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Sample records for certification plan transuranic

  1. Hanford Site Transuranic (TRU) Waste Certification Plan

    Energy Technology Data Exchange (ETDEWEB)

    GREAGER, T.M.

    1999-09-09

    The Hanford Site Transuranic Waste Certification Plan establishes the programmatic framework and criteria within which the Hanford Site ensures that contract-handled TRU wastes can be certified as compliant with the WIPP WAC and TRUPACT-II SARP.

  2. Hanford Site Transuranic (TRU) Waste Certification Plan

    Energy Technology Data Exchange (ETDEWEB)

    GREAGER, T.M.

    1999-12-14

    The Hanford Site Transuranic Waste Certification Plan establishes the programmatic framework and criteria with in which the Hanford Site ensures that contract-handled TRU wastes can be certified as compliant with the WIPP WAC and TRUPACT-II SARP.

  3. Hanford Site Transuranic (TRU) Waste Certification Plan

    International Nuclear Information System (INIS)

    The Hanford Site Transuranic Waste Certification Plan establishes the programmatic framework and criteria within which the Hanford Site ensures that contract-handled TRU wastes can be certified as compliant with the WIPP WAC and TRUPACT-II SARP

  4. Hanford Site Transuranic (TRU) Waste Certification Plan

    International Nuclear Information System (INIS)

    The Hanford Site Transuranic Waste Certification Plan establishes the programmatic framework and criteria with in which the Hanford Site ensures that contract-handled TRU wastes can be certified as compliant with the WIPP WAC and TRUPACT-II SARP

  5. Hanford Site Transuranic (TRU) Waste Certification Plan

    Energy Technology Data Exchange (ETDEWEB)

    GREAGER, T.M.

    2000-12-06

    As a generator of transuranic (TRU) and TRU mixed waste destined for disposal at the Waste Isolation Pilot Plant (WIPP), the Hanford Site must ensure that its TRU waste meets the requirements of US. Department of Energy (DOE) 0 435.1, ''Radioactive Waste Management,'' and the Contact-Handled (CH) Transuranic Waste Acceptance Criteria for the Waste Isolation Pilot Plant (WIPP-WAC). WIPP-WAC requirements are derived from the WIPP Technical Safety Requirements, WIPP Safety Analysis Report, TRUPACT-II SARP, WIPP Land Withdrawal Act, WIPP Hazardous Waste Facility Permit, and Title 40 Code of Federal Regulations (CFR) 191/194 Compliance Certification Decision. The WIPP-WAC establishes the specific physical, chemical, radiological, and packaging criteria for acceptance of defense TRU waste shipments at WIPP. The WPP-WAC also requires that participating DOE TRU waste generator/treatment/storage sites produce site-specific documents, including a certification plan, that describe their program for managing TRU waste and TRU waste shipments before transferring waste to WIPP. Waste characterization activities provide much of the data upon which certification decisions are based. Waste characterization requirements for TRU waste and TRU mixed waste that contains constituents regulated under the Resource Conservation and Recovery Act (RCRA) are established in the WIPP Hazardous Waste Facility Permit Waste Analysis Plan (WAP). The Hanford Site Quality Assurance Project Plan (QAPjP) (HNF-2599) implements the applicable requirements in the WAP and includes the qualitative and quantitative criteria for making hazardous waste determinations. The Hanford Site must also ensure that its TRU waste destined for disposal at WPP meets requirements for transport in the Transuranic Package Transporter-11 (TRUPACT-11). The US. Nuclear Regulatory Commission (NRC) establishes the TRUPACT-11 requirements in the Safety Analysis Report for the TRUPACT-II Shipping Package

  6. Hanford Site Transuranic (TRU) Waste Certification Plan

    International Nuclear Information System (INIS)

    As a generator of transuranic (TRU) and TRU mixed waste destined for disposal at the Waste Isolation Pilot Plant (WIPP), the Hanford Site must ensure that its TRU waste meets the requirements of US. Department of Energy (DOE) 0 435.1, ''Radioactive Waste Management,'' and the Contact-Handled (CH) Transuranic Waste Acceptance Criteria for the Waste Isolation Pilot Plant (WIPP-WAC). WIPP-WAC requirements are derived from the WIPP Technical Safety Requirements, WIPP Safety Analysis Report, TRUPACT-II SARP, WIPP Land Withdrawal Act, WIPP Hazardous Waste Facility Permit, and Title 40 Code of Federal Regulations (CFR) 191/194 Compliance Certification Decision. The WIPP-WAC establishes the specific physical, chemical, radiological, and packaging criteria for acceptance of defense TRU waste shipments at WIPP. The WPP-WAC also requires that participating DOE TRU waste generator/treatment/storage sites produce site-specific documents, including a certification plan, that describe their program for managing TRU waste and TRU waste shipments before transferring waste to WIPP. Waste characterization activities provide much of the data upon which certification decisions are based. Waste characterization requirements for TRU waste and TRU mixed waste that contains constituents regulated under the Resource Conservation and Recovery Act (RCRA) are established in the WIPP Hazardous Waste Facility Permit Waste Analysis Plan (WAP). The Hanford Site Quality Assurance Project Plan (QAPjP) (HNF-2599) implements the applicable requirements in the WAP and includes the qualitative and quantitative criteria for making hazardous waste determinations. The Hanford Site must also ensure that its TRU waste destined for disposal at WPP meets requirements for transport in the Transuranic Package Transporter-11 (TRUPACT-11). The US. Nuclear Regulatory Commission (NRC) establishes the TRUPACT-11 requirements in the Safety Analysis Report for the TRUPACT-II Shipping Package (TRUPACT-11 SARP). In

  7. Savannah River Certification Plan for newly generated, contact-handled transuranic waste

    International Nuclear Information System (INIS)

    This Certification Plan document describes the necessary processes and methods for certifying unclassified, newly generated, contact-handled solid transuranic (TRU) waste at the Savannah River Plant and Laboratory (SRP, SRL) to comply with the Waste Isolation Pilot Plant Waste Acceptance Criteria (WIPP-WAC). Section 2 contains the organizational structure as related to waste certification including a summary of functional responsibilities, levels of authority, and lines of communication of the various organizations involved in certification activities. Section 3 describes general plant operations and TRU waste generation. Included is a description of the TRU Waste classification system. Section 4 contains the SR site TRU Waste Quality Assurance Program Plan. Section 5 describes waste container procurement, inspection, and certification prior to being loaded with TRU waste. Certification of waste packages, after package closure in the waste generating areas, is described in Section 6. The packaging and certification of individual waste forms is described in Attachments 1-5. Included in each attachment is a description of controls used to ensure that waste packages meet all applicable waste form compliance requirements for shipment to the WIPP. 3 figs., 3 tabs

  8. National transuranic program plan

    International Nuclear Information System (INIS)

    As a result of various program initiatives, the U.S. generated and will continue to generate waste contaminated with radioactive materials. Because of increased awareness of the risks and special requirements to safely manage long-lived alpha-emitting radionuclides, a new category of radioactive waste, transuranic (TRU) waste, was adopted in 1970. Heads of Field Elements can determine that other alpha-contaminated wastes, peculiar to a specific site, must be managed as transuranic wasteclose quotes. TRU waste is generated and stored at various DOE sites around the country. In December 1993, the National Transuranic Program Office (NTPO) was established as part of the Carlsbad Area Office (CAO) to integrate and coordinate the diverse organizational elements that contribute to the complex-wide management of TRU waste. Numerous sites with small TRU waste inventories are also part of the national TRU waste system. The majority of TRU waste is also contaminated with hazardous materials and is thus considered mixed waste. Mixed waste must be managed in compliance with all federal, state, and local regulations that are applicable to the radioactive and/or hazardous component of the waste. Each generator site is responsible for the management of its respective waste. Sites must plan and implement programs to minimize, characterize, package, treat, store, ship, and dispose of all TRU waste; construct required waste management facilities and equipment; obtain permits; perform site-specific National Environmental Policy Act (NEPA) analyses; conduct environmental studies; perform laboratory analyses; and certify that waste meets appropriate disposal facility criteria. Due to the toxicity and long half-lives of TRU radionuclides, TRU waste must be disposed in a manner that offers greater confinement than shallow land burial

  9. Oak Ridge National Laboratory Transuranic Waste Certification Program

    Energy Technology Data Exchange (ETDEWEB)

    Smith, J.H.; Bates, L.D.; Box, W.D.; Aaron, W.S.; Setaro, J.A.

    1988-08-01

    The US Department of Energy (DOE) has requested that all DOE facilities handling defense transuranic (TRU) waste develop and implement a program whereby all TRU waste will be contained, stored, and shipped to the Waste Isolation Pilot Plant (WIPP) in accordance with the requirements set forth in the DOE certification documents WIPP-DOE-069, 114, 120, 137, 157, and 158. The program described in this report describes how Oak Ridge National Laboratory (ORNL) intends to comply with these requirements and the techniques and procedures used to ensure that ORNL TRU wastes are certifiable for shipment to WIPP. This document describes the program for certification of newly generated (NG) contact-handled transuranic (CH-TRU) waste. Previsions have been made for addenda, which will extend the coverage of this document to include certification of stored CH-TRU and NG and stored remote-handled transuranic (RH-TRU) waste, as necessary. 24 refs., 11 figs., 4 tabs.

  10. Transuranic Waste Characterization Quality Assurance Program Plan

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-04-30

    This quality assurance plan identifies the data necessary, and techniques designed to attain the required quality, to meet the specific data quality objectives associated with the DOE Waste Isolation Pilot Plant (WIPP). This report specifies sampling, waste testing, and analytical methods for transuranic wastes.

  11. Los Alamos National Laboratory transuranic waste quality assurance project plan. Revision 1

    International Nuclear Information System (INIS)

    This Transuranic (TRU) Waste Quality Assurance Project Plan (QAPjP) serves as the quality management plan for the characterization of transuranic waste in preparation for certification and transportation. The Transuranic Waste Characterization/Certification Program (TWCP) consists of personnel who sample and analyze waste, validate and report data; and provide project management, quality assurance, audit and assessment, and records management support, all in accordance with established requirements for disposal of TRU waste at the Waste Isolation Pilot Plant (WIPP) facility. This QAPjP addresses how the TWCP meets the quality requirements of the Carlsbad Area Office (CAO) Quality Assurance Program Description (QAPD) and the technical requirements of the Transuranic Waste Characterization Quality Assurance Program Plan (QAPP). The TWCP characterizes and certifies retrievably stored and newly generated TRU waste using the waste selection, testing, sampling, and analytical techniques and data quality objectives (DQOs) described in the QAPP, the Los Alamos National Laboratory Transuranic Waste Certification Plan (Certification Plan), and the CST Waste Management Facilities Waste Acceptance Criteria and Certification [Los Alamos National Laboratory (LANL) Waste Acceptance Criteria (WAC)]. At the present, the TWCP does not address remote-handled (RH) waste

  12. Final Hanford Site Transuranic (TRU) Waste Characterization QA Project Plan

    Energy Technology Data Exchange (ETDEWEB)

    GREAGER, T.M.

    2000-12-06

    The Quality Assurance Project Plan (QAPjP) has been prepared for waste characterization activities to be conducted by the Transuranic (TRU) Project at the Hanford Site to meet requirements set forth in the Waste Isolation Pilot Plan (WIPP) Hazardous Waste Facility Permit, 4890139088-TSDF, Attachment B, including Attachments B1 through B6 (WAP) (DOE, 1999a). The QAPjP describes the waste characterization requirements and includes test methods, details of planned waste sampling and analysis, and a description of the waste characterization and verification process. In addition, the QAPjP includes a description of the quality assurance/quality control (QA/QC) requirements for the waste characterization program. Before TRU waste is shipped to the WIPP site by the TRU Project, all applicable requirements of the QAPjP shall be implemented. Additional requirements necessary for transportation to waste disposal at WIPP can be found in the ''Quality Assurance Program Document'' (DOE 1999b) and HNF-2600, ''Hanford Site Transuranic Waste Certification Plan.'' TRU mixed waste contains both TRU radioactive and hazardous components, as defined in the WLPP-WAP. The waste is designated and separately packaged as either contact-handled (CH) or remote-handled (RH), based on the radiological dose rate at the surface of the waste container. RH TRU wastes are not currently shipped to the WIPP facility.

  13. Final Hanford Site Transuranic (TRU) Waste Characterization QA Project Plan

    International Nuclear Information System (INIS)

    The Quality Assurance Project Plan (QAPjP) has been prepared for waste characterization activities to be conducted by the Transuranic (TRU) Project at the Hanford Site to meet requirements set forth in the Waste Isolation Pilot Plan (WIPP) Hazardous Waste Facility Permit, 4890139088-TSDF, Attachment B, including Attachments B1 through B6 (WAP) (DOE, 1999a). The QAPjP describes the waste characterization requirements and includes test methods, details of planned waste sampling and analysis, and a description of the waste characterization and verification process. In addition, the QAPjP includes a description of the quality assurance/quality control (QA/QC) requirements for the waste characterization program. Before TRU waste is shipped to the WIPP site by the TRU Project, all applicable requirements of the QAPjP shall be implemented. Additional requirements necessary for transportation to waste disposal at WIPP can be found in the ''Quality Assurance Program Document'' (DOE 1999b) and HNF-2600, ''Hanford Site Transuranic Waste Certification Plan.'' TRU mixed waste contains both TRU radioactive and hazardous components, as defined in the WLPP-WAP. The waste is designated and separately packaged as either contact-handled (CH) or remote-handled (RH), based on the radiological dose rate at the surface of the waste container. RH TRU wastes are not currently shipped to the WIPP facility

  14. Final Inventory Work-Off Plan for ORNL transuranic wastes (1986 version)

    International Nuclear Information System (INIS)

    The Final Inventory Work-Off Plan (IWOP) for ORNL Transuranic Wastes addresses ORNL's strategy for retrieval, certification, and shipment of its stored and newly generated contact-handled (CH) and remote-handled (RH) transuranic (TRU) wastes to the Waste Isolation Pilot Plant (WIPP), the proposed geologic repository near Carlsbad, New Mexico. This document considers certification compliance with the WIPP waste acceptance criteria (WAC) and is consistent with the US Department of Energy's Long-Range Master Plan for Defense Transuranic Waste Management. This document characterizes Oak Ridge National Laboratory's (ORNL's) TRU waste by type and estimates the number of shipments required to dispose of it; describes the methods, facilities, and systems required for its certification and shipment; presents work-off strategies and schedules for retrieval, certification, and transportation; discusses the resource needs and additions that will be required for the effort and forecasts costs for the long-term TRU waste management program; and lists public documentation required to support certification facilities and strategies. 22 refs., 6 figs., 10 tabs

  15. Final Hanford Site Transuranic (TRU) Waste Characterization Quality Assurance Project Plan

    International Nuclear Information System (INIS)

    The Transuranic Waste Characterization Quality Assurance Program Plan required each US Department of Energy (DOE) site that characterizes transuranic waste to be sent the Waste Isolation Pilot Plan that addresses applicable requirements specified in the QAPP

  16. Certification document for newly generated contact-handled transuranic waste

    International Nuclear Information System (INIS)

    The US Department of Energy has requested that all national laboratories handling defense waste develop and augment a program whereby all newly generated contact-handled transuranic (TRU) waste be contained, stored, and then shipped to the Waste Isolation Pilot Plant (WIPP) in accordance with the requirements set forth in WIPP-DOE-114. The program described in this report delineates how Oak Ridge National Laboratory intends to comply with these requirements and lists the procedures used by each generator to ensure that their TRU wastes are certifiable for shipment to WIPP

  17. Transuranic (TRU) Waste Phase I Retrieval Plan

    CERN Document Server

    McDonald, K M

    2000-01-01

    From 1970 to 1987, TRU and suspect TRU wastes at Hanford were placed in the SWBG. At the time of placement in the SWBG these wastes were not regulated under existing Resource Conservation and Recovery Act (RCRA) regulations, since they were generated and disposed of prior to the effective date of RCRA at the Hanford Site (1987). From the standpoint of DOE Order 5820.2A1, the TRU wastes are considered retrievably stored, and current plans are to retrieve these wastes for shipment to WIPP for disposal. This plan provides a strategy for the Phase I retrieval that meets the intent of TPA milestone M-91 and Project W-113, and incorporates the lessons learned during TRU retrieval campaigns at Hanford, LANL, and SRS. As in the original Project W-113 plans, the current plan calls for examination of approximately 10,000 suspect-TRU drums located in the 218-W-4C burial ground followed by the retrieval of those drums verified to contain TRU waste. Unlike the older plan, however, this plan proposes an open-air retrieval ...

