla, D.; Smailos, E.; Staupendahl, G.; Till, E.; Zankl, M.

    1995-01-01

    In order to improve the final concept for the disposal of high-level radioactive waste (HAW) in boreholes drilled into salt formation plans were developed a couple of years ago for a full scale testing of the complete technical system of an underground repository. To satisfy the test objectives, thirty highly radioactive radiation sources were planned to be emplaced in six boreholes located in two test galleries at the 800-m-level in the Asse salt mine. A duration of testing of approximately five years was envisaged. Because of licensing uncertainties the German Federal Government decided on December 3rd, 1992 to stop all activities for the preparation of the test disposal immediately. In the course of the preparation of the test disposal, however, a system, necessary for handling of the radiation sources was developed and installed in the Asse salt mine and two non-radioactive reference tests with electrical heaters were started in November 1988. These tests served for the investigation of thermal effects in comparison to the planned radioactive tests. An accompanying scientific investigation programme performed in situ and in the laboratory comprises the estimation and observation of the thermal, radiation-induced, and mechanical interaction between the rock salt and the electrical heaters and the radiation sources, respectively. The laboratory investigations are carried out at Braunschweig (FRG), Petten (NL), Saclay (F) and Barcelona (E). As a consequence of the premature termination of the project the working programme was revised. The new programme agreed to by the project partners included a controlled shutdown of the heater tests in 1993 and a continuation of the laboratory activities until the end of 1994. (orig.)

  17. Radiation

    International Nuclear Information System (INIS)

    Winther, J.F.; Ulbak, K.; Dreyer, L.; Pukkala, E.; Oesterlind, A.

    1997-01-01

    Exposure to solar and ionizing radiation increases the risk for cancer in humans. Some 5% of solar radiation is within the ultraviolet spectrum and may cause both malignant melanoma and non-melanocytic skin cancer; the latter is regarded as a benign disease and is accordingly not included in our estimation of avoidable cancers. Under the assumption that the rate of occurrence of malignant melanoma of the buttocks of both men and women and of the scalp of women would apply to all parts of the body in people completely unexposed to solar radiation, it was estimated that approximately 95% of all malignant melanomas arising in the Nordic populations around the year 2000 will be due to exposure to natural ultraviolet radiation, equivalent to an annual number of about 4700 cases, with 2100 in men and 2600 in women, or some 4% of all cancers notified. Exposure to ionizing radiation in the Nordic countries occurs at an average effective dose per capita per year of about 3 mSv (Iceland, 1.1 mSv) from natural sources, and about 1 mSv from man-made sources. While the natural sources are primarily radon in indoor air, natural radionuclides in food, cosmic radiation and gamma radiation from soil and building materials, the man-made sources are dominated by the diagnostic and therapeutic use of ionizing radiation. On the basis of measured levels of radon in Nordic dwellings and associated risk estimates for lung cancer derived from well-conducted epidemiological studies, we estimated that about 180 cases of lung cancer (1% of all lung cancer cases) per year could be avoided in the Nordic countries around the year 2000 if indoor exposure to radon were eliminated, and that an additional 720 cases (6%) could be avoided annually if either radon or tobacco smoking were eliminated. Similarly, it was estimated that the exposure of the Nordic populations to natural sources of ionizing radiation other than radon and to medical sources will each give rise to an annual total of 2120

  18. Strategies and guidance for establishing an inclusive radiation monitoring in case of long term radioactive contamination: the SAGE project

    International Nuclear Information System (INIS)

    Lepicard, S.

    2004-01-01

    The evaluation of the rehabilitation strategies implemented in the CIS countries affected by the Chernobyl catastrophe pointed out the importance to involve the population in the day-to-day management of the radiological situation. The ETHOS experience in Belarus has revealed that to be effective and sustainable, this involvement must rely on the dissemination of a practical radiological protection culture within the population and especially within health professionals. As part of this culture, the implementation of an inclusive radiation monitoring system is a key element to allow the population and the local professionals to regain control on the day-to-day situation as far as the radiological risk is concerned. The SAGE Project, funded by the European Commission, started in October 2002 and will last 30 months. The objective is to develop strategies and guidance for disseminating such a system in Western Europe, in case of a long-term radiological contamination. The partnership of the Project is composed of 5 teams of researchers from the following institutions: BB RIR (the Brest Branch of the Research Institute of Radiology - Belarus), BELRAD (the Institute of Radiation Safety - Belarus), CEPN (France), GSF (Germany) and NRPB (United Kingdom). The key output of the project will be a handbook giving a comprehensive guidance on how to tackle the questionings and problems faced by the population. The proposed strategies and guidance are developed by national 'stakeholders panels' involving representatives from the society (medical doctors, radiation protection experts, teachers, representatives from NGOs,...) both in the contaminated territories of Belarus and in the above mentioned three Member States. This paper will present the methodology of work with the stakeholder panels and the major findings so far, especially the elements they have pointed out to be of a particular importance. The preliminary contents of the handbook will be presented as well. (author)

  19. HIC1 interacts with a specific subunit of SWI/SNF complexes, ARID1A/BAF250A

    International Nuclear Information System (INIS)

    Van Rechem, Capucine; Boulay, Gaylor; Leprince, Dominique

    2009-01-01

    HIC1, a tumor suppressor gene epigenetically silenced in many human cancers encodes a transcriptional repressor involved in regulatory loops modulating p53-dependent and E2F1-dependent cell survival and stress responses. HIC1 is also implicated in growth control since it recruits BRG1, one of the two alternative ATPases (BRM or BRG1) of SWI/SNF chromatin-remodeling complexes to repress transcription of E2F1 in quiescent fibroblasts. Here, through yeast two-hybrid screening, we identify ARID1A/BAF250A, as a new HIC1 partner. ARID1A/BAF250A is one of the two mutually exclusive ARID1-containing subunits of SWI/SNF complexes which define subsets of complexes endowed with anti-proliferative properties. Co-immunoprecipitation assays in WI38 fibroblasts and in BRG1-/- SW13 cells showed that endogenous HIC1 and ARID1A proteins interact in a BRG1-dependent manner. Furthermore, we demonstrate that HIC1 does not interact with BRM. Finally, sequential chromatin immunoprecipitation (ChIP-reChIP) experiments demonstrated that HIC1 represses E2F1 through the recruitment of anti-proliferative SWI/SNF complexes containing ARID1A.

  20. Dynamic Recruitment of Functionally Distinct Swi/Snf Chromatin Remodeling Complexes Modulates Pdx1 Activity in Islet β Cells

    Directory of Open Access Journals (Sweden)

    Brian McKenna

    2015-03-01

    Full Text Available Pdx1 is a transcription factor of fundamental importance to pancreas formation and adult islet β cell function. However, little is known about the positive- and negative-acting coregulators recruited to mediate transcriptional control. Here, we isolated numerous Pdx1-interacting factors possessing a wide range of cellular functions linked with this protein, including, but not limited to, coregulators associated with transcriptional activation and repression, DNA damage response, and DNA replication. Because chromatin remodeling activities are essential to developmental lineage decisions and adult cell function, our analysis focused on investigating the influence of the Swi/Snf chromatin remodeler on Pdx1 action. The two mutually exclusive and indispensable Swi/Snf core ATPase subunits, Brg1 and Brm, distinctly affected target gene expression in β cells. Furthermore, physiological and pathophysiological conditions dynamically regulated Pdx1 binding to these Swi/Snf complexes in vivo. We discuss how context-dependent recruitment of coregulatory complexes by Pdx1 could impact pancreas cell development and adult islet β cell activity.

  1. EXPERIENCE SANITARY-EPIDEMIOLOGICAL EXAMINATION PROJECT OF PLACING A SOURCE OF IONIZING RADIATION (GENERATING) IN HEALTH CARE INSTITUTIONS

    OpenAIRE

    I. A. Rakitin; A. L. Zel’din; V. B. Karpov

    2015-01-01

    The article reviews the results of long-term sanitary-epidemiological examination of projects of placing of ionizing radiation (generating) sources in health care institutions of Saint-Petersburg. The majority among the placed sources presented for examination was X-ray diagnostic units and sets – 35.7%, dentist X-rays – 39.4% and fluorography units – 10.8%. Mammography units and computer tomographs made 6.7% each, accelerants – 0.7%.The most frequent reasons of primary refusals to accept des...

  2. The SWI/SNF BAF-A complex is essential for neural crest development.

    Science.gov (United States)

    Chandler, Ronald L; Magnuson, Terry

    2016-03-01

    Growing evidence indicates that chromatin remodeler mutations underlie the pathogenesis of human neurocristopathies or disorders that affect neural crest cells (NCCs). However, causal relationships among chromatin remodeler subunit mutations and NCC defects remain poorly understood. Here we show that homozygous loss of ARID1A-containing, SWI/SNF chromatin remodeling complexes (BAF-A) in NCCs results in embryonic lethality in mice, with mutant embryos succumbing to heart defects. Strikingly, monoallelic loss of ARID1A in NCCs led to craniofacial defects in adult mice, including shortened snouts and low set ears, and these defects were more pronounced following homozygous loss of ARID1A, with the ventral cranial bones being greatly reduced in size. Early NCC specification and expression of the BRG1 NCC target gene, PLEXINA2, occurred normally in the absence of ARID1A. Nonetheless, mutant embryos displayed incomplete conotruncal septation of the cardiac outflow tract and defects in the posterior pharyngeal arteries, culminating in persistent truncus arteriosus and agenesis of the ductus arteriosus. Consistent with this, migrating cardiac NCCs underwent apoptosis within the circumpharyngeal ridge. Our data support the notion that multiple, distinct chromatin remodeling complexes govern genetically separable events in NCC development and highlight a potential pathogenic role for NCCs in the human BAF complex disorder, Coffin-Siris Syndrome. Copyright © 2016 Elsevier Inc. All rights reserved.

  3. The role of BAF (mSWI/SNF) complexes in mammalian neural development.

    Science.gov (United States)

    Son, Esther Y; Crabtree, Gerald R

    2014-09-01

    The BAF (mammalian SWI/SNF) complexes are a family of multi-subunit ATP-dependent chromatin remodelers that use ATP hydrolysis to alter chromatin structure. Distinct BAF complex compositions are possible through combinatorial assembly of homologous subunit families and can serve non-redundant functions. In mammalian neural development, developmental stage-specific BAF assemblies are found in embryonic stem cells, neural progenitors and postmitotic neurons. In particular, the neural progenitor-specific BAF complexes are essential for controlling the kinetics and mode of neural progenitor cell division, while neuronal BAF function is necessary for the maturation of postmitotic neuronal phenotypes as well as long-term memory formation. The microRNA-mediated mechanism for transitioning from npBAF to nBAF complexes is instructive for the neuronal fate and can even convert fibroblasts into neurons. The high frequency of BAF subunit mutations in neurological disorders underscores the rate-determining role of BAF complexes in neural development, homeostasis, and plasticity. © 2014 Wiley Periodicals, Inc.

  4. SWI/SNF-like chromatin remodeling factor Fun30 supports point centromere function in S. cerevisiae.

    Directory of Open Access Journals (Sweden)

    Mickaël Durand-Dubief

    2012-09-01

    Full Text Available Budding yeast centromeres are sequence-defined point centromeres and are, unlike in many other organisms, not embedded in heterochromatin. Here we show that Fun30, a poorly understood SWI/SNF-like chromatin remodeling factor conserved in humans, promotes point centromere function through the formation of correct chromatin architecture at centromeres. Our determination of the genome-wide binding and nucleosome positioning properties of Fun30 shows that this enzyme is consistently enriched over centromeres and that a majority of CENs show Fun30-dependent changes in flanking nucleosome position and/or CEN core micrococcal nuclease accessibility. Fun30 deletion leads to defects in histone variant Htz1 occupancy genome-wide, including at and around most centromeres. FUN30 genetically interacts with CSE4, coding for the centromere-specific variant of histone H3, and counteracts the detrimental effect of transcription through centromeres on chromosome segregation and suppresses transcriptional noise over centromere CEN3. Previous work has shown a requirement for fission yeast and mammalian homologs of Fun30 in heterochromatin assembly. As centromeres in budding yeast are not embedded in heterochromatin, our findings indicate a direct role of Fun30 in centromere chromatin by promoting correct chromatin architecture.

  5. Project and construction of a measurement system and nuclear radiations analysis

    International Nuclear Information System (INIS)

    Castro, R. B. de.

    1983-01-01

    A counting system was designed and built, aiming to: detect and measure nuclear radiations using a Geiger-Mueller counter; and to measure the amplitudes of pulses from either a proportional or a NaI detector. The results obtained of the Cs-137 and Co-60 energy spectra were compared with results obtained from other researches. (Author) [pt

  6. Pilot project for implantation of the National Commission on Radiation Protection and Dosimetry of CONTER, Brazil

    International Nuclear Information System (INIS)

    Padilha Filho, L.G.; Santos, J.R.A.; Dmitruk, P.P.; Souza, J.H.C.; Hamann, J.H.; Soboll, D.S.

    2017-01-01

    This work presents the pilot project of the National Council of Technicians and Technologists in Radiology (CONTER), which created the National Commission on Radioprotection and Dosimetry (CNRD), in order to develop a radioprotection culture for professionals in radiographic techniques

  7. Strengthening the Radiation Protection System in Cuba (SRPS - Cuba). A co-operation project between Cuban and Swedish institutions, February 2001 - June 2003

    Energy Technology Data Exchange (ETDEWEB)

    Avila, Rodolfo; Larsson, Carl-Magnus; Prendes, Miguel; Zerquera, Juan Tomas

    2004-02-01

    This project results from the co-operation between a number of Cuban and Swedish institutions. It started in February 2001 and ended in June 2003 and was made possible thanks to the contributions of the Swedish International Development Co-operation Agency (SIDA), the Centro de Proteccion e Higiene de las Radiaciones, Cuba (CPHR), and the Swedish Radiation Protection Authority (SSI). The overall objective was to strengthen the radiation protection system in Cuba, and in this way contribute with the control and reduction of risks to man and the environment from exposures to ionizing radiation. The project focused on four priority areas: 1) Protection of workers and patients exposed to radiation in radiation practices; 2) Preparedness for response to an emergency situation; 3) Environmental radiological protection; and, 4) Exposure to radiation in areas with high levels of natural radioactivity. The present report summarizes the findings of the whole project period, providing an overview of the overall achievements, as well as listing its deliverables. The results of an evaluation of the project, conducted during the final workshop, are also included. The report ends with a list of generic and specific conclusions and recommendations for implementation of the project's achievements and for further development of co-operation.

  8. Strengthening the Radiation Protection System in Cuba (SRPS - Cuba). A co-operation project between Cuban and Swedish institutions, February 2001 - June 2003

    International Nuclear Information System (INIS)

    Avila, Rodolfo; Larsson, Carl-Magnus; Prendes, Miguel; Zerquera, Juan Tomas

    2004-02-01

    This project results from the co-operation between a number of Cuban and Swedish institutions. It started in February 2001 and ended in June 2003 and was made possible thanks to the contributions of the Swedish International Development Co-operation Agency (SIDA), the Centro de Proteccion e Higiene de las Radiaciones, Cuba (CPHR), and the Swedish Radiation Protection Authority (SSI). The overall objective was to strengthen the radiation protection system in Cuba, and in this way contribute with the control and reduction of risks to man and the environment from exposures to ionizing radiation. The project focused on four priority areas: 1) Protection of workers and patients exposed to radiation in radiation practices; 2) Preparedness for response to an emergency situation; 3) Environmental radiological protection; and, 4) Exposure to radiation in areas with high levels of natural radioactivity. The present report summarizes the findings of the whole project period, providing an overview of the overall achievements, as well as listing its deliverables. The results of an evaluation of the project, conducted during the final workshop, are also included. The report ends with a list of generic and specific conclusions and recommendations for implementation of the project's achievements and for further development of co-operation

  9. A Safety Case Approach for Deep Geologic Disposal of DOE HLW and DOE SNF in Bedded Salt - 13350

    Energy Technology Data Exchange (ETDEWEB)

    Sevougian, S. David [Advanced Nuclear Energy Programs Group, Sandia National Laboratories, P.O. Box 5800, Albuquerque, NM 87185 (United States); MacKinnon, Robert J. [Advanced Nuclear Energy Programs Group, Sandia National Laboratories, P.O. Box 5800, Albuquerque, NM 87185 (United States); Leigh, Christi D. [Defense Waste Management Programs Group, Sandia National Laboratories, P.O. Box 5800, Albuquerque, NM 87185 (United States); Hansen, Frank D. [Geoscience Research and Applications Group, Sandia National Laboratories, P.O. Box 5800, Albuquerque, NM 87185 (United States)

    2013-07-01

    The primary objective of this study is to investigate the feasibility and utility of developing a defensible safety case for disposal of United States Department of Energy (U.S. DOE) high-level waste (HLW) and DOE spent nuclear fuel (SNF) in a conceptual deep geologic repository that is assumed to be located in a bedded salt formation of the Delaware Basin [1]. A safety case is a formal compilation of evidence, analyses, and arguments that substantiate and demonstrate the safety of a proposed or conceptual repository. We conclude that a strong initial safety case for potential licensing can be readily compiled by capitalizing on the extensive technical basis that exists from prior work on the Waste Isolation Pilot Plant (WIPP), other U.S. repository development programs, and the work published through international efforts in salt repository programs such as in Germany. The potential benefits of developing a safety case include leveraging previous investments in WIPP to reduce future new repository costs, enhancing the ability to effectively plan for a repository and its licensing, and possibly expediting a schedule for a repository. A safety case will provide the necessary structure for organizing and synthesizing existing salt repository science and identifying any issues and gaps pertaining to safe disposal of DOE HLW and DOE SNF in bedded salt. The safety case synthesis will help DOE to plan its future R and D activities for investigating salt disposal using a risk-informed approach that prioritizes test activities that include laboratory, field, and underground investigations. It should be emphasized that the DOE has not made any decisions regarding the disposition of DOE HLW and DOE SNF. Furthermore, the safety case discussed herein is not intended to either site a repository in the Delaware Basin or preclude siting in other media at other locations. Rather, this study simply presents an approach for accelerated development of a safety case for a potential

  10. A Safety Case Approach for Deep Geologic Disposal of DOE HLW and DOE SNF in Bedded Salt - 13350

    International Nuclear Information System (INIS)

    Sevougian, S. David; MacKinnon, Robert J.; Leigh, Christi D.; Hansen, Frank D.

