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Sample records for cleanup verification package

  1. Cleanup Verification Package for the 300-18 Waste Site

    International Nuclear Information System (INIS)

    This cleanup verification package documents completion of remedial action for the 300-18 waste site. This site was identified as containing radiologically contaminated soil, metal shavings, nuts, bolts, and concrete

  2. Cleanup Verification Package for the 118-F-2 Burial Ground

    International Nuclear Information System (INIS)

    This cleanup verification package documents completion of remedial action, sampling activities, and compliance with cleanup criteria for the 118-F-2 Burial Ground. This burial ground, formerly called Solid Waste Burial Ground No. 1, was the original solid waste disposal site for the 100-F Area. Eight trenches contained miscellaneous solid waste from the 105-F Reactor and one trench contained solid waste from the biology facilities

  3. Cleanup Verification Package for the 118-F-6 Burial Ground

    International Nuclear Information System (INIS)

    This cleanup verification package documents completion of remedial action for the 118-F-6 Burial Ground located in the 100-FR-2 Operable Unit of the 100-F Area on the Hanford Site. The trenches received waste from the 100-F Experimental Animal Farm, including animal manure, animal carcasses, laboratory waste, plastic, cardboard, metal, and concrete debris as well as a railroad tank car

  4. Cleanup Verification Package for the 618-2 Burial Ground

    International Nuclear Information System (INIS)

    This cleanup verification package documents completion of remedial action for the 618-2 Burial Ground, also referred to as Solid Waste Burial Ground No. 2; Burial Ground No. 2; 318-2; and Dry Waste Burial Site No. 2. This waste site was used primarily for the disposal of contaminated equipment, materials and laboratory waste from the 300 Area Facilities

  5. Cleanup Verification Package for the 600-259 Waste Site

    Energy Technology Data Exchange (ETDEWEB)

    J. M. Capron

    2006-02-09

    This cleanup verification package documents completion of remedial action for the 600-259 waste site. The site was the former site of the Special Waste Form Lysimeter, consisting of commercial reactor isotope waste forms in contact with soils within engineered caissons, and was used by Pacific Northwest National Laboratory to collect data regarding leaching behavior for target analytes. A Grout Waste Test Facility also operated at the site, designed to test leaching rates of grout-solidified low-level radioactive waste.

  6. Cleanup Verification Package for the 618-8 Burial Ground

    International Nuclear Information System (INIS)

    This cleanup verification package documents completion of remedial action for the 618-8 Burial Ground, also referred to as the Solid Waste Burial Ground No. 8, 318-8, and the Early Solid Waste Burial Ground. During its period of operation, the 618-8 site is speculated to have been used to bury uranium-contaminated waste derived from fuel manufacturing, and construction debris from the remodeling of the 313 Building

  7. Cleanup Verification Package for the 618-3 Burial Ground

    Energy Technology Data Exchange (ETDEWEB)

    M. J. Appel

    2006-09-12

    This cleanup verification package documents completion of remedial action for the 618-3 Solid Waste Burial Ground, also referred to as Burial Ground Number 3 and the Dry Waste Burial Ground Number 3. During its period of operation, the 618-3 site was used to dispose of uranium-contaminated construction debris from the 311 Building and construction/demolition debris from remodeling of the 313, 303-J and 303-K Buildings.

  8. Cleanup Verification Package for the 618-3 Burial Ground

    International Nuclear Information System (INIS)

    This cleanup verification package documents completion of remedial action for the 618-3 Solid Waste Burial Ground, also referred to as Burial Ground Number 3 and the Dry Waste Burial Ground Number 3. During its period of operation, the 618-3 site was used to dispose of uranium-contaminated construction debris from the 311 Building and construction/demolition debris from remodeling of the 313, 303-J and 303-K Buildings

  9. Cleanup Verification Package for the 118-F-1 Burial Ground

    International Nuclear Information System (INIS)

    This cleanup verification package documents completion of remedial action for the 118-F-1 Burial Ground on the Hanford Site. This burial ground is a combination of two locations formerly called Minor Construction Burial Ground No. 2 and Solid Waste Burial Ground No. 2. This waste site received radioactive equipment and other miscellaneous waste from 105-F Reactor operations, including dummy elements and irradiated process tubing; gun barrel tips, steel sleeves, and metal chips removed from the reactor; filter boxes containing reactor graphite chips; and miscellaneous construction solid waste

  10. Cleanup Verification Package for the 116-K-2 Effluent Trench

    Energy Technology Data Exchange (ETDEWEB)

    J. M. Capron

    2006-04-04

    This cleanup verification package documents completion of remedial action for the 116-K-2 effluent trench, also referred to as the 116-K-2 mile-long trench and the 116-K-2 site. During its period of operation, the 116-K-2 site was used to dispose of cooling water effluent from the 105-KE and 105-KW Reactors by percolation into the soil. This site also received mixed liquid wastes from the 105-KW and 105-KE fuel storage basins, reactor floor drains, and miscellaneous decontamination activities.

  11. Cleanup Verification Package for the 300-8 Waste Site

    International Nuclear Information System (INIS)

    This cleanup verification package documents completion of remedial action for the 300-8 waste site. This waste site was formerly used to stage scrap metal from the 300 Area in support of a program to recycle aluminum. This cleanup verification package documents completion of remedial action for the 300-8 waste site. The 300-8 site is located within the 300-FF-2 Operable Unit in the 300 Area of the Hanford Site in southeastern Washington State. The site was formerly used to stage scrap metal from the 300 Area in support of a program to recycle aluminum. Staging and loading activities at the site scattered scrap metal over an approximately 34,000-m2 (366,000-ft2) area, with residual metallic debris generally present within the top 0.4 m (1.5 ft) of soil. Site excavation and waste disposal are complete, and post-excavation geophysical surveys confirm the removal of residual metallic debris. The exposed surfaces have been sampled and analyzed to verify attainment of the remedial action goals. Results of the sampling, laboratory analyses, and data evaluations for the 300-8 site indicate that all remedial action objectives and goals for direct exposure, protection of groundwater, and protection of the Columbia River have been met for industrial land use (Table ES-1). Because residual soil concentrations indicated that cleanup levels for more stringent land uses may have been achieved for the 300-8 site, a supplemental evaluation was performed against unrestricted land-use cleanup objectives established in the Explanation of Significant Differences for the 300-FF-2 Operable Unit Record of Decision (EPA 2004). Results of the evaluation (Table ES-2) demonstrate that residual contaminant concentrations do not preclude any future uses (as bounded by the rural-residential scenario) and allow for unrestricted use of shallow zone soils (i.e., surface to 4.6 m (15 ft) deep). This site does not have a deep zone; therefore, no deep zone institutional controls are required. The site

  12. Cleanup Verification Package for the 118-F-5 PNL Sawdust Pit

    Energy Technology Data Exchange (ETDEWEB)

    L. D. Habel

    2008-05-20

    This cleanup verification package documents completion of remedial action, sampling activities, and compliance with cleanup criteria for the 118-F-5 Burial Ground, the PNL (Pacific Northwest Laboratory) Sawdust Pit. The 118-F-5 Burial Ground was an unlined trench that received radioactive sawdust from the floors of animal pens in the 100-F Experimental Animal Farm.

  13. Cleanup Verification Package for the 118-C-1, 105-C Solid Waste Burial Ground

    Energy Technology Data Exchange (ETDEWEB)

    M. J. Appel and J. M. Capron

    2007-07-25

    This cleanup verification package documents completion of remedial action for the 118-C-1, 105-C Solid Waste Burial Ground. This waste site was the primary burial ground for general wastes from the operation of the 105-C Reactor and received process tubes, aluminum fuel spacers, control rods, reactor hardware, spent nuclear fuel and soft wastes.

  14. Cleanup Verification Package for the 126-F-1, 184-F Powerhouse Ash Pit

    Energy Technology Data Exchange (ETDEWEB)

    S. W. Clark and H. M Sulloway

    2007-10-31

    This cleanup verification package documents completion of remedial action for the 126-F-1, 184-F Powerhouse Ash Pit. This waste site received coal ash from the 100-F Area coal-fired steam plant. Leakage of process effluent from the 116-F-14 , 107-F Retention Basins flowed south into the ash pit, contaminating the northern portion.

  15. Cleanup Verification Package for the 118-C-1, 105-C Solid Waste Burial Ground

    International Nuclear Information System (INIS)

    This cleanup verification package documents completion of remedial action for the 118-C-1, 105-C Solid Waste Burial Ground. This waste site was the primary burial ground for general wastes from the operation of the 105-C Reactor and received process tubes, aluminum fuel spacers, control rods, reactor hardware, spent nuclear fuel and soft wastes

  16. Cleanup Verification Package for the 126-F-1, 184-F Powerhouse Ash Pit

    International Nuclear Information System (INIS)

    This cleanup verification package documents completion of remedial action for the 126-F-1, 184-F Powerhouse Ash Pit. This waste site received coal ash from the 100-F Area coal-fired steam plant. Leakage of process effluent from the 116-F-14 , 107-F Retention Basins flowed south into the ash pit, contaminating the northern portion

  17. Cleanup Verification Package for the 100-F-20, Pacific Northwest Laboratory Parallel Pits

    International Nuclear Information System (INIS)

    This cleanup verification package documents completion of remedial action for the 100-F-20, Pacific Northwest Laboratory Parallel Pits waste site. This waste site consisted of two earthen trenches thought to have received both radioactive and nonradioactive material related to the 100-F Experimental Animal Farm

  18. Cleanup Verification Package for the 118-F-7, 100-F Miscellaneous Hardware Storage Vault

    International Nuclear Information System (INIS)

    This cleanup verification package documents completion of remedial action for the 118-F-7, 100-F Miscellaneous Hardware Storage Vault. The site consisted of an inactive solid waste storage vault used for temporary storage of slightly contaminated reactor parts that could be recovered and reused for the 100-F Area reactor operations

  19. Cleanup Verification Package for the 126-F-1, 184-F Powerhouse Ash Pit

    Energy Technology Data Exchange (ETDEWEB)

    S. W. Clark and H. M. Sulloway

    2007-09-26

    This cleanup verification package documents completion of remedial action for the 126-F-1, 184-F Powerhouse Ash Pit. This waste site received coal ash from the 100-F Area coal-fired steam plant. Leakage of process effluent from the 116-F-14 , 107-F Retention Basins flowed south into the ash pit, contaminating the northern portion.

  20. Cleanup Verification Package for the 118-B-6, 108-B Solid Waste Burial Ground

    Energy Technology Data Exchange (ETDEWEB)

    M. L. Proctor

    2006-06-13

    This cleanup verification package documents completion of remedial action for the 118-B-6, 108-B Solid Waste Burial Ground. The 118-B-6 site consisted of 2 concrete pipes buried vertically in the ground and capped by a concrete pad with steel lids. The site was used for the disposal of wastes from the "metal line" of the P-10 Tritium Separation Project.

  1. Cleanup Verification Package for the 118-B-1, 105-B Solid Waste Burial Ground

    International Nuclear Information System (INIS)

    This cleanup verification package documents completion of remedial action, sampling activities, and compliance criteria for the 118-B-1, 105-B Solid Waste Burial Ground. This waste site was the primary burial ground for general wastes from the operation of the 105-B Reactor and P-10 Tritium Separation Project and also received waste from the 105-N Reactor. The burial ground received reactor hardware, process piping and tubing, fuel spacers, glassware, electrical components, tritium process wastes, soft wastes and other miscellaneous debris

  2. Cleanup Verification Package for the 118-F-3, Minor Construction Burial Ground

    International Nuclear Information System (INIS)

    This cleanup verification package documents completion of remedial action for the 118-F-3, Minor Construction Burial Ground waste site. This site was an open field covered with cobbles, with no vegetation growing on the surface. The site received irradiated reactor parts that were removed during conversion of the 105-F Reactor from the Liquid 3X to the Ball 3X Project safety systems and received mostly vertical safety rod thimbles and step plugs

  3. Cleanup Verification Package for the 118-F-8:4 Fuel Storage Basin West Side Adjacent and Side Slope Soils

    International Nuclear Information System (INIS)

    This cleanup verification package documents completion of remedial action, sampling activities, and compliance with cleanup criteria for the 118-F-8:4 Fuel Storage Basin West Side Adjacent and Side Slope Soils. The rectangular-shaped concrete basin on the south side of the 105-F Reactor building served as an underwater collection, storage, and transfer facility for irradiated fuel elements discharged from the reactor

  4. Packaged low-level waste verification system

    Energy Technology Data Exchange (ETDEWEB)

    Tuite, K.; Winberg, M.R.; McIsaac, C.V. [Idaho National Engineering Lab., Idaho Falls, ID (United States)

    1995-12-31

    The Department of Energy through the National Low-Level Waste Management Program and WMG Inc. have entered into a joint development effort to design, build, and demonstrate the Packaged Low-Level Waste Verification System. Currently, states and low-level radioactive waste disposal site operators have no method to independently verify the radionuclide content of packaged low-level waste that arrives at disposal sites for disposition. At this time, the disposal site relies on the low-level waste generator shipping manifests and accompanying records to ensure that low-level waste received meets the site`s waste acceptance criteria. The subject invention provides the equipment, software, and methods to enable the independent verification of low-level waste shipping records to ensure that the site`s waste acceptance criteria are being met. The objective of the prototype system is to demonstrate a mobile system capable of independently verifying the content of packaged low-level waste.

  5. Inspection and verification of waste packages for near surface disposal

    International Nuclear Information System (INIS)

    Extensive experience has been gained with various disposal options for low and intermediate level waste at or near surface disposal facilities. Near surface disposal is based on proven and well demonstrated technologies. To ensure the safety of near surface disposal facilities when available technologies are applied, it is necessary to control and assure the quality of the repository system's performance, which includes waste packages, engineered features and natural barriers, as well as siting, design, construction, operation, closure and institutional controls. Recognizing the importance of repository performance, the IAEA is producing a set of technical publications on quality assurance and quality control (QA/QC) for waste disposal to provide Member States with technical guidance and current information. These publications cover issues on the application of QA/QC programmes to waste disposal, long term record management, and specific QA/QC aspects of waste packaging, repository design and R and D. Waste package QA/QC is especially important because the package is the primary barrier to radionuclide release from a disposal facility. Waste packaging also involves interface issues between the waste generator and the disposal facility operator. Waste should be packaged by generators to meet waste acceptance requirements set for a repository or disposal system. However, it is essential that the disposal facility operator ensure that waste packages conform with disposal facility acceptance requirements. Demonstration of conformance with disposal facility acceptance requirements can be achieved through the systematic inspection and verification of waste packages at both the waste generator's site and at the disposal facility, based on a waste package QA/QC programme established by the waste generator and approved by the disposal operator. However, strategies, approaches and the scope of inspection and verification will be somewhat different from country to country

  6. Cleanup Verification Package for the 118-H-6:2, 105-H Reactor Ancillary Support Areas, Below-Grade Structures, and Underlying Soils; the 118-H-6:3, 105-H Reactor Fuel Storage Basin and Underlying Soils; The 118-H-6:3 Fuel Storage Basin Deep Zone Side Slope Soils; the 100-H-9, 100-H-10, and 100-H-13 French Drains; the 100-H-11 and 100-H-12 Expansion Box French Drains; and the 100-H-14 and 100-H-31 Surface Contamination Zones

    Energy Technology Data Exchange (ETDEWEB)

    M. J. Appel

    2006-06-29

    This cleanup verification package documents completion of removal actions for the 105-H Reactor Ancillary Support Areas, Below-Grade Structures, and Underlying Soils (subsite 118-H-6:2); 105-H Reactor Fuel Storage Basin and Underlying Soils (118-H-6:3); and Fuel Storage Basin Deep Zone Side Slope Soils. This CVP also documents remedial actions for the following seven additional waste sties: French Drain C (100-H-9), French Drain D (100-H-10), Expansion Box French Drain E (100-H-11), Expansion Box French Drain F (100-H-12), French Drain G (100-H-13), Surface Contamination Zone H (100-H-14), and the Polychlorinated Biphenyl Surface Contamination Zone (100-H-31).

  7. Verification test calculations for the Source Term Code Package

    International Nuclear Information System (INIS)

    The purpose of this report is to demonstrate the reasonableness of the Source Term Code Package (STCP) results. Hand calculations have been performed spanning a wide variety of phenomena within the context of a single accident sequence, a loss of all ac power with late containment failure, in the Peach Bottom (BWR) plant, and compared with STCP results. The report identifies some of the limitations of the hand calculation effort. The processes involved in a core meltdown accident are complex and coupled. Hand calculations by their nature must deal with gross simplifications of these processes. Their greatest strength is as an indicator that a computer code contains an error, for example that it doesn't satisfy basic conservation laws, rather than in showing the analysis accurately represents reality. Hand calculations are an important element of verification but they do not satisfy the need for code validation. The code validation program for the STCP is a separate effort. In general the hand calculation results show that models used in the STCP codes (e.g., MARCH, TRAP-MELT, VANESA) obey basic conservation laws and produce reasonable results. The degree of agreement and significance of the comparisons differ among the models evaluated. 20 figs., 26 tabs

  8. Documentation and verification required for type A packaging use

    International Nuclear Information System (INIS)

    This document furnishes knowledge and methods for verifying compliance with the U.S. Department of Transportation (DOT) packaging requirements for shipping Type A quantities of radioactive material. The primary emphasis is on the requirements identified in 49 CFR 173.415(a), which states, ''Each offeror of a Specification 7A package must maintain on file for at least one year after the shipment, and shall provide to DOT on request, complete documentation of tests and an engineering evaluation of comparative data showing that the construction methods, packaging design, and materials of construction comply with that specification.'' This guidance document uses a checklist to show compliance

  9. Documentation and verification required for type A packaging use

    Energy Technology Data Exchange (ETDEWEB)

    O`Brien, J.H.

    1997-07-30

    This document furnishes knowledge and methods for verifying compliance with the U.S. Department of Transportation (DOT) packaging requirements for shipping Type A quantities of radioactive material. The primary emphasis is on the requirements identified in 49 CFR 173.415(a), which states, ``Each offeror of a Specification 7A package must maintain on file for at least one year after the shipment, and shall provide to DOT on request, complete documentation of tests and an engineering evaluation of comparative data showing that the construction methods, packaging design, and materials of construction comply with that specification.`` This guidance document uses a checklist to show compliance.

  10. Study of applicable methods on safety verification of disposal facilities and waste packages

    International Nuclear Information System (INIS)

    Three subjects about safety verification on the disposal of low level radioactive waste were investigated in FY. 2012. For radioactive waste disposal facilities, specs and construction techniques of covering with soil to prevent possible destruction caused by natural events (e.g. earthquake) were studied to consider verification methods for those specs. For waste packages subject to near surface pit disposal, settings of scaling factor and average radioactivity concentration (hereafter referred to as ''SF'') on container-filled and solidified waste packages generated from Kashiwazaki Kariwa Nuclear Power Station Unit 1-5, setting of cesium residual ratio of molten solidified waste generated from Tokai and Tokai No.2 Power Stations, etc. were studied. Those results were finalized in consideration of the opinion from advisory panel, and publicly opened as JNES-EV reports. In FY 2012, five JNES reports were published and these have been used as standards of safety verification on waste packages. The verification method of radioactive wastes subject to near-surface trench disposal and intermediate depth disposal were also studied. For radioactive wastes which will be returned from overseas, determination methods of radioactive concentration, heat rate and hydrogen generation rate of CSD-C were established. Determination methods of radioactive concentration and heat rate of CSD-B were also established. These results will be referred to verification manuals. (author)

  11. The Use of the Hanford Onsite Packaging and Transportation Safety Program to Meet Cleanup Milestones Under the Hanford Site Cleanup 2015 Vision and the American Recovery and Reinvestment Act of 2009 - 12403

    Energy Technology Data Exchange (ETDEWEB)

    Lavender, John C. [CH2M HILL Plateau Remediation Company, Richland, WA 99354 (United States); Edwards, W. Scott [Areva Federal Services, Richland, WA 99354 (United States); Macbeth, Paul J.; Self, Richard J. [U.S. Department of Energy Richland Operations Office, Richland, WA 99352 (United States); West, Lori D. [Materials and Energy Corporation, Richland, WA 99354 (United States)

    2012-07-01

    The Hanford Site presents unique challenges in meeting the U.S. Department of Energy Richland Operations Office (DOE-RL) 2015 Cleanup Vision. CH2M Hill Plateau Remediation Company (CHPRC), its subcontractors, and DOE-RL were challenged to retrieve, transport and remediate a wide range of waste materials. Through a collaborative effort by all Hanford Onsite Central Plateau Cleanup Team Members, disposition pathways for diverse and seemingly impossible to ship wastes were developed under a DOE Order 460.1C-compliant Hanford Onsite Transportation Safety Program. The team determined an effective method for transporting oversized compliant waste payloads to processing and disposition facilities. The use of the onsite TSD packaging authorizations proved to be vital to safely transporting these materials for processing and eventual final disposition. The American Recovery and Reinvestment Act of 2009 (ARRA) provided additional resources to expedite planning and execution of these important cleanup milestones. Through the innovative and creative use of the TSD, the Hanford Onsite Central Plateau Cleanup Team Members have developed and are executing an integrated project plan that enables the safe and compliant transport of a wide variety of difficult-to-transport waste items, accelerating previous cleanup schedules to meet cleanup milestones. (authors)

  12. The Use of the Hanford Onsite Packaging and Transportation Safety Program to Meet Cleanup Milestones Under the Hanford Site Cleanup 2015 Vision and the American Recovery and Reinvestment Act of 2009 - 12403

    International Nuclear Information System (INIS)

    The Hanford Site presents unique challenges in meeting the U.S. Department of Energy Richland Operations Office (DOE-RL) 2015 Cleanup Vision. CH2M Hill Plateau Remediation Company (CHPRC), its subcontractors, and DOE-RL were challenged to retrieve, transport and remediate a wide range of waste materials. Through a collaborative effort by all Hanford Onsite Central Plateau Cleanup Team Members, disposition pathways for diverse and seemingly impossible to ship wastes were developed under a DOE Order 460.1C-compliant Hanford Onsite Transportation Safety Program. The team determined an effective method for transporting oversized compliant waste payloads to processing and disposition facilities. The use of the onsite TSD packaging authorizations proved to be vital to safely transporting these materials for processing and eventual final disposition. The American Recovery and Reinvestment Act of 2009 (ARRA) provided additional resources to expedite planning and execution of these important cleanup milestones. Through the innovative and creative use of the TSD, the Hanford Onsite Central Plateau Cleanup Team Members have developed and are executing an integrated project plan that enables the safe and compliant transport of a wide variety of difficult-to-transport waste items, accelerating previous cleanup schedules to meet cleanup milestones. (authors)

  13. Verification of a BWR code package by gamma scan measurements

    International Nuclear Information System (INIS)

    High-burnup 8 x 8 fuel with a large central water rod (called step 2 fuel) has been recently introduced to the latest Japanese boiling water reactor (BWR) plants. Lanthanum-140 gamma intensity is almost directly related to nodal powers. By gamma scan measurement, the axial distribution of 140La in the exposed fuel was measured at the end of cycle (EOC) 1 and was compared with the calculation by a BWR code package TGBLA/LOGOS. The multienrichment fuel-type core (MEC) design was adopted for the initial cycle core of the plants. The MEC design contains three different enrichment types of fuels to simulate the equilibrium cycles, achieve much higher discharge exposure, and save fuel cycle cost, and the low-enrichment fuels are loaded in periphery and in control cells. Such MEC design could be a challenge to the BWR design methods because of the large spectrum mismatch among the fuel assemblies of the different enrichments. The aforementioned comparison has shown that the accuracy of the TGBLA/LOGOS code package is satisfactory

  14. VIPEX (Vital-area Identification Package EXpert) Software Verification and Validation

    International Nuclear Information System (INIS)

    The purposes of this report are (1) to perform a Verification and Validation (V and V) test for the VIPEX(Vital-area Identification Package EXpert) software and (2) to improve a software quality through the V and V test. The VIPEX was developed in Korea Atomic Energy Research Institute (KAERI) for the Vital Area Identification (VAI) of nuclear power plants. The version of the VIPEX which was distributed is 3.2.0.0. The VIPEX was revised based on the first V and V test and the second V and V test was performed. We have performed the following tasks for the V and V test on Windows XP and VISTA operating systems: Ο Testing basic functions including fault tree editing Ο Testing all kind of functions Ο Research for update from Visual BASIC 6.0 to Visual BASIC 2008

  15. Engineering design tools for wind diesel systems. Volume 2 - JODYMOD dynamic wind diesel simulation software package: Model verification

    Energy Technology Data Exchange (ETDEWEB)

    Lundsager, P.; Bindner, H. [Risoe National Lab., Roskilde (Denmark); Infield, D. [Rutherford Appleton Lab., Chilton (United Kingdom)

    1995-09-11

    A design tools software package for wind diesel systems has been developed with support from the CEC JOULE programme. The package has been developed cooperatively by several EEC and EFTA countries. The complete package includes modelling of both dynamic and logistic aspects of system operation, and runs on a PC. This report describes the model verification of the dynamic model JODYMOD (JOule DYnamic MODular MODel), developed by the project. JODYMOD is based on a concept similar to the finite element technique in structural mechanics, where the equations of a model are built by the program according to the user`s system specification. The model is modular in the sense that it gives the user the opportunity to build a system model by combining a set of available component models. Separate reports contain the User`s Guide and a validation against measured results from two different wind diesel systems. 16 refs., 29 figs., 4 tabs.

  16. Guidelines for the verification and validation of expert system software and conventional software: Volume 5, Rationale and description of verification and validation guideline packages and procedures. Final report

    International Nuclear Information System (INIS)

    This report is the fifth volume in a series of reports describing the results of the Expert System Verification and Validation (V ampersand V) project which is jointly funded by US NRC and EPRI toward formulating guidelines for V ampersand V of expert systems for use in nuclear power applications. This report provides the rationale for and description of those guidelines. The actual guidelines themselves (and the accompanying 11 step by step Procedures) are presented in Volume 7, User's Manual. Three factors determine what V ampersand V is needed: (1) the stage, of the development life cycle (requirements, design, or implementation), (2) whether the overall system or a specialized component needs be tested (knowledge base component, inference engine or other highly reusable element, or a component involving conventional software), and (3) the stringency of V ampersand V that is needed (as judged from an assessment of the system's complexity and the requirement for its integrity to form three Classes). A V ampersand V guideline package is provided for each of the combinations of these three variables. The package specifies the V ampersand V methods recommended and the order in which they should be administered, the assurances each method provides, the qualifications needed by the V ampersand V team to employ each Particular method, the degree to which the methods should be applied, the performance measures that should be taken, and the decision criteria for accepting, conditionally accepting, or rejecting an evaluated system. In addition to the guideline packages, highly detailed step-by-step procedures are provided for 11 of the more important methods, to ensure that they Can be implemented correctly. The guidelines can apply to conventional procedural software systems as well as all kinds of AI systems

  17. Code Package to Analyze Parameters of the WWER Fuel Rod. TOPRA-2 Code - Verification Data

    International Nuclear Information System (INIS)

    Presented are the data for computer codes to analyze WWER fuel rods, used in the WWER department of RRC 'Kurchatov Institute'. Presented is the description of TOPRA-2 code intended for the engineering analysis of thermophysical and strength parameters of the WWER fuel rod - temperature distributions along the fuel radius, gas pressures under the cladding, stresses in the cladding, etc. for the reactor operation in normal conditions. Presented are some results of the code verification against test problems and the data obtained in the experimental programs. Presented are comparison results of the calculations with TOPRA-2 and TRANSURANUS (V1M1J06) codes. Results obtained in the course of verification demonstrate possibility of application of the methodology and TOPRA-2 code for the engineering analysis of the WWER fuel rods

  18. Evaluation of Hitachi CAD to CD-SEM metrology package for OPC model tuning and product devices OPC verification

    Science.gov (United States)

    Cantu, Pietro; Capetti, Gianfranco; Catarisano, Chiara; D'Angelo, Fabrizio; Evangelista, Elena; Severgnini, Ermes; Trovati, Silvia; Vasconi, Mauro; Sutani, Takumichi; Wahl, Stephan; Steffen, Robert

    2005-05-01

    Optical proximity corrections are widely used in semiconductor industry to compensate non-linear effects occurring when printing features smaller than exposure wavelength. Most advanced OPC software packages simulate optical behavior starting from a physical description of illumination and projection optics, while the characterization of resist development and etch loading effects is still performed empirically, with different approaches that, generally, require the collection of a huge amount of experimental data. Due to the wide variety of target patterns, which makes conventional CD-SEM recipe creation impossible, critical dimension (CD) measurements are usually performed manually, requiring long time and, despite the attention paid while measuring, with poor guarantee of repeatability. The introduction of 193nm resists, much more sensitive to SEM e-beam exposure if compared to 248nm materials, required increased attention to be paid on both focusing and measuring phases in order to obtain reliable results. As well as OPC model tuning, the verification of correction effectiveness on product devices is performed almost in the same way leading to the same kind of issues. In order to overcome most of these problems ST is evaluating a new CD metrology package from Hitachi High Technologies; this tool allows fully automatic CD measurements starting from GDS II coordinate input. The exact recognition of measurement locations is obtained through an algorithm, based on the superposition of the drawn GDS II layout to the SEM wafer images, which allows achieving high positioning accuracy. The introduction of the tool significantly reduces measuring time down to the range of normal automated CD measurement times, while guarantying improved repeatability and optimized conditions even with 193nm resists due to the possibility of defining different structures for addressing and focusing before the measurement. This new system opens new perspectives in OPC modeling giving the

  19. Remaining Sites Verification Package for the 1607-F5 Sanitary Sewer System (124-F-5), Waste Site Reclassification Form 2006-043

    Energy Technology Data Exchange (ETDEWEB)

    L. M. Dittmer

    2006-09-14

    The 1607-F5 waste site is a former septic tank, tile field, and associated pipeline located within the 100-FR-1 Operable Unit that received sewage from the former 181-F Pumphouse. Lead, gamma-chlordane, and heptachlor epoxide were identified within or around the septic system at concentrations exceeding the direct exposure cleanup criteria. Multiple metal and pesticide constituents were also identified as exceeding the groundwater and river protection cleanup criteria. The results of verification sampling demonstrated that residual contaminant concentrations do not preclude any future uses and allow for unrestricted use of shallow zone soils. The results also showed that residual contaminant concentrations are protective of groundwater and the Columbia River.

  20. Remaining Sites Verification Package for the 1607-F5 Sanitary Sewer System (124-F-5). Attachment to Waste Site Reclassification Form 2006-043

    International Nuclear Information System (INIS)

    The 1607-F5 waste site is a former septic tank, tile field, and associated pipeline located within the 100-FR-1 Operable Unit that received sewage from the former 181-F Pumphouse. Lead, gamma-chlordane, and heptachlor epoxide were identified within or around the septic system at concentrations exceeding the direct exposure cleanup criteria. Multiple metal and pesticide constituents were also identified as exceeding the groundwater and river protection cleanup criteria. The results of verification sampling demonstrated that residual contaminant concentrations do not preclude any future uses and allow for unrestricted use of shallow zone soils. The results also showed that residual contaminant concentrations are protective of groundwater and the Columbia River

  1. Remaining Sites Verification Package for the 141-C Large Animal Barn and Biology Laboratory (Hog Barn). Attachment to Waste Site Reclassification Form 2006-027

    International Nuclear Information System (INIS)

    The 141-C waste site is a former large animal barn and biology laboratory within the 100-F Area experimental animal farm. Strontium-90, arsenic, and multiple polycyclic aromatic hydrocarbons were detected within residual demolition debris at concentrations exceeding cleanup criteria. The site has been remediated by removing approximately 900 bank cubic meters of soil and debris within the former building footprint to the Environmental Restoration Disposal Facility. The results of verification sampling demonstrated that residual contaminant concentrations do not preclude any future uses and allow for unrestricted use of shallow zone soils. The results also showed that residual contaminant concentrations are protective of groundwater and the Columbia River

  2. Status of Verification and Validation of Physics Codes in COSINE Code Package

    International Nuclear Information System (INIS)

    COre and System INtegrated Engine for design and analysis (COSINE), an integrated nuclear engineering code package, is being developed by State Nuclear Power Software Development Center (SNPSDC) in China since 2011. A brief introduction of V and V strategy for the LATC/CORE reactor physics codes in COSINE code package was presented. And some results are shown as above. The preliminary results of V and V shows that the codes could give reasonable results, but still need to be continuously improved. In the next few years, the SNPSDC will build a test data base, including data from the critical experiments and operation plants, in order to continuously carry out the V and V of physics codes in COSINE

  3. Review of waste package verification tests. Semiannual report, April 1984-September 1984. Volume 5

    International Nuclear Information System (INIS)

    This ongoing study is part of a task to specify tests that may be used to verify that engineered waste package/repository systems comply with NRC radionuclide containment and controlled release performance objectives. Work covered in this report includes crushed tuff packing material for use in a high level waste tuff repository. A review of available tests to quantify packing performance is given together with recommendations for future testing work. 27 refs., 6 figs., 3 tabs

  4. Review of waste package verification tests. Semiannual report, April 1985-September 1985

    International Nuclear Information System (INIS)

    Several studies were completed this period to evaluate experimental and analytical methodologies being used in the DOE waste package program. The first involves a determination of the relevance of the test conditions being used by DOE to characterize waste package component behavior in a salt repository system. Another study focuses on the testing conditions and procedures used to measure radionuclide solubility and colloid formation in repository groundwaters. An attempt was also made to evaluate the adequacy of selected waste package performance codes. However, the latter work was limited by an inability to obtain several codes from DOE. Nevertheless, it was possible to comment briefly on the structures and intents of the codes based on publications in the open literature. The final study involved an experimental program to determine the likelihood of stress-corrosion cracking of austenitic stainless steels and Incoloy 825 in simulated tuff repository environments. Tests for six-month exposure periods in water and air-steam conditions are described. 52 figs., 48 tabs

  5. Review of waste package verification tests. Semiannual report, April 1985-September 1985

    Energy Technology Data Exchange (ETDEWEB)

    Soo, P. (ed.)

    1986-01-01

    Several studies were completed this period to evaluate experimental and analytical methodologies being used in the DOE waste package program. The first involves a determination of the relevance of the test conditions being used by DOE to characterize waste package component behavior in a salt repository system. Another study focuses on the testing conditions and procedures used to measure radionuclide solubility and colloid formation in repository groundwaters. An attempt was also made to evaluate the adequacy of selected waste package performance codes. However, the latter work was limited by an inability to obtain several codes from DOE. Nevertheless, it was possible to comment briefly on the structures and intents of the codes based on publications in the open literature. The final study involved an experimental program to determine the likelihood of stress-corrosion cracking of austenitic stainless steels and Incoloy 825 in simulated tuff repository environments. Tests for six-month exposure periods in water and air-steam conditions are described. 52 figs., 48 tabs.

  6. Verification of SAPFIR95andRC code package against operational data of WWER units

    International Nuclear Information System (INIS)

    The previous report on the same subject represents a brief description of procedure laid down in the code package SAPFIR 95 and RC and gives calculation results of fuel cycles by operational data of WWER-440 power Units (Kola NPP, Unit No.1 and Dukovany NPP, Unit No.2). The given paper additionally represents simulation results of fuel cycles as compared with operational data of Dukovany NPP, Unit No.3 and power Units with WWER-1000 reactors (Volgodon NPP, Unit No.1, Kalinin NPP, Unit No.3) (Authors)

  7. Review of waste package verification tests. Semiannual report, October 1984-March 1985

    Energy Technology Data Exchange (ETDEWEB)

    Soo, P. (ed.)

    1985-07-01

    The potential of WAPPA, a second-generation waste package system code, to meet the needs of the regulatory community is analyzed. The analysis includes an indepth review of WAPPA`s individual process models and a review of WAPPA`s operation. It is concluded that the code is of limited use to the NRC in the present form. Recommendations for future improvement, usage, and implementation of the code are given. This report also describes the results of a testing program undertaken to determine the chemical environment that will be present near a high-level waste package emplaced in a basalt repository. For this purpose, low carbon 1020 steel (a current BWIP reference container material), synthetic basaltic groundwater and a mixture of bentonite and basalt were exposed, in an autoclave, to expected conditions some period after repository sealing (150{sup 0}C, {approx_equal}10.4 MPa). Parameters measured include changes in gas pressure with time and gas composition, variation in dissolved oxygen (DO), pH and certain ionic concentrations of water in the packing material across an imposed thermal gradient, mineralogic alteration of the basalt/bentonite mixture, and carbon steel corrosion behavior. A second testing program was also initiated to check the likelihood of stress corrosion cracking of austenitic stainless steels and Incoloy 825 which are being considered for use as waste container materials in the tuff repository program. 82 refs., 70 figs., 27 tabs.

  8. Review of waste package verification tests. Semiannual report, October 1984-March 1985

    International Nuclear Information System (INIS)

    The potential of WAPPA, a second-generation waste package system code, to meet the needs of the regulatory community is analyzed. The analysis includes an indepth review of WAPPA's individual process models and a review of WAPPA's operation. It is concluded that the code is of limited use to the NRC in the present form. Recommendations for future improvement, usage, and implementation of the code are given. This report also describes the results of a testing program undertaken to determine the chemical environment that will be present near a high-level waste package emplaced in a basalt repository. For this purpose, low carbon 1020 steel (a current BWIP reference container material), synthetic basaltic groundwater and a mixture of bentonite and basalt were exposed, in an autoclave, to expected conditions some period after repository sealing (1500C, approx. =10.4 MPa). Parameters measured include changes in gas pressure with time and gas composition, variation in dissolved oxygen (DO), pH and certain ionic concentrations of water in the packing material across an imposed thermal gradient, mineralogic alteration of the basalt/bentonite mixture, and carbon steel corrosion behavior. A second testing program was also initiated to check the likelihood of stress corrosion cracking of austenitic stainless steels and Incoloy 825 which are being considered for use as waste container materials in the tuff repository program. 82 refs., 70 figs., 27 tabs

  9. Verification and validation of the SAPHIRE Version 4.0 PRA software package

    International Nuclear Information System (INIS)

    A verification and validation (V ampersand V) process has been performed for the System Analysis Programs for Hands-on Integrated Reliability Evaluation (SAPHIRE). SAPHIRE is a set of four computer programs that the Nuclear Regulatory Commission (NRC) developed to perform probabilistic risk assessments (PRAs). These programs allow an analyst to create, quantify, and evaluate the risk associated with a facility or process being analyzed. The programs included in this set are Integrated Reliability and Risk Analysis System (IRRAS), System Analysis and Risk Assessment (SARA), Models and Results Database (MAR-D), and Fault Tree/Event Tree/Piping and Instrumentation Diagram (FEP) graphical editor. The V ampersand V steps included a V ampersand V plan to describe the process and criteria by which the V ampersand V would be performed; a software requirements documentation review to determine the correctness, completeness, and traceability of the requirements; a user survey to determine the usefulness of the user documentation, identification and testing of vital and non-vital features, and documentation of the test results

  10. Remaining Sites Verification Package for the 100-D-2 Lead Sheeting Waste Site, Waste Site Reclassification Form 2007-030

    Energy Technology Data Exchange (ETDEWEB)

    L. M. Dittmer

    2008-03-19

    The 100-D-2 Lead Sheeting waste site was located approximately 50 m southwest of the 185-D Building and approximately 16 m north of the east/west oriented road. The site consisted of a lead sheet covering a concrete pad. In accordance with this evaluation, the verification sampling results support a reclassification of this site to Interim Closed Out. The results of verification sampling show that residual contaminant concentrations do not preclude any future uses and allow for unrestricted use of shallow zone soils. The results also demonstrate that residual contaminant concentrations are protective of groundwater and the Columbia River.

  11. Remaining Sites Verification Package for the 1607-F3 Sanitary Sewer System, Waste Site Reclassification Form 2006-047

    Energy Technology Data Exchange (ETDEWEB)

    L. M. Dittmer

    2007-04-26

    The 1607-F3 waste site is the former location of the sanitary sewer system that supported the 182-F Pump Station, the 183-F Water Treatment Plant, and the 151-F Substation. The sanitary sewer system included a septic tank, drain field, and associated pipeline, all in use between 1944 and 1965. In accordance with this evaluation, the verification sampling results support a reclassification of this site to Interim Closed Out. The results of verification sampling demonstrated that residual contaminant concentrations do not preclude any future uses and allow for unrestricted use of shallow zone soils. The results also showed that residual contaminant concentrations are protective of groundwater and the Columbia River.

  12. Remaining Sites Verification Package for the 120-F-1 Glass Dump Waste Site, Waste Site Reclassification Form 2008-028

    Energy Technology Data Exchange (ETDEWEB)

    J. M. Capron

    2008-06-27

    The 120-F-1 waste site consisted of two dumping areas located 660 m southeast of the 105-F Reactor containing laboratory equipment and bottles, demolition debris, light bulbs and tubes, small batteries, small drums, and pesticide contaminated soil. It is probable that 108-F was the source of the debris but the material may have come from other locations within the 100-F Area. In accordance with this evaluation, the verification sampling results support a reclassification of this site to Interim Closed Out. The results of verification sampling show that residual contaminant concentrations do not preclude any future uses and allow for unrestricted use of shallow zone soils. The results also demonstrate that residual contaminant concentrations are protective of groundwater and the Columbia River.

  13. Remaining Sites Verification Package for the 1607-F4 Sanitary Sewer System, Waste Site Reclassification Form 2004-131

    Energy Technology Data Exchange (ETDEWEB)

    L. M. Dittmer

    2007-12-03

    The 1607-F4 waste site is the former location of the sanitary sewer system that serviced the former 115-F Gas Recirculation Building. The system included a septic tank, drain field, and associated pipeline that were in use from 1944 to 1965. The 1607-F4 waste site received unknown amounts of sanitary sewage from the 115-F Gas Recirculation Building and may have potentially contained hazardous and radioactive contamination. In accordance with this evaluation, the verification sampling results support a reclassification of this site to Interim Closed Out. The results of verification sampling demonstrated that residual contaminant concentrations do not preclude any future uses and allow for unrestricted use of shallow zone soils. The results also showed that residual contaminant concentrations are protective of groundwater and the Columbia River.

  14. Remaining Sites Verification Package for the 1607-D4 Septic System, Waste Site Reclassification Form 2005-036

    Energy Technology Data Exchange (ETDEWEB)

    R. A. Carlson

    2006-02-23

    The 1607-D4 Septic System was a septic tank and tile field that received sanitary sewage from the 115-D/DR Gas Recirculation Facility. This septic system operated from 1944 to 1968. Decommissioning took place in 1985 and 1986 when all above-grade features were demolished and the tank backfilled. The results of verification sampling demonstrated that residual contaminant concentrations do not preclude any future uses and allow for unrestricted use of shallow zone soils. The results also showed that residual contaminant concentrations are protective of groundwater and the Columbia River.

  15. Remaining Sites Verification Package for the 128-B-3 Burn Pit Site, Waste Site Reclassification Form 2006-058

    Energy Technology Data Exchange (ETDEWEB)

    L. M. Dittmer

    2006-11-17

    The 128-B-3 waste site is a former burn and disposal site for the 100-B/C Area, located adjacent to the Columbia River. The 128-B-3 waste site has been remediated to meet the remedial action objectives specified in the Remaining Sites ROD. The results of verification sampling demonstrated that residual contaminant concentrations do not preclude any future uses and allow for unrestricted use of shallow zone soils. The results of sampling at upland areas of the site also showed that residual contaminant concentrations are protective of groundwater and the Columbia River.

  16. Guidelines for the verification and validation of expert system software and conventional software: Rationale and description of V ampersand V guideline packages and procedures. Volume 5

    International Nuclear Information System (INIS)

    This report is the fifth volume in a series of reports describing the results of the Expert System Verification C, and Validation (V ampersand V) project which is jointly funded by the U.S. Nuclear Regulatory Commission and the Electric Power Research Institute toward the objective of formulating Guidelines for the V ampersand V of expert systems for use in nuclear power applications. This report provides the rationale for and description of those guidelines. The actual guidelines themselves are presented in Volume 7, open-quotes User's Manual.close quotes Three factors determine what V ampersand V is needed: (1) the stage of the development life cycle (requirements, design, or implementation); (2) whether the overall system or a specialized component needs to be tested (knowledge base component, inference engine or other highly reusable element, or a component involving conventional software); and (3) the stringency of V ampersand V that is needed (as judged from an assessment of the system's complexity and the requirement for its integrity to form three Classes). A V ampersand V Guideline package is provided for each of the combinations of these three variables. The package specifies the V ampersand V methods recommended and the order in which they should be administered, the assurances each method provides, the qualifications needed by the V ampersand V team to employ each particular method, the degree to which the methods should be applied, the performance measures that should be taken, and the decision criteria for accepting, conditionally accepting, or rejecting an evaluated system. In addition to the Guideline packages, highly detailed step-by-step procedures are provided for 11 of the more important methods, to ensure that they can be implemented correctly. The Guidelines can apply to conventional procedural software systems as well as all kinds of Al systems

  17. Remaining Sites Verification Package for the 100-B-14:1 Process Sewer, Waste Site Reclassification Form 2004-005

    Energy Technology Data Exchange (ETDEWEB)

    L. M. Dittmer

    2007-02-22

    The 100-B-14:1 subsite encompasses the former process sewer main associated with the 105-B Reactor Building, 108-B Chemical Pumphouse and Tritium Separation Facility, 184-B Boiler House and the 100-B water treatment facilities, as well as the feeder lines associated with the 108-B facility, formerly discharging to the 116-B-7 Outfall Structure. The subsite has been remediated to achieve the remedial action objectives specified in the Remaining Sites ROD. The results of verification sampling demonstrated that residual contaminant concentrations do not preclude any future uses and allow for unrestricted use of shallow zone soils. The results also showed that residual contaminant concentrations are protective of groundwater and the Columbia River.

  18. Remaining Sites Verification Package for the 126-F-2, 183-F Clearwells, Waste Site Reclassification Form 2006-017

    International Nuclear Information System (INIS)

    The 126-F-2 site is the clearwell facility formerly used as part of the reactor cooling water treatment at the 183-F facility. During demolition operations in the 1970s, potentially contaminated debris was disposed in the eastern clearwell structure. The site has been remediated by removing all debris in the clearwell structure to the Environmental Restoration Disposal Facility. The results of radiological surveys and visual inspection of the remediated clearwell structure show neither residual contamination nor the potential for contaminant migration beyond the clearwell boundaries. The results of verification sampling at the remediation waste staging area demonstrated that residual contaminant concentrations do not preclude any future uses and allow for unrestricted use of shallow zone soils. The results also showed that residual contaminant concentrations are protective of groundwater and the Columbia River

  19. Remaining Sites Verification Package for the 126-F-2, 183-F Clearwells, Waste Site Reclassification Form 2006-017

    Energy Technology Data Exchange (ETDEWEB)

    R. A. Carlson

    2006-05-04

    The 126-F-2 site is the clearwell facility formerly used as part of the reactor cooling water treatment at the 183-F facility. During demolition operations in the 1970s, potentially contaminated debris was disposed in the eastern clearwell structure. The site has been remediated by removing all debris in the clearwell structure to the Environmental Restoration Disposal Facility. The results of radiological surveys and visual inspection of the remediated clearwell structure show neither residual contamination nor the potential for contaminant migration beyond the clearwell boundaries. The results of verification sampling at the remediation waste staging area demonstrated that residual contaminant concentrations do not preclude any future uses and allow for unrestricted use of shallow zone soils. The results also showed that residual contaminant concentrations are protective of groundwater and the Columbia River.

  20. HANFORD SITE CENTRAL PLATEAU CLEANUP COMPLETION STRATEGY

    Energy Technology Data Exchange (ETDEWEB)

    BERGMAN TB

    2011-01-14

    Cleanup of the Hanford Site is a complex and challenging undertaking. The U.S. Department of Energy (DOE) has developed a comprehensive vision for completing Hanford's cleanup mission including transition to post-cleanup activities. This vision includes 3 principle components of cleanup: the {approx}200 square miles ofland adjacent to the Columbia River, known as the River Corridor; the 75 square miles of land in the center of the Hanford Site, where the majority of the reprocessing and waste management activities have occurred, known as the Central Plateau; and the stored reprocessing wastes in the Central Plateau, the Tank Wastes. Cleanup of the River Corridor is well underway and is progressing towards completion of most cleanup actions by 2015. Tank waste cleanup is progressing on a longer schedule due to the complexity of the mission, with construction of the largest nuclear construction project in the United States, the Waste Treatment Plant, over 50% complete. With the progress on the River Corridor and Tank Waste, it is time to place increased emphasis on moving forward with cleanup of the Central Plateau. Cleanup of the Hanford Site has been proceeding under a framework defmed in the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement). In early 2009, the DOE, the State of Washington Department of Ecology, and the U.S. Environmental Protection Agency signed an Agreement in Principle in which the parties recognized the need to develop a more comprehensive strategy for cleanup of the Central Plateau. DOE agreed to develop a Central Plateau Cleanup Completion Strategy as a starting point for discussions. This DOE Strategy was the basis for negotiations between the Parties, discussions with the State of Oregon, the Hanford Advisory Board, and other Stakeholder groups (including open public meetings), and consultation with the Tribal Nations. The change packages to incorporate the Central Plateau Cleanup Completion Strategy were

  1. Enabling cleanup technology transfer

    International Nuclear Information System (INIS)

    Technology transfer in the environmental restoration, or cleanup, area has been challenging. While there is little doubt that innovative technologies are needed to reduce the times, risks, and costs associated with the cleanup of federal sites, particularly those of the Departments of Energy (DOE) and Defense, the use of such technologies in actual cleanups has been relatively limited. There are, of course, many reasons why technologies do not reach the implementation phase or do not get transferred from developing entities to the user community. For example, many past cleanup contracts provided few incentives for performance that would compel a contractor to seek improvement via technology applications. While performance-based contracts are becoming more common, they alone will not drive increased technology applications. This paper focuses on some applications of cleanup methodologies and technologies that have been successful and are illustrative of a more general principle. The principle is at once obvious and not widely practiced. It is that, with few exceptions, innovative cleanup technologies are rarely implemented successfully alone but rather are implemented in the context of enabling processes and methodologies. And, since cleanup is conducted in a regulatory environment, the stage is better set for technology transfer when the context includes substantive interactions with the relevant stakeholders. Examples of this principle are drawn from Argonne National Laboratory's experiences in Adaptive Sampling and Analysis Programs (ASAPs), Precise Excavation, and the DOE Technology Connection (TechCon) Program. The lessons learned may be applicable to the continuing challenges posed by the cleanup and long-term stewardship of radioactive contaminants and unexploded ordnance (UXO) at federal sites

  2. Cleanup of contaminated areas

    International Nuclear Information System (INIS)

    The paper deals with the problem of contaminated areas cleanup, in order to eliminate every possible damage for man safety and environment and to site recovery for some utilization, The first step of cleanup operation is site characterization, that is followed by a pianificazion activity for a better definition of staff qualification, technology to be used, protection and prevention instruments for the risks due to contaminants handling. The second section describes the different remedial technologies for contaminated sites. Remedial technologies may be divided into on-site/off-site and in-situ treatments, according to whether materials (waste, soil, water) are moved to another location or not, respectively. Finally, it is outlined that contaminated areas cleanup is a typical multidisciplinary activity because very different competences are required. (author)

  3. Environmental compliance and cleanup

    International Nuclear Information System (INIS)

    This section of the 1994 Hanford Site Environmental Report summarizes the roles of the principal agencies, organizations, and public in environmental compliance and cleanup of the Hanford Site. Regulatory oversight, the Federal Facility Agreement and Consent Order, the role of Indian tribes, public participation, and CERCLA Natural Resource Damage Assessment Trustee Activities are all discussed

  4. Environmental compliance and cleanup

    Energy Technology Data Exchange (ETDEWEB)

    Black, D.G.

    1995-06-01

    This section of the 1994 Hanford Site Environmental Report summarizes the roles of the principal agencies, organizations, and public in environmental compliance and cleanup of the Hanford Site. Regulatory oversight, the Federal Facility Agreement and Consent Order, the role of Indian tribes, public participation, and CERCLA Natural Resource Damage Assessment Trustee Activities are all discussed.