  18. Final Hanford Site Transuranic (TRU) Waste Characterization Qualit Assurance Project Plan

    International Nuclear Information System (INIS)

    The Transuranic Waste Characterization Quality Assurance Program Plan required each U.S. Department of Energy (DOE) site that characterizes transuranic waste to be sent the Waste Isolation Pilot Plan that addresses applicable requirements specified in the quality assurance project plan (QAPP)

  19. Project plans for transuranic waste at small quantity sites in the Department of Energy comples-10522

    Energy Technology Data Exchange (ETDEWEB)

    Mctaggart, Jerri Lynne [Los Alamos National Laboratory; Lott, Sheila [Los Alamos National Laboratory; Gadbury, Casey [DOE

    2009-01-01

    Los Alamos National Laboratory, Carlsbad Office (LANL-CO), has been tasked to write Project Plans for all of the Small Quantity Sites (SQS) with defense related Transuranic (TRU) waste in the Department of Energy (DOE) complex. Transuranic Work-Off Plans were precursors to the Project Plans. LANL-CO prepared a Work-Off Plan for each small quantity site. The Work-Off Plan that identified issues, drivers, schedules, and inventory. Eight sites have been chosen to deinventory their legacy TRU waste; Bettis Atomic Power Laboratory, General Electric-Vallecitos Nuclear Center, Lawrence Berkeley National Laboratory, Lawrence Livermore National Laboratory-Area 300, Nevada Test Site, Nuclear Radiation Development, Sandia National Laboratory, and the Separations Process Research Unit. Each plan was written for contact and/or remote handled waste if present at the site. These project plans will assist the small quantity sites to ship legacy TRU waste offsite and de-inventory the site of legacy TRU waste. The DOE is working very diligently to reduce the nuclear foot print in the United States. Each of the eight SQSs will be de-inventoried of legacy TRU waste during a campaign that ends September 2011. The small quantity sites have a fraction of the waste that large quantity sites possess. During this campaign, the small quantity sites will package all of the legacy TRU waste and ship to Idaho or directly to the Waste Isolation Pilot Plant (WIPP) in Carlsbad, New Mexico. The sites will then be removed from the Transuranic Waste Inventory if they are de-inventoried of all waste. Each Project Plan includes the respective site inventory report, schedules, resources, drivers and any issues. These project plans have been written by the difficult waste team and will be approved by each site. Team members have been assigned to each site to write site specific project plans. Once the project plans have been written, the difficult team members will visit the sites to ensure nothing has

  20. Defense Waste Management Plan for buried transuranic-contaminated waste, transuranic-contaminated soil, and difficult-to-certify transuranic waste

    International Nuclear Information System (INIS)

    GAO recommended that DOE provide specific plans for permanent disposal of buried TRU-contaminated waste, TRU-contaminated soil, and difficult-to-certify TRU waste; cost estimates for permanent disposal of all TRU waste, including the options for the buried TRU-contaminated waste, TRU-contaminated soil, and difficult-to-certify TRU waste; and specific discussions of environmental and safety issues for the permanent disposal of TRU waste. Purpose of this document is to respond to the GAO recommendations by providing plans and cost estimates for the long-term isolation of the buried TRU-contaminated waste, TRU-contaminated soil, and difficult-to-certify TRU waste. This report also provides cost estimates for processing and certifying stored and newly generated TRU waste, decontaminating and decommissioning TRU waste processing facilities, and interim operations

  1. Test plan for preparing the Rapid Transuranic Monitoring Laboratory for field deployment

    International Nuclear Information System (INIS)

    This plan describes experimental work that will be performed during fiscal year 1994 to prepare the Rapid Transuranic Monitoring Laboratory (RTML) for routine field use by US Department of Energy (DOE) Environmental Restoration and Waste Management programs. The RTML is a mobile, field-deployable laboratory developed at the Idaho National Engineering Laboratory (INEL) that provides a rapid, cost-effective means of characterizing and monitoring radioactive waste remediation sites for low-level radioactive contaminants. Analytical instruments currently installed in the RTML include an extended-range, germanium photon analysis spectrometer with an automatic sample changer; two, large-area, ionization chamber alpha spectrometers; and four alpha continuous air monitors. The RTML was field tested at the INEL during June 1993 in conjunction with the Buried Waste Integrated Demonstration's remote retrieval demonstration. The major tasks described in this test plan are to (a) evaluate the beta detectors for use in screening soil samples for 90Sr, (b) upgrade the alpha spectral analysis software programs, and (c) upgrade the photon spectral analysis software programs

  2. Test plan for glove box testing with the real-time transuranic dust monitor

    International Nuclear Information System (INIS)

    This test plan describes the objectives, instrumentation, and testing procedures used to prove the feasibility of a real-time transuranic dust monitor (RTDM). The RTDM is under development at the Idaho National Engineering Laboratory (INEL) as a Waste Characterization Technology funded by the Buried Waste Integrated Demonstration Project. The instrument is an in situ monitor that uses optical techniques to establish particle size, particle number density, and mass and species of heavy metal contamination. US Department of Energy orders mandate the assessment of radiological exposure and contamination spread during the remediation of radioactive waste. Of particular concern is heavy metal contamination of dust, both radioactive and nonradioactive. Small particles of metal, particularly the radioactive species, tend to become electrically charged and consequently attach themselves to dust particles. This airborne activated dust is a primary means of contamination transport during remediation activities, and therefore, must be continuously monitored to protect personnel involved in the operations and to control the spread of contamination. If real-time monitoring is not available there is increased likelihood of generating unacceptably high levels of contamination and being forced to shut down costly retrieval operations to decontaminate. A series of experiments are described to determine the optimal experimental design, operational parameters, and levels of detection for the RTDM. Initial screening will be performed using monodisperse particle standards to set parameters and calibrate the instrument. Additional testing will be performed using INEL soil samples spiked with a surrogate, cerium oxide, to prove the design before transporting the apparatus to the Test Reactor Area for testing with plutonium-contaminated dusts

  3. Human Systems Integration: Unmanned Aircraft Control Station Certification Plan Guidance

    Science.gov (United States)

    2005-01-01

    This document provides guidance to the FAA on important human factors considerations that can be used to support the certification of a UAS Aircraft Control Station (ACS). This document provides a synopsis of the human factors analysis, design and test activities to be performed to provide a basis for FAA certification. The data from these analyses, design activities, and tests, along with data from certification/qualification tests of other key components should be used to establish the ACS certification basis. It is expected that this information will be useful to manufacturers in developing the ACS Certification Plan,, and in supporting the design of their ACS.

  4. De-Inventory Plan for Transuranic Waste Stored at Area G

    Energy Technology Data Exchange (ETDEWEB)

    Hargis, Kenneth Marshall [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Christensen, Davis V. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Shepard, Mark D. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2016-06-21

    This report describes the strategy and detailed work plan developed by Los Alamos National Laboratory (LANL) to disposition transuranic (TRU) waste stored at its Area G radioactive waste storage site. The focus at this time is on disposition of 3,706 m3 of TRU waste stored above grade by June 30, 2014, which is one of the commitments within the Framework Agreement: Realignment of Environmental Priorities between the Department of Energy (DOE) National Nuclear Security Administration (NNSA) and the State of New Mexico Environment Department (NMED), Reference 1. A detailed project management schedule has been developed to manage this work and better ensure that all required activities are aligned and integrated. The schedule was developed in conjunction with personnel from the NNSA Los Alamos Site Office (LASO), the DOE Carlsbad Field Office (CBFO), the Central Characterization Project (CCP), and Los Alamos National Security, LLC (LANS). A detailed project management schedule for the remainder of the above grade inventory and the below grade inventory will be developed and incorporated into the De-Inventory Plan by December 31, 2012. This schedule will also include all newly-generated TRU waste received at Area G in FYs 2012 and 2013, which must be removed by no later than December 31, 2014, under the Framework Agreement. The TRU waste stored above grade at Area G is considered to be one of the highest nuclear safety risks at LANL, and the Defense Nuclear Facility Safety Board has expressed concern for the radioactive material at risk (MAR) contained within the above grade TRU waste inventory and has formally requested that DOE reduce the MAR. A large wildfire called the Las Conchas Fire burned extensive areas west of LANL in late June and July 2011. Although there was minimal to no impact by the fire to LANL, the fire heightened public concern and news media attention on TRU waste storage at Area G. After the fire, New Mexico Governor Susana Martinez also

  5. WASTE CERTIFICATION PROGRAM PLAN - REVISION 7

    Energy Technology Data Exchange (ETDEWEB)

    MORGAN, LK

    2002-01-08

    The primary changes that have been made to this revision reflect the relocation of the Waste Certification Official (WCO) organizationally from the Quality Services Division (QSD) into the Laboratory Waste Services (LWS) Organization. Additionally, the responsibilities for program oversight have been differentiated between the QSD and LWS. The intent of this effort is to ensure that those oversight functions, which properly belonged to the WCO, moved with that function; but retain an independent oversight function outside of the LWS Organization ensuring the potential for introduction of organizational bias, regarding programmatic and technical issues, is minimized. The Waste Certification Program (WCP) itself has been modified to allow the waste certification function to be performed by any of the personnel within the LWS Waste Acceptance/Certification functional area. However, a single individual may not perform both the technical waste acceptance review and the final certification review on the same 2109 data package. Those reviews must be performed by separate individuals in a peer review process. There will continue to be a designated WCO who will have lead programmatic responsibility for the WCP and will exercise overall program operational oversite as well as determine the overall requirements of the certification program. The quality assurance organization will perform independent, outside oversight to ensure that any organizational bias does not degrade the integrity of the waste certification process. The core elements of the previous WCP have been retained, however, the terms and process structure have been modified.. There are now two ''control points,'' (1) the data package enters the waste certification process with the signature of the Generator Interface/Generator Interface Equivalent (GI/GIE), (2) the package is ''certified'', thus exiting the process. The WCP contains three steps, (1) the technical review

  6. RETRIEVING SUSPECT TRANSURANIC WASTE FROM THE HANFORD BURIAL GROUNDS PROGRESS PLANS AND CHALLENGES

    International Nuclear Information System (INIS)

    This paper describes the scope and status of the program for retrieval of suspect transuranic (TRU) waste stored in the Hanford Site low-level burial grounds. Beginning in 1970 and continuing until the late 1980's, waste suspected of containing significant quantities of transuranic isotopes was placed in ''retrievable'' storage in designated modules in the Hanford burial grounds, with the intent that the waste would be retrieved when a national repository for disposal of such waste became operational. Approximately 15,000 cubic meters of waste, suspected of being TRU, was placed in storage modules in four burial grounds. With the availability of the national repository (the Waste Isolation Pilot Plant), retrieval of the suspect TRU waste is now underway. Retrieval efforts, to date, have been conducted in storage modules that contain waste, which is in general, contact-handled, relatively new (1980's and later), is stacked in neat, engineered configurations, and has a relatively good record of waste characteristics. Even with these optimum conditions, retrieval personnel have had to deal with a large number of structurally degraded containers, radioactive contamination issues, and industrial hazards (including organic vapors). Future retrieval efforts in older, less engineered modules are expected to present additional hazards and difficult challenges

  7. RETRIEVING SUSPECT TRANSURANIC (TRU) WASTE FROM THE HANFORD BURIAL GROUNDS PROGRESS PLANS & CHALLENGES

    Energy Technology Data Exchange (ETDEWEB)

    FRENCH, M.S.

    2006-02-01

    This paper describes the scope and status of the program for retrieval of suspect transuranic (TRU) waste stored in the Hanford Site low-level burial grounds. Beginning in 1970 and continuing until the late 1980's, waste suspected of containing significant quantities of transuranic isotopes was placed in ''retrievable'' storage in designated modules in the Hanford burial grounds, with the intent that the waste would be retrieved when a national repository for disposal of such waste became operational. Approximately 15,000 cubic meters of waste, suspected of being TRU, was placed in storage modules in four burial grounds. With the availability of the national repository (the Waste Isolation Pilot Plant), retrieval of the suspect TRU waste is now underway. Retrieval efforts, to date, have been conducted in storage modules that contain waste, which is in general, contact-handled, relatively new (1980's and later), is stacked in neat, engineered configurations, and has a relatively good record of waste characteristics. Even with these optimum conditions, retrieval personnel have had to deal with a large number of structurally degraded containers, radioactive contamination issues, and industrial hazards (including organic vapors). Future retrieval efforts in older, less engineered modules are expected to present additional hazards and difficult challenges.

  8. National Transuranic Program Charter

    International Nuclear Information System (INIS)

    The National Transuranic Program Plan and Charter describes the functional elements of the National TRU Program, organizational relationships, programmatic responsibilities, division of work scope among the various DOE organizations that comprise the program, and program baselines against which overall progress will be measured. The charter defines the authorities and responsibilities of various organizations involved in the management of TRU waste throughout the DOE complex

  9. 42 CFR 456.481 - Admission certification and plan of care.

    Science.gov (United States)

    2010-10-01

    ... Individuals Under Age 21: Admission and Plan of Care Requirements § 456.481 Admission certification and plan of care. If a facility provides inpatient psychiatric services to a recipient under age 21— (a) The... 42 Public Health 4 2010-10-01 2010-10-01 false Admission certification and plan of care....

  10. 34 CFR 76.104 - A State shall include certain certifications in its State plan.

    Science.gov (United States)

    2010-07-01

    ... 34 Education 1 2010-07-01 2010-07-01 false A State shall include certain certifications in its State plan. 76.104 Section 76.104 Education Office of the Secretary, Department of Education STATE... include certain certifications in its State plan. (a) A State shall include the following...

  11. Processing Plan for Potentially Reactive/Ignitable Remote Handled Transuranic Waste at the Idaho Cleanup Project - 12090

    International Nuclear Information System (INIS)

    Remote Handle Transuranic (RH-TRU) Waste generated at Argonne National Laboratory - East, from the examination of irradiated and un-irradiated fuel pins and other reactor materials requires a detailed processing plan to ensure reactive/ignitable material is absent to meet WIPP Waste Acceptance Criteria prior to shipping and disposal. The Idaho Cleanup Project (ICP) approach to repackaging Lot 2 waste and how we ensure prohibited materials are not present in waste intended for disposal at Waste Isolation Pilot Plant 'WIPP' uses an Argon Repackaging Station (ARS), which provides an inert gas blanket. Opening of the Lot 2 containers under an argon gas blanket is proposed to be completed in the ARS. The ARS is an interim transition repackaging station that provides a mitigation technique to reduce the chances of a reoccurrence of a thermal event prior to rendering the waste 'Safe'. The consequences, should another thermal event be encountered, (which is likely) is to package the waste, apply the reactive and or ignitable codes to the container, and store until the future treatment permit and process are available. This is the same disposition that the two earlier containers in the 'Thermal Events' were assigned. By performing the initial handling under an inert gas blanket, the waste can sorted and segregate the fines and add the Met-L-X to minimize risk before it is exposed to air. The 1-gal cans that are inside the ANL-E canister will be removed and each can is moved to the ARS for repackaging. In the ARS, the 1-gal can is opened in the inerted environment. The contained waste is sorted, weighed, and visually examined for non compliant items such as unvented aerosol cans and liquids. The contents of the paint cans are transferred into a sieve and manipulated to allow the fines, if any, to be separated into the tray below. The fines are weighed and then blended with a minimum 5:1 mix of Met-L-X. Other debris materials found are segregated from the cans into containers

  12. Transuranic waste characterization sampling and analysis methods manual. Revision 1

    International Nuclear Information System (INIS)

    This Methods Manual provides a unified source of information on the sampling and analytical techniques that enable Department of Energy (DOE) facilities to comply with the requirements established in the current revision of the Transuranic Waste Characterization Quality Assurance Program Plan (QAPP) for the Waste Isolation Pilot Plant (WIPP) Transuranic (TRU) Waste Characterization Program (the Program) and the WIPP Waste Analysis Plan. This Methods Manual includes all of the testing, sampling, and analytical methodologies accepted by DOE for use in implementing the Program requirements specified in the QAPP and the WIPP Waste Analysis Plan. The procedures in this Methods Manual are comprehensive and detailed and are designed to provide the necessary guidance for the preparation of site-specific procedures. With some analytical methods, such as Gas Chromatography/Mass Spectrometry, the Methods Manual procedures may be used directly. With other methods, such as nondestructive characterization, the Methods Manual provides guidance rather than a step-by-step procedure. Sites must meet all of the specified quality control requirements of the applicable procedure. Each DOE site must document the details of the procedures it will use and demonstrate the efficacy of such procedures to the Manager, National TRU Program Waste Characterization, during Waste Characterization and Certification audits

  13. Transuranic waste characterization sampling and analysis methods manual. Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    Suermann, J.F.

    1996-04-01

    This Methods Manual provides a unified source of information on the sampling and analytical techniques that enable Department of Energy (DOE) facilities to comply with the requirements established in the current revision of the Transuranic Waste Characterization Quality Assurance Program Plan (QAPP) for the Waste Isolation Pilot Plant (WIPP) Transuranic (TRU) Waste Characterization Program (the Program) and the WIPP Waste Analysis Plan. This Methods Manual includes all of the testing, sampling, and analytical methodologies accepted by DOE for use in implementing the Program requirements specified in the QAPP and the WIPP Waste Analysis Plan. The procedures in this Methods Manual are comprehensive and detailed and are designed to provide the necessary guidance for the preparation of site-specific procedures. With some analytical methods, such as Gas Chromatography/Mass Spectrometry, the Methods Manual procedures may be used directly. With other methods, such as nondestructive characterization, the Methods Manual provides guidance rather than a step-by-step procedure. Sites must meet all of the specified quality control requirements of the applicable procedure. Each DOE site must document the details of the procedures it will use and demonstrate the efficacy of such procedures to the Manager, National TRU Program Waste Characterization, during Waste Characterization and Certification audits.

  14. Overall strategy and program plan for management of radioactively contaminated liquid wastes and transuranic sludges at the Oak Ridge National Laboratory

    International Nuclear Information System (INIS)

    The use of hydrofracture was terminated after 1984, and LW concentrate has been accumulated and stored since that time. Currently, the volume of stored LW concentrate is near the safe fill limit for the 11 storage tanks in the active LW system, and significant operational constraints are being experienced. The tanks that provide the storage capacity of the active LW system contain significant volumes of TRU sludges that have been designated remote-handled transuranic (RH-TRU) wastes because of associated quantities of other radioisotopes, including 90Sr and 137Cs. Thirty-three additional tanks, which are inactive, also contain significant volumes of TRU waste and radioactive LW. A lack of adequate storage volume for LW jeopardizes ORNL's ability to ensure continued conduct of research and development (RandD) activities that generate LW because an unexpected operational incident could quickly deplete the remaining storage volume. Accordingly, a planning team comprised of staff members from the ORNL Nuclear and Chemical Waste Programs (NCWP) was created for developing recommended actions to be taken for management of LW. A program plan is presented which outlines work required for the development of a disposal method for each of the likely future waste streams associated with LW management and the disposal of the bulk of the resulting solid waste on the ORR. 8 refs., 20 figs., 12 tabs

  15. Repository disposal requirements for commercial transuranic wastes (generated without reprocessing)

    International Nuclear Information System (INIS)

    This report forms a preliminary planning basis for disposal of commercial transuranic (TRU) wastes in a geologic repository. Because of the unlikely prospects for commercial spent nuclear fuel reprocessing in the near-term, this report focuses on TRU wastes generated in a once-through nuclear fuel cycle. The four main objectives of this study were to: develop estimates of the current inventories, projected generation rates, and characteristics of commercial TRU wastes; develop proposed acceptance requirements for TRU wastes forms and waste canisters that ensure a safe and effective disposal system; develop certification procedures and processing requirements that ensure that TRU wastes delivered to a repository for disposal meet all applicable waste acceptance requirements; and identify alternative conceptual strategies for treatment and certification of commercial TRU first objective was accomplished through a survey of commercial producers of TRU wastes. The TRU waste acceptance and certification requirements that were developed were based on regulatory requirements, information in the literature, and from similar requirements already established for disposal of defense TRU wastes in the Waste Isolation Pilot Plant (WIPP) which were adapted, where necessary, to disposal of commercial TRU wastes. The results of the TRU waste-producer survey indicated that there were a relatively large number of producers of small quantities of TRU wastes

  16. Validity of Health Plan and Birth Certificate Data for Pregnancy Research

    Science.gov (United States)

    Andrade, Susan E.; Scott, Pamela E.; Davis, Robert L.; Li, De-Kun; Getahun, Darios; Cheetham, T. Craig; Raebel, Marsha A.; Toh, Sengwee; Dublin, Sascha; Pawloski, Pamala A.; Hammad, Tarek A.; Beaton, Sarah J.; Smith, David H.; Dashevsky, Inna; Haffenreffer, Katherine; Cooper, William O.