    2013-01-01

    The primary objective of this study is to investigate the feasibility and utility of developing a defensible safety case for disposal of United States Department of Energy (U.S. DOE) high-level waste (HLW) and DOE spent nuclear fuel (SNF) in a conceptual deep geologic repository that is assumed to be located in a bedded salt formation of the Delaware Basin [1]. A safety case is a formal compilation of evidence, analyses, and arguments that substantiate and demonstrate the safety of a proposed or conceptual repository. We conclude that a strong initial safety case for potential licensing can be readily compiled by capitalizing on the extensive technical basis that exists from prior work on the Waste Isolation Pilot Plant (WIPP), other U.S. repository development programs, and the work published through international efforts in salt repository programs such as in Germany. The potential benefits of developing a safety case include leveraging previous investments in WIPP to reduce future new repository costs, enhancing the ability to effectively plan for a repository and its licensing, and possibly expediting a schedule for a repository. A safety case will provide the necessary structure for organizing and synthesizing existing salt repository science and identifying any issues and gaps pertaining to safe disposal of DOE HLW and DOE SNF in bedded salt. The safety case synthesis will help DOE to plan its future R and D activities for investigating salt disposal using a risk-informed approach that prioritizes test activities that include laboratory, field, and underground investigations. It should be emphasized that the DOE has not made any decisions regarding the disposition of DOE HLW and DOE SNF. Furthermore, the safety case discussed herein is not intended to either site a repository in the Delaware Basin or preclude siting in other media at other locations. Rather, this study simply presents an approach for accelerated development of a safety case for a potential

  11. Radiation and environmental monitoring at the nuclear legacy sites in Russia

    Energy Technology Data Exchange (ETDEWEB)

    Shandala, N.; Kiselev, S.; Titov, A.; Seregin, V.; Akhromeev, S.; Aladova, R.; Isaev, D. [SRC Burnasyan Federal Medical Biophysical Center (Russian Federation); Sneve, M. [Norwegian Radiation Protection Authority - NRPA (Norway)

    2014-07-01

    In 1960's, in the Northwest and Far East regions of Russia the technical bases of the Navy Fleet were built to maintain nuclear submarines by performing reloading of nuclear fuel, receiving and storing radioactive waste (RW) and spent nuclear fuel (SNF). In 2000, SevRAO enterprise in the northwest of Russia and DalRAO enterprise in the Far East were set up for the purposes of environmental remediation of the nuclear legacy sites. Regulatory supervision for radiation protection and safety at the nuclear legacy sites in Russian Far east and Northwest regions is one of regulatory functions of the Federal medical biological agency (FMBA of Russia). Improvement of the normative and regulatory basis has significant impact on effectiveness and efficiency of industrial projects aimed at reduction of nuclear and radiation hazard risk at the sites for the SNF and RW temporary storage (STS).To get unbiased comprehensive information on the current radiation conditions at the STSs and provide the effective response to changing radiation situation, the environmental radiation monitoring of the SevRAO and DalRAO facilities has been carried out during 2005-2013. The nature and peculiarity of the STS area radioactive contamination on the Kola Peninsula and in the Far East are the following: 1) high levels of radioactive contamination on the industrial site; 2) non-uniformity of the contamination distribution; 3) spread of contamination in the area of health protection zone. The following environmental components are contaminated: soil, vegetation, bottom sediments and seaweeds at the offshore sea waters. The dominant radionuclides are cesium-137 and strontium-90. At the facilities under inspection for the purpose of the dynamic control of the radiation situation the radio-ecological monitoring system was arranged. It presupposes regular radiometry inspections in-situ, their analysis and assessment of the radiation situation forecast in the course of the STS remediation main

  12. Actual Situation and Further Development of Interim Storage of Spent Nuclear Fuel (SNF) and Highly Active Waste (HAW) from the View of the Competent Authority in the Field of section 6

    International Nuclear Information System (INIS)

    Gastl, Christoph; Drobniewski, Christian

    2014-01-01

    According to the German atomic law the storage of nuclear material has to be licensed following section 6 by the competent authority in this field, which is the Federal Office for Radiation Protection. Interim storage in its actual form started in 2002 in the interim storage facility next to the NPP Lingen. Since this time each NPP erected its own storage facilities and three central storage facilities have been built. The spent nuclear fuel (SNF) and the vitrified high level waste (HAW) will be stored there until final disposal. The time span from now on to the point of opening of a final disposal facility shall be presented from a regulators point of view, divided into different phase which could spread from years to decades. Special attention shall be drawn on the different aspects influencing the licensing process and its duration at the moment and in future including the capabilities of the competent authority. (authors)

  13. Projectables

    DEFF Research Database (Denmark)

    Rasmussen, Troels A.; Merritt, Timothy R.

    2017-01-01

    CNC cutting machines have become essential tools for designers and architects enabling rapid prototyping, model-building and production of high quality components. Designers often cut from new materials, discarding the irregularly shaped remains. We introduce ProjecTables, a visual augmented...... reality system for interactive packing of model parts onto sheet materials. ProjecTables enables designers to (re)use scrap materials for CNC cutting that would have been previously thrown away, at the same time supporting aesthetic choices related to wood grain, avoiding surface blemishes, and other...... relevant material properties. We conducted evaluations of ProjecTables with design students from Aarhus School of Architecture, demonstrating that participants could quickly and easily place and orient model parts reducing material waste. Contextual interviews and ideation sessions led to a deeper...

  14. Investigation of microscopic radiation damage in waste forms using ODNMR and AEM techniques. (EMSP Project Final Report)

    International Nuclear Information System (INIS)

    Liu, G.; Luo, J.; Beitz, J.; Li, S.; Williams, C.; Zhorin, V.

    2000-01-01

    This project seeks to understand the microscopic effects of radiation damage in nuclear waste forms. The authors' approach to this challenge encompasses studies of ceramics and glasses containing short-lived alpha- and beta-emitting actinides with electron microscopy, laser and X-ray spectroscopic techniques, and computational modeling and simulations. In order to obtain information on long-term radiation effects on waste forms, much of the effort is to investigate α-decay induced microscopic damage in 18-year old samples of crystalline yttrium and lutetium orthophosphates that initially contained ∼ 1(wt)% of the alpha-emitting isotope 244 Cm (18.1 y half life). Studies also are conducted on borosilicate glasses that contain 244 Cm, 241 Am, or 249 Bk, respectively. The authors attempt to gain clear insights into the properties of radiation-induced structure defects and the consequences of collective defect-environment interactions, which are critical factors in assessing the long-term performance of high-level nuclear waste forms

  15. Investigation of microscopic radiation damage in waste forms using ODNMR and AEM techniques. (EMSP Project Final Report)

    Energy Technology Data Exchange (ETDEWEB)

    Liu, G.; Luo, J.; Beitz, J.; Li, S.; Williams, C.; Zhorin, V.

    2000-04-21

    This project seeks to understand the microscopic effects of radiation damage in nuclear waste forms. The authors' approach to this challenge encompasses studies of ceramics and glasses containing short-lived alpha- and beta-emitting actinides with electron microscopy, laser and X-ray spectroscopic techniques, and computational modeling and simulations. In order to obtain information on long-term radiation effects on waste forms, much of the effort is to investigate {alpha}-decay induced microscopic damage in 18-year old samples of crystalline yttrium and lutetium orthophosphates that initially contained {approximately} 1(wt)% of the alpha-emitting isotope {sup 244}Cm (18.1 y half life). Studies also are conducted on borosilicate glasses that contain {sup 244}Cm, {sup 241}Am, or {sup 249}Bk, respectively. The authors attempt to gain clear insights into the properties of radiation-induced structure defects and the consequences of collective defect-environment interactions, which are critical factors in assessing the long-term performance of high-level nuclear waste forms.

  16. Radiation hardness of two CMOS prototypes for the ATLAS HL-LHC upgrade project

    CERN Document Server

    Huffman, B T; Arndt, K; Bates, R; Benoit, M; Di Bello, F; Blue, A; Bortoletto, D; Buckland, M; Buttar, C; Caragiulo, P; Das, D; Dopke, J; Dragone, A; Ehrler, F; Fadeyev, V; Galloway, Z; Grabas, H; Gregor, I M; Grenier, P; Grillo, A; Hoeferkamp, M; Hommels, L B A; John, J; Kanisauskas, K; Kenney, C; Kramberger, J; Liang, Z; Mandic, I; Maneuski, D; Martinez-McKinney, F; McMahon, S; Meng, L; Mikuž, M; Muenstermann, D; Nickerson, R; Peric, I; Phillips, P; Plackett, R; Rubbo, F; Segal, J; Seidel, S; Seiden, A; Shipsey, I; Song, W; Stanitzki, M; Su, D; Tamma, C; Turchetta, R; Vigani, L; olk, J; Wang, R; Warren, M; Wilson, F; Worm, S; Xiu, Q; Zhang, J; Zhu, H

    2016-01-01

    The LHC luminosity upgrade, known as the High Luminosity LHC (HL-LHC), will require the replacement of the existing silicon strip tracker and the transistion radiation tracker. Although a baseline design for this tracker exists the ATLAS collaboration and other non-ATLAS groups are exploring the feasibility of using CMOS Monolithic Active Pixel Sensors (MAPS) which would be arranged in a strip-like fashion and would take advantage of the service and support structure already being developed for the upgrade. Two test devices made with theAMSH35 process (a High voltage or HV CMOS process) have been subjected to various radiation environments and have performed well. The results of these tests are presented in this paper.

  17. Big savings from small holes. [Liquid Droplet Radiator project for space vehicles

    Science.gov (United States)

    White, Alan

    1989-01-01

    The status and results to date of the NASA-Lewis/USAF Astronautics study of technology for large spacecraft heat-dissipation by means of liquid-droplet radiation (LDR) are discussed. The LDR concept uses a droplet generator to create billions of 200-micron droplets of a heatsink fluid which will cool through radiation into deep space as they fly toward a dropet collector. This exposure to the space environment entails the maintenance of vapor pressure as low as 10 to the -7th torr; the fluid must also be very stable chemically. While certain oils are good fluids for LDR use at low temperatures, higher-temperature heatsink fluids include Li, Sn, and Ga liquid metals.

  18. Radiation Dose Assessment for Military Personnel of the Enewetak Atoll Cleanup Project (1977-1980)

    Science.gov (United States)

    2018-04-13

    effects. This conclusion is supported by the Health Physics Society’s position statement regarding radiation health risks: Substantial and...support from DoD’s Dose Assessment and Recording Working Group (DARWG) and professional health physics experts of the military services who are ECUP...sample.8 At the time ECUP was underway, a trigger level was established based on the proposal of the American Health Physics Society Plutonium

  19. Report on the project research 'exposure to environmental radiation due to nuclear facilities'

    International Nuclear Information System (INIS)

    1984-03-01

    This special research was carried out for five years from fiscal 1978 to fiscal 1982, and its constitution was as follows: the investigation research on the behavior of radioactive substances in ocean and land environments, the investigation research on the metabolism of radioactive substances within bodies, the measurement of the dose absorbed in organs due to environmental radiation and the evaluation, and the investigation research on low level environmental radiation monitoring. As the sources of environmental radiation exposure, not only the release into the atmosphere and sea from nuclear power stations, nuclear fuel reprocessing plants and other facilities, but also the disposal of radioactive wastes on land and into ocean were considered. As the method of research, the experiment using living things and others, the analysis of the fallout nuclides existing in environment and living things, the analysis of the results of quantitative determination of stable elements and others were used. The detailed results of the above described researches are reported. By having executed this special research, the accumulation of new knowledge was obtained on the behavior of radioactive nuclides in environment and living things. (Kako, I.)

  20. Standing on the Shoulders of Giants: Results From the Radiation Oncology Academic Development and Mentorship Assessment Project (ROADMAP)

    International Nuclear Information System (INIS)

    Holliday, Emma B.; Jagsi, Reshma; Thomas, Charles R.; Wilson, Lynn D.; Fuller, Clifton D.

    2014-01-01

    Purpose: To analyze survey information regarding mentorship practices and cross-correlate the results with objective metrics of academic productivity among academic radiation oncologists at US Accreditation Council for Graduate Medical Education (ACGME)-accredited residency training programs. Methods and Materials: An institutional review board-approved survey for the Radiation Oncology Academic Development and Mentorship Assessment Project (ROADMAP) was sent to 1031 radiation oncologists employed at an ACGME-accredited residency training program and administered using an international secure web application designed exclusively to support data capture for research studies. Data collected included demographics, presence of mentorship, and the nature of specific mentoring activities. Productivity metrics, including number of publications, number of citations, h-index, and date of first publication, were collected for each survey respondent from a commercially available online database, and m-index was calculated. Results: A total of 158 academic radiation oncologists completed the survey, 96 of whom reported having an academic/scientific mentor. Faculty with a mentor had higher numbers of publications, citations, and h- and m-indices. Differences in gender and race/ethnicity were not associated with significant differences in mentorship rates, but those with a mentor were more likely to have a PhD degree and were more likely to have more time protected for research. Bivariate fit regression modeling showed a positive correlation between a mentor's h-index and their mentee's h-index (R 2 = 0.16; P<.001). Linear regression also showed significant correlates of higher h-index, in addition to having a mentor (P=.001), included a longer career duration (P<.001) and fewer patients in treatment (P=.02). Conclusions: Mentorship is widely believed to be important to career development and academic productivity. These results emphasize the importance of identifying and

  1. Standing on the Shoulders of Giants: Results From the Radiation Oncology Academic Development and Mentorship Assessment Project (ROADMAP)

    Energy Technology Data Exchange (ETDEWEB)

    Holliday, Emma B. [The University of Texas MD Anderson Cancer Center, Houston, Texas (United States); Jagsi, Reshma [The University of Michigan, Ann Arbor, Michigan (United States); Thomas, Charles R. [Oregon Health Science Center Knight Cancer Institute, Portland, Oregon (United States); Wilson, Lynn D. [Department of Therapeutic Radiology, Yale University School of Medicine, Yale Cancer Center, New Haven, Connecticut (United States); Fuller, Clifton D., E-mail: cdfuller@mdanderson.org [The University of Texas MD Anderson Cancer Center, Houston, Texas (United States); Oregon Health Science Center Knight Cancer Institute, Portland, Oregon (United States)

    2014-01-01

    Purpose: To analyze survey information regarding mentorship practices and cross-correlate the results with objective metrics of academic productivity among academic radiation oncologists at US Accreditation Council for Graduate Medical Education (ACGME)-accredited residency training programs. Methods and Materials: An institutional review board-approved survey for the Radiation Oncology Academic Development and Mentorship Assessment Project (ROADMAP) was sent to 1031 radiation oncologists employed at an ACGME-accredited residency training program and administered using an international secure web application designed exclusively to support data capture for research studies. Data collected included demographics, presence of mentorship, and the nature of specific mentoring activities. Productivity metrics, including number of publications, number of citations, h-index, and date of first publication, were collected for each survey respondent from a commercially available online database, and m-index was calculated. Results: A total of 158 academic radiation oncologists completed the survey, 96 of whom reported having an academic/scientific mentor. Faculty with a mentor had higher numbers of publications, citations, and h- and m-indices. Differences in gender and race/ethnicity were not associated with significant differences in mentorship rates, but those with a mentor were more likely to have a PhD degree and were more likely to have more time protected for research. Bivariate fit regression modeling showed a positive correlation between a mentor's h-index and their mentee's h-index (R{sup 2} = 0.16; P<.001). Linear regression also showed significant correlates of higher h-index, in addition to having a mentor (P=.001), included a longer career duration (P<.001) and fewer patients in treatment (P=.02). Conclusions: Mentorship is widely believed to be important to career development and academic productivity. These results emphasize the importance of

  2. Project W-151 flexible receiver radiation detector system acceptance test plan. Revision 1

    International Nuclear Information System (INIS)

    Troyer, G.L.

    1994-01-01

    The attached document is the Acceptance Test Plan for the portion of Project W-151 dealing with acceptance of gamma-ray detectors and associated electronics manufactured at the Idaho National Engineering Laboratory (INEL). The document provides a written basis for testing the detector system, which will take place in the 305 building (300 Area)

  3. Report on a Survey Project in Iceland on the Use of Radiation Pasteurization of Various Seafoods

    Energy Technology Data Exchange (ETDEWEB)

    Hannesson, G.; Dagbjartsson, B. [Icelandic Fisheries Laboratories, Reykjavik (Iceland)

    1970-11-15

    A survey project on the irradiation preservation of seafoods, sponsored by the Government of Iceland, the International Atomic Energy Agency and the United States Atomic Energy Commission has been carried out at the Icelandic Fisheries Laboratories. A summary of results obtained on Norway lobster tails, deep-sea shrimp and cod fish is given in this paper. (author)

  4. Five-year activity (1981-1985) on the project ionizing and nonionizing radiation protection investigations

    International Nuclear Information System (INIS)

    Zaricj, M.

    1987-01-01

    The brief review of the work conducted during five year's period on the project is given. Some organization and financial questions are touched. In spite of the permanent difficulties, it may be concluded that past period was successful. (author) 3 refs

  5. A randomized trial of heart failure disease management in skilled nursing facilities (SNF Connect): Lessons learned.

    Science.gov (United States)

    Daddato, Andrea; Wald, Heidi L; Horney, Carolyn; Fairclough, Diane L; Leister, Erin C; Coors, Marilyn; Capell, Warren H; Boxer, Rebecca S

    2017-06-01

    Conducting clinical trials in skilled nursing facilities is particularly challenging. This manuscript describes facility and patient recruitment challenges and solutions for clinical research in skilled nursing facilities. Lessons learned from the SNF Connect Trial, a randomized trial of a heart failure disease management versus usual care for patients with heart failure receiving post-acute care in skilled nursing facilities, are discussed. Description of the trial design and barriers to facility and patient recruitment along with regulatory issues are presented. The recruitment of Denver-metro skilled nursing facilities was facilitated by key stakeholders of the skilled nursing facilities community. However, there were still a number of barriers to facility recruitment including leadership turnover, varying policies regarding research, fear of litigation and of an increased workload. Engagement of facilities was facilitated by their strong interest in reducing hospital readmissions, marketing potential to hospitals, and heart failure management education for their staff. Recruitment of patients proved difficult and there were few facilitators. Identified patient recruitment challenges included patients being unaware of their heart failure diagnosis, patients overwhelmed with their illness and care, and frequently there was no available proxy for cognitively impaired patients. Flexibility in changing the recruitment approach and targeting skilled nursing facilities with higher rates of admissions helped to overcome some barriers. Recruitment of skilled nursing facilities and patients in skilled nursing facilities for clinical trials is challenging. Strategies to attract both facilities and patients are warranted. These include aligning study goals with facility incentives and flexible recruitment protocols to work with patients in "transition crisis."