  5. Remaining Sites Verification Package for the 100-B-23, 100-B/C Area Surface Debris. Attachment to Waste Site, Waste Site Reclassification Form 2008-027

    International Nuclear Information System (INIS)

    The 100-B-23, 100-B/C Surface Debris, waste consisted of multiple locations of surface debris and chemical stains that were identified during an Orphan Site Evaluation of the 100-B/C Area. Evaluation of the collected information for the surface debris features yielded four generic waste groupings: asbestos-containing material, lead debris, oil and oil filters, and treated wood. Focused verification sampling was performed concurrently with remediation. Site remediation was accomplished by selective removal of the suspect hazardous items and potentially impacted soils. In accordance with this evaluation, the verification sampling results support a reclassification of this site to Interim Closed Out. The results of verification sampling show that residual contaminant concentrations do not preclude any future uses and allow for unrestricted use of shallow zone soils. The results also demonstrate that residual contaminant concentrations are protective of groundwater and the Columbia River

  6. Remaining Sites Verification Package for the 100-D-2 Lead Sheeting Waste Site. Attachment to Waste Site Reclassification Form 2007-030

    International Nuclear Information System (INIS)

    The 100-D-2 Lead Sheeting waste site was located approximately 50 m southwest of the 185-D Building and approximately 16 m north of the east/west oriented road. The site consisted of a lead sheet covering a concrete pad. In accordance with this evaluation, the verification sampling results support a reclassification of this site to Interim Closed Out. The results of verification sampling show that residual contaminant concentrations do not preclude any future uses and allow for unrestricted use of shallow zone soils. The results also demonstrate that residual contaminant concentrations are protective of groundwater and the Columbia River

  7. Remaining Sites Verification Package for the 1607-F3 Sanitary Sewer System. Attachment to Waste Site Reclassification Form 2006-047

    International Nuclear Information System (INIS)

    The 1607-F3 waste site is the former location of the sanitary sewer system that supported the 182-F Pump Station, the 183-F Water Treatment Plant, and the 151-F Substation. The sanitary sewer system included a septic tank, drain field, and associated pipeline, all in use between 1944 and 1965. In accordance with this evaluation, the verification sampling results support a reclassification of this site to Interim Closed Out. The results of verification sampling demonstrated that residual contaminant concentrations do not preclude any future uses and allow for unrestricted use of shallow zone soils. The results also showed that residual contaminant concentrations are protective of groundwater and the Columbia River

  8. Remaining Sites Verification Package for the 116-C-3, 105-C Chemical Waste Tanks, Waste Site Reclassification Form 2008-002

    Energy Technology Data Exchange (ETDEWEB)

    L. M. Dittmer

    2008-01-31

    The 116-C-3 waste site consisted of two underground storage tanks designed to receive mixed waste from the 105-C Reactor Metals Examination Facility chemical dejacketing process. Confirmatory evaluation and subsequent characterization of the site determined that the southern tank contained approximately 34,000 L (9,000 gal) of dejacketing wastes, and that the northern tank was unused. In accordance with this evaluation, the verification sampling and modeling results support a reclassification of this site to Interim Closed Out. The results of verification sampling demonstrate that residual contaminant concentrations do not preclude any future uses and allow for unrestricted use of shallow zone soils. The results also show that residual contaminant concentrations are protective of groundwater and the Columbia River.

  9. Remaining Sites Verification Package for the 1607-F4 Sanitary Sewer System. Attachment to Waste Site Reclassification Form 2004-131

    International Nuclear Information System (INIS)

    The 1607-F4 waste site is the former location of the sanitary sewer system that serviced the former 115-F Gas Recirculation Building. The system included a septic tank, drain field, and associated pipeline that were in use from 1944 to 1965. The 1607-F4 waste site received unknown amounts of sanitary sewage from the 115-F Gas Recirculation Building and may have potentially contained hazardous and radioactive contamination. In accordance with this evaluation, the verification sampling results support a reclassification of this site to Interim Closed Out. The results of verification sampling demonstrated that residual contaminant concentrations do not preclude any future uses and allow for unrestricted use of shallow zone soils. The results also showed that residual contaminant concentrations are protective of groundwater and the Columbia River

  10. Remaining Sites Verification Package for the 100-F-26:13, 108-F Drain Pipelines, Waste Site Reclassification Form 2005-011

    Energy Technology Data Exchange (ETDEWEB)

    L. M. Dittmer

    2008-03-03

    The 100-F-26:13 waste site is the network of process sewer pipelines that received effluent from the 108-F Biological Laboratory and discharged it to the 188-F Ash Disposal Area (126-F-1 waste site). The pipelines included one 0.15-m (6-in.)-, two 0.2-m (8-in.)-, and one 0.31-m (12-in.)-diameter vitrified clay pipe segments encased in concrete. In accordance with this evaluation, the verification sampling results support a reclassification of this site to Interim Closed Out. The results of verification sampling demonstrated that residual contaminant concentrations do not preclude any future uses and allow for unrestricted use of shallow zone soils. The results also showed that residual contaminant concentrations are protective of groundwater and the Columbia River.

  11. Remaining Sites Verification Package for the 100-F-26:9, 1607-F2 Sanitary Sewer Pipelines. Attachment to Waste Site Reclassification Form 2008-029

    International Nuclear Information System (INIS)

    The 100-F-26:9 underground pipeline subsite consists of the sanitary sewers servicing the 105-F, 108-F, 184-F, 185-F, and 190-F buildings, and the 1700-F administration and service buildings (1704-F, 1707-F, 1707-FA, 1713-F, 1717-F, 1719-F, and 1722-F). In accordance with this evaluation, the confirmatory and verification sampling results support a reclassification of this site to Interim Closed Out. The current site conditions achieve the remedial action objectives and the corresponding remedial action goals established in the Remaining Sites ROD. The results of verification sampling show that residual contaminant concentrations do not preclude any future uses and allow for unrestricted use of shallow zone soils. The results also demonstrate that residual contaminant concentrations are protective of groundwater and the Columbia River

  12. Remaining Sites Verification Package for the 100-F-26:9, 1607-F2 Sanitary Sewer Pipelines, Waste Site Reclassification Form 2008-029

    Energy Technology Data Exchange (ETDEWEB)

    J. M. Capron

    2008-10-29

    The 100-F-26:9 underground pipeline subsite consists of the sanitary sewers servicing the 105-F, 108-F, 184-F, 185-F, and 190-F buildings, and the 1700-F administration and service buildings (1704-F, 1707-F, 1707-FA, 1713-F, 1717-F, 1719-F, and 1722-F). In accordance with this evaluation, the confirmatory and verification sampling results support a reclassification of this site to Interim Closed Out. The current site conditions achieve the remedial action objectives and the corresponding remedial action goals established in the Remaining Sites ROD. The results of verification sampling show that residual contaminant concentrations do not preclude any future uses and allow for unrestricted use of shallow zone soils. The results also demonstrate that residual contaminant concentrations are protective of groundwater and the Columbia River.

  13. Remaining Sites Verification Package for the 120-F-1 Glass Dump Waste Site. Attachment to Waste Site Reclassification Form 2008-028

    International Nuclear Information System (INIS)

    The 120-F-1 waste site consisted of two dumping areas located 660 m southeast of the 105-F Reactor containing laboratory equipment and bottles, demolition debris, light bulbs and tubes, small batteries, small drums, and pesticide contaminated soil. It is probable that 108-F was the source of the debris but the material may have come from other locations within the 100-F Area. In accordance with this evaluation, the verification sampling results support a reclassification of this site to Interim Closed Out. The results of verification sampling show that residual contaminant concentrations do not preclude any future uses and allow for unrestricted use of shallow zone soils. The results also demonstrate that residual contaminant concentrations are protective of groundwater and the Columbia River

  14. Remaining Sites Verification Package for the 100-F-26:12, 1.8-m (72-in.) Main Process Sewer Pipeline, Waste Site Reclassification Form 2007-034

    Energy Technology Data Exchange (ETDEWEB)

    J. M. Capron

    2008-04-29

    The 100-F-26:12 waste site was an approximately 308-m-long, 1.8-m-diameter east-west-trending reinforced concrete pipe that joined the North Process Sewer Pipelines (100-F-26:1) and the South Process Pipelines (100-F-26:4) with the 1.8-m reactor cooling water effluent pipeline (100-F-19). In accordance with this evaluation, the verification sampling results support a reclassification of this site to Interim Closed Out. The results of verification sampling show that residual contaminant concentrations do not preclude any future uses and allow for unrestricted use of shallow zone soils. The results also demonstrate that residual contaminant concentrations are protective of groundwater and the Columbia River.

  15. Remaining Sites Verification Package for the 128-F-2, 100-F Burning Pit Waste Site. Attachment to Waste Site Reclassification Form 2008-031

    International Nuclear Information System (INIS)

    The 128-F-2 waste site consisted of multiple burn and debris filled pits located directly east of the 107-F Retention Basin and approximately 30.5 m east of the northeast corner of the 100-F Area perimeter road that runs along the riverbank. The burn pits were used for incinerating nonradioactive, combustible materials from 1945 to 1965. In accordance with this evaluation, the verification sampling results support a reclassification of this site to Interim Closed Out. The current site conditions achieve the remedial action objectives and the corresponding remedial action goals established in the Remaining Sites ROD. The results of verification sampling show that residual contaminant concentrations do not preclude any future uses and allow for unrestricted use of shallow zone soils. The results also demonstrate that residual contaminant concentrations are protective of groundwater and the Columbia River

  16. Remaining Sites Verification Package for the 116-F-8, 1904-F Outfall Structure and the 100-F-42, 1904-F Spillway, Waste Site Reclassification Form 2006-038

    Energy Technology Data Exchange (ETDEWEB)

    L. M. Dittmer

    2006-09-25

    The 116-F-8 waste site is the former 1904-F Outfall Structure used to discharge reactor cooling water effluent fro mthe 107-F Retention Basin to the Columbia River. The results of verification sampling show that residual contaminant concentrations do not preclude any future uses and allow for unrestricted use of shallow zone soils. The results also demonstrate that residual contaminant concentrations are protective of groundwater and the Columbia River.

  17. Remaining Sites Verification Package for the 100-B-20, 1716-B Maintenance Garage Underground Tank. Attachment to Waste Site Reclassification Form 2006-019

    International Nuclear Information System (INIS)

    The 100-B-20 waste site, located in the 100-BC-1 Operable Unit of the Hanford Site, consisted of an underground oil tank that once serviced the 1716-B Maintenance Garage. The selected action for the 100-B-20 waste site involved removal of the oil tanks and their contents and demonstrating through confirmatory sampling that all cleanup goals have been met. In accordance with this evaluation, a reclassification status of interim closed out has been determined. The results demonstrate that the site will support future unrestricted land uses that can be represented by a rural-residential scenario. These results also show that residual concentrations support unrestricted future use of shallow zone soil and that contaminant levels remaining in the soil are protective of groundwater and the Columbia River

  18. Cleanup contract protest upheld

    International Nuclear Information System (INIS)

    Cleanup of the huge Hanford nuclear weapon site in Washington state, long mired in disputes over contract awards, faces another potential delay. On October 12 the US General Accounting Office upheld a protest to the award of the site's $800-million Environmental Restoration Management Contract (ERMC). GAO has ordered the US DOE to review the contract award to a team led by Bechtel Group Inc., a process observers say could be quick or a quagmire. GAO sustained part of a protest filed in early 1993 by Parsons Environmental Services Inc., Pasadena, California, which led an unsuccessful team bid for the ERMC

  19. Remaining Sites Verification Package for the 100-F-33, 146-F Aquatic Biology Fish Ponds, Waste Site Reclassification Form 2006-021

    Energy Technology Data Exchange (ETDEWEB)

    L. M. Dittmer

    2006-08-25

    The 100-F-33, 146-F Aquatice Biology Fish Ponds waste site was an area with six small rectangular ponds and one large circular pond used to conduct tests on fish using various mixtures of river and reactor effluent water. The current site conditions achieve the remedial action objectives specified in the Remaining Sites ROD. The results of verification and applicable confirmatory sampling show that residual contaminant concentrations do not preclude any future uses and allow for unrestricted use of shallow zone soils. The results also demonstrate that residual contaminant concentrations are protective of groundwater and the Columbia River.

  20. Remaining Sites Verification Package for the 100-C-9:2 Sanitary Sewer Pipelines, Waste Site Reclassification Form 2004-013

    Energy Technology Data Exchange (ETDEWEB)

    L. M. Dittmer

    2007-07-11

    The 100-C-9:2 sanitary sewer pipelines include the feeder pipelines associated with the 1607-B8, the 1607-B9, the 1607-B10 and the 1607-B11 septic systems. Contaminated soil and piping from the feeder lines to the septic systems were removed and disposed of. The remaining soil in the excavations has been shown to meet the remedial action objectives specified in the Remaining Sites ROD. The results of verification sampling show that residual contaminant concentrations do not preclude any future uses and allow for unrestricted use of shallow zone soils. The results also demonstrate that residual contaminant concentrations are protective of groundwater and the Columbia River.

  1. Remaining Sites Verification Package for the 126-B-3, 184-B Coal Pit Dumping Area, Waste Site Reclassification Form 2005-028

    Energy Technology Data Exchange (ETDEWEB)

    L. M. Dittmer

    2006-08-07

    The 126-B-3 waste site is the former coal storage pit for the 184-B Powerhouse. During demolition operations in the 1970s, the site was used for disposal of demolition debris from 100-B/C Area facilities. The site has been remediated by removing debris and contaminated soils. The results of verification sampling demonstrated that residual contaminant concentrations do not preclude any future uses and allow for unrestricted use of shallow zone soils. The results also showed that residual contaminant concentrations are protective of groundwater and the Columbia River.

  2. Remaining Sites Verification Package for the 128-B-2, 100-B Burn Pit No.2 Waste Site. Attchment to Waste Site Reclassification Form 2005-038

    International Nuclear Information System (INIS)

    The 128-B-2 waste site was a burn pit historically used for the disposal of combustible and noncombustible wastes, including paint and solvents, office waste, concrete debris, and metallic debris. This site has been remediated by removing approximately 5,627 bank cubic meters of debris, ash, and contaminated soil to the Environmental Restoration Disposal Facility. The results of verification sampling demonstrated that residual contaminant concentrations do not preclude any future uses and allow for unrestricted use of shallow zone soils. The results also showed that residual contaminant concentrations are protective of groundwater and the Columbia River

  3. Remaining Sites Verification Package for the 128-B-3 Burn Pit Site. Attachment to Waste Site Reclassification Form 2006-058

    International Nuclear Information System (INIS)

    The 128-B-3 waste site is a former burn and disposal site for the 100-B/C Area, located adjacent to the Columbia River. The 128-B-3 waste site has been remediated to meet the remedial action objectives specified in the Remaining Sites ROD. The results of verification sampling demonstrated that residual contaminant concentrations do not preclude any future uses and allow for unrestricted use of shallow zone soils. The results of sampling at upland areas of the site also showed that residual contaminant concentrations are protective of groundwater and the Columbia River

  4. Remaining Sites Verification Package for the 120-B-1, 105-B Battery Acid Sump. Attachment to Waste Site Reclassification Form 2006-057

    International Nuclear Information System (INIS)

    The 120-B-1 waste site, located in the 100-BC-1 Operable Unit of the Hanford Site, consisted of a concrete battery acid sump that was used from 1944 to 1969 to neutralize the spent sulfuric acid from lead cell batteries of emergency power packs and the emergency lighting system. The battery acid sump was associated with the 105-B Reactor Building and was located adjacent to the building's northwest corner. The results of verification sampling demonstrated that residual contaminant concentrations do not preclude any future uses and allow for unrestricted use of shallow zone soils. The results also showed that residual contaminant concentrations are protective of groundwater and the Columbia River

  5. Remaining Sites Verification Package for the 100-F-33, 146-F Aquatic Biology Fish Ponds. Attachment to Waste Site Reclassification Form 2006-021

    International Nuclear Information System (INIS)

    The 100-F-33, 146-F Aquatice Biology Fish Ponds waste site was an area with six small rectangular ponds and one large circular pond used to conduct tests on fish using various mixtures of river and reactor effluent water. The current site conditions achieve the remedial action objectives specified in the Remaining Sites ROD. The results of verification and applicable confirmatory sampling show that residual contaminant concentrations do not preclude any future uses and allow for unrestricted use of shallow zone soils. The results also demonstrate that residual contaminant concentrations are protective of groundwater and the Columbia River

  6. Remaining Sites Verification Package for the 100-C-9:2 Sanitary Sewer Pipelines. Attachment to Waste Site Reclassification Form 2004-013

    International Nuclear Information System (INIS)

    The 100-C-9:2 sanitary sewer pipelines include the feeder pipelines associated with the 1607-B8, the 1607-B9, the 1607-B10 and the 1607-B11 septic systems. Contaminated soil and piping from the feeder lines to the septic systems were removed and disposed of. The remaining soil in the excavations has been shown to meet the remedial action objectives specified in the Remaining Sites ROD. The results of verification sampling show that residual contaminant concentrations do not preclude any future uses and allow for unrestricted use of shallow zone soils. The results also demonstrate that residual contaminant concentrations are protective of groundwater and the Columbia River

  7. Remaining Sites Verification Package for the 100-F-31, 144-F Sanitary Sewer System. Attachment to Waste Site Reclassification Form 2006-033

    International Nuclear Information System (INIS)

    The 100-F-31 waste site is a former septic system that supported the inhalation laboratories, also referred to as the 144-F Particle Exposure Laboratory (132-F-2 waste site), which housed animals exposed to particulate material. The 100-F-31 waste site has been remediated to achieve the remedial action objectives specified in the Remaining Sites ROD. The results of verification sampling show that residual contaminant concentrations do not preclude any future uses and allow for unrestricted use of shallow zone soils. The results also demonstrate that residual contaminant concentrations are protective of groundwater and the Columbia River

  8. Remaining Sites Verification Package for the 126-B-3, 184-B Coal Pit Dumping Area. Attachment to Waste Site Reclassification Form 2005-028

    International Nuclear Information System (INIS)

    The 126-B-3 waste site is the former coal storage pit for the 184-B Powerhouse. During demolition operations in the 1970s, the site was used for disposal of demolition debris from 100-B/C Area facilities. The site has been remediated by removing debris and contaminated soils. The results of verification sampling demonstrated that residual contaminant concentrations do not preclude any future uses and allow for unrestricted use of shallow zone soils. The results also showed that residual contaminant concentrations are protective of groundwater and the Columbia River

  9. Remaining Sites Verification Package for the 100-F-31, 144-F Sanitary Sewer System, Waste Site Reclassification Form 2006-033

    Energy Technology Data Exchange (ETDEWEB)

    L. M. Dittmer

    2006-08-24

    The 100-F-31 waste site is a former septic system that supported the inhalation laboratories, also referred to as the 144-F Particle Exposure Laboratory (132-F-2 waste site), which housed animals exposed to particulate material. The 100-F-31 waste site has been remediated to achieve the remedial action objectives specified in the Remaining Sites ROD. The results of verification sampling show that residual contaminant concentrations do not preclude any future uses and allow for unrestricted use of shallow zone soils. The results also demonstrate that residual contaminant concentrations are protective of groundwater and the Columbia River.

  10. Remaining Sites Verification Package for the 116-F-8, 1904-F Outfall Structure and the 100-F-42, 1904-F Spillway, Waste Site Reclassification Form 2006-045

    Energy Technology Data Exchange (ETDEWEB)

    L. M. Dittmer

    2006-09-26

    The 100-F-42 waste site is the portion of the former emergency overflow spillway for the 1904-F Outfall Structure formerly existing above the ordinary high water mark of the Columbia River. The spillway consisted of a concrete flume designed to discharge effluent from the 107-F Retention Basin in the event that flows could not be completely discharged via the river outfall pipelines. The results of verification sampling show that residual contaminant concentrations do not preclude any future uses and allow for unrestricted use of shallow zone soils. The results also demonstrate that residual contaminant concentrations are protective of groundwater and the Columbia River.

  11. Reactor coolant cleanup facility

    International Nuclear Information System (INIS)

    A depressurization device is disposed in pipelines upstream of recycling pumps of a reactor coolant cleanup facility to reduce a pressure between the pressurization device and the recycling pump at the downstream, thereby enabling high pressure coolant injection from other systems by way of the recycling pumps. Upon emergency, the recycling pumps of the coolant cleanup facility can be used in common to an emergency reactor core cooling facility and a reactor shutdown facility. Since existent pumps of the emergency reactor core cooling facility and the reactor shutdown facility which are usually in a stand-by state can be removed, operation confirmation test and maintenance for equipments in both of facilities can be saved, so that maintenance and reliability of the plant are improved and burdens on operators can also be mitigated. Moreover, low pressure design can be adopted for a non-regenerative heat exchanger and recycling coolant pumps, which enables to improve the reliability and economical property due to reduction of possibility of leakage. (N.H.)

  12. Remaining Sites Verification Package for the 100-C-9:1 Main Process Sewer Collection Line. Attachment to Waste Site Reclassification Form 2004-012

    International Nuclear Information System (INIS)

    The 100-C-9:1 main process sewer pipeline, also known as the twin box culvert, was a dual reinforced process sewer that collected process effluent from the 183-C and 190-C water treatment facilities, discharging at the 132-C-2 Outfall. For remedial action purposes, the 100-C-9:1 waste site was subdivided into northern and southern sections. The 100-C-9:1 subsite has been remediated to achieve the remedial action objectives specified in the Remaining Sites ROD. The results of verification sampling show that residual contaminant concentrations do not preclude any future uses and allow for unrestricted use of shallow zone soils. The results also demonstrate that residual contaminant concentrations are protective of groundwater and the Columbia River

  13. Remaining Sites Verification Package for the 100-C-9:1 Main Process Sewer Collection Line, Waste Site Reclassification Form 2004-012

    Energy Technology Data Exchange (ETDEWEB)

    L. M. Dittmer

    2007-06-11

    The 100-C-9:1 main process sewer pipeline, also known as the twin box culvert, was a dual reinforced process sewer that collected process effluent from the 183-C and 190-C water treatment facilities, discharging at the 132-C-2 Outfall. For remedial action purposes, the 100-C-9:1 waste site was subdivided into northern and southern sections. The 100-C-9:1 subsite has been remediated to achieve the remedial action objectives specified in the Remaining Sites ROD. The results of verification sampling show that residual contaminant concentrations do not preclude any future uses and allow for unrestricted use of shallow zone soils. The results also demonstrate that residual contaminant concentrations are protective of groundwater and the Columbia River.

  14. Remaining Sites Verification Package for the 1607-B2 Septic System and 100-B-14:2 Sanitary Sewer System, Waste Site Reclassification Form 2006-055

    Energy Technology Data Exchange (ETDEWEB)

    L. M. Dittmer

    2007-03-21

    The 1607-B2 waste site is a former septic system associated with various 100-B facilities, including the 105-B, 108-B, 115-B/C, and 185/190-B buildings. The site was evaluated based on confirmatory results for feeder lines within the 100-B-14:2 subsite and determined to require remediation. The 1607-B2 waste site has been remediated to achieve the remedial action objectives specified in the Remaining Sites ROD. The results of verification sampling show that residual contaminant concentrations do not preclude any future uses and allow for unrestricted use of shallow zone soils. The results also demonstrate that residual contaminant concentrations are protective of groundwater and the Columbia River.

  15. Remaining Sites Verification Package for the 1607-B2 Septic System and 100-B-14:2 Sanitary Sewer System, Waste Site Reclassification Form 2004-006

    Energy Technology Data Exchange (ETDEWEB)

    L. M. Dittmer

    2007-03-21

    The 100-B-14:2 subsite encompasses the former sanitary sewer feeder lines associated with the 1607-B2 and 1607-B7 septic systems. Feeder lines associated with the 185/190-B building have also been identified as the 100-B-14:8 subsite, and feeder lines associated with the 1607-B7 septic system have also been identified as the 100-B-14:9 subsite. These two subsites have been administratively cancelled to resolve the redundancy. The results of verification sampling show that residual contaminant concentrations do not preclude any future uses and allow for unrestricted use of shallow zone soils. The results also demonstrate that residual contaminant concentrations are protective of groundwater and the Columbia River.

  16. Implications of the KONVERGENCE Model for Difficult Cleanup Decisions

    Energy Technology Data Exchange (ETDEWEB)

    Piet, Steven James; Dakins, Maxine Ellen; Gibson, Patrick Lavern; Joe, Jeffrey Clark; Kerr, Thomas A; Nitschke, Robert Leon

    2002-08-04

    Abstract—Some cleanup decisions, such as cleanup of intractable contaminated sites or disposal of spent nuclear fuel, have proven difficult to make. Such decisions face high resistance to agreement from stakeholders possibly because they do not trust the decision makers, view the consequences of being wrong as too high, etc. Our project’s goal is to improve sciencebased cleanup decision-making. This includes diagnosing intractable situations, as a step to identifying a path toward sustainable solutions. Companion papers describe the underlying philosophy of the KONVERGENCE Model for Sustainable Decisions,1 and the overall framework and process steps.2 Where knowledge, values, and resources converge (the K, V, and R in KONVERGENCE), you will find a sustainable decision – a decision that works over time. For intractable cases, serious consideration of the adaptable class of alternatives is warranted – if properly implemented and packaged.

  17. Cleanup under Airlock of an Old Uranium Foundry - 13273

    International Nuclear Information System (INIS)

    up and dismantling the first portion of the building, the enclosure was repositioned on the second and the last third of the building, by sliding it on support pads. Almost 7,000 m2 of concrete surface has been treated with no dust dispersion outside the enclosure. After treatment, all the remaining surfaces were controlled by an independent entity to verify their acceptability with regards to residual contamination (less than 0.4 Bq/cm2 (24 DPM) for alpha contamination and less than 1 Bq/g of total uranium). Approximately 1,900 MT of equipment and waste were generated in batches of 1m3, in order to be staged on site, and then characterized and packaged in 20 foot containers for shipment to the final ANDRA repository. The package certification included the verification of the physical and chemical characteristics and the radiological characteristics (mass activity, dose rate, and residual outside surface contamination). Finally, after cleanup and dismantling of the foundry, a concrete slab was poured on the free surface as a clean base for implementation of new activities. (authors)

  18. Cleanup of demineralizer resins

    International Nuclear Information System (INIS)

    Radiocesium is being removed from demineralizers A and B (DA and DB) by a process that was developed from laboratory tests on small samples of resin from the demineralizers. The process was designed to elute the radiocesium from the demineralizer resins and then to resorb it onto the zeolite ion exchangers contained in the Submerged Demineralizer System (SDS). It was also required to limit the maximum cesium activities in the resin eluates (SDSD feeds) so that the radiation field surrounding the pipelines would not be excessive. The process consisted of 17 stages of batch elution. In the initial stage, the resin was contacted with 0.18 M boric acid. Subsequent stages subjected the resin to increasing concentrations of sodium in NaH2BO3-H3BO3 solution (total boron= 0.35 M) and then 1 M sodium hydroxide in the final stages. Results on the performance of the process in the cleanup of the demineralizers at TMI-2 are compared with those obtained from laboratory tests with small samples of the DA and DB resins. To date, 15 stages of batch elution have been completed on the demineralizers at TMI-2, which resulted in the removal of about 750 Ci of radiocesium from DA and about 3300 Ci from DB

  19. Graphite waste pit cleanup

    International Nuclear Information System (INIS)

    The UP1 plant in Marcoule reprocessed nearly 20,000 tons of used natural uranium gas cooled reactor fuel coming from the first generation of civil nuclear reactors in France. During more than 40 years, the decladding operations produced thousands of tons of processed waste, mainly magnesium and graphite fragments. In the absence of a French repository for the graphite waste, the graphite sludge content of the storage pit had to be retrieved and transferred into a newer and safer pit. So, this project consists in the full retrieval and transfer of 15 m3 of water mixed with graphite dust located in the decladding facility, as well as the complete cleanup and decontamination of the pit. The equipment and process necessary for retrieval operations were designed, built and tested. The process is mainly based on the use of two pumps (one to capture and the other one to transfer the sludge) working one after the other and a robotic arm mounted on a telescopic mast. A dedicated process was also set up for the removal of the biggest fragments. In the pit, the sludge retrieval and transfer operations have been almost completed. Most of the non-pumpable graphite fragments has been removed and transferred to a new storage pit. As irradiant fragments have been discovered in the pit, specific studies are in progress in order to remove them to the laboratory for dissolution. This work is expected to 2014. (authors)

  20. Cleanups in my Community Widget

    Data.gov (United States)

    U.S. Environmental Protection Agency — The Cleanups in my Community widget returns facilities within the area of interest that are in the process of being cleaned up, or have been cleaned up, by programs...

  1. Accelerating cleanup: Paths to closure

    International Nuclear Information System (INIS)

    This report describes the status of Environmental Management's (EM's) cleanup program and a direction forward to complete achievement of the 2006 vision. Achieving the 2006 vision results in significant benefits related to accomplishing EM program objectives. As DOE sites accelerate cleanup activities, risks to public health, the environment, and worker safety and health are all reduced. Finding more efficient ways to conduct work can result in making compliance with applicable environmental requirements easier to achieve. Finally, as cleanup activities at sites are completed, the EM program can focus attention and resources on the small number of sites with more complex cleanup challenges. Chapter 1 describes the process by which this report has been developed and what it hopes to accomplish, its relationship to the EM decision-making process, and a general background of the EM mission and program. Chapter 2 describes how the site-by-site projections were constructed, and summarizes, for each of DOE's 11 Operations/Field Offices, the projected costs and schedules for completing the cleanup mission. Chapter 3 presents summaries of the detailed cleanup projections from three of the 11 Operations/Field Offices: Rocky Flats (Colorado), Richland (Washington), and Savannah River (South Carolina). The remaining eight Operations/Field Office summaries are in Appendix E. Chapter 4 reviews the cost drivers, budgetary constraints, and performance enhancements underlying the detailed analysis of the 353 projects that comprise EM's accelerated cleanup and closure effort. Chapter 5 describes a management system to support the EM program. Chapter 6 provides responses to the general comments received on the February draft of this document

  2. Accelerating cleanup: Paths to closure

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-06-01

    This report describes the status of Environmental Management`s (EM`s) cleanup program and a direction forward to complete achievement of the 2006 vision. Achieving the 2006 vision results in significant benefits related to accomplishing EM program objectives. As DOE sites accelerate cleanup activities, risks to public health, the environment, and worker safety and health are all reduced. Finding more efficient ways to conduct work can result in making compliance with applicable environmental requirements easier to achieve. Finally, as cleanup activities at sites are completed, the EM program can focus attention and resources on the small number of sites with more complex cleanup challenges. Chapter 1 describes the process by which this report has been developed and what it hopes to accomplish, its relationship to the EM decision-making process, and a general background of the EM mission and program. Chapter 2 describes how the site-by-site projections were constructed, and summarizes, for each of DOE`s 11 Operations/Field Offices, the projected costs and schedules for completing the cleanup mission. Chapter 3 presents summaries of the detailed cleanup projections from three of the 11 Operations/Field Offices: Rocky Flats (Colorado), Richland (Washington), and Savannah River (South Carolina). The remaining eight Operations/Field Office summaries are in Appendix E. Chapter 4 reviews the cost drivers, budgetary constraints, and performance enhancements underlying the detailed analysis of the 353 projects that comprise EM`s accelerated cleanup and closure effort. Chapter 5 describes a management system to support the EM program. Chapter 6 provides responses to the general comments received on the February draft of this document.

  3. Innovative technologies for groundwater cleanup

    International Nuclear Information System (INIS)

    These notes provide a broad overview of current developments in innovative technologies for groundwater cleanup. In this context, groundwater cleanup technologies include site remediation methods that deal with contaminants in ground water or that may move from the vadose zone into ground water. This discussion attempts to emphasize approaches that may be able to achieve significant improvements in groundwater cleanup cost or effectiveness. However, since data for quantitative performance and cost comparisons of new cleanup methods are scarce, preliminary comparisons must be based on the scientific approach used by each method and on the site-specific technical challenges presented by each groundwater contamination situation. A large number of technical alternatives that are now in research, development, and testing can be categorized by the scientific phenomena that they employ and by the site contamination situations that they treat. After reviewing a representative selection of these technologies, one of the new technologies, the Microbial Filter method, is discussed in more detail to highlight a promising in situ groundwater cleanup technology that is now being readied for field testing

  4. Innovative technologies for soil cleanup

    International Nuclear Information System (INIS)

    These notes provide a broad overview of current developments in innovative technologies for soil cleanup. In this context, soil cleanup technologies include site remediation methods that deal primarily with the vadose zone and with relatively shallow, near-surface contamination of soil or rock materials. This discussion attempts to emphasize approaches that may be able to achieve significant improvements in soil cleanup cost or effectiveness. However, since data for quantitative performance and cost comparisons of new cleanup methods are scarce, preliminary comparisons must be based on the scientific approach used by each method and on the sits-specific technical challenges presented by each sold contamination situation. A large number of technical alternatives that are now in research, development, and testing can be categorized by the scientific phenomena that they employ and by the site contamination situations that they treat. After cataloging a representative selection of these technologies, one of the new technologies, Dynamic Underground Stripping, is discussed in more detail to highlight a promising soil cleanup technology that is now being field tested

  5. Radioactive Waste and Clean-up: Introduction

    International Nuclear Information System (INIS)

    The primary mission of the Radioactive Waste and Clean-up division is to propose, to develop and to evaluate solutions for a safe, acceptable and sustainable management of radioactive waste. The Radioactive Waste and Clean-up division programme consists in research, studies, development and demonstration aiming to realise the objective of Agenda 21 on sustainable development in the field of radioactive waste and rehabilitation on radioactively contaminated sites. Indeed, it participates in the realisation of an objective which is to ensure that radioactive wastes are safely managed, transported, stored and disposed of, with a view to protecting human health and the environment, within a wider framework of an interactive and integrated approach to radioactive waste management and safety. We believe that nuclear energy will be necessary for the sustainable development of mankind in the 21st century, but we well understand that it would not be maintained if it is not proven that within benefits of nuclear energy a better protection of the environment is included. Although the current waste management practices are both technically and from the environmental point of view adequate, efforts in relation of future power production and waste management technologies should be put on waste minimisation. Therefore, the new and innovative reactors, fuel cycle and waste management processes and installations should be designed so that the waste generation can be kept in minimum. In addition to the design, the installations should be operated so as to create less waste; consideration should be given e.g. to keeping water chemistry clean and other quality factors. SCK-CEN in general and the Radioactive Waste and Clean-up division in particular are present in international groups preparing the development of innovative nuclear reactors, as Generation 4 and INPRO. Because performance assessments are often black boxes for the public, demonstration is needed for the acceptation of

  6. Oil spills and their cleanup

    International Nuclear Information System (INIS)

    Oil spills are an unfortunately common occurrence in the world's seas and can have extensive damaging environmental consequences. This article examines various methods of cleaning up oil spills, evaluates their effectiveness in various situations, and identifies areas where, current methods being inadequate, further research is needed. Containment, mechanical removal, shoreline cleanup, chemical treating agents, in situ burning, natural recovery and enhanced bioremediation are all assessed. The cleanup method must be selected to match environmental conditions. Results are good in quiet, sheltered waters, but need extensive development in open waters and high seas. (UK)

  7. Packaging fluency

    DEFF Research Database (Denmark)

    Mocanu, Ana; Chrysochou, Polymeros; Bogomolova, Svetlana;

    2011-01-01

    Research on packaging stresses the need for packaging design to read easily, presuming fast and accurate processing of product-related information. In this paper we define this property of packaging as “packaging fluency”. Based on the existing marketing and cognitive psychology literature...... on packaging design and processing fluency, our aim is to define and conceptualise packaging fluency. We stress the important role of packaging fluency since it is anticipated that a fluent package would influence the evaluative judgments for a product. We conclude this paper by setting the research agenda...

  8. Recycling Facilities - Land Recycling Cleanup Locations

    Data.gov (United States)

    NSGIC GIS Inventory (aka Ramona) — Land Recycling Cleanup Location Land Recycling Cleanup Locations (LRCL) are divided into one or more sub-facilities categorized as media: Air, Contained Release or...

  9. Methodology for setting cleanup criteria

    International Nuclear Information System (INIS)

    The U.S. Department of Energy (DOE) has developed guidance for establishing cleanup criteria or authorized limits for sites containing residual radioactive material. The DOE requires that the as-low-as-reasonably-achievable (ALARA) process be applied. This process results in the development of cleanup levels that are as low as practicable giving due consideration to health, environment, economics, cultural, and natural resources and other factors. The process employs a cost-benefit optimization analysis and, where appropriate and feasible, considers multiple attributes. Frequently, some important factors or attributes do not lend themselves to quantification in a cost-benefit study and therefore must be considered qualitatively in the process. While the cost-benefit analysis is not the only consideration, it is an important clement in the establishment of cleanup criteria and selection of remedial alternatives. Key to the cost-benefit process is the relation between cleanup level and dose. This is determined through pathway analysis methodology. This paper discusses the pathway analysis process and will cover radiologically and nonradiologically contaminated sites and building contamination

  10. Characterization of plutonium contamination at Maralinga: Dosimetry and cleanup criteria

    International Nuclear Information System (INIS)

    An area of South Australia remained contaminated following British atomic tests at Maralinga during 1955-1963. Of importance is the long lived 239Pu of which some 24 kg was explosively dispersed in several 'minor trials'. The extent, quantities and physical characteristics of the plutonium have been assessed and estimates of dose, dominated by the inhalation pathway in the critical group of Aborigines living a semi-traditional lifestyle, have been made for potential occupants. Dosimetry, together with social and economic factors, underpins the setting of cleanup criteria in terms of activity concentrations averaged over large areas and permissible concentrations of contaminated particles. The possibility of intentional behaviour such as fragment scavenging has also influenced limits on particulate contamination. Rehabilitation of the most contaminated areas is underway, with scraping of surface soil and burial on site completed. Vehicular-mounted radiation detector systems for wide area and particle monitoring have been developed, and procedures established for determining cleanup boundaries and for the verification monitoring to ensure that the cleanup process has met the specified criteria. Data are being obtained for a final dose and health risk assessment of the cleaned up site. (author)

  11. Microelectronic packaging

    CERN Document Server

    Datta, M; Schultze, J Walter

    2004-01-01

    Microelectronic Packaging analyzes the massive impact of electrochemical technologies on various levels of microelectronic packaging. Traditionally, interconnections within a chip were considered outside the realm of packaging technologies, but this book emphasizes the importance of chip wiring as a key aspect of microelectronic packaging, and focuses on electrochemical processing as an enabler of advanced chip metallization.Divided into five parts, the book begins by outlining the basics of electrochemical processing, defining the microelectronic packaging hierarchy, and emphasizing the impac

  12. Complex-Wide Waste Flow Analysis V1.0 verification and validation report

    International Nuclear Information System (INIS)

    The complex-wide waste flow analysis model (CWWFA) was developed to assist the Department of Energy (DOE) Environmental Management (EM) Office of Science and Technology (EM-50) to evaluate waste management scenarios with emphasis on identifying and prioritizing technology development opportunities to reduce waste flows and public risk. In addition, the model was intended to support the needs of the Complex-Wide Environmental Integration (EMI) team supporting the DOE's Accelerating Cleanup: 2006 Plan. CWWFA represents an integrated environmental modeling system that covers the life cycle of waste management activities including waste generation, interim process storage, retrieval, characterization and sorting, waste preparation and processing, packaging, final interim storage, transport, and disposal at a final repository. The CWWFA shows waste flows through actual site-specific and facility-specific conditions. The system requirements for CWWFA are documented in the Technical Requirements Document (TRD). The TRD is intended to be a living document that will be modified over the course of the execution of CWWFA development. Thus, it is anticipated that CWWFA will continue to evolve as new requirements are identified (i.e., transportation, small sites, new streams, etc.). This report provides a documented basis for system verification of CWWFA requirements. System verification is accomplished through formal testing and evaluation to ensure that all performance requirements as specified in the TRD have been satisfied. A Requirement Verification Matrix (RVM) was used to map the technical requirements to the test procedures. The RVM is attached as Appendix A. Since February of 1997, substantial progress has been made toward development of the CWWFA to meet the system requirements. This system verification activity provides a baseline on system compliance to requirements and also an opportunity to reevaluate what requirements need to be satisfied in FY-98

  13. Accelerating cleanup: Paths to closure

    Energy Technology Data Exchange (ETDEWEB)

    Edwards, C.

    1998-06-30

    This document was previously referred to as the Draft 2006 Plan. As part of the DOE`s national strategy, the Richland Operations Office`s Paths to Closure summarizes an integrated path forward for environmental cleanup at the Hanford Site. The Hanford Site underwent a concerted effort between 1994 and 1996 to accelerate the cleanup of the Site. These efforts are reflected in the current Site Baseline. This document describes the current Site Baseline and suggests strategies for further improvements in scope, schedule and cost. The Environmental Management program decided to change the name of the draft strategy and the document describing it in response to a series of stakeholder concerns, including the practicality of achieving widespread cleanup by 2006. Also, EM was concerned that calling the document a plan could be misconstrued to be a proposal by DOE or a decision-making document. The change in name, however, does not diminish the 2006 vision. To that end, Paths to Closure retains a focus on 2006, which serves as a point in time around which objectives and goals are established.

  14. Professional verification a guide to advanced functional verification

    CERN Document Server

    Wilcox, Paul

    2007-01-01

    The Profession of Verification.- Verification Challenges.- Advanced Funtional Verification.- Successful Verification.- Professional Verification.- The Unified Verification Methodology.- The Unified Verification Methodology.- UVM System-Level Design.- Control Digital Subsystems.- Algorithmic Digital Subsystems.- Analog/RF Subsystems.- Integration and System Verification.- Tools of the Trade.- System-Level Design.- Formal Verification Tools.- Testbench Development.- Advanced Testbenches.- Hardware-Based Verification.

  15. Remaining Sites Verification Package for the 100-B-21:2 Subsite (100-B/C Discovery Pipeline DS-100BC-002), Waste Site Reclassification Form 2008-003

    Energy Technology Data Exchange (ETDEWEB)

    J. M. Capron

    2008-06-16

    The 100-B-21:2 waste site consists of the immediate area of the DS-100BC-02 pipeline. In accordance with this evaluation, the confirmatory and verification sampling results support a reclassification of this site to Interim Closed Out. The results of verification sampling show that residual contaminant concentrations do not preclude any future uses and allow for unrestricted use of shallow zone soils. The results also demonstrate that residual contaminant concentrations are protective of groundwater and the Columbia River.

  16. Remaining Sites Verification Package for the 100-B-21:2 Subsite (100-B/C Discovery Pipeline DS-100BC-002). Attachment Waste Site Reclassification Form 2008-003

    International Nuclear Information System (INIS)

    The 100-B-21:2 waste site consists of the immediate area of the DS-100BC-02 pipeline. In accordance with this evaluation, the confirmatory and verification sampling results support a reclassification of this site to Interim Closed Out. The results of verification sampling show that residual contaminant concentrations do not preclude any future uses and allow for unrestricted use of shallow zone soils. The results also demonstrate that residual contaminant concentrations are protective of groundwater and the Columbia River

  17. MEMS packaging

    CERN Document Server

    Hsu , Tai-Ran

    2004-01-01

    MEMS Packaging discusses the prevalent practices and enabling techniques in assembly, packaging and testing of microelectromechanical systems (MEMS). The entire spectrum of assembly, packaging and testing of MEMS and microsystems, from essential enabling technologies to applications in key industries of life sciences, telecommunications and aerospace engineering is covered. Other topics included are bonding and sealing of microcomponents, process flow of MEMS and microsystems packaging, automated microassembly, and testing and design for testing.The Institution of Engineering and Technology is

  18. General Electric SPDS verification and validation

    International Nuclear Information System (INIS)

    Verification and validation are critical quality assurance activities for the successful design and implementation of computer systems. Verification and validation methodology involves an extensive series of paper and product related activities. The individual activities must be clearly focused on specific objectives so when taken as a total package, they represent a thorough test and evaluation of the integrated hardware/software system. This paper provides an overview description of the extensive verification and validation program General Electric has put in place for its Safety Parameter Display System and other computer system products

  19. Data Packages for the Hanford Immobilized Low-Activity Tank Waste Performance Assessment: 2001 Version

    International Nuclear Information System (INIS)

    Data package supporting the 2001 Immobilized Low-Activity Waste Performance Analysis. Geology, hydrology, geochemistry, facility, waste form, and dosimetry data based on recent investigation are provided. Verification and benchmarking packages for selected software codes are provided

  20. As-Built Verification Plan Spent Nuclear Fuel Canister Storage Building MCO Handling Machine

    International Nuclear Information System (INIS)

    This as-built verification plan outlines the methodology and responsibilities that will be implemented during the as-built field verification activity for the Canister Storage Building (CSB) MCO HANDLING MACHINE (MHM). This as-built verification plan covers THE ELECTRICAL PORTION of the CONSTRUCTION PERFORMED BY POWER CITY UNDER CONTRACT TO MOWAT. The as-built verifications will be performed in accordance Administrative Procedure AP 6-012-00, Spent Nuclear Fuel Project As-Built Verification Plan Development Process, revision I. The results of the verification walkdown will be documented in a verification walkdown completion package, approved by the Design Authority (DA), and maintained in the CSB project files

  1. Surface and subsurface cleanup protocol for radionuclides, Gunnison, Colorado, UMTRA project processing site

    International Nuclear Information System (INIS)

    Surface and subsurface soil cleanup protocols for the Gunnison, Colorado, processing sits are summarized as follows: In accordance with EPA-promulgated land cleanup standards (40 CFR 192), in situ Ra-226 is to be cleaned up based on bulk concentrations not exceeding 5 and 15 pCi/g in 15-cm surface and subsurface depth increments, averaged over 100-m2 grid blocks, where the parent Ra-226 concentrations are greater than, or in secular equilibrium with, the Th-230 parent. A bulk interpretation of these EPA standards has been accepted by the Nuclear Regulatory Commission (NRC), and while the concentration of the finer-sized soil fraction less than a No. 4 mesh sieve contains the higher concentration of radioactivity, the bulk approach in effect integrates the total sample radioactivity over the entire sample mass. In locations where Th-230 has differentially migrated in subsoil relative to Ra-226, a Th-230 cleanup protocol has been developed in accordance with Supplemental Standard provisions of 40 CFR 192 for NRC/Colorado Department of Health (CDH) approval for timely implementation. Detailed elements of the protocol are contained in Appendix A, Generic Protocol from Thorium-230 Cleanup/Verification at UMTRA Project Processing Sites. The cleanup of other radionuclides or nonradiological hazards that pose a significant threat to the public and the environment will be determined and implemented in accordance with pathway analysis to assess impacts and the implications of ALARA specified in 40 CFR 192 relative to supplemental standards

  2. Surface and subsurface cleanup protocol for radionuclides, Gunnison, Colorado, UMTRA project processing site. Final [report

    Energy Technology Data Exchange (ETDEWEB)

    1993-09-01

    Surface and subsurface soil cleanup protocols for the Gunnison, Colorado, processing sits are summarized as follows: In accordance with EPA-promulgated land cleanup standards (40 CFR 192), in situ Ra-226 is to be cleaned up based on bulk concentrations not exceeding 5 and 15 pCi/g in 15-cm surface and subsurface depth increments, averaged over 100-m{sup 2} grid blocks, where the parent Ra-226 concentrations are greater than, or in secular equilibrium with, the Th-230 parent. A bulk interpretation of these EPA standards has been accepted by the Nuclear Regulatory Commission (NRC), and while the concentration of the finer-sized soil fraction less than a No. 4 mesh sieve contains the higher concentration of radioactivity, the bulk approach in effect integrates the total sample radioactivity over the entire sample mass. In locations where Th-230 has differentially migrated in subsoil relative to Ra-226, a Th-230 cleanup protocol has been developed in accordance with Supplemental Standard provisions of 40 CFR 192 for NRC/Colorado Department of Health (CDH) approval for timely implementation. Detailed elements of the protocol are contained in Appendix A, Generic Protocol from Thorium-230 Cleanup/Verification at UMTRA Project Processing Sites. The cleanup of other radionuclides or nonradiological hazards that pose a significant threat to the public and the environment will be determined and implemented in accordance with pathway analysis to assess impacts and the implications of ALARA specified in 40 CFR 192 relative to supplemental standards.

  3. Remaining Sites Verification Package for the 100-F-26:10, 1607-F3 Sanitary Sewer Pipelines (182-F, 183-F, and 151-F Sanitary Sewer Lines), Waste Site Reclassification Form 2007-028

    Energy Technology Data Exchange (ETDEWEB)

    L. M. Dittmer

    2007-12-03

    The 100-F-26:10 waste site includes sanitary sewer lines that serviced the former 182-F, 183-F, and 151-F Buildings. In accordance with this evaluation, the verification sampling results support a reclassification of this site to Interim Closed Out. The results of verification sampling show that residual contaminant concentrations do not preclude any future uses and allow for unrestricted use of shallow zone soils. The results also demonstrate that residual contaminant concentrations are protective of groundwater and the Columbia River.

  4. Remaining Sites Verification Package for the 100-F-36, 108-F Biological Laboratory, and for the 116-F-15, 108-F Radiation Crib, Waste Site Reclassification Form 2007-003

    Energy Technology Data Exchange (ETDEWEB)

    L. M. Dittmer

    2007-05-24

    The 116-F-15 waste site is the former location of the 108-F Radiation Crib that was located in the first floor of the 108-F Biological Laboratory. In accordance with this evaluation, the verification sampling results support a reclassification of this site to Interim Closed Out. The current site conditions achieve the remedial action objectives and the corresponding remedial action goals established in the Remaining Sites ROD. The results of verification sampling show that residual contaminant concentrations do not preclude any future uses and allow for unrestricted use of shallow zone soils. The results also demonstrate that residual contaminant concentrations are protective of groundwater and the Columbia River.

  5. Remaining Sites Verification Package for the 100-F-36, 108-F Biological Laboratory, and for the 116-F-15, 108-F Radiation Crib. Attachment to Waste Site Reclassification Form 2007-002 and 2007-003

    International Nuclear Information System (INIS)

    The 116-F-15 waste site is the former location of the 108-F Radiation Crib that was located in the first floor of the 108-F Biological Laboratory. In accordance with this evaluation, the verification sampling results support a reclassification of this site to Interim Closed Out. The current site conditions achieve the remedial action objectives and the corresponding remedial action goals established in the Remaining Sites ROD. The results of verification sampling show that residual contaminant concentrations do not preclude any future uses and allow for unrestricted use of shallow zone soils. The results also demonstrate that residual contaminant concentrations are protective of groundwater and the Columbia River

  6. Remaining Sites Verification Package for the 100-F-26:15 Miscellaneous Pipelines Associated with the 132-F-6, 1608-F Waste Water Pumping Station. Attachment to Waste Site Reclassification Form 2007-031

    International Nuclear Information System (INIS)

    The 100-F-26:15 waste site consisted of the remnant portions of underground process effluent and floor drain pipelines that originated at the 105-F Reactor. In accordance with this evaluation, the verification sampling results support a reclassification of this site to Interim Closed Out. The results of verification sampling show that residual contaminant concentrations do not preclude any future uses and allow for unrestricted use of shallow zone soils. The results also demonstrate that residual contaminant concentrations are protective of groundwater and the Columbia River

  7. Remaining Sites Verification Package for the 100-F-26:10, 1607-F3 Sanitary Sewer Pipelines (182-F, 183-F, and 151-F Sanitary Sewer Lines). Attachment to Waste Site Reclassification Form 2007-028

    International Nuclear Information System (INIS)

    The 100-F-26:10 waste site includes sanitary sewer lines that serviced the former 182-F, 183-F, and 151-F Buildings. In accordance with this evaluation, the verification sampling results support a reclassification of this site to Interim Closed Out. The results of verification sampling show that residual contaminant concentrations do not preclude any future uses and allow for unrestricted use of shallow zone soils. The results also demonstrate that residual contaminant concentrations are protective of groundwater and the Columbia River

  8. Enhancing aquifer cleanup with reinjection

    International Nuclear Information System (INIS)

    Injection of water or steam, with or without chemical surfactants, is a common petroleum industry technique to enhance product recovery. In the geothermal industry, reinjection (reinjection is used to mean the injection of ground water that was previously injected) of heat- depleted subsurface fluids is commonly used to maintain reservoir pressure, thus prolonging field productivity. The use reinjection in ground-water remediation projects allows for the application of both traditional production field management and a variety of additional enhancements to the cleanup process. Development of the ideas in this paper was stimulated by an initial suggestion by Dr. Jacob Bear (personal discussions, 1990--1991) that reinjected water might be heated to aid the desorption process

  9. HANFORD SITE RIVER CORRIDOR CLEANUP

    International Nuclear Information System (INIS)

    In 2005, the US Department of Energy (DOE) launched the third generation of closure contracts, including the River Corridor Closure (RCC) Contract at Hanford. Over the past decade, significant progress has been made on cleaning up the river shore that bordes Hanford. However, the most important cleanup challenges lie ahead. In March 2005, DOE awarded the Hanford River Corridor Closure Contract to Washington Closure Hanford (WCH), a limited liability company owned by Washington Group International, Bechtel National and CH2M HILL. It is a single-purpose company whose goal is to safely and efficiently accelerate cleanup in the 544 km2 Hanford river corridor and reduce or eliminate future obligations to DOE for maintaining long-term stewardship over the site. The RCC Contract is a cost-plus-incentive-fee closure contract, which incentivizes the contractor to reduce cost and accelerate the schedule. At $1.9 billion and seven years, WCH has accelerated cleaning up Hanford's river corridor significantly compared to the $3.2 billion and 10 years originally estimated by the US Army Corps of Engineers. Predictable funding is one of the key features of the new contract, with funding set by contract at $183 million in fiscal year (FY) 2006 and peaking at $387 million in FY2012. Another feature of the contract allows for Washington Closure to perform up to 40% of the value of the contract and subcontract the balance. One of the major challenges in the next few years will be to identify and qualify sufficient subcontractors to meet the goal

  10. Formal Development and Verification of Railway Control Systems

    DEFF Research Database (Denmark)

    Vu Hong, Linh; Haxthausen, Anne Elisabeth; Peleska, Jan

    This paper presents work package WP4.1 of the RobustRails research project. The work package aims at suggesting a methodology for efficient development and verification of safe and robust railway control systems. 1 Project background and state of the art Over the next 10 years all Danish railway...

  11. Packaging Design Criteria for the MCO Cask

    Energy Technology Data Exchange (ETDEWEB)

    FLANAGAN, B.D.