    2012-01-01

    Purpose To evaluate the validity of health plan and birth certificate data for pregnancy research. Methods A retrospective study was conducted using administrative and claims data from 11 U.S. health plans, and corresponding birth certificate data from state health departments. Diagnoses, drug dispensings, and procedure codes were used to identify infant outcomes (cardiac defects, anencephaly, preterm birth, and neonatal intensive care unit [NICU] admission) and maternal diagnoses (asthma and systemic lupus erythematosus [SLE]) recorded in the health plan data for live born deliveries between January 2001 and December 2007. A random sample of medical charts (n = 802) was abstracted for infants and mothers identified with the specified outcomes. Information on newborn, maternal, and paternal characteristics (gestational age at birth, birth weight, previous pregnancies and live births, race/ethnicity) was also abstracted and compared to birth certificate data. Positive predictive values (PPVs) were calculated with documentation in the medical chart serving as the gold standard. Results PPVs were 71% for cardiac defects, 37% for anencephaly, 87% for preterm birth, and 92% for NICU admission. PPVs for algorithms to identify maternal diagnoses of asthma and SLE were ≥ 93%. Our findings indicated considerable agreement (PPVs > 90%) between birth certificate and medical record data for measures related to birth weight, gestational age, prior obstetrical history, and race/ethnicity. Conclusions Health plan and birth certificate data can be useful to accurately identify some infant outcomes, maternal diagnoses, and newborn, maternal, and paternal characteristics. Other outcomes and variables may require medical record review for validation. PMID:22753079

  17. B Plant complex hazardous, mixed and low level waste certification plan

    Energy Technology Data Exchange (ETDEWEB)

    Beam, T.G.

    1994-11-01

    This plan describes the administrative steps and handling methodology for certification of hazardous waste, mixed waste, and low level waste generated at B Plant Complex. The plan also provides the applicable elements of waste reduction and pollution prevention, including up front minimization and end product reduction of volume and/or toxicity. The plan is written to satisfy requirements for Hanford Site waste generators to have a waste certification program in place at their facility. This plan, as described, applies only to waste which is generated at, or is the responsibility of, B Plant Complex. The scope of this plan is derived from the requirements found in WHC-EP-0063, Hanford Site Solid Waste Acceptance Criteria.

  18. Intercalibration of transuranic measurements

    International Nuclear Information System (INIS)

    One of the major objectives of the coordinated research programme on Transuranic Cycling Behaviour in the Marine Environment has been to achieve the comparability of the measurement results among the laboratories from different countries participating in the programme. In order to fulfil this objective, the intercalibration exercises of transuranic measurements using sea water and sediment samples were organized by the Monaco Laboratory within the duration of the programme in 1979-1981. The sediment and sea water samples were collected respectively by the Bhabha Atomic Research Centre of India and the Hydrographic Institute of the Federal Republic of Germany. In the present report the results of these intercalibration exercises are surveyed

  19. Long-term management USDOE transuranic waste

    International Nuclear Information System (INIS)

    Activities for permanent disposal of US DOE TRU waste are presently focused on newly generated and stored waste. The buried waste and contaminated soils pose no near term problem. Decisions on any possible actions for these wastes will be deferred until the newly generated and stored wastes are being placed into disposal on a routine basis. Several elements must be in place before such disposal can become routine. These elements consist of: a disposal facility; waste acceptance criteria; waste certification mechanisms; waste processing facilities; and a waste transportation system. Each of these elements has been the subject of considerable activity in the recent past. Progress and plans for each element are summarized. As of January 1981, DOE has 60,500 m3 of waste classified as Transuranic waste (TRU) in retrievable storage, and projects that additional TRU waste will be generated at an average rate of 4500 m3 per year for the next 10 years. Over 99% of this waste is contact handled, with the remainder being remote handled, i.e., surface radiation dose levels exceeding 200 mrem/h. An estimated 273,000 m3 of TRU waste were placed in shallow land burial prior to establishment of the 1970 policy. In addition, large quantities of soil at DOE sites are contaminated with TRU elements due to disposal of liquid wastes and by contact of soil with solid, buried waste whose original containers are now badly degraded. Possibly as much as 10,000,000 m3 of soil are contaminated above 10 nCi/gm. Less than 1,000,000 m3 are estimated to be contaminated above 100 nCi/gm

  20. Transuranic waste characterization sampling and analysis methods manual

    International Nuclear Information System (INIS)

    The Transuranic Waste Characterization Sampling and Analysis Methods Manual (Methods Manual) provides a unified source of information on the sampling and analytical techniques that enable Department of Energy (DOE) facilities to comply with the requirements established in the current revision of the Transuranic Waste Characterization Quality Assurance Program Plan (QAPP) for the Waste Isolation Pilot Plant (WIPP) Transuranic (TRU) Waste Characterization Program (the Program). This Methods Manual includes all of the testing, sampling, and analytical methodologies accepted by DOE for use in implementing the Program requirements specified in the QAPP

  1. Transuranic waste characterization sampling and analysis methods manual

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-05-01

    The Transuranic Waste Characterization Sampling and Analysis Methods Manual (Methods Manual) provides a unified source of information on the sampling and analytical techniques that enable Department of Energy (DOE) facilities to comply with the requirements established in the current revision of the Transuranic Waste Characterization Quality Assurance Program Plan (QAPP) for the Waste Isolation Pilot Plant (WIPP) Transuranic (TRU) Waste Characterization Program (the Program). This Methods Manual includes all of the testing, sampling, and analytical methodologies accepted by DOE for use in implementing the Program requirements specified in the QAPP.

  2. Hanford Tank Farms Waste Certification Flow Loop Test Plan

    Energy Technology Data Exchange (ETDEWEB)

    Bamberger, Judith A.; Meyer, Perry A.; Scott, Paul A.; Adkins, Harold E.; Wells, Beric E.; Blanchard, Jeremy; Denslow, Kayte M.; Greenwood, Margaret S.; Morgen, Gerald P.; Burns, Carolyn A.; Bontha, Jagannadha R.

    2010-01-01

    A future requirement of Hanford Tank Farm operations will involve transfer of wastes from double shell tanks to the Waste Treatment Plant. As the U.S. Department of Energy contractor for Tank Farm Operations, Washington River Protection Solutions anticipates the need to certify that waste transfers comply with contractual requirements. This test plan describes the approach for evaluating several instruments that have potential to detect the onset of flow stratification and critical suspension velocity. The testing will be conducted in an existing pipe loop in Pacific Northwest National Laboratory’s facility that is being modified to accommodate the testing of instruments over a range of simulated waste properties and flow conditions. The testing phases, test matrix and types of simulants needed and the range of testing conditions required to evaluate the instruments are described

  3. TRU waste inventory collection and work off plans for the centralization of TRU waste characterization/certification at INL - on your mark - get set - 9410

    Energy Technology Data Exchange (ETDEWEB)

    Mctaggert, Jerri Lynne [Los Alamos National Laboratory; Lott, Sheila A [Los Alamos National Laboratory; Gadbury, Casey [CBFO

    2008-01-01

    The U.S. Department of Energy (DOE) amended the Record of Decision (ROD) for the Waste Management Program: Treatment and Storage of Transuranic Waste to centralize transuranic (TRU) waste characterization/certification from fourteen TRU waste sites. This centralization will allow for treatment, characterization and certification ofTRU waste from the fourteen sites, thirteen of which are sites with small quantities ofTRU waste, at the Idaho National Laboratory (INL) prior to shipping the waste to the Waste Isolation Pilot Plant (WIPP) for disposal. Centralization of this TRU waste will avoid the cost of building treatment, characterization, certification, and shipping capabilities at each of the small quantity sites that currently do not have existing facilities. Advanced Mixed Waste Treatment Project (AMWTP) and Idaho Nuclear Technology and Engineering Center (INTEC) will provide centralized shipping facilities, to WIPP, for all of the small quantity sites. Hanford, the one large quantity site identified in the ROD, has a large number of waste in containers that are overpacked into larger containers which are inefficient for shipment to and disposal at WIPP. The AMWTF at the INL will reduce the volume of much of the CH waste and make it much more efficient to ship and dispose of at WIPP. In addition, the INTEC has a certified remote handled (RH) TRU waste characterization/certification program at INL to disposition TRU waste from the sites identified in the ROD.

  4. HANFORD SITE RIVER PROTECTION PROJECT (RPP) TRANSURANIC (TRU) TANK WASTE IDENTIFICATION and PLANNING FOR REVRIEVAL TREATMENT and EVENTUAL DISPOSAL AT WIPP

    International Nuclear Information System (INIS)

    The CH2M HILL Manford Group, Inc. (CHG) conducts business to achieve the goals of the Office of River Protection (ORP) at Hanford. As an employee owned company, CHG employees have a strong motivation to develop innovative solutions to enhance project and company performance while ensuring protection of human health and the environment. CHG is responsible to manage and perform work required to safely store, enhance readiness for waste feed delivery, and prepare for treated waste receipts for the approximately 53 million gallons of legacy mixed radioactive waste currently at the Hanford Site tank farms. Safety and environmental awareness is integrated into all activities and work is accomplished in a manner that achieves high levels of quality while protecting the environment and the safety and health of workers and the public. This paper focuses on the innovative strategy to identify, retrieve, treat, and dispose of Hanford Transuranic (TRU) tank waste at the Waste Isolation Pilot Plant (WIPP)

  5. Waste management/waste certification plan for the Oak Ridge National Laboratory Environmental Restoration Program

    International Nuclear Information System (INIS)

    This Waste Management/Waste Certification (C) Plan, written for the Environmental Restoration (ER) Program at Oak Ridge National Laboratory (ORNL), outlines the criteria and methodologies to be used in the management of waste generated during ORNL ER field activities. Other agreed upon methods may be used in the management of waste with consultation with ER and Waste Management Organization. The intent of this plan is to provide information for the minimization, handling, and disposal of waste generated by ER activities. This plan contains provisions for the safe and effective management of waste consistent with the U.S. Environmental Protection Agency's (EPA's) guidance. Components of this plan have been designed to protect the environment and the health and safety of workers and the public. It, therefore, stresses that investigation derived waste (IDW) and other waste be managed to ensure that (1) all efforts be made to minimize the amount of waste generated; (2) costs associated with sampling storage, analysis, transportation, and disposal are minimized; (3) the potential for public and worker exposure is not increased; and (4) additional contaminated areas are not created

  6. Waste management/waste certification plan for the Oak Ridge National Laboratory Environmental Restoration Program

    Energy Technology Data Exchange (ETDEWEB)

    Clark, C. Jr.; Hunt-Davenport, L.D.; Cofer, G.H.

    1995-03-01

    This Waste Management/Waste Certification (C) Plan, written for the Environmental Restoration (ER) Program at Oak Ridge National Laboratory (ORNL), outlines the criteria and methodologies to be used in the management of waste generated during ORNL ER field activities. Other agreed upon methods may be used in the management of waste with consultation with ER and Waste Management Organization. The intent of this plan is to provide information for the minimization, handling, and disposal of waste generated by ER activities. This plan contains provisions for the safe and effective management of waste consistent with the U.S. Environmental Protection Agency`s (EPA`s) guidance. Components of this plan have been designed to protect the environment and the health and safety of workers and the public. It, therefore, stresses that investigation derived waste (IDW) and other waste be managed to ensure that (1) all efforts be made to minimize the amount of waste generated; (2) costs associated with sampling storage, analysis, transportation, and disposal are minimized; (3) the potential for public and worker exposure is not increased; and (4) additional contaminated areas are not created.

  7. Graph certificates, lookahead in dynamic graph problems, and assembly planning in robotics

    Energy Technology Data Exchange (ETDEWEB)

    Khanna, S.; Motwani, R. [Stanford Univ., CA (United States); Wilson, R.H. [Sandia National Labs., Albuquerque, NM (United States)

    1994-12-31

    Despite intensive efforts in the area of dynamic graph algorithms, no efficient algorithms are known for the dynamic versions of some basic graph problems such as strong connectivity and transitive closure. We provide some explanation for this lack of success by presenting quadratic lower bounds on the strong certificate complexity of such problems, thereby establishing the inapplicability of the only known general technique for designing dynamic graph algorithms, viz., sparsification. These results also provide evidence of the inherent intractability of such dynamic graph problems. Some of our results are based on a general technique for obtaining lower bounds on the strong certificate complexity for a class of graph properties by establishing a relationship with the witness complexity. In many real applications of dynamic graph problems, a certain amount of lookahead is available. Specifically, we consider the problems of assembly planning in robotics and the maintenance of relations in databases which, respectively, give rise to dynamic strong connectivity and transitive closure. We exploit the (naturally available) lookahead in these two applications to circumvent the inherent complexity of the dynamic graph problems. We propose a variant of sparsification, viz., lookahead based sparsification, and apply it to obtain the first efficient fully dynamic algorithms for strong connectivity and transitive closure.

  8. Neonatal Mortality of Planned Home Birth in the United States in Relation to Professional Certification of Birth Attendants.

    Directory of Open Access Journals (Sweden)

    Amos Grünebaum

    Full Text Available Over the last decade, planned home births in the United States (US have increased, and have been associated with increased neonatal mortality and other morbidities. In a previous study we reported that neonatal mortality is increased in planned home births but we did not perform an analysis for the presence of professional certification status.The objective of this study therefore was to undertake an analysis to determine whether the professional certification status of midwives or the home birth setting are more closely associated with the increased neonatal mortality of planned midwife-attended home births in the United States.This study is a secondary analysis of our prior study. The 2006-2009 period linked birth/infant deaths data set was analyzed to examine total neonatal deaths (deaths less than 28 days of life in term singleton births (37+ weeks and newborn weight ≥ 2,500 grams without documented congenital malformations by certification status of the midwife: certified nurse midwives (CNM, nurse midwives certified by the American Midwifery Certification Board, and "other" or uncertified midwives who are not certified by the American Midwifery Certification Board.Neonatal mortality rates in hospital births attended by certified midwives were significantly lower (3.2/10,000, RR 0.33 95% CI 0.21-0.53 than home births attended by certified midwives (NNM: 10.0/10,000; RR 1 and uncertified midwives (13.7/10,000; RR 1.41 [95% CI, 0.83-2.38]. The difference in neonatal mortality between certified and uncertified midwives at home births did not reach statistical levels (10.0/10,000 births versus 13.7/10,000 births p = 0.2.This study confirms that when compared to midwife-attended hospital births, neonatal mortality rates at home births are significantly increased. While NNM was increased in planned homebirths attended by uncertified midwives when compared to certified midwives, this difference was not statistically significant. Neonatal

  9. Quality Assurance Project Plan for the HWMA/RCRA Closure Certification of the TRA-731 Caustic and Acid Storage Tank System - 1997 Notice of Violation Consent Order

    Energy Technology Data Exchange (ETDEWEB)

    Evans, Susan Kay; Orchard, B. J.

    2002-01-01

    This Quality Assurance Project Plan for the HWMA/RCRA Closure Certification of the TRA-731 Caustic and Acid Storage Tank System is one of two documents that comprise the Sampling and Analysis Plan for the HWMA/RCRA closure certification of the TRA-731 caustic and acid storage tank system at the Idaho National Engineering and Environmental Laboratory. This plan, which provides information about the project description, project organization, and quality assurance and quality control procedures, is to be used in conjunction with the Field Sampling Plan for the HWMA/RCRA Closure Certification of the TRA-731 Caustic and Acid Storage Tank System. This Quality Assurance Project Plan specifies the procedures for obtaining the data of known quality required by the closure activities for the TRA-731 caustic and acid storage tank system.

  10. Quality Assurance Project Plan for the HWMA/RCRA Closure Certification of the TRA-731 Caustic and Acid Storage Tank System - 1997 Notice of Violation Consent Order

    Energy Technology Data Exchange (ETDEWEB)

    Evans, S.K.

    2002-01-31

    This Quality Assurance Project Plan for the HWMA/RCRA Closure Certification of the TRA- 731 Caustic and Acid Storage Tank System is one of two documents that comprise the Sampling and Analysis Plan for the HWMA/RCRA closure certification of the TRA-731 caustic and acid storage tank system at the Idaho National Engineering and Environmental Laboratory. This plan, which provides information about the project description, project organization, and quality assurance and quality control procedures, is to be used in conjunction with the Field Sampling Plan for the HWMA/RCRA Closure Certification of the TRA-731 Caustic and Acid Storage Tank System. This Quality Assurance Project Plan specifies the procedures for obtaining the data of known quality required by the closure activities for the TRA-731 caustic and acid storage tank system.

  11. Waste management facilities cost information for transuranic waste

    International Nuclear Information System (INIS)

    This report contains preconceptual designs and planning level life-cycle cost estimates for managing transuranic waste. The report's information on treatment and storage modules can be integrated to develop total life-cycle costs for various waste management options. A procedure to guide the U.S. Department of Energy and its contractor personnel in the use of cost estimation data is also summarized in this report

  12. Waste management facilities cost information for transuranic waste

    Energy Technology Data Exchange (ETDEWEB)

    Shropshire, D.; Sherick, M.; Biagi, C.

    1995-06-01

    This report contains preconceptual designs and planning level life-cycle cost estimates for managing transuranic waste. The report`s information on treatment and storage modules can be integrated to develop total life-cycle costs for various waste management options. A procedure to guide the U.S. Department of Energy and its contractor personnel in the use of cost estimation data is also summarized in this report.