  6. SNF1-related protein kinases 2 are negatively regulated by a plant-specific calcium sensor.

    Science.gov (United States)

    Bucholc, Maria; Ciesielski, Arkadiusz; Goch, Grażyna; Anielska-Mazur, Anna; Kulik, Anna; Krzywińska, Ewa; Dobrowolska, Grażyna

    2011-02-04

    SNF1-related protein kinases 2 (SnRK2s) are plant-specific enzymes involved in environmental stress signaling and abscisic acid-regulated plant development. Here, we report that SnRK2s interact with and are regulated by a plant-specific calcium-binding protein. We screened a Nicotiana plumbaginifolia Matchmaker cDNA library for proteins interacting with Nicotiana tabacum osmotic stress-activated protein kinase (NtOSAK), a member of the SnRK2 family. A putative EF-hand calcium-binding protein was identified as a molecular partner of NtOSAK. To determine whether the identified protein interacts only with NtOSAK or with other SnRK2s as well, we studied the interaction of an Arabidopsis thaliana orthologue of the calcium-binding protein with selected Arabidopsis SnRK2s using a two-hybrid system. All kinases studied interacted with the protein. The interactions were confirmed by bimolecular fluorescence complementation assay, indicating that the binding occurs in planta, exclusively in the cytoplasm. Calcium binding properties of the protein were analyzed by fluorescence spectroscopy using Tb(3+) as a spectroscopic probe. The calcium binding constant, determined by the protein fluorescence titration, was 2.5 ± 0.9 × 10(5) M(-1). The CD spectrum indicated that the secondary structure of the protein changes significantly in the presence of calcium, suggesting its possible function as a calcium sensor in plant cells. In vitro studies revealed that the activity of SnRK2 kinases analyzed is inhibited in a calcium-dependent manner by the identified calcium sensor, which we named SCS (SnRK2-interacting calcium sensor). Our results suggest that SCS is involved in response to abscisic acid during seed germination most probably by negative regulation of SnRK2s activity.

  7. DESIGN OF A CONCRETE SLAB FOR STORAGE OF SNF AND HLW CASKS

    International Nuclear Information System (INIS)

    J. Bisset

    2005-01-01

    This calculation documents the design of the Spent Nuclear Fuel (SNF) and High-Level Waste (HLW) Cask storage slab for the Aging Area. The design is based on the weights of casks that may be stored on the slab, the weights of vehicles that may be used to move the casks, and the layout shown on the sketch for a 1000 Metric Ton of Heavy Metal (MTHM) storage pad on Attachment 2, Sht.1 of the calculation 170-C0C-C000-00100-000-00A (BSC 2004a). The analytical model used herein is based on the storage area for 8 vertical casks. To simplify the model, the storage area of the horizontal concrete modules and their related shield walls is not included. The heavy weights of the vertical storage casks and the tensile forces due to pullout at the anchorages will produce design moments and shear forces that will envelope those that would occur in the storage area of the horizontal modules. The design loadings will also include snow and live loads. In addition, the design will also reflect pertinent geotechnical data. This calculation will document the preliminary thickness and general reinforcing steel requirements for the slab. This calculation also documents the initial design of the cask anchorage. Other slab details are not developed in this calculation. They will be developed during the final design process. The calculation also does not include the evaluation of the effects of cask drop loads. These will be evaluated in this or another calculation when the exact cask geometry is known

  8. Spent Nuclear Fuel Project operational staffing plan

    International Nuclear Information System (INIS)

    Debban, B.L.

    1996-03-01

    Using the Spent Nuclear Fuel (SNF) Project's current process flow concepts and knowledge from cognizant engineering and operational personnel, an initial assessment of the SNF Project radiological exposure and resource requirements was completed. A small project team completed a step by step analysis of fuel movement in the K Basins to the new interim storage location, the Canister Storage Building (CSB). This analysis looked at fuel retrieval, conditioning of the fuel, and transportation of the fuel. This plan describes the staffing structure for fuel processing, fuel movement, and the maintenance and operation (M ampersand O) staffing requirements of the facilities. This initial draft does not identify the support function resources required for M ampersand O, i.e., administrative and engineering (technical support). These will be included in future revisions to the plan. This plan looks at the resource requirements for the SNF subprojects, specifically, the operations of the facilities, balances resources where applicable, rotates crews where applicable, and attempts to use individuals in multi-task assignments. This plan does not apply to the construction phase of planned projects that affect staffing levels of K Basins

  9. Virtual reality technology for radiation visualisation during the remediation at Andreeva Bay in Russia as support to operational and regulatory supervision - 59400

    International Nuclear Information System (INIS)

    Mark, Niels-Kristian; Sneve, Malgorzata

    2012-01-01

    Document available in abstract form only. Full text of publication follows: The Norwegian Radiation Protection Authorities (NRPA) has since 1996 carried out a program of regulatory support projects, funded by the Norwegian Ministry of Foreign Affairs (NMFA) The objective of the program has been to support the Russian civilian and military regulators, the Federal Medical Biological Authorities of Russia (FMBA) and the Federal Environmental, Industrial and Nuclear Supervision Service of Russia, as well as the corresponding nuclear and radiation safety authority within the Russian Ministry of Defense with development and implementation of methods and tools for better regulatory supervision of the Andreeva Bay and Gremikha Sites of Temporary Storage (STS) for Spent Nuclear Fuel (SNF) and Radioactive Waste (RW). In 2005-2009 regulatory investigations were completed at the Andreeva Bay and Gremikha within the collaborative NRPAFMBA program. The radiation and radio-ecological situation was assessed, and criteria and regulations of the STS remediation were developed, as well as the guidance for their application for three possible options of environmental remediation (conservation, conversion and liquidation). As part of the project the Federal Medical-Biological Centre, a technical support organisation to FMBA, developed the DOSEMAP and DATAMAP applications for the FMBA, supporting radiation risk monitoring, worker radiation exposure control

  10. Assessment of Global Cloud Datasets from Satellites: Project and Database Initiated by the GEWEX Radiation Panel

    Science.gov (United States)

    Stubenrauch, C. J.; Rossow, W. B.; Kinne, S.; Ackerman, S.; Cesana, G.; Chepfer, H.; Getzewich, B.; Di Girolamo, L.; Guignard, A.; Heidinger, A.; hide

    2012-01-01

    Clouds cover about 70% of the Earth's surface and play a dominant role in the energy and water cycle of our planet. Only satellite observations provide a continuous survey of the state of the atmosphere over the whole globe and across the wide range of spatial and temporal scales that comprise weather and climate variability. Satellite cloud data records now exceed more than 25 years in length. However, climatologies compiled from different satellite datasets can exhibit systematic biases. Questions therefore arise as to the accuracy and limitations of the various sensors. The Global Energy and Water cycle Experiment (GEWEX) Cloud Assessment, initiated in 2005 by the GEWEX Radiation Panel, provided the first coordinated intercomparison of publically available, standard global cloud products (gridded, monthly statistics) retrieved from measurements of multi-spectral imagers (some with multiangle view and polarization capabilities), IR sounders and lidar. Cloud properties under study include cloud amount, cloud height (in terms of pressure, temperature or altitude), cloud radiative properties (optical depth or emissivity), cloud thermodynamic phase and bulk microphysical properties (effective particle size and water path). Differences in average cloud properties, especially in the amount of high-level clouds, are mostly explained by the inherent instrument measurement capability for detecting and/or identifying optically thin cirrus, especially when overlying low-level clouds. The study of long-term variations with these datasets requires consideration of many factors. A monthly, gridded database, in common format, facilitates further assessments, climate studies and the evaluation of climate models.

  11. The HAW Project. Test disposal of highly radioactive radiation sources in the Asse salt mine

    International Nuclear Information System (INIS)

    Rothfuchs, T.; Mueller-Lyda, I.; Raynal, M.; Major, J.C.

    1993-01-01

    In order to prove the safe disposal of high-level radioactive waste (HAW) in salt a five years test disposal of thirty highly radioactive canisters is planned in the Asse salt mine in the Federal Republic of Germany. The thirty canisters containing the radionuclides Caesium 137 and Strontium 90 in quantities sufficient to cover the bandwith of heat generation and gamma radiation of real HAW will be emplaced in six boreholes located in two galleries at the 800-m-level. Two electrical heater tests were already started in November 1988 and are continuously surveyed in respect of the thermomechanical and geochemical response of the rock mass. Also the handling system necessary for the emplacement of the radioactive canisters was developed and successfully tested. A laboratory investigation programme on radiation effects in salt is being performed in advance to the radioactive canister emplacement. This programme includes the investigation of thermally and radiolytically induced water and gas release from the rock salt and the radiolytical decomposition of salt minerals. For gamma dose and dose rate measurements in the test field measuring systems consisting of ionization chambers as well as solid state dosemeters were developed and tested. 70 refs

  12. Solar particle radiation storms forecasting and analysis the HESPERIA HORIZON 2020 project and beyond

    CERN Document Server

    Crosby, Norma

    2018-01-01

    Solar energetic particles (SEPs) emitted from the Sun are a major space weather hazard motivating the development of predictive capabilities. This book presents the results and findings of the HESPERIA (High Energy Solar Particle Events forecasting and Analysis) project of the EU HORIZON 2020 programme. It discusses the forecasting operational tools developed within the project, and presents progress to SEP research contributed by HESPERIA both from the observational as well as the SEP modelling perspective. Using multi-frequency observational data and simulations HESPERIA investigated the chain of processes from particle acceleration in the corona, particle transport in the magnetically complex corona and interplanetary space, to the detection near 1 AU. The book also elaborates on the unique software that has been constructed for inverting observations of relativistic SEPs to physical parameters that can be compared with spac e-borne measurements at lower energies. Introductory and pedagogical material incl...

  13. MO-E-18C-02: Hands-On Monte Carlo Project Assignment as a Method to Teach Radiation Physics

    International Nuclear Information System (INIS)

    Pater, P; Vallieres, M; Seuntjens, J

    2014-01-01

    Purpose: To present a hands-on project on Monte Carlo methods (MC) recently added to the curriculum and to discuss the students' appreciation. Methods: Since 2012, a 1.5 hour lecture dedicated to MC fundamentals follows the detailed presentation of photon and electron interactions. Students also program all sampling steps (interaction length and type, scattering angle, energy deposit) of a MC photon transport code. A handout structured in a step-by-step fashion guides student in conducting consistency checks. For extra points, students can code a fully working MC simulation, that simulates a dose distribution for 50 keV photons. A kerma approximation to dose deposition is assumed. A survey was conducted to which 10 out of the 14 attending students responded. It compared MC knowledge prior to and after the project, questioned the usefulness of radiation physics teaching through MC and surveyed possible project improvements. Results: According to the survey, 76% of students had no or a basic knowledge of MC methods before the class and 65% estimate to have a good to very good understanding of MC methods after attending the class. 80% of students feel that the MC project helped them significantly to understand simulations of dose distributions. On average, students dedicated 12.5 hours to the project and appreciated the balance between hand-holding and questions/implications. Conclusion: A lecture on MC methods with a hands-on MC programming project requiring about 14 hours was added to the graduate study curriculum since 2012. MC methods produce “gold standard” dose distributions and slowly enter routine clinical work and a fundamental understanding of MC methods should be a requirement for future students. Overall, the lecture and project helped students relate crosssections to dose depositions and presented numerical sampling methods behind the simulation of these dose distributions. Research funding from governments of Canada and Quebec. PP acknowledges

  14. MO-E-18C-02: Hands-On Monte Carlo Project Assignment as a Method to Teach Radiation Physics

    Energy Technology Data Exchange (ETDEWEB)

    Pater, P; Vallieres, M; Seuntjens, J [McGill University, Montreal, Quebec (Canada)

    2014-06-15

    Purpose: To present a hands-on project on Monte Carlo methods (MC) recently added to the curriculum and to discuss the students' appreciation. Methods: Since 2012, a 1.5 hour lecture dedicated to MC fundamentals follows the detailed presentation of photon and electron interactions. Students also program all sampling steps (interaction length and type, scattering angle, energy deposit) of a MC photon transport code. A handout structured in a step-by-step fashion guides student in conducting consistency checks. For extra points, students can code a fully working MC simulation, that simulates a dose distribution for 50 keV photons. A kerma approximation to dose deposition is assumed. A survey was conducted to which 10 out of the 14 attending students responded. It compared MC knowledge prior to and after the project, questioned the usefulness of radiation physics teaching through MC and surveyed possible project improvements. Results: According to the survey, 76% of students had no or a basic knowledge of MC methods before the class and 65% estimate to have a good to very good understanding of MC methods after attending the class. 80% of students feel that the MC project helped them significantly to understand simulations of dose distributions. On average, students dedicated 12.5 hours to the project and appreciated the balance between hand-holding and questions/implications. Conclusion: A lecture on MC methods with a hands-on MC programming project requiring about 14 hours was added to the graduate study curriculum since 2012. MC methods produce “gold standard” dose distributions and slowly enter routine clinical work and a fundamental understanding of MC methods should be a requirement for future students. Overall, the lecture and project helped students relate crosssections to dose depositions and presented numerical sampling methods behind the simulation of these dose distributions. Research funding from governments of Canada and Quebec. PP acknowledges

  15. Computational modeling of Repeat1 region of INI1/hSNF5: An evolutionary link with ubiquitin

    Science.gov (United States)

    Bhutoria, Savita

    2016-01-01

    Abstract The structure of a protein can be very informative of its function. However, determining protein structures experimentally can often be very challenging. Computational methods have been used successfully in modeling structures with sufficient accuracy. Here we have used computational tools to predict the structure of an evolutionarily conserved and functionally significant domain of Integrase interactor (INI)1/hSNF5 protein. INI1 is a component of the chromatin remodeling SWI/SNF complex, a tumor suppressor and is involved in many protein‐protein interactions. It belongs to SNF5 family of proteins that contain two conserved repeat (Rpt) domains. Rpt1 domain of INI1 binds to HIV‐1 Integrase, and acts as a dominant negative mutant to inhibit viral replication. Rpt1 domain also interacts with oncogene c‐MYC and modulates its transcriptional activity. We carried out an ab initio modeling of a segment of INI1 protein containing the Rpt1 domain. The structural model suggested the presence of a compact and well defined ββαα topology as core structure in the Rpt1 domain of INI1. This topology in Rpt1 was similar to PFU domain of Phospholipase A2 Activating Protein, PLAA. Interestingly, PFU domain shares similarity with Ubiquitin and has ubiquitin binding activity. Because of the structural similarity between Rpt1 domain of INI1 and PFU domain of PLAA, we propose that Rpt1 domain of INI1 may participate in ubiquitin recognition or binding with ubiquitin or ubiquitin related proteins. This modeling study may shed light on the mode of interactions of Rpt1 domain of INI1 and is likely to facilitate future functional studies of INI1. PMID:27261671

  16. Innovative nuclear technologies based on radiation induced surface activation (RISA). 1. The project overview

    International Nuclear Information System (INIS)

    Fujisawa, Kyosuke; Morooka, Shinichi; Hishida, Mamoru

    2004-01-01

    This research of the Innovative nuclear technologies based on Radiation Induced Surface Activation (RISA) is due to start from 2003 and to be ended to 2006, and performed fund by Ministry of Economy, Trade and Industry (METI) Japan. One of the innovative technologies is to develop a high performance corrosion-proof film to prevent the surface of reactor internals from stress corrosion cracking (SCC), the other one is to develop the film for improving the heat transfer performance a high performance of the nuclear fuel rod. Both of these properties are derived under gamma ray irradiation by the RISA effect. This paper reports about the summary of this subsidy enterprise by METI. (author)

  17. Off-Site Radiation Exposure Review Project: Phase 2 soils program

    Energy Technology Data Exchange (ETDEWEB)

    McArthur, R.D.; Miller, F.L. Jr.

    1989-12-01

    To help estimate population doses of radiation from fallout originating at the Nevada Test Site, soil samples were collected throughout the western United States. Each sample was prepared by drying and ball-milling, then analyzed by gamma-spectrometry to determine the amount of {sup 137}Cs it contained. Most samples were also analyzed by chemical separation and alpha-spectrometry to determine {sup 239 + 240}Pu and by isotope mass spectroscopy to determine the ratios of {sup 240}Pu to {sup 239}Pu and {sup 241}Pu to {sup 239}Pu. The total inventories of cesium and plutonium at 171 sites were computed from the results. This report describes the sample collection, processing, and analysis, presents the analytical results, and assesses the quality of the data. 10 refs., 9 figs., 12 tabs.