    2000-08-01

    Approximately 2,100 metric tons of unprocessed, irradiated, nuclear fuel elements are presently stored in the K Basins (including approximately 700 additional elements from the Plutonium-Uranium Extraction Plant, N Reactor, and 327 Laboratory). To permit cleanup of the K Basins and fuel conditioning, the fuel will be transported from the 100 K Area to a Canister Storage Building (CSB) in the 200 East Area. The purpose of this packaging design criteria is to provide criteria for the design, fabrication, and use of a packaging system to transport the large quantities of irradiated nuclear fuel elements positioned within Multi-canister Overpacks. Concurrent with the K Basin cleanup, 72 Shippingport Pressurized Water Reactor Core 2 fuel assemblies will be transported from T Plant to the CSB to provide space at T Plant for K Basin sludge canisters.

  12. Packaging design criteria for the MCO cask

    International Nuclear Information System (INIS)

    Approximately 2,100 metric tons of unprocessed, irradiated nuclear fuel elements are presently stored in the K Basins (including possibly 700 additional elements from PUREX, N Reactor, and 327 Laboratory). The basin water, particularly in the K East Basin, contains significant quantities of dissolved nuclear isotopes and radioactive fuel corrosion particles. To permit cleanup of the K Basins and fuel conditioning, the fuel will be transported from the 100 K Area to a Canister Storage Building (CSB) in the 200 East area. In order to initiate K Basin cleanup on schedule, the two-year fuel-shipping campaign must begin by December 1997. The purpose of this packaging design criteria is to provide criteria for the design, fabrication, and use of a packaging system to transport the large quantities of irradiated nuclear fuel elements positioned within Multiple Canister Overpacks

  13. Remaining Sites Verification Package for the 100-F-26:12, 1.8-m (72-in.) Main Process Sewer Pipeline. Attachment to Waste Site Reclassification Form 2007-034

    International Nuclear Information System (INIS)

    The 100-F-26:12 waste site was an approximately 308-m-long, 1.8-m-diameter east-west-trending reinforced concrete pipe that joined the North Process Sewer Pipelines (100-F-26:1) and the South Process Pipelines (100-F-26:4) with the 1.8-m reactor cooling water effluent pipeline (100-F-19). In accordance with this evaluation, the verification sampling results support a reclassification of this site to Interim Closed Out. The results of verification sampling show that residual contaminant concentrations do not preclude any future uses and allow for unrestricted use of shallow zone soils. The results also demonstrate that residual contaminant concentrations are protective of groundwater and the Columbia River

  14. Remaining Sites Verification Package for the 1607-F1 Sanitary Sewer System (124-F-1) and the 100-F-26:8 (1607-F1) Sanitary Sewer Pipelines Waste Sites, Waste Site Reclassification Form 2004-130

    Energy Technology Data Exchange (ETDEWEB)

    L. M. Dittmer

    2008-03-14

    The 1607-F1 Sanitary Sewer System (124-F-1), consisted of a septic tank, drain field, and associated pipelines that received sanitary waste water from the 1701-F Gatehouse, 1709-F Fire Station, and the 1720-F Administrative Office via the 100-F-26:8 pipelines. The septic tank required remedial action based on confirmatory sampling. In accordance with this evaluation, the verification sampling results support a reclassification of this site to Interim Closed Out. The results of verification sampling show that residual contaminant concentrations do not preclude any future uses and allow for unrestricted use of shallow zone soils. The results also demonstrate that residual contaminant concentrations are protective of groundwater and the Columbia River.

  15. Remaining Sites Verification Package for the 116-F-8, 1904-F Outfall Structure and the 100-F-42, 1904-F Spillway. Attachment to Waste Site Reclassification Form 2006-038 and 2006-045

    International Nuclear Information System (INIS)

    The 116-F-8 waste site is the former 1904-F Outfall Structure used to discharge reactor cooling water effluent from the 107-F Retention Basin to the Columbia River. The results of verification sampling show that residual contaminant concentrations do not preclude any future uses and allow for unrestricted use of shallow zone soils. The results also demonstrate that residual contaminant concentrations are protective of groundwater and the Columbia River

  16. Packaging design criteria for the MCO cask

    International Nuclear Information System (INIS)

    Approximately 2,100 metric tons of unprocessed, irradiated nuclear fuel elements are presently stored in the K Basins. To permit cleanup of the K Basins and fuel conditioning, the fuel will be transported from the K Basins to a Canister Storage Building in the 200 East Area. The purpose of this packaging design criteria is to provide criteria for the design, fabrication, and use of a packaging system to transport the large quantities of irradiated nuclear fuel elements positioned within Multiple Canister Overpacks

  17. Alternatives for Ground Water Cleanup

    Science.gov (United States)

    Hudak, P. F.

    Aquifer remediation is one of our most difficult environmental challenges; technological limitations and problems arising from the physical and chemical complexities of contaminated subsurface environments thwart our best efforts. A 19-member committee of leaders in environmental engineering, hydrogeology, epidemiology, environmental economics, and environmental policy has written an ambitious book that broadly addresses the groundwater remediation problem. Topics include site characterization, capabilities and limitations of pump-and-treat and alternative technologies, alternative goals for ground water cleanup, and policy implications.One of the book's strengths is its information base, which includes various public and private groups, data from 80 pump-and-treat sites, and an extensive literature review. The text is clearly written and well organized. Specific conclusions are stated at the end of each major chapter, and sound policy recommendations are offered at the end of the final chapter. An appendix summarizes pump-andtreat systems reviewed during the study. Several case studies, diagrams, and photographs effectively illustrate concepts and ideas conveyed in the text.

  18. Bioventing reduces soil cleanup costs

    International Nuclear Information System (INIS)

    An offshoot technology from soil venting, bioventing offers a win-win solution for soils contaminated with volatile organic compounds (VOCs) and nonvolatile contaminants such as diesel and fuel oil. Using low air flowrates through permeable soils, bioventing injects sufficient oxygen to support naturally-occurring bacteria, which biodegraded the VOCs and other contaminants into benign byproducts. Waste gas can be directly discharged to atmosphere without further treatment. This results in no offgas treatment required. Bioventing is a cost-effective alternative to traditional soil-venting techniques. Soil venting uses air to volatilize organic-compound contamination from the vadose zone, the unsaturated soil layer above groundwater. Unfortunately, this simple-and-fast approach creates a waste offgas that requires further treatment before discharge, thus adding significantly to overall project costs. In contrast, bioventing uses low air flowrates, which require lower capital and operating costs. No offgas treatment further reduces equipment and operating costs and often eliminates air permitting. As in all treatment strategies, the process must meet the cleanup objectives. Bioventing is an alternative technique making inroads into refining and petrochemical soil-remediation applications

  19. Data Packages for the Hanford Immobilized Low Activity Tank Waste Performance Assessment 2001 Version [SEC 1 THRU 5

    Energy Technology Data Exchange (ETDEWEB)

    MANN, F.M.

    2000-03-02

    Data package supporting the 2001 Immobilized Low-Activity Waste Performance Analysis. Geology, hydrology, geochemistry, facility, waste form, and dosimetry data based on recent investigation are provided. Verification and benchmarking packages for selected software codes are provided.

  20. Increased leukemia risk in Chernobyl cleanup workers

    Science.gov (United States)

    A new study found a significantly elevated risk for chronic lymphocytic leukemia among workers who were engaged in recovery and clean-up activities following the Chernobyl power plant accident in 1986.

  1. Nuclear radiation cleanup and uranium prospecting

    Energy Technology Data Exchange (ETDEWEB)

    Mariella, Jr., Raymond P.; Dardenne, Yves M.

    2016-02-02

    Apparatus, systems, and methods for nuclear radiation cleanup and uranium prospecting include the steps of identifying an area; collecting samples; sample preparation; identification, assay, and analysis; and relating the samples to the area.

  2. Assessment, Cleanup and Redevelopment Exchange System (ACRES)

    Data.gov (United States)

    U.S. Environmental Protection Agency — The Assessment, Cleanup and Redevelopment Exchange System (ACRES) is an online database for Brownfields Grantees to electronically submit data directly to EPA.

  3. Bioavailability: implications for science/cleanup policy

    Energy Technology Data Exchange (ETDEWEB)

    Denit, Jeffery; Planicka, J. Gregory

    1998-12-01

    This paper examines the role of bioavailability in risk assessment and cleanup decisions. Bioavailability refers to how chemicals ''behave'' and their ''availability'' to interact with living organisms. Bioavailability has significant implications for exposure risks, cleanup goals, and site costs. Risk to human health and the environment is directly tied to the bioavailability of the chemicals of concern.

  4. HARVESTING EMSP RESEARCH RESULTS FOR WASTE CLEANUP

    International Nuclear Information System (INIS)

    The extent of environmental contamination created by the nuclear weapons legacy combined with expensive, ineffective waste cleanup strategies at many U.S. Department of Energy (DOE) sites prompted Congress to pass the FY96 Energy and Water Development Appropriations Act, which directed the DOE to: ''provide sufficient attention and resources to longer-term basic science research, which needs to be done to ultimately reduce cleanup costs'', ''develop a program that takes advantage of laboratory and university expertise, and'' ''seek new and innovative cleanup methods to replace current conventional approaches which are often costly and ineffective.'' In response, the DOE initiated the Environmental Management Science Program (EMSP)-a targeted, long-term research program intended to produce solutions to DOE's most pressing environmental problems. EMSP funds basic research to lower cleanup cost and reduce risk to workers, the public, and the environment; direct the nation's scientific infrastructure towards cleanup of contaminated waste sites; and bridge the gap between fundamental research and technology development activities. EMSP research projects are competitively awarded based on the project's scientific, merit coupled with relevance to addressing DOE site needs. This paper describes selected EMSP research projects with long, mid, and short-term deployment potential and discusses the impacts, focus, and results of the research. Results of EMSP research are intended to accelerate cleanup schedules, reduce cost or risk for current baselines, provide alternatives for contingency planning, or provide solutions to problems where no solutions exist

  5. Remaining Sites Verification Package for the 116-F-16, PNL Outfall and the 100-F-43, PNL Outfall Spillway. Attachment to Waste Site Reclassification Form 2006-039 and 2006-046

    International Nuclear Information System (INIS)

    The 100-F-43 waste site is the portion of the former discharge spillway for the PNL Outfall formerly existing above the ordinary high water mark of the Columbia River. The spillway consisted of a concrete flume used to discharge waste effluents from the 100-F Experimental Animal Farm. The results of verification sampling show that residual contaminant concentrations do not preclude any future uses and allow for unrestricted use of shallow zone soils. The results also demonstrate that residual contaminant concentrations are protective of groundwater and the Columbia River

  6. Remaining Sites Verification Package for the 116-F-8, 1904-F Outfall Structure and the 100-F-42, 1904-F Spillway. Attachment to Waste Site Reclassification Form 2006-038 and 2006-045

    International Nuclear Information System (INIS)

    The 100-F-42 waste site is the portion of the former emergency overflow spillway for the 1904-F Outfall Structure formerly existing above the ordinary high water mark of the Columbia River. The spillway consisted of a concrete flume designed to discharge effluent from the 107-F Retention Basin in the event that flows could not be completely discharged via the river outfall pipelines. The results of verification sampling show that residual contaminant concentrations do not preclude any future uses and allow for unrestricted use of shallow zone soils. The results also demonstrate that residual contaminant concentrations are protective of groundwater and the Columbia River

  7. Document image cleanup and binarization

    Science.gov (United States)

    Wu, Victor; Manmatha, Raghaven

    1998-04-01

    Image binarization is a difficult task for documents with text over textured or shaded backgrounds, poor contrast, and/or considerable noise. Current optical character recognition (OCR) and document analysis technology do not handle such documents well. We have developed a simple yet effective algorithm for document image clean-up and binarization. The algorithm consists of two basic steps. In the first step, the input image is smoothed using a low-pass filter. The smoothing operation enhances the text relative to any background texture. This is because background texture normally has higher frequency than text does. The smoothing operation also removes speckle noise. In the second step, the intensity histogram of the smoothed image is computed and a threshold automatically selected as follows. For black text, the first peak of the histogram corresponds to text. Thresholding the image at the value of the valley between the first and second peaks of the histogram binarizes the image well. In order to reliably identify the valley, the histogram is smoothed by a low-pass filter before the threshold is computed. The algorithm has been applied to some 50 images from a wide variety of source: digitized video frames, photos, newspapers, advertisements in magazines or sales flyers, personal checks, etc. There are 21820 characters and 4406 words in these images. 91 percent of the characters and 86 percent of the words are successfully cleaned up and binarized. A commercial OCR was applied to the binarized text when it consisted of fonts which were OCR recognizable. The recognition rate was 84 percent for the characters and 77 percent for the words.

  8. Multi-canister overpack project - verification and validation, MCNP 4A

    International Nuclear Information System (INIS)

    This supporting document contains the software verification and validation (V and V) package used for Phase 2 design of the Spent Nuclear Fuel Multi-Canister Overpack. V and V packages for both ANSYS and MCNP are included. Description of Verification Run(s): This software requires that it be compiled specifically for the machine it is to be used on. Therefore to facilitate ease in the verification process the software automatically runs 25 sample problems to ensure proper installation and compilation. Once the runs are completed the software checks for verification by performing a file comparison on the new output file and the old output file. Any differences between any of the files will cause a verification error. Due to the manner in which the verification is completed a verification error does not necessarily indicate a problem. This indicates that a closer look at the output files is needed to determine the cause of the error

  9. Remaining Sites Verification Package for the 1607-B2 Septic System and 100-B-14:2 Sanitary Sewer System. Attachment to Waste Site Reclassification Form 2066-055 and 2004-006

    International Nuclear Information System (INIS)

    The 100-B-14:2 subsite encompasses the former sanitary sewer feeder lines associated with the 1607-B2 and 1607-B7 septic systems. Feeder lines associated with the 185/190-B building have also been identified as the 100-B-14:8 subsite, and feeder lines associated with the 1607-B7 septic system have also been identified as the 100-B-14:9 subsite. These two subsites have been administratively canceled to resolve the redundancy. The results of verification sampling show that residual contaminant concentrations do not preclude any future uses and allow for unrestricted use of shallow zone soils. The results also demonstrate that residual contaminant concentrations are protective of groundwater and the Columbia River

  10. Remaining Sites Verification Package for the 1607-B2 Septic System and 100-B-14:2 Sanitary Sewer System. Attachment to Waste Site Reclassification Form 2006-055 and 2004-006

    International Nuclear Information System (INIS)

    The 1607-B2 waste site is a former septic system associated with various 100-B facilities, including the 105-B, 108-B, 115-B/C, and 185/190-B buildings. The site was evaluated based on confirmatory results for feeder lines within the 100-B-14:2 subsite and determined to require remediation. The 1607-B2 waste site has been remediated to achieve the remedial action objectives specified in the Remaining Sites ROD. The results of verification sampling show that residual contaminant concentrations do not preclude any future uses and allow for unrestricted use of shallow zone soils. The results also demonstrate that residual contaminant concentrations are protective of groundwater and the Columbia River

  11. Tamper indicating packaging

    International Nuclear Information System (INIS)

    Protecting sensitive items from undetected tampering in an unattended environment is crucial to the success of non-proliferation efforts relying on the verification of critical activities. Tamper Indicating Packaging (TIP) technologies are applied to containers, packages, and equipment that require an indication of a tamper attempt. Examples include: the transportation and storage of nuclear material, the operation and shipment of surveillance equipment and monitoring sensors, and the retail storage of medicine and food products. The spectrum of adversarial tampering ranges from attempted concealment of a pin-hole sized penetration to the complete container replacement, which would involve counterfeiting efforts of various degrees. Sandia National Laboratories (SNL) has developed a technology base for advanced TIP materials, sensors, designs, and processes which can be adapted to various future monitoring systems. The purpose of this technology base is to investigate potential new technologies, and to perform basic research of advanced technologies. This paper will describe the theory of TIP technologies and recent investigations of TIP technologies at SNL

  12. HARVESTING EMSP RESEARCH RESULTS FOR WASTE CLEANUP

    Energy Technology Data Exchange (ETDEWEB)

    Guillen, Donna Post; Nielson, R. Bruce; Phillips, Ann Marie; Lebow, Scott

    2003-02-27

    The extent of environmental contamination created by the nuclear weapons legacy combined with expensive, ineffective waste cleanup strategies at many U.S. Department of Energy (DOE) sites prompted Congress to pass the FY96 Energy and Water Development Appropriations Act, which directed the DOE to: ''provide sufficient attention and resources to longer-term basic science research, which needs to be done to ultimately reduce cleanup costs'', ''develop a program that takes advantage of laboratory and university expertise, and'' ''seek new and innovative cleanup methods to replace current conventional approaches which are often costly and ineffective.'' In response, the DOE initiated the Environmental Management Science Program (EMSP)-a targeted, long-term research program intended to produce solutions to DOE's most pressing environmental problems. EMSP funds basic research to lower cleanup cost and reduce risk to workers, the public, and the environment; direct the nation's scientific infrastructure towards cleanup of contaminated waste sites; and bridge the gap between fundamental research and technology development activities. EMSP research projects are competitively awarded based on the project's scientific, merit coupled with relevance to addressing DOE site needs. This paper describes selected EMSP research projects with long, mid, and short-term deployment potential and discusses the impacts, focus, and results of the research. Results of EMSP research are intended to accelerate cleanup schedules, reduce cost or risk for current baselines, provide alternatives for contingency planning, or provide solutions to problems where no solutions exist.

  13. Verification and disarmament

    International Nuclear Information System (INIS)

    The main features are described of the IAEA safeguards verification system that non-nuclear weapon states parties of the NPT are obliged to accept. Verification activities/problems in Iraq and North Korea are discussed

  14. Verification and disarmament

    Energy Technology Data Exchange (ETDEWEB)

    Blix, H. [IAEA, Vienna (Austria)

    1998-07-01

    The main features are described of the IAEA safeguards verification system that non-nuclear weapon states parties of the NPT are obliged to accept. Verification activities/problems in Iraq and North Korea are discussed.

  15. Retroactive insurance may fund TMI-2 cleanup

    International Nuclear Information System (INIS)

    A Pennsylvania task force recommended that nuclear utilities insure their plants with a mandatory national property insurance program. The proposed Nuclear Powerplant Property Damage Insurance Act of 1981 will cover the cleanup costs of onsite damage in excess of $350 million for a single accident ($50 million when private insurance is added on) and a ceiling of two billion dollars. Participation in the insurance pool would be in conjunction with licensing and would permit no grandfathering. Total payout for Three Mile Island-2 would cover 75% of the cleanup costs, the remainder to be apportioned among other parties. The insurance pool will have a $750 million goal supported by utility premiums

  16. Verification of component mode techniques for flexible multibody systems

    Science.gov (United States)

    Wiens, Gloria J.

    1990-01-01

    Investigations were conducted in the modeling aspects of flexible multibodies undergoing large angular displacements. Models were to be generated and analyzed through application of computer simulation packages employing the 'component mode synthesis' techniques. Multibody Modeling, Verification and Control Laboratory (MMVC) plan was implemented, which includes running experimental tests on flexible multibody test articles. From these tests, data was to be collected for later correlation and verification of the theoretical results predicted by the modeling and simulation process.

  17. Independent Verification Final Summary Report for the David Witherspoon, Inc. 1630 Site Knoxville, Tennessee

    International Nuclear Information System (INIS)

    The primary objective of the independent verification was to determine if BJC performed the appropriate actions to meet the specified 'hot spot' cleanup criteria of 500 picocuries per gram (pCi/g) uranium-238 (U-238) in surface soil. Specific tasks performed by the independent verification team (IVT) to satisfy this objective included: (1) performing radiological walkover surveys, and (2) collecting soil samples for independent analyses. The independent verification (IV) efforts were designed to evaluate radioactive contaminants (specifically U-238) in the exposed surfaces below one foot of the original site grade, given that the top one foot layer of soil on the site was removed in its entirety.

  18. Remaining Sites Verification Package for the 600-111, P-11 Critical Mass Laboratory Crib, and UPR-600-16, Fire and Contamination Spread Waste Sites. Attachment to Waste Site Reclassification Form 2004-065 and 2008-045

    International Nuclear Information System (INIS)

    The UPR-600-16, Fire and Contamination Spread waste site is an unplanned release that occurred on December 4, 1951, when plutonium contamination was spread by a fire that ignited inside the 120 Experimental Building. The 120 Experimental Building was a laboratory building that was constructed in 1949 and used for plutonium criticality studies as part of the P-11 Project. In November 1951, a criticality occurred in the 120 Experimental Building that resulted in extensive plutonium contamination inside the building. The confirmatory evaluation supports a reclassification of this site to Interim Closed Out. The current site conditions achieve the remedial action objectives and the corresponding remedial action goals established in the Remaining Sites ROD. The results of the extensive radiological survey of the surface soil and the confirmatory and verification sampling show that residual contaminant concentrations do not preclude any future uses and allow for unrestricted use of shallow zone soils. The results also demonstrate that residual contaminant concentrations are protective of groundwater and the Columbia River

  19. Final report: Fuel spill cleanup at the Del Air Unit

    Data.gov (United States)

    US Fish and Wildlife Service, Department of the Interior — This report summarizes the cleanup of a fuel spill on the Delair Unit of Great River NWR in 1994. Soil test results are provided, the cleanup process is summarized,...

  20. US nuclear cleanup shows signs of progress

    International Nuclear Information System (INIS)

    The U.S. Department of Energy's program for dealing with the radioactive and hazardous wastes at its former nuclear weapons production sites and at the national laboratories has been criticized for its expense and slow pace of cleanup. The largest environmental restoration and waste management program in the world faces formidable technical and scientific problems and these, according to numerous investigative committees and commissions, have been compounded by poor management, misuse of technology, and failure to appreciate the need for new basic scientific knowledge to solve many of the cleanup problems. In the past three years, DOE's Office of Environmental Management (EM), often spurred by congressional action, has begun to trim costs and accomplish more. New measures have been introduced to improve contract efficiency, better utilize existing remediation technologies, renegotiate compliance agreements, and begin basic research. Environmental Management Assistant Undersecretary Alvin Alm, appointed in May 1996, is seeking to solidify these changes into an ambitious plan to clean up most of DOE's 130 sites by 2006. But there are widespread doubts that EM has the money, skill, and will to turn itself around. There are also concerns that, in the name of efficiency and economy, EM may be negotiating lower cleanup standards and postponing some difficult cleanup tasks. This article discusses these issues. 7 refs

  1. CONOCO DOLOMITE HOT GAS CLEANUP SYSTEM

    Science.gov (United States)

    This report analyzes a proposal that EPA sponsor a large-scale pilot plant to develop the Conoco (formerly Consol) Dolomite Hot Gas Clean-up system. The report includes a history of the prior development program, the technology involved comparisons with competitive technologies i...

  2. Experience in mining plutonium for soil cleanup

    International Nuclear Information System (INIS)

    Plutonium contamination from nuclear tests in 1962 is present at Johnston Atoll in soil throughout a 10-ha site. Since the middle 1980s, the Defense Nuclear Agency has been developing a mining operation to cleanup the contaminated soil. A plant now routinely mines plutonium from soil to make most of the soil clean and suitable for beneficial use. Before this initiative, the mining paradigm was to concentrate a valuable substance and leave waste tailings. Mining for cleanup represents a paradigm shift as it concentrates the radioactive substance for waste disposal and leaves the valuable substance, clean soil. The cleanup plant combines conventional mining and milling technology, radiation detection equipment, and microprocessor computer controls. A variety of technologies have been evaluated since the plant was first started in 1990. Success has come from soil sorters and classifiers. To May 1993, there were 37 weeks with some soil cleanup. The plant processed 17,000 tons of soil and made 98% clean. Production at 1,000 tons/week is routine. The plant concentrate will be further processed to reduce waste below 2%

  3. Evaluation of contaminated groundwater cleanup objectives

    International Nuclear Information System (INIS)

    The US Department of Energy's (DOE's) Environmental Restoration Program will be responsible for remediating the approximately 230 contaminated groundwater sites across the DOE Complex. A major concern for remediation is choosing the appropriate cleanup objective. The cleanup objective chosen will influence the risk to the nearby public during and after remediation; risk to remedial and non-involved workers during remediation; and the cost of remediation. This paper discusses the trends shown in analyses currently being performed at Oak Ridge National Laboratories' (ORNL's) Center for Risk Management (CRM). To evaluate these trends, CRM is developing a database of contaminated sites. This paper examines several contaminated groundwater sites selected for assessment from CRM's data base. The sites in this sample represent potential types of contaminated groundwater sites commonly found at an installation within DOE. The baseline risk from these sites to various receptors is presented. Residual risk and risk during remediation is reported for different cleanup objectives. The cost associated with remediating to each of these objectives is also estimated for each of the representative sites. Finally, the general trends of impacts as a function of cleanup objective will be summarized. The sites examined include the Savannah River site, where there was substantial ground pollution from radionuclides, oil, coal stockpiles, and other forms of groundwater contamination. The effects of various types of groundwater contamination on various types of future user is described. 4 refs., 3 figs., 2 tabs

  4. Radioactive Waste and Clean-up Division

    International Nuclear Information System (INIS)

    The main objectives of the Radioactive Waste and Clean-up division of SCK-CEN are outlined. The division's programme consists of research, development and demonstration projects and aims to contribute to the objectives of Agenda 21 on sustainable development in the field of radioactive waste and rehabilitation of radioactively contaminated sites

  5. High-level waste vitrification off-gas cleanup technology

    International Nuclear Information System (INIS)

    This brief overview is intended to be a basis for discussion of needs and problems existing in the off-gas clean-up technology. A variety of types of waste form and processes are being developed in the United States and abroad. A description of many of the processes can be found in the Technical Alternative Documents (TAD). Concurrently, off-gas processing systems are being developed with most of the processes. An extensive review of methodology as well as decontamination factors can be found in the literature. Since it is generally agreed that the most advanced solidification process is vitrification, discussion here centers about the off-gas problems related to vitrification. With a number of waste soldification facilities around the world in operation, it can be shown that present technology can satisfy the present requirement for off-gas control. However, a number of areas within the technology base show potential for improvement. Fundamental as well as verification studies are needed to obtain the improvements

  6. Cleanups In My Community (CIMC) - Recovery Act Funded Cleanups, National Layer

    Data.gov (United States)

    U.S. Environmental Protection Agency — This data layer provides access to Recovery Act Funded Cleanup sites as part of the CIMC web service. The American Recovery and Reinvestment Act was signed into law...

  7. FEFTRA TM verification. Update 2013

    International Nuclear Information System (INIS)

    FEFTRA is a finite element program package developed at VTT for the analyses of groundwater flow in Posiva's site evaluation programme that seeks a final repository for spent nuclear fuel in Finland. The code is capable of modelling steady-state or transient groundwater flow, solute transport and heat transfer as coupled or separate phenomena. Being a typical research tool used only by its developers, the FEFTRA code lacked long of a competent testing system and precise documentation of the verification of the code. In 2006 a project was launched, in which the objective was to reorganise all the material related to the existing verification cases and place them into the FEFTRA program path under the version-control system. The work also included development of a new testing system, which automatically calculates the selected cases, checks the new results against the old approved results and constructs a summary of the test run. All the existing cases were gathered together, checked and added into the new testing system. The documentation of each case was rewritten with the LATEX document preparation system and added into the testing system in a way that the whole test documentation (this report) could easily be generated in a postscript or pdf-format. The current report is the updated version of the verification report published in 2007. At the moment the report includes mainly the cases related to the testing of the primary result quantities (i.e. hydraulic head, pressure, salinity concentration, temperature). The selected cases, however, represent typical hydrological applications, in which the program package has been and will be employed in the Posiva's site evaluation programme, i.e. the simulations of groundwater flow, solute transport and heat transfer as separate or coupled phenomena. The comparison of the FEFTRA results to the analytical, semianalytical and/or other numerical solutions proves the capability of FEFTRA to simulate such problems

  8. Verification Survey of Uranium Mine Remediation

    International Nuclear Information System (INIS)

    The Canadian Nuclear Safety Commission (CNSC) contracted an independent verification of an intensive gamma radiation survey conducted by a mining company to demonstrate that remediation of disturbed areas was complete. This site was the first of the recent mines being decommissioned in Canada and experience gained here may be applied to other mines being decommissioned in the future. The review included examination of the site-specific basis for clean-up criteria and ALARA as required by CNSC guidance. A paper review of the company report was conducted to determine if protocols were followed and that the summarized results could be independently reproduced. An independent verification survey was conducted on parts of the site and comparisons were made between gamma radiation measurements from the verification survey and the original company survey. Some aspects of data collection using rate meters linked to GPS data loggers are discussed as are aspects for data management and analyses methods required for the large amount of data collected during these surveys. Recommendations were made for implementation of future surveys and reporting the data from those surveys in order to ensure that remediation was complete. (authors)

  9. Comparison of different LED Packages

    Science.gov (United States)

    Dieker, Henning; Miesner, Christian; Püttjer, Dirk; Bachl, Bernhard

    2007-09-01

    In this paper different technologies for LED packaging are compared, focusing on Chip on Board (COB) and SMD technology. The package technology which is used depends on the LED application. A critical fact in LED technology is the thermal management, especially for high brightness LED applications because the thermal management is important for reliability, lifetime and electrooptical performance of the LED module. To design certain and long life LED applications knowledge of the heat flow from LEDs to the complete application is required. High sophisticated FEM simulations are indispensable for modern development of high power LED applications. We compare simulations of various substrate materials and packaging technologies simulated using FLOTHERM software. Thereby different substrates such as standard FR4, ceramic and metal core printed circuit boards are considered. For the verification of the simulated results and the testing of manufactured modules, advanced measurement tools are required. We show different ways to experimentally characterize the thermal behavior of LED modules. The thermal path is determined by the transient thermal analysis using the MicReD T3Ster analyzer. Afterwards it will be compared to the conventional method using thermocouples. The heat distribution over the module is investigated by an IR-Camera. We demonstrate and compare simulation and measurement results of Chip-on-Board (COB) and Sub-Mounted Devices (SMD) technology. The results reveal that for different applications certain packages are ideal.

  10. Transportation and packaging resource guide

    Energy Technology Data Exchange (ETDEWEB)

    Arendt, J.W.; Gove, R.M.; Welch, M.J.

    1994-12-01

    The purpose of this resource guide is to provide a convenient reference document of information that may be useful to the U.S. Department of Energy (DOE) and DOE contractor personnel involved in packaging and transportation activities. An attempt has been made to present the terminology of DOE community usage as it currently exists. DOE`s mission is changing with emphasis on environmental cleanup. The terminology or nomenclature that has resulted from this expanded mission is included for the packaging and transportation user for reference purposes. Older terms still in use during the transition have been maintained. The Packaging and Transportation Resource Guide consists of four sections: Sect. 1, Introduction; Sect. 2, Abbreviations and Acronyms; Sect. 3, Definitions; and Sect. 4, References for packaging and transportation of hazardous materials and related activities, and Appendices A and B. Information has been collected from DOE Orders and DOE documents; U.S Department of Transportation (DOT), U.S. Environmental Protection Agency (EPA), and U.S. Nuclear Regulatory Commission (NRC) regulations; and International Atomic Energy Agency (IAEA) standards and other international documents. The definitions included in this guide may not always be a regulatory definition but are the more common DOE usage. In addition, the definitions vary among regulatory agencies. It is, therefore, suggested that if a definition is to be used in a regulatory or a legal compliance issue, the definition should be verified with the appropriate regulation. To assist in locating definitions in the regulations, a listing of all definition sections in the regulations are included in Appendix B. In many instances, the appropriate regulatory reference is indicated in the right-hand margin.

  11. Transportation and packaging resource guide

    International Nuclear Information System (INIS)

    The purpose of this resource guide is to provide a convenient reference document of information that may be useful to the U.S. Department of Energy (DOE) and DOE contractor personnel involved in packaging and transportation activities. An attempt has been made to present the terminology of DOE community usage as it currently exists. DOE's mission is changing with emphasis on environmental cleanup. The terminology or nomenclature that has resulted from this expanded mission is included for the packaging and transportation user for reference purposes. Older terms still in use during the transition have been maintained. The Packaging and Transportation Resource Guide consists of four sections: Sect. 1, Introduction; Sect. 2, Abbreviations and Acronyms; Sect. 3, Definitions; and Sect. 4, References for packaging and transportation of hazardous materials and related activities, and Appendices A and B. Information has been collected from DOE Orders and DOE documents; U.S Department of Transportation (DOT), U.S. Environmental Protection Agency (EPA), and U.S. Nuclear Regulatory Commission (NRC) regulations; and International Atomic Energy Agency (IAEA) standards and other international documents. The definitions included in this guide may not always be a regulatory definition but are the more common DOE usage. In addition, the definitions vary among regulatory agencies. It is, therefore, suggested that if a definition is to be used in a regulatory or a legal compliance issue, the definition should be verified with the appropriate regulation. To assist in locating definitions in the regulations, a listing of all definition sections in the regulations are included in Appendix B. In many instances, the appropriate regulatory reference is indicated in the right-hand margin

  12. ATLAS software packaging

    CERN Document Server

    Rybkin, G

    2012-01-01

    Software packaging is indispensable part of build and prerequisite for deployment processes. Full ATLAS software stack consists of TDAQ, HLT, and Offline software. These software groups depend on some 80 external software packages. We present tools, package PackDist, developed and used to package all this software except for TDAQ project. PackDist is based on and driven by CMT, ATLAS software configuration and build tool, and consists of shell and Python scripts. The packaging unit used is CMT project. Each CMT project is packaged as several packages - platform dependent (one per platform available), source code excluding header files, other platform independent files, documentation, and debug information packages (the last two being built optionally). Packaging can be done recursively to package all the dependencies. The whole set of packages for one software release, distribution kit, also includes configuration packages and contains some 120 packages for one platform. Also packaged are physics analysis pro...

  13. Requirements Verification Report AN Farm to 200E Waste Transfer System for Project W-314, Tank Farm Restoration and Safe Operations

    International Nuclear Information System (INIS)

    This Requirements Verification Report (RVR) for Project W-314 ''AN Farm to 200E Waste Transfer System'' package provides documented verification of design compliance to all the applicable Project Development Specification (PDS) requirements. Additional PDS requirements verification will be performed during the project's procurement, construction, and testing phases, and the RVR will be updated to reflect this information as appropriate

  14. GPU seeks new funding for TMI cleanup

    International Nuclear Information System (INIS)

    General Public Utilities (GPU) wants approval for annual transfer of money from base rate increases in other accounts to pay for the cleanup at Three Mile Island (TMI) until TMI-1 returns to service or the public utility commission takes further action. This proposal confirms fears of a delay in TMI-1 startup and demonstrates that the January negotiated settlement will produce little funding for TMI-2 cleanup. A review of the settlement terms outlines the three-step process for base rate increases and revenue adjustments after the startup of TMI-1, and points out where controversy and delays due to psychological stress make a new source of money essential. GPU thinks customer funding will motivate other parties to a broad-based cost-sharing agreement

  15. Cleanup around an old waste site

    International Nuclear Information System (INIS)

    42,500 m3 of contaminated soil were removed from off-site areas around an old, low-level radioactive waste site near Port Hope, Ontario. The cleanup was done by means of conventional excavation equipment to criteria developed by Eldorado specific to the land use around the company's waste management facility. These cleanup criteria were based on exposure analyses carried out for critical receptors in two different scenarios. The excavated soils, involving eight different landowners, were placed on the original burial area of the waste management facility. Measures were also undertaken to stabilize the soils brought on-site and to ensure that there would be no subsequent recontamination of the off-site areas

  16. Methodologies for estimating shoreline cleanup costs

    Energy Technology Data Exchange (ETDEWEB)

    Etkin, D.S. [Environmental Research Consulting, Winchester, MA (United States)

    2001-07-01

    Once oil from an offshore oil spill hits a shoreline, cleanup operations become more complicated, expensive and time consuming because shoreline and intertidal ecosystems are complex and susceptible to serious impacts both from oiling and response functions. This paper described and compared methodologies for estimating shoreline cleanup costs for hypothetical spill scenarios based on projected shoreline oiling from oil spill trajectory modelling and on the factors that influence cost. It is important to estimate cleanup costs in order to optimize the allocation of resources for shoreline response and restoration. The factors that influence the amount of work needed and resulting cost are the characteristics of the impacted shoreline, the type of oil that has been spilled, and the standards to which cleanup is conducted. The cost estimation methods described in this paper were based on algorithms derived from statistical analyses of historical oil spill cost data in the Environmental Research Consulting database. This included modelling of labour requirements for different types of shorelines and types of oils, as well as other research studies. It was noted that there are serious limitations to these cost estimation methods. These include the fact that vessel and facility response plans are required to address worst case scenarios which have never actually occurred in the US or anywhere else in the world. Some strategies were recommended for improving the modelling of shoreline response costs. It was suggested that the predicted costs should be adjusted to take into account variations in spill situations. Also, contingency plans stress the importance of keeping the oil off the shoreline with booms, skimmers and dispersants. 31 refs., 22 figs.

  17. RISKIND verification and benchmark comparisons

    International Nuclear Information System (INIS)

    This report presents verification calculations and benchmark comparisons for RISKIND, a computer code designed to estimate potential radiological consequences and health risks to individuals and the population from exposures associated with the transportation of spent nuclear fuel and other radioactive materials. Spreadsheet calculations were performed to verify the proper operation of the major options and calculational steps in RISKIND. The program is unique in that it combines a variety of well-established models into a comprehensive treatment for assessing risks from the transportation of radioactive materials. Benchmark comparisons with other validated codes that incorporate similar models were also performed. For instance, the external gamma and neutron dose rate curves for a shipping package estimated by RISKIND were compared with those estimated by using the RADTRAN 4 code and NUREG-0170 methodology. Atmospheric dispersion of released material and dose estimates from the GENII and CAP88-PC codes. Verification results have shown the program to be performing its intended function correctly. The benchmark results indicate that the predictions made by RISKIND are within acceptable limits when compared with predictions from similar existing models

  18. Accelerating cleanup. Paths to closure Hanford Site

    International Nuclear Information System (INIS)

    This document was previously referred to as the Draft 2006 Plan. As part of the DOE's national strategy, the Richland Operations Office's Paths to Closure summarizes an integrated path forward for environmental cleanup at the Hanford Site. The Hanford Site underwent a concerted effort between 1994 and 1996 to accelerate the cleanup of the Site. These efforts are reflected in the current Site Baseline. This document describes the current Site Baseline and suggests strategies for further improvements in scope, schedule and cost. The Environmental Management program decided to change the name of the draft strategy and the document describing it in response to a series of stakeholder concerns, including the practicality of achieving widespread cleanup by 2006. Also, EM was concerned that calling the document a plan could be misconstrued to be a proposal by DOE or a decision-making document. The change in name, however, does not diminish the 2006 vision. To that end, Paths to Closure retains a focus on 2006, which serves as a point in time around which objectives and goals are established

  19. Inspector measurement verification activities

    International Nuclear Information System (INIS)

    e most difficult and complex activity facing a safeguards inspector involves the verification of measurements and the performance of the measurement system. Remeasurement is the key to measurement verification activities. Remeasurerements using the facility's measurement system provide the bulk of the data needed for determining the performance of the measurement system. Remeasurements by reference laboratories are also important for evaluation of the measurement system and determination of systematic errors. The use of these measurement verification activities in conjunction with accepted inventory verification practices provides a better basis for accepting or rejecting an inventory. (U.S.)

  20. High density packaging technology ultra thin package & new tab package

    Science.gov (United States)

    Nakagawa, Osamu; Shimamoto, Haruo; Ueda, Tetsuya; Shimomura, Kou; Hata, Tsutomu; Tachikawa, Toru; Fukushima, Jiro; Banjo, Toshinobu; Yamamoto, Isamu

    1989-09-01

    As electronic devices become more highly integrated, the demand for small, high pin count packages has been increasing. We have developed two new types of IC packages in response to this demand. One is an ultra thin small outline package (TSOP) which has been reduced in size from the standard SOP and the other, which uses Tape Automated Bonding (TAB) technology, is a super thin, high pin count TAB in cap (T.I.C.) package. In this paper, we present these packages and their features along with the technologies used to improve package reliability and TAB. Thin packages are vulnerable to high humidity exposure, especially after heat shock.1 The following items were therefore investigated in order to improve humidity resistance: (1) The molding compound thermal stress, (2) Water absorption into the molding compound and its effect on package cracking during solder dipping, (3) Chip attach pad area and its affect on package cracking, (4) Adhesion between molding resin and chip attach pad and its affect on humidity resistance. With the improvements made as a result of these investigations, the reliability of the new thin packages is similar to that of the standard thicker plastic packages.

  1. Results of Remediation and Verification Sampling for the 600-270 Horseshoe Landfill

    Energy Technology Data Exchange (ETDEWEB)

    W. S. Thompson

    2005-12-14

    This report presents the results of the 2005 remedial action and verification soil sampling conducted at the 600-270 waste site after removal of soil containing residual concentrations of dichlorodiphenyl trichloroethane and its breakdown products dichlorodiphenyl dichloroethylene and dichlorodiphenyl dichloroethane. The remediation was performed in response to post-closure surface soil sampling performed between 1998 and 2003 that indicated the presence of residual DDT contamination exceeding the Record of Decision for the 1100 Area National Priorities List site cleanup criteria of 1 mg/kg that was established for the original 1994 cleanup activities.

  2. Results of Remediation and Verification Sampling for the 600-270 Horseshoe Landfill

    International Nuclear Information System (INIS)

    This report presents the results of the 2005 remedial action and verification soil sampling conducted at the 600-270 waste site after removal of soil containing residual concentrations of dichlorodiphenyl trichloroethane and its breakdown products dichlorodiphenyl dichloroethylene and dichlorodiphenyl dichloroethane. The remediation was performed in response to post-closure surface soil sampling performed between 1998 and 2003 that indicated the presence of residual DDT contamination exceeding the Record of Decision for the 1100 Area National Priorities List site cleanup criteria of 1 mg/kg that was established for the original 1994 cleanup activities.

  3. Verification Account Management System (VAMS)

    Data.gov (United States)

    Social Security Administration — The Verification Account Management System (VAMS) is the centralized location for maintaining SSA's verification and data exchange accounts. VAMS account management...

  4. The ecological impact of land restoration and cleanup. Technical report

    International Nuclear Information System (INIS)

    The report is concerned with the ecological impacts of specific cleanup treatment on the land where they were carried out. The cleanup procedures given apply equally to chemical or radioactive materials. Guidance is provided for cleanup procedures likely to be suggested by government, industry, or environmental groups. The basic types of cleanup procedures for removing or deactiving spilled contamination involve moving people and animals from the affected area, scraping and grading the contaminated soil into windrows, plowing the contamination under, or digging up the contamination and hauling it away. The report describes and evaluates the various land-type cleanup effects in terms of impact of the techniques on the environment. Part I defines several natural ecosystems and some of their natural derivations. Part II presents managed ecosystems which are imposed on natural ecosystems and are no longer bound by the initial native ecosystem balances. Part III deals with avion and mammilian wild life displaced by cleanup

  5. Preplanning of early cleanup. Annual report 1996

    International Nuclear Information System (INIS)

    A pre-study 'Pre-planning of early cleanup after fallout of radioactive material' made by Studvik EcoSafe has pointed out the need and request for pre-planning of actions. Based on the pre-study this project was started with the goal to work out guidelines and checklists. Because of the common interest between the Nordic countries NKS is the organization responsible for the project. The results of the project will be a document pointing out what can be planned in advance, including guidelines and checklists, regarding early cleanup actions after a nuclear plant accident in or in the vicinity of the Nordic countries. In this work 'early' means the three first weeks after an accident. The project only deals with questions concerning external radiation. The document shall be usable by persons in charge of planning or decision makers on the appropriate level of organization for each country. The document shall principally be aimed towards persons without professional competence in the field of radiology. The result will be presented for a limited number of generalized environments and fallout situations: urban/suburban/rural (concentrating on urban/suburban); regional differences (in for example house types and constructing material); dry or wet deposition. Five housing environments, ten cleanup actions and wet or dry deposition are treated. For 66 combinations calculations are made and the results are documented as data sheets, each describing the beneficial effects, costs and disadvantages of application of a feasible method for cleaning in the early phase of a specific type of surface in one of five different urban or suburban environments. This data forms the foundation for the recommendations on guidelines, which are the ultimate goal of the EKO-5 project. (EG)

  6. Shoreline clean-up methods : biological treatments

    Energy Technology Data Exchange (ETDEWEB)

    Massoura, S.T. [Oil Spill Response Limited, Southampton (United Kingdom)

    2009-07-01

    The cleanup of oil spills in shoreline environments is a challenging issue worldwide. Oil spills receive public and media attention, particularly in the event of a coastal impact. It is important to evaluate the efficiency and effectiveness of cleanup methods when defining the level of effort and consequences that are appropriate to remove or treat different types of oil on different shoreline substrates. Of the many studies that have compared different mechanical, chemical and biological treatments for their effectiveness on various types of oil, biological techniques have received the most attention. For that reason, this paper evaluated the effectiveness and effects of shoreline cleanup methods using biological techniques. It summarized data from field experiments and oil spill incidents, including the Exxon Valdez, Sea Empress, Prestige, Grand Eagle, Nakhodka, Guanabara Bay and various Gulf war oil spills. Five major shoreline types were examined, notably rocky intertidal, cobble/pebble/gravel, sand/mud, saltmarsh, and mangrove/sea-grass. The biological techniques that were addressed were nutrient enrichment, hydrocarbon-utilizing bacteria, vegetable oil biosolvents, plants, surf washing, oil-particle interactions and natural attenuation. The study considered the oil type, volume and fate of stranded oil, location of coastal materials, extent of pollution and the impact of biological techniques. The main factors that affect biodegradation of hydrocarbons are the volume, chemical composition and weathering state of the petroleum product as well as the temperature, oxygen availability of nutrients, water salinity, pH level, water content, and microorganisms in the shoreline environment. The interaction of these factors also affect the biodegradation of oil. It was concluded that understanding the fate of stranded oil can help in the development of techniques that improve the weathering and degradation of oil on complex shoreline substrates. 39 refs.

  7. Oil spill cleanup method and apparatus

    Energy Technology Data Exchange (ETDEWEB)

    Mayes, F.M.

    1980-06-24

    A method for removing oil from the surface of water where an oil spill has occurred, particularly in obstructed or shallow areas, which comprises partially surrounding a hovercraft with a floating oil-collecting barrier, there being no barrier at the front of the hovercraft, moving the oil-barrier-surrounded-hovercraft into oil contaminated water, and collecting oil gathered within the barrier behind the hovercraft through a suction line which carries the oil to a storage tank aboard the hovercraft. The invention also embodies the hovercraft adapted to effect an oil spill cleanup.

  8. Landfill gas cleanup for fuel cells

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-08-01

    EPRI is to test the feasibility of using a carbonate fuel cell to generate electricity from landfill gas. Landfills produce a substantial quantity of methane gas, a natural by-product of decaying organic wastes. Landfill gas, however, contains sulfur and halogen compounds, which are known contaminants to fuel cells and their fuel processing equipment. The objective of this project is to clean the landfill gas well enough to be used by the fuel cell without making the process prohibitively expensive. The cleanup system tested in this effort could also be adapted for use with other fuel cells (e.g., solid oxide, phosphoric acid) running on landfill gas.

  9. Particulate hot gas stream cleanup technical issues

    Energy Technology Data Exchange (ETDEWEB)

    Pontius, D.H.; Snyder, T.R.

    1999-09-30

    The analyses of hot gas stream cleanup particulate samples and descriptions of filter performance studied under this contract were designed to address problems with filter operation that have been linked to characteristics of the collected particulate matter. One objective of this work was to generate an interactive, computerized data bank of the key physical and chemical characteristics of ash and char collected from operating advanced particle filters and to relate these characteristics to the operation and performance of these filters. The interactive data bank summarizes analyses of over 160 ash and char samples from fifteen pressurized fluidized-bed combustion and gasification facilities utilizing high-temperature, high pressure barrier filters.

  10. The drift-flux correlation package MDS

    International Nuclear Information System (INIS)

    Based on the SONNENBURG drift-flux correlation, developed at GRS/Garching (Germany), a comprehensive drift-flux correlation package (MDS) has been established. Its aim is to support thermal-hydraulic mixture-fluid models, models being used for the simulation of the steady state and transient behaviour of characteristic thermal-hydraulic parameters of single- or two-phase fluids flowing along coolant channels of different types (being, e.g., parts of NPP-s, steam generators etc.). The characteristic properties of this package with respect to the behaviour at co- and counter-current flow, its inverse solutions needed for steady state simulations, its behaviour when approaching the lower or upper boundary of a two-phase region, its verification and behaviour with respect to other correlations will be discussed. An adequate driver code, MDSDRI, has been established too, allowing to test the package very thoroughly out of the complex thermal-hydraulic codes. (author)

  11. MEMS performance challenges: packaging and shock tests

    Science.gov (United States)

    Chang, Jiyoung; Yang, Chen; Zhang, Bin; Lin, Liwei

    2011-06-01

    This paper describes recent advances in the MEMS performance challenges with emphases on packaging and shock tests. In the packaging area, metal to metal bonding processes have been developed to overcome limitations of the glass frit bonding by means of two specific methods: (1) pre-reflow of solder for enhanced bonding adhesion, and (2) the insertion of thin metal layer between parent metal bonding materials. In the shock test area, multiscale analysis for a MEMS package system has been developed with experimental verifications to investigate dynamic responses under drop-shock tests. Structural deformation and stress distribution data are extracted and predicted for device fracture and in-operation stiction analyses for micro mechanical components in various MEMS sensors, including accelerometers and gyroscopes.

  12. FMCT verification: Case studies

    International Nuclear Information System (INIS)

    Full text: How to manage the trade-off between the need for transparency and the concern about the disclosure of sensitive information would be a key issue during the negotiations of FMCT verification provision. This paper will explore the general concerns on FMCT verification; and demonstrate what verification measures might be applied to those reprocessing and enrichment plants. A primary goal of an FMCT will be to have the five declared nuclear weapon states and the three that operate unsafeguarded nuclear facilities become parties. One focus in negotiating the FMCT will be verification. Appropriate verification measures should be applied in each case. Most importantly, FMCT verification would focus, in the first instance, on these states' fissile material production facilities. After the FMCT enters into force, all these facilities should be declared. Some would continue operating to produce civil nuclear power or to produce fissile material for non- explosive military uses. The verification measures necessary for these operating facilities would be essentially IAEA safeguards, as currently being applied to non-nuclear weapon states under the NPT. However, some production facilities would be declared and shut down. Thus, one important task of the FMCT verifications will be to confirm the status of these closed facilities. As case studies, this paper will focus on the verification of those shutdown facilities. The FMCT verification system for former military facilities would have to differ in some ways from traditional IAEA safeguards. For example, there could be concerns about the potential loss of sensitive information at these facilities or at collocated facilities. Eventually, some safeguards measures such as environmental sampling might be seen as too intrusive. Thus, effective but less intrusive verification measures may be needed. Some sensitive nuclear facilities would be subject for the first time to international inspections, which could raise concerns

  13. Advanced verification topics

    CERN Document Server

    Bhattacharya, Bishnupriya; Hall, Gary; Heaton, Nick; Kashai, Yaron; Khan Neyaz; Kirshenbaum, Zeev; Shneydor, Efrat

    2011-01-01

    The Accellera Universal Verification Methodology (UVM) standard is architected to scale, but verification is growing and in more than just the digital design dimension. It is growing in the SoC dimension to include low-power and mixed-signal and the system integration dimension to include multi-language support and acceleration. These items and others all contribute to the quality of the SOC so the Metric-Driven Verification (MDV) methodology is needed to unify it all into a coherent verification plan. This book is for verification engineers and managers familiar with the UVM and the benefits it brings to digital verification but who also need to tackle specialized tasks. It is also written for the SoC project manager that is tasked with building an efficient worldwide team. While the task continues to become more complex, Advanced Verification Topics describes methodologies outside of the Accellera UVM standard, but that build on it, to provide a way for SoC teams to stay productive and profitable.

  14. REVISED INDEPENDENT VERIFICATION SURVEY OF THE A AND B RADIOACTIVE WASTE TRANSFER LINES TRENCH BROOKHAVEN NATIONAL LABORATORY UPTON, NEW YORK

    International Nuclear Information System (INIS)

    The objective of the verification survey was to obtain evidence by means of measurements and sampling to confirm that the final radiological conditions were less than the established release criteria. This objective was achieved via multiple verification components including document reviews to determine the accuracy and adequacy of FSS documentation. During the period between September 28 and 29, 2009 and December 9 and 10, 2009 an independent verification team with the Oak Ridge Institute for Science and Education conducted measurements and sampling of the A and B Radioactive Waste Transfer Line Trench at the Brookhaven National Laboratory site. Gamma walkover scans did not identify radiation levels that warranted additional investigation. ORISE collected ten judgmental soil samples. All individual samples and the corresponding mean concentration were determined to be below the established cleanup goals. Therefore, it is the opinion of ORISE that the remedial actions implemented by BNL sufficiently meet the established clean-up goals.

  15. Packaging for logistical support

    Science.gov (United States)

    Twede, Diana; Hughes, Harold

    Logistical packaging is conducted to furnish protection, utility, and communication for elements of a logistical system. Once the functional requirements of space logistical support packaging have been identified, decision-makers have a reasonable basis on which to compare package alternatives. Flexible packages may be found, for example, to provide adequate protection and superior utility to that of rigid packages requiring greater storage and postuse waste volumes.