  13. Transuranic Behavior in Soils and Plants

    International Nuclear Information System (INIS)

    The principal objectives of these investigations are to determine (1) the potential for alteration of transuranic solubility through formation of transuranic complexes in soil and the role of the soil microflora in this process, (2) the extent of uptake nd translocation by plants and the sites of plant deposition of transuranics or their complexes, (3) the bond types and chemical forms of transuranics or their metabolites in microbes, plant tissues and soils, (4) the influence of soil properties, environmental conditions and cropping on these processes, and (5) the retention of airborne pollutants by plant foliage and their subsequent absorption by leaves and transport to seeds and roots

  14. Dosimetry of incorporated transuranic radionuclides

    International Nuclear Information System (INIS)

    Modern in vivo and in vitro techniques for detecting transuranic radionuclides within the human body are described with special emphasis on multiparameter measuring methods developed at the National Board of Nuclear Safety and Radiation Protection. Furthermore, problems related to calibration and interpretation of measuring data are discussed and new methods presented for the calculation of committed dose equivalents on the basis of data from ICRP Publication 30. Also included is an introductory chapter on radiobiological fundamentals of intake, translocation and metabolism of these nuclides. (author)

  15. Idaho National Engineering Laboratory code assessment of the Rocky Flats transuranic waste

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-07-01

    This report is an assessment of the content codes associated with transuranic waste shipped from the Rocky Flats Plant in Golden, Colorado, to INEL. The primary objective of this document is to characterize and describe the transuranic wastes shipped to INEL from Rocky Flats by item description code (IDC). This information will aid INEL in determining if the waste meets the waste acceptance criteria (WAC) of the Waste Isolation Pilot Plant (WIPP). The waste covered by this content code assessment was shipped from Rocky Flats between 1985 and 1989. These years coincide with the dates for information available in the Rocky Flats Solid Waste Information Management System (SWIMS). The majority of waste shipped during this time was certified to the existing WIPP WAC. This waste is referred to as precertified waste. Reassessment of these precertified waste containers is necessary because of changes in the WIPP WAC. To accomplish this assessment, the analytical and process knowledge available on the various IDCs used at Rocky Flats were evaluated. Rocky Flats sources for this information include employee interviews, SWIMS, Transuranic Waste Certification Program, Transuranic Waste Inspection Procedure, Backlog Waste Baseline Books, WIPP Experimental Waste Characterization Program (headspace analysis), and other related documents, procedures, and programs. Summaries are provided of: (a) certification information, (b) waste description, (c) generation source, (d) recovery method, (e) waste packaging and handling information, (f) container preparation information, (g) assay information, (h) inspection information, (i) analytical data, and (j) RCRA characterization.

  16. Idaho National Engineering Laboratory code assessment of the Rocky Flats transuranic waste

    International Nuclear Information System (INIS)

    This report is an assessment of the content codes associated with transuranic waste shipped from the Rocky Flats Plant in Golden, Colorado, to INEL. The primary objective of this document is to characterize and describe the transuranic wastes shipped to INEL from Rocky Flats by item description code (IDC). This information will aid INEL in determining if the waste meets the waste acceptance criteria (WAC) of the Waste Isolation Pilot Plant (WIPP). The waste covered by this content code assessment was shipped from Rocky Flats between 1985 and 1989. These years coincide with the dates for information available in the Rocky Flats Solid Waste Information Management System (SWIMS). The majority of waste shipped during this time was certified to the existing WIPP WAC. This waste is referred to as precertified waste. Reassessment of these precertified waste containers is necessary because of changes in the WIPP WAC. To accomplish this assessment, the analytical and process knowledge available on the various IDCs used at Rocky Flats were evaluated. Rocky Flats sources for this information include employee interviews, SWIMS, Transuranic Waste Certification Program, Transuranic Waste Inspection Procedure, Backlog Waste Baseline Books, WIPP Experimental Waste Characterization Program (headspace analysis), and other related documents, procedures, and programs. Summaries are provided of: (a) certification information, (b) waste description, (c) generation source, (d) recovery method, (e) waste packaging and handling information, (f) container preparation information, (g) assay information, (h) inspection information, (i) analytical data, and (j) RCRA characterization

  17. Privatization of contact-handled transuranic waste transportation services

    International Nuclear Information System (INIS)

    The U.S. Department of Energy (DOE) currently stores and generates contact-handled (CH) transuranic (TRU) waste at 10 major and 13 smaller sites across the United States. The opening of the Waste Isolation Pilot Plant (WIPP) in May 1998 will begin the use of a radioactive waste transportation system to transport TRU waste from these sites to the WIPP for disposal. The DOE will transport CH-TRU waste in a U.S. Nuclear Regulatory Commission (NRC)-certified type B package called the TRUPACT-II. The Carlsbad Area Office (CAO) has determined that the CH-TRU waste transportation system is sufficiently well defined to allow privatization, resulting in significant cost savings. The CAO manages the National Transuranic Program and has developed the National Transuranic (TRU) Waste Management Plan for integrating TRU waste management activities throughout the DOE complex. The management plan outlines an aggressive schedule for transporting and disposing of TRU waste at the WIPP. The WIPP is scheduled to begin receiving CH-TRU waste in May 1998, at which time five truck sets (a truck set consists of tractor, trailer, and three TRUPACT-IIs) will be in service. Starting in 1998, truck sets will be added until the fleet size reaches 20 in 2000. The WIPP CH-TRU waste-handling capacity will start at a rate of 250 shipments per year in 1998 and will increase to 850 shipments per year by the year 2000

  18. Transuranic element behavior in soils and plants

    International Nuclear Information System (INIS)

    The principal objective of this study is to define soil, plant, and foliar interaction processes that influence the availability of transuranic elements to agricultural plants and animals as a basis for improved modeling and dose-assessment. Major areas of emphasis are: (1) soil and soil-microbial processes that influence the concentration and form of transuranic elements in soil solutions and availability to the plant root with time; (2) deposition and plant interception of airborne submicronic particles containing transuranic elements and their susceptibility to leaching; (3) plant processes that influence transport across plant root membrane and foliar surfaces, as well as the form and sites of deposition of transuranic elements in mature plants; and (4) the integrated effect of soil and plant processes on transuranic element availability to, and form in, animals that consume plants

  19. Remote-handled transuranic system assessment appendices. Volume 2

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-11-01

    Volume 2 of this report contains six appendices to the report: Inventory and generation of remote-handled transuranic waste; Remote-handled transuranic waste site storage; Characterization of remote-handled transuranic waste; RH-TRU waste treatment alternatives system analysis; Packaging and transportation study; and Remote-handled transuranic waste disposal alternatives.

  20. Automated Sorting of Transuranic Waste

    Energy Technology Data Exchange (ETDEWEB)

    Shurtliff, Rodney Marvin

    2001-03-01

    The HANDSS-55 Transuranic Waste Sorting Module is designed to sort out items found in 55-gallon drums of waste as determined by an operator. Innovative imaging techniques coupled with fast linear motor-based motion systems and a flexible end-effector system allow the operator to remove items from the waste stream by a touch of the finger. When all desired items are removed from the waste stream, the remaining objects are automatically moved to a repackaging port for removal from the glovebox/cell. The Transuranic Waste Sorting Module consists of 1) a high accuracy XYZ Stereo Measurement and Imaging system, 2) a vibrating/tilting sorting table, 3) an XY Deployment System, 4) a ZR Deployment System, 5) several user-selectable end-effectors, 6) a waste bag opening system, 7) control and instrumentation, 8) a noncompliant waste load-out area, and 9) a Human/Machine Interface (HMI). The system is modular in design to accommodate database management tools, additional load-out ports, and other enhancements. Manually sorting the contents of a 55-gallon drum takes about one day per drum. The HANDSS-55 Waste Sorting Module is designed to significantly increase the throughput of this sorting process by automating those functions that are strenuous and tiresome for an operator to perform. The Waste Sorting Module uses the inherent ability of an operator to identify the items that need to be segregated from the waste stream and then, under computer control, picks that item out of the waste and deposits it in the appropriate location. The operator identifies the object by locating the visual image on a large color display and touches the image on the display with his finger. The computer then determines the location of the object, and performing a highspeed image analysis determines its size and orientation, so that a robotic gripper can be deployed to pick it up. Following operator verification by voice or function key, the object is deposited into a specified location.

  1. Transuranic contaminated waste functional definition and implementation

    International Nuclear Information System (INIS)

    The purpose of this report is to examine the problem(s) of TRU waste classification and to document the development of an easy-to-apply standard(s) to determine whether or not this waste package should be emplaced in a geologic repository for final disposition. Transuranic wastes are especially significant because they have long half-lives and some are rather radiotoxic. Transuranic radionuclides are primarily produced by single or multiple neutron capture by U-238 in fuel elements during the operation of a nuclear reactor. Reprocessing of spent fuel elements attempts to remove plutonium, but since the separation is not complete, the resulting high-activity liquids still contain some plutonium as well as other transuranics. Likewise, transuranic contamination of low-activity wastes also occurs when the transuranic materials are handled or processed, which is primarily at federal facilities involved in R and D and nuclear weapons production. Transuranics are persistent in the environment and, as a general rule, are strongly retained by soils. They are not easily transported through most food chains, although some reconcentration does take place in the aquatic food chain. They pose no special biological hazard to humans upon ingestion because they are weakly absorbed from the gastrointestional tract. A greater hazard results from inhalation since they behave like normal dust and fractionate accordingly

  2. Transuranics Laboratory, achievements and performance

    International Nuclear Information System (INIS)

    The Marine and Aquatic Radioecology Group (MARG) was established in 1985 with the main scope of analysing the consequences of the Palomares accident in the adjacent Mediterranean ecosystem. From then on and up to now , this Group has extended its investigations to other European marine environments, such as the Spanish Mediterranean margin, the Artic and the Atlantic. The main research of long-lived radionuclides (plutonium, americium and Cs-137) determining the orography influence, riverine inputs and their geo-chemical associations. This group is currently accomplishing new challenges on the radioecology field such as the development of techniques for transuranics speciation to determine their geo-chemical association to the main sediment compounds. Natural and anthropogenic radionuclides distribution on salt-marsh areas affected by dry-wet periods is being studied as well as the possibilities of fusing crossed techniques for dating recent sediments (pollen, anthropogenic, ''210 Pb, etc). The Laboratory performance description, the procedures used, calculations, challenges and gaps are described in this report. (Author) 22 refs

  3. Hanford transuranic storage corrosion review

    International Nuclear Information System (INIS)

    The rate of atmospheric corrosion of the transuranic (TRU) waste drums at the US Department of Energy's Hanford Project, near Richland, Washington, was evaluated by Pacific Northwest Laboratory (PNL). The rate of corrosion is principally contingent upon the effects of humidity, airborne pollutants, and temperature. Results of the study indicate that actual penetration of barrels due to atmospheric corrosion will probably not occur within the 20-year specified recovery period. Several other US burial sites were surveyed, and it appears that there is sufficient uncertainty in the available data to prevent a clearcut statement of the corrosion rate at a specific site. Laboratory and site tests are recommended before any definite conclusions can be made. The corrosion potential at the Hanford TRU waste site could be reduced by a combination of changes in drum materials (for example, using galvanized barrels instead of the currently used mild steel barrels), environmental exposure conditions (for example, covering the barrels in one of numerous possible ways), and storage conditions

  4. Remote-Handled Transuranic Content Codes

    Energy Technology Data Exchange (ETDEWEB)

    Washington TRU Solutions

    2001-08-01

    The Remote-Handled Transuranic (RH-TRU) Content Codes (RH-TRUCON) document representsthe development of a uniform content code system for RH-TRU waste to be transported in the 72-Bcask. It will be used to convert existing waste form numbers, content codes, and site-specificidentification codes into a system that is uniform across the U.S. Department of Energy (DOE) sites.The existing waste codes at the sites can be grouped under uniform content codes without any lossof waste characterization information. The RH-TRUCON document provides an all-encompassing|description for each content code and compiles this information for all DOE sites. Compliance withwaste generation, processing, and certification procedures at the sites (outlined in this document foreach content code) ensures that prohibited waste forms are not present in the waste. The contentcode gives an overall description of the RH-TRU waste material in terms of processes and|packaging, as well as the generation location. This helps to provide cradle-to-grave traceability ofthe waste material so that the various actions required to assess its qualification as payload for the72-B cask can be performed. The content codes also impose restrictions and requirements on themanner in which a payload can be assembled.The RH-TRU Waste Authorized Methods for Payload Control (RH-TRAMPAC), Appendix 1.3.7of the 72-B Cask Safety Analysis Report (SAR), describes the current governing procedures|applicable for the qualification of waste as payload for the 72-B cask. The logic for this|classification is presented in the 72-B Cask SAR. Together, these documents (RH-TRUCON,|RH-TRAMPAC, and relevant sections of the 72-B Cask SAR) present the foundation and|justification for classifying RH-TRU waste into content codes. Only content codes described in thisdocument can be considered for transport in the 72-B cask. Revisions to this document will be madeas additional waste qualifies for transport. |Each content code uniquely

  5. Remote-Handled Transuranic Content Codes

    International Nuclear Information System (INIS)

    The Remote-Handled Transuranic (RH-TRU) Content Codes (RH-TRUCON) document represents the development of a uniform content code system for RH-TRU waste to be transported in the 72-Bcask. It will be used to convert existing waste form numbers, content codes, and site-specific identification codes into a system that is uniform across the U.S. Department of Energy (DOE) sites.The existing waste codes at the sites can be grouped under uniform content codes without any lossof waste characterization information. The RH-TRUCON document provides an all-encompassing description for each content code and compiles this information for all DOE sites. Compliance with waste generation, processing, and certification procedures at the sites (outlined in this document foreach content code) ensures that prohibited waste forms are not present in the waste. The content code gives an overall description of the RH-TRU waste material in terms of processes and packaging, as well as the generation location. This helps to provide cradle-to-grave traceability of the waste material so that the various actions required to assess its qualification as payload for the 72-B cask can be performed. The content codes also impose restrictions and requirements on the manner in which a payload can be assembled. The RH-TRU Waste Authorized Methods for Payload Control (RH-TRAMPAC), Appendix 1.3.7 of the 72-B Cask Safety Analysis Report (SAR), describes the current governing procedures applicable for the qualification of waste as payload for the 72-B cask. The logic for this classification is presented in the 72-B Cask SAR. Together, these documents (RH-TRUCON, RH-TRAMPAC, and relevant sections of the 72-B Cask SAR) present the foundation and justification for classifying RH-TRU waste into content codes. Only content codes described in thisdocument can be considered for transport in the 72-B cask. Revisions to this document will be madeas additional waste qualifies for transport. Each content code uniquely

  6. Standards and general criteria for the planning and certification of need of megavoltage radiation oncology units in health care facilities

    International Nuclear Information System (INIS)

    Minimum standards and guidelines to be applied by State agencies and New Jersey health systems agencies in the examination of certificate-of-need applications and in the development of planning activities for radiation oncology units in health care facilities are presented. Radiation oncology is a medical discipline devoted to education and research in the use of ionizing radiation for the treatment of neoplastic disease. The proper application of radiation can be directed at either curative or palliative intent. It is an important and effective technique for the management of cancer. Radiotherapy equipment in clinical use is divided into four main categories: superficial, orthovoltage, megavoltage, and treatment planning facilities. Particular attention is given to megavoltage equipment which emits or generates rays over 1,000 kilovolts. These high energy rays effect better penetration of human tissue and are skin-sparing in nature, thus allowing for better tumor-to- skin dose ratios. The regionalization of megavoltage therapy services is discussed. Data on hospital megavoltage facilities in New Jersey for 1974, 1975, and 1976 are provided. The standards and guidelines pertain to utilization, personnel, and general criteria. A form for use by megavoltage radiation therapy units is appended

  7. Emergency Preparedness Hazards Assessment for Transuranic (TRU) Waste Pads. Revision 1

    International Nuclear Information System (INIS)

    This report is a revision of the facility Emergency Preparedness Hazards Assessment (EPHA) for the Transuranic (TRU) Waste Pads located on the Department of Energy (DOE) Savannah River Site (SRS). The EPHA was conducted in accordance with Emergency Management Program Procedure (EMPP) 6Q-001 (Ref. 1). The EPHA provides the technical basis for facility emergency planning efforts

  8. The value of assessments in Lawrence Livermore National Laboratory's Waste Certification Programs

    International Nuclear Information System (INIS)

    This paper will discuss the value of assessments in Lawrence Livermore National Laboratory's Waste Certification Programs by: introducing the organization and purpose of the LLNL Waste Certification Programs for transuranic, low-level, and hazardous waste; examining the differences in internal assessment/audit requirements for these programs; discussing the values and costs of assessments in a waste certification program; presenting practical recommendations to maximize the value of your assessment programs; and presenting improvements in LLNL's waste certification processes that resulted from assessments

  9. Integration of Professional Certification Examinations with the Financial Planning Curriculum: Increasing Efficiency, Motivation, and Professional Success

    Science.gov (United States)

    Goetz, Joseph W.; Zhu, Dandan; Hampton, Vickie L.; Chatterjee, Swarn; Salter, John

    2011-01-01

    This article provides a theoretical-based rationale and plan of action for educational programs to encourage and create opportunities for the integration of course study with professional exam preparation, while highlighting the complementary benefits for students, academic programs, and the financial services profession. Serving primarily as a…

  10. TRANSURANIC METAL HALIDES AND A PROCESS FOR THE PRODUCTION THEREOF

    Science.gov (United States)

    Fried, S.

    1951-03-20

    Halides of transuranic elements are prepared by contacting with aluminum and a halogen, or with an aluminum halide, a transuranic metal oxide, oxyhalide, halide, or mixture thereof at an elevated temperature.