  18. The realism project reconciling nuclear power and radiation policies with the real world

    International Nuclear Information System (INIS)

    Theodore Rockwell

    2006-01-01

    Let's get real. It is crazy to fear that one's health and life are threatened by entities known to be harmless, whether those entities are goblins under the bed or trivial levels of radiation from non-existent radiological catastrophes. The nuclear community is in that paranoid state, and no advice from public relations experts can cure it. Some people claim that overstating risk is a prudent thing to do, but in practice it may do harm. Let us recall what we have said and done to create this situation. Then let us look at what the real world tells us about those risks. And then we will consider what might be done to return to reason. (author)

  19. RIKEN-JAERI 8-GeV synchrotron radiation project - SPring-8

    International Nuclear Information System (INIS)

    Awaya, Yohko

    1990-01-01

    The plan of an 8-GeV synchrotron radiation facility, which is called SPring-8 (Super Photon Ring-8GeV), had been proposed by Science and Technology Agency (STA) in Japan and it was decided that its construction would be started from April 1990. An atomic physics group in Japan had the first meeting in December 1988 to discuss the future studies of atomic physics and related problems at SPring-8 and plans of research and development (R and D) for them. Their report was published in May 1990. In this report, an outline of SPring-8 is described. Results of the discussions of Japanese working group of atomic physics and the present status of R and D of this group will be presented by M. Kimura in this workshop

  20. Development of Space Life Supporting System Using Radiation Technology (Top Brand Project)

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Ju Woon; Kim, Jae Hun; Song, Beom Seok; Choi, Jong Il; Yoon, Yo Han; Park, Jin Kyu; Park, Jae Nam; Han, In Jun; Lee, Yoon Jong [KAERI, Daejeon (Korea, Republic of)

    2010-08-15

    To simulate the space environment of microgravity and expose to space radiation, Hindlimb Suspension Model was established in Gamma Phytotron. Hindlimb suspended group exposed to irradiation, non-suspended group not exposed to irradiation, and non-suspended group exposed to irradiation were experimented for 2 weeks at the dose rate of 3.2 mSV/day. The results showed that muscle weight was decreased by suspension. To develop the countermeasure to physiological changes in space environment, the peptides from soy beam was selected to evaluate the effect with the space environment simulation model. Suing the microscopic and fluorescent images, the growth of microorganisms were detected. The species were identified based on primer-targeted gene sequence analysis. Also, the radiation resistance of species was defined. To research on sustainable nutritional supply and improvement of human physiology in space environment, four kinds of new Korean space foods (Bulgogi, Bibimbap, Seaweed soup, and Mulberry beverage) were developed using the irradiation technology and certified as space foods by the Russian Institute of Biomedical Problems. The contract on joint research of MARS-500 between KAERI and IBMP was made. In the experiment, crews for expedition to Mars will eat Korean space foods (Bulgogi, Bibimbap, Seaweed soup, Mulberry beverage, Kimchi, Sujeonggwa) for 120 days, then their immunity will be examined and compared with it on the ground. The developed technology and know-how could be spun out to the various fields, such as aircraft, automobile, military, information and communication, bio technologies. Moreover, the results obtained from this research can be used for the further development for military use or special food area such as foods for patient

  1. Development of Space Life Supporting System Using Radiation Technology (Top Brand Project)

    International Nuclear Information System (INIS)

    Lee, Ju Woon; Kim, Jae Hun; Song, Beom Seok; Choi, Jong Il; Yoon, Yo Han; Park, Jin Kyu; Park, Jae Nam; Han, In Jun; Lee, Yoon Jong

    2010-08-01

    To simulate the space environment of microgravity and expose to space radiation, Hindlimb Suspension Model was established in Gamma Phytotron. Hindlimb suspended group exposed to irradiation, non-suspended group not exposed to irradiation, and non-suspended group exposed to irradiation were experimented for 2 weeks at the dose rate of 3.2 mSV/day. The results showed that muscle weight was decreased by suspension. To develop the countermeasure to physiological changes in space environment, the peptides from soy beam was selected to evaluate the effect with the space environment simulation model. Suing the microscopic and fluorescent images, the growth of microorganisms were detected. The species were identified based on primer-targeted gene sequence analysis. Also, the radiation resistance of species was defined. To research on sustainable nutritional supply and improvement of human physiology in space environment, four kinds of new Korean space foods (Bulgogi, Bibimbap, Seaweed soup, and Mulberry beverage) were developed using the irradiation technology and certified as space foods by the Russian Institute of Biomedical Problems. The contract on joint research of MARS-500 between KAERI and IBMP was made. In the experiment, crews for expedition to Mars will eat Korean space foods (Bulgogi, Bibimbap, Seaweed soup, Mulberry beverage, Kimchi, Sujeonggwa) for 120 days, then their immunity will be examined and compared with it on the ground. The developed technology and know-how could be spun out to the various fields, such as aircraft, automobile, military, information and communication, bio technologies. Moreover, the results obtained from this research can be used for the further development for military use or special food area such as foods for patient

  2. The gel forming characteristics and the palatability of pasteurized and radiation processed egg magma in baked custard - a class project

    International Nuclear Information System (INIS)

    Van Wyk, S.; Verhoef, L.

    1991-01-01

    In a research project conducted by third-year students, baked custard was made from six different samples of frozen egg magma subjected to various treatments. The treatments were pasteurization and various radiation doses. A sample made from untreated fresh egg magma was added as a control sample. Various objective measurements were executed: penetrometer testing with the skin of the baked custard left intact, penetrometer testing with the skin of the baked custards removed, syneresis testing, and determination of the percentage sag of the baked custard. Sensory evaluation included comparing the color of the baked custards with a predetermined color sample, evaluating the texture by means of visual as well as oral evaluation methods, evaluating the consistency of the baked custards, and the general acceptability of the baked custards to a trained sensory panel. Objective evaluation detected little difference between the egg magma samples. Sensory evaluation also detected little difference between the samples. 11 refs., 4 tabs., 1 fig

  3. Mcm1p binding sites in ARG1 positively regulate Gcn4p binding and SWI/SNF recruitment

    OpenAIRE

    Yoon, Sungpil; Hinnebusch, Alan G.

    2009-01-01

    Transcription of the arginine biosynthetic gene ARG1 is activated by Gcn4p, a transcription factor induced by starvation for any amino acid. Previously we showed that Gcn4p binding stimulates the recruitment of Mcm1p and co-activator SWI/SNF to ARG1 in cells via Gcn4p induction through amino acid starvation. Here we report that Gcn4p binding is reduced by point mutations of the Mcm1p binding site and increased by overexpression of Mcm1p. This result suggests that Mcm1p plays a positive role i...

  4. Status of Progress Made Toward Safety Analysis and Technical Site Evaluations for DOE Managed HLW and SNF.

    Energy Technology Data Exchange (ETDEWEB)

    Sevougian, S. David [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Stein, Emily [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Gross, Michael B [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Hammond, Glenn Edward [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Frederick, Jennifer M [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Mariner, Paul [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2016-11-01

    The Spent Fuel and Waste Science and Technology (SFWST) Campaign of the U.S. Department of Energy (DOE) Office of Nuclear Energy (NE) is conducting research and development (R&D) on generic deep geologic disposal systems (i.e., repositories). This report describes specific activities in FY 2016 associated with the development of a Defense Waste Repository (DWR)a for the permanent disposal of a portion of the HLW and SNF derived from national defense and research and development (R&D) activities of the DOE.

  5. EPOS-An intense positron beam project at the ELBE radiation source in Rossendorf

    International Nuclear Information System (INIS)

    Krause-Rehberg, R.; Sachert, S.; Brauer, G.; Rogov, A.; Noack, K.

    2006-01-01

    EPOS, the acronym of ELBE Positron Source, describes a running project to build an intense pulsed beam of mono-energetic positrons (0.2-40 keV) for materials research. Positrons will be created via pair production at a tungsten target using the pulsed 40 MeV electron beam of the superconducting linac electron linac with high brilliance and low emittance (ELBE) at Forschungszentrum Rossendorf (near Dresden, Germany). The chosen design of the system under construction is described and results of calculations simulating the interaction of the electron beam with the target are presented, and positron beam formation and transportation is also discussed

  6. Research activities in radiation protection. Programme report 1996. Report on the departmental research programme of the Federal Ministry for Environment, Nature Conservation and Reactor Safety (BMU), performed under the scientific and administrative project management of the Federal Office for Radiation Protection (BfS)

    International Nuclear Information System (INIS)

    Schmitt-Hannig, A.; Thieme, M.; Goedde, R.

    1997-02-01

    On behalf of the Ministry for Environment, Nature Conservation and Nuclear Safety (BMU), the Federal Office for Radiation Protection is placing research and study contracts in the field of radiation protection. The results of these projects are used for developing radiation protection rules and to fulfill the special radiation protection tasks of the BMU, required by law. Planning, expert and administrative management, placing, assistance as well as expert evaluation of the results from these research projects lies within the responsibility of the Federal Office for Radiation Protection. This report provides information on preliminary and final results of radiation protection projects within the BMU Department Research Programme of the year 1996. (orig.) [de

  7. How do environmental and behavioral factors impact ultraviolet radiation effects on health: the RISC-UV Project

    Science.gov (United States)

    Correa, M. P.; Godin-Beekmann, S.; Haeffelin, M.; Saiag, P.; Mahe, E.; Brogniez, C.; Dupont, J. C.; Pazmiño, A.; Auriol, F.; Bonnel, B.

    2009-04-01

    Introduction: RISC-UV is a research project on "Impact of climate change on ultraviolet radiation and risks for health", a research project in which physicists, meteorologists and physicians work together to assess the relative role played by environmental and behavioral factors in the UV-related diseases as skin cancer and vitamin D deficiency. Environmental factors are related to the role played by the alteration in intensity of UV radiation at the Earth's surface resulting from variation in several factors affected by climate change and human activities: stratospheric ozone, cloud cover, aerosols and the reflectivity of the surface. On the other hand, behavioral factors are related to the sun over/underexposure and the correct use of sun-protection (hats, caps, sunglasses, sunscreen lotion, etc.). RISC-UV is organized around three main areas: 1) Organization of a workshop, scheduled for January 2009, which aims to describe the state of the art in the subject within each community and define the requirements of pathologists for epidemiological studies; 2) A pilot study intended to evaluate the consistency between UV measurements delivered simultaneously by satellite-based instruments, ground instruments, radiometers and individual dosimeters. This study is based on measurements campaigns and an analysis of the long-term consistency of data series relating to UV radiation and associated parameters; and 3) Analysis of the weights of medical, behavioral and environmental parameters involved in skin carcinogenesis. A detailed description of these areas can be found in http://www.gisclimat.fr/Doc/GB/D_projects/RISC-UV_GB.html. This presentation focuses on the first results of the UV experimental measurements performed between September 8th and October 8th 2008 in Palaiseau, France (48.7˚ N; 2.2˚ E; 170m - Haeffelin et al., 2005). A second campaign is foreseen for the spring of 2009. The purpose of these campaigns is to obtain, analyze and quantitatively link the

  8. Gnome site decontamination and decommissioning project radiation contamination clearance report, March 28, 1979-September 23, 1979

    International Nuclear Information System (INIS)

    Berry, H.A.

    1981-08-01

    This report describes the operations and radiological activities conducted during Phase II and Phase III of the Gnome site decontamination and decommissioning (D/D) project in Carlsbad, New Mexico. The onsite radiological monitoring and documentation activities were performed for the Department of Energy, Nevada Operations (DOE/NV) by Reynolds Electrical and Engineering Co., Inc. (REECo) and EG and G, Inc., from March 28, 1979 to September 23, 1979. The monitoring program included soil sampling and analyses, portable instrument area surveys, thermoluminescent dosimeter (TLD) measurements and a post-operational aerial survey to document the final site status and to insure public and occupational health and safety. Although the analysis of data gathered during the final stages of the D/D project will provide the information necessary for DOE to return the Gnome site to the Department of the Interior, Bureau of Land Management (BLM) for unrestricted use of the land surface, there are permanent restrictions on excavation and/or drilling on the site at any depth between the surface and 1500 feet

  9. Use of 4MAT Learning Theory to Promote Better Skin Care During Radiation Therapy: An Evidence-Based Quality Improvement Project.

    Science.gov (United States)

    Bauer, Carole; Magnan, Morris; Laszewski, Pamela

    Radiation therapy is a key treatment modality for cancer patients, but it is associated with adverse side effects such as radiation dermatitis. To mitigate the adverse effects of radiation on the skin, patients must participate in skin-related self-care. However, even with self-care instruction, adherence can be poor. This quality improvement project used best available evidence for skin care in patients undergoing radiation therapy and a theoretical framework, 4MATing, to provide a structured approach to patient education designed to enhance adherence to skin care recommendations. Implementation of this approach resulted in increased adherence to a topical skin care protocol in our facility. Patients were highly satisfied with their education. While there was a 4-day delay in the onset of radiation dermatitis, this difference was not statistically significant.

  10. HIV-1 replication in cell lines harboring INI1/hSNF5 mutations.

    Science.gov (United States)

    Sorin, Masha; Yung, Eric; Wu, Xuhong; Kalpana, Ganjam V

    2006-08-31

    INI1/hSNF5 is a cellular protein that directly interacts with HIV-1 integrase (IN). It is specifically incorporated into HIV-1 virions. A dominant negative mutant derived from INI1 inhibits HIV-1 replication. Recent studies indicate that INI1 is associated with pre-integration and reverse transcription complexes that are formed upon viral entry into the target cells. INI1 also is a tumor suppressor, biallelically deleted/mutated in malignant rhabdoid tumors. We have utilized cell lines derived from the rhabdoid tumors, MON and STA-WT1, that harbor either null or truncating mutations of INI1 respectively, to assess the effect of INI1 on HIV-1 replication. We found that while HIV-1 virions produced in 293T cells efficiently transduced MON and STA-WT1 cells, HIV-1 particle production was severely reduced in both of these cells. Reintroduction of INI1 into MON and STA-WT1 significantly enhanced the particle production in both cell lines. HIV-1 particles produced in MON cells were reduced for infectivity, while those produced in STA-WT1 were not. Further analysis indicated the presence of INI1 in those virions produced from STA-WT1 but not from those produced from MON cells. HIV-1 produced in MON cells were defective for synthesis of early and late reverse transcription products in the target cells. Furthermore, virions produced in MON cells were defective for exogenous reverse transcriptase activity carried out using exogenous template, primer and substrate. Our results suggest that INI1-deficient cells exhibit reduced particle production that can be partly enhanced by re-introduction of INI1. Infectivity of HIV-1 produced in some but not all INI1 defective cells, is affected and this defect may correlate to the lack of INI1 and/or some other proteins in these virions. The block in early events of virion produced from MON cells appears to be at the stage of reverse transcription. These studies suggest that presence of INI1 or some other host factor in virions and

  11. HIV-1 replication in cell lines harboring INI1/hSNF5 mutations

    Directory of Open Access Journals (Sweden)

    Wu Xuhong

    2006-08-01

    Full Text Available Abstract Background INI1/hSNF5 is a cellular protein that directly interacts with HIV-1 integrase (IN. It is specifically incorporated into HIV-1 virions. A dominant negative mutant derived from INI1 inhibits HIV-1 replication. Recent studies indicate that INI1 is associated with pre-integration and reverse transcription complexes that are formed upon viral entry into the target cells. INI1 also is a tumor suppressor, biallelically deleted/mutated in malignant rhabdoid tumors. We have utilized cell lines derived from the rhabdoid tumors, MON and STA-WT1, that harbor either null or truncating mutations of INI1 respectively, to assess the effect of INI1 on HIV-1 replication. Results We found that while HIV-1 virions produced in 293T cells efficiently transduced MON and STA-WT1 cells, HIV-1 particle production was severely reduced in both of these cells. Reintroduction of INI1 into MON and STA-WT1 significantly enhanced the particle production in both cell lines. HIV-1 particles produced in MON cells were reduced for infectivity, while those produced in STA-WT1 were not. Further analysis indicated the presence of INI1 in those virions produced from STA-WT1 but not from those produced from MON cells. HIV-1 produced in MON cells were defective for synthesis of early and late reverse transcription products in the target cells. Furthermore, virions produced in MON cells were defective for exogenous reverse transcriptase activity carried out using exogenous template, primer and substrate. Conclusion Our results suggest that INI1-deficient cells exhibit reduced particle production that can be partly enhanced by re-introduction of INI1. Infectivity of HIV-1 produced in some but not all INI1 defective cells, is affected and this defect may correlate to the lack of INI1 and/or some other proteins in these virions. The block in early events of virion produced from MON cells appears to be at the stage of reverse transcription. These studies suggest that

  12. The HAW-Project: Test disposal of highly radioactive radiation sources in the Asse salt mine

    International Nuclear Information System (INIS)

    1992-04-01

    Two electrical heater tests were already started in November 1988 and are continuously surveyed in respect of the thermomechanical and geochemical response of the rock mass. Also the handling system necessary for the emplacement of 30 radioactive canisters (Sr-90 and Cs-137 sources) was developed and succesfully tested. This system consists of six multiple transport and storage casks of the type Castor-GSF-5, two above ground/below ground shuttle transport casks of the type Asse TB1, an above ground transfer station, an underground transport vehicle, a disposal machine, and a borehole slider. A laboratory investigation program on radiation effects in salt is being performed in advance to the radioactive canister emplacement. This program includes the investigation of thermally and radiolytically induced water and gas release from the rock salt and the radiolytical decomposition of salt minerals. For gamma dose and dose rate measurements in the test field measuring systems consisting of ionisation chambers as well as solid state dosemeters were developed and tested. Thermomechanical computer code validation is performed by calculational predictions and parallel investigation of the stress and displacement fields in the underground test field. (orig./HP)

  13. Preoperational radiation surveillance of the WIPP Project by EEG for the years 1993 - 1995

    Energy Technology Data Exchange (ETDEWEB)

    Kenney, J.W.; Gray, D.H.; Ballard, S.C. [Environmental Evaluation Group, Carlsbad, NM (United States)

    1998-03-01

    Average {sup 241}Am, {sup 239+240}Pu and {sup 238}Pu concentrations measured in ambient air near the Waste Isolation Pilot Plant (WIPP) site during 1993, 1994 and 1995 are consistent with similar data reported by the U.S. Environmental Protection Agency (EPA) and Los Alamos National Laboratory (LANL) for Espanola, Pojoaque and Santa Fe, New Mexico. Through the use of replicate analyses of matrix blanks minimum detectable activity (MDA), minimum detectable concentration (MDC) and action levels (ACTL) were established for the Environmental Evaluation Group (EEG) measurement system. Using MDA data from fixed air sampler (FAS) filters and conservative assumptions applied in the National Council on Radiation Protection and Measurements (NCRP) Report 123 (NCRP 1996), it is shown that the EEG sampling and measurement methodology is capable of detecting effluent air emissions which would produce a dose that is approximately 1000 times below the 40 CFR 191 Subpart A limit of 2.5E{sup -4} Sv/y (25 mrem/y). A similar calculation using the NCRP worksheet with storm water effluent MDCs found the EEG measurement program capable of detecting actinide emissions which would result in a dose that is approximately 10 times below the dose limits in 40 CFR 191 Subpart A and 40 CFR 61 Subpart H.