  16. Nuclear test ban verification

    International Nuclear Information System (INIS)

    This report describes verification and its rationale, the basic tasks of seismic verification, the physical basis for earthquake/explosion source discrimination and explosion yield determination, the technical problems pertaining to seismic monitoring of underground nuclear tests, the basic problem-solving strategy deployed by the forensic seismology resarch team at the University of Toronto, and the scientific significance of the team's research. The research carried out at the Univeristy of Toronto has two components: teleseismic verification using P wave recordings from the Yellowknife Seismic Array (YKA), and regional (close-in) verification using high-frequency Lg and Pn recordings from the Eastern Canada Telemetered Network. Major differences have been found in P was attenuation among the propagation paths connecting the YKA listening post with seven active nuclear explosion testing areas in the world. Significant revisions have been made to previously published P wave attenuation results, leading to more interpretable nuclear explosion source functions. (11 refs., 12 figs.)

  17. SSN Verification Service

    Data.gov (United States)

    Social Security Administration — The SSN Verification Service is used by Java applications to execute the GUVERF02 service using the WebSphere/CICS Interface. It accepts several input data fields...

  18. Final Report Independent Verification Survey of the High Flux Beam Reactor, Building 802 Fan House Brookhaven National Laboratory Upton, New York

    Energy Technology Data Exchange (ETDEWEB)

    Harpeneau, Evan M. [Oak Ridge Institute for Science and Education, Oak Ridge, TN (United States). Independent Environmental Assessment and Verification Program

    2011-06-24

    On May 9, 2011, ORISE conducted verification survey activities including scans, sampling, and the collection of smears of the remaining soils and off-gas pipe associated with the 802 Fan House within the HFBR (High Flux Beam Reactor) Complex at BNL. ORISE is of the opinion, based on independent scan and sample results obtained during verification activities at the HFBR 802 Fan House, that the FSS (final status survey) unit meets the applicable site cleanup objectives established for as left radiological conditions.

  19. Final Report - Independent Verification Survey of the High Flux Beam Reactor, Building 802 Fan House Brookhaven National Laboratory Upton, New York

    International Nuclear Information System (INIS)

    On May 9, 2011, ORISE conducted verification survey activities including scans, sampling, and the collection of smears of the remaining soils and off-gas pipe associated with the 802 Fan House within the HFBR (High Flux Beam Reactor) Complex at BNL. ORISE is of the opinion, based on independent scan and sample results obtained during verification activities at the HFBR 802 Fan House, that the FSS (final status survey) unit meets the applicable site cleanup objectives established for as left radiological conditions

  20. TFE design package final report, TFE Verification Program

    International Nuclear Information System (INIS)

    The program objective is to demonstrate the technology readiness of a TFE suitable for use as the basic element in a thermionic reactor with electric power output in the 0.5 to 5.0 MW(e) range, and a full-power life of 7 years. A TFE for a megawatt class system is described. Only six cells are considered for simplicity; a megawatt class TFE would have many more cells, the exact number dependent on optimization trade studies

  1. TFE design package final report, TFE Verification Program

    Energy Technology Data Exchange (ETDEWEB)

    1994-06-01

    The program objective is to demonstrate the technology readiness of a TFE suitable for use as the basic element in a thermionic reactor with electric power output in the 0.5 to 5.0 MW(e) range, and a full-power life of 7 years. A TFE for a megawatt class system is described. Only six cells are considered for simplicity; a megawatt class TFE would have many more cells, the exact number dependent on optimization trade studies.

  2. Bioavailability: implications for science/cleanup policy; FINAL

    International Nuclear Information System (INIS)

    This paper examines the role of bioavailability in risk assessment and cleanup decisions. Bioavailability refers to how chemicals ''behave'' and their ''availability'' to interact with living organisms. Bioavailability has significant implications for exposure risks, cleanup goals, and site costs. Risk to human health and the environment is directly tied to the bioavailability of the chemicals of concern

  3. Architecture synthesis basis for the Hanford Cleanup system: First issue

    International Nuclear Information System (INIS)

    This document describes a set of candidate alternatives proposed to accomplish the Hanford Cleanup system functions defined in a previous work. Development of alternatives is part of a sequence of system engineering activities which lead to definition of all the products which, when completed, accomplish the cleanup mission. The alternative set is developed to functional level four or higher depending on need

  4. New technologies aid DOE in site characterization, cleanup

    International Nuclear Information System (INIS)

    The Department of Energy is using what reportedly is the world's largest remotely operated mobile-work system to excavate a landfill contaminated with radioactive materials at the Idaho National Engineering Laboratory. The 1,500-ton, self-propelled machine made by Sonsub Inc. (Houston) will span and excavate landfills up to 120 feet wide. As the unit digs, it will separate waste from the soil, package the waste for transport, then backfill the pit. DOE will use the machine to excavate Pit 9, a 400-foot-long, 120-foot-wide landfill that was used as a waste-disposal site in the 1960s. Using computer modeling applications to identify hazardous and radioactive wastes can protect workers from exposure and, in some cases, reduce remediation costs. Canberra Industries (Meridien, Conn.) in November was awarded a contract by EG and G Mound Applied Technologies to perform gamma spectroscopy radiological waste characterization on waste containers that have been stored since 1978 at the Mound site in Ohio. The 55-gallon drums and boxes at the site reportedly contain transuranic waste; however, officials say they anticipate that, once characterization is performed, about 25% of the waste will be downgraded to low-level waste (below 100nCI/gm). In another application involving landfill cleanup, Komar Industries Inc. (Groveport, Ohio) in late 1995 was contracted to design and construct a system for processing radioactive waste from an unnamed DOE landfill. The company says it will design a triauger with injector configuration to serve as a fully contained size-reduction, blending and feeding system that will allow engineers to blend a variety of wastes found at the site. Machined, O-ring, sealed surfaces will maintain a negative water column under normal operations. The system will be designed to handle pressures up to 10 bar, while the processor will have a 6-cubic-yard charge capacity and the ability to accept 15 to 20 charges per hour

  5. Saudis map $450 million gulf spill cleanup

    International Nuclear Information System (INIS)

    This paper reports on Saudi Arabia which has earmarked about $450 million to clean up Persian Gulf beaches polluted by history's worst oil spills, created during the Persian Gulf crisis. Details of the proposed cleanup measures were outlined by Saudi environmental officials at a seminar on the environment in Dubai, OPEC News Agency reported. The seminar was sponsored by the Gulf Area Oil Companies Mutual Aid Organization, an environmental cooperative agency set up by Persian Gulf governments. Meantime, a Saudi government report has outlined early efforts designed to contain the massive oil spills that hit the Saudi coast before oil could contaminate water intakes at the huge desalination plants serving Riyadh and cooling water facilities at Al Jubail

  6. Improving oiled shoreline cleanup with COREXIT 9580

    Energy Technology Data Exchange (ETDEWEB)

    Fiocco, R.J.; Lessard, R.R. [Exxon Research and Engineering Co., Florham Park, NJ (United States); Canevari, G.P. [G.P. Canevari Associates, Cranford, NJ (United States)

    1996-08-01

    The cleanup of oiled shorelines has generally been by mechanical, labor-intensive means. The use of a chemical shoreline cleaner to assist in water-flushing oil from the surfaces can result in more complete and more rapid cleaning. Not only is the cleaning process more efficient, but it can also be less environmentally damaging since there is potentially much less human intrusion and stress on the biological community. This paper describes research and applications of COREXIT 9580 shoreline cleaner for treatment of oiled shorelines, including four recent applications in Puerto Rico, Bermuda, Texas and Nova Scotia. Research work on shoreline vegetation, such as mangroves, has also demonstrated the potential use of this product to save and restore oiled vegetation.

  7. Helping with the clean-up

    International Nuclear Information System (INIS)

    Successes in public involvement efforts for nuclear waste management are so few that they deserve careful documentation and analysis. This paper chronicles the goals, process, problems and outcomes of one such success, the Northwest Defense Waste Citizens Forum (CF), created by the DOE-Richland manager in 1986 to advise DOE on its plans for nuclear waste disposal and cleanup of the Hanford site n eastern Washington state. In the evolving, often-controversial, highly-visible area of agency-public interactions, citizen task forces (TFs) have been shown to be useful in developing public policy at the local level. Making them work at the state level is more problematic. This case shows that a diverse, two-state citizen group can make significant contributions to complex EIS evaluations with heavy technical components. The CFs principal contribution to public policy was communication of its findings to business and professional groups, to area political representatives and state agencies, thereby laying the ground work for refocusing the Northwest upon the need for action on DW cleanup at Hanford. In going well beyond NEPA requirements for public involvement in agency decision making, DOE-Richland demonstrated innovative ways of dealing with the difficult issues of public confidence and public trust by means of agency openness, responsiveness to citizen needs for information, and good faith two-way communication. The success of this pro-active DOE initiative was due to many factors including selecting the right issue (existing wastes), structuring the CF at a broad, regional level, and intensive implementation of trust-building strategies

  8. Waste Package Lifting Calculation

    International Nuclear Information System (INIS)

    The objective of this calculation is to evaluate the structural response of the waste package during the horizontal and vertical lifting operations in order to support the waste package lifting feature design. The scope of this calculation includes the evaluation of the 21 PWR UCF (pressurized water reactor uncanistered fuel) waste package, naval waste package, 5 DHLW/DOE SNF (defense high-level waste/Department of Energy spent nuclear fuel)--short waste package, and 44 BWR (boiling water reactor) UCF waste package. Procedure AP-3.12Q, Revision 0, ICN 0, calculations, is used to develop and document this calculation

  9. Comparative Packaging Study

    Science.gov (United States)

    Perchonok, Michele; Antonini, David

    2008-01-01

    This viewgraph presentation describes a comparative packaging study for use on long duration space missions. The topics include: 1) Purpose; 2) Deliverables; 3) Food Sample Selection; 4) Experimental Design Matrix; 5) Permeation Rate Comparison; and 6) Packaging Material Information.

  10. Dual Use Packaging Project

    Data.gov (United States)

    National Aeronautics and Space Administration — NASA seeks down-weighted packaging compatible with microwave preparation and perhaps high hydrostatic pressure processing. New packaging must satisfy NASA's 3-year...

  11. Merganser Download Package

    Data.gov (United States)

    U.S. Environmental Protection Agency — This data download package contains an Esri 10.0 MXD, file geodatabase and copy of this FGDC metadata record. The data in this package are used in support of the...

  12. Tephra fall clean-up in urban environments

    Science.gov (United States)

    Hayes, Josh L.; Wilson, Thomas M.; Magill, Christina

    2015-10-01

    Tephra falls impact urban communities by disrupting transport systems, contaminating and damaging buildings and infrastructures, and are potentially hazardous to human health. Therefore, prompt and effective tephra clean-up measures are an essential component of an urban community's response to tephra fall. This paper reviews case studies of tephra clean-up operations in urban environments around the world, spanning 50 years. It identifies methods used in tephra clean-up and assesses a range of empirical relationships between level of tephra accumulation and clean-up metrics such as collected tephra volume, costs, and duration of operations. Results indicate the volume of tephra collected from urban areas is proportional to tephra accumulation. Urban areas with small tephra accumulations (1,000 m3/km2 or an average of 1 mm thickness) may collect 50,000 m3/km2 or an average of 50 mm thickness) remove up to 80%. This relationship can inform impact and risk assessments by providing an estimate of the likely response required for a given tephra fall. No strong relationship was found between tephra fall accumulation and clean-up cost or duration for urban environments which received one-off tephra falls, suggesting that these aspects of tephra fall clean-up operations are context specific. Importantly, this study highlights the advantage of effective planning for tephra clean-up and disposal in potentially exposed areas.

  13. Recycling glass packaging

    OpenAIRE

    Monica Delia DOMNICA; Leila BARDAªUC

    2015-01-01

    From the specialized literature it follows that glass packaging is not as used as other packages, but in some industries are highly needed. Following, two features of glass packaging will become important until 2017: the shape of the glass packaging and glass recycling prospects in Romania. The recycling of glass is referred to the fact that it saves energy, but also to be in compliance with the provisions indicating the allowable limit values for the quantities of lead and cadmium.

  14. Materials for advanced packaging

    CERN Document Server

    Lu, Daniel

    2010-01-01

    Significant progress has been made in advanced packaging in recent years. Several new packaging techniques have been developed and new packaging materials have been introduced. This book provides a comprehensive overview of the recent developments in this industry, particularly in the areas of microelectronics, optoelectronics, digital health, and bio-medical applications. The book discusses established techniques, as well as emerging technologies, in order to provide readers with the most up-to-date developments in advanced packaging.

  15. ATLAS software packaging

    Science.gov (United States)

    Rybkin, Grigory

    2012-12-01

    Software packaging is indispensable part of build and prerequisite for deployment processes. Full ATLAS software stack consists of TDAQ, HLT, and Offline software. These software groups depend on some 80 external software packages. We present tools, package PackDist, developed and used to package all this software except for TDAQ project. PackDist is based on and driven by CMT, ATLAS software configuration and build tool, and consists of shell and Python scripts. The packaging unit used is CMT project. Each CMT project is packaged as several packages—platform dependent (one per platform available), source code excluding header files, other platform independent files, documentation, and debug information packages (the last two being built optionally). Packaging can be done recursively to package all the dependencies. The whole set of packages for one software release, distribution kit, also includes configuration packages and contains some 120 packages for one platform. Also packaged are physics analysis projects (currently 6) used by particular physics groups on top of the full release. The tools provide an installation test for the full distribution kit. Packaging is done in two formats for use with the Pacman and RPM package managers. The tools are functional on the platforms supported by ATLAS—GNU/Linux and Mac OS X. The packaged software is used for software deployment on all ATLAS computing resources from the detector and trigger computing farms, collaboration laboratories computing centres, grid sites, to physicist laptops, and CERN VMFS and covers the use cases of running all applications as well as of software development.

  16. Materials for advanced packaging

    CERN Document Server

    Wong, CP

    2008-01-01

    Significant progress has been made in advanced packaging in recent years. Several new packaging techniques have been developed and new packaging materials have been introduced. This book provides a comprehensive overview of the recent developments in this industry, particularly in the areas of microelectronics, optoelectronics, digital health, and bio-medical applications. The book discusses established techniques, as well as emerging technologies, in order to provide readers with the most up-to-date developments in advanced packaging.

  17. ATLAS software packaging

    International Nuclear Information System (INIS)

    Software packaging is indispensable part of build and prerequisite for deployment processes. Full ATLAS software stack consists of TDAQ, HLT, and Offline software. These software groups depend on some 80 external software packages. We present tools, package PackDist, developed and used to package all this software except for TDAQ project. PackDist is based on and driven by CMT, ATLAS software configuration and build tool, and consists of shell and Python scripts. The packaging unit used is CMT project. Each CMT project is packaged as several packages—platform dependent (one per platform available), source code excluding header files, other platform independent files, documentation, and debug information packages (the last two being built optionally). Packaging can be done recursively to package all the dependencies. The whole set of packages for one software release, distribution kit, also includes configuration packages and contains some 120 packages for one platform. Also packaged are physics analysis projects (currently 6) used by particular physics groups on top of the full release. The tools provide an installation test for the full distribution kit. Packaging is done in two formats for use with the Pacman and RPM package managers. The tools are functional on the platforms supported by ATLAS—GNU/Linux and Mac OS X. The packaged software is used for software deployment on all ATLAS computing resources from the detector and trigger computing farms, collaboration laboratories computing centres, grid sites, to physicist laptops, and CERN VMFS and covers the use cases of running all applications as well as of software development.

  18. Central heating: package boilers

    Energy Technology Data Exchange (ETDEWEB)

    Farahan, E.

    1977-05-01

    Performance and cost data for electrical and fossil-fired package boilers currently available from manufacturers are provided. Performance characteristics investigated include: unit efficiency, rated capacity, and average expected lifetime of units. Costs are tabulated for equipment and installation of various package boilers. The information supplied in this report will simplify the process of selecting package boilers required for industrial, commercial, and residential applications.

  19. Biobased packaging catalogue

    NARCIS (Netherlands)

    Molenveld, K.; Oever, van den M.J.A.; Bos, H.L.

    2015-01-01

    The purpose of the catalogue is to showcase biobased packaging products and provide an overview of commercially available biobased packaging in 2014. This catalogue is a translation of the Dutch version of the biobased packaging catalogue that was launched September 2014. The raw materials, products

  20. Procedure generation and verification

    International Nuclear Information System (INIS)

    The Department of Energy has used Artificial Intelligence of ''AI'' concepts to develop two powerful new computer-based techniques to enhance safety in nuclear applications. The Procedure Generation System, and the Procedure Verification System, can be adapted to other commercial applications, such as a manufacturing plant. The Procedure Generation System can create a procedure to deal with the off-normal condition. The operator can then take correct actions on the system in minimal time. The Verification System evaluates the logic of the Procedure Generator's conclusions. This evaluation uses logic techniques totally independent of the Procedure Generator. The rapid, accurate generation and verification of corrective procedures can greatly reduce the human error, possible in a complex (stressful/high stress) situation

  1. Nuclear disarmament verification

    Energy Technology Data Exchange (ETDEWEB)

    DeVolpi, A.

    1993-12-31

    Arms control treaties, unilateral actions, and cooperative activities -- reflecting the defusing of East-West tensions -- are causing nuclear weapons to be disarmed and dismantled worldwide. In order to provide for future reductions and to build confidence in the permanency of this disarmament, verification procedures and technologies would play an important role. This paper outlines arms-control objectives, treaty organization, and actions that could be undertaken. For the purposes of this Workshop on Verification, nuclear disarmament has been divided into five topical subareas: Converting nuclear-weapons production complexes, Eliminating and monitoring nuclear-weapons delivery systems, Disabling and destroying nuclear warheads, Demilitarizing or non-military utilization of special nuclear materials, and Inhibiting nuclear arms in non-nuclear-weapons states. This paper concludes with an overview of potential methods for verification.

  2. Nuclear disarmament verification

    International Nuclear Information System (INIS)

    Arms control treaties, unilateral actions, and cooperative activities -- reflecting the defusing of East-West tensions -- are causing nuclear weapons to be disarmed and dismantled worldwide. In order to provide for future reductions and to build confidence in the permanency of this disarmament, verification procedures and technologies would play an important role. This paper outlines arms-control objectives, treaty organization, and actions that could be undertaken. For the purposes of this Workshop on Verification, nuclear disarmament has been divided into five topical subareas: Converting nuclear-weapons production complexes, Eliminating and monitoring nuclear-weapons delivery systems, Disabling and destroying nuclear warheads, Demilitarizing or non-military utilization of special nuclear materials, and Inhibiting nuclear arms in non-nuclear-weapons states. This paper concludes with an overview of potential methods for verification

  3. Approach and plan for cleanup actions in the 100-FR-2 operable unit of the Hanford Site, Revision 0

    International Nuclear Information System (INIS)

    A new administrative approach is being used to reach a cleanup decision for the 100-FR-2 Operable Unit. The unit, located at the 100-F Area, contains solid waste sites and is one of the remaining operable units scheduled for characterization and cleanup in the 100 Area. This Focus Package (1) describes the new approach and activities needed to reach a decision on cleanup actions for the 100-FR-2 Operable Unit and (2) invites public participation into the planning process. The previous approach included the production of a Work Plan, a Limited Field Investigation Report, a Qualitative Risk Assessment, a Focused Feasibility Study, and a Proposed Plan, all culminating in an interim action Record of Decision. Information gathered to date on other operable units allows the analgous site approach to be used on the 100-FR-2 Operable Unit, and therefore, a reduction in documentation preparation. The U.S. Environmental Protection Agency, Washington State Department of Ecology, and the U.S. Department of Energy (Tri-Party Agreement) believe that the new approach will save time and funding. In the new approach, the Work Plan has been condensed into this 12 page Focus Package. The Focus Package includes a summary of 100-F Area information, a list of waste sites in the 100-FR-2 Operable Unit, a summary of proposed work, and a schedule. The new approach will also combine the Limited Field Investigation and Qualitative Risk Assessment reports into the Focused Feasibility Study. The Focused Feasibility Study will analyze methods and costs to clean up waste sites. Consolidating the documents should reduce the time to complete the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) process by 16 months, compared to the previous approach

  4. Eye pathologies of Chernobyl clean-up workers

    International Nuclear Information System (INIS)

    Diseases of the nervous system and sense organs have become the most significant pathologies of Chernobyl clean-up workers during the last four years. The aim of this work was to evaluate the incidence of eye disorders among Chernobyl clean-up workers to provide more information for health specialists. During the last 10 years, the most common eye pathology has been angiopathia retinae, followed by myopia and cataracta. Statistical analyses showed that the clean-up workers have higher risk to develop angiopathia retinae than the control group. (author)

  5. Tritium research laboratory cleanup and transition project final report

    International Nuclear Information System (INIS)

    This Tritium Research Laboratory Cleanup and Transition Project Final Report provides a high-level summary of this project's multidimensional accomplishments. Throughout this report references are provided for in-depth information concerning the various topical areas. Project related records also offer solutions to many of the technical and or administrative challenges that such a cleanup effort requires. These documents and the experience obtained during this effort are valuable resources to the DOE, which has more than 1200 other process contaminated facilities awaiting cleanup and reapplication or demolition

  6. Tritium research laboratory cleanup and transition project final report

    Energy Technology Data Exchange (ETDEWEB)

    Johnson, A.J.

    1997-02-01

    This Tritium Research Laboratory Cleanup and Transition Project Final Report provides a high-level summary of this project`s multidimensional accomplishments. Throughout this report references are provided for in-depth information concerning the various topical areas. Project related records also offer solutions to many of the technical and or administrative challenges that such a cleanup effort requires. These documents and the experience obtained during this effort are valuable resources to the DOE, which has more than 1200 other process contaminated facilities awaiting cleanup and reapplication or demolition.

  7. Verification and validation benchmarks.

    Energy Technology Data Exchange (ETDEWEB)

    Oberkampf, William Louis; Trucano, Timothy Guy

    2007-02-01

    Verification and validation (V&V) are the primary means to assess the accuracy and reliability of computational simulations. V&V methods and procedures have fundamentally improved the credibility of simulations in several high-consequence fields, such as nuclear reactor safety, underground nuclear waste storage, and nuclear weapon safety. Although the terminology is not uniform across engineering disciplines, code verification deals with assessing the reliability of the software coding, and solution verification deals with assessing the numerical accuracy of the solution to a computational model. Validation addresses the physics modeling accuracy of a computational simulation by comparing the computational results with experimental data. Code verification benchmarks and validation benchmarks have been constructed for a number of years in every field of computational simulation. However, no comprehensive guidelines have been proposed for the construction and use of V&V benchmarks. For example, the field of nuclear reactor safety has not focused on code verification benchmarks, but it has placed great emphasis on developing validation benchmarks. Many of these validation benchmarks are closely related to the operations of actual reactors at near-safety-critical conditions, as opposed to being more fundamental-physics benchmarks. This paper presents recommendations for the effective design and use of code verification benchmarks based on manufactured solutions, classical analytical solutions, and highly accurate numerical solutions. In addition, this paper presents recommendations for the design and use of validation benchmarks, highlighting the careful design of building-block experiments, the estimation of experimental measurement uncertainty for both inputs and outputs to the code, validation metrics, and the role of model calibration in validation. It is argued that the understanding of predictive capability of a computational model is built on the level of

  8. Assessing mixtures risks for cleanup and stewardship

    International Nuclear Information System (INIS)

    The U.S. Department of Energy (DOE) is responsible for addressing contamination from past research, production, and disposal activities at over 100 sites and facilities across the country. Use of emerging science to assess risks for these facilities is the key to defining appropriate solutions. Safely managing contamination is a priority to protect workers in the near term, and sustained protection is a priority for local communities over the long term. The Department conducts its environmental management program with input from a number of groups who have expressed concern about the safety of DOE sites over time and the possible conversion of some lands to other uses. In general, past facility activities and disposal operations have contaminated about 10% of the total collective area of DOE sites while surrounding lands have served as buffer zones. Portions of several sites have been released for other uses, such as wildlife preserves. Soil, surface water, and groundwater have been contaminated in most instances, and on-site waste disposal is targeted for many sites. Wastes and contamination that will remain in the environment are at the heart of ongoing future use and long-term management deliberations. For this reason, oversight groups and local citizens are scrutinizing the risk assessments being conducted to support decisions on final cleanup and long-term stewardship. Contaminants exist throughout the world not as individual chemicals but as combinations. The standard risk assessment process broadly applied to support cleanup decisions for contaminated sites is based on single-chemical analyses that do not consider joint toxicity. That is, possible nonadditive effects (commonly termed synergistic or antagonistic) of multiple exposures to multiple chemicals are not generally addressed. The U.S. Environmental Protection Agency (EPA) has been developing a process to assess risks of multiple chemicals (EPA 1990, 2000), but it is not yet being applied to address

  9. Particulate hot gas stream cleanup technical issues

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-09-01

    This is the tenth in a series of quarterly reports describing the activities performed under Contract No. DE-AC21-94MC31160. Analyses of Hot Gas Stream Cleanup (HGCU) ashes and descriptions of filter performance address aspects of filter operation that are apparently linked to the characteristics of the collected ash or the performance of the ceramic bed filter elements. Task I is designed to generate a data base of the key characteristics of ashes collected from operating advanced particle filters (APFS) and to relate these ash properties to the operation and performance of these filters. Task 2 concerns testing and failure analysis of ceramic filter elements. Under Task I during the past quarter, analyses were performed on a particulate sample from the Transport Reactor Demonstration Unit (TRDU) located at the University of North Dakota Energy and Environmental Research Center. Analyses are in progress on ash samples from the Advanced Particulate Filter (APF) at the Pressurized Fluidized-Bed Combustor (PFBC) that was in operation at Tidd and ash samples from the Pressurized Circulating Fluid Bed (PCFB) system located at Karhula, Finland. A site visit was made to the Power Systems Development Facility (PSDF) to collect ash samples from the filter vessel and to document the condition of the filter vessel with still photographs and videotape. Particulate samples obtained during this visit are currently being analyzed for entry into the Hot Gas Cleanup (HGCU) data base. Preparations are being made for a review meeting on ash bridging to be held at Department of Energy Federal Energy Technology Center - Morgantown (DOE/FETC-MGN) in the near future. Most work on Task 2 was on hold pending receipt of additional funds; however, creep testing of Schumacher FT20 continued. The creep tests on Schumacher FT20 specimens just recently ended and data analysis and comparisons to other data are ongoing. A summary and analysis of these creep results will be sent out shortly. Creep

  10. Open verification methodology cookbook

    CERN Document Server

    Glasser, Mark

    2009-01-01

    Functional verification is an art as much as a science. It requires not only creativity and cunning, but also a clear methodology to approach the problem. The Open Verification Methodology (OVM) is a leading-edge methodology for verifying designs at multiple levels of abstraction. It brings together ideas from electrical, systems, and software engineering to provide a complete methodology for verifying large scale System-on-Chip (SoC) designs. OVM defines an approach for developing testbench architectures so they are modular, configurable, and reusable. This book is designed to help both novic

  11. Central Plateau Cleanup at DOE's Hanford Site - 12504

    International Nuclear Information System (INIS)

    The discussion of Hanford's Central Plateau includes significant work in and around the center of the Hanford Site - located about 7 miles from the Columbia River. The Central Plateau is the area to which operations will be shrunk in 2015 when River Corridor cleanup is complete. This work includes retrieval and disposal of buried waste from miles of trenches; the cleanup and closure of massive processing canyons; the clean-out and demolition to 'slab on grade' of the high-hazard Plutonium Finishing Plant; installation of key groundwater treatment facilities to contain and shrink plumes of contaminated groundwater; demolition of all other unneeded facilities; and the completion of decisions about remaining Central Plateau waste sites. A stated goal of EM has been to shrink the footprint of active cleanup to less than 10 square miles by 2020. By the end of FY2011, Hanford will have reduced the active footprint of cleanup by 64 percent exceeding the goal of 49 percent. By 2015, Hanford will reduce the active footprint of cleanup by more than 90 percent. The remaining footprint reduction will occur between 2015 and 2020. The Central Plateau is a 75-square-mile region near the center of the Hanford Site including the area designated in the Hanford Comprehensive Land Use Plan Environmental Impact Statement (DOE 1999) and Record of Decision (64 FR 61615) as the Industrial-Exclusive Area, a rectangular area of about 20 square miles in the center of the Central Plateau. The Industrial-Exclusive Area contains the 200 East and 200 West Areas that have been used primarily for Hanford's nuclear fuel processing and waste management and disposal activities. The Central Plateau also encompasses the 200 Area CERCLA National Priorities List site. The Central Plateau has a large physical inventory of chemical processing and support facilities, tank systems, liquid and solid waste disposal and storage facilities, utility systems, administrative facilities, and groundwater monitoring

  12. Requirement Assurance: A Verification Process

    Science.gov (United States)

    Alexander, Michael G.

    2011-01-01

    Requirement Assurance is an act of requirement verification which assures the stakeholder or customer that a product requirement has produced its "as realized product" and has been verified with conclusive evidence. Product requirement verification answers the question, "did the product meet the stated specification, performance, or design documentation?". In order to ensure the system was built correctly, the practicing system engineer must verify each product requirement using verification methods of inspection, analysis, demonstration, or test. The products of these methods are the "verification artifacts" or "closure artifacts" which are the objective evidence needed to prove the product requirements meet the verification success criteria. Institutional direction is given to the System Engineer in NPR 7123.1A NASA Systems Engineering Processes and Requirements with regards to the requirement verification process. In response, the verification methodology offered in this report meets both the institutional process and requirement verification best practices.

  13. Reactor cavity cleanup system shielded filter installation

    International Nuclear Information System (INIS)

    The Seabrook Station reactor cavity cleanup system provides a flow path for refueling pool purification and drain down during plant refueling evolutions. The original system design included refueling pool surface skimmers and drains, a skimmer pump, an unshielded duplex basket type pump suction strainer and interconnecting stainless steel piping. The piping design utilized socket welded joints in small bore pipe with diaphragm values installed in the horizontal pipe runs downstream of the skimmer pump. The previously installed unshielded strainer in addition to the skimmer pump downstream piping components were determined to be inconsistent with Seabrook's proactive approach to dose reduction. To be consistent with ALARA (As Low As Reasonably Achievable) policy, a plant design change was authorized to install a lead shielded filter unit as a replacement for the existing duplex strainer. This filter unit, which utilizes multiple micron rating disposable basket type cartridges, has a threefold function of protecting the skimmer pump from large solids, providing bulk filtration of activated corrosion products from the refueling water in order to minimize CRUD buildup in downstream components, and enabling retrieval of foreign material drawn into the refueling pool drains

  14. Oil spill cleanup for soft sediments

    International Nuclear Information System (INIS)

    A series of experimental trials are in progress to investigate the effectiveness and consequences of oil spill cleanup methods for areas of mud flats and salt marsh. Trials have shown that wheeled and tracked vehicles have limited utility. Field measurements of the load bearing capacity of the mud can show where such vehicles may be used. Lightweight hover craft provide a useful means of transport. Shallow-draft boats can have a useful transport role: whether such craft can be used depends on the local topography and tidal regime. The trials showed that practical problems associated with implementing low-pressure flushing operations (lack of water for flushing, recovery of the flushed oil) can be overcome - although the environmental effects have yet to be assessed. The use of straw matting as a sorbent material was also demonstrated. The objective of the first two phases of the project, reported here, was to select workable methods with a view to subsequently employing them in larger-scale trials. The environmental consequences of using the selected methods will be examined in the later trials

  15. Dillingham plan attacks oil spill cleanup problem

    Energy Technology Data Exchange (ETDEWEB)

    1970-07-27

    A detailed scheme has been proposed for combating oil spills in U.S. offshore waters, hopefully moving oil spill control out of its infancy and at least into the toddler stage. In a comprehensive one-year systems study for the American Petroleum Institute (API), the results of which were released this week, Dillingham Environmental Co., studied major past oil spills and analyzed equipment and control techniques currently available to deal with them. The project director and his 5-man group recommend a multicomponent scheme including booms, absorbents, sinking agents, and chemical dispersants for oil containment and cleanup. The first phase, definition of the nature and scope of the problem, includes analysis of past oil spills to determine the basic characteristics of major oil spills; delineation of geographic regions where oil spills are likely to occur; and analysis of how oil spills affect, and are affected by the environment. The Dillingham report examines the effect of past oil spills on the environment. It concludes that isolated oil spills do not appear to present a major environmental threat resulting in lasting damage.

  16. Cleanup of a jet fuel spill

    Science.gov (United States)

    Fesko, Steve

    1996-11-01

    Eaton operates a corporate aircraft hanger facility in Battle Creek, Michigan. Tests showed that two underground storage tanks leaked. Investigation confirmed this release discharged several hundred gallons of Jet A kerosene into the soil and groundwater. The oil moved downward approximately 30 feet and spread laterally onto the water table. Test results showed kerosene in the adsorbed, free and dissolved states. Eaton researched and investigated three clean-up options. They included pump and treat, dig and haul and bioremediation. Jet fuel is composed of readily biodegradable hydrocarbon chains. This fact coupled with the depth to groundwater and geologic setting made bioremediation the low cost and most effective alternative. A recovery well was installed at the leading edge of the dissolved contamination. A pump moved water from this well into a nutrient addition system. Nutrients added included nitrogen, phosphorous and potassium. Additionally, air was sparged into the water. The water was discharged into an infiltration gallery installed when the underground storage tanks were removed. Water circulated between the pump and the infiltration basin in a closed loop fashion. This oxygenated, nutrient rich water actively and aggressively treated the soils between the bottom of the gallery and the top of the groundwater and the groundwater. The system began operating in August of 1993 and reduced jet fuel to below detection levels. In August of 1995 The State of Michigan issued a clean closure declaration to the site.

  17. Molten metal, Martin Marietta target DOE, DOD cleanup markets

    International Nuclear Information System (INIS)

    This article describes a joint venture between Martin Marietta Corp. and Molten Metal Technology, Inc. to sell MMT innovative waste processing technology to the Energy and Defense departments, environmental cleanup programs

  18. The Secretary's Vision of the Cleanup Program

    Energy Technology Data Exchange (ETDEWEB)

    Golan, Paul

    2003-02-24

    This paper discusses the Secretary of Energy's vision of the cleanup program. Topics include development a new plan to swiftly clean up serious problems at sites and reduce the risks to human health, safety and the environment.

  19. IMPROVED SILICA GEL CLEANUP METHOD FOR ORGANOPHOSPHORUS PESTICIDES

    Science.gov (United States)

    Quantitative recovery of some organophosphorus pesticide residues has not been possible with existing silica gel-cleanup procedures. The authors have developed a modification that permits quantitative recovery of all organophosphorus pesticides tested, except those with a carbama...

  20. Geographical information system (GIS) support for shoreline cleanup operations

    International Nuclear Information System (INIS)

    A GIS-based system was introduced which was capable of simplifying map production. The importance of an accurate map in shoreline cleanup operations was emphasized. Maps are used to analyze data and are also an effective communication tool, simplifying work coordination between teams. A GIS-based system allows spatial representations to be used much more extensively in integrating information. Two software products, SHORECLEAN and MAPINFO, were used to create a set of maps to be evaluated. The four main categories of tasks involved in shoreline operations were: (1) to collect data on the state of oiling, (2) to plan cleanup operations, (3) to keep track of cleanup operations, and (4) to monitor long-term changes in the state of the shoreline. It was suggested that electronic data captured directly with the portable computer on site on an oiled shoreline, helps accelerate the cleanup decision making process. 14 refs., 2 tabs., 8 figs

  1. Is flow verification necessary

    International Nuclear Information System (INIS)

    Safeguards test statistics are used in an attempt to detect diversion of special nuclear material. Under assumptions concerning possible manipulation (falsification) of safeguards accounting data, the effects on the statistics due to diversion and data manipulation are described algebraically. A comprehensive set of statistics that is capable of detecting any diversion of material is defined in terms of the algebraic properties of the effects. When the assumptions exclude collusion between persons in two material balance areas, then three sets of accounting statistics are shown to be comprehensive. Two of the sets contain widely known accountancy statistics. One of them does not require physical flow verification - comparisons of operator and inspector data for receipts and shipments. The third set contains a single statistic which does not require physical flow verification. In addition to not requiring technically difficult and expensive flow verification, this single statistic has several advantages over other comprehensive sets of statistics. This algebraic approach as an alternative to flow verification for safeguards accountancy is discussed in this paper

  2. Integrated Java Bytecode Verification

    DEFF Research Database (Denmark)

    Gal, Andreas; Probst, Christian; Franz, Michael

    2005-01-01

    Existing Java verifiers perform an iterative data-flow analysis to discover the unambiguous type of values stored on the stack or in registers. Our novel verification algorithm uses abstract interpretation to obtain definition/use information for each register and stack location in the program...

  3. Budgeting for environmental clean-up of Army bases

    OpenAIRE

    Goette, Herbert

    1996-01-01

    Approved for public release; distribution is unlimited The United States Army obtained congressional approval in 1995 to close or realign 40 installations. These actions create a unique opportunity for the civilian communities surrounding the installations to reuse them to satisfy commercial or community needs. However, future reuse can be impeded by the need for environmental clean-up, which is an expensive business. The current clean-up cost estimate for 32 of the 40 installations is $1 ...

  4. Optimal Discounting of Benefits From Cleanup at Waste Sites

    OpenAIRE

    Lyon, Kenneth S.; Caliendo, Frank

    2005-01-01

    This paper uses a general equilibrium optimal growth model to discuss the role of optimal discounting of future benefits from cleanup at high level toxic waste sites. Cleanup simultaneously generates two streams of benefits. One of these is directly from utility and the other is indirectly from the added productivity of workers. We note that the optimal discount rate is different for these two types of benefits. Along the optimal path, the former are discounted at the rate of time preference ...

  5. An investigation into improving non-NPS cleanup process.

    OpenAIRE

    Whitson, Mark E.

    1992-01-01

    Approved for public release; distribution is unlimited This research investigates the process required to remediate (cleanup) non-National Priorities List (non-NPL) hazardous waste sites. The research addresses the many laws and regulations on hazardous waste cleanup specific to Department of Defence and Navy processes to correct and remediate existing sites. The thesis gathered data through survey of the seven Engineering Field Divisions within the Naval Facilities Command organi...

  6. Solvent degradation and cleanup: a survey and recent ORNL studies

    International Nuclear Information System (INIS)

    This paper surveys the mechanisms for degradation of the tributyl phosphate and diluent components of Purex solvent by acid and radiation, reviews the problems encountered in plant operations resulting from the presence of these degradation products, and discusses methods for minimizing the formation of degradation products and accomplishing their removal. Scrubbing solutions containing sodium carbonate or hydroxylamine salts and secondary cleanup of solvents using solid sorbents are evaluated. Finally, recommendations for improved solvent cleanup are presented. 50 references, 4 figures, 3 tables

  7. Disposal of waste from the cleanup of large areas contaminated as a result of a nuclear accident

    International Nuclear Information System (INIS)

    The report provides an overview of the methodology and technology available to load, transport and dispose of large volumes of contaminated material arising from the cleanup of areas after a nuclear accident and includes data on the planning, implementation, management and costing of such activities. To demonstrate the use of this information, three cleanup and disposal scenarios are examined, ranging from disposal in many small mounds or trenches within the contaminated area to disposal in a large facility away from the plant. As in the two companion reports, it is assumed that the population has been evacuated from the affected area. The report reviews the generic types of low level radioactive waste which are likely to arise from such a cleanup. The report does not deal with the recovery and disposal of intermediate and high level radioactive material on or near the plant site. This material will have to be recovered, packaged, transported and stored on-site or disposed of at an appropriate facility. These operations should be done by specialist teams using shielded or remotely operated equipment. Also not included are methods of in situ stabilization of contamination, for example ploughing to bury the top contaminated layer at a suitable depth. These techniques, which are likely to be widely used in part of the evacuated are, are discussed in IAEA Technical Reports Series No. 300, Vienna, 1989. 50 refs, 18 figs, 4 tabs

  8. FLUOR HANFORD (FH) MAKES CLEANUP A REALITY IN NEARLY 11 YEARS AT HANFORD

    Energy Technology Data Exchange (ETDEWEB)

    GERBER, M.S.

    2007-05-24

    For nearly 11 years, Fluor Hanford has been busy cleaning up the legacy of nuclear weapons production at one of the Department of Energy's (DOE'S) major sites in the United States. As prime nuclear waste cleanup contractor at the vast Hanford Site in southeastern Washington state, Fluor Hanford has changed the face of cleanup. Fluor beginning on October 1, 1996, Hanford Site cleanup was primarily a ''paper exercise.'' The Tri-Party Agreement, officially called the Hanford Federal Facility Agreement and Consent Order - the edict governing cleanup among the DOE, U.S. Environmental Protection Agency (EPA) and Washington state - was just seven years old. Milestones mandated in the agreement up until then had required mainly waste characterization, reporting, and planning, with actual waste remediation activities off in the future. Real work, accessing waste ''in the field'' - or more literally in huge underground tanks, decaying spent fuel POO{approx}{approx}S, groundwater, hundreds of contaminated facilities, solid waste burial grounds, and liquid waste disposal sites -began in earnest under Fluor Hanford. The fruits of labors initiated, completed and/or underway by Fluor Hanford can today be seen across the site. Spent nuclear fuel is buttoned up in secure, dry containers stored away from regional water resources, reactive plutonium scraps are packaged in approved containers, transuranic (TRU) solid waste is being retrieved from burial trenches and shipped offsite for permanent disposal, contaminated facilities are being demolished, contaminated groundwater is being pumped out of aquifers at record rates, and many other inventive solutions are being applied to Hanford's most intransigent nuclear wastes. (TRU) waste contains more than 100 nanocuries per gram, and contains isotopes higher than uranium on the Periodic Table of the Elements. (A nanocurie is one-billionth of a curie.) At the same time, Fluor Hanford

  9. FEFTRA {sup TM} verification. Update 2013

    Energy Technology Data Exchange (ETDEWEB)

    Loefman, J. [VTT Technical Research Centre of Finland, Espoo (Finland); Meszaros, F. [The Relief Lab., Harskut, (Hungary)

    2013-12-15

    FEFTRA is a finite element program package developed at VTT for the analyses of groundwater flow in Posiva's site evaluation programme that seeks a final repository for spent nuclear fuel in Finland. The code is capable of modelling steady-state or transient groundwater flow, solute transport and heat transfer as coupled or separate phenomena. Being a typical research tool used only by its developers, the FEFTRA code lacked long of a competent testing system and precise documentation of the verification of the code. In 2006 a project was launched, in which the objective was to reorganise all the material related to the existing verification cases and place them into the FEFTRA program path under the version-control system. The work also included development of a new testing system, which automatically calculates the selected cases, checks the new results against the old approved results and constructs a summary of the test run. All the existing cases were gathered together, checked and added into the new testing system. The documentation of each case was rewritten with the LATEX document preparation system and added into the testing system in a way that the whole test documentation (this report) could easily be generated in a postscript or pdf-format. The current report is the updated version of the verification report published in 2007. At the moment the report includes mainly the cases related to the testing of the primary result quantities (i.e. hydraulic head, pressure, salinity concentration, temperature). The selected cases, however, represent typical hydrological applications, in which the program package has been and will be employed in the Posiva's site evaluation programme, i.e. the simulations of groundwater flow, solute transport and heat transfer as separate or coupled phenomena. The comparison of the FEFTRA results to the analytical, semianalytical and/or other numerical solutions proves the capability of FEFTRA to simulate such problems

  10. Packaging for Sustainability

    CERN Document Server

    Lewis, Helen; Fitzpatrick, Leanne

    2012-01-01

    The packaging industry is under pressure from regulators, customers and other stakeholders to improve packaging’s sustainability by reducing its environmental and societal impacts. This is a considerable challenge because of the complex interactions between products and their packaging, and the many roles that packaging plays in the supply chain. Packaging for Sustainability is a concise and readable handbook for practitioners who are trying to implement sustainability strategies for packaging. Industry case studies are used throughout the book to illustrate possible applications and scenarios. Packaging for Sustainability draws on the expertise of researchers and industry practitioners to provide information on business benefits, environmental issues and priorities, environmental evaluation tools, design for environment, marketing strategies, and challenges for the future.

  11. Smart packaging for photonics

    Energy Technology Data Exchange (ETDEWEB)

    Smith, J.H.; Carson, R.F.; Sullivan, C.T.; McClellan, G.; Palmer, D.W. [ed.

    1997-09-01

    Unlike silicon microelectronics, photonics packaging has proven to be low yield and expensive. One approach to make photonics packaging practical for low cost applications is the use of {open_quotes}smart{close_quotes} packages. {open_quotes}Smart{close_quotes} in this context means the ability of the package to actuate a mechanical change based on either a measurement taken by the package itself or by an input signal based on an external measurement. One avenue of smart photonics packaging, the use of polysilicon micromechanical devices integrated with photonic waveguides, was investigated in this research (LDRD 3505.340). The integration of optical components with polysilicon surface micromechanical actuation mechanisms shows significant promise for signal switching, fiber alignment, and optical sensing applications. The optical and stress properties of the oxides and nitrides considered for optical waveguides and how they are integrated with micromechanical devices were investigated.

  12. Packaging for meat products

    OpenAIRE

    Vojtíšková, Zuzana

    2014-01-01

    Packaging for meat products Summary Packaging is usually integral to production process in meat industry. The packing has mainly influence on shelf life and quality of meat and meat products. It protects the product from adverse effects such as oxidation, especially fats. In addition it affects transport, storage and serves as a means of communication with customers (logo, marketing benefits, legislation). Significant is also the impact of packaging to keep attractive look of the prod...

  13. Verification of the thermal design of electronic equipment

    Energy Technology Data Exchange (ETDEWEB)

    Hienonen, R.; Karjalainen, M.; Lankinen, R. [VTT Automation, Espoo (Finland). ProTechno

    1997-12-31

    The project `Verification of the thermal design of electronic equipment` studied the methodology to be followed in the verification of thermal design of electronic equipment. This project forms part of the `Cool Electronics` research programme funded by TEKES, the Finnish Technology Development Centre. This project was carried out jointly by VTT Automation, Lappeenranta University of Technology, Nokia Research Center and ABB Industry Oy VSD-Technology. The thermal design of electronic equipment has a significant impact on the cost, reliability, tolerance to different environments, selection of components and materials, and ergonomics of the product. This report describes the method for verification of thermal design. It assesses the goals set for thermal design, environmental requirements, technical implementation of the design, thermal simulation and modelling, and design qualification testing and the measurements needed. The verification method covers all packaging levels of electronic equipment from the system level to the electronic component level. The method described in this report can be used as part of the quality system of a corporation. The report includes information about the measurement and test methods needed in the verification process. Some measurement methods for the temperature, flow and pressure of air are described. (orig.) Published in Finnish VTT Julkaisuja 824. 22 refs.

  14. Remaining Sites Verification Package for the 1607-F1 Sanitary Sewer System (124-F-1) and the 100-F-26:8 (1607-F1) Sanitary Sewer Pipelines Waste Sites. Attachment to Waste Site Reclassification Forms 2004-130 and 2005-004

    International Nuclear Information System (INIS)

    The 100-F-26:8 waste site consisted of the underground pipelines that conveyed sanitary waste water from the 1701-F Gatehouse, 1709-F Fire Station, and the 1720-F Administrative Office to the 1607-F1 septic tank. The site has been remediated and presently exists as an open excavation. In accordance with this evaluation, the verification sampling results support a reclassification of this site to Interim Closed Out. The results of verification sampling demonstrated that residual contaminant concentrations do not preclude any future uses and allow for unrestricted use of shallow zone soils. The results also showed that residual contaminant concentrations are protective of groundwater and the Columbia River

  15. Verification for radiological decommissioning - Lessons learned

    International Nuclear Information System (INIS)

    During the past 10 years, the Environmental Survey and Site Assessment Program (ESSAP) at Oak ridge Associated Universities has performed radiological surveys to confirm the adequacy of cleanup and/or decommissioning actions at sites and facilities where radioactive materials have been handled. These surveys are part of the independent oversight programs of the US Department of Energy (DOE) and the US Nuclear Regulatory Commission (NRC). Results of verification activities have been discouraging. Numerous independent surveys have identified residual contamination requiring further remediation; in some cases, initial decontamination and postremedial action monitoring were totally inadequate. While participating in decommission projects, ESSAP learned valuable lessons and has given this information to regulating agencies and decommissioning sites. The goal of this presentation is to highlight the difficulties encountered by ESSAP in its involvement with NRC and DOE decommissioning projects. Decommissioning projects require teamwork, and success depends to a large degree on the communication, cooperation, and coordination of efforts among the individual organizations involved. This information could be used by organizations involved in future decontamination projects to avoid some of the pitfalls associated with this process

  16. User friendly packaging

    DEFF Research Database (Denmark)

    Geert Jensen, Birgitte

    2010-01-01

    “User-friendly Packaging” aims to create a platform for developing more user-friendly packaging. One intended outcome of the project is a guideline that industry can use in development efforts. The project also points the way for more extended collaboration between companies and design researchers. How...... can design research help industry in packaging innovation?......Most consumers have experienced occasional problems with opening packaging. Tomato sauce from the tinned mackerel splattered all over the kitchen counter, the unrelenting pickle jar lid, and the package of sliced ham that cannot be opened without a knife or a pair of scissors. The research project...

  17. HIRENASD analysis Information Package

    Data.gov (United States)

    National Aeronautics and Space Administration — Updated November 2, 2011 Contains summary information and analysis condition details for the Aeroelastic Prediction Workshop Information plotted in this package is...

  18. Plasma physics plotting package

    International Nuclear Information System (INIS)

    We describe a package of plotting routines that do up to six two- or three-dimensional plots on a frame with minimal loss of resolution. The package now runs on a PDP-10 with PLOT-10 TCS primitives and on a Control Data Corporation-7600 and a Cray-1 with TV80LIB primitives on the National Magnetic Fusion Energy Computer Center network. The package is portable to other graphics systems because only the primitive plot calls are used from the underlying system's graphics package

  19. Requirements Verification Report AN Farm to 200E Waste Transfer System for Project W-314 Tank Farm Restoration and Safe Operations

    Energy Technology Data Exchange (ETDEWEB)

    MCGREW, D.L.

    1999-09-28

    This Requirements Verification Report (RVR) for Project W-314 ''AN Farm to 200E Waste Transfer System'' package provides documented verification of design compliance to all the applicable Project Development Specification (PDS) requirements. Additional PDS requirements verification will be performed during the project's procurement, construction, and testing phases, and the RVR will be updated to reflect this information as appropriate.

  20. Distorted Fingerprint Verification System

    Directory of Open Access Journals (Sweden)

    Divya KARTHIKAESHWARAN

    2011-01-01

    Full Text Available Fingerprint verification is one of the most reliable personal identification methods. Fingerprint matching is affected by non-linear distortion introduced in fingerprint impression during the image acquisition process. This non-linear deformation changes both the position and orientation of minutiae. The proposed system operates in three stages: alignment based fingerprint matching, fuzzy clustering and classifier framework. First, an enhanced input fingerprint image has been aligned with the template fingerprint image and matching score is computed. To improve the performance of the system, a fuzzy clustering based on distance and density has been used to cluster the feature set obtained from the fingerprint matcher. Finally a classifier framework has been developed and found that cost sensitive classifier produces better results. The system has been evaluated on fingerprint database and the experimental result shows that system produces a verification rate of 96%. This system plays an important role in forensic and civilian applications.