  11. Implications of Fast Reactor Transuranic Conversion Ratio

    Energy Technology Data Exchange (ETDEWEB)

    Steven J. Piet; Edward A. Hoffman; Samuel E. Bays

    2010-11-01

    Theoretically, the transuranic conversion ratio (CR), i.e. the transuranic production divided by transuranic destruction, in a fast reactor can range from near zero to about 1.9, which is the average neutron yield from Pu239 minus 1. In practice, the possible range will be somewhat less. We have studied the implications of transuranic conversion ratio of 0.0 to 1.7 using the fresh and discharge fuel compositions calculated elsewhere. The corresponding fissile breeding ratio ranges from 0.2 to 1.6. The cases below CR=1 (“burners”) do not have blankets; the cases above CR=1 (“breeders”) have breeding blankets. The burnup was allowed to float while holding the maximum fluence to the cladding constant. We graph the fuel burnup and composition change. As a function of transuranic conversion ratio, we calculate and graph the heat, gamma, and neutron emission of fresh fuel; whether the material is “attractive” for direct weapon use using published criteria; the uranium utilization and rate of consumption of natural uranium; and the long-term radiotoxicity after fuel discharge. For context, other cases and analyses are included, primarily once-through light water reactor (LWR) uranium oxide fuel at 51 MWth-day/kg-iHM burnup (UOX-51). For CR<1, the heat, gamma, and neutron emission increase as material is recycled. The uranium utilization is at or below 1%, just as it is in thermal reactors as both types of reactors require continuing fissile support. For CR>1, heat, gamma, and neutron emission decrease with recycling. The uranium utilization exceeds 1%, especially as all the transuranic elements are recycled. exceeds 1%, especially as all the transuranic elements are recycled. At the system equilibrium, heat and gamma vary by somewhat over an order of magnitude as a function of CR. Isotopes that dominate heat and gamma emission are scattered throughout the actinide chain, so the modest impact of CR is unsurprising. Neutron emitters are preferentially found

  12. Assessment of LANL transuranic waste management documentation

    International Nuclear Information System (INIS)

    This report presents the findings that resulted from the evaluation of the Los Alamos National Laboratory (LANL) TRU Waste Characterization Procedures, conducted to determine their compliance with applicable DOE requirements. The driving requirements for the procedures appear to be contained in DOE Order 5820.2A; specific reference is made to Chapter II of that document. In addition, the WIPP-WAC sets forth specific waste forms and establishes the basis for LANL's TRU Waste Acceptance Criteria; any characterization plan must utilize procedures that address the requirements of the WIPP-WAC in order to ensure compliance with it. The purpose of the characterization procedures is to provide details to waste generators and/or waste certifiers regarding how the characterization plan is implemented for the gathering of analytical and/or knowledge-of-process information to allow certification of the waste. An annotated outline was developed from those criteria found in Sections 4.0 and 5.0 of the WIPP-WAC. The annotated outline of elements that should be addressed in characterization procedures is provided

  13. Contact-Handled Transuranic Waste Acceptance Criteria for the Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    The purpose of this document is to summarize the waste acceptance criteria applicable to the transportation, storage, and disposal of contact-handled transuranic (CH-TRU) waste at the Waste Isolation Pilot Plant (WIPP). These criteria serve as the U.S. Department of Energy's (DOE) primary directive for ensuring that CH-TRU waste is managed and disposed of in a manner that protects human health and safety and the environment.The authorization basis of WIPP for the disposal of CH-TRU waste includes the U.S.Department of Energy National Security and Military Applications of Nuclear EnergyAuthorization Act of 1980 (reference 1) and the WIPP Land Withdrawal Act (LWA;reference 2). Included in this document are the requirements and associated criteriaimposed by these acts and the Resource Conservation and Recovery Act (RCRA,reference 3), as amended, on the CH-TRU waste destined for disposal at WIPP.|The DOE TRU waste sites must certify CH-TRU waste payload containers to thecontact-handled waste acceptance criteria (CH-WAC) identified in this document. Asshown in figure 1.0, the flow-down of applicable requirements to the CH-WAC istraceable to several higher-tier documents, including the WIPP operational safetyrequirements derived from the WIPP CH Documented Safety Analysis (CH-DSA;reference 4), the transportation requirements for CH-TRU wastes derived from theTransuranic Package Transporter-Model II (TRUPACT-II) and HalfPACT Certificates ofCompliance (references 5 and 5a), the WIPP LWA (reference 2), the WIPP HazardousWaste Facility Permit (reference 6), and the U.S. Environmental Protection Agency(EPA) Compliance Certification Decision and approval for PCB disposal (references 7,34, 35, 36, and 37). The solid arrows shown in figure 1.0 represent the flow-down of allapplicable payload container-based requirements. The two dotted arrows shown infigure 1.0 represent the flow-down of summary level requirements only; i.e., the sitesmust reference the regulatory source

  14. Expert system for transuranic waste assay

    International Nuclear Information System (INIS)

    Transuranic wastes are generated at the Savannah River Site (SRS) as a result of routine production of nuclear materials. These wastes contain Pu-238 and Pu-239 and are placed into lined 55-gallon waste drums. The drums are placed on monitored storage pads pending shipment to the Waste Isolation Pilot Plant in New Mexico. A passive-active neutron (PAN) assay system is used to determine the mass of the radioactive material within the waste drums. Assay results are used to classify the wastes as either low-level or transuranic (TRU). During assays, the PAN assay system communicates with an IBM-AT computer. A Fortran computer program, called NEUT, controls and performs all data analyses. Unassisted, the NEUT program cannot adequately interpret assay results. To eliminate this limitation, an expert system shell was used to write a new algorithm, called the Transuranic Expert System (TRUX), to drive the NEUT program and add decision making capabilities for analysis of the assay results. The TRUX knowledge base was formulated by consulting with human experts in the field of neutron assay, by direct experimentation on the PAN assay system, and by observing operations on a daily basis. TRUX, with its improved ability to interpret assay results, has eliminated the need for close supervision by a human expert, allowing skilled technicians to operate the PAN assay system. 4 refs., 1 fig., 4 tabs

  15. Xenon Isotope Releases from Buried Transuranic Waste

    Science.gov (United States)

    Dresel, P. E.; Waichler, S. R.; Kennedy, B. M.; Hayes, J. C.; McIntyre, J. I.; Giles, J. R.; Sondrup, A. J.

    2004-12-01

    Xenon is an inert rare gas produced as a fission product in nuclear reactors and through spontaneous fission of some transuranic isotopes. Thus, xenon will be released from buried transuranic waste. Two complementary methods are used to measure xenon isotopes: radiometric analysis for short-lived radioxenon isotopes and mass spectrometry for detection of stable xenon isotopes. Initial measurements near disposal facilities at the U.S. Department of Energy's Hanford Site show radioxenon and stable xenon isotopic signatures that are indicative of transuranic waste. Radioxenon analysis has greater sensitivity due to the lower background concentrations and indicates spontaneous fission due to the short half life of the isotopes. Stable isotope ratios may be used to distinguish irradiated fuel sources from pure spontaneous fission sources and are not as dependent on rapid release from the waste form. The release rate is dependent on the type of waste and container integrity and is the greatest unknown in application of this technique. Numerical multi-phase transport modeling of burial grounds at the Idaho National Engineering and Environmental Laboratory indicates that, under generalized conditions, the radioxenon isotopes will diffuse away from the waste and be found in the soil cap and adjacent to the burial ground at levels many orders of magnitude above the detection limit.

  16. 33 CFR 274.5 - Certification.

    Science.gov (United States)

    2010-07-01

    ... PEST CONTROL PROGRAM FOR CIVIL WORKS PROJECTS Project Operation § 274.5 Certification. Under the... certification of Civil Works personnel. Pending final approval of the DOD Agency Plan, all Corps of Engineers... and the Division Engineer....

  17. Defense Transuranic Waste Program. Transuranic waste transportation assessment and guidance report

    Energy Technology Data Exchange (ETDEWEB)

    1985-08-01

    The Transportation Assessment and Guidance Report (TAGR) is designed to provide DOE-managed defense sites with guidance and citable analyses addressing National Environmental Policy Act (NEPA) requirements for qualifying and transporting transuranic (TRU) wastes to the Waste Isolation Pilot Plant (WIPP) in southeastern New Mexico.

  18. Defense Transuranic Waste Program. Transuranic waste transportation assessment and guidance report

    International Nuclear Information System (INIS)

    The Transportation Assessment and Guidance Report (TAGR) is designed to provide DOE-managed defense sites with guidance and citable analyses addressing National Environmental Policy Act (NEPA) requirements for qualifying and transporting transuranic (TRU) wastes to the Waste Isolation Pilot Plant (WIPP) in southeastern New Mexico

  19. Making transuranic assay measurements using modern controllers

    International Nuclear Information System (INIS)

    This paper describes methodology and computer-controlled instrumentation developed at the Los Alamos National Laboratory that accurately performs nondestructive assays of large containers bearing transuranic wastes and nonradioactive matrix materials. These assay systems can measure fissile isotopes with 1-mg sensitivity and spontaneous neutron-emitting isotopes at a 10-mg sensitivity. The assays are performed by neutron interrogation, detection, and counting in a custom assay chamber. An International Business Machines Personal Computer (IBM-PC) is used to control the CAMAC-based instrumentation system that acquires the assay data. 6 refs., 7 figs

  20. From the global efforts on certification of bioenergy towards an integrated approach based on sustainable land use planning

    International Nuclear Information System (INIS)

    This paper presents an overview of 67 ongoing certification initiatives to safeguard the sustainability of bioenergy. Most recent initiatives are focused on the sustainability of liquid biofuels. Content-wise, most of these initiatives have mainly included environmental principles. Despite serious concerns in various parts of the world on the socio-economic impacts of bioenergy production, these are generally not included in existing bioenergy initiatives. At the same time, the overview shows a strong proliferation of standards. The overview shows that certification has the potential to influence direct, local impacts related to environmental and social effects of direct bioenergy production. Key recommendations to come to an efficient certification system include the need for further harmonization, availability of reliable data and linking indicators on a micro, meso and macro levels. Considering the multiple spatial scales, certification should be combined with additional measurements and tools on a regional, national and international level. The role of bioenergy production on indirect land use change (ILUC) is still very uncertain and current initiatives have rarely captured impacts from ILUC in their standards. Addressing unwanted LUC requires first of all sustainable land use production and good governance, regardless of the end-use of the product. It is therefore recommended to extend measures to mitigate impacts from LUC to other lands and feedstock. (author)

  1. Fusion-Fission Burner for Transuranic Actinides

    Science.gov (United States)

    Choi, Chan

    2013-10-01

    The 14-MeV DT fusion neutron spectrum from mirror confinement fusion can provide a unique capability to transmute the transuranic isotopes from light water reactors (LWR). The transuranic (TRU) actinides, high-level radioactive wastes, from spent LWR fuel pose serious worldwide problem with long-term decay heat and radiotoxicity. However, ``transmuted'' TRU actinides can not only reduce the inventory of the TRU in the spent fuel repository but also generate additional energy. Typical commercial LWR fuel assemblies for BWR (boiling water reactor) and PWR (pressurized water reactor) measure its assembly lengths with 4.470 m and 4.059 m, respectively, while its corresponding fuel rod lengths are 4.064 m and 3.851 m. Mirror-based fusion reactor has inherently simple geometry for transmutation blanket with steady-state reactor operation. Recent development of gas-dynamic mirror configuration has additional attractive feature with reduced size in central plasma chamber, thus providing a unique capability for incorporating the spent fuel assemblies into transmutation blanket designs. The system parameters for the gas-dynamic mirror-based hybrid burner will be discussed.

  2. In situ grouting of buried transuranic waste

    International Nuclear Information System (INIS)

    This task is a demonstration and evaluation of the in situ hydrologic stabilization of buried transuranic waste at a humid site via grout injection. Two small trenches, containing buried transuranic waste, were filled with 34,000 liters of polyacrylamide grout. Initial field results have indicated that voids within the trenches were totally filled by the grout and that the intratrench hydraulic conductivity was reduced to below field-measurable values. The grout was also completely contained within the two trenches as no grout constituents were observed in the 12 perimeter ground water monitoring wells. Polyacrylamide grout was selected for field demonstration over polyacrylate grout because of its superior performance in laboratory degradation studies. Also supporting the selection of polyacrylamide was the difficulty of controlling the set time of the acrylate polymerization process in the presence of potassium ferricyanide. Based on preliminary degradation monitoring, polyacrylamide was estimated to have a microbiological half-life of 115 years in the test soil. However, this calculated value is likely to be conservatively low because microbial degradation of the grout set accelerator or residual monomer may be contributing most to the measured microbial respiration. Addition work, using 14C-labeled acrylate and acrylamide grouts, is being carried out to more accurately estimate the grouts' microbiological half-life

  3. Pre-1970 transuranic solid waste at the Hanford Site

    Energy Technology Data Exchange (ETDEWEB)

    Greenhalgh, W.O.

    1995-05-23

    The document is based on a search of pre-1970 Hanford Solid Waste Records. The available data indicates seven out of thirty-one solid waste burial sites used for pre-1970 waste appear to be Transuranic (TRU). A burial site defined to be TRU contains >100 nCi/gm Transuranic nuclides.

  4. Bone and lung tumor response following inhalation of transuranic nitrates

    International Nuclear Information System (INIS)

    Eight-hundred five rats exposed to transuranic nitrate aerosols developed 111 lung tumors and 24 bone tumors. Results for 239Pu(NO3)4, 238Pu(NO3)4, and 253Es(NO3)3 were similar, and comparable to what has been shown for the more refractory transuranic oxides

  5. Hanford Site Hazardous waste determination report for transuranic debris waste streams NPFPDL2A

    Energy Technology Data Exchange (ETDEWEB)

    WINTERHALDER, J.A.

    1999-09-29

    This hazardous waste determination report (Report) describes the process and information used on the Hanford Site to determine that waste stream number NPFPDLZA, consisting of 30 containers of contact-handled transuranic debris waste, is not hazardous waste regulated by the Resource Conservation and Recovery Act (RCRA) or the New Mexico Hazardous Waste Act. For a waste to be hazardous under these statutes, the waste either must be specifically listed as a hazardous waste, or exhibit one or more of the characteristics of a hazardous waste, Le., ignitability, corrosivity, reactivity, or toxicity. Waste stream NPFPDLZA was generated, packaged, and placed into storage between 1993 and 1997. Extensive knowledge of the waste generating process, facility operational history, and administrative controls and operating procedures in effect at the time of generation, supported the initial nonhazardous waste determination. Because of the extent and reliability of information pertaining to this waste type, and the total volume of waste in the debris matrix parameter category, the Hanford Site is focusing initial efforts on this and similar waste streams for the first shipment to the Waste Isolation Pilot Plant (WIPP). RCRA regulations authorize hazardous waste determinations to be made either by using approved sampling and analysis methods or by applying knowledge of the waste in light of the materials or the process(es) used. This latter approach typically is referred to as process knowledge. The Transuranic Waste Characterization Quality Assurance Program Plan (CAO-94-1010) for WIPP refers to acceptable knowledge in essentially the same terms; acceptable knowledge as used throughout this Report is synonymous with the term process knowledge. The 30 containers addressed in this Report were characterized by the following methods: Acceptable knowledge; Nondestructive examination using real-time radiography; Visual examination; and Headspace gas sampling and analysis. The initial

  6. The National Remote-Handled Transuranic Waste Program

    International Nuclear Information System (INIS)

    Since the Waste Isolation Pilot Plant (WIPP) opened for nonmixed contact-handled (CH) transuranic (TRU) waste receipt on March 26, 1999, planning for the receipt of remote-handled (RH) TRU waste has been revitalized. WIPP is scheduled to begin receiving RH TRU waste in January 2002. Before the first receipt of RH waste at WIPP, the disposal of RH TRU waste must be coordinated with the waste management plans at the TRU waste sites, the packaging and transportation system must be in place and operational, and the WIPP RH must be operational. Successful implementation of the National RH TRU Waste Program will require that a commitment to sustained funding and full support of the entire DOE TRU waste complex be maintained. Implementation will also require effective application of capital assets, human resources, and a continued effort to identify and resolve programmatic and technical issues. Involvement of regulatory agencies, stakeholders, and affected tribal nations in decision-making processes will have a positive impact on successful implementation

  7. TRU waste certification and TRUPACT-2 payload verification

    International Nuclear Information System (INIS)

    The Waste Isolation Pilot Plant (WIPP) established a policy that requires each waste shipper to verify that all waste shipments meet the requirements of the Waste Acceptance Criteria (WAC) prior to being shipped. This verification provides assurance that transuranic (TRU) wastes meet the criteria while still retained in a facility where discrepancies can be immediately corrected. Each Department of Energy (DOE) TRU waste facility planning to ship waste to the Waste Isolation Pilot Plant (WIPP) is required to develop and implement a specific program including Quality Assurance (QA) provisions to verify that waste is in full compliance with WIPP's WAC. This program is audited by a composite DOE and contractor audit team prior to granting the facility permission to certify waste. During interaction with the Nuclear Regulatory Commission (NRC) on payload verification for shipping in TRUPACT-II, a similar system was established by DOE. The TRUPACT-II Safety Analysis Report (SAR) contains the technical requirements and physical and chemical limits that payloads must meet (like the WAC). All shippers must plan and implement a payload control program including independent QA provisions. A similar composite audit team will conduct preshipment audits, frequent subsequent audits, and operations inspections to verify that all TRU waste shipments in TRUPACT-II meet the requirements of the Certificate of Compliance issued by the NRC which invokes the SAR requirements. 1 fig

  8. Recovery of transuranics from process residues

    International Nuclear Information System (INIS)

    Process residues are generated at both the Rocky Flats Plant (RFP) and the Savannah River Plant (SRP) during aqueous chemical and pyrochemical operations. Frequently, process operations will result in either impure products or produce residues sufficiently contaminated with transuranics to be nondiscardable as waste. Purification and recovery flowsheets for process residues have been developed to generate solutions compatible with subsequent Purex operations and either solid or liquid waste suitable for disposal. The ''scrub alloy'' and the ''anode heel alloy'' are examples of materials generated at RFP which have been processed at SRP using the developed recovery flowsheets. Examples of process residues being generated at SRP for which flowsheets are under development include LECO crucibles and alpha-contaminated hydraulic oil

  9. Physical Properties of Hanford Transuranic Waste Sludge

    International Nuclear Information System (INIS)

    Equipment that was purchased in the abbreviated year 1 of this project has been used during year 2 to study the fundamental behavior of materials that simulate the behavior of the Hanford transuranic waste sludge. Two significant results have been found, and each has been submitted for publication. Both studies found non-DLVO behavior in simulant systems. These separate but related studies were performed concurrently. It was previously shown in Rassat et al.'s report Physical and Liquid Chemical Simulant Formulations for Transuranic Wastes in Hanford Single-Shell Tanks that colloidal clays behave similarly to transuranic waste sludge (PNNL-14333, National Technical Information Service, U.S. Dept. of Commerce). Rassat et al. also discussed the pH and salt content of actual waste materials. It was shown that these materials exist at high pHs, generally above 10, and at high salt content, approximately 1.5 M from a mixture of different salts. A type of clay commonly studied, due to its uniformity, is a synthetic hectorite, Laponite. Therefore the work performed over the course of the last year was done mainly using suspensions of Laponite at high pH and involving high salt concentrations. One study was titled ''Relating Clay Rheology to Colloidal Parameters''. It has been submitted to the Journal of Colloid and INterface Science and is currently in the review process. The idea was to gain the ability to use measurable quantities to predict the flow behavior of clay systems, which should be similar to transuranic waste sludge. Leong et al. had previously shown that the yield stress of colloidal slurries of titania and alumina could be predicted, given the measurement of the accessible parameter zeta potential (Leong YK et al. J Chem Soc Faraday Trans, 19 (1993) 2473). Colloidal clays have a fundamentally different morphology and surface charge distribution than the spheroidal, uniformly charged colloids previously studied. This study was therefore performed in order to

  10. Physical Properties of Hanford Transuranic Waste

    Energy Technology Data Exchange (ETDEWEB)

    Berg, John C.