  14. Thinking about Thoron and Thoron daughters: radiation studies and interpretations for a rare earths project

    International Nuclear Information System (INIS)

    Sonter, Mark; Hondros, Jim

    2016-01-01

    The emerging rare earths mining and processing industry involves projects which will invariably handle ores containing some levels of thorium, and to a lesser extent, uranium. The thorium levels which can be encountered range from tens of ppm up to percent levels. (Thorium content of pure monazite is in the range 5% to 8% or so.) This technical note focuses on the understanding of thoron releases into the air from thorium- bearing ores in situ and in process, and subsequent generation of thoron decay products in air, and the Potential Alpha Energy Concentration levels and dose estimations that result. It presents some theory, literature search results and a description of test work done on Nolans ore at Arafura's Darwin facility and in the field at Nolans Bore.

  15. Project, construction and characterization of ionization chambers for use as standard systems in X and gamma radiation beams

    International Nuclear Information System (INIS)

    Perini, Ana Paula

    2013-01-01

    Ionization chambers present some advantages in relation to other dosimeters: easiness of handling, low energy dependence and high precision. The advantages associated to ionization chambers and the large number of diagnostic radiology exams and therapeutic treatments motivated the development of this PhD program. In this project ionization chambers were developed and characterized to be applied in diagnostic radiology and therapy beam dosimetry, with high precision and performance, in compliance with international recommendations. They were assembled in a simple way, utilizing low-cost national materials, so they can be reproduced and applied at calibration laboratories. The project of these ionization chambers presents some differences in relation to commercial ionization chambers, as the materials utilized and geometrical arrangements. Besides the development of the ionization chambers to be utilized in standard X-ray beam dosimetry as work standard systems, two graphite parallel-plate ionization chambers were developed and characterized to be applied as reference standard systems for determining the air kerma rates of gamma radiation sources. Comparing the air kerma rates determined with the reference standard of the Calibration Laboratory of IPEN, a Farmer ionization chamber, with the values of the air kerma rates obtained with the graphite ionization chambers, the maximum differences obtained were only 1.7% and 1.2% for the G1 and G2 graphite ionization chambers, respectively. Moreover, these ionization chambers presented correction factors close to 1.000, which is ideal for an ionization chamber be characterized as a reference standard system. (author)

  16. Projections of UV radiation changes in the 21st century: impact of ozone recovery and cloud effects

    Directory of Open Access Journals (Sweden)

    A. F. Bais

    2011-08-01

    Full Text Available Monthly averaged surface erythemal solar irradiance (UV-Ery for local noon from 1960 to 2100 has been derived using radiative transfer calculations and projections of ozone, temperature and cloud change from 14 chemistry climate models (CCM, as part of the CCMVal-2 activity of SPARC. Our calculations show the influence of ozone depletion and recovery on erythemal irradiance. In addition, we investigate UV-Ery changes caused by climate change due to increasing greenhouse gas concentrations. The latter include effects of both stratospheric ozone and cloud changes. The derived estimates provide a global picture of the likely changes in erythemal irradiance during the 21st century. Uncertainties arise from the assumed scenarios, different parameterizations – particularly of cloud effects on UV-Ery – and the spread in the CCM projections. The calculations suggest that relative to 1980, annually mean UV-Ery in the 2090s will be on average ~12 % lower at high latitudes in both hemispheres, ~3 % lower at mid latitudes, and marginally higher (~1 % in the tropics. The largest reduction (~16 % is projected for Antarctica in October. Cloud effects are responsible for 2–3 % of the reduction in UV-Ery at high latitudes, but they slightly moderate it at mid-latitudes (~1 %. The year of return of erythemal irradiance to values of certain milestones (1965 and 1980 depends largely on the return of column ozone to the corresponding levels and is associated with large uncertainties mainly due to the spread of the model projections. The inclusion of cloud effects in the calculations has only a small effect of the return years. At mid and high latitudes, changes in clouds and stratospheric ozone transport by global circulation changes due to greenhouse gases will sustain the erythemal irradiance at levels below those in 1965, despite the removal of ozone depleting substances. At northern high latitudes (60°–90°, the projected decreases in cloud

  17. SNF3 as high affinity glucose sensor and its function in supporting the viability of Candida glabrata under glucose-limited environment

    Directory of Open Access Journals (Sweden)

    Tzu Shan eNg

    2015-12-01

    Full Text Available Candida glabrata is an emerging human fungal pathogen that has efficacious nutrient sensing and responsiveness ability. It can be seen through its ability to thrive in diverse range of nutrient limited-human anatomical sites. Therefore, nutrient sensing particularly glucose sensing is thought to be crucial in contributing to the development and fitness of the pathogen. This study aimed to elucidate the role of SNF3 (Sucrose Non Fermenting 3 as a glucose sensor and its possible role in contributing to the fitness and survivability of C. glabrata in glucose-limited environment. The SNF3 knockout strain was constructed and subjected to different glucose concentrations to evaluate its growth, biofilm formation, amphotericin B susceptibility, ex vivo survivability and effects on the transcriptional profiling of the sugar receptor repressor (SRR pathway-related genes. The SNF3Δ strain showed a retarded growth in low glucose environments (0.01% and 0.1% in both fermentation and respiration-preferred conditions but grew well in high glucose concentration environments (1% and 2%. It was also found to be more susceptible to amphotericin B in low glucose environment (0.1% and macrophage engulfment but showed no difference in the biofilm formation capability. The deletion of SNF3 also resulted in the down-regulation of about half of hexose transporters genes (4 out of 9. Overall, the deletion of SNF3 causes significant reduction in the ability of C. glabrata to sense limited surrounding glucose and consequently disrupts its competency to transport and perform the uptake of this critical nutrient. This study highlighted the role of SNF3 as a high affinity glucose sensor and its role in aiding the survivability of C. glabrata particularly in glucose limited environment.

  18. Evaluation of the WIPP Project's compliance with the EPA radiation protection standards for disposal of transuranic waste

    International Nuclear Information System (INIS)

    Neill, R.H.; Chaturvedi, L.; Rucker, D.F.; Silva, M.K.; Walker, B.A.; Channell, J.K.; Clemo, T.M.

    1998-03-01

    The US Environmental Protection Agency's (EPA) proposed rule to certify that the Waste Isolation Pilot Plant (WIPP) meets compliance with the long-term radiation protection standards for geologic repositories (40CFR191 Subparts B and C), is one of the most significant milestones to date for the WIPP project in particular, and for the nuclear waste issue in general. The Environmental Evaluation Group (EEG) has provided an independent technical oversight for the WIPP project since 1978, and is responsible for many improvements in the location, design, and testing of various aspects of the project, including participation in the development of the EPA standards since the early 1980s. The EEG reviewed the development of documentation for assessing the WIPP's compliance by the Sandia National Laboratories following the 1985 promulgation by EPA, and provided many written and verbal comments on various aspects of this effort, culminating in the overall review of the 1992 performance assessment. For the US Department of Energy's (DOE) compliance certification application (CCA), the EEG provided detailed comments on the draft CCA in March, 1996, and additional comments through unpublished letters in 1997 (included as Appendices 8.1 and 8.2 in this report). Since the October 30, 1997, publication of the EPA's proposed rule to certify WIPP, the EEG gave presentations on important issues to the EPA on December 10, 1997, and sent a December 31, 1997 letter with attachments to clarify those issues (Appendix 8.3). The EEG has raised a number of questions that may have an impact on compliance. In spite of the best efforts by the EEG, the EPA reaction to reviews and suggestions has been slow and apparently driven by legal considerations. This report discusses in detail the questions that have been raised about containment requirements. Also discussed are assurance requirements, groundwater protection, individual protection, and an evaluation of EPA's responses to EEG's comments

  19. Fuel transfer system ALARA design review - Project A.15

    International Nuclear Information System (INIS)

    KUEBERTH, L.R.

    2001-01-01

    One mission of the Spent Nuclear Fuel (SNF) Project is to move the SNF from the K Basins in the Hanford 100K Area to an interim dry storage at the Canister Storage Building (CSB) in the Hanford 200 East Area. The Fuel Transfer System (FTS) is a subproject that will move the SNF from the 105K East (KE) Facility to the 105K West (KW) Facility. The SNF will be treated for shipment to the Cold Vacuum Drying (CVD) facility at the KW Basin. The SNF canisters will be loaded underwater into a Shielded Transfer Cask (STC) in the KE Basin. The fully loaded STC will be brought out of the water and placed into a Cask Transfer Overpack (CTO) by the STC Straddle Carrier. As the STC is removed from the water, it will be washed down with demineralized water by an manual rinse system. The CTO with the STC inside will be placed on a transport trailer and transferred to the KW Basin as an intra-facility transfer. The CTO will be unloaded from the shipping trailer at the KW Basin and the STC will be removed from the CTO. The STC will then be lowered into the KW Basin water and the fuel will be removed. The SNF will then be processed for shipment to the CVD. As soon as all of the fuel has been removed from the STC, the cask will be removed from the KW Basin water and placed into the CTO. The CTO will again be placed on the trailer for transport back to the KE Basin where the entire cycle will be repeated approximately 400 times. This document records the As Low As Reasonably Achievable (ALARA) findings and design recommendations/requirements by the SNF Project noted during the Final Design Review of the STC, CTO, STC Transfer System, Annexes and Roadways for support of FTS. This document is structured so that all statements that include the word ''shall'' represent design features that have been or will be implemented within the project scope. Statements that include the words ''should'' or ''recommend'' represent ALARA design features to be evaluated for future implementation

  20. Spent Nuclear Fuel Project FY 1996 Multi-Year Program Plan WBS No. 1.4.1, Revision 1

    International Nuclear Information System (INIS)

    1995-09-01

    This document describes the Spent Nuclear Fuel (SNF) Project portion of the Hanford Strategic Plan for the Hanford Reservation in Richland, Washington. The SNF Project was established to evaluate and integrate the urgent risks associated with N-reactor fuel currently stored at the Hanford site in the K Basins, and to manage the transfer and disposition of other spent nuclear fuels currently stored on the Hanford site. An evaluation of alternatives for the expedited removal of spent fuels from the K Basin area was performed. Based on this study, a Recommended Path Forward for the K Basins was developed and proposed to the U.S. DOE

  1. Spent Nuclear Fuel Project FY 1996 Multi-Year Program Plan WBS No. 1.4.1, Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-09-01

    This document describes the Spent Nuclear Fuel (SNF) Project portion of the Hanford Strategic Plan for the Hanford Reservation in Richland, Washington. The SNF Project was established to evaluate and integrate the urgent risks associated with N-reactor fuel currently stored at the Hanford site in the K Basins, and to manage the transfer and disposition of other spent nuclear fuels currently stored on the Hanford site. An evaluation of alternatives for the expedited removal of spent fuels from the K Basin area was performed. Based on this study, a Recommended Path Forward for the K Basins was developed and proposed to the U.S. DOE.

  2. CRITICALITY CALCULATION FOR THE MOST REACTIVE DEGRADED CONFIGURATIONS OF THE FFTF SNF CODISPOSAL WP CONTAINING AN INTACT IDENT-69 CONTAINER

    International Nuclear Information System (INIS)

    D.R. Moscalu

    2002-01-01

    The objective of this calculation is to perform additional degraded mode criticality evaluations of the Department of Energy's (DOE) Fast Flux Test Facility (FFTF) Spent Nuclear Fuel (SNF) codisposed in a 5-Defense High-Level Waste (5-DHLW) Waste Package (WP). The scope of this calculation is limited to the most reactive degraded configurations of the codisposal WP with an almost intact Ident-69 container (breached and flooded but otherwise non-degraded) containing intact FFTF SNF pins. The configurations have been identified in a previous analysis (CRWMS M andO 1999a) and the present evaluations include additional relevant information that was left out of the original calculations. The additional information describes the exact distribution of fissile material in each container (DOE 2002a). The effects of the changes that have been included in the baseline design of the codisposal WP (CRWMS M andO 2000) are also investigated. The calculation determines the effective neutron multiplication factor (k eff ) for selected degraded mode internal configurations of the codisposal waste package. These calculations will support the demonstration of the technical viability of the design solution adopted for disposing of MOX (FFTF) spent nuclear fuel in the potential repository. This calculation is subject to the Quality Assurance Requirements and Description (QARD) (DOE 2002b) per the activity evaluation under work package number P6212310M2 in the technical work plan TWP-MGR-MD-0000101 (BSC 2002)

  3. An innovative way of thinking nuclear waste management - Neutron physics of a reactor directly operating on SNF.

    Science.gov (United States)

    Merk, Bruno; Litskevich, Dzianis; Bankhead, Mark; Taylor, Richard J

    2017-01-01

    A solution for the nuclear waste problem is the key challenge for an extensive use of nuclear reactors as a major carbon free, sustainable, and applied highly reliable energy source. Partitioning and Transmutation (P&T) promises a solution for improved waste management. Current strategies rely on systems designed in the 60's for the massive production of plutonium. We propose an innovative strategic development plan based on invention and innovation described with the concept of developments in s-curves identifying the current boundary conditions, and the evolvable objectives. This leads to the ultimate, universal vision for energy production characterized by minimal use of resources and production of waste, while being economically affordable and safe, secure and reliable in operation. This vision is transformed into a mission for a disruptive development of the future nuclear energy system operated by burning of existing spent nuclear fuel (SNF) without prior reprocessing. This highly innovative approach fulfils the sustainability goals and creates new options for P&T. A proof on the feasibility from neutronic point of view is given demonstrating sufficient breeding of fissile material from the inserted SNF. The system does neither require new resources nor produce additional waste, thus it provides a highly sustainable option for a future nuclear system fulfilling the requests of P&T as side effect. In addition, this nuclear system provides enhanced resistance against misuse of Pu and a significantly reduced fuel cycle. However, the new system requires a demand driven rethinking of the separation process to be efficient.

  4. The SWI/SNF chromatin-remodeling factors BAF60a, b, and c in nutrient signaling and metabolic control

    Directory of Open Access Journals (Sweden)

    Ruo-Ran Wang

    2017-07-01

    Full Text Available ABSTRACT Metabolic syndrome has become a global epidemic that adversely affects human health. Both genetic and environmental factors contribute to the pathogenesis of metabolic disorders; however, the mechanisms that integrate these cues to regulate metabolic physiology and the development of metabolic disorders remain incompletely defined. Emerging evidence suggests that SWI/SNF chromatin-remodeling complexes are critical for directing metabolic reprogramming and adaptation in response to nutritional and other physiological signals. The ATP-dependent SWI/SNF chromatin-remodeling complexes comprise up to 11 subunits, among which the BAF60 subunit serves as a key link between the core complexes and specific transcriptional factors. The BAF60 subunit has three members, BAF60a, b, and c. The distinct tissue distribution patterns and regulatory mechanisms of BAF60 proteins confer each isoform with specialized functions in different metabolic cell types. In this review, we summarize the emerging roles and mechanisms of BAF60 proteins in the regulation of nutrient sensing and energy metabolism under physiological and disease conditions.

  5. Modern projection of the old electroscope for nuclear radiation quantitative work and demonstrations

    Science.gov (United States)

    Oliveira Bastos, Rodrigo; Baltokoski Boch, Layara

    2017-11-01

    Although quantitative measurements in radioactivity teaching and research are only believed to be possible with high technology, early work in this area was fully accomplished with very simple apparatus such as zinc sulphide screens and electroscopes. This article presents an experimental practice using the electroscope, which is a very simple apparatus that has been widely used for educational purposes, although generally for qualitative work. The main objective is to show the possibility of measuring radioactivity not only in qualitative demonstrations, but also in quantitative experimental practices. The experimental set-up is a low-cost ion chamber connected to an electroscope in a configuration that is very similar to that used by Marie and Pierre Currie, Rutherford, Geiger, Pacini, Hess and other great researchers from the time of the big discoveries in nuclear and high-energy particle physics. An electroscope leaf is filmed and projected, permitting the collection of quantitative data for the measurement of the 220Rn half-life, collected from the emanation of the lantern mantles. The article presents the experimental procedures and the expected results, indicating that the experiment may provide support for nuclear physics classes. These practices could spread widely to either university or school didactic laboratories, and the apparatus has the potential to allow the development of new teaching activity for nuclear physics.

  6. Post Irradiation Examination Plan for High-Burnup Demonstration Project Sister Rods

    Energy Technology Data Exchange (ETDEWEB)

    Scaglione, John M [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Montgomery, Rose [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Bevard, Bruce Balkcom [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

    2016-04-01

    This test plan describes the experimental work to be implemented by the U.S. Department of Energy (DOE) Office of Nuclear Energy (NE) to characterize high burnup (HBU) spent nuclear fuel (SNF) in conjunction with the High Burnup Dry Storage Cask Research and Development Project and serves to coordinate and integrate the multi-year experimental program to collect and develop data regarding the continued storage and eventual transport of HBU (i.e., >45 GWd/MTU) SNF. The work scope involves the development, performance, technical integration, and oversight of measurements and collection of relevant data, guided by analyses and demonstration of need.