  1. Environmental Cleanup of the East Tennessee Technology Park Year One - Execution with Certainty SM - 13120

    International Nuclear Information System (INIS)

    On August 1, 2011, URS - CH2M Oak Ridge LLC (UCOR) began its five-year, $1.4 billion cleanup of the East Tennessee Technology Park (ETTP), located on the U.S. Department of Energy's (DOE) Oak Ridge Reservation in Tennessee. UCOR will close out cleanup operations that began in 1998 under a previous contract. When the Contract Base scope of work [1] is completed in 2016, the K-25 gaseous diffusion building will have been demolished and all waste dispositioned, demolition will have started on the K-27 gaseous diffusion building, all contact-handled and remote-handled transuranic waste in inventory (approximately 500 cubic meters) will have been transferred to the Transuranic Waste Processing Center, previously designated 'No-Path-To-Disposition Waste' will have been dispositioned to the extent possible, and UCOR will have managed DOE Office of Environmental Management (EM)- owned facilities at ETTP, Oak Ridge National Laboratory (ORNL), and the Y-12 National Security Complex in a safe and cost-effective manner. Since assuming its responsibilities as the ETTP cleanup contractor, UCOR has completed its life-cycle Performance Measurement Baseline; received its Earned Value Management System (EVMS) certification; advanced the deactivation and demolition (D and D) of the K-25 gaseous diffusion building; recovered and completed the Tank W-1A and K-1070-B Burial Ground remediation projects; characterized, packaged, and shipped contact-handled transuranic waste to the Transuranic Waste Processing Center; disposed of more than 90,000 cubic yards of cleanup waste while managing the Environmental Management Waste Management Facility (EMWMF); and provided operations, surveillance, and maintenance activities at DOE EM facilities at ETTP, ORNL, and the Y-12 National Security Complex. Project performance as of December 31, 2012 has been excellent: - Cost Performance Index - 1.06; - Schedule Performance Index - 1.02. At the same time, since safety is the foundation of all cleanup

  2. Material integrity verification radar

    International Nuclear Information System (INIS)

    The International Atomic Energy Agency (IAEA) has the need for verification of 'as-built' spent fuel-dry storage containers and other concrete structures. The IAEA has tasked the Special Technologies Laboratory (STL) to fabricate, test, and deploy a stepped-frequency Material Integrity Verification Radar (MIVR) system to nondestructively verify the internal construction of these containers. The MIVR system is based on previously deployed high-frequency, ground penetrating radar (GPR) systems that have been developed by STL for the U.S. Department of Energy (DOE). Whereas GPR technology utilizes microwave radio frequency energy to create subsurface images, MTVR is a variation for which the medium is concrete instead of soil. The purpose is to nondestructively verify the placement of concrete-reinforcing materials, pipes, inner liners, and other attributes of the internal construction. The MIVR system underwent an initial field test on CANDU reactor spent fuel storage canisters at Atomic Energy of Canada Limited (AECL), Chalk River Laboratories, Ontario, Canada, in October 1995. A second field test at the Embalse Nuclear Power Plant in Embalse, Argentina, was completed in May 1996. The DOE GPR also was demonstrated at the site. Data collection and analysis were performed for the Argentine National Board of Nuclear Regulation (ENREN). IAEA and the Brazilian-Argentine Agency for the Control and Accounting of Nuclear Material (ABACC) personnel were present as observers during the test. Reinforcing materials were evident in the color, two-dimensional images produced by the MIVR system. A continuous pattern of reinforcing bars was evident and accurate estimates on the spacing, depth, and size were made. The potential uses for safeguard applications were jointly discussed. The MIVR system, as successfully demonstrated in the two field tests, can be used as a design verification tool for IAEA safeguards. A deployment of MIVR for Design Information Questionnaire (DIQ

  3. Robust verification analysis

    Science.gov (United States)

    Rider, William; Witkowski, Walt; Kamm, James R.; Wildey, Tim

    2016-02-01

    We introduce a new methodology for inferring the accuracy of computational simulations through the practice of solution verification. We demonstrate this methodology on examples from computational heat transfer, fluid dynamics and radiation transport. Our methodology is suited to both well- and ill-behaved sequences of simulations. Our approach to the analysis of these sequences of simulations incorporates expert judgment into the process directly via a flexible optimization framework, and the application of robust statistics. The expert judgment is systematically applied as constraints to the analysis, and together with the robust statistics guards against over-emphasis on anomalous analysis results. We have named our methodology Robust Verification. Our methodology is based on utilizing multiple constrained optimization problems to solve the verification model in a manner that varies the analysis' underlying assumptions. Constraints applied in the analysis can include expert judgment regarding convergence rates (bounds and expectations) as well as bounding values for physical quantities (e.g., positivity of energy or density). This approach then produces a number of error models, which are then analyzed through robust statistical techniques (median instead of mean statistics). This provides self-contained, data and expert informed error estimation including uncertainties for both the solution itself and order of convergence. Our method produces high quality results for the well-behaved cases relatively consistent with existing practice. The methodology can also produce reliable results for ill-behaved circumstances predicated on appropriate expert judgment. We demonstrate the method and compare the results with standard approaches used for both code and solution verification on well-behaved and ill-behaved simulations.

  4. Secure Location Verification

    OpenAIRE

    Becker, Georg T.; Lo, Sherman C.; De Lorenzo, David S.; Enge, Per K.; Paar, Christof

    2010-01-01

    The use of location based services has increased significantly over the last few years. However, location information is only sparsely used as a security mechanism. One of the reasons for this is the lack of location verification techniques with global coverage. Recently, a new method for authenticating signals from Global Navigation Satellite Systems(GNSS) such as GPS or Galileo has been proposed. In this paper, we analyze the security of this signal authentication mechanism and show how it ...

  5. Distorted Fingerprint Verification System

    OpenAIRE

    Divya KARTHIKAESHWARAN; Jeyalatha SIVARAMAKRISHNAN

    2011-01-01

    Fingerprint verification is one of the most reliable personal identification methods. Fingerprint matching is affected by non-linear distortion introduced in fingerprint impression during the image acquisition process. This non-linear deformation changes both the position and orientation of minutiae. The proposed system operates in three stages: alignment based fingerprint matching, fuzzy clustering and classifier framework. First, an enhanced input fingerprint image has been aligned with the...

  6. TFE verification program

    Science.gov (United States)

    1990-03-01

    The information presented herein will include evaluated test data, design evaluations, the results of analyses and the significance of results. The program objective is to demonstrate the technology readiness of a Thermionic Fuel Element (TFE) suitable for use as the basic element in a thermionic reactor with electric power output in the 0.5 to 5.0 MW(e) range, and a full-power life of 7 years. The TF Verification Program builds directly on the technology and data base developed in the 1960s and 1970s in an AEC/NASA program, and in the SP-100 program conducted in 1983, 1984 and 1985. In the SP-100 program, the attractive features of thermionic power conversion technology were recognized but concern was expressed over the lack of fast reactor irradiation data. The TFE Verification Program addresses this concern. The general logic and strategy of the program to achieve its objectives is shown. Five prior programs form the basis for the TFE Verification Program: (1) AEC/NASA program of the 1960s and early 1970; (2) SP-100 concept development program; (3) SP-100 thermionic technology program; (4) Thermionic irradiations program in TRIGA in FY-88; and (5) Thermionic Program in 1986 and 1987.

  7. Particulate hot gas stream cleanup technical issues

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-09-01

    This is the eleventh in a series of quarterly reports describing the activities performed under Contract No. DE-AC21-94MC31160. Analyses of Hot Gas Stream Cleanup (HGCU) ashes and descriptions of filter performance address aspects of filter operation that are apparently linked to the characteristics of the collected ash or the performance of the ceramic bed filter elements. Task 1 is designed to generate a data base of the key characteristics of ashes collected from operating advanced particle filters (APFS) and to relate these ash properties to the operation and performance of these filters. Task 2 concerns testing and failure analysis of ceramic filter elements. Under Task 1 during the past quarter, analyses were completed on samples obtained during a site visit to the Power Systems Development Facility (PSDF). Analyses are in progress on ash samples from the Advanced Particulate Filter (APF) at the Pressurized Fluidized-Bed Combustor (PFBC) that was in operation at Tidd and ash samples from the Pressurized Circulating Fluid Bed (PCFB) system located at Karhula, Finland. An additional analysis was performed on a particulate sample from the Transport Reactor Demonstration Unit (TRDU) located at the University of North Dakota Energy and Environmental Research Center. A manuscript and poster were prepared for presentation at the Advanced Coal-Based Power and Environmental Systems `97 Conference scheduled for July 22 - 24, 1997. A summary of recent project work covering the mechanisms responsible for ash deposit consolidation and ash bridging in APF`s collecting PFB ash was prepared and presented at FETC-MGN in early July. The material presented at that meeting is included in the manuscript prepared for the Contractor`s Conference and also in this report. Task 2 work during the past quarter included mechanical testing and microstructural examination of Schumacher FT20 and Pall 326 as- manufactured, after 540 hr in service at Karhula, and after 1166 hr in service at

  8. Advanced fingerprint verification software

    Science.gov (United States)

    Baradarani, A.; Taylor, J. R. B.; Severin, F.; Maev, R. Gr.

    2016-05-01

    We have developed a fingerprint software package that can be used in a wide range of applications from law enforcement to public and private security systems, and to personal devices such as laptops, vehicles, and door- locks. The software and processing units are a unique implementation of new and sophisticated algorithms that compete with the current best systems in the world. Development of the software package has been in line with the third generation of our ultrasonic fingerprinting machine1. Solid and robust performance is achieved in the presence of misplaced and low quality fingerprints.

  9. Worldwide analysis of marine oil spill cleanup cost factors

    International Nuclear Information System (INIS)

    The many factors that influence oil spill response costs were discussed with particular emphasis on how spill responses differ around the world because of differing cultural values, socio-economic factors and labor costs. This paper presented an analysis of marine oil spill cleanup costs based on the country, proximity to shoreline, spill size, oil type, degree of shoreline oiling and cleanup methodology. The objective was to determine how each factor impacts per-unit cleanup costs. Near-shore spills and in-port spills were found to be 4-5 times more expensive to clean than offshore spills. Responses to spills of heavy fuels also cost 10 times more than for lighter crudes and diesel. Spill responses for spills under 30 tonnes are 10 times more costly than on a per-unit basis, for spills of 300 tonnes. A newly developed modelling technique that can be used on different types of marine spills was described. It is based on updated cost data acquired from case studies of more than 300 spills in 40 countries. The model determines a per-unit cleanup cost estimation by taking into consideration oil type, location, spill size, cleanup methodology, and shoreline oiling. It was concluded that the actual spill costs are totally dependent on the actual circumstances of the spill. 13 refs., 10 tabs., 3 figs

  10. Consolidating federal facility cleanup: Some pros and cons

    International Nuclear Information System (INIS)

    It has been suggested that Congress establish a permanent, full-time, independent national commission for radioactive waste management activities at DOE's Nuclear Weapons Complex. DOE regulates certain aspects of its treatment, storage, and disposal of radioactive waste by orders that are not promulgated by ''notice and comment'' or other procedures in the Administration Procedures Act. Because many agencies are not legally and technologically structured to handle their own cleanup problems, these activities might be conducted by one entity that can share information and staff among these agencies. There are rational arguments for both sides of this issue. Some of the advantages of such an organization include: focusing Congress's attention on an integrated federal facility cleanup instead of a fragmented, agency by agency approach, and an ability to prioritize cleanup decisions among agencies. Some significant obstacles include: reluctance by Congress and the executive branch to create any new bureaucracy at a time of budget deficits, and a loss of momentum from the progress already being made by the agencies. Given that more than $9 billion was proposed for FY 93 alone for federal facilities' cleanup programs and that decades will pass before all problems are addressed, it is appropriate to consider new approaches to environmental cleanup. This paper begins the dialogue about new ways to improve decision-making and government spending

  11. Waste package scenario modelling

    International Nuclear Information System (INIS)

    UK Nirex has supported a programme of work to develop models describing the post-closure evolution of intermediate-level waste packages with the objectives of: - providing support and justification for the parameters and representations used in performance assessment models; - informing future model development and packaging advice. Scenarios for the potential evolution of a waste package were developed and modelled taking explicit account of waste package heterogeneity and the time-dependence of the physical and chemical characteristics of the system. The modelling work highlighted the treatment of organic complexants and the representation of physical containment as two areas in which the impacts of time dependence and package scale heterogeneity might be particularly significant. A subsequent study of the impact of organic complexants emphasised the importance of heterogeneity in package inventory in determining the radionuclide release from the near field. The degree of containment afforded by the wasteform and the waste container has been investigated as part of a study to develop a preliminary understanding of the mixing scales within the repository. The study suggests that the most important control on the release of radionuclides from the waste packages is the integrity of the waste encapsulation grout. Interactions between neighbouring packages are to be expected, but the degree to which homogeneous (well mixed) conditions develop may be limited in both time and space. (author)

  12. WASTE PACKAGE TRANSPORTER DESIGN

    International Nuclear Information System (INIS)

    The purpose of this Design Analysis is to develop preliminary design of the waste package transporter used for waste package (WP) transport and related functions in the subsurface repository. This analysis refines the conceptual design that was started in Phase I of the Viability Assessment. This analysis supports the development of a reliable emplacement concept and a retrieval concept for license application design. The scope of this analysis includes the following activities: (1) Assess features of the transporter design and evaluate alternative design solutions for mechanical components. (2) Develop mechanical equipment details for the transporter. (3) Prepare a preliminary structural evaluation for the transporter. (4) Identify and recommend the equipment design for waste package transport and related functions. (5) Investigate transport equipment interface tolerances. This analysis supports the development of the waste package transporter for the transport, emplacement, and retrieval of packaged radioactive waste forms in the subsurface repository. Once the waste containers are closed and accepted, the packaged radioactive waste forms are termed waste packages (WP). This terminology was finalized as this analysis neared completion; therefore, the term disposal container is used in several references (i.e., the System Description Document (SDD)) (Ref. 5.6). In this analysis and the applicable reference documents, the term ''disposal container'' is synonymous with ''waste package''

  13. WASTE PACKAGE TRANSPORTER DESIGN

    Energy Technology Data Exchange (ETDEWEB)

    D.C. Weddle; R. Novotny; J. Cron

    1998-09-23

    The purpose of this Design Analysis is to develop preliminary design of the waste package transporter used for waste package (WP) transport and related functions in the subsurface repository. This analysis refines the conceptual design that was started in Phase I of the Viability Assessment. This analysis supports the development of a reliable emplacement concept and a retrieval concept for license application design. The scope of this analysis includes the following activities: (1) Assess features of the transporter design and evaluate alternative design solutions for mechanical components. (2) Develop mechanical equipment details for the transporter. (3) Prepare a preliminary structural evaluation for the transporter. (4) Identify and recommend the equipment design for waste package transport and related functions. (5) Investigate transport equipment interface tolerances. This analysis supports the development of the waste package transporter for the transport, emplacement, and retrieval of packaged radioactive waste forms in the subsurface repository. Once the waste containers are closed and accepted, the packaged radioactive waste forms are termed waste packages (WP). This terminology was finalized as this analysis neared completion; therefore, the term disposal container is used in several references (i.e., the System Description Document (SDD)) (Ref. 5.6). In this analysis and the applicable reference documents, the term ''disposal container'' is synonymous with ''waste package''.

  14. The DYNAMIC program package

    International Nuclear Information System (INIS)

    The most important constituents and capacities of the practice-oriented program package DYNAMIC are explained. The versatility of the package in dealing with problems of structural dynamics is shown by examples (seismic qualification of SF6 switchgear equipment, turbine building of a BWR). The examples explain applications in the fields of construction engineering and electromechanics. (orig./HP)

  15. Continuous verification using multimodal biometrics.

    Science.gov (United States)

    Sim, Terence; Zhang, Sheng; Janakiraman, Rajkumar; Kumar, Sandeep

    2007-04-01

    Conventional verification systems, such as those controlling access to a secure room, do not usually require the user to reauthenticate himself for continued access to the protected resource. This may not be sufficient for high-security environments in which the protected resource needs to be continuously monitored for unauthorized use. In such cases, continuous verification is needed. In this paper, we present the theory, architecture, implementation, and performance of a multimodal biometrics verification system that continuously verifies the presence of a logged-in user. Two modalities are currently used--face and fingerprint--but our theory can be readily extended to include more modalities. We show that continuous verification imposes additional requirements on multimodal fusion when compared to conventional verification systems. We also argue that the usual performance metrics of false accept and false reject rates are insufficient yardsticks for continuous verification and propose new metrics against which we benchmark our system. PMID:17299225

  16. Waste package performance analysis

    International Nuclear Information System (INIS)

    A performance assessment model for multiple barrier packages containing unreprocessed spent fuel has been applied to several package designs. The resulting preliminary assessments were intended for use in making decisions about package development programs. A computer model called BARIER estimates the package life and subsequent rate of release of selected nuclides. The model accounts for temperature, pressure (and resulting stresses), bulk and localized corrosion, and nuclide retardation by the backfill after water intrusion into the waste form. The assessment model assumes a post-closure, flooded, geologic repository. Calculations indicated that, within the bounds of model assumptions, packages could last for several hundred years. Intact backfills of appropriate design may be capable of nuclide release delay times on the order of 107 yr for uranium, plutonium, and americium. 8 references, 6 figures, 9 tables

  17. Advanced flip chip packaging

    CERN Document Server

    Lai, Yi-Shao; Wong, CP

    2013-01-01

    Advanced Flip Chip Packaging presents past, present and future advances and trends in areas such as substrate technology, material development, and assembly processes. Flip chip packaging is now in widespread use in computing, communications, consumer and automotive electronics, and the demand for flip chip technology is continuing to grow in order to meet the need for products that offer better performance, are smaller, and are environmentally sustainable. This book also: Offers broad-ranging chapters with a focus on IC-package-system integration Provides viewpoints from leading industry executives and experts Details state-of-the-art achievements in process technologies and scientific research Presents a clear development history and touches on trends in the industry while also discussing up-to-date technology information Advanced Flip Chip Packaging is an ideal book for engineers, researchers, and graduate students interested in the field of flip chip packaging.

  18. Quantum money with classical verification

    International Nuclear Information System (INIS)

    We propose and construct a quantum money scheme that allows verification through classical communication with a bank. This is the first demonstration that a secure quantum money scheme exists that does not require quantum communication for coin verification. Our scheme is secure against adaptive adversaries - this property is not directly related to the possibility of classical verification, nevertheless none of the earlier quantum money constructions is known to possess it

  19. Quantum money with classical verification

    Energy Technology Data Exchange (ETDEWEB)

    Gavinsky, Dmitry [NEC Laboratories America, Princeton, NJ (United States)

    2014-12-04

    We propose and construct a quantum money scheme that allows verification through classical communication with a bank. This is the first demonstration that a secure quantum money scheme exists that does not require quantum communication for coin verification. Our scheme is secure against adaptive adversaries - this property is not directly related to the possibility of classical verification, nevertheless none of the earlier quantum money constructions is known to possess it.

  20. Verification and validation for induction heating

    Energy Technology Data Exchange (ETDEWEB)

    Lam, Kin [Los Alamos National Laboratory; Tippetts, Trevor B [Los Alamos National Laboratory; Allen, David W [NON LANL

    2008-01-01

    Truchas is a software package being developed at LANL within the Telluride project for predicting the complex physical processes in metal alloy casting. The software was designed to be massively parallel, multi-material, multi-physics, and to run on 3D, fully unstructured meshes. This work describes a Verification and Validation assessment of Truchas for simulating the induction heating phase of a casting process. We used existing data from a simple experiment involving the induction heating of a graphite cylinder, as graphite is a common material used for mold assemblies. Because we do not have complete knowledge of all the conditions and properties in this experiment (as is the case in many other experiments), we performed a parameter sensitivity study, modeled the uncertainties of the most sensitive parameters, and quantified how these uncertainties propagate to the Truchas output response. A verification analysis produced estimates of the numerical error of the Truchas solution to our computational model. The outputs from Truchas runs with randomly sampled parameter values were used for the validation study.

  1. Verification and validation of control system software

    International Nuclear Information System (INIS)

    The following guidelines are proposed for verification and validation (V ampersand V) of nuclear power plant control system software: (a) use risk management to decide what and how much V ampersand V is needed; (b) classify each software application using a scheme that reflects what type and how much V ampersand V is needed; (c) maintain a set of reference documents with current information about each application; (d) use Program Inspection as the initial basic verification method; and (e) establish a deficiencies log for each software application. The following additional practices are strongly recommended: (a) use a computer-based configuration management system to track all aspects of development and maintenance; (b) establish reference baselines of the software, associated reference documents, and development tools at regular intervals during development; (c) use object-oriented design and programming to promote greater software reliability and reuse; (d) provide a copy of the software development environment as part of the package of deliverables; and (e) initiate an effort to use formal methods for preparation of Technical Specifications. The paper provides background information and reasons for the guidelines and recommendations. 3 figs., 3 tabs

  2. Scalable Techniques for Formal Verification

    CERN Document Server

    Ray, Sandip

    2010-01-01

    This book presents state-of-the-art approaches to formal verification techniques to seamlessly integrate different formal verification methods within a single logical foundation. It should benefit researchers and practitioners looking to get a broad overview of the spectrum of formal verification techniques, as well as approaches to combining such techniques within a single framework. Coverage includes a range of case studies showing how such combination is fruitful in developing a scalable verification methodology for industrial designs. This book outlines both theoretical and practical issue

  3. Core seismic methods verification report

    International Nuclear Information System (INIS)

    Information on HTGR reactor core seismic requirements is presented concerning element properties and code parameters; correlation and verification of the codes; sensitivity studies; and application to design

  4. Deriving cleanup guidelines for radionuclides at Brookhaven National Laboratory

    International Nuclear Information System (INIS)

    Past activities at Brookhaven National Laboratory (BNL) resulted in soil and groundwater contamination. As a result, BNL was designated a Superfund site under the Comprehensive Environmental Response Compensation and Liability Act (CERCLA). BNL's Office of Environmental Restoration (OER) is overseeing environmental restoration activities at the Laboratory. With the exception of radium, there are no regulations or guidelines to establish cleanup guidelines for radionuclides in soils at BNL. BNL must derive radionuclide soil cleanup guidelines for a number of Operable Units (OUs) and Areas of Concern (AOCs). These guidelines are required by DOE under a proposed regulation for radiation protection of public health and the environment as well as to satisfy the requirements of CERCLA. The objective of this report is to propose a standard approach to deriving risk-based cleanup guidelines for radionuclides in soil at BNL. Implementation of the approach is briefly discussed

  5. United States Policies for Cleanup at Radioactively Contaminated Sites

    International Nuclear Information System (INIS)

    The United States Environmental Protection Agency (EPA) Office of Superfund Remediation and Technology Innovation is responsible for implementing the long term (non-emergency) portion of a key law regulating cleanup: the Comprehensive Environmental Response, Compensation and Liability Act, CERCLA, nicknamed ‘Superfund.’ This paper provides a brief overview of the approach used by EPA to conduct Superfund cleanups at contaminated sites, including those that are contaminated with radionuclides, and to ensure protection of human health and the environment. The theme emphasized throughout the paper is that within the Superfund remediation framework, radioactive contamination is dealt with in a manner consistent with chemical contamination, except to account for the technical differences between radionuclides and chemicals. This consistency is important since at every radioactively contaminated site being addressed under Superfund’s primary programme for long term cleanup (the National Priorities List), chemical contamination is also present. (author)

  6. Coolant clean-up method in PWR type reactors

    International Nuclear Information System (INIS)

    Purpose: To perform coolant clean-up while climinating the need of replacing boric acid with plant primary coolants and using anionic exchange resins in which the amount of Cl anionic exchange resins as impurities is decreased. Method: OH type anionic exchange resins are previously treated with an aqueous boric acid not containing radioactivity at a place other than the equipment for use (that is desalting tower) into boric acid type anionic ion exchange resins and, thereafter, the boric acid type anionic exchange resins are filled into a desalting tower of the clean-up system to perform primary coolant clean-up. In this case, since the resins can be used directly for the purpose without performing boric acid replacement after charging into the equipment for use, the procedures in the plant being in operation can be saved. (Yoshino, Y.)

  7. Interim Site Assessment and Clean-up Guidebook

    International Nuclear Information System (INIS)

    In April 1995 an Interim Site Investigation and Clean-up Guidebook (for petroleum hydrocarbon and volatile organic compound impacted sites) was developed for public use. The purpose of the Guidebook was to offer a new approach to the site cleanup process: one that reduces time, cuts costs, and establishes a defined endpoint for investigations and cleanup actions. The Guidebook provided a matrix to screen for low-risk contaminated sites. After a year of use, the Guidebook was revised in May 1996. The most notable change was in the Petroleum Hydrocarbon Section and the modification of the screening table for petroleum hydrocarbon contaminated sites. The changes considered the strong influence of lithology on contaminant transport and recognized the large attenuation of the long chain, heavy oil and tar, hydrocarbons in soils

  8. Uranium mill tailings cleanup: Federal leadership at last

    International Nuclear Information System (INIS)

    The Department of Energy has proposed legislation that would allow it to enter into cooperative agreements with various States to clean up residual radioactive materials--commonly called uranium mill tailings--at 22 inactive uranium mills. About 25 million tons of mill tailings have accumulated at these sites since the 1940s. GAO analyzed the need for, and adequacy of, the proposed legislation and recommends that the cleanup program be endorsed. While the Federal Government has no apparent legal responsibility for such a cleanup, it does have a moral responsibility since the mills primarily produced uranium for Federal programs. Further, it is the only organization able to undertake such a cleanup program on a comprehensive basis. GAO also suggests several areas where the proposed legislation could be strengthened

  9. Deriving cleanup guidelines for radionuclides at Brookhaven National Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Meinhold, A.F.; Morris, S.C.; Dionne, B.; Moskowitz, P.D.

    1997-01-01

    Past activities at Brookhaven National Laboratory (BNL) resulted in soil and groundwater contamination. As a result, BNL was designated a Superfund site under the Comprehensive Environmental Response Compensation and Liability Act (CERCLA). BNL`s Office of Environmental Restoration (OER) is overseeing environmental restoration activities at the Laboratory. With the exception of radium, there are no regulations or guidelines to establish cleanup guidelines for radionuclides in soils at BNL. BNL must derive radionuclide soil cleanup guidelines for a number of Operable Units (OUs) and Areas of Concern (AOCs). These guidelines are required by DOE under a proposed regulation for radiation protection of public health and the environment as well as to satisfy the requirements of CERCLA. The objective of this report is to propose a standard approach to deriving risk-based cleanup guidelines for radionuclides in soil at BNL. Implementation of the approach is briefly discussed.

  10. UTILIZING THE RIGHT MIX OF ENVIRONMENTAL CLEANUP TECHNOLOGIES

    International Nuclear Information System (INIS)

    The Savannah River Site (SRS) Figure 1 is a 310-square-mile United States Department of Energy nuclear facility located along the Savannah River near Aiken, South Carolina. During operations, which started in 1951, hazardous substances (chemicals and radionuclides) were released to the environment. The releases occurred as a result of inadvertent spills and waste disposal in unlined pits and basins which was common practice before environmental regulations existed. The hazardous substances have migrated to the vadose zone and groundwater in many areas of the SRS, resulting in 515 waste units that are required by environmental regulations, to undergo characterization and, if needed, remediation. In the initial years of the SRS environmental cleanup program (early 1990s), the focus was to use common technologies (such as pump and treat, air stripping, excavation and removal) that actively and tangibly removed contamination. Exclusive use of these technologies required continued and significant funding while often failing to meet acceptable clean-up goals and objectives. Recognizing that a more cost-effective approach was needed, SRS implemented new and complementary remediation methods focused on active and passive technologies targeted to solve specific remediation problems. Today, SRS uses technologies such as chemical/pH-adjusting injection, phytoremediation, underground cutoff walls, dynamic underground stripping, soil fracturing, microbial degradation, baroballs, electrical resistance heating, soil vapor extraction, and microblowers to more effectively treat contamination at lower costs. Additionally, SRS's remediation approach cost effectively maximizes cleanup as SRS works proactively with multiple regulatory agencies. Using GIS, video, animation, and graphics, SRS is able to provide an accurate depiction of the evolution of SRS groundwater and vadose zone cleanup activities to convince stakeholders and regulators of the effectiveness of various cleanup

  11. Cleanup/stimulation of a horizontal wellbore using propellants

    Energy Technology Data Exchange (ETDEWEB)

    Rougeot, J.E.; Lauterbach, K.A.

    1993-01-01

    This report documents the stimulation/cleanup of a horizontal well bore (Wilson 25) using propellants. The Wilson 25 is a Bartlesville Sand well located in the Flatrock Field, Osage County, Oklahoma. The Wilson 25 was drilled to determine if horizontal drilling could be used as a means to economically recover primary oil that had been left in place in a mostly abandoned oil field because of the adverse effects of water coning. Pump testing of the Wilson 25 horizontal well bore before cleanup or stimulation produced 6 barrels of oil and .84 barrels of water per day. The high percentage of daily oil production to total daily fluid production indicated that the horizontal well bore had accessed potentially economical oil reserves if the fluid production rate could be increased by performing a cleanup/stimulation treatment. Propellants were selected as an inexpensive means to stimulate and cleanup the near well bore area in a uniform manner. The ignition of a propellant creates a large volume of gas which penetrates the formation, creating numerous short cracks through which hydrocarbons can travel into the well bore. More conventional stimulation/cleanup techniques were either significantly more expensive, less likely to treat uniformly, or could not be confined to the near well bore area. Three different propellant torpedo designs were tested with a total of 304' of horizontal well bore being shot and producible. The initial test shot caused 400' of the horizontal well bore to become plugged off, and subsequently it could not be production tested. The second and third test shots were production tested, with the oil production being increased 458% and 349%, respectively, on a per foot basis. The Wilson 25 results indicate that a propellant shot treatment is an economically viable means to cleanup/stimulate a horizontal well bore.

  12. Cleanup standards for inland oil spills : a review

    International Nuclear Information System (INIS)

    There are a wide range of issues that should be addressed in the development of oil spill cleanup criteria and standards, yet there is currently no clear and concise decision procedure that can be applied by a spill response management team. This paper presented three inland spill cases which demonstrated different parts of the spectrum of cleanup standards. These case study examples showed that there is a progression with increasing levels of concern and increasing levels of treatment or cleanup effort. The first case study described the removal of mobile oil in a remote location. It involved a series of large crude oil spills in 1994 from sections of the Vosei-Golovnye pipeline in the Komi Republic of Russia. The second case study described multiple standards for the removal of oil residues and oiled vegetation in a populated rural region. It involved a spill of 29,000 bbl of mixed crude oil and condensate in January 2000 from the OSSA II pipeline at the Rio Desaguadero river crossing in Bolivia. The third case study described the restoration of a salmon spawning stream to a lowest effects concentration. It involved a gasoline release, explosion and fire that resulted from the Olympic Pipe Line rupture in June 1999 in Bellingham, Washington. Each of the three response operations was based on different objectives and different cleanup standards for the completion of the cleanup. The process by which criteria are developed for inland oil spills was described. The choice of treatment ranges from no treatment to a zero tolerance position. Deciding which measure is appropriate is a social and political process that is not based on science alone. While soil and water quality standards have been established by government agencies, these are intended mostly for chronic situations rather than for one-time events such as oil spills. Almost all assessments of an appropriate cleanup program consider the net environmental benefits (NEB) and risk associated with different

  13. UTILIZING THE RIGHT MIX OF ENVIRONMENTAL CLEANUP TECHNOLOGIES

    Energy Technology Data Exchange (ETDEWEB)

    Bergren, C; Wade Whitaker, W; Mary Flora, M

    2007-05-25

    The Savannah River Site (SRS) Figure 1 is a 310-square-mile United States Department of Energy nuclear facility located along the Savannah River near Aiken, South Carolina. During operations, which started in 1951, hazardous substances (chemicals and radionuclides) were released to the environment. The releases occurred as a result of inadvertent spills and waste disposal in unlined pits and basins which was common practice before environmental regulations existed. The hazardous substances have migrated to the vadose zone and groundwater in many areas of the SRS, resulting in 515 waste units that are required by environmental regulations, to undergo characterization and, if needed, remediation. In the initial years of the SRS environmental cleanup program (early 1990s), the focus was to use common technologies (such as pump and treat, air stripping, excavation and removal) that actively and tangibly removed contamination. Exclusive use of these technologies required continued and significant funding while often failing to meet acceptable clean-up goals and objectives. Recognizing that a more cost-effective approach was needed, SRS implemented new and complementary remediation methods focused on active and passive technologies targeted to solve specific remediation problems. Today, SRS uses technologies such as chemical/pH-adjusting injection, phytoremediation, underground cutoff walls, dynamic underground stripping, soil fracturing, microbial degradation, baroballs, electrical resistance heating, soil vapor extraction, and microblowers to more effectively treat contamination at lower costs. Additionally, SRS's remediation approach cost effectively maximizes cleanup as SRS works proactively with multiple regulatory agencies. Using GIS, video, animation, and graphics, SRS is able to provide an accurate depiction of the evolution of SRS groundwater and vadose zone cleanup activities to convince stakeholders and regulators of the effectiveness of various cleanup

  14. Historical research in the Hanford site waste cleanup

    International Nuclear Information System (INIS)

    This paper will acquaint the audience with role of historical research in the Hanford Site waste cleanup - the largest waste cleanup endeavor ever undertaken in human history. There were no comparable predecessors to this massive waste remediation effort, but the Hanford historical record can provide a partial road map and guide. It can be, and is, a useful tool in meeting the goal of a successful, cost-effective, safe and technologically exemplary waste cleanup. The Hanford historical record is rich and complex. Yet, it poses difficult challenges, in that no central and complete repository or data base exists, records contain obscure code words and code numbers, and the measurement systems and terminology used in the records change many times over the years. Still, these records are useful to the current waste cleanup in technical ways, and in ways that extend beyond a strictly scientific aspect. Study and presentations of Hanford Site history contribute to the huge educational and outreach tasks of helping the Site's work force deal with 'culture change' and become motivated for the cleanup work that is ahead, and of helping the public and the regulators to place the events at Hanford in the context of WWII and the Cold War. This paper traces historical waste practices and policies as they changed over the years at the Hanford Site, and acquaints the audience with the generation of the major waste streams of concern in Hanford Site cleanup today. It presents original, primary-source research into the waste history of the Hanford Site. The earliest, 1940s knowledge base, assumptions and calculations about radioactive and chemical discharges, as discussed in the memos, correspondence and reports of the original Hanford Site (then Hanford Engineer Works) builders and operators, are reviewed. The growth of knowledge, research efforts, and subsequent changes in Site waste disposal policies and practices are traced. Examples of the strengths and limitations of the

  15. Needs for Risk Informing Environmental Cleanup Decision Making - 13613

    International Nuclear Information System (INIS)

    This paper discusses the needs for risk informing decision making by the U.S. Department of Energy (DOE) Office of Environmental Management (EM). The mission of the DOE EM is to complete the safe cleanup of the environmental legacy brought about from the nation's five decades of nuclear weapons development and production and nuclear energy research. This work represents some of the most technically challenging and complex cleanup efforts in the world and is projected to require the investment of billions of dollars and several decades to complete. Quantitative assessments of health and environmental risks play an important role in work prioritization and cleanup decisions of these challenging environmental cleanup and closure projects. The risk assessments often involve evaluation of performance of integrated engineered barriers and natural systems over a period of hundreds to thousands of years, when subject to complex geo-environmental transformation processes resulting from remediation and disposal actions. The requirement of resource investments for the cleanup efforts and the associated technical challenges have subjected the EM program to continuous scrutiny by oversight entities. Recent DOE reviews recommended application of a risk-informed approach throughout the EM complex for improved targeting of resources. The idea behind this recommendation is that by using risk-informed approaches to prioritize work scope, the available resources can be best utilized to reduce environmental and health risks across the EM complex, while maintaining the momentum of the overall EM cleanup program at a sustainable level. In response to these recommendations, EM is re-examining its work portfolio and key decision making with risk insights for the major sites. This paper summarizes the review findings and recommendations from the DOE internal reviews, discusses the needs for risk informing the EM portfolio and makes an attempt to identify topics for R and D in integrated

  16. Accelerated cleanup Initiatives Putting the Acceleration Plans into Action

    International Nuclear Information System (INIS)

    This paper describes project successes during the last year and presents strategies for accomplishing work required to accelerate waste retrieval, treatment and closure of 177 large underground waste tanks at the Hanford Site. The tanks contain approximately 53 million gallons of liquid, sludge, and solid waste resulting from decades of national defense production. The Hanford Site is a 560 square-mile area in southeastern Washington State. One of the nation's largest rivers, the Columbia River, flows through the site and within seven miles of the waste tanks. The US. Department of Energy (DOE) Office of River Protection and CH2M HILL Hanford Group, Inc. (CH2M HILL) drew upon the recommendations in the DOE's Top-To-Bottom Review and the ideas that emerged from the Cleanup Challenges and Constraints Team (C3T) when creating new initiatives last fall in accelerated tank cleanup. The initiatives reflect discussions and planning during the last year by the DOE, regulatory,agencies, Hanford stakeholders, and CH2M HILL on how to accelerate tank cleanup and closure. The initiatives focus on near-term risk reduction, deployment of proven cleanup technologies, and completing the feed delivery and waste storage systems needed to support Hanford's Waste Treatment Plant. Working with the Office of River Protection, CH2M HILL is changing the way it does business to align with the new focus on accelerated tank cleanup initiatives. A key concept of this new approach is to deploy simple, proven technologies whenever possible to accomplish program goals. Finding existing technologies and evaluating whether they can be applied to or adapted to Hanford tank cleanup provide the best chance for success in achieving treatment of all of Hanford's tank waste by 2028

  17. The radioactive materials packaging handbook: Design, operations, and maintenance

    Energy Technology Data Exchange (ETDEWEB)

    Shappert, L.B.; Bowman, S.M. [Oak Ridge National Lab., TN (United States); Arnold, E.D. [Lockheed Martin Energy Systems, Oak Ridge, TN (United States)] [and others

    1998-08-01

    As part of its required activities in 1994, the US Department of Energy (DOE) made over 500,000 shipments. Of these shipments, approximately 4% were hazardous, and of these, slightly over 1% (over 6,400 shipments) were radioactive. Because of DOE`s cleanup activities, the total quantities and percentages of radioactive material (RAM) that must be moved from one site to another is expected to increase in the coming years, and these materials are likely to be different than those shipped in the past. Irradiated fuel will certainly be part of the mix as will RAM samples and waste. However, in many cases these materials will be of different shape and size and require a transport packaging having different shielding, thermal, and criticality avoidance characteristics than are currently available. This Handbook provides guidance on the design, testing, certification, and operation of packages for these materials.

  18. The radioactive materials packaging handbook: Design, operations, and maintenance

    International Nuclear Information System (INIS)

    As part of its required activities in 1994, the US Department of Energy (DOE) made over 500,000 shipments. Of these shipments, approximately 4% were hazardous, and of these, slightly over 1% (over 6,400 shipments) were radioactive. Because of DOE's cleanup activities, the total quantities and percentages of radioactive material (RAM) that must be moved from one site to another is expected to increase in the coming years, and these materials are likely to be different than those shipped in the past. Irradiated fuel will certainly be part of the mix as will RAM samples and waste. However, in many cases these materials will be of different shape and size and require a transport packaging having different shielding, thermal, and criticality avoidance characteristics than are currently available. This Handbook provides guidance on the design, testing, certification, and operation of packages for these materials

  19. Bioremediation: environmental clean-up through pathway engineering.

    Science.gov (United States)

    Singh, Shailendra; Kang, Seung Hyun; Mulchandani, Ashok; Chen, Wilfred

    2008-10-01

    Given the immense risk posed by widespread environmental pollution by inorganic and organic chemicals, novel methods of decontamination and clean-up are required. Owing to the relatively high cost and the non-specificity of conventional techniques, bioremediation is a promising alternative technology for pollutant clean-up. Advances in bioremediation harness molecular, genetic, microbiology, and protein engineering tools and rely on identification of novel metal-sequestering peptides, rational and irrational pathway engineering, and enzyme design. Recent advances have been made for enhanced inorganic chemical remediation and organic chemical degradation using various pathway-engineering approaches and these are discussed in this review. PMID:18760355

  20. Sodium cleanup system of fast reactor NPP (retrospectively - prospective outlook)

    International Nuclear Information System (INIS)

    When reasoned the coolant cleanup system of perspective fast reactor NPPs the traditional methods of coolant purification (cold traps, sorbents for cesium) as well as possibility to use hot traps for sodium purification from oxygen have been analyzed. It is shown that cold trap must be a mandatory element of cleanup system built in tank; hot traps can provide sodium coolant purification from oxygen during NPP nominal condition. Recommendations on further lines of work for improving cold traps characteristics are given, and further lines of work for hot traps parameters optimization are considered

  1. High-level verification

    CERN Document Server

    Lerner, Sorin; Kundu, Sudipta

    2011-01-01

    Given the growing size and heterogeneity of Systems on Chip (SOC), the design process from initial specification to chip fabrication has become increasingly complex. This growing complexity provides incentive for designers to use high-level languages such as C, SystemC, and SystemVerilog for system-level design. While a major goal of these high-level languages is to enable verification at a higher level of abstraction, allowing early exploration of system-level designs, the focus so far for validation purposes has been on traditional testing techniques such as random testing and scenario-based

  2. Advanced formal verification

    CERN Document Server

    Drechsler, Rolf

    2007-01-01

    Preface. Contributing Authors. Introduction; R. Drechsler. 1. Formal Verification. 2. Challenges. 3. Contributions to this Book. 1: What SAT-Solvers Can and Cannot Do; E. Goldberg. 1. Introduction. 2. Hard Equivalence Checking CNF Formulas. 3. Stable Sets of Points. 2: Advancements in Mixed BDD and SAT Techniques; G. Cabodi, S. Quer. 1. Introduction. 2. Background. 3. Comparing SAT and BDD Approaches: Are they Different? 4. Decision Diagrams as a Slave Engine in General SAT: Clause Compression by Means of ZBDDs. 5. Decision Diagram Preprocessing and Circuit-Based SAT. 6. Using SAT in Symbolic

  3. Verification of LHS distributions.

    Energy Technology Data Exchange (ETDEWEB)

    Swiler, Laura Painton

    2006-04-01

    This document provides verification test results for normal, lognormal, and uniform distributions that are used in Sandia's Latin Hypercube Sampling (LHS) software. The purpose of this testing is to verify that the sample values being generated in LHS are distributed according to the desired distribution types. The testing of distribution correctness is done by examining summary statistics, graphical comparisons using quantile-quantile plots, and format statistical tests such as the Chisquare test, the Kolmogorov-Smirnov test, and the Anderson-Darling test. The overall results from the testing indicate that the generation of normal, lognormal, and uniform distributions in LHS is acceptable.

  4. Safety Analysis Report - Packages, 9965, 9968, 9972-9975 Packages

    International Nuclear Information System (INIS)

    This Safety Analysis Report for Packaging (SARP) documents the analysis and testing performed on four type B Packages: the 9972, 9973, 9974, and 9975 packages. Because all four packages have similar designs with very similar performance characteristics, all of them are presented in a single SARP. The performance evaluation presented in this SARP documents the compliance of the 9975 package with the regulatory safety requirements. Evaluations of the 9972, 9973, and 9974 packages support that of the 9975. To avoid confusion arising from the inclusion of four packages in a single document, the text segregates the data for each package in such a way that the reader interested in only one package can progress from Chapter 1 through Chapter 9. The directory at the beginning of each chapter identifies each section that should be read for a given package. Sections marked ''all'' are generic to all packages

  5. Hermeticity of electronic packages

    CERN Document Server

    Greenhouse, Hal; Romenesco, Bruce

    2011-01-01

    This is a book about the integrity of sealed packages to resist foreign gases and liquids penetrating the seal or an opening (crack) in the packageùespecially critical to the reliability and longevity of electronics. The author explains how to predict the reliability and the longevity of the packages based on leak rate measurements and the assumptions of impurities. Non-specialists in particular will benefit from the author's long involvement in the technology. Hermeticity is a subject that demands practical experience, and solving one problem does not necessarily give one the background to so

  6. Hermeticity of electronic packages

    CERN Document Server

    Greenhouse, Hal

    2000-01-01

    This is a book about the integrity of sealed packages to resist foreign gases and liquids penetrating the seal or an opening (crack) in the package-especially critical to the reliability and longevity of electronics. The author explains how to predict the reliability and the longevity of the packages based on leak rate measurements and the assumptions of impurities. Non-specialists in particular will benefit from the author's long involvement in the technology. Hermeticity is a subject that demands practical experience, and solving one problem does not necessarily give one the background to so

  7. Remaining Sites Verification Package for the 1607-F1 Sanitary Sewer System (124-F-1) and the 100-F-26:8 (1607-F1) Sanitary Sewer Pipelines Waste Sites. Attachment to Waste Site Reclassification Forms 2004-130 and 2005-004

    International Nuclear Information System (INIS)

    The 1607-F1 Sanitary Sewer System (124-F-1), consisted of a septic tank, drain field, and associated pipelines that received sanitary waste water from the 1701-F Gatehouse, 1709-F Fire Station, and the 1720-F Administrative Office via the 100-F-26:8 pipelines. The septic tank required remedial action based on confirmatory sampling. In accordance with this evaluation, the verification sampling results support a reclassification of this site to Interim Closed Out. The results of verification sampling show that residual contaminant concentrations do not preclude any future uses and allow for unrestricted use of shallow zone soils. The results also demonstrate that residual contaminant concentrations are protective of groundwater and the Columbia River

  8. Clinical Verification of Homeopathy

    Directory of Open Access Journals (Sweden)

    Michel Van Wassenhoven

    2011-07-01

    Full Text Available The world is changing! This is certainly true regarding the homeopathic practice and access to homeopathic medicine. Therefore our first priority at the ECH-LMHI [1] has been to produce a yearly report on the scientific framework of homeopathy. In the 2010 version a new chapter about epidemic diseases has been added including the Leptospirosis survey on the Cuban population. A second priority has been to review the definition of the homeopathic medicines respecting the new framework generated by the official registration procedure and the WHO report. We are working now on a documented (Materia Medica and provings list of homeopathic remedies to facilitate the registration of our remedies. The new challenges are: first of all more good research proposals and as such more funding (possible through ISCHI + Blackie Foundation as examples [2]; international acceptance of new guidelines for proving and clinical verification of homeopathic symptoms (Proposals are ready for discussion; total reconsideration of the homeopathic repertories including results of the clinical verification of the symptoms. The world is changing, we are part of the world and changes are needed also for homeopathy!

  9. HDL to verification logic translator

    Science.gov (United States)

    Gambles, J. W.; Windley, P. J.

    1992-01-01

    The increasingly higher number of transistors possible in VLSI circuits compounds the difficulty in insuring correct designs. As the number of possible test cases required to exhaustively simulate a circuit design explodes, a better method is required to confirm the absence of design faults. Formal verification methods provide a way to prove, using logic, that a circuit structure correctly implements its specification. Before verification is accepted by VLSI design engineers, the stand alone verification tools that are in use in the research community must be integrated with the CAD tools used by the designers. One problem facing the acceptance of formal verification into circuit design methodology is that the structural circuit descriptions used by the designers are not appropriate for verification work and those required for verification lack some of the features needed for design. We offer a solution to this dilemma: an automatic translation from the designers' HDL models into definitions for the higher-ordered logic (HOL) verification system. The translated definitions become the low level basis of circuit verification which in turn increases the designer's confidence in the correctness of higher level behavioral models.

  10. London 2012 packaging guidelines

    OpenAIRE

    2013-01-01

    These guidelines are intended to provide supplemental advice to suppliers and licensees regarding the provisions of the LOCOG Sustainable Sourcing Code that relate to packaging design and materials selection.

  11. Dual Use Packaging Project

    Data.gov (United States)

    National Aeronautics and Space Administration — NASA calculation that over a kg of packaging waste are generated per day for a 6 member crew. This represents over 1.5 metric tons of waste during a Mars mission....

  12. FLEXIBLE FOOD PACKAGING LABORATORY

    Data.gov (United States)

    Federal Laboratory Consortium — This laboratory contains equipment to fabricate and test prototype packages of many types and sizes (e.g., bags, pouches, trays, cartons, etc.). This equipment can...

  13. CH Packaging Program Guidance

    International Nuclear Information System (INIS)

    The purpose of this document is to provide the technical requirements for preparation for use, operation, inspection, and maintenance of a Transuranic Package Transporter Model II (TRUPACT-II), a HalfPACT Shipping Package, and directly related components. This document complies with the minimum requirements as specified in TRUPACT-II Safety Analysis Report for Packaging (SARP), HalfPACT SARP, and Nuclear Regulatory Commission (NRC) Certificates of Compliance (C of C) 9218 and 9279, respectively. In the event there is a conflict between this document and the SARP or C of C, the SARP and/or C of C shall govern. C of Cs state: ''each package must be prepared for shipment and operated in accordance with the procedures described in Chapter 7.0, Operating Procedures, of the application.'' They further state: ''each package must be tested and maintained in accordance with the procedures described in Chapter 8.0, Acceptance Tests and Maintenance Program of the Application.'' Chapter 9.0 of the SAR P charges the WIPP Management and Operation (M and O) contractor with assuring packaging is used in accordance with the requirements of the C of C. Because the packaging is NRC-approved, users need to be familiar with 10 CFR 71.11. Any time a user suspects or has indications that the conditions of approval in the C of C were not met, the Carlsbad Field Office (CBFO) shall be notified immediately. CBFO will evaluate the issue and notify the NRC if required. This document details the instructions to be followed to operate, maintain, and test the TRUPACT-II and HalfPACT packaging. The intent of these instructions is to standardize these operations. All users will follow these instructions or equivalent instructions that assure operations are safe and meet the requirements of the SARPs

  14. CH Packaging Program Guidance

    International Nuclear Information System (INIS)

    The purpose of this document is to provide the technical requirements for preparation for use, operation, inspection, and maintenance of a Transuranic Package Transporter Model II (TRUPACT-II), a HalfPACT shipping package, and directly related components. This document complies with the minimum requirements as specified in the TRUPACT-II Safety Analysis Report for Packaging (SARP), HalfPACT SARP, and Nuclear Regulatory Commission (NRC) Certificates of Compliance (C of C) 9218 and 9279, respectively. In the event of a conflict between this document and the SARP or C of C, the C of C shall govern. The C of Cs state: ''each package must be prepared for shipment and operated in accordance with the procedures described in Chapter 7.0, Operating Procedures, of the application.'' They further state: ''each package must be tested and maintained in accordance with the procedures described in Chapter 8.0, Acceptance Tests and Maintenance Program of the Application.'' Chapter 9.0 of the SARP charges the WIPP management and operating (M and O) contractor with assuring packaging is used in accordance with the requirements of the C of C. Because the packaging is NRC-approved, users need to be familiar with 10 CFR 71.11. Any time a user suspects or has indications that the conditions of approval in the C of C were not met, the Carlsbad Field Office (CBFO) shall be notified immediately. CBFO will evaluate the issue and notify the NRC if required. This document provides the instructions to be followed to operate, maintain, and test the TRUPACT-II and HalfPACT packaging. The intent of these instructions is to standardize operations. All users will follow these instructions or equivalent instructions that assure operations are safe and meet the requirements of the SARPs

  15. The ENSDF Java Package

    International Nuclear Information System (INIS)

    A package of computer codes has been developed to process and display nuclear structure and decay data stored in the ENSDF (Evaluated Nuclear Structure Data File) library. The codes were written in an object-oriented fashion using the java language. This allows for an easy implementation across multiple platforms as well as deployment on web pages. The structure of the different java classes that make up the package is discussed as well as several different implementations

  16. Packaging sustainability assessment

    OpenAIRE

    Rubio Peregrina, Silvia

    2015-01-01

    Packaging is an essential part of the majority of products in the actual market. Therefore, packaging design must draw attention to improve its sustainable character in order to satisfy consumers, enhance its environmental performance and keep economic costs to a minimum. Measuring packaging’s sustainability would provide consumers information so as to raise awareness and, moreover, a tool that would help companies to find product weaknesses to be improved. For that purpose, this projec...

  17. Battery packaging - Technology review

    International Nuclear Information System (INIS)

    This paper gives a brief overview of battery packaging concepts, their specific advantages and drawbacks, as well as the importance of packaging for performance and cost. Production processes, scaling and automation are discussed in detail to reveal opportunities for cost reduction. Module standardization as an additional path to drive down cost is introduced. A comparison to electronics and photovoltaics production shows 'lessons learned' in those related industries and how they can accelerate learning curves in battery production

  18. Lush Cosmetics packaging

    OpenAIRE

    Hudson, Frazer

    2014-01-01

    Frazer Hudson – Lush Cosmetics Packaging Commissioned by Suzie Hackney for Lush Cosmetics via illustration Agency - Debut Art - February 2014 I was approached in February 2014 via my London based Illustration agency Debut Art to create packaging illustration designs for the high street retailer and International cosmetics brand ‘Lush’. The illustrations would be used on an octagonal gift box set and be positioned amongst other bespoke gift box set designs within Lush Cosme...

  19. Planning for cleanup of large areas contaminated as a result of a nuclear accident

    International Nuclear Information System (INIS)

    The cleanup of large areas of contaminated as a result of an accident at a nuclear facility could cost hundreds of millions of dollars and cause inconvenience to the public. Such a cleanup programme would be undertaken only if the detriment to health and social life resulting from cleanup activities would be less than that resulting from further exposures. All reasonable means should, however, be used to minimize the costs and detriment to humans of such a cleanup. For such a cleanup to be carried out safely, efficiently and as quickly as possible under adverse conditions requires: Good preliminary and final planning; A cleanup team having a well defined management structure and well trained personnel; and Suitable cleanup methods and equipment and cleanup criteria. 35 refs, 8 figs, 5 tabs

  20. Technical papers presented at a DOE meeting on criteria for cleanup of transuranium elements in soil

    International Nuclear Information System (INIS)

    Transuranium element soil contamination cleanup experience gained from nuclear weapons accidents and cleanup at Eniwetok Atoll was reviewed. Presentations have been individually abstracted for inclusion in the data base

  1. Technical papers presented at a DOE meeting on criteria for cleanup of transuranium elements in soil

    Energy Technology Data Exchange (ETDEWEB)

    1984-09-01

    Transuranium element soil contamination cleanup experience gained from nuclear weapons accidents and cleanup at Eniwetok Atoll was reviewed. Presentations have been individually abstracted for inclusion in the data base. (ACR)

  2. Generic System Verilog Universal Verification Methodology Based Reusable Verification Environment for Efficient Verification of Image Signal Processing IPS/SOCS

    Directory of Open Access Journals (Sweden)

    Abhishek Jain

    2013-01-01

    Full Text Available In this paper, we present Generic System Verilog Universal Verification Methodology based ReusableVerification Environment for efficient verification of Image Signal Processing IP’s/SoC’s. With the tightschedules on all projects it is important to have a strong verification methodology which contributes toFirst Silicon Success. Deploy methodologies which enforce full functional coverage and verification ofcorner cases through pseudo random test scenarios is required. Also, standardization of verification flow isneeded. Previously, inside imaging group of ST, Specman (e/Verilog based Verification Environment forIP/Subsystem level verification and C/C++/Verilog based Directed Verification Environment for SoC LevelVerification was used for Functional Verification. Different Verification Environments were used at IPlevel and SoC level. Different Verification/Validation Methodologies were used for SoC Verification acrossmultiple sites. Verification teams were also looking for the ways how to catch bugs early in the designcycle? Thus, Generic System Verilog Universal Verification Methodology (UVM based ReusableVerification Environment is required to avoid the problem of having so many methodologies and provides astandard unified solution which compiles on all tools.