    2010-03-25

    The research described herein was undertaken to provide needed physical property descriptions of the Hanford transuranic tank sludges under conditions that might exist during retrieval, treatment, packaging and transportation for disposal. The work addressed the development of a fundamental understanding of the types of systems represented by these sludge suspensions through correlation of the macroscopic rheological properties with particle interactions occurring at the colloidal scale in the various liquid media. The results of the work have advanced existing understanding of the sedimentation and aggregation properties of complex colloidal suspensions. Bench scale models were investigated with respect to their structural, colloidal and rheological properties that should be useful for the development and optimization of techniques to process the wastes at various DOE sites.

  11. Safer Transportation and Disposal of Remote Handled Transuranic Waste - 12033

    Energy Technology Data Exchange (ETDEWEB)

    Rojas, Vicente; Timm, Christopher M.; Fox, Jerry V. [PECOS Management Services, Inc., Albuquerque, NM (United States)

    2012-07-01

    Since disposal of remote handled (RH) transuranic (TRU) waste at the Waste Isolation Pilot Plant (WIPP) began in 2007, the Department of Energy (DOE) has had difficulty meeting the plans and schedule for disposing this waste. PECOS Management Services, Inc. (PECOS) assessed the feasibility of proposed alternate RH-TRU mixed waste containerisation concepts that would enhance the transportation rate of RH-TRU waste to WIPP and increase the utilization of available WIPP space capacity for RH-TRU waste disposal by either replacing or augmenting current and proposed disposal methods. In addition engineering and operational analyses were conducted that addressed concerns regarding criticality, heat release, and worker exposure to radiation. The results of the analyses showed that the concept, development, and use of a concrete pipe based design for an RH-TRU waste shipping and disposal container could be potentially advantageous for disposing a substantial quantity of RHTRU waste at WIPP in the same manner as contact-handled RH waste. Additionally, this new disposal method would eliminate the hazard associated with repackaging this waste in other containers without the requirement for NRC approval for a new shipping container. (authors)

  12. Optimization of magnetite carrier precipitation process for transuranic waste reduction

    Energy Technology Data Exchange (ETDEWEB)

    Slater, S.A.; Chamberlain, D.B.; Aase, S.A.; Babcock, B.D.; Conner, C.; Sedlet, J.; Vandegrift, G.F. [Argonne National Lab., IL (United States). Chemical Technology Div.

    1995-12-31

    Transuranic (TRU) waste that is being generated at Argonne National Laboratory has a TRU activity ranging from 10{sup 2} to 10{sup 7} nCi/g with a wide variety of chemical compositions. Currently, the waste is stored in highly acidic solutions that must be neutralized for intermediate storage. A magnetite carrier precipitation process has been adapted to concentrate TRU isotopes in a noncorrosive solid phase. In this paper, the authors report the results of a series of laboratory tests done to optimize the process. The parameters they optimized included (1) magnetite concentration used to precipitate the TRUs from solution, (2) formation of magnetite (in situ or ex situ), (3) processing pH, and (4) temperature and mixing time of the carrier precipitation. They also studied the effects of anions, cations, and complexing agents in the waste solutions on the carrier precipitation and the effect of magnetite solids loading on the filtration equipment. An overview is given of the planned full-scale process, which will be operated in a glovebox.

  13. IMPROVEMENTS IN HANFORD TRANSURANIC (TRU) PROGRAM UTILIZING SYSTEMS MODELING AND ANALYSES

    Energy Technology Data Exchange (ETDEWEB)

    UYTIOCO EM

    2007-11-12

    Hanford's Transuranic (TRU) Program is responsible for certifying contact-handled (CH) TRU waste and shipping the certified waste to the Waste Isolation Pilot Plant (WIPP). Hanford's CH TRU waste includes material that is in retrievable storage as well as above ground storage, and newly generated waste. Certifying a typical container entails retrieving and then characterizing it (Real-Time Radiography, Non-Destructive Assay, and Head Space Gas Sampling), validating records (data review and reconciliation), and designating the container for a payload. The certified payload is then shipped to WIPP. Systems modeling and analysis techniques were applied to Hanford's TRU Program to help streamline the certification process and increase shipping rates.

  14. Chemical behaviour of transuranic elements in the natural environment

    International Nuclear Information System (INIS)

    The chemical behaviour of transuranic elements in natural aquifer systems is governed by a variety of geochemical reactions, such as dissolution reaction (solubility), hydrolysis, complexation with inorganics or organics, redox reaction, colloid formation, geochemical interaction with surfaces of various minerals, coprecipitation, mineralisation etc. This paper reviews the present state of knowledge on some of these particular reactions. The emphasis is placed on how the individual reactions can be appraised for the long-term prediction of the geochemical behaviour of transuranic elements in the natural environment. Of the various reactions, the primary thermodynamic processes of dissolution of transuranic compounds in aquatic solution, complexation with important anions present in groundwater and colloid generation are discussed with notable examples. Various laser spectroscopy in use for the chemical speciation are mentioned briefly as for their spectroscopic capability as well as applicability. The present review discussion is primarily directed to a better understanding of the migration behaviour of transuranic elements in natural aquifer systems. (author) 100 refs

  15. Transuranic contaminated waste form characterization and data base

    International Nuclear Information System (INIS)

    This volume contains 5 appendices. Title listing are: technologies for recovery of transuranics; nondestructive assay of TRU contaminated wastes; miscellaneous waste characteristics; acceptance criteria for TRU waste; and TRU waste treatment technologies

  16. TRANSURANIC INTERFACIAL REACTION STUDIES ON MANGANESE OXIDE HYDROXIDE MINERAL SURFACES

    Science.gov (United States)

    Several DOE sites have been contaminated by transuranic radionuclide (TRU) discharges. Of these TRU, neptunium and plutonium are highly toxic and potentially mobile in the vadose zone. Modeling predictions of their potential hazard to humans require reliable estimates of migrat...

  17. Transuranic radionuclides dispersed into the aquatic environment, a bibliography

    Energy Technology Data Exchange (ETDEWEB)

    Noshkin, V.E.; Stoker, A.C.; Wong, Kai M. [and others

    1994-04-01

    The purpose of this project was to compile a bibliography of references containing environmental transuranic radionuclide data. Our intent was to identify those parameters affecting transuranic radionuclide transport that may be generic and those that may be dependent on chemical form and/or environmental conditions (i.e., site specific) in terrestrial, aquatic and atmospheric environments An understanding of the unique characteristics and similarities between source terms and environmental conditions relative to transuranic radionuclide transport and cycling will provide the ability to assess and predict the long term impact on man and the environment. An additional goal of our literature review, was to extract the ranges of environmental transuranic radionuclide data from the identified references for inclusion in a data base. Related to source term, these ranges of data can be used to calculate the dose to man from the radionuclides, and to perform uncertainty analyses on these dose assessments. On the basis of our reviews, we have arbitrarily outlined five general source terms. These are fallout, fuel cycle waste, accidents, disposal sites and resuspension. Resuspension of the transuranic radionuclides is a unique source term, in that the radionuclides can originate from any of the other source terms. If these transuranic radionuclides become resuspended into the air, they then become important as a source of inhaled radionuclides.

  18. Hanford Site Hazardous waste determination report for transuranic debris waste streams NPFPDL1A, NPFPDL1B, NPFPDL1C and NPFPDL1D

    Energy Technology Data Exchange (ETDEWEB)

    WINTERHALDER, J.A.

    1999-09-29

    This Hazardous Waste Determination Report is intended to satisfy the terms of a Memorandum of Agreement (Agreement signed on June 16, 1999) between the U.S. Department of Energy and the New Mexico Environment Department. The Agreement pertains to the exchange of information before a final decision is made on the Waste Isolation Pilot Plant application for a permit under the ''New Mexico Hazardous Waste Act''. The Agreement will terminate upon the effective date of a final ''New Mexico Hazardous Waste Act'' permit for the Waste Isolation Pilot Plant. In keeping with the principles and terms of the Agreement, this report describes the waste stream data and information compilation process, and the physical and chemical analyses that the U.S. Department of Energy has performed on selected containers of transuranic debris waste to confirm that the waste is nonhazardous (non-mixed). This also summarizes the testing and analytical results that support the conclusion that the selected transuranic debris waste is not hazardous and thus, not subject to regulation under the ''Resource Conservation and Recovery Act'' or the ''New Mexico Hazardous Waste Act''. This report will be submitted to the New Mexico Environment Department no later than 45 days before the first shipment of waste from the Hanford Site to the Waste Isolation Pilot Plant, unless the parties mutually agree in writing to a shorter time. The 52 containers of transuranic debris waste addressed in this report were generated, packaged, and placed into storage between 1995 and 1997. Based on reviews of administrative documents, operating procedures, waste records, generator certifications, and personnel interviews, this transuranic debris waste was determined to be nonhazardous. This determination is supported by the data derived from nondestructive examination, confirmatory visual examination, and the results of container headspace

  19. Recertification Project Plan

    International Nuclear Information System (INIS)

    The Waste Isolation Pilot Plant's (WIPP) Recertification Project was established to meet the requirement placed in the WIPP Land Withdrawal Act (LWA) to demonstrate WIPP's continued compliance with the Environmental Protection Agency's (EPA) disposal regulations at five-year intervals. This plan delineates the end goal of the effort, sets out interim goals, and offers up guiding assumptions. In general, it sets the overall direction for a highly complex and interdependent set of tasks leading to recertification of the repository in the spring of 2004. In addition, this plan establishes the institutional roles and responsibilities of WIPP project participants in the recertification effort and lays out a high-level schedule for producing the Compliance Recertification Application (CRA). Detailed plans from each organization supporting this project have been included with this document as attachments. Each participant plan provides significantly more detail with descriptions of activities that are designed to ensure a successful outcome. Woven throughout this plan are the elements of guidance and direction gained from technical exchanges with EPA managers and staff. An important principle on which this plan is built is that the process of recertification will not involve modification to the certification baseline, nor will it involve rule making of any kind. Only changes previously approved by the EPA will be detailed in the CRA. EPA-approved changes to the WIPP certification will be accepted through modification or will be approved through the annual change reporting process. For any compliance areas that have not changed since the submission of the Compliance Certification Application(CCA), these will merely be incorporated in the CRA by reference. The CRA will cover all information since the October 1996 submittal of the CCA. A second major principle on which this plan is built stems from the EPA WIPP Recertification Guidance. That guidance makes it clear that, if

  20. Transuranic contaminated waste form characterization and data base

    International Nuclear Information System (INIS)

    This report outlines the sources, quantities, characteristics and treatment of transuranic wastes in the United States. This document serves as part of the data base necessary to complete preparation and initiate implementation of transuranic wastes, waste forms, waste container and packaging standards and criteria suitable for inclusion in the present NRC waste management program. No attempt is made to evaluate or analyze the suitability of one technology over another. Indeed, by the nature of this report, there is little critical evaluation or analysis of technologies because such analysis is only appropriate when evaluating a particular application or transuranic waste streams. Due to fiscal restriction, the data base is developed from a myriad of technical sources and does not necessarily contain operating experience and the current status of all technologies. Such an effort was beyond the scope of this report

  1. Transuranic contaminated waste form characterization and data base

    Energy Technology Data Exchange (ETDEWEB)

    McArthur, W.C.; Kniazewycz, B.G.

    1980-07-01

    This report outlines the sources, quantities, characteristics and treatment of transuranic wastes in the United States. This document serves as part of the data base necessary to complete preparation and initiate implementation of transuranic wastes, waste forms, waste container and packaging standards and criteria suitable for inclusion in the present NRC waste management program. No attempt is made to evaluate or analyze the suitability of one technology over another. Indeed, by the nature of this report, there is little critical evaluation or analysis of technologies because such analysis is only appropriate when evaluating a particular application or transuranic waste streams. Due to fiscal restriction, the data base is developed from a myriad of technical sources and does not necessarily contain operating experience and the current status of all technologies. Such an effort was beyond the scope of this report.

  2. Structural analysis of the TRansUranic PACkage Transporter (TRUPACT)

    International Nuclear Information System (INIS)

    The TRansUranic PACkage Transporter (TRUPACT) is a Type B container under development at the Transportation Technology Center, Sandia National Laboratory, for use in the transportation of contact-handled transuranic waste. This report describes the numerical analyses of the container's response to end-on, side-on, and center of gravity over corner impacts on an unyielding surface following a 9 m free fall. The results of the analyses are compared to available experimental data. In general, the analytical predictions and experimental comparisons confirm the validity of the TRUPACT design concept

  3. Contact-handled transuranic transportation system structural analysis

    International Nuclear Information System (INIS)

    The Transuranic Package Transporter (TRUPACT) is a Type B overpack being developed for contact-handled transuranic waste. End-on, side-on, and corner impacts of the loaded TRUPACT due to a 9 m drop onto an unyielding surface have been analyzed. In each case the analyses progressed from simplified hand approaches to successively more complex finite element calculations. The first analysis of each series represents the hand calculations which were carried out to obtain initial thicknesses of foam. The remaining analyses were performed using the dynamic and nonlinear analysis capabilities of ADINA, a structural analysis finite element computer program

  4. EVALUATION OF ALTERNATIVE STRONIUM AND TRANSURANIC SEPARATION PROCESSES

    Energy Technology Data Exchange (ETDEWEB)

    SMALLEY CS

    2011-04-25

    In order to meet contract requirements on the concentrations of strontium-90 and transuranic isotopes in the immobilized low-activity waste, strontium-90 and transuranics must be removed from the supernate of tanks 241-AN-102 and 241-AN-107. The process currently proposed for this application is an in-tank precipitation process using strontium nitrate and sodium permanganate. Development work on the process has not proceeded since 2005. The purpose of the evaluation is to identify whether any promising alternative processes have been developed since this issue was last examined, evaluate the alternatives and the baseline process, and recommend which process should be carried forward.

  5. Evaluation Of Alternative Stronium And Transuranic Separation Processes

    International Nuclear Information System (INIS)

    In order to meet contract requirements on the concentrations of strontium-90 and transuranic isotopes in the immobilized low-activity waste, strontium-90 and transuranics must be removed from the supernate of tanks 241-AN-102 and 241-AN-107. The process currently proposed for this application is an in-tank precipitation process using strontium nitrate and sodium permanganate. Development work on the process has not proceeded since 2005. The purpose of the evaluation is to identify whether any promising alternative processes have been developed since this issue was last examined, evaluate the alternatives and the baseline process, and recommend which process should be carried forward.

  6. Mobile loading transuranic waste at small quantity sites in the Department of Energy complex-10523

    Energy Technology Data Exchange (ETDEWEB)

    Carter, Mitch [Los Alamos National Laboratory; Howard, Bryan [Los Alamos National Laboratory; Weyerman, Wade [Los Alamos National Laboratory; Mctaggart, Jerri [Los Alamos National Laboratory

    2009-01-01

    Los Alamos National Laboratory, Carlsbad Office (LANL-CO), operates mobile loading operations for all of the large and small quantity transuranic (TRU) waste sites in the Department of Energy (DOE) complex. The mobile loading team performs loading and unloading evolutions for both contact handled (CH) and remote handled (RH) waste. For small quantity sites, many of which have yet to remove their TRU waste, the mobile loading team will load shipments that will ship to Idaho National Laboratory, a centralization site, or ship directly to the Waste Isolation Pilot Plant (WIPP). For example, Argonne National Laboratory and General Electric Vallecitos Nuclear Center have certified programs for RH waste so they will ship their RH waste directly to WIPP. Many of the other sites will ship their waste to Idaho for characterization and certification. The Mobile Loading Units (MLU) contain all of the necessary equipment needed to load CH and RH waste into the appropriate shipping vessels. Sites are required to provide additional equipment, such as cranes, fork trucks, and office space. The sites are also required to provide personnel to assist in the shipping operations. Each site requires a site visit from the mobile loading team to ensure that all of the necessary site equipment, site requirements and space for shipping can be provided. The mobile loading team works diligently with site representatives to ensure that all safety and regulatory requirements are met. Once the waste is ready and shipping needs are met, the mobile loading team can be scheduled to ship the waste. The CH MLU is designed to support TRUPACT-II and HalfPACT loading activities wherever needed within the DOE complex. The team that performs the mobile loading operation has obtained national certification under DOE for TRUPACT-II and HalfPACT loading and shipment certification. The RH MLU is designed to support removable lid canister (RLC) and RH-72B cask loading activities wherever needed within the DOE

  7. Utilization of borosilicate glass for transuranic waste immobilization

    International Nuclear Information System (INIS)

    Incinerated transuranic waste and other low-level residues have been successfully vitrified by mixing with boric acid and sodium carbonate and heating to 10500C in a bench-scale continuous melter. The resulting borosilicate glass demonstrates excellent mechanical durability and chemical stability

  8. Management feature of transuranic for HTGR and LWR

    International Nuclear Information System (INIS)

    Long-lived actinides from spent fuels can cause potential long-term environ- mental hazards. The generation and incineration of transuranic in different closed fuel cycles were studied. U and Pu were recycled from spent fuel in the 250 MW high-temperature gas-cooled reactor-pebble-bed-module (HTR-PM) U-Pu fuelled core, and then PuO2 and MOX fuel elements were designed based on this recycled U and Pu. These fuel elements were used to build up a new PuO2 or MOX fuelled core with the same geometry of the original reactor. Characteristics of transuranic incineration with HTGR open and closed fuel cycles were studied with VSOP code, and the corresponding results from the light water reactor were compared and analyzed. The transuranic generation with HTGR open fuel cycle is almost half of the corresponding result of the light water reactor. Thus, HTGR closed fuel cycles can effectively burn transuranic. (authors)

  9. Developing an institutional strategy for transporting defense transuranic waste materials

    International Nuclear Information System (INIS)

    In late 1988, the US Department of Energy (DOE) expects to begin emplacing transuranic waste materials in the Waste Isolation Pilot Plant (WIPP), an R and D facility to demonstrate the safe disposal of radioactive wastes resulting from defense program activities. Transuranic wastes are production-related materials, e.g., clothes, rags, tools, and similar items. These materials are contaminated with alpha-emitting transuranium radionuclides with half-lives of > 20 yr and concentrations > 100 nCi/g. Much of the institutional groundwork has been done with local communities and the State of New Mexico on the siting and construction of the facility. A key to the success of the emplacement demonstration, however, will be a qualified transportation system together with institutional acceptance of the proposed shipments. The DOE's Defense Transuranic Waste Program, and its contractors, has lead responsibility for achieving this goal. The Joint Integration Office (JIO) of the DOE, located in Albuquerque, New Mexico, is taking the lead in implementing an integrated strategy for assessing nationwide institutional concerns over transportation of defense transuranic wastes and in developing ways to resolve or mitigate these concerns. Parallel prototype programs are under way to introduce both the new packaging systems and the institutional strategy to interested publics and organizations

  10. Dialysis technicians' perception of certification.

    Science.gov (United States)

    Williams, Helen F; Garbin, Margery

    2015-03-01

    The Nephrology Nursing Certification Commission initiated this research project to study the viewpoint of dialysis technicians regarding the value of certification. A national convenience sample was obtained using both paper-and-pencil and online forms of the survey instrument. Demographic characteristics were obtained concerning age, race, ethnicity, education, and future employment planning. Technicians' primary work settings, the roles they fill, and the types of certification they hold are described. Incentives offered by employers are considered to explore how they contribute to job satisfaction. Understanding the perceptions of technicians regarding the benefits of certification and the limitations of workplace incentives should enable employers to improve their recruitment and retention programs. Information obtained may offer a baseline for future observations of the characteristics of these significant and essential contributors to the nephrology workforce. PMID:26480642

  11. 40 CFR 68.185 - Certification.