  7. Radiation safety during remediation of the SevRAO facilities: 10 years of regulatory experience.

    Science.gov (United States)

    Sneve, M K; Shandala, N; Kiselev, S; Simakov, A; Titov, A; Seregin, V; Kryuchkov, V; Shcheblanov, V; Bogdanova, L; Grachev, M; Smith, G M

    2015-09-01

    In compliance with the fundamentals of the government's policy in the field of nuclear and radiation safety approved by the President of the Russian Federation, Russia has developed a national program for decommissioning of its nuclear legacy. Under this program, the State Atomic Energy Corporation 'Rosatom' is carrying out remediation of a Site for Temporary Storage of spent nuclear fuel (SNF) and radioactive waste (RW) at Andreeva Bay located in Northwest Russia. The short term plan includes implementation of the most critical stage of remediation, which involves the recovery of SNF from what have historically been poorly maintained storage facilities. SNF and RW are stored in non-standard conditions in tanks designed in some cases for other purposes. It is planned to transport recovered SNF to PA 'Mayak' in the southern Urals. This article analyses the current state of the radiation safety supervision of workers and the public in terms of the regulatory preparedness to implement effective supervision of radiation safety during radiation-hazardous operations. It presents the results of long-term radiation monitoring, which serve as informative indicators of the effectiveness of the site remediation and describes the evolving radiation situation. The state of radiation protection and health care service support for emergency preparedness is characterized by the need to further study the issues of the regulator-operator interactions to prevent and mitigate consequences of a radiological accident at the facility. Having in mind the continuing intensification of practical management activities related to SNF and RW in the whole of northwest Russia, it is reasonable to coordinate the activities of the supervision bodies within a strategic master plan. Arrangements for this master plan are discussed, including a proposed programme of actions to enhance the regulatory supervision in order to support accelerated mitigation of threats related to the nuclear legacy in the

  8. Special report for UNDP on regional RCA project for Asia and the Pacific on industrial applications of isotopes and radiation technology. Technical, economic and commercial analyses

    International Nuclear Information System (INIS)

    1980-01-01

    The report contains seven sub-projects for RCA countries on the following problems: tracer technology in industry; non-destructive testing practice; radiation processing; nucleonic control systems for paper manufacture and steel manufacture; mineral exploration, mining and process control; nuclear instruments maintenance practices

  9. Some perspectives on research into the biological response to non-ionizing electromagnetic radiation. [relation to SETI, SPS, and other government projects

    Science.gov (United States)

    Sharp, J. C.

    1979-01-01

    Research on the biological effects of RF radiation in the United States has undergone a series of swings during the last three decades. The resurgence of research during the past decade is examined in the light of two projects: the proposed Space Power Station and SETI.

  10. Radiation protection of patients in medical exposures: regional project IAEA 2007-2008 RLA/9/57

    International Nuclear Information System (INIS)

    2007-01-01

    The radiation protection of patients in medical exposures as a project is composed of 5 regional covers some 80 countries, 94 hospitals and 120 activities related to radiology and radiation. A workshop was developed with the following objectives: to provide theoretical and practical elements for professionals in radiation protection of patients developing tasks assigned, to identify the methodology by measurement through sheets for data collection and interpretation of the same, to perform practical exercises of the procedures to apply in radiology, mammography, computed tomography and interventionism. The workshop was divided into theoretical and practical sections, sections for analysis and interpretation of data and a final exam. This project aims to identify strengths and weaknesses, simple primary objectives with fast results, involvement of doctors, institutional commitment to see results after more complex stages, technique stiffness, sustainability. Among the goals of the member states are: To prevent radioinjury in interventional procedures and reduce the probability of stochastic effect, especially in pediatrics; dose reduction changing of rare earth in countries that have not yet made, optimization in mammography, optimization of protection in CT, with emphasis in pediatrics; protection of family and the public to give discharge the patient, after therapy with radiopharmaceuticals; to prevent accidental exposures in radiotherapy and pediatric radiology. The content is divided into four parts which include different forms to collect information constituted on the following topics: Intervention, with information over Uncertainties in calibration of the meter P K A, Evaluation of dose with radiochromatic movie, Data processing and radiation protection, Measurements of kerma-area product, Practice: Exposure assessment of the patient in interventional radiology, Determination of the Hemi reducer layer, Recalibration and use of a meter of Kerma-area product

  11. SPENT NUCLEAR FUEL (SNF) PROJECT CANISTER STORAGE BUILDING (CSB) MULTI CANISTER OVERPACK (MCO) SAMPLING SYSTEM VALIDATION (OCRWM)

    International Nuclear Information System (INIS)

    BLACK, D.M.; KLEM, M.J.

    2003-01-01

    Approximately 400 Multi-canister overpacks (MCO) containing spent nuclear fuel are to be interim stored at the Canister Storage Building (CSB). Several MCOs (monitored MCOs) are designated to be gas sampled periodically at the CSB sampling/weld station (Bader 2002a). The monitoring program includes pressure, temperature and gas composition measurements of monitored MCOs during their first two years of interim storage at the CSB. The MCO sample cart (CART-001) is used at the sampling/weld station to measure the monitored MCO gas temperature and pressure, obtain gas samples for laboratory analysis and refill the monitored MCO with high purity helium as needed. The sample cart and support equipment were functionally and operationally tested and validated before sampling of the first monitored MCO (H-036). This report documents the results of validation testing using training MCO (TR-003) at the CSB. Another report (Bader 2002b) documents the sample results from gas sampling of the first monitored MCO (H-036). Validation testing of the MCO gas sampling system showed the equipment and procedure as originally constituted will satisfactorily sample the first monitored MCO. Subsequent system and procedural improvements will provide increased flexibility and reliability for future MCO gas sampling. The physical operation of the sampling equipment during testing provided evidence that theoretical correlation factors for extrapolating MCO gas composition from sample results are unnecessarily conservative. Empirically derived correlation factors showed adequate conservatism and support use of the sample system for ongoing monitored MCO sampling

  12. The results of the pilot project in Georgia to install a network of electromagnetic radiation before the earthquake

    Science.gov (United States)

    Machavariani, Kakhaber; Khazaradze, Giorgi; Turazashvili, Ioseb; Kachakhidze, Nino; Kachakhidze, Manana; Gogoberidze, Vitali

    2016-04-01

    The world's scientific literature recently published many very important and interesting works of VLF / LF electromagnetic emissions, which is observed in the process of earthquake preparation. This works reliable earthquake prediction in terms of trends. Because, Georgia is located in Trans Asian earthquake zone, VLF / LF electromagnetic emissions network are essential. In this regard, it was possible to take first steps. It is true that our university has Shota Rustaveli National Science Foundation № DI / 21 / 9-140 / 13 grant, which included the installation of a receiver in Georgia, but failed due to lack of funds to buy this device. However, European friends helped us (Prof. Dr. PF Biagi and Prof. Dr. Aydın BÜYÜKSARAÇ) and made possible the installation of a receiver. Turkish scientists expedition in Georgia was organized in August 2015. They brought with them VLF / LF electromagnetic emissions receiver and together with Georgian scientists install near Tbilisi. The station was named GEO-TUR. It should be noted that Georgia was involved in the work of the European network. It is possible to completely control the earthquake in Georgia in terms of electromagnetic radiation. This enables scientists to obtain the relevant information not only on the territory of our country, but also on seismically active European countries as well. In order to maintain and develop our country in this new direction, it is necessary to keep independent group of scientists who will learn electromagnetic radiation ahead of an earthquake in Georgia. At this stage, we need to remedy this shortcoming, it is necessary and appropriate specialists to Georgia to engage in a joint international research. The work is carried out in the frame of grant (DI/21/9-140/13 „Pilot project of before earthquake detected Very Low Frequency/Low Frequency electromagnetic emission network installation in Georgia") by financial support of Shota Rustaveli National Science Foundation.

  13. Reduction of radiation risks in patients undergoing some X-ray examinations by using optimal projections: A Monte Carlo program-based mathematical calculation

    Directory of Open Access Journals (Sweden)

    A Chaparian

    2014-01-01

    Full Text Available The objectives of this paper were calculation and comparison of the effective doses, the risks of exposure-induced cancer, and dose reduction in the gonads for male and female patients in different projections of some X-ray examinations. Radiographies of lumbar spine [in the eight projections of anteroposterior (AP, posteroanterior (PA, right lateral (RLAT, left lateral (LLAT, right anterior-posterior oblique (RAO, left anterior-posterior oblique (LAO, right posterior-anterior oblique (RPO, and left posterior-anterior oblique (LPO], abdomen (in the two projections of AP and PA, and pelvis (in the two projections of AP and PA were investigated. A solid-state dosimeter was used for the measuring of the entrance skin exposure. A Monte Carlo program was used for calculation of effective doses, the risks of radiation-induced cancer, and doses to the gonads related to the different projections. Results of this study showed that PA projection of abdomen, lumbar spine, and pelvis radiographies caused 50%-57% lower effective doses than AP projection and 50%-60% reduction in radiation risks. Also use of LAO projection of lumbar spine X-ray examination caused 53% lower effective dose than RPO projection and 56% and 63% reduction in radiation risk for male and female, respectively, and RAO projection caused 28% lower effective dose than LPO projection and 52% and 39% reduction in radiation risk for males and females, respectively. About dose reduction in the gonads, using of the PA position rather than AP in the radiographies of the abdomen, lumbar spine, and pelvis can result in reduction of the ovaries doses in women, 38%, 31%, and 25%, respectively and reduction of the testicles doses in males, 76%, 86%, and 94%, respectively. Also for oblique projections of lumbar spine X-ray examination, with employment of LAO rather than RPO and also RAO rather than LPO, demonstrated 22% and 13% reductions to the ovaries doses and 66% and 54% reductions in the

  14. Solar Particle Radiation Storms Forecasting and Analysis within the Framework of the `HESPERIA' HORIZON 2020 Project

    Science.gov (United States)

    Posner, A.; Malandraki, O.; Nunez, M.; Heber, B.; Labrenz, J.; Kühl, P.; Milas, N.; Tsiropoula, G.; Pavlos, E.

    2017-12-01

    operational on the HESPERIA server maintained at the National Observatory of Athens (https://www.hesperia.astro.noa.gr/). This project received funding from the EU's Horizon 2020 research and innovation programme under grant No 637324.

  15. Tropospheric ozone changes, radiative forcing and attribution to emissions in the Atmospheric Chemistry and Climate Model Intercomparison Project (ACCMIP

    Directory of Open Access Journals (Sweden)

    D. S. Stevenson

    2013-03-01

    Full Text Available Ozone (O3 from 17 atmospheric chemistry models taking part in the Atmospheric Chemistry and Climate Model Intercomparison Project (ACCMIP has been used to calculate tropospheric ozone radiative forcings (RFs. All models applied a common set of anthropogenic emissions, which are better constrained for the present-day than the past. Future anthropogenic emissions follow the four Representative Concentration Pathway (RCP scenarios, which define a relatively narrow range of possible air pollution emissions. We calculate a value for the pre-industrial (1750 to present-day (2010 tropospheric ozone RF of 410 mW m−2. The model range of pre-industrial to present-day changes in O3 produces a spread (±1 standard deviation in RFs of ±17%. Three different radiation schemes were used – we find differences in RFs between schemes (for the same ozone fields of ±10%. Applying two different tropopause definitions gives differences in RFs of ±3%. Given additional (unquantified uncertainties associated with emissions, climate-chemistry interactions and land-use change, we estimate an overall uncertainty of ±30% for the tropospheric ozone RF. Experiments carried out by a subset of six models attribute tropospheric ozone RF to increased emissions of methane (44±12%, nitrogen oxides (31 ± 9%, carbon monoxide (15 ± 3% and non-methane volatile organic compounds (9 ± 2%; earlier studies attributed more of the tropospheric ozone RF to methane and less to nitrogen oxides. Normalising RFs to changes in tropospheric column ozone, we find a global mean normalised RF of 42 mW m−2 DU−1, a value similar to previous work. Using normalised RFs and future tropospheric column ozone projections we calculate future tropospheric ozone RFs (mW m−2; relative to 1750 for the four future scenarios (RCP2.6, RCP4.5, RCP6.0 and RCP8.5 of 350, 420, 370 and 460 (in 2030, and 200, 300, 280 and 600 (in 2100. Models show some coherent responses of ozone to climate change

  16. Spent nuclear fuel project multi-canister overpack, additional NRC requirements

    International Nuclear Information System (INIS)

    Garvin, L.J.

    1998-01-01

    The US Department of Energy (DOE), established in the K Basin Spent Nuclear Fuel Project Regulatory Policy, dated August 4, 1995 (hereafter referred to as the Policy), the requirement for new Spent Nuclear Fuel (SNF) Project facilities to achieve nuclear safety equivalency to comparable US Nuclear Regulatory Commission (NRC)-licensed facilities. For activities other than during transport, when the Multi-Canister Overpack (MCO) is used and resides in the Canister Storage Building (CSB), Cold Vacuum Drying (CVD) facility or Hot Conditioning System, additional NRC requirements will also apply to the MCO based on the safety functions it performs and its interfaces with the SNF Project facilities. An evaluation was performed in consideration of the MCO safety functions to identify any additional NRC requirements needed, in combination with the existing and applicable DOE requirements, to establish nuclear safety equivalency for the MCO. The background, basic safety issues and general comparison of NRC and DOE requirements for the SNF Project are presented in WHC-SD-SNF-DB-002

  17. Intercomparison for individual monitoring of external exposure from photon radiation. Results of a co-ordinated research project 1996-1998

    International Nuclear Information System (INIS)

    1999-12-01

    This TECDOC presents the results of a Co-ordinated Research Project on Intercomparison for Individual Monitoring of External Exposure from photon radiation. The International Basic Safety Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources (BSS) have endorsed the use of the operational quantities for monitoring purposes. Specifically, personal dose equivalent, H p (d), is to be used for individual dosimetry to demonstrate compliance with the exposure limit recommendations, while for workplace area monitoring the ambient dose equivalent and the directional dose equivalent are recommended. In view of the technical difficulties associated with the introduction of these operational quantities the IAEA decided to assist Member States in their provision of appropriate dosimetry for occupational protection. In this respect, intercomparisons have proven to be a cost effective method of providing such support. A Co-ordinated Research Project (CRP) was started in 1997 on Intercomparison for Individual Monitoring of External Exposure from photon radiation, involving more than twenty laboratories from eastern Europe and the countries of the former Soviet Union, and focusing on personnel dosimetry services for nuclear power plants. This CRP was part of the activities of the IAEA Occupational Protection Programme, the objective4s of which are to promote and internationally harmonized approach for optimizing occupational radiation protection through: the development of guides, within the IAEA activities for establishing standards for radiation protection, for restricting radiation exposures in the workplace and for applying current occupational radiation protection techniques, and the promotion of the application of these guidelines. The preparatory phase included, in May 1997, a workshop aimed at familiarizing the participants with the new operational quantities

  18. GENII (Generation II): The Hanford Environmental Radiation Dosimetry Software System: Volume 3, Code maintenance manual: Hanford Environmental Dosimetry Upgrade Project

    Energy Technology Data Exchange (ETDEWEB)

    Napier, B.A.; Peloquin, R.A.; Strenge, D.L.; Ramsdell, J.V.

    1988-09-01

    The Hanford Environmental Dosimetry Upgrade Project was undertaken to incorporate the internal dosimetry models recommended by the International Commission on Radiological Protection (ICRP) in updated versions of the environmental pathway analysis models used at Hanford. The resulting second generation of Hanford environmental dosimetry computer codes is compiled in the Hanford Environmental Dosimetry System (Generation II, or GENII). This coupled system of computer codes is intended for analysis of environmental contamination resulting from acute or chronic releases to, or initial contamination of, air, water, or soil, on through the calculation of radiation doses to individuals or populations. GENII is described in three volumes of documentation. This volume is a Code Maintenance Manual for the serious user, including code logic diagrams, global dictionary, worksheets to assist with hand calculations, and listings of the code and its associated data libraries. The first volume describes the theoretical considerations of the system. The second volume is a Users' Manual, providing code structure, users' instructions, required system configurations, and QA-related topics. 7 figs., 5 tabs.

  19. GENII [Generation II]: The Hanford Environmental Radiation Dosimetry Software System: Volume 3, Code maintenance manual: Hanford Environmental Dosimetry Upgrade Project

    International Nuclear Information System (INIS)

    Napier, B.A.; Peloquin, R.A.; Strenge, D.L.; Ramsdell, J.V.

    1988-09-01

    The Hanford Environmental Dosimetry Upgrade Project was undertaken to incorporate the internal dosimetry models recommended by the International Commission on Radiological Protection (ICRP) in updated versions of the environmental pathway analysis models used at Hanford. The resulting second generation of Hanford environmental dosimetry computer codes is compiled in the Hanford Environmental Dosimetry System (Generation II, or GENII). This coupled system of computer codes is intended for analysis of environmental contamination resulting from acute or chronic releases to, or initial contamination of, air, water, or soil, on through the calculation of radiation doses to individuals or populations. GENII is described in three volumes of documentation. This volume is a Code Maintenance Manual for the serious user, including code logic diagrams, global dictionary, worksheets to assist with hand calculations, and listings of the code and its associated data libraries. The first volume describes the theoretical considerations of the system. The second volume is a Users' Manual, providing code structure, users' instructions, required system configurations, and QA-related topics. 7 figs., 5 tabs

  20. GENII: The Hanford Environmental Radiation Dosimetry Software System: Volume 2, Users' manual: Hanford Environmental Dosimetry Upgrade Project

    International Nuclear Information System (INIS)

    Napier, B.A.; Peloquin, R.A.; Strenge, D.L.; Ramsdell, J.V.