  3. Generic System Verilog Universal Verification Methodology Based Reusable Verification Environment for Efficient Verification of Image Signal Processing IPS/SOCS

    Directory of Open Access Journals (Sweden)

    Abhishek Jain

    2012-12-01

    Full Text Available In this paper, we present Generic System Verilog Universal Verification Methodology based Reusable Verification Environment for efficient verification of Image Signal Processing IP’s/SoC’s. With the tight schedules on all projects it is important to have a strong verification methodology which contributes to First Silicon Success. Deploy methodologies which enforce full functional coverage and verification of corner cases through pseudo random test scenarios is required. Also, standardization of verification flow is needed. Previously, inside imaging group of ST, Specman (e/Verilog based Verification Environment forIP/Subsystem level verification and C/C++/Verilog based Directed Verification Environment for SoC Level Verification was used for Functional Verification. Different Verification Environments were used at IP level and SoC level. Different Verification/Validation Methodologies were used for SoC Verification across multiple sites. Verification teams were also looking for the ways how to catch bugs early in the design cycle? Thus, Generic System Verilog Universal Verification Methodology (UVM based Reusable Verification Environment is required to avoid the problem of having so many methodologies and provides a standard unified solution which compiles on all tools.

  4. ITER task T299 (1996) : fuel cleanup system demonstration tests

    International Nuclear Information System (INIS)

    The objective of this task is to demonstrate processes for efficient cleanup and detritiation of the plasma exhaust. In this subtask, the objectives were to provide further design data on the HITEX process, and to build and demonstrate 2-stage high-detritiation HITEX performance. (author). 9 refs., 1 tab., 11 figs

  5. Enewetak fact book (a resume of pre-cleanup information)

    International Nuclear Information System (INIS)

    The book contains a group of short treatises on the precleanup condition of the islands in Enewetak Atoll. Their purpose was to provide brief guidance to the radiological history and radiological condition of the islands for use in cleanup of the atoll

  6. Enewetak fact book (a resume of pre-cleanup information)

    Energy Technology Data Exchange (ETDEWEB)

    Bliss, W. (comp.)

    1982-09-01

    The book contains a group of short treatises on the precleanup condition of the islands in Enewetak Atoll. Their purpose was to provide brief guidance to the radiological history and radiological condition of the islands for use in cleanup of the atoll. (ACR)

  7. Cleanup at Los Alamos National Laboratory - the challenges - 9493

    Energy Technology Data Exchange (ETDEWEB)

    Stiger, Susan G [Los Alamos National Laboratory; Hargis, Kenneth M [Los Alamos National Laboratory; Graham, Michael J [Los Alamos National Laboratory; Rael, George J [NNSL/LASO

    2008-01-01

    This paper provides an overview of environmental cleanup at the Los Alamos National Laboratory (LANL) and some of the unique aspects and challenges. Cleanup of the 65-year old Department of Energy Laboratory is being conducted under a RCRA Consent Order with the State of New Mexico. This agreement is one of the most recent cleanup agreements signed in the DOE complex and was based on lessons learned at other DOE sites. A number of attributes create unique challenges for LANL cleanup -- the proximity to the community and pueblos, the site's topography and geology, and the nature of LANL's on-going missions. This overview paper will set the stage for other papers in this session, including papers that present: Plans to retrieve buried waste at Material Disposal Area B, across the street from oen of Los Alamos' commercial districts and the local newspaper; Progress to date and joint plans with WIPP for disposal of the remaining inventory of legacy transuranic waste; Reviews of both groundwater and surface water contamination and the factors complicating both characterization and remediation; Optimizing the disposal of low-level radioactive waste from ongoing LANL missions; A stakeholder environmental data transparency project (RACER), with full public access to all available information on contamination at LANL, and A description of the approach to waste processing cost recovery from the programs that generate hazardous and radioactive waste at LANL.

  8. Cleanup at the Los Alamos National Laboratory - The Challenges

    International Nuclear Information System (INIS)

    This paper provides an overview of environmental cleanup at the Los Alamos National Laboratory (LANL) and some of the unique aspects and challenges. Cleanup of the 65-year old Department of Energy laboratory is being conducted under a RCRA Consent Order with the State of New Mexico. This agreement is one of the most recent cleanup agreements signed in the DOE complex and was based on lessons learned at other DOE sites. A number of attributes create unique challenges for LANL cleanup - the proximity to the community and pueblos, the site's topography and geology, and the nature of LANL's on-going missions. This overview paper will set the stage for other papers in this session, including papers that present: - Plans to retrieve buried waste at Material Disposal Area B, across the street from one of Los Alamos' commercial districts and the local newspaper; - Progress to date and joint plans with WIPP for disposal of the remaining inventory of legacy transuranic waste; - Reviews of both groundwater and surface water contamination and the factors complicating both characterization and remediation; - Optimizing the disposal of low-level radioactive waste from ongoing LANL missions; - A stakeholder environmental data transparency project (RACER), with full public access to all available information on contamination at LANL, and - A description of the approach to waste processing cost recovery from the programs that generate hazardous and radioactive waste at LANL. (authors)

  9. Modeling of vapour generator for clean-up separator module

    International Nuclear Information System (INIS)

    233U clean-up process plays an important role in the thorium fuel cycle. This process is based on laser isotope separation (LIS) using atomic vapour, where the impure 233U (containing 232U) is evaporated in high vacuum environment. The vapour is interacted with laser beam to selectively ionize 232U, which is removed by electrostatic means

  10. A restructuring of CF package for MIDAS computer code

    Energy Technology Data Exchange (ETDEWEB)

    Park, S. H.; Kim, K. R.; Kim, D. H.; Cho, S. W. [KAERI, Taejon (Korea, Republic of)

    2004-07-01

    CF package, which evaluates user-specified 'control functions' and applies them to define or control various aspects of computation, has been restructured for the MIDAS computer code. MIDAS is being developed as an integrated severe accident analysis code with a user-friendly graphical user interface and modernized data structure. To do this, data transferring methods of current MELCOR code are modified and adopted into the CF package. The data structure of the current MELCOR code using FORTRAN77 causes a difficult grasping of meaning of the variables as well as waste of memory, difficulty is more over because its data is location information of other package's data due to characteristics of CF package. New features of FORTRAN90 make it possible to allocate the storage dynamically and to use the user-defined data type, which lead to an efficient memory treatment and an easy understanding of the code. Restructuring of the CF package addressed in this paper includes module development, subroutine modification, and treats MELGEN, which generates data file, as well as MELCOR, which is processing a calculation. The verification has been done by comparing the results of the modified code with those from the existing code. As the trends are similar to each other, it hints that the same approach could be extended to the entire code package. It is expected that code restructuring will accelerate the code domestication thanks to direct understanding of each variable and easy implementation of modified or newly developed models.

  11. A restructuring of CF package for MIDAS computer code

    International Nuclear Information System (INIS)

    CF package, which evaluates user-specified 'control functions' and applies them to define or control various aspects of computation, has been restructured for the MIDAS computer code. MIDAS is being developed as an integrated severe accident analysis code with a user-friendly graphical user interface and modernized data structure. To do this, data transferring methods of current MELCOR code are modified and adopted into the CF package. The data structure of the current MELCOR code using FORTRAN77 causes a difficult grasping of meaning of the variables as well as waste of memory, difficulty is more over because its data is location information of other package's data due to characteristics of CF package. New features of FORTRAN90 make it possible to allocate the storage dynamically and to use the user-defined data type, which lead to an efficient memory treatment and an easy understanding of the code. Restructuring of the CF package addressed in this paper includes module development, subroutine modification, and treats MELGEN, which generates data file, as well as MELCOR, which is processing a calculation. The verification has been done by comparing the results of the modified code with those from the existing code. As the trends are similar to each other, it hints that the same approach could be extended to the entire code package. It is expected that code restructuring will accelerate the code domestication thanks to direct understanding of each variable and easy implementation of modified or newly developed models

  12. CH Packaging Program Guidance

    International Nuclear Information System (INIS)

    The purpose of this document is to provide the technical requirements for preparation for use, operation, inspection, and maintenance of a Transuranic Package Transporter Model II (TRUPACT-II), a HalfPACT shipping package, and directly related components. This document complies with the minimum requirements as specified in the TRUPACT-II Safety Analysis Report for Packaging (SARP), HalfPACT SARP, and U.S. Nuclear Regulatory Commission (NRC) Certificates of Compliance (C of C) 9218 and 9279, respectively. In the event of a conflict between this document and the SARP or C of C, the C of C shall govern. The C of Cs state: 'each package must be prepared for shipment and operated in accordance with the procedures described in Chapter 7.0, Operating Procedures, of the application.' They further state: 'each package must be tested and maintained in accordance with the procedures described in Chapter 8.0, Acceptance Tests and Maintenance Program of the Application.' Chapter 9.0 of the SARP charges the U.S. Department of Energy (DOE) or the Waste Isolation Pilot Plant (WIPP) management and operating (M and O) contractor with assuring packaging is used in accordance with the requirements of the C of C. Because the packaging is NRC-approved, users need to be familiar with Title 10 Code of Federal Regulations (CFR) 71.8. Any time a user suspects or has indications that the conditions of approval in the C of C were not met, the Carlsbad Field Office (CBFO) shall be notified immediately. The CBFO will evaluate the issue and notify the NRC if required. In accordance with 10 CFR Part 71, certificate holders, packaging users, and contractors or subcontractors who use, design, fabricate, test, maintain, or modify the packaging shall post copies of (1) 10 CFR Part 21 regulations, (2) Section 206 of the Energy Reorganization Act of 1974, and (3) NRC Form 3, Notice to Employees. These documents must be posted in a conspicuous location where the activities subject to these regulations

  13. RH Packaging Program Guidance

    Energy Technology Data Exchange (ETDEWEB)

    Washington TRU Solutions LLC

    2006-11-07

    The purpose of this program guidance document is to provide the technical requirements for use, operation, inspection, and maintenance of the RH-TRU 72-B Waste Shipping Package and directly related components. This document complies with the requirements as specified in the RH-TRU 72-B Safety Analysis Report for Packaging (SARP), and Nuclear Regulatory Commission (NRC) Certificate of Compliance (C of C) 9212. If there is a conflict between this document and the SARP and/or C of C, the C of C shall govern. The C of C states: "...each package must be prepared for shipment and operated in accordance with the procedures described in Chapter 7.0, Operating Procedures, of the application." It further states: "...each package must be tested and maintained in accordance with the procedures described in Chapter 8.0, Acceptance Tests and Maintenance Program of the Application." Chapter 9.0 of the SARP tasks the Waste Isolation Pilot Plant (WIPP) Management and Operating (M&O) Contractor with assuring the packaging is used in accordance with the requirements of the C of C. Because the packaging is NRC-approved, users need to be familiar with 10 Code of Federal Regulations (CFR) §71.8, "Deliberate Misconduct." Any time a user suspects or has indications that the conditions of approval in the C of C were not met, the U.S. Department of Energy (DOE) Carlsbad Field Office (CBFO) shall be notified immediately. CBFO will evaluate the issue and notify the NRC if required. In accordance with 10 CFR Part 71, "Packaging and Transportation of Radioactive Material," certificate holders, packaging users, and contractors or subcontractors who use, design, fabricate, test, maintain, or modify the packaging shall post copies of (1) 10 CFR Part 21, "Reporting of Defects and Noncompliance," regulations, (2) Section 206 of the Energy Reorganization Act of 1974, and (3) NRC Form 3, Notice to Employees. These documents must be posted in a conspicuous location where the activities subject to

  14. CH Packaging Program Guidance

    Energy Technology Data Exchange (ETDEWEB)

    None, None

    2009-06-01

    The purpose of this document is to provide the technical requirements for preparation for use, operation, inspection, and maintenance of a Transuranic Package Transporter Model II (TRUPACT-II), a HalfPACT shipping package, and directly related components. This document complies with the minimum requirements as specified in the TRUPACT-II Safety Analysis Report for Packaging (SARP), HalfPACT SARP, and U.S. Nuclear Regulatory Commission (NRC) Certificates of Compliance (C of C) 9218 and 9279, respectively. In the event of a conflict between this document and the SARP or C of C, the C of C shall govern. The C of Cs state: "each package must be prepared for shipment and operated in accordance with the procedures described in Chapter 7.0, Operating Procedures, of the application." They further state: "each package must be tested and maintained in accordance with the procedures described in Chapter 8.0, Acceptance Tests and Maintenance Program of the Application." Chapter 9.0 of the SARP charges the U.S. Department of Energy (DOE) or the Waste Isolation Pilot Plant (WIPP) management and operating (M&O) contractor with assuring packaging is used in accordance with the requirements of the C of C. Because the packaging is NRC-approved, users need to be familiar with Title 10 Code of Federal Regulations (CFR) §71.8. Any time a user suspects or has indications that the conditions of approval in the C of C were not met, the Carlsbad Field Office (CBFO) shall be notified immediately. The CBFO will evaluate the issue and notify the NRC if required. In accordance with 10 CFR Part 71, certificate holders, packaging users, and contractors or subcontractors who use, design, fabricate, test, maintain, or modify the packaging shall post copies of (1) 10 CFR Part 21 regulations, (2) Section 206 of the Energy Reorganization Act of 1974, and (3) NRC Form 3, Notice to Employees. These documents must be posted in a conspicuous location where the activities subject to these regulations are

  15. CH Packaging Program Guidance

    Energy Technology Data Exchange (ETDEWEB)

    None, None

    2008-09-11

    The purpose of this document is to provide the technical requirements for preparation for use, operation, inspection, and maintenance of a Transuranic Package Transporter Model II (TRUPACT-II), a HalfPACT shipping package, and directly related components. This document complies with the minimum requirements as specified in the TRUPACT-II Safety Analysis Report for Packaging (SARP), HalfPACT SARP, and U.S. Nuclear Regulatory Commission (NRC) Certificates of Compliance (C of C) 9218 and 9279, respectively. In the event of a conflict between this document and the SARP or C of C, the C of C shall govern. The C of Cs state: "each package must be prepared for shipment and operated in accordance with the procedures described in Chapter 7.0, Operating Procedures, of the pplication." They further state: "each package must be tested and maintained in accordance with the procedures described in Chapter 8.0, Acceptance Tests and Maintenance Program of the Application." Chapter 9.0 of the SARP charges the U.S. Department of Energy (DOE) or the Waste Isolation Pilot Plant (WIPP) management and operating (M&O) contractor with assuring packaging is used in accordance with the requirements of the C of C. Because the packaging is NRC-approved, users need to be familiar with Title 10 Code of Federal Regulations (CFR) §71.8. Any time a user suspects or has indications that the conditions of approval in the C of C were not met, the Carlsbad Field Office (CBFO) shall be notified immediately. The CBFO will evaluate the issue and notify the NRC if required. In accordance with 10 CFR Part 71, certificate holders, packaging users, and contractors or subcontractors who use, design, fabricate, test, maintain, or modify the packaging shall post copies of (1) 10 CFR Part 21 regulations, (2) Section 206 of the Energy Reorganization Act of 1974, and (3) NRC Form 3, Notice to Employees. These documents must be posted in a conspicuous location where the activities subject to these regulations are

  16. RH Packaging Program Guidance

    Energy Technology Data Exchange (ETDEWEB)

    Washington TRU Solutions LLC

    2008-01-12

    The purpose of this program guidance document is to provide the technical requirements for use, operation, inspection, and maintenance of the RH-TRU 72-B Waste Shipping Package (also known as the "RH-TRU 72-B cask") and directly related components. This document complies with the requirements as specified in the RH-TRU 72-B Safety Analysis Report for Packaging (SARP), and Nuclear Regulatory Commission (NRC) Certificate of Compliance (C of C) 9212. If there is a conflict between this document and the SARP and/or C of C, the C of C shall govern. The C of C states: "...each package must be prepared for shipment and operated in accordance with the procedures described in Chapter 7.0, Operating Procedures, of the application." It further states: "...each package must be tested and maintained in accordance with the procedures described in Chapter 8.0, Acceptance Tests and Maintenance Program of the Application." Chapter 9.0 of the SARP tasks the Waste Isolation Pilot Plant (WIPP) Management and Operating (M&O) Contractor with assuring the packaging is used in accordance with the requirements of the C of C. Because the packaging is NRC-approved, users need to be familiar with Title 10 Code of Federal Regulations (CFR) §71.8, "Deliberate Misconduct." Any time a user suspects or has indications that the conditions of approval in the C of C were not met, the U.S. Department of Energy (DOE) Carlsbad Field Office (CBFO) shall be notified immediately. The CBFO will evaluate the issue and notify the NRC if required.In accordance with 10 CFR Part 71, "Packaging and Transportation of Radioactive Material," certificate holders, packaging users, and contractors or subcontractors who use, design, fabricate, test, maintain, or modify the packaging shall post copies of (1) 10 CFR Part 21, "Reporting of Defects and Noncompliance," regulations, (2) Section 206 of the Energy Reorganization Act of 1974, and (3) NRC Form 3, Notice to Employees. These documents must be posted in a

  17. Verification of Simulation Tools

    International Nuclear Information System (INIS)

    Before qualifying a simulation tool, the requirements shall first be clearly identified, i.e.: - What type of study needs to be carried out? - What phenomena need to be modeled? This phase involves writing a precise technical specification. Once the requirements are defined, the most adapted product shall be selected from the various software options available on the market. Before using a particular version of a simulation tool to support the demonstration of nuclear safety studies, the following requirements shall be met. - An auditable quality assurance process complying with development international standards shall be developed and maintained, - A process of verification and validation (V and V) shall be implemented. This approach requires: writing a report and/or executive summary of the V and V activities, defining a validated domain (domain in which the difference between the results of the tools and those of another qualified reference is considered satisfactory for its intended use). - Sufficient documentation shall be available, - A detailed and formal description of the product (software version number, user configuration, other settings and parameters) in the targeted computing environment shall be available. - Source codes corresponding to the software shall be archived appropriately. When these requirements are fulfilled, the version of the simulation tool shall be considered qualified for a defined domain of validity, in a given computing environment. The functional verification shall ensure that: - the computer architecture of the tool does not include errors, - the numerical solver correctly represents the physical mathematical model, - equations are solved correctly. The functional verification can be demonstrated through certification or report of Quality Assurance. The functional validation shall allow the user to ensure that the equations correctly represent the physical phenomena in the perimeter of intended use. The functional validation can

  18. Single-serve ice cream packaging: packaging structures enhancing brand

    OpenAIRE

    Salo, August

    2014-01-01

    The thesis focuses on packaging structures and branding; discussing the role packaging plays in brand identity. In today’s crowded marketplaces brands must fight to differentiate themselves from the competition by offering unique product experiences. As most products are packaged in one way or another, packaging has become a valuable element in brand communication and marketing. Packaging is seen as a part of the product experience, adding value and personality to otherwise similar products. ...

  19. 77 FR 9847 - Safety Zone; Kinnickinnic River Containment and Cleanup; Milwaukee, WI

    Science.gov (United States)

    2012-02-21

    ... SECURITY Coast Guard 33 CFR Part 165 RIN 1625-AA00 Safety Zone; Kinnickinnic River Containment and Cleanup... presented by the containment and cleanup of petroleum product are immediate and do not allow time for a... Michigan, has determined that the containment and cleanup poses a serious risk of injury to persons...

  20. CH Packaging Program Guidance

    International Nuclear Information System (INIS)

    The purpose of this document is to provide the technical requirements for preparation for use, operation, inspection, and maintenance of a Transuranic Package Transporter Model II (TRUPACT-II), a HalfPACT shipping package, and directly related components. This document complies with the minimum requirements as specified in the TRUPACT-II Safety Analysis Report for Packaging (SARP), HalfPACT SARP, and U.S. Nuclear Regulatory Commission (NRC) Certificates of Compliance (C of C) 9218 and 9279, respectively. In the event of a conflict between this document and the SARP or C of C, the C of C shall govern. The C of Cs state: ''each package must be prepared for shipment and operated in accordance with the procedures described in Chapter 7.0, Operating Procedures, of the application.'' They further state: ''each package must be tested and maintained in accordance with the procedures described in Chapter 8.0, Acceptance Tests and Maintenance Program of the Application.'' Chapter 9.0 of the SARP charges the Waste Isolation Pilot Plant (WIPP) management and operating (M and O) contractor with assuring packaging is used in accordance with the requirements of the C of C. Because the packaging is NRC-approved, users need to be familiar with Title 10 Code of Federal Regulations (CFR) 71.8. Any time a user suspects or has indications that the conditions of approval in the C of C were not met, the Carlsbad Field Office (CBFO) shall be notified immediately. The CBFO will evaluate the issue and notify the NRC if required.

  1. Food Packaging Materials

    Science.gov (United States)

    1978-01-01

    The photos show a few of the food products packaged in Alure, a metallized plastic material developed and manufactured by St. Regis Paper Company's Flexible Packaging Division, Dallas, Texas. The material incorporates a metallized film originally developed for space applications. Among the suppliers of the film to St. Regis is King-Seeley Thermos Company, Winchester, Ma'ssachusetts. Initially used by NASA as a signal-bouncing reflective coating for the Echo 1 communications satellite, the film was developed by a company later absorbed by King-Seeley. The metallized film was also used as insulating material for components of a number of other spacecraft. St. Regis developed Alure to meet a multiple packaging material need: good eye appeal, product protection for long periods and the ability to be used successfully on a wide variety of food packaging equipment. When the cost of aluminum foil skyrocketed, packagers sought substitute metallized materials but experiments with a number of them uncovered problems; some were too expensive, some did not adequately protect the product, some were difficult for the machinery to handle. Alure offers a solution. St. Regis created Alure by sandwiching the metallized film between layers of plastics. The resulting laminated metallized material has the superior eye appeal of foil but is less expensive and more easily machined. Alure effectively blocks out light, moisture and oxygen and therefore gives the packaged food long shelf life. A major packaging firm conducted its own tests of the material and confirmed the advantages of machinability and shelf life, adding that it runs faster on machines than materials used in the past and it decreases product waste; the net effect is increased productivity.

  2. Online fingerprint verification.

    Science.gov (United States)

    Upendra, K; Singh, S; Kumar, V; Verma, H K

    2007-01-01

    As organizations search for more secure authentication methods for user access, e-commerce, and other security applications, biometrics is gaining increasing attention. With an increasing emphasis on the emerging automatic personal identification applications, fingerprint based identification is becoming more popular. The most widely used fingerprint representation is the minutiae based representation. The main drawback with this representation is that it does not utilize a significant component of the rich discriminatory information available in the fingerprints. Local ridge structures cannot be completely characterized by minutiae. Also, it is difficult quickly to match two fingerprint images containing different number of unregistered minutiae points. In this study filter bank based representation, which eliminates these weakness, is implemented and the overall performance of the developed system is tested. The results have shown that this system can be used effectively for secure online verification applications. PMID:17365425

  3. Verification of uncertainty budgets

    DEFF Research Database (Denmark)

    Heydorn, Kaj; Madsen, B.S.

    2005-01-01

    , because their influence requires samples taken at long intervals, e.g., the acquisition of a new calibrant. It is therefore recommended to include verification of the uncertainty budget in the continuous QA/QC monitoring; this will eventually lead to a test also for such rarely occurring effects....... full range of matrices and concentrations for which the budget is assumed to be valid. In this way the assumptions made in the uncertainty budget can be experimentally verified, both as regards sources of variability that are assumed negligible, and dominant uncertainty components. Agreement between...... observed and expected variability is tested by means of the T-test, which follows a chi-square distribution with a number of degrees of freedom determined by the number of replicates. Significant deviations between predicted and observed variability may be caused by a variety of effects, and examples will...

  4. Type A Verification Report For The High Flux Beam Reactor Stack And Grounds, Brookhaven National Laboratory, Upton, New York DCN: 5098-SR-08-0

    International Nuclear Information System (INIS)

    The U.S. Department of Energy (DOE) Order 458.1 requires independent verification (IV) of DOE cleanup projects (DOE 2011). The Oak Ridge Institute for Science and Education (ORISE) has been designated as the responsible organization for IV of the High Flux Beam Reactor (HFBR) Stack and Grounds area at Brookhaven National Laboratory (BNL) in Upton, New York. The IV evaluation may consist of an in-process inspection with document and data reviews (Type A Verification) or a confirmatory survey of the site (Type B Verification). DOE and ORISE determined that a Type A verification of the documents and data for the HFBR Stack and Grounds: Survey Units (SU) 6, 7, and 8 was appropriate based on the initial survey unit classification, the walkover surveys, and the final analytical results provided by the Brookhaven Science Associates (BSA).

  5. Terminating Safeguards on Excess Special Nuclear Material: Defense TRU Waste Clean-up and Nonproliferation - 12426

    International Nuclear Information System (INIS)

    The Department of Energy (DOE) and the National Nuclear Security Administration (NNSA) manages defense nuclear material that has been determined to be excess to programmatic needs and declared waste. When these wastes contain plutonium, they almost always meet the definition of defense transuranic (TRU) waste and are thus eligible for disposal at the Waste Isolation Pilot Plant (WIPP). The DOE operates the WIPP in a manner that physical protections for attractiveness level D or higher special nuclear material (SNM) are not the normal operating condition. Therefore, there is currently a requirement to terminate safeguards before disposal of these wastes at the WIPP. Presented are the processes used to terminate safeguards, lessons learned during the termination process, and how these approaches might be useful for future defense TRU waste needing safeguards termination prior to shipment and disposal at the WIPP. Also described is a new criticality control container, which will increase the amount of fissile material that can be loaded per container, and how it will save significant taxpayer dollars. Retrieval, compliant packaging and shipment of retrievably stored legacy TRU waste has dominated disposal operations at WIPP since it began operations 12 years ago. But because most of this legacy waste has successfully been emplaced in WIPP, the TRU waste clean-up focus is turning to newly-generated TRU materials. A major component will be transuranic SNM, currently managed in safeguards-protected vaults around the weapons complex. As DOE and NNSA continue to consolidate and shrink the weapons complex footprint, it is expected that significant quantities of transuranic SNM will be declared surplus to the nation's needs. Safeguards termination of SNM varies due to the wide range of attractiveness level of the potential material that may be directly discarded as waste. To enhance the efficiency of shipping waste with high TRU fissile content to WIPP, DOE designed an over

  6. CH Packaging Program Guidance

    International Nuclear Information System (INIS)

    The purpose of this document is to provide the technical requirements for preparation for use, operation, inspection, and maintenance of a Transuranic Package Transporter Model II (TRUPACT-II), a HalfPACT shipping package, and directly related components. This document complies with the minimum requirements as specified in the TRUPACT-II Safety Analysis Report for Packaging (SARP), HalfPACT SARP, and U.S. Nuclear Regulatory Commission (NRC) Certificates of Compliance (C of C) 9218 and 9279, respectively. In the event of a conflict between this document and the SARP or C of C, the C of C shall govern. The C of Cs state: 'each package must be prepared for shipment and operated in accordance with the procedures described in Chapter 7.0, Operating Procedures, of the application.' They further state: 'each package must be tested and maintained in accordance with the procedures described in Chapter 8.0, Acceptance Tests and Maintenance Program of the Application.' Chapter 9.0 of the SARP charges the U.S. Department of Energy (DOE) or the Waste Isolation Pilot Plant| (WIPP) management and operating (M and O) contractor with assuring packaging is used in accordance with the requirements of the C of C. Because the packaging is NRC-approved, users need to be familiar with Title 10 Code of Federal Regulations(CFR) 71.8. Any time a user suspects or has indications that the conditions of approval in the C of C were not met, the Carlsbad Field Office (CBFO) shall be notified immediately. The CBFO will evaluate the issue and notify the NRC if required.In accordance with 10 CFR Part 71, certificate holders, packaging users, and contractors or subcontractors who use, design, fabricate, test, maintain, or modify the packaging shall post copies of (1) 10 CFR Part 21 regulations, (2) Section 206 of the Energy Reorganization Act of 1974, and (3) NRC Form 3, Notice to Employees. These documents must be posted in a conspicuous location where the activities subject to these regulations

  7. CH Packaging Program Guidance

    International Nuclear Information System (INIS)

    The purpose of this document is to provide the technical requirements for preparation for use, operation, inspection, and maintenance of a Transuranic Package Transporter Model II (TRUPACT-II), a HalfPACT shipping package, and directly related components. This document complies with the minimum requirements as specified in the TRUPACT-II Safety Analysis Report for Packaging (SARP), HalfPACT SARP, and U.S. Nuclear Regulatory Commission (NRC) Certificates of Compliance (C of C) 9218 and 9279, respectively. In the event of a conflict between this document and the SARP or C of C, the C of C shall govern. The C of Cs state: 'each package must be prepared for shipment and operated in accordance with the procedures described in Chapter 7.0, Operating Procedures, of the application.' They further state: 'each package must be tested and maintained in accordance with the procedures described in Chapter 8.0, Acceptance Tests and Maintenance Program of the Application.' Chapter 9.0 of the SARP charges the U.S. Department of Energy (DOE) or the Waste Isolation Pilot Plant (WIPP) management and operating (M and O) contractor with assuring packaging is used in accordance with the requirements of the C of C. Because the packaging is NRC-approved, users need to be familiar with Title 10 Code of Federal Regulations (CFR) 71.8. Any time a user suspects or has indications that the conditions of approval in the C of C were not met, the Carlsbad Field Office (CBFO) shall be notified immediately. The CBFO will evaluate the issue and notify the NRC if required.In accordance with 10 CFR Part 71, certificate holders, packaging users, and contractors or subcontractors who use, design, fabricate, test, maintain, or modify the packaging shall post copies of (1) 10 CFR Part 21 regulations, (2) Section 206 of the Energy Reorganization Act of 1974, and (3) NRC Form 3, Notice to Employees. These documents must be posted in a conspicuous location where the activities subject to these regulations

  8. CH Packaging Program Guidance

    Energy Technology Data Exchange (ETDEWEB)

    None, None

    2006-04-25

    The purpose of this document is to provide the technical requirements for preparation for use, operation, inspection, and maintenance of a Transuranic Package TransporterModel II (TRUPACT-II), a HalfPACT shipping package, and directly related components. This document complies with the minimum requirements as specified in the TRUPACT-II Safety Analysis Report for Packaging (SARP), HalfPACT SARP, and U.S. Nuclear Regulatory Commission (NRC) Certificates of Compliance (C of C) 9218 and 9279, respectively. In the event of a conflict between this document and the SARP or C of C, the C of C shall govern. The C of Cs state: "each package must be prepared for shipment and operated in accordance with the procedures described in Chapter 7.0, Operating Procedures, of the application." They further state: "each package must be tested and maintained in accordance with the procedures described in Chapter 8.0, Acceptance Tests and Maintenance Program of the Application." Chapter 9.0 of the SARP charges the U.S. Department of Energy (DOE) or the Waste Isolation Pilot Plant| (WIPP) management and operating (M&O) contractor with assuring packaging is used in accordance with the requirements of the C of C. Because the packaging is NRC-approved, users need to be familiar with Title 10 Code of Federal Regulations(CFR) §71.8. Any time a user suspects or has indications that the conditions ofapproval in the C of C were not met, the Carlsbad Field Office (CBFO) shall be notified immediately. The CBFO will evaluate the issue and notify the NRC if required.In accordance with 10 CFR Part 71, certificate holders, packaging users, and contractors or subcontractors who use, design, fabricate, test, maintain, or modify the packaging shall post copies of (1) 10 CFR Part 21 regulations, (2) Section 206 of the Energy Reorganization Act of 1974, and (3) NRC Form 3, Notice to Employees. These documents must be posted in a conspicuous location where the activities subject to these regulations are

  9. CH Packaging Program Guidance

    Energy Technology Data Exchange (ETDEWEB)

    None, None

    2007-12-13

    The purpose of this document is to provide the technical requirements for preparation for use, operation, inspection, and maintenance of a Transuranic Package Transporter Model II (TRUPACT-II), a HalfPACT shipping package, and directly related components. This document complies with the minimum requirements as specified in the TRUPACT-II Safety Analysis Report for Packaging (SARP), HalfPACT SARP, and U.S. Nuclear Regulatory Commission (NRC) Certificates of Compliance (C of C) 9218 and 9279, respectively. In the event of a conflict between this document and the SARP or C of C, the C of C shall govern. The C of Cs state: "each package must be prepared for shipment and operated in accordance with the procedures described in Chapter 7.0, Operating Procedures, of the application." They further state: "each package must be tested and maintained in accordance with the procedures described in Chapter 8.0, Acceptance Tests and Maintenance Program of the Application." Chapter 9.0 of the SARP charges the U.S. Department of Energy (DOE) or the Waste Isolation Pilot Plant (WIPP) management and operating (M&O) contractor with assuring packaging is used in accordance with the requirements of the C of C. Because the packaging is NRC-approved, users need to be familiar with Title 10 Code of Federal Regulations (CFR) §71.8. Any time a user suspects or has indications that the conditions of approval in the C of C were not met, the Carlsbad Field Office (CBFO) shall be notified immediately. The CBFO will evaluate the issue and notify the NRC if required.In accordance with 10 CFR Part 71, certificate holders, packaging users, and contractors or subcontractors who use, design, fabricate, test, maintain, or modify the packaging shall post copies of (1) 10 CFR Part 21 regulations, (2) Section 206 of the Energy Reorganization Act of 1974, and (3) NRC Form 3, Notice to Employees. These documents must be posted in a conspicuous location where the activities subject to these regulations are

  10. Environmental Assessment For Cleanup and Closure of the Energy Technology Engineering Center. Final Report

    Energy Technology Data Exchange (ETDEWEB)

    None, None

    2003-03-01

    DOE analyzed two cleanup and closure alternatives and the No Action Alternative, in accordance with the Council on Environmental Quality regulations implementing NEPA (40 CFR Parts 1500-1508) and DOE's NEPA implementing regulations (10 CFR Part 1021). Under Alternative 1, DOE is proposing to clean up the remaining ETEC facilities using the existing site specific cleanup standard of 15 mrem/yr. (plus DOE's As Low As Reasonably Achievable--ALARA-principle) for decontamination of radiological facilities and surrounding soils (Alternative 1). An annual 15-millirem additional radiation dose to the maximally exposed individual (assumed to be an individual living in a residential setting on Area IV) from all exposure pathways (air, soil, groundwater) equates to an additional theoretical lifetime cancer risk of no more than 3 x 10-4 (3 in 10,000). For perspective, it is estimated that the average individual in the United States receives a dose of about 300 millirem each year from natural sources of radiation. However, actual exposures generally will be much lower as a result of the application of the ''as low as reasonably achievable'' (ALARA) principle. Based on post-remediation verification sampling previous cleanups have generally resulted in a 2 x 10-6 level of residual risk. DOE would decontaminate, decommission, and demolish the remaining radiological facilities. DOE would also decommission and demolish the one remaining sodium facility and all of the remaining uncontaminated support buildings for which it is responsible. The ongoing RCRA corrective action program, including groundwater treatment (interim measures), would continue. Other environmental impacts would include 2.5 x 10-3 fatalities as a result of LLW shipments and 6.0 x 10-3 fatalities as a result of emission exhaust from all shipments. DOE would also decommission and demolish the remaining sodium facility and decommission and

  11. Cleanup procedures at the Nevada Test Site and at other radioactively contaminated sites including representative costs of cleanup and treatment of contaminated areas

    International Nuclear Information System (INIS)

    This review summarizes available information on cleanup procedures at the Nevada Test Site and at other radioactively contaminated sites. Radionuclide distribution and inventory, size of the contaminated areas, equipment, and cleanup procedures and results are included. Information about the cost of cleanup and treatment for contaminated land is presented. Selected measures that could be useful in estimating the costs of cleaning up radioactively contaminated areas are described. 76 refs., 16 tabs

  12. Reconfigurable system design and verification

    CERN Document Server

    Hsiung, Pao-Ann; Huang, Chun-Hsian

    2009-01-01

    Reconfigurable systems have pervaded nearly all fields of computation and will continue to do so for the foreseeable future. Reconfigurable System Design and Verification provides a compendium of design and verification techniques for reconfigurable systems, allowing you to quickly search for a technique and determine if it is appropriate to the task at hand. It bridges the gap between the need for reconfigurable computing education and the burgeoning development of numerous different techniques in the design and verification of reconfigurable systems in various application domains. The text e

  13. Garbage Collector Verification for Proof-Carrying Code

    Institute of Scientific and Technical Information of China (English)

    Chun-Xiao Lin; Yi-Yun Chen; Long Li; Bei Hua

    2007-01-01

    We present the verification of the machine-level implementation of a conservative variant of the standard mark-sweep garbage collector in a Hoare-style program logic. The specification of the collector is given on a machine-level memorymodel using separation logic, and is strong enough to preserve the safety property of any common mutator program. Ourverification is fully implemented in the Coq proof assistant and can be packed immediately as foundational proof-carryingcode package. Our work makes important attempt toward building fully certified production-quality garbage collectors.

  14. Multi-Agency Radiation Survey and Site Investigation Manual (MARSSIM) overview and use for final status (verification) surveys at several sites in the United States

    International Nuclear Information System (INIS)

    This paper will provide an overview of the Multi-Agency Radiation Survey and Site Investigation Manual (MARSSIM). MARSSIM was written by the four United States agencies most involved with radioactive site cleanups. MARSSIM provides a single, nationally consistent, flexible, performance based approach for scientifically planning, conducting and evaluating cleanup demonstration measurements and making subsequent decisions. MARSSIM works with any cleanup goal, dose, risk, or radioactivity concentration. In addition, this paper will report on the use of the MARSSIM methodology for Final Status (Verification) Surveys at several types of sites in the United States. MARSSIM's use at these sites produced improved survey plans and caused fewer costly measurements to demonstrate that the sites had been remediated. (author)

  15. Utilizing the right mix of environmental cleanup technologies

    International Nuclear Information System (INIS)

    The Savannah River Site (SRS) is a 310-square-mile United States Department of Energy nuclear facility located along the Savannah River near Aiken, South Carolina. During operations, which started in 1951, hazardous substances (chemicals and radionuclides) were released to the environment. The releases occurred as a result of inadvertent spills and waste disposal in unlined pits and basins which was common practice before environmental regulations existed. The hazardous substances have migrated to the vadose zone and groundwater in many areas of the SRS, resulting in 515 waste units that are required by environmental regulations, to undergo characterization and, if needed, remediation. In the initial years of the SRS environmental cleanup program (early 1990's), the focus was to use common technologies (such as pump and treat, air stripping, excavation and removal) that actively and tangibly removed contamination. Exclusive use of these technologies required continued and significant funding while often failing to meet acceptable clean-up goals and objectives. Recognizing that a more cost-effective approach was needed, SRS implemented new and complementary remediation methods focused on active and passive technologies targeted to solve specific remediation problems. Today, SRS uses technologies such as chemical / pH-adjusting injection, phyto-remediation, underground cutoff walls, dynamic underground stripping, soil fracturing, microbial degradation, baro-balls, electrical resistance heating, soil vapor extraction, and micro-blowers to more effectively treat contamination at lower costs. Additionally, SRS's remediation approach cost effectively maximizes cleanup as SRS works pro-actively with multiple regulatory agencies. Using GIS, video, animation, and graphics, SRS is able to provide an accurate depiction of the evolution of SRS groundwater and vadose zone cleanup activities to convince stakeholders and regulators of the effectiveness of various cleanup

  16. Waste package characterisation

    International Nuclear Information System (INIS)

    Radioactive wastes originating from the hot labs of the Belgian Nuclear Research Centre SCK-CEN contain a wide variety of radiotoxic substances. The accurate characterisation of the short- and long-term radiotoxic components is extremely difficult but required in view of geological disposal. This paper describes the methodology which was developed and adopted to characterise the high- and medium-level waste packages at the SCK-CEN hot laboratories. The proposed method is based on the estimation of the fuel inventory evacuated in a particular waste package; a calculation of the relative fission product contribution on the fuel fabrication and irradiation footing; a comparison of the calculated, as expected, dose rate and the real measured dose rate of the waste package. To cope with the daily practice an appropriate fuel inventory estimation route, a user friendly computer programme for fission product and corresponding dose rate calculation, and a simple dose rate measurement method have been developed and implemented

  17. Packaging Solutions : Delivering customer value through Logistical Packaging: A Case Study at Stora Enso Packaging

    OpenAIRE

    Shan, Kun; Julius, Joezer

    2015-01-01

    AbstractBackground;Despite of the significant role of packaging within logistics and supply chain management, packaging is infrequently studied as focal point in supply chain. Most of the previous logistics research studies tend to explain the integration between packaging and logistics through logistical packaging. In very rare cases, the studies mentioned about customer value. Therefore the major disadvantage of these studies is that, they didn’t consider logistical packaging and customer v...

  18. SPHINX experimenters information package

    Energy Technology Data Exchange (ETDEWEB)

    Zarick, T.A. [Sandia National Lab., Albuquerque, NM (United States). Radiation Effects Experimentation Dept.

    1996-08-01

    This information package was prepared for both new and experienced users of the SPHINX (Short Pulse High Intensity Nanosecond X-radiator) flash X-Ray facility. It was compiled to help facilitate experiment design and preparation for both the experimenter(s) and the SPHINX operational staff. The major areas covered include: Recording Systems Capabilities,Recording System Cable Plant, Physical Dimensions of SPHINX and the SPHINX Test cell, SPHINX Operating Parameters and Modes, Dose Rate Map, Experiment Safety Approval Form, and a Feedback Questionnaire. This package will be updated as the SPHINX facilities and capabilities are enhanced.

  19. SPHINX experimenters information package

    International Nuclear Information System (INIS)

    This information package was prepared for both new and experienced users of the SPHINX (Short Pulse High Intensity Nanosecond X-radiator) flash X-Ray facility. It was compiled to help facilitate experiment design and preparation for both the experimenter(s) and the SPHINX operational staff. The major areas covered include: Recording Systems Capabilities,Recording System Cable Plant, Physical Dimensions of SPHINX and the SPHINX Test cell, SPHINX Operating Parameters and Modes, Dose Rate Map, Experiment Safety Approval Form, and a Feedback Questionnaire. This package will be updated as the SPHINX facilities and capabilities are enhanced

  20. Autonomous packaging robot

    OpenAIRE

    Vo, Van Thanh

    2010-01-01

    The objective of the autonomous packaging robot application is to replace manual product packaging in food industry with a fully automatic robot. The objective is achieved by using the combination of machine vision, central computer, sensors, microcontroller and a typical ABB robot. The method is to equip the robot with different sensors: camera as “eyes” of robot, distance sensor and microcontroller as “sense of touch” of the robot, central computer as “brain” of the robot. Because the ro...

  1. Optimization of Cardboard Packaging

    OpenAIRE

    Dominika Crnjac Milic

    2010-01-01

    The paper will show that the area of a cube is less than the area of a parallelepiped of the same volume, and that the volume of the cube is greater than the volume of the parallelepiped of the same area, what is of major importance for the transportation of goods in cardboard packaging with the possibility of application to other packaging materials. Motivation for finding an exact mathematical proof for this problem originates from the Nestle company, since inadequate forms of product packa...

  2. Performance verification of Maanshan compact simulator against plant data

    International Nuclear Information System (INIS)

    The Maanshan compact simulator was built during the real-time simulation technology transfer project (from June 1991 to May 1993) to demonstrate the success of associated technology transfer. In building this simulator, master products from GP International, lnc. (GPI) are used. Currently, the associate software packages developed by GPI have been demonstrated on the Maanshan compact simulator - the first simulator ever adopting all GPI's master products. This paper demonstrates the excellent simulation capacity of the Maanshan compact simulator in the characteristic operational transients which have been recorded in the Maanshan plant, such as complete loss of main feedwater, turbine trip, net load trip, and large load reduction. The verification results presented in this paper conclude the simulation package from GPI is one of the best in the world, which can perform best-estimate calculation in simulating the whole plant in real time. (author)

  3. Assessment of Quality Assurance Measures for Radioactive Material Transport Packages not Requiring Competent Authority Design Approval - 13282

    Energy Technology Data Exchange (ETDEWEB)

    Komann, Steffen; Groeke, Carsten; Droste, Bernhard [BAM Federal Institute for Materials Research and Testing, Unter den Eichen 44-46, 12203 Berlin (Germany)

    2013-07-01

    The majority of transports of radioactive materials are carried out in packages which don't need a package design approval by a competent authority. Low-active radioactive materials are transported in such packages e.g. in the medical and pharmaceutical industry and in the nuclear industry as well. Decommissioning of NPP's leads to a strong demand for packages to transport low and middle active radioactive waste. According to IAEA regulations the 'non-competent authority approved package types' are the Excepted Packages and the Industrial Packages of Type IP-1, IP-2 and IP-3 and packages of Type A. For these types of packages an assessment by the competent authority is required for the quality assurance measures for the design, manufacture, testing, documentation, use, maintenance and inspection (IAEA SSR 6, Chap. 306). In general a compliance audit of the manufacturer of the packaging is required during this assessment procedure. Their regulatory level in the IAEA regulations is not comparable with the 'regulatory density' for packages requiring competent authority package design approval. Practices in different countries lead to different approaches within the assessment of the quality assurance measures in the management system as well as in the quality assurance program of a special package design. To use the package or packaging in a safe manner and in compliance with the regulations a management system for each phase of the life of the package or packaging is necessary. The relevant IAEA-SSR6 chap. 801 requires documentary verification by the consignor concerning package compliance with the requirements. (authors)

  4. Assessment of Quality Assurance Measures for Radioactive Material Transport Packages not Requiring Competent Authority Design Approval - 13282

    International Nuclear Information System (INIS)

    The majority of transports of radioactive materials are carried out in packages which don't need a package design approval by a competent authority. Low-active radioactive materials are transported in such packages e.g. in the medical and pharmaceutical industry and in the nuclear industry as well. Decommissioning of NPP's leads to a strong demand for packages to transport low and middle active radioactive waste. According to IAEA regulations the 'non-competent authority approved package types' are the Excepted Packages and the Industrial Packages of Type IP-1, IP-2 and IP-3 and packages of Type A. For these types of packages an assessment by the competent authority is required for the quality assurance measures for the design, manufacture, testing, documentation, use, maintenance and inspection (IAEA SSR 6, Chap. 306). In general a compliance audit of the manufacturer of the packaging is required during this assessment procedure. Their regulatory level in the IAEA regulations is not comparable with the 'regulatory density' for packages requiring competent authority package design approval. Practices in different countries lead to different approaches within the assessment of the quality assurance measures in the management system as well as in the quality assurance program of a special package design. To use the package or packaging in a safe manner and in compliance with the regulations a management system for each phase of the life of the package or packaging is necessary. The relevant IAEA-SSR6 chap. 801 requires documentary verification by the consignor concerning package compliance with the requirements. (authors)

  5. Numident Online Verification Utility (NOVU)

    Data.gov (United States)

    Social Security Administration — NOVU is a mainframe application that accesses the NUMIDENT to perform real-time SSN verifications. This program is called by other SSA online programs that serve as...

  6. TPS verification with UUT simulation

    Science.gov (United States)

    Wang, Guohua; Meng, Xiaofeng; Zhao, Ruixian

    2006-11-01

    TPS's (Test Program Set) verification or first article acceptance test commonly depends on fault insertion experiment on UUT (Unit Under Test). However the failure modes injected on UUT is limited and it is almost infeasible when the UUT is in development or in a distributed state. To resolve this problem, a TPS verification method based on UUT interface signal simulation is putting forward. The interoperability between ATS (automatic test system) and UUT simulation platform is very important to realize automatic TPS verification. After analyzing the ATS software architecture, the approach to realize interpretability between ATS software and UUT simulation platform is proposed. And then the UUT simulation platform software architecture is proposed based on the ATS software architecture. The hardware composition and software architecture of the UUT simulation is described in details. The UUT simulation platform has been implemented in avionics equipment TPS development, debug and verification.

  7. NRC plan for cleanup operations at Three Mile Island Unit 2

    International Nuclear Information System (INIS)

    This NRC Plan, which defines NRC's functional role in cleanup operations at Three Mile Island Unit 2 and outlines NRC's regulatory responsibilities in fulfilling this role, is the first revision to the initial plan issued in July 1980 (NUREG-0698). Since 1980, a number of policy developments have occurred which will have an impact on the course of cleanup operations. This revision reflects these developments in the area of NRC's review and approval process with regard to cleanup operations as well as NRC's interface with the Department of Energy's involvement in the cleanup and waste disposal. This revision is also intended to update the cleanup schedule by presenting the cleanup progress that has taken place and NRC's role in ongoing and future cleanup activities

  8. Video-Based Fingerprint Verification

    OpenAIRE

    Lili Liu; Yilong Yin; Wei Qin

    2013-01-01

    Conventional fingerprint verification systems use only static information. In this paper, fingerprint videos, which contain dynamic information, are utilized for verification. Fingerprint videos are acquired by the same capture device that acquires conventional fingerprint images, and the user experience of providing a fingerprint video is the same as that of providing a single impression. After preprocessing and aligning processes, “inside similarity” and “outside similarity” are defined and...

  9. Combining innovative technology demonstrations with dense nonaqueous phase liquids cleanup

    International Nuclear Information System (INIS)

    Radioactively contaminated acidic aqueous wastes and organic liquids were discharged to the soil column at three disposal sites within the 200 West Area of the Hanford Site, Washington. As a result, a portion of the underlying groundwater is contaminated with carbon tetrachloride several orders of magnitude above the maximum contaminant level accepted for a drinking water supply. Treatability testing and cleanup actions have been initiated to remove the contamination from both the unsaturated soils to minimize further groundwater contamination and the groundwater itself. To expedite cleanup, innovative technologies for (1) drilling, (2) site characterization, (3) monitoring, (4) well field development, and (5) contaminant treatment are being demonstrated and subsequently used where possible to improve the rates and cost savings associated with the removal of carbon tetrachloride from the soils and groundwater

  10. INDEPENDENT VERIFICATION SURVEY OF THE HIGH FLUX BEAM REACTOR DECOMMISSIONING PROJECT OUTSIDE AREAS BROOKHAVEN NATIONAL LABORATORY UPTON, NEW YORK

    International Nuclear Information System (INIS)

    The objective of the verification survey was to obtain evidence by means of measurements and sampling to confirm that the final radiological conditions meet the established cleanup goals. This objective was achieved via multiple verification components including document reviews, instrument scans, and sample analysis to determine the accuracy and adequacy of FSS documentation. During the period between August 18 to 25 and September 24 to 29, 2010, ORISE conducted measurements and sampling of the HFBR 'Outside Areas' at the BNL site. ORISE performed gamma walkover scans in all eight SUs with SUs 2, 4, 6, 7, and 8 receiving high density scans of accessible areas. The remainder of SUs received low density scans. While scanning, ORISE team members observed a significant spike in count rate activity in SU 8. Just as quickly as the count rate increased the count rate decreased. A previous pass in the area did not identify any activity associated with soil contamination. The team determined that both detector instrument electronics functioned normally, and that the increased activity was due to a site activity. All individual sample concentrations and corresponding mean concentrations evaluated were determined to be below the established cleanup goal. A review of the data collected by ORISE has not identified any areas of contamination exceeding cleanup goals.