    Science.gov (United States)

    2010-07-01

    ... 40 Protection of Environment 15 2010-07-01 2010-07-01 false Certification. 68.185 Section 68.185 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) AIR PROGRAMS (CONTINUED) CHEMICAL ACCIDENT PREVENTION PROVISIONS Risk Management Plan § 68.185 Certification. (a) For Program 1...

  12. Certification/enforcement analysis

    Energy Technology Data Exchange (ETDEWEB)

    None

    1980-06-01

    Industry compliance with minimum energy efficiency standards will be assured through a two-part program approach of certification and enforcement activities. The technical support document (TSD) presents the analyses upon which the proposed rule for assuring that consumer product comply with applicable energy efficiency standards is based. Much of the TSD is based upon support provided DOE by Vitro Laboratories. The OAO Corporation provided additional support in the development of the sampling plan incorporated in the proposed rule. Vitro's recommended approach to appliance certification and enforcement, developed after consideration of various program options, benefits, and impacts, establishes the C/E program framework, general criteria, and procedures for assuring a specified level of energy efficiency performance of covered consumer products. The results of the OAO analysis are given in Volume II of the TSD.

  13. DB2 9 Fundamentals Certification Study Guide

    CERN Document Server

    Sanders, Roger E

    2007-01-01

    Starting with the certification process itself and ending with the concept of isolation levels and locking, this guide covers everything needed to know to pass the DB2 9 Fundamentals Certification Exam (Exam 730). The prerequisite for all intermediate and follow-on DB2 certifications, XML usage, basic table creation, a rich set of sample questions, and detailed answers are all included, forming the foundation for understanding the newest version of IBM's flagship database product. Regardless of what future certification path the reader is planning on pursuing, this study guide will chart a cou

  14. Progress and Lessons Learned in Transuranic Waste Disposition at The Department of Energy's Advanced Mixed Waste Treatment Project

    Energy Technology Data Exchange (ETDEWEB)

    J.D. Mousseau; S.C. Raish; F.M. Russo

    2006-05-18

    This paper provides an overview of the Department of Energy's (DOE) Advanced Mixed Waste Treatment Project (AMWTP) located at the Idaho National Laboratory (INL) and operated by Bechtel BWXT Idaho, LLC(BBWI) It describes the results to date in meeting the 6,000-cubic-meter Idaho Settlement Agreement milestone that was due December 31, 2005. The paper further describes lessons that have been learned from the project in the area of transuranic (TRU) waste processing and waste certification. Information contained within this paper would be beneficial to others who manage TRU waste for disposal at the Waste Isolation Pilot Plant (WIPP).

  15. Environmental aspects of the transuranics: a selected, annotated bibliography

    Energy Technology Data Exchange (ETDEWEB)

    Fore, C.S.; Martin, F.M.; Faust, R.A. (comp.)

    1976-07-01

    This bibliography of 500 references is compiled from the Data Base on the Environmental Aspects of the Transuranics built to provide information support to the Nevada Applied Ecology Group (NAEG) of ERDA`s Nevada Operations Office. The general scope is environmental aspects of uranium and the transuranic elements, with emphasis on plutonium. Laboratory and field studies dealing with the effects of plutonium-239 on animals are highlighted in this bibliography. Supporting information on ecology of the Nevada Test Site and reviews on the effects of other radionuclides upon man and his environment has been included at the request of the NAEG. The references are arranged by subject category with first authors appearing alphabetically in each category. Indexes are given for author, geographic location, keywords, taxons, permuted title and publication description.

  16. Effects of transuranics on pulmonary lymph nodes of rodents

    International Nuclear Information System (INIS)

    Pulmonary lymph nodes have been suggested as the ''critical'' tissue for insoluble, inhaled transuranic compounds owing to the high concentration of transuranics in these lymph nodes. About 800 rats were given from 0.2 to 3600 nCi of 238PuO2 or 239PuO2 by inhalation, intratracheal instillation, intrapleural injection, or intraperitoneal injection. From about 1 to 10 percent of deposited plutonium was translocated to pulmonary lymph nodes, the amount depending on the time after deposition and the route of administration; 238PuO2 was cleared from pulmonary lymph nodes faster than 239PuO2 owing to the greater in vivo solubility of 238PuO2. No primary tumors of pulmonary lymph nodes were observed, indicating that this tissue was not the critical tissue for carcinogenic induction

  17. Environmental aspects of the transuranics: a selected, annotated bibliography

    International Nuclear Information System (INIS)

    This eighth published bibliography of 427 references is compiled from the Nevada Applied Ecology Information Center's Data Base on the Environmental Aspects of the Transuranics. The data base was built to provide information support to the Nevada Applied Ecology Group (NAEG) of ERDA's Nevada Operations Office. The general scope covers environmental aspects of uranium and the transuranic elements, with emphasis on plutonium. This bibliography highlights literature on plutonium 238 and 239 and americium in the critical organs of man and animals. Supporting information on ecology of the Nevada Test Site and reviews and summarizing literature on other radionuclides have been included at the request of the NAEG. The references are arranged by subject category with leading authors appearing alphabetically in each category. Indexes are provided for author(s), geographic location, keyword(s), taxon, title, and publication description

  18. Environmental aspects of the transuranics. A selected, annotated bibliography

    International Nuclear Information System (INIS)

    This bibliography of 470 references is from the computer file built to provide information support to the Nevada Applied Ecology Group (NAEG) of ERDA's Nevada Operations Office. The general scope is environmental aspects of uranium and the transuranic elements, with emphasis on plutonium. Biological aspects of the transuranics is highlighted in this bibliography. In addition, supporting materials involving basic ecology studies, ecology of the Nevada Test Site, and reviews on other radionuclides are entered at the request of the NAEG. Significant numeric data is shown in tabular display or is noted for reference to the original document. The references are arranged by subject category with first authors arranged alphabetically within the category. Indexes are given for author, keywords, geographic location, permuted title, taxons, and publication description. (U.S.)

  19. Environmental aspects of the transuranics: a selected, annotated bibliography

    International Nuclear Information System (INIS)

    This bibliography of 500 references is compiled from the Data Base on the Environmental Aspects of the Transuranics built to provide information support to the Nevada Applied Ecology Group (NAEG) of ERDA's Nevada Operations Office. The general scope is environmental aspects of uranium and the transuranic elements, with emphasis on plutonium. Laboratory and field studies dealing with the effects of plutonium-239 on animals are highlighted in this bibliography. Supporting information on ecology of the Nevada Test Site and reviews on the effects of other radionuclides upon man and his environment has been included at the request of the NAEG. The references are arranged by subject category with first authors appearing alphabetically in each category. Indexes are given for author, geographic location, keywords, taxons, permuted title and publication description

  20. In situ grouting of buried transuranic waste with polyacrylamide

    International Nuclear Information System (INIS)

    This project is a demonstration and evaluation of the in situ hydrologic stabilization of buried transuranic waste at a humid site via grout injection. Two small trenches, containing buried transuranic waste, were filled with 34.000 L of polyacrylamide grout. Initial field results have indicated that voids within the trenches were totally filled by the grout and that the intratrench hydraulic conductivity was reduced to below field-measurable values. No evidence of grout constituents were observed in twelve perimeter groundwater monitoring wells indicating that grout was contained completely within the two trenches. Polyacrylamide grout was selected for field demonstration over the polyacrylate grout due to its superior performance in laboratory degradation studies. Also supporting the selection of polyacrylamide was the difficulty in controlling the set time of the acrylate polymerization. Based on preliminary degradation monitoring, the polyacrylamide was estimated to have a microbiological half-life of 362 years in the test soil. 15 refs., 9 figs., 12 tabs

  1. Solid waste transuranic storage and assay facility indoor air sampling

    Energy Technology Data Exchange (ETDEWEB)

    Pingel, L.A., Westinghouse Hanford

    1996-08-20

    The purpose of the study is to collect and analyze samples of the indoor air at the Transuranic Storage and Assay Facility (TRUSAF), Westinghouse Hanford. A modified US EPA TO-14 methodology, using gas chromatography/mass spectrography, may be used for the collection and analysis of the samples. The information obtained will be used to estimate the total release of volatile organic compounds from TRUSAF to determine the need for air emmission permits.

  2. Strategic management of health risks posed by buried transuranic wastes

    International Nuclear Information System (INIS)

    A strategy is presented for reducing health risks at sites contaminated with buried transuranic (TRU) wastes by first taking measures to immobilize the contaminants until the second step, final action, becomes cost-effective and poses less risk to the remediation workers. The first step of this strategy does not preclude further action if it is warranted and is in harmony with environmental laws and regulations

  3. Acceptable knowledge document for INEEL stored transuranic waste -- Rocky Flats Plant waste. Revision 2

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-01-23

    This document and supporting documentation provide a consistent, defensible, and auditable record of acceptable knowledge for waste generated at the Rocky Flats Plant which is currently in the accessible storage inventory at the Idaho National Engineering and Environmental Laboratory. The inventory consists of transuranic (TRU) waste generated from 1972 through 1989. Regulations authorize waste generators and treatment, storage, and disposal facilities to use acceptable knowledge in appropriate circumstances to make hazardous waste determinations. Acceptable knowledge includes information relating to plant history, process operations, and waste management, in addition to waste-specific data generated prior to the effective date of the RCRA regulations. This document is organized to provide the reader a comprehensive presentation of the TRU waste inventory ranging from descriptions of the historical plant operations that generated and managed the waste to specific information about the composition of each waste group. Section 2 lists the requirements that dictate and direct TRU waste characterization and authorize the use of the acceptable knowledge approach. In addition to defining the TRU waste inventory, Section 3 summarizes the historical operations, waste management, characterization, and certification activities associated with the inventory. Sections 5.0 through 26.0 describe the waste groups in the inventory including waste generation, waste packaging, and waste characterization. This document includes an expanded discussion for each waste group of potential radionuclide contaminants, in addition to other physical properties and interferences that could potentially impact radioassay systems.

  4. Acceptable knowledge document for INEEL stored transuranic waste - Rocky Flats Plant waste. Revision 2

    International Nuclear Information System (INIS)

    This document and supporting documentation provide a consistent, defensible, and auditable record of acceptable knowledge for waste generated at the Rocky Flats Plant which is currently in the accessible storage inventory at the Idaho National Engineering and Environmental Laboratory. The inventory consists of transuranic (TRU) waste generated from 1972 through 1989. Regulations authorize waste generators and treatment, storage, and disposal facilities to use acceptable knowledge in appropriate circumstances to make hazardous waste determinations. Acceptable knowledge includes information relating to plant history, process operations, and waste management, in addition to waste-specific data generated prior to the effective date of the RCRA regulations. This document is organized to provide the reader a comprehensive presentation of the TRU waste inventory ranging from descriptions of the historical plant operations that generated and managed the waste to specific information about the composition of each waste group. Section 2 lists the requirements that dictate and direct TRU waste characterization and authorize the use of the acceptable knowledge approach. In addition to defining the TRU waste inventory, Section 3 summarizes the historical operations, waste management, characterization, and certification activities associated with the inventory. Sections 5.0 through 26.0 describe the waste groups in the inventory including waste generation, waste packaging, and waste characterization. This document includes an expanded discussion for each waste group of potential radionuclide contaminants, in addition to other physical properties and interferences that could potentially impact radioassay systems

  5. Transuranic distribution beneath a retired underground disposal facility, Hanford Site

    International Nuclear Information System (INIS)

    Past liquid waste disposal practices at the Hanford Site included the discharge of solutions containing low-level concentrations of transuranics directly to the ground via structures collectively termed cribs. A study was conducted to determine the present spatial distribution of plutonium and americium beneath the retired 216-Z-1A Crib, which contains one of the highest cumulative plutonium inventories, 57 kilograms. Sixteen shallow wells were drilled in the unsaturated sediments underlying the facility using specialized, totally contained drilling techniques. Samples from each well were analyzed to obtain profiles of both sediment type and plutonium and americium concentrations as a function of depth beneath the facility. The results of the study show that the highest concentration of plutonium (>104 nCi/g of sediment) occurs within the first 3 meters of sediment beneath the central distribution pipe. The high activity at this position is tentatively attributed to the removal of solid particles from the waste stream by sediment filtration. The distributions of plutonium and americium in the sediments are similar. Peak transuranic activity in the sediment profile is generally associated with silt lenses or with major sedimentary unit interfaces (ie, sand to gravel). The maximum vertical extent of transuranic activity found is approximately 30 meters below the bottom of the crib or approximately 25 meters above the regional water table. No contamination greater than the instrumental limit of detection of 10-5 nCi/g of sediment was found from a depth of 30 to 40 meters, the maximum depth of sampling

  6. Defense waste management plan

    International Nuclear Information System (INIS)

    Defense high-level waste (HLW) and defense transuranic (TRU) waste are in interim storage at three sites, namely: at the Savannah River Plant, in South Carolina; at the Hanford Reservation, in Washington; and at the Idaho National Engineering Laboratory, in Idaho. Defense TRU waste is also in interim storage at the Oak Ridge National Laboratory, in Tennessee; at the Los Alamos National Laboratory, in New Mexico; and at the Nevada Test Site, in Nevada. (Figure E-2). This document describes a workable approach for the permanent disposal of high-level and transuranic waste from atomic energy defense activities. The plan does not address the disposal of suspect waste which has been conservatively considered to be high-level or transuranic waste but which can be shown to be low-level waste. This material will be processed and disposed of in accordance with low-level waste practices. The primary goal of this program is to utilize or dispose of high-level and transuranic waste routinely, safely, and effectively. This goal will include the disposal of the backlog of stored defense waste. A Reference Plan for each of the sites describes the sequence of steps leading to permanent disposal. No technological breakthroughs are required to implement the reference plan. Not all final decisions concerning the activities described in this document have been made. These decisions will depend on: completion of the National Environmental Policy Act process, authorization and appropriation of funds, agreements with states as appropriate, and in some cases, the results of pilot plant experiments and operational experience. The major elements of the reference plan for permanent disposal of defense high-level and transuranic waste are summarized

  7. Implementation plan for WRAP Module 1 operational readiness review

    International Nuclear Information System (INIS)

    The Waste Receiving and Processing Module 1 (WRAP 1) will be used to receive, sample, treat, and ship contact-handled (CH) transuranic (TRU), low-level waste (LLW), and low-level mixed waste (LLMW) to storage and disposal sites both on the Hanford site and off-site. The primary mission of WRAP 1 is to characterize and certify CH waste in 55-gallon and 85-gallon drums; and its secondary function is to certify CH waste standard waste boxes (SWB) and boxes of similar size for disposal. The WRAP 1 will provide the capability for examination (including x-ray, visual, and contents sampling), limited treatment, repackaging, and certification of CH suspect-TRU waste in 55-gallon drums retrieved from storage, as well as newly generated CH LLW and CH TRU waste drums. The WRAP 1 will also provide examination (X-ray and visual only) and certification of CH LLW and CH TRU waste in small boxes. The decision to perform an Operational Readiness Review (ORR) was made in accordance with WHC-CM-5-34, Solid Waste Disposal Operations Administration, Section 1.4, Operational Readiness Activities. The ORR will ensure plant and equipment readiness, management and personnel readiness, and management programs readiness for the initial startup of the facility. This implementation plan is provided for defining the conduct of the WHC ORR

  8. In situ vitrification: application analysis for stabilization of transuranic waste

    Energy Technology Data Exchange (ETDEWEB)

    Oma, K.H.; Farnsworth, R.K.; Rusin, J.M.

    1982-09-01

    The in situ vitrification process builds upon the electric melter technology previously developed for high-level waste immobilization. In situ vitrification converts buried wastes and contaminated soil to an extremely durable glass and crystalline waste form by melting the materials, in place, using joule heating. Once the waste materials have been solidified, the high integrity waste form should not cause future ground subsidence. Environmental transport of the waste due to water or wind erosion, and plant or animal intrusion, is minimized. Environmental studies are currently being conducted to determine whether additional stabilization is required for certain in-ground transuranic waste sites. An applications analysis has been performed to identify several in situ vitrification process limitations which may exist at transuranic waste sites. Based on the process limit analysis, in situ vitrification is well suited for solidification of most in-ground transuranic wastes. The process is best suited for liquid disposal sites. A site-specific performance analysis, based on safety, health, environmental, and economic assessments, will be required to determine for which sites in situ vitrification is an acceptable disposal technique. Process economics of in situ vitrification compare favorably with other in-situ solidification processes and are an order of magnitude less than the costs for exhumation and disposal in a repository. Leachability of the vitrified product compares closely with that of Pyrex glass and is significantly better than granite, marble, or bottle glass. Total release to the environment from a vitrified waste site is estimated to be less than 10/sup -5/ parts per year. 32 figures, 30 tables.