    1988-11-01

    The Hanford Environmental Dosimetry Upgrade Project was undertaken to incorporate the internal dosimetry models recommended by the International Commission on Radiological Protection (ICRP) in updated versions of the environmental pathway analysis models used at Hanford. The resulting second generation of Hanford environmental dosimetry computer codes is compiled in the Hanford Environmental Dosimetry System (Generation II, or GENII). The purpose of this coupled system of computer codes is to analyze environmental contamination of, air, water, or soil. This is accomplished by calculating radiation doses to individuals or populations. GENII is described in three volumes of documentation. This second volume is a Users' Manual, providing code structure, users' instructions, required system configurations, and QA-related topics. The first volume describes the theoretical considerations of the system. The third volume is a Code Maintenance Manual for the user who requires knowledge of code detail. It includes logic diagrams, global dictionary, worksheets, example hand calculations, and listings of the code and its associated data libraries. 27 refs., 17 figs., 23 tabs

  1. National spent fuel program preliminary report RCRA characteristics of DOE-owned spent nuclear fuel DOE-SNF-REP-002. Revision 3

    International Nuclear Information System (INIS)

    1995-07-01

    This report presents information on the preliminary process knowledge to be used in characterizing all Department of Energy (DOE)-owned Spent Nuclear Fuel (SNF) types that potentially exhibit a Resource Conservation and Recovery Act (RCRA) characteristic. This report also includes the process knowledge, analyses, and rationale used to preliminarily exclude certain SNF types from RCRA regulation under 40 CFR section 261.4(a)(4), ''Identification and Listing of Hazardous Waste,'' as special nuclear and byproduct material. The evaluations and analyses detailed herein have been undertaken as a proactive approach. In the event that DOE-owned SNF is determined to be a RCRA solid waste, this report provides general direction for each site regarding further characterization efforts. The intent of this report is also to define the path forward to be taken for further evaluation of specific SNF types and a recommended position to be negotiated and established with regional and state regulators throughout the DOE Complex regarding the RCRA-related policy issues

  2. National spent fuel program preliminary report RCRA characteristics of DOE-owned spent nuclear fuel DOE-SNF-REP-002. Revision 3

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-07-01

    This report presents information on the preliminary process knowledge to be used in characterizing all Department of Energy (DOE)-owned Spent Nuclear Fuel (SNF) types that potentially exhibit a Resource Conservation and Recovery Act (RCRA) characteristic. This report also includes the process knowledge, analyses, and rationale used to preliminarily exclude certain SNF types from RCRA regulation under 40 CFR {section}261.4(a)(4), ``Identification and Listing of Hazardous Waste,`` as special nuclear and byproduct material. The evaluations and analyses detailed herein have been undertaken as a proactive approach. In the event that DOE-owned SNF is determined to be a RCRA solid waste, this report provides general direction for each site regarding further characterization efforts. The intent of this report is also to define the path forward to be taken for further evaluation of specific SNF types and a recommended position to be negotiated and established with regional and state regulators throughout the DOE Complex regarding the RCRA-related policy issues.

  3. Rhabdoid and Undifferentiated Phenotype in Renal Cell Carcinoma: Analysis of 32 Cases Indicating a Distinctive Common Pathway of Dedifferentiation Frequently Associated With SWI/SNF Complex Deficiency.

    Science.gov (United States)

    Agaimy, Abbas; Cheng, Liang; Egevad, Lars; Feyerabend, Bernd; Hes, Ondřej; Keck, Bastian; Pizzolitto, Stefano; Sioletic, Stefano; Wullich, Bernd; Hartmann, Arndt

    2017-02-01

    Undifferentiated (anaplastic) and rhabdoid cell features are increasingly recognized as adverse prognostic findings in renal cell carcinoma (RCC), but their molecular pathogenesis has not been studied sufficiently. Recent studies identified alterations in the Switch Sucrose nonfermentable (SWI/SNF) chromatin remodeling complex as molecular mechanisms underlying dedifferentiation and rhabdoid features in carcinomas of different organs. We herein have analyzed 32 undifferentiated RCCs having in common an undifferentiated (anaplastic) phenotype, prominent rhabdoid features, or both, irrespective of the presence or absence of conventional RCC component. Cases were stained with 6 SWI/SNF pathway members (SMARCB1, SMARCA2, SMARCA4, ARID1A, SMARCC1, and SMARCC2) in addition to conventional RCC markers. Patients were 20 males and 12 females aged 32 to 85 years (mean, 59). A total of 22/27 patients with known stage presented with ≥pT3. A differentiated component varying from microscopic to major component was detected in 20/32 cases (16 clear cell and 2 cases each chromophobe and papillary RCC). The undifferentiated component varied from rhabdoid dyscohesive cells to large epithelioid to small monotonous anaplastic cells. Variable loss of at least 1 SWI/SNF complex subunit was noted in the undifferentiated/rhabdoid component of 21/32 cases (65%) compared with intact or reduced expression in the differentiated component. A total of 15/17 patients (88%) with follow-up died of metastatic disease (mostly within 1 y). Only 2 patients were disease free at last follow-up (1 and 6 y). No difference in survival, age distribution, or sex was observed between the SWI/SNF-deficient and the SWI/SNF-intact group. This is the first study exploring the role of SWI/SNF deficiency as a potential mechanism underlying undifferentiated and rhabdoid phenotype in RCC. Our results highlight the association between the aggressive rhabdoid phenotype and the SWI/SNF complex deficiency, consistent

  4. STRUCTURAL CALCULATIONS FOR THE LIFTING IN VERTICAL ORIENTATION OF 5-DHLW/DOE SNF SINGLE CRM WASTE PACKAGES

    International Nuclear Information System (INIS)

    S. Mastilovic

    1999-01-01

    The purpose of this activity is to determine the structural response of the extension of outer shell (which is referred to as skirt throughout this document) designs of both long and short design concepts of 5-Defense High-Level Waste (DHLW) Department of Energy (DOE) spent nuclear fuel (SNF) single corrosion resistant material (CRM) waste packages (WP), subjected to a gravitational load in the course of lifting in vertical orientation. The scope of this document is limited to reporting the calculation results in terms of stress intensity magnitudes. This activity is associated with the WP design; calculations are performed by the Waste Package Design group. AP-3.124, Revision 0, ICN 0, Calculations, is used to perform the calculation and develop the document

  5. Regional Geologic Evaluations for Disposal of HLW and SNF: The Pierre Shale of the Northern Great Plains

    Energy Technology Data Exchange (ETDEWEB)

    Perry, Frank Vinton [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Kelley, Richard E. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2017-09-14

    The DOE Spent Fuel and Waste Technology (SWFT) R&D Campaign is supporting research on crystalline rock, shale (argillite) and salt as potential host rocks for disposal of HLW and SNF in a mined geologic repository. The distribution of these three potential repository host rocks is limited to specific regions of the US and to different geologic and hydrologic environments (Perry et al., 2014), many of which may be technically suitable as a site for mined geologic disposal. This report documents a regional geologic evaluation of the Pierre Shale, as an example of evaluating a potentially suitable shale for siting a geologic HLW repository. This report follows a similar report competed in 2016 on a regional evaluation of crystalline rock that focused on the Superior Province of the north-central US (Perry et al., 2016).

  6. Reduction of solar radiation by manmade aerosol in Europe. A joint European project EV5V-CT92-0171

    Energy Technology Data Exchange (ETDEWEB)

    Ten Brink, H M [Netherlands Energy Research Foundation (ECN), Petten (Netherlands); Grassl, H; Schult, I [Max Planck Institut fuer Meteorologie, Hamburg (Germany); Maracchi, G; Bindi, M [Centro di Studio per l` Applicazione dell` Informatica in Agricoltura, Firenze (Italy); Scott, J A [University College Dublin (Ireland); Dlugi, R [Meteorologisches Institut der Universitaet Muenchen (Germany); Russak, V [Institute of Astro-Physics and Atmospheric Physics, Toravere (Estonia)

    1995-08-01

    Results of a study on the reduction of solar radiation by back-scattering on manmade aerosol in Europe are presented. A localized study was carried out due to the relatively short residence time of aerosols in the atmosphere which limits the extent of the European aerosol to the European area. The regional character of the aerosol forcing called for a regional investigation which was performed along three lines: (a) measurement of the light-scattering by aerosol components known to be of anthropogenic origin (sulfate and nitrate) in The Netherlands; (b) the trend in solar radiation in Italy, Ireland, Estonia and Germany; (c) calculations of the radiative transfer of solar radiation through the atmosphere with typical continental aerosol. The combined results of the project led to a first indicative value of the reduction in solar radiation in Europe of -3 to -4 W.m{sup - }2. This value is based on combining the following results from the subprojects. Nitrate increases the amount of light scattered by aerosol in The Netherlands, compared to the reference compound in the IPCC estimate (sulfate) by a factor of two. Carbonaceous aerosol material seems to have an equally large contribution to the light-scattering. A decrease in the radiation over the last forty years with 3 to 5 % was observed in Italy and in Estonia, while a decrease was absent at a background station in Ireland with predominantly natural marine aerosol. The trend values are indicative of an even higher decrease in solar radiation than the mentioned -3 to -4 W.m{sup -2}. A reduction of solar radiation of order -20 W.m{sup -2} on cloudless days was deduced from a limited set of measurements in The Netherlands. 1-dimensional modeling of climate parameters with integrated aerosol forcing indicates a local cooling of 1.3 K for the mentioned reduction in solar radiation. The mentioned values have an estimated uncertainty of the same magnitude as the actual values. (Abstract Truncated)

  7. Case studies in the application of probabilistic safety assessment techniques to radiation sources. Final report of a coordinated research project 2001-2003

    International Nuclear Information System (INIS)

    2006-04-01

    Radiation sources are used worldwide in many industrial and medical applications. In general, the safety record associated with their use has been very good. However, accidents involving these sources have occasionally resulted in unplanned exposures to individuals. When assessed prospectively, this type of exposure is termed a 'potential exposure'. The International Commission on Radiological Protection (ICRP) has recommended the assessment of potential exposures that may result from radiation sources and has suggested that probabilistic safety assessment (PSA) techniques may be used in this process. Also, Paragraph 2.13 of the International Basic Safety Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources (BSS) requires that the authorization process for radiation sources include an assessment of all exposures, including potential exposures, which may result from the use of a radiation source. In light of the ICRP's work described above, and the possibility that PSA techniques could be used in exposure assessments that are required by the BSS, the IAEA initiated a coordinated research project (CRP) to study the benefits and limitations of the application of PSA techniques to radiation sources. The results of this CRP are presented in this publication. It should be noted that these results are based solely on the work performed, and the conclusions drawn, by the research teams involved in this CRP. It is intended that international organizations involved in radiation protection will review the information in this report and will take account of it during the development of guidance and requirements related to the assessment of potential exposures from radiation sources. Also, it is anticipated that the risk insights obtained through the studies will be considered by medical practitioners, facility staff and management, equipment designers, and regulators in their safety management and risk evaluation activities. A draft

  8. An innovative way of thinking nuclear waste management - Neutron physics of a reactor directly operating on SNF.

    Directory of Open Access Journals (Sweden)

    Bruno Merk

    Full Text Available A solution for the nuclear waste problem is the key challenge for an extensive use of nuclear reactors as a major carbon free, sustainable, and applied highly reliable energy source. Partitioning and Transmutation (P&T promises a solution for improved waste management. Current strategies rely on systems designed in the 60's for the massive production of plutonium. We propose an innovative strategic development plan based on invention and innovation described with the concept of developments in s-curves identifying the current boundary conditions, and the evolvable objectives. This leads to the ultimate, universal vision for energy production characterized by minimal use of resources and production of waste, while being economically affordable and safe, secure and reliable in operation. This vision is transformed into a mission for a disruptive development of the future nuclear energy system operated by burning of existing spent nuclear fuel (SNF without prior reprocessing. This highly innovative approach fulfils the sustainability goals and creates new options for P&T. A proof on the feasibility from neutronic point of view is given demonstrating sufficient breeding of fissile material from the inserted SNF. The system does neither require new resources nor produce additional waste, thus it provides a highly sustainable option for a future nuclear system fulfilling the requests of P&T as side effect. In addition, this nuclear system provides enhanced resistance against misuse of Pu and a significantly reduced fuel cycle. However, the new system requires a demand driven rethinking of the separation process to be efficient.

  9. An innovative way of thinking nuclear waste management – Neutron physics of a reactor directly operating on SNF

    Science.gov (United States)

    Litskevich, Dzianis; Bankhead, Mark; Taylor, Richard J.

    2017-01-01

    A solution for the nuclear waste problem is the key challenge for an extensive use of nuclear reactors as a major carbon free, sustainable, and applied highly reliable energy source. Partitioning and Transmutation (P&T) promises a solution for improved waste management. Current strategies rely on systems designed in the 60’s for the massive production of plutonium. We propose an innovative strategic development plan based on invention and innovation described with the concept of developments in s-curves identifying the current boundary conditions, and the evolvable objectives. This leads to the ultimate, universal vision for energy production characterized by minimal use of resources and production of waste, while being economically affordable and safe, secure and reliable in operation. This vision is transformed into a mission for a disruptive development of the future nuclear energy system operated by burning of existing spent nuclear fuel (SNF) without prior reprocessing. This highly innovative approach fulfils the sustainability goals and creates new options for P&T. A proof on the feasibility from neutronic point of view is given demonstrating sufficient breeding of fissile material from the inserted SNF. The system does neither require new resources nor produce additional waste, thus it provides a highly sustainable option for a future nuclear system fulfilling the requests of P&T as side effect. In addition, this nuclear system provides enhanced resistance against misuse of Pu and a significantly reduced fuel cycle. However, the new system requires a demand driven rethinking of the separation process to be efficient. PMID:28749952

  10. Solution NMR structure of the HLTF HIRAN domain: a conserved module in SWI2/SNF2 DNA damage tolerance proteins

    International Nuclear Information System (INIS)

    Korzhnev, Dmitry M.; Neculai, Dante; Dhe-Paganon, Sirano; Arrowsmith, Cheryl H.; Bezsonova, Irina

    2016-01-01

    HLTF is a SWI2/SNF2-family ATP-dependent chromatin remodeling enzyme that acts in the error-free branch of DNA damage tolerance (DDT), a cellular mechanism that enables replication of damaged DNA while leaving damage repair for a later time. Human HLTF and a closely related protein SHPRH, as well as their yeast homologue Rad5, are multi-functional enzymes that share E3 ubiquitin-ligase activity required for activation of the error-free DDT. HLTF and Rad5 also function as ATP-dependent dsDNA translocases and possess replication fork reversal activities. Thus, they can convert Y-shaped replication forks into X-shaped Holliday junction structures that allow error-free replication over DNA lesions. The fork reversal activity of HLTF is dependent on 3′-ssDNA-end binding activity of its N-terminal HIRAN domain. Here we present the solution NMR structure of the human HLTF HIRAN domain, an OB-like fold module found in organisms from bacteria (as a stand-alone domain) to plants, fungi and metazoan (in combination with SWI2/SNF2 helicase-like domain). The obtained structure of free HLTF HIRAN is similar to recently reported structures of its DNA bound form, while the NMR analysis also reveals that the DNA binding site of the free domain exhibits conformational heterogeneity. Sequence comparison of N-terminal regions of HLTF, SHPRH and Rad5 aided by knowledge of the HLTF HIRAN structure suggests that the SHPRH N-terminus also includes an uncharacterized structured module, exhibiting weak sequence similarity with HIRAN regions of HLTF and Rad5, and potentially playing a similar functional role.

  11. Solution NMR structure of the HLTF HIRAN domain: a conserved module in SWI2/SNF2 DNA damage tolerance proteins

    Energy Technology Data Exchange (ETDEWEB)

    Korzhnev, Dmitry M. [University of Connecticut Health, Department of Molecular Biology and Biophysics (United States); Neculai, Dante [Zhejiang University, School of Medicine (China); Dhe-Paganon, Sirano [Dana-Farber Cancer Institute, Department of Cancer Biology (United States); Arrowsmith, Cheryl H. [University of Toronto, Structural Genomics Consortium (Canada); Bezsonova, Irina, E-mail: bezsonova@uchc.edu [University of Connecticut Health, Department of Molecular Biology and Biophysics (United States)

    2016-11-15

    HLTF is a SWI2/SNF2-family ATP-dependent chromatin remodeling enzyme that acts in the error-free branch of DNA damage tolerance (DDT), a cellular mechanism that enables replication of damaged DNA while leaving damage repair for a later time. Human HLTF and a closely related protein SHPRH, as well as their yeast homologue Rad5, are multi-functional enzymes that share E3 ubiquitin-ligase activity required for activation of the error-free DDT. HLTF and Rad5 also function as ATP-dependent dsDNA translocases and possess replication fork reversal activities. Thus, they can convert Y-shaped replication forks into X-shaped Holliday junction structures that allow error-free replication over DNA lesions. The fork reversal activity of HLTF is dependent on 3′-ssDNA-end binding activity of its N-terminal HIRAN domain. Here we present the solution NMR structure of the human HLTF HIRAN domain, an OB-like fold module found in organisms from bacteria (as a stand-alone domain) to plants, fungi and metazoan (in combination with SWI2/SNF2 helicase-like domain). The obtained structure of free HLTF HIRAN is similar to recently reported structures of its DNA bound form, while the NMR analysis also reveals that the DNA binding site of the free domain exhibits conformational heterogeneity. Sequence comparison of N-terminal regions of HLTF, SHPRH and Rad5 aided by knowledge of the HLTF HIRAN structure suggests that the SHPRH N-terminus also includes an uncharacterized structured module, exhibiting weak sequence similarity with HIRAN regions of HLTF and Rad5, and potentially playing a similar functional role.

  12. Comparison of additive (absolute) risk projection models and multiplicative (relative) risk projection models in estimating radiation-induced lifetime cancer risk

    International Nuclear Information System (INIS)

    Kai, Michiaki; Kusama, Tomoko

    1990-01-01

    Lifetime cancer risk estimates depend on risk projection models. While the increasing lengths of follow-up observation periods of atomic bomb survivors in Hiroshima and Nagasaki bring about changes in cancer risk estimates, the validity of the two risk projection models, the additive risk projection model (AR) and multiplicative risk projection model (MR), comes into question. This paper compares the lifetime risk or loss of life-expectancy between the two projection models on the basis of BEIR-III report or recently published RERF report. With Japanese cancer statistics the estimates of MR were greater than those of AR, but a reversal of these results was seen when the cancer hazard function for India was used. When we investigated the validity of the two projection models using epidemiological human data and animal data, the results suggested that MR was superior to AR with respect to temporal change, but there was little evidence to support its validity. (author)

  13. Combustion and radiation modeling of laminar premixed flames using OpenFOAM: A numerical investigation of radiative heat transfer in the RADIADE project

    OpenAIRE

    Haider, Sajjad; Pang, Kar Mun; Ivarsson, Anders; Schramm, Jesper

    2013-01-01

    This paper presents the computational fluid dynamics modelling of a laminar premixed flame. A specific solver named ’rareLTSFoam’ is developed using OpenFOAM ® code. The solver is used to simulate experimental stoichiometric and rich laminar premixed flames. The modelling is carried out for thermal flow and combusting flow cases. The results show that without including radiation modelling, the predicted flame temperature is higher than the measured values. P1 radiation Model is used with sub-...