  11. Public participation in the evaluation of innovative environmental cleanup technology

    International Nuclear Information System (INIS)

    Technologies for remediation of contamination are urgently needed to clean up US Department of Energy (DOE) sites across the country. DOE is managing a national program to develop, demonstrate, and deploy new technologies with promise to expedite this cleanup. The Integrated Demonstration for Cleanup of Volatile Organic Compounds at Arid Sites (VOC-Arid ID) is one such effort. Time and resources, however, are too limited to be invested in methods of remediation that will never be deployed because they have not been rigorously evaluated or because they face the withering opposition of stakeholders. Therefore the VOC-Arid ID is assessing technology both in terms of its technical effectiveness and its stakeholder acceptability. Only if a technology performs as required and is acceptable to regulators, users of technology, and the public will the VOC-Arid ID recommend its use. What distinguishes public involvement in the VOC-Arid ID is the direct influence stakeholders have on the design of technology demonstrations by working directly with technology developers. Stakeholders participated in defining the criteria with which innovative environmental cleanup technology is being evaluated. The integrated demonstration is committed to providing stakeholders with the information they've indicated they need to reach reasoned judgments about the use of specific cleanup technologies. A guiding principle of the VOC-Arid ID is that stakeholder participation improves the technologies being developed, enhances the acceptance of the technologies, and will lead to the broad and timely deployment of appropriate and effective methods of environmental remediation. The VOC-Arid ID has involved stakeholders from the host demonstration site, Hanford, Washington, and from other and sites where the ID technologies may be deployed

  12. Using Advanced Mixed Waste Treatment Technology To Meet Accelerated Cleanup Program Milestones

    International Nuclear Information System (INIS)

    . The waste materials were extremely challenging; at times exceeding 85% total organic chemical content. Vacuum thermal desorption operations are described that resulted in waste processing rates as high as 376 drum equivalents per month, with an average over 300 drums/month for a four month period. During this same time period, performance verification sampling demonstrated 99.2% successful VTD treatment, with only 10 drums failing out of 1,244 drums processed. These 10 drums were successfully treated upon reprocessing in the VTD unit. Condensate volume of 14,400 gallons was collected from the 1,244 drums, composed of approximately 2/3 organic liquid having high chlorine content from both solvents and PCBs. This condensate is being shipped for off-site incineration as it meets the acceptance criteria for that disposal method. With this combination of management initiative, permits, and technology, important Accelerated Cleanup Program milestones have been met. (authors)

  13. A risk-based cleanup criterion for PCE in soil

    International Nuclear Information System (INIS)

    The most important attribute of a chemical contaminant at a hazardous-wastes site for decision makers to consider with regard to its cleanup is the potential risk associated with human exposure. For this reason we have developed a strategy for establishing a risk-based cleanup criterion for chemicals in soil. We describe this strategy by presenting a cleanup criterion for tetrachloroethylene (PCE) in soil associated with a representative California landscape. We being by discussing the environmental fate and transport model, developed at the Lawrence Livermore National Laboratory (LLNL), that we used to predict the equilibrium concentration of PCE in five environmental media from a steady-state source in soil. Next, we explain the concept and application of pathway-exposure factors (PEFs), the hazard index, and cancer-potency factors (CPFs) for translating the predicted concentrations of PCE into estimated potential hazard or risk for hypothetically exposed individuals. Finally, the relationship between concentration and an allowable level of risk is defined and the societal and financial implications are discussed. 22 refs., 6 tabs

  14. Rocky Flats Cleanup Agreement implementation successes and challenges

    International Nuclear Information System (INIS)

    On July 19, 1996 the US Department of Energy (DOE), State of Colorado (CDPHE), and US Environmental Protection Agency (EPA) entered into an agreement called the Rocky Flats Cleanup Agreement (RFCA) for the cleanup and closure of the Rocky Flats Environmental Technology Site (RFETS or Rocky Flats). Major elements of the agreement include: an Integrated Site-Wide Baseline; up to twelve significant enforceable milestones per year; agreed upon soil and water action levels and standards for cleanup; open space as the likely foreseeable land use; the plutonium and TRU waste removed by 2015; streamlined regulatory process; agreement with the Defense Nuclear Facilities Safety Board (DNFSB) to coordinate activities; and a risk reduction focus. Successful implementation of RFCA requires a substantial effort by the parties to change their way of thinking about RFETS and meet the deliverables and commitments. Substantial progress toward Site closure through the implementation of RFCA has been accomplished in the short time since the signing, yet much remains to be done. Much can be learned from the Rocky Flats experience by other facilities in similar situations

  15. Aquaculture Information Package

    Energy Technology Data Exchange (ETDEWEB)

    Boyd, T.; Rafferty, K. [editors

    1998-01-01

    This package of information is intended to provide background to developers of geothermal aquaculture projects. The material is divided into eight sections and includes information on market and price information for typical species, aquaculture water quality issues, typical species culture information, pond heat loss calculations, an aquaculture glossary, regional and university aquaculture offices and state aquaculture permit requirements.

  16. Openability of tamperproof packaging

    NARCIS (Netherlands)

    Del Castillo C., A.; Wever, R.; Buijs, P.J.; Stevels, A.

    2007-01-01

    Communication, product protection and presentation are three key aspects in the world of packaging nowadays. Due to a retail landscape consisting of large stores, displaying packed products on the shelves in self-service environments, these aspects become increasingly important, not only for Fast Mo

  17. Printer Graphics Package

    Science.gov (United States)

    Blanchard, D. C.

    1986-01-01

    Printer Graphics Package (PGP) is tool for making two-dimensional symbolic plots on line printer. PGP created to support development of Heads-Up Display (HUD) simulation. Standard symbols defined with HUD in mind. Available symbols include circle, triangle, quadrangle, window, line, numbers, and text. Additional symbols easily added or built up from available symbols.

  18. Polymers in Waveguide Packaging

    Institute of Scientific and Technical Information of China (English)

    Zhiyi Zhang; G. Z.Xiao; Jiaren Liu; C. P. Grover

    2003-01-01

    Polymers were successfully used in the packaging of waveguide-based photonic components in the area of fiber-to-waveguide coupling, waveguide die attachment, strain relief, and waveguide encapsulation. The application results of these polymers were described in this paper.

  19. Waste disposal package

    Science.gov (United States)

    Smith, M.J.

    1985-06-19

    This is a claim for a waste disposal package including an inner or primary canister for containing hazardous and/or radioactive wastes. The primary canister is encapsulated by an outer or secondary barrier formed of a porous ceramic material to control ingress of water to the canister and the release rate of wastes upon breach on the canister. 4 figs.

  20. Geothermal Greenhouse Information Package

    Energy Technology Data Exchange (ETDEWEB)

    Rafferty, K. [P.E.; Boyd, T. [ed.

    1997-01-01

    This package of information is intended to provide a foundation of background information for developers of geothermal greenhouses. The material is divided into seven sections covering such issues as crop culture and prices, operating costs for greenhouses, heating system design, vendors and a list of other sources of information.

  1. The Swarm Magnetometry Package

    DEFF Research Database (Denmark)

    Merayo, José M.G.; Jørgensen, John Leif; Friis-Christensen, Eigil;

    2008-01-01

    The Swarm mission under the ESA's Living Planet Programme is planned for launch in 2010 and consists of a constellation of three satellites at LEO. The prime objective of Swarm is to measure the geomagnetic field with unprecedented accuracy in space and time. The magnetometry package consists of an...

  2. The Swarm Magnetometry Package

    DEFF Research Database (Denmark)

    Merayo, José M.G.; Jørgensen, John Leif; Friis-Christensen, Eigil; Brauer, Peter; Primdahl, Fritz; Jørgensen, Peter Siegbjørn; Allin, Thomas Højgaard; Denver, Troelz

    The Swarm mission under the ESA's Living Planet Programme is planned for launch in 2010 and consists of a constellation of three satellites at LEO. The prime objective of Swarm is to measure the geomagnetic field with unprecedented accuracy in space and time. The magnetometry package consists of an...

  3. EQ3/6 software test and verification report 9/94

    International Nuclear Information System (INIS)

    This document is the Software Test and Verification Report (STVR) for the EQ3/6 suite of codes as stipulated in the Individual Software Plan for Initial Qualification of EQ3/6 (ISP-NF-07, Revision 1, 11/25/92). The software codes, EQPT, EQ3NR, EQ6, and the software library EQLIB constitute the EQ3/6 software package. This software test and verification project for EQ3/6 was started under the requirements of the LLNL Yucca Mountain Project Software Quality Assurance Plan (SQAP), Revision 0, December 14, 1989, but QP 3.2, Revision 2, June 21, 1994 is now the operative controlling procedure. This is a ''V and V'' report in the language of QP 3.2, Revision 2. Because the author of this report does not have a background in geochemistry, other technical sources were consulted in order to acquire some familiarity with geochemisty, the terminology minology involved, and to review comparable computational methods especially, geochemical aqueous speciation-solubility calculations. The software for the EQ3/6 package consists of approximately 47,000 lines of FORTRAN77 source code and nine on platforms ranging from workstations to supercomputers. The physical control of EQ3/6 software package and documentation is on a SUN SPARC station. Walkthroughs of each principal software packages, EQPT, EQ3NR, and EQ6 were conducted in order to understand the computational procedures involved, to determine any commonality in procedures, and then to establish a plan for the test and verification of EQ3/6. It became evident that all three phases depended upon solving an n x n matrix by the Newton-Raphson Method. Thus, a great deal of emphasis on the test and verification of this procedure was carried out on the first code in the software package EQPT

  4. A restructuring of RN1 package for MIDAS computer code

    International Nuclear Information System (INIS)

    RN1 package, which is one of two fission product-related packages in MELCOR, has been restructured for the MIDAS computer code. MIDAS is being developed as an integrated severe accident analysis code with a user-friendly graphical user interface and modernized data structure. To do this, data transferring methods of current MELCOR code are modified and adopted into the RN1 package. The data structure of the current MELCOR code using FORTRAN77 causes a difficult grasping of meaning of the variables as well as waste of memory. New features of FORTRAN90 make it possible to allocate the storage dynamically and to use the user-defined data type, which lead to an efficient memory treatment and an easy understanding of the code. Restructuring of the RN1 package addressed in this paper includes module development, subroutine modification, and treats MELGEN, which generates data file, as well as MELCOR, which is processing a calculation. The verification has been done by comparing the results of the modified code with those from the existing code. As the trends are similar to each other, it hints that the same approach could be extended to the entire code package. It is expected that code restructuring will accelerate the code domestication thanks to direct understanding of each variable and easy implementation of modified or newly developed models

  5. A restructuring of RN1 package for MIDAS computer code

    Energy Technology Data Exchange (ETDEWEB)

    Park, S. H.; Kim, D. H.; Kim, K. R. [KAERI, Taejon (Korea, Republic of)

    2003-10-01

    RN1 package, which is one of two fission product-related packages in MELCOR, has been restructured for the MIDAS computer code. MIDAS is being developed as an integrated severe accident analysis code with a user-friendly graphical user interface and modernized data structure. To do this, data transferring methods of current MELCOR code are modified and adopted into the RN1 package. The data structure of the current MELCOR code using FORTRAN77 causes a difficult grasping of meaning of the variables as well as waste of memory. New features of FORTRAN90 make it possible to allocate the storage dynamically and to use the user-defined data type, which lead to an efficient memory treatment and an easy understanding of the code. Restructuring of the RN1 package addressed in this paper includes module development, subroutine modification, and treats MELGEN, which generates data file, as well as MELCOR, which is processing a calculation. The verification has been done by comparing the results of the modified code with those from the existing code. As the trends are similar to each other, it hints that the same approach could be extended to the entire code package. It is expected that code restructuring will accelerate the code domestication thanks to direct understanding of each variable and easy implementation of modified or newly developed models.

  6. Monitoring and inspection techniques for long term storage of higher activity waste packages

    International Nuclear Information System (INIS)

    In 2009, following recent changes in United Kingdom (UK) Government Policy, the Nuclear Decommissioning Authority (NDA) identified a knowledge gap in the area of long term interim storage of waste packages. A cross-industry Integrated Project Team (IPT) for Interim Storage was created with responsibility for delivering Industry Guidance on the storage of packaged Higher Activity Waste (HAW) for the current UK civil decommissioning and clean-up programmes. This included a remit to direct research and development projects via the NDA's Direct Research Portfolio (DRP) to fill the knowledge gap. The IPT for Interim Storage published Industry Guidance in 2012 which established a method to define generic package performance criteria and made recommendations on monitoring and inspection. The package performance method consists of the following steps; identification of the package safety function, identification of evolutionary processes that may affect safety function performance, determination of measurable indicators of these evolutionary processes and calibration of the indicators into package performance zones. This article provides an overview of three projects funded by the NDA's DRP that the UK National Nuclear Laboratory (NNL) have completed to address monitoring and inspection needs of waste packages in interim storage. (orig.)

  7. Lakes Ecosystem Services Download Package

    Data.gov (United States)

    U.S. Environmental Protection Agency — This data download package contains Esri 10.0 MXDs, file geodatabases and copy of this FGDC metadata record. The data in this package are used in support of the...

  8. Packaging based on polymeric materials

    OpenAIRE

    Jovanović Slobodan M.; Živković Predrag M.; Stoiljković Dragoslav M.

    2005-01-01

    In the past two years the consumption of common in the developed countries world wide (high tonnage) polymers for packaging has approached a value of 50 wt.%. In the same period more than 50% of the packaging units on the world market were made of polymeric materials despite the fact that polymeric materials present 17 wt.% of all packaging materials. The basic properties of polymeric materials and their environmental and economical advantages, providing them such a position among packaging m...

  9. Sustainable Library Development Training Package

    Science.gov (United States)

    Peace Corps, 2012

    2012-01-01

    This Sustainable Library Development Training Package supports Peace Corps' Focus In/Train Up strategy, which was implemented following the 2010 Comprehensive Agency Assessment. Sustainable Library Development is a technical training package in Peace Corps programming within the Education sector. The training package addresses the Volunteer…

  10. Functional verification of floating point arithmetic unit

    International Nuclear Information System (INIS)

    For continuous real-time reactivity monitoring of PFBR reactivity safety channel, a FPGA based reactivity meter has been developed by Electronics Division, BARC. Verification of designs involved in Safety Critical systems is very important and necessary. Functional verification of this design is presently carried out by EID, IGCAR. In Reactivity meter, Floating Point Arithmetic Unit (FPAU) is a major and very important sub module, which needs to be completely verified first. Two types of verifications are possible: Functional verification and Formal verification. This paper discusses and shares the experiences of functional verification of FPAU module for all special floating point numbers. (author)

  11. Verification of Chemical Weapons Destruction

    International Nuclear Information System (INIS)

    The Chemical Weapons Convention is the only multilateral treaty that bans completely an entire category of weapons of mass destruction under international verification arrangements. Possessor States, i.e. those that have chemical weapons stockpiles at the time of becoming party to the CWC, commit to destroying these. All States undertake never to acquire chemical weapons and not to help other States acquire such weapons. The CWC foresees time-bound chemical disarmament. The deadlines for destruction for early entrants to the CWC are provided in the treaty. For late entrants, the Conference of States Parties intervenes to set destruction deadlines. One of the unique features of the CWC is thus the regime for verifying destruction of chemical weapons. But how can you design a system for verification at military sites, while protecting military restricted information? What degree of assurance is considered sufficient in such circumstances? How do you divide the verification costs? How do you deal with production capability and initial declarations of existing stockpiles? The founders of the CWC had to address these and other challenges in designing the treaty. Further refinement of the verification system has followed since the treaty opened for signature in 1993 and since inspection work was initiated following entry-into-force of the treaty in 1997. Most of this work concerns destruction at the two large possessor States, Russia and the United States. Perhaps some of the lessons learned from the OPCW experience may be instructive in a future verification regime for nuclear weapons. (author)

  12. Anticounterfeit packaging technologies

    Directory of Open Access Journals (Sweden)

    Ruchir Y Shah

    2010-01-01

    Full Text Available Packaging is the coordinated system that encloses and protects the dosage form. Counterfeit drugs are the major cause of morbidity, mortality, and failure of public interest in the healthcare system. High price and well-known brands make the pharma market most vulnerable, which accounts for top priority cardiovascular, obesity, and antihyperlipidemic drugs and drugs like sildenafil. Packaging includes overt and covert technologies like barcodes, holograms, sealing tapes, and radio frequency identification devices to preserve the integrity of the pharmaceutical product. But till date all the available techniques are synthetic and although provide considerable protection against counterfeiting, have certain limitations which can be overcome by the application of natural approaches and utilization of the principles of nanotechnology.

  13. KAPPA -- Kernel Application Package

    Science.gov (United States)

    Currie, Malcolm J.; Berry, David. S.

    KAPPA is an applications package comprising about 180 general-purpose commands for image processing, data visualisation, and manipulation of the standard Starlink data format---the NDF. It is intended to work in conjunction with Starlink's various specialised packages. In addition to the NDF, KAPPA can also process data in other formats by using the `on-the-fly' conversion scheme. Many commands can process data arrays of arbitrary dimension, and others work on both spectra and images. KAPPA operates from both the UNIX C-shell and the ICL command language. This document describes how to use KAPPA and its features. There is some description of techniques too, including a section on writing scripts. This document includes several tutorials and is illustrated with numerous examples. The bulk of this document comprises detailed descriptions of each command as well as classified and alphabetical summaries.

  14. The Ettention software package.

    Science.gov (United States)

    Dahmen, Tim; Marsalek, Lukas; Marniok, Nico; Turoňová, Beata; Bogachev, Sviatoslav; Trampert, Patrick; Nickels, Stefan; Slusallek, Philipp

    2016-02-01

    We present a novel software package for the problem "reconstruction from projections" in electron microscopy. The Ettention framework consists of a set of modular building-blocks for tomographic reconstruction algorithms. The well-known block iterative reconstruction method based on Kaczmarz algorithm is implemented using these building-blocks, including adaptations specific to electron tomography. Ettention simultaneously features (1) a modular, object-oriented software design, (2) optimized access to high-performance computing (HPC) platforms such as graphic processing units (GPU) or many-core architectures like Xeon Phi, and (3) accessibility to microscopy end-users via integration in the IMOD package and eTomo user interface. We also provide developers with a clean and well-structured application programming interface (API) that allows for extending the software easily and thus makes it an ideal platform for algorithmic research while hiding most of the technical details of high-performance computing. PMID:26686659

  15. Software packager user's guide

    Science.gov (United States)

    Callahan, John R.

    1995-01-01

    Software integration is a growing area of concern for many programmers and software managers because the need to build new programs quickly from existing components is greater than ever. This includes building versions of software products for multiple hardware platforms and operating systems, building programs from components written in different languages, and building systems from components that must execute on different machines in a distributed network. The goal of software integration is to make building new programs from existing components more seamless -- programmers should pay minimal attention to the underlying configuration issues involved. Libraries of reusable components and classes are important tools but only partial solutions to software development problems. Even though software components may have compatible interfaces, there may be other reasons, such as differences between execution environments, why they cannot be integrated. Often, components must be adapted or reimplemented to fit into another application because of implementation differences -- they are implemented in different programming languages, dependent on different operating system resources, or must execute on different physical machines. The software packager is a tool that allows programmers to deal with interfaces between software components and ignore complex integration details. The packager takes modular descriptions of the structure of a software system written in the package specification language and produces an integration program in the form of a makefile. If complex integration tools are needed to integrate a set of components, such as remote procedure call stubs, their use is implied by the packager automatically and stub generation tools are invoked in the corresponding makefile. The programmer deals only with the components themselves and not the details of how to build the system on any given platform.

  16. Aquaculture information package

    Energy Technology Data Exchange (ETDEWEB)

    Boyd, T.; Rafferty, K.

    1998-08-01

    This package of information is intended to provide background information to developers of geothermal aquaculture projects. The material is divided into eight sections and includes information on market and price information for typical species, aquaculture water quality issues, typical species culture information, pond heat loss calculations, an aquaculture glossary, regional and university aquaculture offices and state aquaculture permit requirements. A bibliography containing 68 references is also included.

  17. Standard integrated head package

    International Nuclear Information System (INIS)

    An integrated head package for a standard-type nuclear reactor is described which consolidates many components and subassemblies of the upper reactor structure into a single unit which may be removed from the reactor vessel in a single lift. Included among the consolidated elements are a pressure vessel head, a cooling shroud, control rod drive mechanisms, a missile shield, a lifting rig, a hoist assembly, and a cable tray assembly. (author)

  18. Design of Small Test Facility for Engineering Safety Feature Air Clean-up System

    International Nuclear Information System (INIS)

    USNRC (United State Nuclear Regulatory Committee) issued Regulatory Guide 1.52, Rev. 3 (RG. 1.52 Rev.3) in 2006, and the major changes of Rev. 3 with respect to Rev.2 are[1]: 1) the test time was reduced from 10 hours to 15 minutes, 2) instead of DOP (Dioctyl Phthalate) , an alternative challenge agent for the In-place aerosol leak tests of the HEPA (high-efficiency particulate air) filters is also viable, and 3) extension of the test period from 18 months to 24 months for the In-place aerosol leak tests. It is clear that the revised guideline can provide benefits for the licensees without degrading safety standards, and Korean nuclear industry initiated a project to accumulate the background information of these changes and examine if similar changes can be taken places in domestic plants since it is believed that the revised guidance can be applicable if sufficient justifications are provided. As a part of these activities manufacturing the small test facility and testing the performance of ESF ACS (Engineering Safety Feature Air Clean-up System) is required. This paper deals with the design principle and actual design methodology. At first the theoretical review on the filtration mechanism was carried out and then the substantial strategy for test facility design was setup. Actual verification for the goodness of test facility design was conducted using CFD (Computational Fluid Dynamic) analysis. These CFD analyses provide the flow field information both the plant ESF ACS and test facility, and these velocity fields are key parameters for the filtration efficiency

  19. MACCS2 development and verification efforts

    International Nuclear Information System (INIS)

    MACCS2 represents a major enhancement of the capabilities of its predecessor MACCS, the MELCOR Accident Consequence Code System. MACCS, released in 1987, was developed to estimate the potential impacts to the surrounding public of severe accidents at nuclear power plants. The principal phenomena considered in MACCS/MACCS2 are atmospheric transport and deposition under time-variant meteorology, short-term and long-term mitigative actions and exposure pathways, deterministic and stochastic health effects, and economic costs. MACCS2 was developed as a general-purpose analytical tool applicable to diverse reactor and nonreactor facilities. The MACCS2 package includes three primary enhancements: (1) a more flexible emergency response model, (2) an expanded library of radionuclides, and (3) a semidynamic food-chain model. In addition, errors that had been identified in MACCS version1.5.11.1 were corrected, including an error that prevented the code from providing intermediate-phase results. MACCS2 version 1.10 beta test was released to the beta-test group in May, 1995. In addition, the University of New Mexico (UNM) has completed an independent verification study of the code package. Since the beta-test release of MACCS2 version 1.10, a number of minor errors have been identified and corrected, and a number of enhancements have been added to the code package. The code enhancements added since the beta-test release of version 1.10 include: (1) an option to allow the user to input the σy and σz plume expansion parameters in a table-lookup form for incremental downwind distances, (2) an option to define different initial dimensions for up to four segments of a release, (3) an enhancement to the COMIDA2 food-chain model preprocessor to allow the user to supply externally calculated tables of tritium food-chain dose per unit deposition on farmland to support analyses of tritium releases, and (4) the capability to calculate direction-dependent doses

  20. 78 FR 19007 - Certain Products Having Laminated Packaging, Laminated Packaging, and Components Thereof...

    Science.gov (United States)

    2013-03-28

    ... COMMISSION Certain Products Having Laminated Packaging, Laminated Packaging, and Components Thereof.... 1337, on behalf of Lamina Packaging Innovations LLC of Longview, Texas. An amended complaint was filed... importation of certain products having laminated packaging, laminated packaging, and components thereof...

  1. 78 FR 13083 - Products Having Laminated Packaging, Laminated Packaging, and Components Thereof; Notice of...

    Science.gov (United States)

    2013-02-26

    ... COMMISSION Products Having Laminated Packaging, Laminated Packaging, and Components Thereof; Notice of... Commission has received a complaint entitled Products Having Laminated ] Packaging, Laminated Packaging, and... filed on behalf of Lamina Packaging Innovations LLC on February 20, 2013. The complaint...

  2. Plutonium stabilization and packaging system

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-05-01

    This document describes the functional design of the Plutonium Stabilization and Packaging System (Pu SPS). The objective of this system is to stabilize and package plutonium metals and oxides of greater than 50% wt, as well as other selected isotopes, in accordance with the requirements of the DOE standard for safe storage of these materials for 50 years. This system will support completion of stabilization and packaging campaigns of the inventory at a number of affected sites before the year 2002. The package will be standard for all sites and will provide a minimum of two uncontaminated, organics free confinement barriers for the packaged material.

  3. Ensuring socially responsible packaging design

    DEFF Research Database (Denmark)

    Jensen, Birgitte Geert; Widding, Sofie Hartvig

    "User‐friendly Packaging" aims to create a platform for developing more user‐friendly packaging. One intended outcome of the project is a guideline that industry can use in development efforts. The project also points the way for more extended collaboration between companies and design researchers. How...... can design research help industry in packaging innovation?......Most consumers have experienced occasional problems with opening packaging. Tomato sauce from the tinned mackerel splattered all over the kitchen counter, the unrelenting pickle jar lid, and the package of sliced ham that cannot be opened without a knife or a pair of scissors. The research project...

  4. Plutonium stabilization and packaging system

    International Nuclear Information System (INIS)

    This document describes the functional design of the Plutonium Stabilization and Packaging System (Pu SPS). The objective of this system is to stabilize and package plutonium metals and oxides of greater than 50% wt, as well as other selected isotopes, in accordance with the requirements of the DOE standard for safe storage of these materials for 50 years. This system will support completion of stabilization and packaging campaigns of the inventory at a number of affected sites before the year 2002. The package will be standard for all sites and will provide a minimum of two uncontaminated, organics free confinement barriers for the packaged material

  5. Automated Verification of Virtualized Infrastructures

    DEFF Research Database (Denmark)

    Bleikertz, Sören; Gross, Thomas; Mödersheim, Sebastian Alexander

    2011-01-01

    Virtualized infrastructures and clouds present new challenges for security analysis and formal verification: they are complex environments that continuously change their shape, and that give rise to non-trivial security goals such as isolation and failure resilience requirements. We present a...... platform that connects declarative and expressive description languages with state-of-the art verification methods. The languages integrate homogeneously descriptions of virtualized infrastructures, their transformations, their desired goals, and evaluation strategies. The different verification tools...... range from model checking to theorem proving; this allows us to exploit the complementary strengths of methods, and also to understand how to best represent the analysis problems in different contexts. We consider first the static case where the topology of the virtual infrastructure is fixed and...

  6. 21 CFR 355.20 - Packaging conditions.

    Science.gov (United States)

    2010-04-01

    ... (toothpastes and tooth powders) packages shall not contain more than 276 milligrams (mg) total fluorine per... packages shall not contain more than 120 mg total fluorine per package. (3) Exception. Package...

  7. EBR-II cover-gas cleanup system upgrade

    International Nuclear Information System (INIS)

    Technology advances in the past few years have prompted an effort at Argonne National Laboratory to replace existing equipment with high-performance digital computers and color-graphic displays. Improved operation of process systems can be achieved by utilizing state-of-the-art computer technology in the areas of process control and process monitoring. The cover-gas cleanup system (CGCS) at the Experimental Breeder Reactor II (EBR-II) is the first system to be upgraded with high-performance digital equipment. The upgrade consisted of a main control computer, a distributed control computer, a front-end input/output computer, a main graphics interface terminal, and a remote graphics interface terminal. This paper describes the main control computer and the operator interface control software. Argonne National Laboratory's EBR-II is a pool-type nuclear reactor demonstration facility that uses liquid sodium as the primary system and secondary system coolant. The primary system tank contains ∼330000 ell of liquid sodium blanketed with an argon cover gas. Despite this inert atmosphere, the primary system requires a cover-gas monitoring and cleanup system, the CGCS. The CGCS maintains low levels of impurities in the cover gas so that even small levels of impurities can be detected to flag a failed fuel element and to support mass spectrometer analysis to identify a failed fuel element. Impurities can be introduced to the argon cover gas by the failure of fuel element cladding and the subsequent release of gaseous fission products or xenon open-quotes tag gasclose quotes placed in the fuel elements for the purpose of signaling a fuel element breach. The CGCS consists of a main cleanup loop and a gas analysis system

  8. Hanford: A Conversation About Nuclear Waste and Cleanup

    International Nuclear Information System (INIS)

    The author takes us on a journey through a world of facts, values, conflicts, and choices facing the most complex environmental cleanup project in the United States, the U.S. Department of Energy's Hanford Site. Starting with the top-secret Manhattan Project, Hanford was used to create tons of plutonium for nuclear weapons. Hundreds of tons of waste remain. In an easy-to-read, illustrated text, Gephart crafts the story of Hanford becoming the world's first nuclear weapons site to release large amounts of contaminants into the environment. This was at a time when radiation biology was in its infancy, industry practiced unbridled waste dumping, and the public trusted what it was told. The plutonium market stalled with the end of the Cold War. Public accountability and environmental compliance ushered in a new cleanup mission. Today, Hanford is driven by remediation choices whose outcomes remain uncertain. It's a story whose epilogue will be written by future generations. This book is an information resource, written for the general reader as well as the technically trained person wanting an overview of Hanford and cleanup issues facing the nuclear weapons complex. Each chapter is a topical mini-series. It's an idea guide that encourages readers to be informed consumers of Hanford news, to recognize that knowledge, high ethical standards, and social values are at the heart of coping with Hanford's past and charting its future. Hanford history is a window into many environmental conflicts facing our nation; it's about building upon success and learning from failure. And therein lies a key lesson, when powerful interests are involved, no generation is above pretense. Roy E. Gephart is a geohydrologist and senior program manager at the Pacific Northwest National Laboratory, Richland, Washington. He has 30 years experience in environmental studies and the nuclear waste industry

  9. The value of superfund cleanups : evidence from U.S. Environmental Protection Agency decisions

    OpenAIRE

    Gupta, Shreekant; Van Houtven, George; Cropper, Maureen L.; DEC

    1994-01-01

    Under the Superfund law, the U.S. Environmental Protection Agency (EPA) is responsible for inspecting hazardous waste sites and for putting those with the most serious contamination problems on a national priorities list. The EPA then oversees the cleanup of these sites, suing potentially responsible parties for the costs of cleanup when possible, and funding the cleanup of"orphaned"sites out of the Superfund, money raised taxing chemical and petroleum products. The Superfund program is contr...

  10. Biometric Technologies and Verification Systems

    CERN Document Server

    Vacca, John R

    2007-01-01

    Biometric Technologies and Verification Systems is organized into nine parts composed of 30 chapters, including an extensive glossary of biometric terms and acronyms. It discusses the current state-of-the-art in biometric verification/authentication, identification and system design principles. It also provides a step-by-step discussion of how biometrics works; how biometric data in human beings can be collected and analyzed in a number of ways; how biometrics are currently being used as a method of personal identification in which people are recognized by their own unique corporal or behavior

  11. Space Telescope performance and verification

    Science.gov (United States)

    Wright, W. F.

    1980-01-01

    The verification philosophy for the Space Telescope (ST) has evolved from years of experience with multispacecraft programs modified by the new factors introduced by the Space Transportation System. At the systems level of test, the ST will undergo joint qualification/acceptance tests with environment simulation using Lockheed's large spacecraft test facilities. These tests continue the process of detecting workmanship defects and module interface incompatibilities. The test program culminates in an 'all up' ST environmental test verification program resulting in a 'ready to launch' ST.

  12. EBR-II cover-gas cleanup system

    International Nuclear Information System (INIS)

    Operation of EBR-II with breached elements results in the continuous release of fission gases to the argon cover gas. To control activity in the reactor, a cover-gas cleanup system (CGCS) was installed to remove xenon and krypton from the cover gas by cryogenic distillation. Although only one breached fuel element will, by intention, be in-core during the early stages of the run-beyond-cladding-breach (RBCB) program now under way, the CGCS is designed to handle the activity released by up to 12 mixed-oxide elements

  13. NHC's contribution to cleanup of the Hanford Site

    International Nuclear Information System (INIS)

    The one billion dollars per year Project Hanford Management Contract (PHMC), managed by Fluor Daniel Hanford, calls for cleanup of the Hanford Site for the Department of Energy. Project Hanford comprises four major subprojects, each managed by a different major contractor. Numatec Hanford Corporation (NHC) is a fifth major subcontractor which provides energy and technology to each of the Hanford projects. NHC draws on the experience and capabilities of its parent companies, COGEMA and SGN, and relies on local support from its sister Company in Richland, COGEMA Engineering Corporation, to bring the best commercial practices and new technology to the Project

  14. Fernald restoration: ecologists and engineers integrate restoration and cleanup

    Energy Technology Data Exchange (ETDEWEB)

    Woods, Eric; Homer, John

    2002-07-15

    As cleanup workers excavate pits and tear down buildings at the Fernald site in southwest Ohio, site ecologists are working side-by-side to create thriving wetlands and develop the early stages of forest, prairie, and savanna ecosystems to restore natural resources that were impacted by years of site operations. In 1998, the U.S. Department of Energy-Fernald Office (DOE-FN) and its cleanup contractor, Fluor Fernald, Inc., initiated several ecological restoration projects in perimeter areas of the site (e.g., areas not used for or impacted by uranium processing or waste management). The projects are part of Fernald's final land use plan to restore natural resources over 904 acres of the 1,050-acre site. Pete Yerace, the DOE-FN Natural Resource Trustee representative is working with the Fernald Natural Resource Trustees in an oversight role to resolve the state of Ohio's 1986 claim against DOE for injuries to natural resources. Fluor Fernald, Inc., and DOE-FN developed the ''Natural Resource Restoration Plan'', which outlines 15 major restoration projects for the site and will restore injured natural resources at the site. In general, Fernald's plan includes grading to maximize the formation of wetlands or expanded floodplain, amending soil where topsoil has been removed during excavation, and establishing native vegetation throughout the site. Today, with cleanup over 35 percent complete and site closure targeted for 2006, Fernald is entering a new phase of restoration that involves heavily remediated areas. By working closely with engineers and cleanup crews, site ecologists can take advantage of remediation fieldwork (e.g., convert an excavated depression into a wetland) and avoid unnecessary costs and duplication. This collaboration has also created opportunities for relatively simple and inexpensive restoration of areas that were discovered during ongoing remediation. To ensure the survival of the plant material in heavily

  15. Risky business: Assessing cleanup plans for waste sites

    International Nuclear Information System (INIS)

    ORNL was chosen to perform human health and ecological risk assessments for DOE because of its risk assessment expertise. The U.S. Department of Energy's many production and research sites contain radioactive and hazardous wastes. These waste sites pose potential risks to the health and safety of remediation and waste management workers and the public. The risks, however, vary from site to site. Some sites undoubtedly present larger risks than others and should be cleaned up first. However, before the cleanup begins, DOE is required by law to prepare an environmental impact statement on any actions that may significantly affect the environment-even actions that would clean it up

  16. The TMI-2 clean-up project collection and databases

    International Nuclear Information System (INIS)

    A publicly accessible collection containing several thousand of the videotapes, photographs, slides and technical reports generated during the clean-up of the TMI-2 reactor has been established by the Pennsylvania State University Libraries. The collection is intended to serve as a technical resource for the nuclear industry as well as the interested public. Two Internet-searchable databases describing the videotapes and technical reports have been created. The development and use of these materials and databases are described in this paper. (orig.)

  17. A portable system for decanting and packaging radioactive sludge

    International Nuclear Information System (INIS)

    Several spent fuel storage basins are maintained to support operation of the N Reactor for the U.S. Department of Energy. These basins have systems to filter and demineralize the basin cooling water, but they have not facilities to remove accumulated radioactive sludge on the bottom of the pool. The sludge becomes stirred up during fuel handling operations, thus obscuring vision and increasing the operator radiation exposure in the basin. The portable sludge removal system (SRS) was built to remove accumulated sludge, and decant, solidify, and package it in a form suitable for disposal. Because of the flexible design of the SRS, other applications that have been identified include particulate separation from neutralized waste acid and cleanup of outfall structures and solar evaporation ponds

  18. Land Use and Land Cover - MO 2008 Brownfields Voluntary Cleanup Program Sites (SHP)

    Data.gov (United States)

    NSGIC GIS Inventory (aka Ramona) — The Brownfields/Voluntary Cleanup Program (BVCP) provides property buyers, sellers, developers, bankers, development agencies, local government and other voluntary...

  19. Hanford Long Term Stewardship Program and Transition [Preparing for Environmental Management Cleanup Completion

    International Nuclear Information System (INIS)

    Long-term stewardship (LTS) at the Hanford Site begins at the completion of the U.S. Department of Energy (DOE), Office of Environmental Management (EM) cleanup mission and is the management of the risks (human health and environmental) associated with any residual contamination and the management of the Site's cultural, biological, and natural resources that remain after the Site is reduced to its post-cleanup-mission size. This document describes the anticipated post-cleanup LTS program, the preparations planned to facilitate the safe and timely transition from the completion of the cleanup program to a future LTS program, and when LTS is complete. Although the completion of cleanup remains several decades away, actions are being taken now to ensure the following: DOE's commitment to meet its long-term, post-cleanup obligations is reaffirmed and that its planning efforts to comply with those obligations are visible; The interface between the cleanup program and the LTS program will be clearly defined; Cleanup decisions will include careful and well-documented consideration of their long-term ramifications (e.g., long-term effectiveness and costs) and Potential impediments to a safe and timely turnover from cleanup to LTS are anticipated and a risk management approach is developed and implemented

  20. Chemical Weapons and Problems of Verification

    Directory of Open Access Journals (Sweden)

    P.K. Ramachandran

    1990-01-01

    Full Text Available This paper reviews the existing treaties for ban and verification of the production and use of chemical weapons. The proposed Chemical Weapons Convection, its thrust areas of verifications, the organisations for and process of verification are described briefly. Various technical verification measures including field techniques, such as detector papers, tubes, enzyme tickets, etc. and analytical methods such as gas chromatography, microsensors, different spectrometry methods including IR techniques and stationary system are also discussed.

  1. On Verification Modelling of Embedded Systems

    OpenAIRE

    Brinksma, Ed; Mader, Angelika

    2004-01-01

    Computer-aided verification of embedded systems hinges on the availability of good verification models of the systems at hand. Such models must be much simpler than full design models or specifications to be of practical value, because of the unavoidable combinatorial complexities in the verification of any non-trivial system. Good verification models, therefore, are lean and mean, and cannot be obtained easily or generated automatically. Current research, however, seems to take the construct...

  2. Packaging - Materials review

    Energy Technology Data Exchange (ETDEWEB)

    Herrmann, Matthias [Hoppecke Advanced Battery Technology GmbH, 08056 Zwickau (Germany)

    2014-06-16

    Nowadays, a large number of different electrochemical energy storage systems are known. In the last two decades the development was strongly driven by a continuously growing market of portable electronic devices (e.g. cellular phones, lap top computers, camcorders, cameras, tools). Current intensive efforts are under way to develop systems for automotive industry within the framework of electrically propelled mobility (e.g. hybrid electric vehicles, plug-in hybrid electric vehicles, full electric vehicles) and also for the energy storage market (e.g. electrical grid stability, renewable energies). Besides the different systems (cell chemistries), electrochemical cells and batteries were developed and are offered in many shapes, sizes and designs, in order to meet performance and design requirements of the widespread applications. Proper packaging is thereby one important technological step for designing optimum, reliable and safe batteries for operation. In this contribution, current packaging approaches of cells and batteries together with the corresponding materials are discussed. The focus is laid on rechargeable systems for industrial applications (i.e. alkaline systems, lithium-ion, lead-acid). In principle, four different cell types (shapes) can be identified - button, cylindrical, prismatic and pouch. Cell size can be either in accordance with international (e.g. International Electrotechnical Commission, IEC) or other standards or can meet application-specific dimensions. Since cell housing or container, terminals and, if necessary, safety installations as inactive (non-reactive) materials reduce energy density of the battery, the development of low-weight packages is a challenging task. In addition to that, other requirements have to be fulfilled: mechanical stability and durability, sealing (e.g. high permeation barrier against humidity for lithium-ion technology), high packing efficiency, possible installation of safety devices (current interrupt device

  3. Packaging - Materials review

    International Nuclear Information System (INIS)

    Nowadays, a large number of different electrochemical energy storage systems are known. In the last two decades the development was strongly driven by a continuously growing market of portable electronic devices (e.g. cellular phones, lap top computers, camcorders, cameras, tools). Current intensive efforts are under way to develop systems for automotive industry within the framework of electrically propelled mobility (e.g. hybrid electric vehicles, plug-in hybrid electric vehicles, full electric vehicles) and also for the energy storage market (e.g. electrical grid stability, renewable energies). Besides the different systems (cell chemistries), electrochemical cells and batteries were developed and are offered in many shapes, sizes and designs, in order to meet performance and design requirements of the widespread applications. Proper packaging is thereby one important technological step for designing optimum, reliable and safe batteries for operation. In this contribution, current packaging approaches of cells and batteries together with the corresponding materials are discussed. The focus is laid on rechargeable systems for industrial applications (i.e. alkaline systems, lithium-ion, lead-acid). In principle, four different cell types (shapes) can be identified - button, cylindrical, prismatic and pouch. Cell size can be either in accordance with international (e.g. International Electrotechnical Commission, IEC) or other standards or can meet application-specific dimensions. Since cell housing or container, terminals and, if necessary, safety installations as inactive (non-reactive) materials reduce energy density of the battery, the development of low-weight packages is a challenging task. In addition to that, other requirements have to be fulfilled: mechanical stability and durability, sealing (e.g. high permeation barrier against humidity for lithium-ion technology), high packing efficiency, possible installation of safety devices (current interrupt device

  4. Packaging - Materials review

    Science.gov (United States)

    Herrmann, Matthias

    2014-06-01

    Nowadays, a large number of different electrochemical energy storage systems are known. In the last two decades the development was strongly driven by a continuously growing market of portable electronic devices (e.g. cellular phones, lap top computers, camcorders, cameras, tools). Current intensive efforts are under way to develop systems for automotive industry within the framework of electrically propelled mobility (e.g. hybrid electric vehicles, plug-in hybrid electric vehicles, full electric vehicles) and also for the energy storage market (e.g. electrical grid stability, renewable energies). Besides the different systems (cell chemistries), electrochemical cells and batteries were developed and are offered in many shapes, sizes and designs, in order to meet performance and design requirements of the widespread applications. Proper packaging is thereby one important technological step for designing optimum, reliable and safe batteries for operation. In this contribution, current packaging approaches of cells and batteries together with the corresponding materials are discussed. The focus is laid on rechargeable systems for industrial applications (i.e. alkaline systems, lithium-ion, lead-acid). In principle, four different cell types (shapes) can be identified - button, cylindrical, prismatic and pouch. Cell size can be either in accordance with international (e.g. International Electrotechnical Commission, IEC) or other standards or can meet application-specific dimensions. Since cell housing or container, terminals and, if necessary, safety installations as inactive (non-reactive) materials reduce energy density of the battery, the development of low-weight packages is a challenging task. In addition to that, other requirements have to be fulfilled: mechanical stability and durability, sealing (e.g. high permeation barrier against humidity for lithium-ion technology), high packing efficiency, possible installation of safety devices (current interrupt device

  5. The PIDCalib package

    CERN Document Server

    Anderlini, Lucio; Jones, Christopher Rob; Malde, Sneha Sirirshkumar; Muller, Dominik; Ogilvy, Stephen; Otalora Goicochea, Juan Martin; Pearce, Alex; Polyakov, Ivan; Qian, Wenbin; Sciascia, Barbara; Vazquez Gomez, Ricardo; Zhang, Yanxi

    2016-01-01

    The PIDCalib package is a tool, widely used within the LHCb Collaboration, providing access to the calibration samples of electrons, muons, pions, kaons and protons. This note covers both theoretical aspects related to the measurement of the efficiency of particle identification requirements, and more technical issues such as the selection of the calibration samples, the background subtraction procedure, and the storage of the data sets in the new data-processing scheme adopted by the LHCb experiment during the second run of the LHC.

  6. The Kull IMC package

    International Nuclear Information System (INIS)

    We describe the Kull IMC package, and Implicit Monte Carlo Program written for use in A and X division radiation hydro codes. The Kull IMC has been extensively tested. Written in C++ and using genericity via the template feature to allow easy integration into different codes, the Kull IMC currently runs coupled radiation hydrodynamic problems in 2 different 3D codes. A stand-alone version also exists, which has been parallelized with mesh replication. This version has been run on up to 384 processors on ASCI Blue Pacific

  7. Rock mechanics data package

    International Nuclear Information System (INIS)

    This data package provides a summary of available laboratory and in situ stress field test results from site characterization investigations by the Basalt Waste Isolation Project Modeling and Analysis Group. The objective is to furnish rock mechanics information for use by Rockwell Hanford Operations and their subcontractors in performance assessment and engineering studies. This release includes Reference Repository Location (RRL) site specific laboratory and field test data from boreholes RRL-2, RRL-6, and RRL-14 as well as previous Hanford wide data available as of April, 1985. 25 refs., 9 figs., 16 tabs

  8. Nuclear application software package

    International Nuclear Information System (INIS)

    The Nuclear Application Software Package generates a full-core distribution and power peaking analysis every six minutes during reactor operation. Information for these calculations is provided by a set of fixed incore, self-powered rhodium detectors whose signals are monitored and averaged to obtain input for the software. Following the calculation of a power distribution and its normalization to a core heat balance, the maximum power peaks in the core and minimum DNBR are calculated. Additional routines are provided to calculate the core reactivity, future xenon concentrations, critical rod positions, and assembly isotopic concentrations

  9. The PIDCalib package

    CERN Document Server

    Anderlini, Lucio; Jones, Christopher Rob; Malde, Sneha Sirirshkumar; Muller, Dominik; Ogilvy, Stephen; Otalora Goicochea, Juan Martin; Pearce, Alex; Polyakov, Ivan; Qian, Wenbin; Sciascia, Barbara; Vazquez Gomez, Ricardo; Zhang, Yanxi

    2016-01-01

    The PIDCalib package is a tool, widely used within the LHCb Collaboration, which provides access to the calibration samples of electrons, muons, pions, kaons and protons. This note covers both theoretical aspects related to the measurement of the efficiency of particle identification requirements, and more technical issues such as the selection of the calibration samples, the background subtraction procedure, and the storage of the data sets in the new data-processing scheme adopted by the LHCb experiment during the second run of the LHC.

  10. Packaging-radiation disinfestation relationships

    International Nuclear Information System (INIS)

    Foods that are susceptible to insect infestation can be irradiated to destroy the infestation; however, the food must be kept essentially insect-free until consumed, or it must be disinfested again, perhaps repeatedly. Insect-resistant packages can be used to prevent reinfestation, but there are certain requirements that must be fulfilled before a package can be made insect resistant. These include the use of insect-light construction and packaging materials that resist boring insects. The relative insect resistance of various packages and packaging materials is discussed, as are behavior traits such as egressive boring that enables insects to escape from packages and the ability of insects to climb on various packaging materials. Some successful and unsuccessful attempts to make various types of packages insect resistant are discussed, as are factors that must be considered in the selection or development of insect-resistant packages for radiation disinfested foods. The latter factors include biological and physical environments, length of storage periods, stresses on packages during shipment, types of storage facilities, governmental regulations, health requirements, and others

  11. A restructuring of COR package for MIDAS computer code

    International Nuclear Information System (INIS)

    The COR package, which calculates the thermal response of the core and the lower plenum internal structures and models the relocation of the core and lower plenum structural materials, has been restructured for the MIDAS computer code. MIDAS is being developed as an integrated severe accident analysis code with a user-friendly graphical user interface and a modernized data structure. To do this, the data transferring methods of the current MELCOR code are modified and adopted into the COR package. The data structure of the current MELCOR code using FORTRAN77 has a difficulty in grasping the meaning of the variables as well as a waste of memory. New features of FORTRAN90 make it possible to allocate the storage dynamically and to use the user-defined data type, which leads to an efficient memory treatment and an easy understanding of the code. Restructuring of the COR package addressed in this paper includes a module development, subroutine modification. The verification has been done by comparing the results of the modified code with those of the existing code. As the trends are similar to each other, it implies that the same approach could be extended to the entire code package. It is expected that the code restructuring will accelerated the code's domestication thanks to a direct understanding of each variable and an easy implementation of the modified or newly developed models. (author)

  12. Safety Analysis Report for packaging (onsite) steel waste package

    Energy Technology Data Exchange (ETDEWEB)

    BOEHNKE, W.M.

    2000-07-13

    The steel waste package is used primarily for the shipment of remote-handled radioactive waste from the 324 Building to the 200 Area for interim storage. The steel waste package is authorized for shipment of transuranic isotopes. The maximum allowable radioactive material that is authorized is 500,000 Ci. This exceeds the highway route controlled quantity (3,000 A{sub 2}s) and is a type B packaging.

  13. Safety Analysis Report for packaging (onsite) steel waste package

    International Nuclear Information System (INIS)

    The steel waste package is used primarily for the shipment of remote-handled radioactive waste from the 324 Building to the 200 Area for interim storage. The steel waste package is authorized for shipment of transuranic isotopes. The maximum allowable radioactive material that is authorized is 500,000 Ci. This exceeds the highway route controlled quantity (3,000 A2s) and is a type B packaging

  14. The Package Blueprint: visually analyzing and quantifying package dependencies

    OpenAIRE

    Abdeen, Hani; Ducasse, Stéphane; Pollet, Damien; Alloui, Ilham; Falleri, Jean-Rémy

    2014-01-01

    Large object-oriented applications are structured over many packages. Packages are important but complex structural entities that are difficult to understand since they act as containers of classes, which can have many dependencies with other classes spread over multiple packages. However to be able to take decisions (e.g., refactoring and/or assessment decisions), maintainers face the challenges of managing (sorting, grouping) the massive amount of dependencies between classes spread over mu...

  15. Verification of safety critical software

    International Nuclear Information System (INIS)

    To assure quality of safety critical software, software should be developed in accordance with software development procedures and rigorous software verification and validation should be performed. Software verification is the formal act of reviewing, testing of checking, and documenting whether software components comply with the specified requirements for a particular stage of the development phase[1]. New software verification methodology was developed and was applied to the Shutdown System No. 1 and 2 (SDS1,2) for Wolsung 2,3 and 4 nuclear power plants by Korea Atomic Energy Research Institute(KAERI) and Atomic Energy of Canada Limited(AECL) in order to satisfy new regulation requirements of Atomic Energy Control Boars(AECB). Software verification methodology applied to SDS1 for Wolsung 2,3 and 4 project will be described in this paper. Some errors were found by this methodology during the software development for SDS1 and were corrected by software designer. Outputs from Wolsung 2,3 and 4 project have demonstrated that the use of this methodology results in a high quality, cost-effective product. 15 refs., 6 figs. (author)

  16. Verification and the safeguards legacy

    International Nuclear Information System (INIS)

    A number of inspection or monitoring systems throughout the world over the last decades have been structured drawing upon the IAEA experience of setting up and operating its safeguards system. The first global verification system was born with the creation of the IAEA safeguards system, about 35 years ago. With the conclusion of the NPT in 1968, inspections were to be performed under safeguards agreements, concluded directly between the IAEA and non-nuclear weapon states parties to the Treaty. The IAEA developed the safeguards system within the limitations reflected in the Blue Book (INFCIRC 153), such as limitations of routine access by the inspectors to 'strategic points', including 'key measurement points', and the focusing of verification on declared nuclear material in declared installations. The system, based as it was on nuclear material accountancy. It was expected to detect a diversion of nuclear material with a high probability and within a given time and therefore determine also that there had been no diversion of nuclear material from peaceful purposes. The most vital element of any verification system is the inspector. Technology can assist but cannot replace the inspector in the field. Their experience, knowledge, intuition and initiative are invaluable factors contributing to the success of any inspection regime. The IAEA inspectors are however not part of an international police force that will intervene to prevent a violation taking place. To be credible they should be technically qualified with substantial experience in industry or in research and development before they are recruited. An extensive training program has to make sure that the inspectors retain their professional capabilities and that it provides them with new skills. Over the years, the inspectors and through them the safeguards verification system gained experience in: organization and management of large teams; examination of records and evaluation of material balances

  17. A scheme for symmetrization verification

    OpenAIRE

    Sancho, Pedro

    2011-01-01

    We propose a scheme for symmetrization verification in two-particle systems, based on one-particle detection and state determination. In contrast to previous proposals, it does not follow a Hong-Ou-Mandel-type approach. Moreover, the technique can be used to generate superposition states of single particles.

  18. A scheme for symmetrization verification

    Science.gov (United States)

    Sancho, Pedro

    2011-08-01

    We propose a scheme for symmetrization verification in two-particle systems, based on one-particle detection and state determination. In contrast to previous proposals, it does not follow a Hong-Ou-Mandel-type approach. Moreover, the technique can be used to generate superposition states of single particles.

  19. Eggspectation : organic egg verification tool

    NARCIS (Netherlands)

    Ruth, van S.M.; Hoogenboom, L.A.P.

    2011-01-01

    In 2009 RIKILT conducted a study on about 2,000 eggs to evaluate three different analytical verification methods: carotenoid profiling, fatty acid profiling and isotope ratio mass spectrometry. The eggs were collected from about 50 Dutch farms. The selection was based on the farms’ location and size

  20. VERIFICATION OF WATER QUALITY MODELS

    Science.gov (United States)

    The basic concepts of water quality models are reviewed and the need to recognize calibration and verification of models with observed data is stressed. Post auditing of models after environmental control procedures are implemented is necessary to determine true model prediction ...

  1. A verification environment for bigraphs

    DEFF Research Database (Denmark)

    Perrone, Gian David; Debois, Søren; Hildebrandt, Thomas

    2013-01-01

    We present the BigMC tool for bigraphical reactive systems that may be instantiated as a verification tool for any formalism or domain-specific modelling language encoded as a bigraphical reactive system. We introduce the syntax and use of BigMC, and exemplify its use with two small examples: a t...

  2. Formal Verification of UML Profil

    DEFF Research Database (Denmark)

    Bhutto, Arifa; Hussain, Dil Muhammad Akbar

    2011-01-01

    and object diagrams and behavioral view model by the activity, use case, state, and sequence diagram. However, UML does not provide the formal syntax, therefore its semantics is not formally definable, so for assure of correctness, we need to incorporate semantic reasoning through verification...

  3. A new model for verification

    Institute of Scientific and Technical Information of China (English)

    DU Zhen-jun; MA Guang-sheng; FENG Gang

    2007-01-01

    Formal verification is playing a significant role in IC design. However, the common models for verification either have their complexity problems or have applicable limitations. In order to overcome the deficiencies, a novel model-WGL (Weighted Generalized List) is proposed, which is based on the general-list decomposition of polynomials, with three different weights and manipulation rules introduced to effect node sharing and the canonicity. Timing parameters and operations on them are also considered. Examples show the word-level WGL is the only model to linearly represent the common word-level functions and the bit-level WGL is especially suitable for arithmetic intensive circuits. The model is proved to be a uniform and efficient model for both bitlevel and word-level functions. Then based on the WGL model, a backward-construction verification approach is proposed, which reduces time and space complexity for multipliers to polynomial complexity ( time complexity is less than O( n3.6) and space complexity is less than O( n1.5) ) without hierarchical partitioning. Both the model and the verification method show their theoretical and applicable significance in IC design.