  14. Online fibre optic OSL in vivo dosimetry for quality assurance of external beam radiation therapy treatments: The ANR-TECSAN Codofer Project

    International Nuclear Information System (INIS)

    Magne, S.; Ferdinand, P.; De Carlan, L.; Bridier, A.; Isambert, A.; Hugon, R.; Guillon, J.

    2010-01-01

    The Codofer Project (2007-2009), led under the ANR-TECSAN Call, was coordinated by CEA LIST, in partnership with IGR and the Fimel company. The aim of the project was to design and test both metrologically and in clinical conditions OSL optical fiber sensors dedicated to in vivo dosimetry during external beam radiation therapy treatment with high-energy electrons. This study, combined with the results of clinical tests obtained within the European Project Maestro, has demonstrated the advantages of OSL/FO dosimetry for providing quality assurance of treatments. However, the French market for dosimetry has greatly changed as a result of the rules decreed by the French government in 2007. The OSL/FO product is now targeted for other treatment modalities lacking suitable dosimeters (ANR-INTRADOSE Project [2009-2011]). (authors)

  15. Radioactive air emissions notice of construction for Canister Storage Building (revised sealing configuration for spent nuclear fuel) - Project W-379

    International Nuclear Information System (INIS)

    Kamberg, L.D.

    1998-01-01

    The purpose of this Notice of Construction (NOC) is to provide a rewritten NOC for obtaining regulatory approval for changes to the previous Canister Storage Building (CSB) NOCs (WDOH, 1996 and EPA, 1996) as were approved by the Washington State Department of Health (WDOH, 1996a) and US Environmental Protection Agency (EPA, 1996a). These changes are because of a revised sealing configuration of the multi-canister overpacks (MCOS) that are used to store the SNF. A flow schematic of the SNF Project is provided in Figure 1-1. A separate notification of startup will be provided apart from this NOC

  16. Software Configuration Management Plan for the K West Basin Integrated Water Treatment System (IWTS) - Project A.9

    International Nuclear Information System (INIS)

    GREEN, J.W.

    2000-01-01

    This document provides a configuration control plan for the software associated with the operation and control of the Integrated Water Treatment System (IWTS). It establishes requirements for ensuring configuration item identification, configuration control, configuration status accounting, defect reporting and resolution of computer software. It is written to comply with HNF-SD-SNF-CM-001, Spent Nuclear Fuel Configuration Management Plan (Forehand 1998) and HNF-PRO-309 Computer Software Quality Assurance Requirements, and applicable sections of administrative procedure CM-6-037-00, SNF Project Process Automation Software and Equipment

  17. Routine oblique radiography of the pediatric lumbar spine: is it necessary. [Oblique radiography entails more than double the gonadal radiation dose of frontal-lateral projections

    Energy Technology Data Exchange (ETDEWEB)

    Roberts, F.F.; Kishore, P.R.S.; Cunningham, M.E.

    1978-08-01

    A series of 86 pediatric lumbar spine abnormalities was evaluated to determine the diagnostic benefit of radiography in oblique projection as compared to frontal-lateral projections alone. In only four patients was an abnormality apparent on the oblique view which had not already been demonstrated by the frontal-lateral series; each of these represented an isolated spondylolysis. Because the diagnostic yield was low at a patient cost of more than double the gonadal radiation dose, it is recommended that oblique views be eliminated in the routine radiography of the pediatric lumbar spine.

  18. MaRIE 1.0: The Matter-Radiation Interactions in Extremes Project, and the Challenge of Dynamic Mesoscale Imaging

    Energy Technology Data Exchange (ETDEWEB)

    Barnes, Cris William [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Barber, John L. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Kober, Edward Martin [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Lookman, Turab [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Sandberg, Richard L. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Shlachter, Jack S. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Sheffield, Richard L. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2015-02-23

    The Matter-Radiation Interactions in Extremes project will build the experimental facility for the time-dependent control of dynamic material performance. An x-ray free electron laser at up to 42-keV fundamental energy and with photon pulses down to sub-nanosecond spacing, MaRIE 1.0 is designed to meet the challenges of time-dependent mesoscale materials science. Those challenges will be outlined, the techniques of coherent diffractive imaging and dynamic polycrystalline diffraction described, and the resulting requirements defined for a coherent x-ray source. The talk concludes with the role of the MaRIE project and science in the future.

  19. Discussion on the environmental protection acceptance method and the critical issues of the completion of projects about radiation usage in the hospitals

    International Nuclear Information System (INIS)

    Wang Wei

    2014-01-01

    It is widely used in the world that the hospitals take advantages of radiation technology. Practically it is involved radioactive isotope, sealed source and the usage of ray device. Based on the environmental protection acceptance of the finished projects, this article is aimed at the actual characteristics of the medical practice and differentiating the major factors of environmental effects, choosing the monitoring criteria and method of environmental protection acceptance and exploring the critical issues in the course of acceptance. Finally this essay is intended to provide theory evidence and technical support in the acceptance of the above projects. (author)

  20. Advances in the project about Pin type silicon radiation detectors; Avances en el proyecto sobre detectores de radiacion de silicio tipo PIN

    Energy Technology Data Exchange (ETDEWEB)

    Ramirez F, J. [Instituto Nacional de Investigaciones Nucleares, Laboratorio de Detectores de Radiacion, A.P. 18-1027, 11801 Mexico D.F. (Mexico); Cerdeira, A.; Aceves, M.; Diaz, A.; Estrada, M.; Rosales, P.; Cabal, A.E.; Montano L, M.; Leyva, A

    1998-07-01

    The obtained advances in the collaboration project ININ-CINVESTAV about development of Pin type semiconductor radiation detectors here are presented. It has been characterized the response to different types of radiation made in CINVESTAV and INAOE. Measurements have been realized with different types of sensitive to charge preamplifiers determining the main characteristics which must be executed to be able to be employed with low capacitance detectors. As applications it has been possible to measure the irradiation time in a mammography machine and X-ray energy spectra have been obtained in the order of 14 KeV, with 4 KeV at ambient temperature. The future actions of project have been indicated and the possible applications of these detectors. (Author)

  1. Radiation synthesis of stimuli-responsive membranes, hydrogels and adsorbents for separation purposes. Final report of a coordinated research project 2000-2004

    International Nuclear Information System (INIS)

    2005-08-01

    This coordinated research project coordinated research work for the development of novel materials prepared by radiation processing techniques. Single and multi-pore polyamide membranes, fast thermo-responsive hydrogels, porous polymer monoliths, stimuli-responsive hydrogels based on natural and synthetic polymers, temperature responsive membranes, selective adsorbents, polymeric nanogels and novel non-ionic thermo-sensitive hydrogels were produced. The application areas explored for beneficially utilizing these novel materials included specialized drug delivery systems (DDS), selective adsorbents, nanopores for single molecule detection, membranes for separation and concentration of solutes, health care and remediation of environmental pollution. The report provides basic information on radiation processing and promotes experience exchange for further developments of radiation technology. Protocols and procedures of preparation of various stimuli responsive membranes and their actual and perspective applications are described in the report. Public awareness and technology acceptance are other factors to be considered for further dissemination. This publication summarizes the present status and the prospects of this technology

  2. Spent nuclear fuel project multi-year work plan WBS number 1.4.1

    International Nuclear Information System (INIS)

    Wells, J.L.

    1997-01-01

    The Spent Nuclear Fuel (SNF) Project Multi-Year Work Plan (MYWP) is a controlled living document that contains the current SNF Project Technical, Schedule and Cost Baselines. These baselines reflect the current Project execution strategies and are controlled via the change control process. Other changes to the MYWP document will be controlled using the document control process. These changes will be processed as they are approved to keep the MYWP a living document. The MYWP will be maintained continuously as the project baseline through the life of the project and not revised annually. The MYWP is the one document which summarizes and links these three baselines in one place. Supporting documentation for each baseline referred to herein may be impacted by changes to the MYWP, and must also be revised through change control to maintain consistency

  3. Radiation protection research projects. Program report 2015. Report on research program radiation protection of the Federal ministry for environment, nature conservation and reactor safety with technical and administrative steering by the Bundesamt fuer Strahlenschutz; Strahlenschutzforschung. Programmreport 2015. Bericht ueber das vom Bundesamt fuer Strahlenschutz fachlich begleitete und administrativ umgesetzte Forschungsprogramm Strahlenschutz des Bundesministeriums fuer Umwelt, Naturschutz, Bau und Reaktorsicherheit

    Energy Technology Data Exchange (ETDEWEB)

    Schmitt-Hannig, Annemarie; Loebke-Reinl, Angelika; Peter, Josef; Goedde, Ralph; Hachenberger, Claudia; Trugenberger-Schnabel, Angela (comps.)

    2016-08-15

    On behalf of the Federal Ministry for the Environment, Nature Conservation, Building and Nuclear Safety (BMUB) the Federal Office for Radiation Protection (BfS) awards research grants for projects in the field of radiation protection. The findings of these projects serve as decision aiding information in the development of radiation protection regulations as well as in the fulfilment of specific tasks in the field of radiation protection. The tasks of the Federal Office for Radiation Protection involve planning, technical and administrative preparation, awarding of contracts, general support as well as the technical evaluation of research and study projects. This report provides information on results, i. e. preliminary (in the form of status reports) and, where applicable, final results of radiation protection projects within the BMUB's Environmental Research Plan for the year 2015.

  4. Integrated data base report - 1996: US spent nuclear fuel and radioactive waste inventories, projections, and characteristics

    International Nuclear Information System (INIS)

    1997-12-01

    The Integrated Data Base Program has compiled historic data on inventories and characteristics of both commercial and U.S. Department of Energy (DOE) spent nuclear fuel (SNF) and commercial and U.S. government-owned radioactive wastes. Inventories of most of these materials are reported as of the end of fiscal year (FY) 1996, which is September 30, 1996. Commercial SNF and commercial uranium mill tailings inventories are reported on an end-of-calendar year (CY) basis. All SNF and radioactive waste data reported are based on the most reliable information available from government sources, the open literature, technical reports, and direct contacts. The information forecasted is consistent with the latest DOE/Energy Information Administration (EIA) projections of U.S. commercial nuclear power growth and the expected DOE-related and private industrial and institutional activities. The radioactive materials considered, on a chapter-by-chapter basis, are SNF, high-level waste, transuranic waste, low-level waste, uranium mill tailings, DOE Environmental Restoration Program contaminated environmental media, naturally occurring and accelerator-produced radioactive material, and mixed (hazardous and radioactive) low-level waste. For most of these categories, current and projected inventories are given through FY 2030, and the radioactivity and thermal power are calculated based on reported or estimated isotopic compositions

  5. Radiation damage evaluation on concrete within a facility for Selective Production of Exotic Species (SPES Project), Italy

    International Nuclear Information System (INIS)

    Pomaro, B.; Salomoni, V.A.; Gramegna, F.; Prete, G.; Majorana, C.E.

    2011-01-01

    Highlights: → We present the effect of radiation on concrete as shielding material. → The coupling between hydro-thermal-mechanical fields and radiation damage is shown. → Attention is focused on numerical modelling of concrete in 3D domains. → A new estimate of the radiation damage parameter is given. → A risk assessment of concrete-radiation interactions is developed. - Abstract: Concrete is commonly used as a biological shield against nuclear radiation. As long as, in the design of nuclear facilities, its load carrying capacity is required together with its shielding properties, changes in the mechanical properties due to nuclear radiation are of particular significance and may have to be taken into account in such circumstances. The study presented here allows for reaching first evidences on the behavior of concrete when exposed to nuclear radiation in order to evaluate the consequent effect on the mechanical field, by means of a proper definition of the radiation damage, strictly connected with the strength properties of the building material. Experimental evidences on the decay of the mechanical modulus of concrete have allowed for implementing the required damage law within a 3D F.E. research code which accounts for the coupling among moisture, heat transfer and the mechanical field in concrete treated as a fully coupled porous medium. The development of the damage front in a concrete shielding wall is analyzed under neutron radiation and results within the wall thickness are reported for long-term radiation spans and several concrete mixtures in order to discuss the resulting shielding properties.

  6. The use of roentgen diagnostics in chiropractor activities. Project based survey according to new regulations regarding radiation protection and use of radiation

    International Nuclear Information System (INIS)

    Raaum, Aud; Widmark, Anders

    2005-12-01

    An audit has been performed in 17 chiropractic enterprises according to new radiation protection legislation. Before the audits a survey of the use of diagnostic imaging in Norwegian chiropractic enterprises was carried out. This report summarizes the results of the survey and the findings at the audits. (Author)

  7. Safety assessment for a potential SNF repository and its implication to the proliferation resistance nuclear fuel cycle

    International Nuclear Information System (INIS)

    Hwang, Y.; Jeong, M.S.; Seo, C.S.

    2007-01-01

    KAERI is developing the pyro-process technology to minimize the burden on permanent disposal of spent nuclear fuel. In addition, KAERI has developed the Korean Reference System for potential spent nuclear fuel disposal since 1997. The deep geologic disposal system is composed of a multi-barrier system in a crystalline rock to dispose of 36,000 MT of spent nuclear fuel (SNF) from a CANDU and a PWR. Quite recently, introduction of advanced nuclear fuel cycles such as pyro-processing is a big issue to solve the everlasting disposal problem and to assure the sustainable supply of fuel for reactors. To compare the effect of direct disposal of SNF with that of the high level waste disposal for waste generated from the advanced nuclear fuel cycles, the total system performance assessment for two different schemes is developed; one for direct disposal of SNF and the other for the introduction of the pyro-processing and direct disposal CANDU spent nuclear fuel. The safety indicators to assess the environmental friendliness of the disposal option are annual individual doses, toxicities and risks. Even though many scientists use the toxicity to understand the environmental friendliness of the disposal, scientifically the annual individual doses or risks are meaningful indicators for it. The major mechanisms to determine the doses and risks for direct disposal are as follows: (1) Dissolution mechanisms of uranium dioxides which control the dissolution of most nuclides such as TRU's and most parts of fission products. (2) Instant release fraction of highly soluble nuclides such as I-129, C-135, Tc-99, and others. (3) Retardation and dilution effect of natural and engineered barriers. (4) Dilution effect in the biosphere. The dominant nuclide is I-129 which follows both congruent and instantaneous release modes. Since its long half life associated with the instantaneous release I-129 is dominant well beyond one million. The impact of the TRU's is negligible until the significant

  8. Spent nuclear fuels project characterization data quality objectives strategy

    International Nuclear Information System (INIS)

    Lawrence, L.A.; Thornton, T.A.; Redus, K.S.

    1994-12-01

    A strategy is presented for implementation of the Data Quality Objectives (DQO) process to the Spent Nuclear Fuels Project (SNFP) characterization activities. Westinghouse Hanford Company (WHC) and the Pacific Northwest Laboratory (PNL) are teaming in the characterization of the SNF on the Hanford Site and are committed to the DQO process outlined in this strategy. The SNFP characterization activities will collect and evaluate the required data to support project initiatives and decisions related to interim safe storage and the path forward for disposal. The DQO process is the basis for the activity specific SNF characterization requirements, termed the SNF Characterization DQO for that specific activity, which will be issued by the WHC or PNL organization responsible for the specific activity. The Characterization Plan prepared by PNL defines safety, remediation, and disposal issues. The ongoing Defense Nuclear Facility Safety Board (DNFSB) requirement and plans and the fuel storage and disposition options studies provide the need and direction for the activity specific DQO process. The hierarchy of characterization and DQO related documentation requirements is presented in this strategy. The management of the DQO process and the means of documenting the DQO process are described as well as the tailoring of the DQO process to the specific need of the SNFP characterization activities. This strategy will assure stakeholder and project management that the proper data was collected and evaluated to support programmatic decisions

  9. Canister Cleaning System Final Design Report - Project A.2.A

    International Nuclear Information System (INIS)

    FARWICK, C.C.

    2000-01-01

    Approximately 2,300 metric tons Spent Nuclear Fuel (SNF) are currently stored within two water filled pools, the 105 K East (KE) fuel storage basin and the 105 K West (KW) fuel storage basin, at the U.S. Department of Energy, Richland Operations Office (RL). The SNF Project is responsible for operation of the K Basins and for the materials within them. A subproject to the SNF Project is the Debris Removal Subproject, which is responsible for removal of empty canisters and lids from the basins. The Canister Cleaning System (CCS) is part of the Debris Removal Project. The CCS will be installed in the KW Basin and operated during the fuel removal activity. The KW Basin has approximately 3600 canisters that require removal from the basin. The CCS is being designed to ''clean'' empty fuel canisters and lids and package them for disposal to the Environmental Restoration Disposal Facility complex. The system will interface with the KW Basin and be located in the Dummy Elevator Pit

  10. The Philippine National Progress Report on IAEA Project RAS/09/062: Promoting and Maintaining Regulatory Infrastructure for the Control of Radiation Sources

    International Nuclear Information System (INIS)

    Borras, A.

    2016-01-01

    In line with the report of the Director General on “Measures to Strengthen International Cooperation in Nuclear, Radiation, Transport and Waste Safety” during the 2014 IAEA General Conference [1], this report aims to share the accomplishments and achievements of the above mentioned project and its impact to the effectiveness and efficiency of NRD-PNRI on delivering their regulatory functions in the country translating to the fulfilment of the PNRI’s mandate. Also, it aims to project the perceive challenges of a regulator with the emerging state of the art industrial and medical nuclear technologies in the country. This could possibly serve as model processes for other countries especially in the Asia and the Pacific Region or globally as a whole. A regional comparative report under the framework of the project could emanate from this report.

  11. Presentation of the project EPI-CT: A cohort study of children with substantial diagnostic medical exposure to ionizing radiation

    International Nuclear Information System (INIS)

    Bosch de Basea, M.; Cardis, E.; Vrijheid, M.

    2011-01-01

    Ionizing radiation for diagnostic purposes are an indispensable tool in modern medicine. The increasing use of computed tomography (CT) in children and adolescents is of concern both from the point of view of radio-protection and public health. children are more sensitive to the carcinogenic effects of ionizing radiation than adults. Children also have a higher life expectancy to show any detrimental effect. Furthermore, because of their smaller mass, CT scans in children receiving higher doses of radiation in specific organs in adults.