  4. Formal Verification of Continuous Systems

    DEFF Research Database (Denmark)

    Sloth, Christoffer

    2012-01-01

    losses. Furthermore, a malfunction in the control system of a surgical robot may cause death of patients. The previous examples involve complex systems that are required to operate according to complex specifications. The systems cannot be formally verified by modern verification techniques, due to the...

  5. The strategic planning initiative for accelerated cleanup of Rocky Flats

    International Nuclear Information System (INIS)

    The difficulties associated with the congressional funding cycles, regulatory redirection, remediation schedule deadlines, and the lack of a mixed waste (MW) repository have adversely impacted the environmental restoration (ER) program across the entire U.S. Department of Energy (DOE) complex including Rocky Flats Plant (RFP). In an effort to counteract and reduce the impacts of these difficulties, RFP management saw the need for developing a revised ER Program. The objective of the revised ER approach is to identify an initiative that would accelerate the cleanup process and reduce costs without compromising either protection of human health or the environment. A special analysis with that assigned objective was initiated in June 1993 using a team that included DOE Headquarters and Rocky Flats Field Office (RFFO), EG ampersand G personnel, and experts from nationally recognized ER firms. The analysis relied on recent regulatory and process innovations such as DOE's Streamlined Approach for Environmental Restoration (SAFER) and EPA's Superfund Accelerated Cleanup Model (SACM) and Corrective Action Management Units (CAMU). The analysis also incorporated other ongoing improvements efforts initiated by RFP, such as the Quality Action Team and the Integrated Planning Process

  6. Solvent cleanup using base-treated silica gel solid adsorbent

    International Nuclear Information System (INIS)

    A solvent cleanup method using silica gel columns treated with either sodium hydroxide (NaOH) or lithium hydroxide (LiOH) has been investigated. Its effectiveness compares favorably with that of traditional wash methods. After treatment with NaOH solution, the gels adsorb HNO3, dibutyl phosphate (DBP), UO22+, Pu4+, various metal-ion fission products, and other species from the solvent. Adsorption mechanisms include neutralization, hydrolysis, polymerization, and precipitation, depending on the species adsorbed. Sodium dibutyl phosphate, which partially distributes to the solvent from the gels, can be stripped with water; the stripping coefficient ranges from 280 to 540. Adsorption rates are diffusion controlled such that temperature effects are relatively small. Recycle of the gels is achieved either by an aqueous elution and recycle sequence or by a thermal treatment method, which may be preferable. Potential advantages of this solvent cleanup method are that (1) some operational problems are avoided and (2) the amount of NaNO3 waste generated per metric ton of nuclear fuel reprocessed would be reduced significantly. 19 references, 6 figures, 12 tables

  7. Hydrophobic modification of polyurethane foam for oil spill cleanup

    International Nuclear Information System (INIS)

    To improve the oleophilic/hydrophobic properties of polyurethane (PU) foams for oil spill cleanup, PU samples were modified by grafting with oleophilic monomer Lauryl methacrylate (LMA) in solvent and/or coating with LMA microspheres through heating and curing. Modified PU cubes were characterized by field emission scanning electron microscopy (FE-SEM) and Fourier transform infrared spectroscopy (FTIR). The water sorption of modified PU cubes was decreased by 24–50%, while the diesel or kerosene sorption of modified PU cubes was increased by 18–27%. In water–oil system, compared with blank PU cubes, the sorption capacity of PU cubes grafted with LMA was increased by 44% for diesel and 100% for kerosene. The sorption capacity of PU cubes coated with LMA microspheres was increased by 20% for diesel and 7% for kerosene. The solvent sorption of modified PU cubes could reach 50–69 g/g. The modified PU cubes can be effectively used in oil/solvent spill cleanup.

  8. A software tool for soil clean-up technology selection

    International Nuclear Information System (INIS)

    Soil remediation is a difficult, time-consuming and expensive operation. A variety of mature and emerging soil remediation technologies is available and future trends in remediation will include continued competition among environmental service companies and technology developers, which will definitely result in further increase in the clean-up options. Consequently, the demand has enhanced developing decision support tools that could help the decision makers to select the most appropriate technology for the specific contaminated site, before the costly remedial actions are taken. Therefore, a software tool for soil clean-up technology selection is currently being developed with the aim of closely working with human decision makers (site owners, local community representatives, environmentalists, regulators, etc.) to assess the available technologies and preliminarily select the preferred remedial options. The analysis for the identification of the best remedial options is based on technical, financial, environmental, and social criteria. These criteria are ranked by all involved parties to determine their relative importance for a particular project. (author)

  9. Use of decision analysis techniques to determine Hanford cleanup priorities

    International Nuclear Information System (INIS)

    In January 1991, the U.S. Department of Energy (DOE) Richland Field Office, Westinghouse Hanford Company, and the Pacific Northwest Laboratory initiated the Hanford Integrated Planning Process (HIPP) to ensure that technically sound and publicly acceptable decisions are made that support the environmental cleanup mission at Hanford. One of the HIPP's key roles is to develop an understanding of the science and technology (S and T) requirements to support the cleanup mission. This includes conducting an annual systematic assessment of the S and T needs at Hanford to support a comprehensive technology development program and a complementary scientific research program. Basic to success is a planning and assessment methodology that is defensible from a technical perspective and acceptable to the various Hanford stakeholders. Decision analysis techniques were used to help identify and prioritize problems and S and T needs at Hanford. The approach used structured elicitations to bring many Hanford stakeholders into the process. Decision analysis, which is based on the axioms and methods of utility and probability theory, is especially useful in problems characterized by uncertainties and multiple objectives. Decision analysis addresses uncertainties by laying out a logical sequence of decisions, events, and consequences and by quantifying event and consequence probabilities on the basis of expert judgments

  10. A computer program for deriving soil cleanup criteria

    International Nuclear Information System (INIS)

    The US Department of Energy (DOE) has issued a new order, DOE Order 5400.5, for Radiation Protection of the Public and the Environment. In this order, the DOE sets forth radiological protection guidelines for the cleanup of residual radioactive materials. Radionuclide concentrations and radioactivity levels have been established that are acceptable if a site is to be used without radiological restrictions. The guidelines can be categorized as either generic (site independent), that is, taken from existing radiation protection standards, or site specific, that is, derived from the basic dose limit using site-specific data and models. The generic guidelines for soil concentrations of 226Ra, 228Ra, 230Th, and 232Th adopted in DOE Order 5400.5 are generally consistent with US Environmental Protection Agency standards in Title 40, Code of Federal Regulations, Part 192. Procedures and data for deriving site-specific guidelines for other radionuclides in soil have been coded in a microcomputer program called RESRAD. The RESRAD code has been used by the DOE and its contractors to calculate postremediation doses and cleanup guidelines. The RESRAD code is a useful, easy to run, and very user-friendly tool

  11. Aviation safely management, Valdez oil spill clean-up

    International Nuclear Information System (INIS)

    The March 24, 1989 Exxon Valdez oil spill in Alaska's Prince William Sound (PWS) resulted in an unprecedented mobilization of personnel and oil spill clean-up equipment. This paper describes the comprehensive safety management system implemented for aviation operations supporting the clean-up response in PWS and the Gulf of Alaska (GOA). Aviation support operations quickly expanded to over 100 aircraft obtained from numerous sources. Beginning with early surveillance flights, aviation operations were subject to comprehensive safety management programs, including safety assessments, minimum flight weather criteria, operational standards and procedures, air carrier qualifications, equipment and procedure audits, and emergency response. Communication networks and flight following procedures were established, arctic survival training was conducted, and a full complement of survival equipment was required. These programs were largely responsible for safety performance of the spill response effort-during the 1989-92 response activities, over 56,000 flight hours, 159,000 equivalent passengers, and 20,000 tons of cargo were handled without an aviation related injury. The programs are applicable to offshore development and operational activities, particularly those located in more remote, severe environments

  12. Development of physical models and correlation packages for the SPACE code

    International Nuclear Information System (INIS)

    SPACE (Safety and Performance Analysis Code) which is based on a multi-dimensional two-fluid, three-field model is under development for a licensing application of Generation III and III Plus type pressurized water reactors. Several research and industrial organizations are participating in the collaboration of the development program. The main task of KAERI is to develop the physical models and correlation packages which are required to solve the field equations as the closure relationships. This task can be categorized into the development of five packages; 1) a flow regime selection package, 2) a wall and interfacial friction package, 3) an interfacial heat and mass transfer package, 4) a droplet entrainment and de-entrainment package and 5) a wall heat transfer package. Unlike RELAP5, TRACE and CATHARE which are major best-estimate nuclear reactor system analysis codes that only consider liquid and vapor phases, the SPACE code incorporates a dispersed liquid field in addition to vapor and continuous liquid fields; interfacial interaction models between continuous, dispersed liquid phases and vapor phase have to be developed separately. In this paper, a development program for the physical models and correlation packages for the SPACE code including some verification results will be introduced. (author)

  13. EFFECTIVE ENVIRONMENTAL COMPLIANCE STRATEGY FOR THE CLEANUP OF K BASINS AT HANFORD SITE WASHINGTON

    International Nuclear Information System (INIS)

    K Basins, consisting of two water-filled storage basins (KW and KE) for spent nuclear fuel (SNF), are part of the 100-K Area of the Hanford Site, along the shoreline of the Columbia River, situated approximately 40 km (25 miles) northwest of the City of Richland, Washington. The KW contained 964 metric tons of SNF in sealed canisters and the KE contained 1152 metric tons of SNF under water in open canisters. The cladding on much of the fuel was damaged allowing the fuel to corrode and degrade during storage underwater. An estimated 1,700 cubic feet of sludge, containing radionuclides and sediments, have accumulated in the KE basin. Various alternatives for removing and processing the SNF, sludge, debris and water were originally evaluated, by USDOE (DOE), in the Environmental Impact Statement (EIS) with a preferred alternative identified in the Record of Decision. The SNF, sludge, debris and water are ''hazardous substances'' under the Comprehensive, Environmental, Response, Compensation and Liability Act of 1980 (CERCLA). Leakage of radiologically contaminated water from one of the basins and subsequent detection of increased contamination in a down-gradient monitoring well helped to form the regulatory bases for cleanup action under CERCLA. The realization that actual or threatened release of hazardous substances from the waste sites and K Basins, if not addressed in a timely manner, may present an imminent and substantial endangerment to public health, welfare and environment led to action under CERCLA, with EPA as the lead regulatory agency. Clean-up of the K Basins as a CERCLA site required SNF retrieval, processing, packaging, vacuum drying and transport to a vaulted storage facility for storage, in conformance with a quality assurance program approved by the Office of Civilian Radioactive Waste Management (OCRWM). Excluding the facilities built for SNF drying and vaulted storage, the scope of CERCLA interim remedial action was limited to the removal of fuel

  14. HPLOT: the graphics interface package for the HBOOK histogramming package

    International Nuclear Information System (INIS)

    The subroutine package HPLOT described in this report, enables the CERN histogramming package HBOOK to produce high-quality pictures by means of high-resolution devices such as plotters. HPLOT can be implemented on any scientific computing system with a Fortran IV compiler and can be interfaced with any graphics package; spectral routines in addition to the basic ones enable users to embellish their histograms. Examples are also given of the use of HPLOT as a graphics package for plotting simple pictures without histograms. (Auth.)

  15. CH Packaging Operations Manual

    International Nuclear Information System (INIS)

    This document provides the user with instructions for assembling a payload. All the steps in Subsections 1.2, Preparing 55-Gallon Drum Payload Assembly; 1.3, Preparing 'Short' 85-Gallon Drum Payload Assembly (TRUPACT-II and HalfPACT); 1.4, Preparing 'Tall' 85-gallon Drum Payload Assembly (HalfPACT only); 1.5, Preparing 100-Gallon Drum Payload Assembly; 1.6, Preparing SWB Payload Assembly; and 1.7, Preparing TDOP Payload Assembly, must be completed, but may be performed in any order as long as radiological control steps are not bypassed. Transport trailer operations, package loading and unloading from transport trailers, hoisting and rigging activities such as ACGLF operations, equipment checkout and shutdown, and component inspection activities must be performed, but may be performed in any order and in parallel with other activities as long as radiological control steps are not bypassed. Steps involving OCA/ICV lid removal/installation and payload removal/loading may be performed in parallel if there are multiple operators working on the same packaging. Steps involving removal/installation of OCV/ICV upper and lower main O-rings must be performed in sequence.

  16. CH Packaging Operations Manual

    International Nuclear Information System (INIS)

    This document provides the user with instructions for assembling a payload. All the steps in Subsections 1.2, Preparing 55-Gallon Drum Payload Assembly; 1.3, Preparing 'Short' 85-Gallon Drum Payload Assembly (TRUPACT-II and HalfPACT); 1.4, Preparing 'Tall' 85-Gallon Drum Payload Assembly (HalfPACT only); 1.5, Preparing 100-Gallon Drum Payload Assembly; 1.6, Preparing Shielded Container Payload Assembly; 1.7, Preparing SWB Payload Assembly; and 1.8, Preparing TDOP Payload Assembly, must be completed, but may be performed in any order as long as radiological control steps are not bypassed. Transport trailer operations, package loading and unloading from transport trailers, hoisting and rigging activities such as ACGLF operations, equipment checkout and shutdown, and component inspection activities must be performed, but may be performed in any order and in parallel with other activities as long as radiological control steps are not bypassed. Steps involving OCA/ICV lid removal/installation and payload removal/loading may be performed in parallel if there are multiple operators working on the same packaging. Steps involving removal/installation of OCV/ICV upper and lower main O-rings must be performed in sequence, except as noted.

  17. Japan's electronic packaging technologies

    Science.gov (United States)

    Tummala, Rao R.; Pecht, Michael

    1995-01-01

    The JTEC panel found Japan to have significant leadership over the United States in the strategic area of electronic packaging. Many technologies and products once considered the 'heart and soul' of U.S. industry have been lost over the past decades to Japan and other Asian countries. The loss of consumer electronics technologies and products is the most notable of these losses, because electronics is the United States' largest employment sector and is critical for growth businesses in consumer products, computers, automobiles, aerospace, and telecommunications. In the past there was a distinction between consumer and industrial product technologies. While Japan concentrated on the consumer market, the United States dominated the industrial sector. No such distinction is anticipated in the future; the consumer-oriented technologies Japan has dominated are expected to characterize both domains. The future of U.S. competitiveness will, therefore, depend on the ability of the United States to rebuild its technological capabilities in the area of portable electronic packaging.

  18. IN-PACKAGE CHEMISTRY ABSTRACTION

    Energy Technology Data Exchange (ETDEWEB)

    E. Thomas

    2005-07-14

    This report was developed in accordance with the requirements in ''Technical Work Plan for Postclosure Waste Form Modeling'' (BSC 2005 [DIRS 173246]). The purpose of the in-package chemistry model is to predict the bulk chemistry inside of a breached waste package and to provide simplified expressions of that chemistry as a function of time after breach to Total Systems Performance Assessment for the License Application (TSPA-LA). The scope of this report is to describe the development and validation of the in-package chemistry model. The in-package model is a combination of two models, a batch reactor model, which uses the EQ3/6 geochemistry-modeling tool, and a surface complexation model, which is applied to the results of the batch reactor model. The batch reactor model considers chemical interactions of water with the waste package materials, and the waste form for commercial spent nuclear fuel (CSNF) waste packages and codisposed (CDSP) waste packages containing high-level waste glass (HLWG) and DOE spent fuel. The surface complexation model includes the impact of fluid-surface interactions (i.e., surface complexation) on the resulting fluid composition. The model examines two types of water influx: (1) the condensation of water vapor diffusing into the waste package, and (2) seepage water entering the waste package as a liquid from the drift. (1) Vapor-Influx Case: The condensation of vapor onto the waste package internals is simulated as pure H{sub 2}O and enters at a rate determined by the water vapor pressure for representative temperature and relative humidity conditions. (2) Liquid-Influx Case: The water entering a waste package from the drift is simulated as typical groundwater and enters at a rate determined by the amount of seepage available to flow through openings in a breached waste package.

  19. Packaging investigation of optoelectronic devices

    Science.gov (United States)

    Zhike, Zhang; Yu, Liu; Jianguo, Liu; Ninghua, Zhu

    2015-10-01

    Compared with microelectronic packaging, optoelectronic packaging as a new packaging type has been developed rapidly and it will play an essential role in optical communication. In this paper, we try to summarize the development history, research status, technology issues and future prospects, and hope to provide a meaningful reference. Project supported by the National High Technology Research and Development Program of China (Nos. 2013AA014201, 2013AA014203) and the National Natural Science Foundation of China (Nos. 61177080, 61335004, 61275031).

  20. Creating R Packages: A Tutorial

    OpenAIRE

    Leisch, Friedrich

    2008-01-01

    This tutorial gives a practical introduction to creating R packages. We discuss how object oriented programming and S formulas can be used to give R code the usual look and feel, how to start a package from a collection of R functions, and how to test the code once the package has been created. As running example we use functions for standard linear regression analysis which are developed from scratch.

  1. K east encapsulation packager modifications

    International Nuclear Information System (INIS)

    This Supporting Document analyzes a proposal for reducing the under-packager volume to decrease the amount of fissile material that could accumulate there. The analysis shows that restricting the under packager volume to no more than 4080 in3 will assure that if accumulated fissile material beneath the packager is added to the worst-case mass of fissile material in the discharge chute, a keff of 0.98 will not be exceeded

  2. Laser Sealed Packaging for Microsystems

    OpenAIRE

    Seigneur, Frank; JACOT, Jacques

    2006-01-01

    Packaging is the last process of microsystem manufacturing. There are mainly two kinds of packages: plastic or metallic. The two main components of the package (base and cover) may either be glued or soldered. Each of these techniques has its advantages and drawbacks, and the choice should be driven by the functionality of the microsystem. The advantage of gluing is that it is quite an easy production process. The drawback is that glue, like all polymers, is not hermetic on the long te...

  3. IN-PACKAGE CHEMISTRY ABSTRACTION

    International Nuclear Information System (INIS)

    This report was developed in accordance with the requirements in ''Technical Work Plan for Postclosure Waste Form Modeling'' (BSC 2005 [DIRS 173246]). The purpose of the in-package chemistry model is to predict the bulk chemistry inside of a breached waste package and to provide simplified expressions of that chemistry as a function of time after breach to Total Systems Performance Assessment for the License Application (TSPA-LA). The scope of this report is to describe the development and validation of the in-package chemistry model. The in-package model is a combination of two models, a batch reactor model, which uses the EQ3/6 geochemistry-modeling tool, and a surface complexation model, which is applied to the results of the batch reactor model. The batch reactor model considers chemical interactions of water with the waste package materials, and the waste form for commercial spent nuclear fuel (CSNF) waste packages and codisposed (CDSP) waste packages containing high-level waste glass (HLWG) and DOE spent fuel. The surface complexation model includes the impact of fluid-surface interactions (i.e., surface complexation) on the resulting fluid composition. The model examines two types of water influx: (1) the condensation of water vapor diffusing into the waste package, and (2) seepage water entering the waste package as a liquid from the drift. (1) Vapor-Influx Case: The condensation of vapor onto the waste package internals is simulated as pure H2O and enters at a rate determined by the water vapor pressure for representative temperature and relative humidity conditions. (2) Liquid-Influx Case: The water entering a waste package from the drift is simulated as typical groundwater and enters at a rate determined by the amount of seepage available to flow through openings in a breached waste package

  4. About the ZOOM minimization package

    Energy Technology Data Exchange (ETDEWEB)

    Fischler, M.; Sachs, D.; /Fermilab

    2004-11-01

    A new object-oriented Minimization package is available for distribution in the same manner as CLHEP. This package, designed for use in HEP applications, has all the capabilities of Minuit, but is a re-write from scratch, adhering to modern C++ design principles. A primary goal of this package is extensibility in several directions, so that its capabilities can be kept fresh with as little maintenance effort as possible. This package is distinguished by the priority that was assigned to C++ design issues, and the focus on producing an extensible system that will resist becoming obsolete.

  5. Natural gas production verification tests

    International Nuclear Information System (INIS)

    This Environmental Assessment (EA) has been prepared by the Department of Energy (DOE) in compliance with the requirements of the National Environmental Policy Act of 1969. The Department of Energy (DOE) proposes to fund, through a contract with Petroleum Consulting Services, Inc. of Canton, Ohio, the testing of the effectiveness of a non-water based hydraulic fracturing treatment to increase gas recovery from low-pressure, tight, fractured Devonian Shale formations. Although Devonian Shales are found in the Appalachian, Michigan, and Illinois Basins, testing will be done only in the dominant, historical five state area of established production. The objective of this proposed project is to assess the benefits of liquid carbon dioxide (CO2)/sand stimulations in the Devonian Shale. In addition, this project would evaluate the potential nondamaging (to the formation) properties of this unique fracturing treatment relative to the clogging or chocking of pores and fractures that act as gas flow paths to the wellbore in the target gas-producing zones of the formation. This liquid CO2/sand fracturing process is water-free and is expected to facilitate gas well cleanup, reduce the time required for post-stimulation cleanup, and result in improved production levels in a much shorter time than is currently experienced

  6. 40 CFR 312.25 - Searches for recorded environmental cleanup liens.

    Science.gov (United States)

    2010-07-01

    ... local law. (b) All information collected regarding the existence of such environmental cleanup liens... 40 Protection of Environment 27 2010-07-01 2010-07-01 false Searches for recorded environmental cleanup liens. 312.25 Section 312.25 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY...

  7. Preliminary cleanup activities at vicinity properties near Salt Lake City, Utah: Environmental assessment

    International Nuclear Information System (INIS)

    This document describes the preliminary cleanup activities and their impacts for the approximately 100 properties in Salt Lake Valley that have been contaminated by radioactive tailings from the site of the inactive Vitro uranium mill. The 23 properties already included on the official list for cleanup have been used as the basis for estimating impacts at all 100 sites

  8. Development of a risk-based approach to Hanford Site cleanup

    International Nuclear Information System (INIS)

    In response to a request from Mr. Thomas Grumbly, Assistant Secretary of Energy for Environmental Management, the Hanford Site contractors developed a conceptual set of risk-based cleanup strategies that (1) protect the public, workers, and environment from unacceptable risks; (2) are executable technically; and (3) fit within an expected annual funding profile of 1.05 billion dollars. These strategies were developed because (1) the US Department of Energy and Hanford Site budgets are being reduced, (2) stakeholders are dissatisfied with the perceived rate of cleanup, (3) the US Congress and the US Department of Energy are increasingly focusing on risk and riskreduction activities, (4) the present strategy is not integrated across the Site and is inconsistent in its treatment of similar hazards, (5) the present cleanup strategy is not cost-effective from a risk-reduction or future land use perspective, and (6) the milestones and activities in the Tri-Party Agreement cannot be achieved with an anticipated funding of 1.05 billion dollars annually. The risk-based strategies described herein were developed through a systems analysis approach that (1) analyzed the cleanup mission; (2) identified cleanup objectives, including risk reduction, land use, and mortgage reduction; (3) analyzed the existing baseline cleanup strategy from a cost and risk perspective; (4) developed alternatives for accomplishing the cleanup mission; (5) compared those alternatives against cleanup objectives; and (6) produced conclusions and recommendations regarding the current strategy and potential risk-based strategies

  9. Techniques for laser spectroscopy of actinide elements: developments in the clean-up process

    International Nuclear Information System (INIS)

    Configuration of an efficient laser clean-up process requires a large amount of basic atomic data provided by careful high resolution spectroscopic experiments involving one or several lasers, both pulsed and cw. Efforts in developing such sources for high resolution spectroscopy in the context of the clean-up process are discussed

  10. Full automatic clean-up robot for dioxin/PCB analysis

    Energy Technology Data Exchange (ETDEWEB)

    Matsumura, T.; Masuzaki, Y.; Takahashi, A.; Koizumi, A. [METOCEAN Environment Inc., Shizuoka (Japan). Environmental Risk Research Center, Inst. of General Science for Environment; Okuyama, H.; Kawada, Y.; Higashiguchi, T. [Moritex Corporation, Yokohama (Japan)

    2004-09-15

    Dioxin analysis requires several steps of clean-up procedures by combination of several column chromatography (e.g. silica gel column chromatography, carbon column chromatography) and sulfuric acid treatment. Full Automatic Clean-up Robot for Dioxin and PCB were developed.

  11. Development of a risk-based approach to Hanford Site cleanup

    Energy Technology Data Exchange (ETDEWEB)

    Hesser, W.A.; Daling, P.M. [Pacific Northwest Lab., Richland, WA (United States); Baynes, P.A. [Westinghouse Hanford Co., Richland, WA (United States)] [and others

    1995-06-01

    In response to a request from Mr. Thomas Grumbly, Assistant Secretary of Energy for Environmental Management, the Hanford Site contractors developed a conceptual set of risk-based cleanup strategies that (1) protect the public, workers, and environment from unacceptable risks; (2) are executable technically; and (3) fit within an expected annual funding profile of 1.05 billion dollars. These strategies were developed because (1) the US Department of Energy and Hanford Site budgets are being reduced, (2) stakeholders are dissatisfied with the perceived rate of cleanup, (3) the US Congress and the US Department of Energy are increasingly focusing on risk and riskreduction activities, (4) the present strategy is not integrated across the Site and is inconsistent in its treatment of similar hazards, (5) the present cleanup strategy is not cost-effective from a risk-reduction or future land use perspective, and (6) the milestones and activities in the Tri-Party Agreement cannot be achieved with an anticipated funding of 1.05 billion dollars annually. The risk-based strategies described herein were developed through a systems analysis approach that (1) analyzed the cleanup mission; (2) identified cleanup objectives, including risk reduction, land use, and mortgage reduction; (3) analyzed the existing baseline cleanup strategy from a cost and risk perspective; (4) developed alternatives for accomplishing the cleanup mission; (5) compared those alternatives against cleanup objectives; and (6) produced conclusions and recommendations regarding the current strategy and potential risk-based strategies.

  12. Monitoring methods for determining compliance with decommissioning cleanup criteria at uranium recovery sites

    International Nuclear Information System (INIS)

    Decommissioning of a uranium processing site requires radiological surveys to: (1) identify buildings, equipment, and open land areas that require cleanup; (2) verify that cleanup operations have been successful; and (3) provide a record of the radiological condition of the site following cleanup. This report describes the instruments, measurements, quality assurance, and statistical procedures that can be used to perform pre- and post-cleanup surveys. The procedures described include: (1) gamma-radiation exposure-rate measurements using micro-R-meters, (2) beta-gamma measurements using Geiger-Mueller tubes, (3) wipe tests for surface contamination, and (4) soil analyses for 226Ra and other 238U daughters. During the pre-cleanup survey, locations likely to have 226Ra concentrations that exceed standards can be identified by gamma-radiation exposure-rate measurements. Samples of soil or other material from locations showing elevated exposure rates then can be analyzed for 226Ra to determine the boundaries of areas that exceed standards. Measurements of 238U in the samples can be used to determine whether the 226Ra is due to mill tailings. Beta-gamma measurements and wipe-sample analyses at locations that are suspected of being contaminated with uranium can be used to determine whether uranium concentrations exceed standards for either fixed or removable contamination. A post-cleanup survey that is similar to the pre-cleanup survey can be used to verify that cleanup has been successful. 16 refs

  13. Acceptance and tracking of waste packages from nuclear power plants at the Centre de l'Aube

    International Nuclear Information System (INIS)

    For 30 years, the French National Agency for Radioactive Waste Management (ANDRA) is in charge of the radioactive waste management and acquired a good knowledge relating to the control of low and intermediate level waste produced by nuclear power plants (NPP), the waste characteristics and the waste conditioning. The integrated waste management system for low-level radioactive waste in France implemented by ANDRA covers all stages from waste generation to final disposal at the Centre de I'Aube near surface facility. ANDRA defined a quality assurance program for waste management that specifies the level of quality to be achieved by solidification and packaging processes, defines quality control requirements and defines waste tracking requirements, from waste generation through final disposal. Verification of quality of waste packages is implemented at three levels of the waste management system. The first one consists of inspections of waste packages at the generator's premises and audits of the quality assurance organization of the waste generator. The second level of verification consists of the waste tracking system. It allows identifying and tracking each waste package from the step it is fabricated to its final disposal at the ANDRA site. The third level of verification is obtained by mean of non-destructive and destructive assays of waste packages. These assays allow to verify generator compliance with ANDRA's technical specifications and to investigate the accuracy of physical and radioactive characteristics reported to ANDRA by the generator. (author)

  14. Pursing other deep pockets: California's underground storage tank cleanup fund and insurance policies

    International Nuclear Information System (INIS)

    When faced with a potentially very expensive environmental cleanup, most companies and individuals try to do the only sensible thing, which is to find out if anyone else will pay the bill. This presentation will outline two avenues that may provide a substantial financial contribution to environmental cleanups: (a) California's Underground Storage Tank Cleanup Fund and (b) insurance policies. The Underground Storage Tank Cleanup Fund was established in 1989 to help eligible owners and operators of petroleum underground storage tanks (USTs) to: (a) get reimbursed for costs of unauthorized releases of petroleum from USTs; (b) get reimbursed for damages awarded to third parties as a result of unauthorized releases of petroleum from USTs; and (c) meet federal and state requirements that the UST owner and/or operator be able to pay for cleanup costs and damages to third parties caused by unauthorized releases of petroleum

  15. Statistical design and analysis in the cleanup of environmental radionuclide contamination. DRI publication No. 45012

    International Nuclear Information System (INIS)

    The cleanup of Eniwetok Island before the return of former residents is discussed. Of the contaminants in the soil of the atoll, the most important for cleanup are Pu-238, 239,240, and Am-241, which are present in sufficient quantities to require cleanup, and isotopes of Sr and Cs which also are present and must be considered since these elements can be taken up by food plants such as coconut, pandanus, and breadfruit, and passed on to man. The design of the cleanup sampling program is described. In addition to soil contamination, much metal and concrete debris, not all of it contaminated, as well as buildings and equipment, remain from the testing. The clean-up agreement covered all of this material, contaminated or not

  16. Geometry methods and packages

    International Nuclear Information System (INIS)

    The authors address the problem of following the trajectory of a particle in simulations. It is necessary to follow the motion of the particle, and to determine its intersection with different geometric surfaces in the problem, in order to relate the stepping of the particle trajectory into real motion through the physical problem at hand. The distance a particle moves before encountering a surface is needed to compare with the actual transport distance that is about to be used in the simulation. Basic mathematical expressions are developed for the intersections of particle trajectories with plane and conic surfaces. The authors show how these are used in the EGS4 code system, which should be typical of the general problem. They also review geometry packages currently being used in electron-photon Monte Carlo programs

  17. Tritium waste package

    Science.gov (United States)

    Rossmassler, Rich; Ciebiera, Lloyd; Tulipano, Francis J.; Vinson, Sylvester; Walters, R. Thomas

    1995-01-01

    A containment and waste package system for processing and shipping tritium xide waste received from a process gas includes an outer drum and an inner drum containing a disposable molecular sieve bed (DMSB) seated within outer drum. The DMSB includes an inlet diffuser assembly, an outlet diffuser assembly, and a hydrogen catalytic recombiner. The DMSB absorbs tritium oxide from the process gas and converts it to a solid form so that the tritium is contained during shipment to a disposal site. The DMSB is filled with type 4A molecular sieve pellets capable of adsorbing up to 1000 curies of tritium. The recombiner contains a sufficient amount of catalyst to cause any hydrogen add oxygen present in the process gas to recombine to form water vapor, which is then adsorbed onto the DMSB.

  18. Electronic equipment packaging technology

    CERN Document Server

    Ginsberg, Gerald L

    1992-01-01

    The last twenty years have seen major advances in the electronics industry. Perhaps the most significant aspect of these advances has been the significant role that electronic equipment plays in almost all product markets. Even though electronic equipment is used in a broad base of applications, many future applications have yet to be conceived. This versatility of electron­ ics has been brought about primarily by the significant advances that have been made in integrated circuit technology. The electronic product user is rarely aware of the integrated circuits within the equipment. However, the user is often very aware of the size, weight, mod­ ularity, maintainability, aesthetics, and human interface features of the product. In fact, these are aspects of the products that often are instrumental in deter­ mining its success or failure in the marketplace. Optimizing these and other product features is the primary role of Electronic Equipment Packaging Technology. As the electronics industry continues to pr...

  19. Clean-up criteria for remediation of contaminated soils

    International Nuclear Information System (INIS)

    'How clean is clean?' is a question commonly raised in the remediation of contaminated soils. To help with the answer, criteria are proposed to serve as guidelines for remedial actions and to define a clean-up level such that the remaining contaminant residuals in the soil will not violate the Drinking Water Standards (DWS). The equations for computing those criteria are developed from the principle of conservation of mass and are functions of the maximum concentration level in the water (MCL) and the sorption coefficient. A multiplier, ranging from 10 to 1000, is also factored into the soil standard equation to reflect the effectiveness of various remediation techniques. Maximum allowable concentration in the soil (MSCL) is presented for several contaminants which are being regulated at the present time. Future modifications are recommended for better estimates of the MSCLs as additional transport mechanisms are incorporated to account for other potentially dominant effects

  20. Statistical methods for evaluating the attainment of cleanup standards

    Energy Technology Data Exchange (ETDEWEB)

    Gilbert, R.O.; Simpson, J.C.

    1992-12-01

    This document is the third volume in a series of volumes sponsored by the US Environmental Protection Agency (EPA), Statistical Policy Branch, that provide statistical methods for evaluating the attainment of cleanup Standards at Superfund sites. Volume 1 (USEPA 1989a) provides sampling designs and tests for evaluating attainment of risk-based standards for soils and solid media. Volume 2 (USEPA 1992) provides designs and tests for evaluating attainment of risk-based standards for groundwater. The purpose of this third volume is to provide statistical procedures for designing sampling programs and conducting statistical tests to determine whether pollution parameters in remediated soils and solid media at Superfund sites attain site-specific reference-based standards. This.document is written for individuals who may not have extensive training or experience with statistical methods. The intended audience includes EPA regional remedial project managers, Superfund-site potentially responsible parties, state environmental protection agencies, and contractors for these groups.

  1. Soil, groundwater cleanup takes the gamble out of casino operation

    International Nuclear Information System (INIS)

    Colorado's rich stores of gold and silver sparked development of towns like Black Hawk and Central City in the 1890s. Today, these communities are the homes of limited-stakes gaming operations. However casino operators are discovering that having gold and silver underground in the form of tailings is not as desirable as collecting it aboveground in slot machines. A unique environmental engineering approach allowed construction of two new casinos and reclamation of the tailings, as well as cleanup of petroleum-saturated soils and groundwater. A treatment system was designed and constructed to treat groundwater at the Black Hawk site. The most economical alternative for disposing treated groundwater was to discharge it into nearby North Clear Creek. An NPDES permit was obtained requiring treatment of the groundwater for petroleum, heavy metals and pH before discharging it

  2. Hot Chili Peppers: Extraction, Cleanup, and Measurement of Capsaicin

    Science.gov (United States)

    Huang, Jiping; Mabury, Scott A.; Sagebiel, John C.

    2000-12-01

    Capsaicin, the pungent ingredient of the red pepper or Capsicum annuum, is widely used in food preparation. The purpose of this experiment was to acquaint students with the active ingredients of hot chili pepper (capsaicin and dihydrocapsaicin), the extraction, cleanup, and analysis of these chemicals, as a fun and informative analytical exercise. Fresh peppers were prepared and extracted with acetonitrile, removing plant co-extractives by addition to a C-18 solid-phase extraction cartridge. Elution of the capsaicinoids was accomplished with a methanol-acetic acid solution. Analysis was completed by reverse-phase HPLC with diode-array or variable wavelength detection and calibration with external standards. Levels of capsaicin and dihydrocapsaicin were typically found to correlate with literature values for a specific hot pepper variety. Students particularly enjoyed relating concentrations of capsaicinoids to their perceived valuation of "hotness".

  3. RCRA corrective action: Action levels and media cleanup standards

    International Nuclear Information System (INIS)

    This Information Brief describes how action levels (ALs), which are used to determine if it is necessary to perform a Corrective Measures Study (CMS), and media cleanup standards (MCSs), which are used to set the standards for remediation performed in conjunction with Corrective Measures Implementation (CMI) are set. It is one of a series of Information Briefs on RCRA Corrective Action. ALs are health-and-environmentally-based levels of hazardous constituents in ground water, surface water, soil, or air, determined to be indicators for protection of human health and the environment. In the corrective action process, the regulator uses ALs to determine if the owner/operator of a treatment, storage, or disposal facility is required to perform a CMS

  4. The Fort McMurray Historic Uranium Cleanup Project

    Energy Technology Data Exchange (ETDEWEB)

    Geddes, R.B. [AMEC Earth and Environmental, Environmental Div., Oakville, Ontario (Canada)]. E-mail: brian.geddes@amec.com; Case, G.G. [Atomic Energy of Canada Limited, Port Hope, Ontario (Canada)]. E-mail: caseg@aecl.ca; Doney, R. [Marshall Macklin Moaghan Limited, Environmental Management, Thornhill, Ontario (Canada)]. E-mail: Doneyr@mmm.ca

    2006-07-01

    The Fort McMurray Historic Uranium Cleanup Project involved the removal of 42,000 m{sup 3} of soils contaminated with uranium ores and ore concentrates from various properties in the City of Fort McMurray, Alberta. These soils were placed into long-term management in a dedicated, locally developed and secure facility. The soil contamination addressed by the program was the result of incidental spillage and tracking of ores during the unloading of barges and the loading of rail cars as materials were transported via Fort McMurray from uranium mines in the Northwest Territories to a refinery in Port Hope, Ontario. The project was executed over a 10- year time period, involved the participation of the local community at critical junctures, and restored 28 ha of land to productive use. (author)

  5. Williston Reservoir: Site preparation and post-flood cleanup

    International Nuclear Information System (INIS)

    Williston Reservoir is the second largest in Canada and ranks ninth on the world scale. It was formed by the construction of the W.A.C. Bennet Dam and is the most important hydroelectric storage reservoir and largest body of fresh water in British Columbia. Site preparation for the reservoir began in 1962, with pre-flood clearing involving salvage of merchantable timber, handfalling, machine downing, burning of slash and burial. Post-flood cleanup included timber salvage, bailing and burning debris, tractor piling and burning, crane piling in shallows, underwater cutting, and hand cutting during low drawdown. Various types of floating debris have presented problems for recreational use, log booming and transport, waterways and aviation. Protection of the spillway is accomplished with a floating boom upstream of the channel. Administration, funding, forest clearance, salvage methods, clearing standards, wood volumes, project costs, environmental concerns, and future priorities are discussed. 5 figs., 2 tabs

  6. Technologies for environmental cleanup: Toxic and hazardous waste management

    International Nuclear Information System (INIS)

    This is the second in a series of EUROCOURSES conducted under the title, ''Technologies for Environmental Cleanup.'' To date, the series consist of the following courses: 1992, soils and groundwater; 1993, Toxic and Hazardous Waste Management. The 1993 course focuses on recent technological developments in the United States and Europe in the areas of waste management policies and regulations, characterization and monitoring of waste, waste minimization and recycling strategies, thermal treatment technologies, photolytic degradation processes, bioremediation processes, medical waste treatment, waste stabilization processes, catalytic organic destruction technologies, risk analyses, and data bases and information networks. It is intended that this course ill serve as a resource of state-of-the-art technologies and methodologies for the environmental protection manager involved in decisions concerning the management of toxic and hazardous waste

  7. Formal Verification of Quantum Protocols

    CERN Document Server

    Nagarajan, R; Nagarajan, Rajagopal; Gay, Simon

    2002-01-01

    We propose to analyse quantum protocols by applying formal verification techniques developed in classical computing for the analysis of communicating concurrent systems. One area of successful application of these techniques is that of classical security protocols, exemplified by Lowe's discovery and fix of a flaw in the well-known Needham-Schroeder authentication protocol. Secure quantum cryptographic protocols are also notoriously difficult to design. Quantum cryptography is therefore an interesting target for formal verification, and provides our first example; we expect the approach to be transferable to more general quantum information processing scenarios. The example we use is the quantum key distribution protocol proposed by Bennett and Brassard, commonly referred to as BB84. We present a model of the protocol in the process calculus CCS and the results of some initial analyses using the Concurrency Workbench of the New Century (CWB-NC).

  8. Soil and groundwater cleanup: benefits and limits of emerging technologies

    Energy Technology Data Exchange (ETDEWEB)

    Caliman, Florentina Anca; Robu, Brindusa Mihaela; Smaranda, Camelia; Pavel, Vasile Lucian; Gavrilescu, Maria [Technical University of Iasi, Department of Environmental Engineering and Management, Faculty of Chemical Engineering and Environmental Protection, Iasi (Romania)

    2011-04-15

    Contaminated soil and groundwater have been the subject of study and research, so that the field of remediation has grown and evolved, continually developing and adopting new technologies in attempts to improve the decontamination. The cleanup of environmental pollution involves a variety of techniques, ranging from simple biological processes to advanced engineering technologies. Cleanup activities may also address a wide range of contaminants. This article is a short analysis of the technologies for cleaning up groundwater and soil, highlighting knowledge and information gaps. Challenges and strategies for cleaning up different types of contaminants, mainly heavy metals and persistent organic compounds are described. Included are technologies that treat ground water contaminants in place in the subsurface and soil technologies that treat the soil either in place or on site in a treatment unit. Emerging technologies such as those based on oxidation-reduction, bioremediation, and nanotechnologies are covered. It is evident that for a good efficiency of remediation, techniques or even whole new technologies may be incorporated into an existing technology as a treatment train, improving its performance or overcome limitations. Several economic and decision-making elements are developed in the final part, based on the analysis carried out throughout the article. The work highlights the fact that excellence in research and technology progress could be attained by the development of technologies to deal more effectively and economically with certain toxic contaminants such as heavy metals, volatile organic compounds, and persistent organic pollutants, associated with optimization of technologies under field remediation conditions and requirements, improving capacity and yields, and reducing costs. Moreover, increasing knowledge of the scope and problem of equipment development could improve the benefits. (orig.)

  9. Plutonium contamination at Maralinga - dosimetry and clean-up criteria

    International Nuclear Information System (INIS)

    An area of South Australia remained contaminated following British nuclear weapons tests at Maralinga during 1955 - 1963. Of importance is the long-lived 239-Pu of which some 24 kg was explosively dispersed in several 'minor trials'. The extent, quantities and physical characteristics of the plutonium have been assessed and estimates of dose, dominated by the inhalation pathway in the critical group of Aborigines living a semi-traditional lifestyle, have been made for potential occupants. Rehabilitation of the most contaminated areas is underway, involving scraping of surface soil and burial at depth on site. Dosimetry, together with social and economic factors, underpins the setting of clean-up criteria in terms of activity concentrations averaged over large areas and permissible concentrations of contaminated particles. The possibility of intentional behaviour such as fragment scavenging has also influenced limits on particulate contamination.The standard for this intervention is that the annual committed dose, for any scenario involving permanent occupancy by semi-traditional Aborigines, will be less than 5 mSv. In fact, following the clean-up, annual doses are not expected to exceed 1 mSv for all realistic scenarios. The possibility of intentional behaviour, such as fragment scavenging, has led to limits on particulate contamination. Three plutonium-contaminated sites have been treated by soil-removal. At Taranaki, the most contaminated site, by limiting the activity of the remaining soil to below about 400 kBq/m2 of 239Pu, and by limiting occupancy factors to those typical of hunting activities in a particular location (0.8%), the dose criteria will be met. An area of about 1.5 km2 has been treated by removal of surface soil at Taranaki. At the other two sites, with no occupancy constraints, more stringent soil-removal criteria have been applied

  10. Oil spill cleanup in severe weather and open ocean conditions

    International Nuclear Information System (INIS)

    Most serious oil spills occur in open water under severe weather conditions. At first the oil stays on the surface, where it is spread by winds and water currents. The action of the waves then mixes the oil into the water column. With time the light elements of crude oil evaporate. The remaining residue is of very low commercial value, but of significant environmental impact. The oil spill can move either out to sea or inshore, where it ends up on the beaches. Normal procedures are to let outbound oil disperse by evaporation and mixing into the water column, and to let the inbound oil collect on the beaches, where the cleanup operations are concentrated. The reason for this is that there is no capability to clean the surface of the water in wave conditions-present-day oil skimmers are ineffective in waves approaching 4 ft in height. It would be simpler, more effective and environmentally more beneficial to skim the oil right at the spill location. This paper describes a method to do this. In the case of an oil spill in open water and high wave conditions, it is proposed to reduce the height of the ocean waves by the use of floating breakwaters to provide a relatively calm area. In such protected areas existing oil skimmers can be used to recover valuable oil and clean up the spill long before it hits the beaches. A floating breakwater developed at the University of Rhode Island by the author can be of great benefit in oil spill cleanup for open ocean conditions. This breakwater is constructed from scrap automobile tires. It is built in units of 20 tires each, which are easily transportable and can be connected together at the spill site to form any desired configuration

  11. Plutonium contamination at Maralinga - dosimetry and clean-up criteria

    Energy Technology Data Exchange (ETDEWEB)

    Cooper, M.B.; Martin, L.J.; O`Brien, R.S.; Williams, G.A. [Australian Radiation Laboratory, Yallambie, VIC (Australia)

    1998-12-31

    An area of South Australia remained contaminated following British nuclear weapons tests at Maralinga during 1955 - 1963. Of importance is the long-lived 239-Pu of which some 24 kg was explosively dispersed in several `minor trials`. The extent, quantities and physical characteristics of the plutonium have been assessed and estimates of dose, dominated by the inhalation pathway in the critical group of Aborigines living a semi-traditional lifestyle, have been made for potential occupants. Rehabilitation of the most contaminated areas is underway, involving scraping of surface soil and burial at depth on site. Dosimetry, together with social and economic factors, underpins the setting of clean-up criteria in terms of activity concentrations averaged over large areas and permissible concentrations of contaminated particles. The possibility of intentional behaviour such as fragment scavenging has also influenced limits on particulate contamination.The standard for this intervention is that the annual committed dose, for any scenario involving permanent occupancy by semi-traditional Aborigines, will be less than 5 mSv. In fact, following the clean-up, annual doses are not expected to exceed 1 mSv for all realistic scenarios. The possibility of intentional behaviour, such as fragment scavenging, has led to limits on particulate contamination. Three plutonium-contaminated sites have been treated by soil-removal. At Taranaki, the most contaminated site, by limiting the activity of the remaining soil to below about 400 kBq/m2 of 239Pu, and by limiting occupancy factors to those typical of hunting activities in a particular location (0.8%), the dose criteria will be met. An area of about 1.5 km{sup 2} has been treated by removal of surface soil at Taranaki. At the other two sites, with no occupancy constraints, more stringent soil-removal criteria have been applied

  12. Verification of Uncurated Protein Annotations

    OpenAIRE

    Rebholz-Schuhmann, Dietrich; Kirsch, Harald; Apweiler, Rolf; Camon, Evelyn; Dimmer, Emily; Lee, Vivian; Silva, Mário J.; Couto, Francisco M.

    2009-01-01

    Molecular Biology research projects produced vast amounts of data, part of which has been preserved in a variety of public databases. However, a large portion of the data contains a significant number of errors and therefore requires careful verification by curators, a painful and costly task, before being reliable enough to derive valid conclusions from it. On the other hand, research in biomedical information retrieval and information extraction are nowadays delivering Text Mining solutions...

  13. Ultrasonic Verification of Composite Structures

    OpenAIRE

    Pelt, Maurice; Boer, Robert Jan,; Schoemaker, Christiaan; Sprik, Rudolf

    2014-01-01

    International audience Ultrasonic Verification is a new method for the monitoring large surface areas of CFRP by ultrasound with few sensors. The echo response of a transmitted pulse through the structure is compared with the response of an earlier obtained reference signal to calculate a fidelity parameter. A change in fidelity over time is indicative for a new defect in the structure. This paper presents an experimental assessment of the effectiveness and reproducibility of the method.

  14. Verification of Stochastic Process Calculi

    DEFF Research Database (Denmark)

    Skrypnyuk, Nataliya

    performed with the purpose to verify the system. In this dissertation it is argued that the verification techniques that have their origin in the analysis of programming code with the purpose to deduce the properties of the code's execution, i.e. Static Analysis techniques, are transferable to stochastic...... description of a system. The presented methods have a clear application in the areas of embedded systems, (randomised) protocols run between a fixed number of parties etc....

  15. An Effective Fingerprint Verification Technique

    OpenAIRE

    Gogoi, Minakshi; Bhattacharyya, D K

    2010-01-01

    This paper presents an effective method for fingerprint verification based on a data mining technique called minutiae clustering and a graph-theoretic approach to analyze the process of fingerprint comparison to give a feature space representation of minutiae and to produce a lower bound on the number of detectably distinct fingerprints. The method also proving the invariance of each individual fingerprint by using both the topological behavior of the minutiae graph and also using a distance ...

  16. Oral Hygiene. Learning Activity Package.

    Science.gov (United States)

    Hime, Kirsten

    This learning activity package on oral hygiene is one of a series of 12 titles developed for use in health occupations education programs. Materials in the package include objectives, a list of materials needed, a list of definitions, information sheets, reviews (self evaluations) of portions of the content, and answers to reviews. These topics…

  17. Packaging Software Assets for Reuse

    Science.gov (United States)

    Mattmann, C. A.; Marshall, J. J.; Downs, R. R.

    2010-12-01

    The reuse of existing software assets such as code, architecture, libraries, and modules in current software and systems development projects can provide many benefits, including reduced costs, in time and effort, and increased reliability. Many reusable assets are currently available in various online catalogs and repositories, usually broken down by disciplines such as programming language (Ibiblio for Maven/Java developers, PyPI for Python developers, CPAN for Perl developers, etc.). The way these assets are packaged for distribution can play a role in their reuse - an asset that is packaged simply and logically is typically easier to understand, install, and use, thereby increasing its reusability. A well-packaged asset has advantages in being more reusable and thus more likely to provide benefits through its reuse. This presentation will discuss various aspects of software asset packaging and how they can affect the reusability of the assets. The characteristics of well-packaged software will be described. A software packaging domain model will be introduced, and some existing packaging approaches examined. An example case study of a Reuse Enablement System (RES), currently being created by near-term Earth science decadal survey missions, will provide information about the use of the domain model. Awareness of these factors will help software developers package their reusable assets so that they can provide the most benefits for software reuse.

  18. Gentoo package dependencies over time

    NARCIS (Netherlands)

    Bloemen, Remco; Amrit, Chintan; Kuhlmann, Stefan; Ordonez-Matamoros, Gonzalo

    2014-01-01

    Open source distributions such as Gentoo need to accurately track dependency relations between software packages in order to install working systems. To do this, Gentoo has a carefully authored database containing those relations. In this paper, we extract the Gentoo package dependency graph and its

  19. Verification and transparency in future arms control

    Energy Technology Data Exchange (ETDEWEB)

    Pilat, J.F.

    1996-09-01

    Verification`s importance has changed dramatically over time, although it always has been in the forefront of arms control. The goals and measures of verification and the criteria for success have changed with the times as well, reflecting such factors as the centrality of the prospective agreement to East-West relations during the Cold War, the state of relations between the United States and the Soviet Union, and the technologies available for monitoring. Verification`s role may be declining in the post-Cold War period. The prospects for such a development will depend, first and foremost, on the high costs of traditional arms control, especially those associated with requirements for verification. Moreover, the growing interest in informal, or non-negotiated arms control does not allow for verification provisions by the very nature of these arrangements. Multilateral agreements are also becoming more prominent and argue against highly effective verification measures, in part because of fears of promoting proliferation by opening sensitive facilities to inspectors from potential proliferant states. As a result, it is likely that transparency and confidence-building measures will achieve greater prominence, both as supplements to and substitutes for traditional verification. Such measures are not panaceas and do not offer all that we came to expect from verification during the Cold war. But they may be the best possible means to deal with current problems of arms reductions and restraints at acceptable levels of expenditure.

  20. Nuclear Data Verification and Standardization

    Energy Technology Data Exchange (ETDEWEB)

    Karam, Lisa R.; Arif, Muhammad; Thompson, Alan K.

    2011-10-01

    The objective of this interagency program is to provide accurate neutron interaction verification and standardization data for the U.S. Department of Energy Division of Nuclear Physics programs which include astrophysics, radioactive beam studies, and heavy-ion reactions. The measurements made in this program are also useful to other programs that indirectly use the unique properties of the neutron for diagnostic and analytical purposes. These include homeland security, personnel health and safety, nuclear waste disposal, treaty verification, national defense, and nuclear based energy production. The work includes the verification of reference standard cross sections and related neutron data employing the unique facilities and capabilities at NIST and other laboratories as required; leadership and participation in international intercomparisons and collaborations; and the preservation of standard reference deposits. An essential element of the program is critical evaluation of neutron interaction data standards including international coordinations. Data testing of critical data for important applications is included. The program is jointly supported by the Department of Energy and the National Institute of Standards and Technology.