  9. No certificate, no chocolate

    CERN Multimedia

    Computer Security Team

    2013-01-01

    Are you already ready to use “certificates” to log into CERN or to connect to the global “eduroam” wireless network? No, I am not talking about your birth certificate, medical certificates or academic certificates. I am referring to “certificates” used for authentication where you would usually use a password.   These digital certificates are a valid alternative to cumbersome passwords. Like the aforementioned personal certificates, a digital certificate is an official document that proves who you are or your qualifications. Your personal digital CERN certificate is tied to your digital identity at CERN. In that respect, a digital certificate is like a password. It is a credential that you must not share with anybody else! With your digital certificate, I can impersonate you and take over your mailbox, your web sessions and more… Digital certificates bind your digital identity to a public/private-key infrastructu...

  10. Fluidized bed incineration process design for transuranic waste

    International Nuclear Information System (INIS)

    A fluidized bed incineration facility has been installed at the Rocky Flats Plant to develop and demonstrate a process for the combustion of transuranic waste. The unit's capacity is about 82 kg/hr of combustible solid waste, which is nine times higher than the rate for the operating pilot-scale unit. The facility utilizes nonaqueous, in situ neutralization of acid gases. These gases are generated during the combustion of halogen-containing materials. The low-temperature (550 0C) operation eliminates refractory-lined equipment

  11. Gas generation from transuranic waste degradation: an interim assessment

    International Nuclear Information System (INIS)

    A review of all available, applicable data pertaining to gas generation from the degradation of transuranic waste matrix material and packaging is presented. Waste forms are representative of existing defense-related TRU wastes and include cellulosics, plastics, rubbers, concrete, process sludges, and mild steel. Degradation mechanisms studied were radiolysis, thermal, bacterial, and chemical corrosion. Gas generation rates are presented in terms of moles of gas produced per year per drum, and in G(gas) values for radiolytic degradation. Comparison of generation rates is made, as is a discussion of potential short- and long-term concerns. Techniques for reducing gas generation rates are discussed. 6 figures, 10 tables

  12. Certification for sugarcane production processes

    Energy Technology Data Exchange (ETDEWEB)

    Oliveira, Camila Ortolan F. de; Walter, Arnaldo

    2012-07-01

    This chapter concerns with the meaning of certification, sustainability of bioenergy, sustainability initiatives and certification schemes, certification tendencies in Brazil, and the challenge for fulfilling criteria.

  13. Input of transuranic elements through rivers into the Mediterranean Sea

    International Nuclear Information System (INIS)

    Measurements of 137Cs, 238Pu, sup(239+240)Pu and 241Am were carried out on river water as well as its suspended matter collected seasonally in 1977 from two Mediterranean rivers, the Var and the Rhone. The results show that although the concentrations of the soluble fractions of these radionuclides are higher in the Rhone than in the Var, even the elevated concentrations of soluble 137Cs (approximately 40 fCi.ltr-1) and sup(239+240)Pu (approximately 0.1 fCi.ltr-1) in the Rhone are much lower than the average concentrations of these nuclides in Mediterranean surface waters. On the other hand, the concentrations of the nuclides measured in suspended matter are roughly an order of magnitude higher in the Rhone than in the Var. Based on the results of measurements on the two rivers, and assuming that the annual average concentrations of the radionuclides in the Var and the Rhone respectively represent those in radiologically uncontaminated and contaminated Mediterranean rivers, the total inputs of 137Cs, 238Pu, sup(239+240)Pu and 241Am through rivers into the Mediterranean Sea have been estimated. Comparison of these estimated values with the inputs of fallout radionuclides by rain indicates that although local accumulation of transuranic nuclides may be observed on sediments taken from some limited estuarine areas, the geochemical behaviour of transuranic elements in the Mediterranean, as a whole, is exclusively governed today by the fallout input of these elements. (author)

  14. Data base of the environmental aspects of the transuranics

    International Nuclear Information System (INIS)

    Indexed and abstracted references to the environmental aspects of the transuranium elements are entered into and are retrievable from a dynamic, computerized information file (or data base) that is easily modified to reflect changing research needs. The information is distilled from the documents with the specific needs of the researcher in mind, such as numeric results, new methods, or instrumentation. The major areas of evaluation are: biological and medical studies on the effects of the transuranics, particularly as these elements relate to health considerations in man; biological and ecological availability, turnover, and food chain dynamics; analysis of environmental materials; environmental transport mechanisms, including resuspension; waste disposal as related to environmental concerns; monitoring; and regulations and standards for environmental levels. Annotated references are indexed to allow easy access for retrieving references to documents of interest to the user. The goal is to furnish the users all the references related to their specific query and few that are unrelated. This is done by liberal use of subject categories and keyterms. The studies on man and animals are divided into the subject categories of medical and biological aspects. Those aspects that are considered important when the document is analyzed are tabulated. These data are sought for in the article, included in the abstracts, and indexed with keyterms. This checklist is one of the ways the Data Base on the Environmental Aspects of the Transuranics strives to give users a reference to every paper in their subject area

  15. Transportation system (TRUPACT) for contact-handled transuranic wastes

    International Nuclear Information System (INIS)

    Contact-handled transuranic defense waste is being, and will continue to be, moved between a number of locations in the United States. The DOE is sponsoring development of safe, efficient, licensable, and cost-effective transportation systems to handle this waste. The systems being developed have been named TRUPACT which stands for TRansUranic PACkage Transporter. The system will be compatible with Type A packagings used by waste generators, interim storage facilities, and repositories. TRUPACT is required to be a Type B packaging since larger than Type A quantities of some radionuclides (particularly plutonium) may be involved in the collection of Type A packagings. TRUPACT must provide structural and thermal protection to the waste in hypothetical accident environments specified in DOT regulations 49CFR173 and NRC regulations 10CFR71. Preliminary design of the systems has been completed and final design for a truck system is underway. The status of the development program is reviewed in this paper and the reference design is described. Tests that have been conducted are discussed and long-term program objectives are reviewed

  16. Assessment of gas flammability in transuranic waste container

    International Nuclear Information System (INIS)

    The Safety Analysis Report for the TRUPACT-II Shipping Package [Transuranic Package Transporter-II (TRUPACT-II) SARP] set limits for gas generation rates, wattage limits, and flammable volatile organic compound (VOC) concentrations in transuranic (TRU) waste containers that would be shipped to the Waste Isolation Pilot Plant (WIPP). Based on existing headspace gas data for drums stored at the Idaho National Engineering Laboratory (INEL) and the Rocky Flats Environmental Technology Site (RFETS), over 30 percent of the contact-handled TRU waste drums contain flammable VOC concentrations greater than the limit. Additional requirements may be imposed for emplacement of waste in the WIPP facility. The conditional no-migration determination (NMD) for the test phase of the facility required that flame tests be performed if significant levels of flammable VOCs were present in TRU waste containers. This paper describes an approach for investigating the potential flammability of TRU waste drums, which would increase the allowable concentrations of flammable VOCS. A flammability assessment methodology is presented that will allow more drums to be shipped to WIPP without treatment or repackaging and reduce the need for flame testing on drums. The approach includes experimental work to determine mixture lower explosive limits (MLEL) for the types of gas mixtures observed in TRU waste, a model for predicting the MLEL for mixtures of VOCS, hydrogen, and methane, and revised screening limits for total flammable VOCs concentrations and concentrations of hydrogen and methane using existing drum headspace gas data and the model predictions

  17. Decontamination of transuranic contaminated metals by melt refining

    International Nuclear Information System (INIS)

    Melt refining of transuranic contaminated metals is a possible decontamination process with the potential advantages of producing metal for reuse and of simplifying chemical analyses. By routinely achieving the 10 nCi/g( about0.1ppm) level by melt refining, scrap metal can be removed from the transuranic waste category. (To demonstrate the effectiveness of this melt refining process, mild steel, stainless steel, nickel, and copper were contaminated with 500 ppm (μg/g) PuO2 and melted with various fluxes. The solidified slags and metals were analyzed for their plutonium contents, and corresponding partition ratios for plutonium were calculated. Some metals were double refined in order to study the effect of secondary slag treatment. The initial weight of the slags was also varied to investigate the effect of slag weight on the degree of plutonium removal. In general, all four metals could be decontaminated below 1 ppm (μg/g) Pu ( about100 nCi/g) by a single slag treatment. Doubling the slag weight did not improve decontamination significantly; however, double slag treatment using 5 wt.% slag did decontaminate the metals to below 0.1 ppm (μg/g) Pu (10 nCi/g).)

  18. W-026, transuranic waste (TRU) glovebox acceptance test report

    Energy Technology Data Exchange (ETDEWEB)

    Leist, K.J.

    1998-03-11

    On July 18, 1997, the Transuranic (TRU) glovebox was tested using glovebox acceptance test procedure 13021A-86. The primary focus of the glovebox acceptance test was to examine control system interlocks, display menus, alarms, and operator messages. Limited mechanical testing involving the drum ports, hoists, drum lifter, compacted drum lifter, drum tipper, transfer car, conveyors, sorting table, lidder/delidder device and the TRU empty drum compactor were also conducted. As of February 25, 1998, 10 of the 102 test exceptions that affect the TRU glovebox remain open. These items will be tracked and closed via the WRAP Master Test Exception Database. As part of Test Exception resolution/closure the responsible individual closing the Test Exception performs a retest of the affected item(s) to ensure the identified deficiency is corrected, and, or to test items not previously available to support testing. Test exceptions are provided as appendices to this report.

  19. Identification of potential transuranic waste tanks at the Hanford Site

    Energy Technology Data Exchange (ETDEWEB)

    Colburn, R.P.

    1995-05-05

    The purpose of this document is to identify potential transuranic (TRU) material among the Hanford Site tank wastes for possible disposal at the Waste Isolation Pilot Plant (WIPP) as an alternative to disposal in the high-level waste (HLW) repository. Identification of such material is the initial task in a trade study suggested in WHC-EP-0786, Tank Waste Remediation System Decisions and Risk Assessment (Johnson 1994). The scope of this document is limited to the identification of those tanks that might be segregated from the HLW for disposal as TRU, and the bases for that selection. It is assumed that the tank waste will be washed to remove soluble inert material for disposal as low-level waste (LLW), and the washed residual solids will be vitrified for disposal. The actual recommendation of a disposal strategy for these materials will require a detailed cost/benefit analysis and is beyond the scope of this document.

  20. W-026, transuranic waste (TRU) glovebox acceptance test report

    International Nuclear Information System (INIS)

    On July 18, 1997, the Transuranic (TRU) glovebox was tested using glovebox acceptance test procedure 13021A-86. The primary focus of the glovebox acceptance test was to examine control system interlocks, display menus, alarms, and operator messages. Limited mechanical testing involving the drum ports, hoists, drum lifter, compacted drum lifter, drum tipper, transfer car, conveyors, sorting table, lidder/delidder device and the TRU empty drum compactor were also conducted. As of February 25, 1998, 10 of the 102 test exceptions that affect the TRU glovebox remain open. These items will be tracked and closed via the WRAP Master Test Exception Database. As part of Test Exception resolution/closure the responsible individual closing the Test Exception performs a retest of the affected item(s) to ensure the identified deficiency is corrected, and, or to test items not previously available to support testing. Test exceptions are provided as appendices to this report

  1. Identification of potential transuranic waste tanks at the Hanford Site

    International Nuclear Information System (INIS)

    The purpose of this document is to identify potential transuranic (TRU) material among the Hanford Site tank wastes for possible disposal at the Waste Isolation Pilot Plant (WIPP) as an alternative to disposal in the high-level waste (HLW) repository. Identification of such material is the initial task in a trade study suggested in WHC-EP-0786, Tank Waste Remediation System Decisions and Risk Assessment (Johnson 1994). The scope of this document is limited to the identification of those tanks that might be segregated from the HLW for disposal as TRU, and the bases for that selection. It is assumed that the tank waste will be washed to remove soluble inert material for disposal as low-level waste (LLW), and the washed residual solids will be vitrified for disposal. The actual recommendation of a disposal strategy for these materials will require a detailed cost/benefit analysis and is beyond the scope of this document

  2. Physical Properties of Hanford Transuranic Waste. Final Report

    International Nuclear Information System (INIS)

    The research described herein was undertaken to provide needed physical property descriptions of the Hanford transuranic tank sludges under conditions that might exist during retrieval, treatment, packaging and transportation for disposal. The work addressed the development of a fundamental understanding of the types of systems represented by these sludge suspensions through correlation of the macroscopic rheological properties with particle interactions occurring at the colloidal scale in the various liquid media. The results of the work have advanced existing understanding of the sedimentation and aggregation properties of complex colloidal suspensions. Bench scale models were investigated with respect to their structural, colloidal and rheological properties that should be useful for the development and optimization of techniques to process the wastes at various DOE sites.

  3. Development of consistent hazard controls for DOE transuranic waste operations

    International Nuclear Information System (INIS)

    This paper describes the results of a re-engineering initiative undertaken with the Department of Energy's (DOE) Office of Environmental Management (EM) in order to standardize hazard analysis assumptions and methods and resulting safety controls applied to multiple transuranic (TRU) waste operations located across the United States. A wide range of safety controls are historically applied to transuranic waste operations, in spite of the fact that these operations have similar operational characteristics and hazard/accident potential. The re-engineering effort supported the development of a DOE technical standard with specific safety controls designated for accidents postulated during waste container retrieval, staging/storage, venting, onsite movements, and characterization activities. Controls cover preventive and mitigative measures; include both hardware and specific administrative controls; and provide protection to the facility worker, onsite co-located workers and the general public located outside of facility boundaries. The Standard development involved participation from all major DOE sites conducting TRU waste operations. Both safety analysts and operations personnel contributed to the re-engineering effort. Acknowledgment is given in particular to the following individuals who formed a core working group: Brenda Hawks, (DOE Oak Ridge Office), Patrice McEahern (CWI-Idaho), Jofu Mishima (Consultant), Louis Restrepo (Omicron), Jay Mullis (DOE-ORO), Mike Hitchler (WSMS), John Menna (WSMS), Jackie East (WSMS), Terry Foppe (CTAC), Carla Mewhinney (WIPP-SNL), Stephie Jennings (WIPP-LANL), Michael Mikolanis (DOESRS), Kraig Wendt (BBWI-Idaho), Lee Roberts (Fluor Hanford), and Jim Blankenhorn (WSRC). Additional acknowledgment is given to Dae Chung (EM) and Ines Triay (EM) for leadership and management of the re-engineering effort. (authors)

  4. Planning a Regional Energy System in Association with the Creation of Energy Performance Certificates (EPCs, Statistical Analysis and Energy Efficiency Measures: An Italian Case Study

    Directory of Open Access Journals (Sweden)

    Kristian Fabbri

    2013-08-01

    Full Text Available Directive 2002/91/EC EPBD introduced the Energy Performance Certificate (EPC as a tool to guide the real estate market in the creation of products (buildings with improved energy performances. The EPC’s information could be useful in the determination of relevant policies and also in studying the characteristics of the building resources of the territory. This paper presents a case study related to the EPC Database of the Emilia-Romagna Region in mid-northern Italy. The case study shows a way of elaborating the EPC information in statistical analysis evaluations with aggregate data, in order to measure a territory and then direct energy policies toward energy efficiency. A statistical approach was used to define a characteristic statistical indicator index of the EPC database, and compare the energy index with the bottom-up and top-down methods, in order to identify some energy policy scenarios.

  5. Building Intercultural Competence through Intercultural Competency Certification of Undergraduate Students

    Science.gov (United States)

    Janeiro, Maria G. Fabregas; Fabre, Ricardo Lopez; Nuno de la Parra, Jose Pablo

    2014-01-01

    The Intercultural Competency Certificate (CCI in Spanish) designed for the Universidad Popular Autonoma del Estado de Puebla (UPAEP University) is a theory based comprehensive plan to develop undergraduate students' intercultural competence. This Certificate is based in the Developmental Model of Intercultural Sensitivity (DMIS) developed by…

  6. In situ quantitative determination of transuranic elements in areas of high-level gamma radiation

    Energy Technology Data Exchange (ETDEWEB)

    Brodzinski, R.L.; Wogman, N.A.

    1978-01-01

    A technique is described for passive neutron monitoring of transuranic elements. The method provides quantitative determinations of transuranic element concentrations in a variety of field situations where no other measurement method is possible. The technique can measure concentrations of transuranic oxides as low as 8 nCi/cm/sup 3/ and is capable of operating in gamma radiation fields up to megarads per hour. Information on chemical and isotopic composition can also be obtained from the data. Several successful applications of the technique are discussed.

  7. Risk perception on management of nuclear high-level and transuranic waste storage

    International Nuclear Information System (INIS)

    The Department of Energy's program for disposing of nuclear High-Level Waste (HLW) and transuranic (TRU) waste has been impeded by overwhelming political opposition fueled by public perceptions of actual risk. Analysis of these perceptions shows them to be deeply rooted in images of fear and dread that have been present since the discovery of radioactivity. The development and use of nuclear weapons linked these images to reality and the mishandling of radioactive waste from the nations military weapons facilities has contributed toward creating a state of distrust that cannot be erased quickly or easily. In addition, the analysis indicates that even the highly educated technical community is not well informed on the latest technology involved with nuclear HLW and TRU waste disposal. It is not surprising then, that the general public feels uncomfortable with DOE's management plans for with nuclear HLW and TRU waste disposal. Postponing the permanent geologic repository and use of Monitored Retrievable Storage (MRS) would provide the time necessary for difficult social and political issues to be resolved. It would also allow time for the public to become better educated if DOE chooses to become proactive

  8. Risk perception on management of nuclear high-level and transuranic waste storage

    Energy Technology Data Exchange (ETDEWEB)

    Dees, L.A.

    1994-08-15

    The Department of Energy`s program for disposing of nuclear High-Level Waste (HLW) and transuranic (TRU) waste has been impeded by overwhelming political opposition fueled by public perceptions of actual risk. Analysis of these perceptions shows them to be deeply rooted in images of fear and dread that have been present since the discovery of radioactivity. The development and use of nuclear weapons linked these images to reality and the mishandling of radioactive waste from the nations military weapons facilities has contributed toward creating a state of distrust that cannot be erased quickly or easily. In addition, the analysis indicates that even the highly educated technical community is not well informed on the latest technology involved with nuclear HLW and TRU waste disposal. It is not surprising then, that the general public feels uncomfortable with DOE`s management plans for with nuclear HLW and TRU waste disposal. Postponing the permanent geologic repository and use of Monitored Retrievable Storage (MRS) would provide the time necessary for difficult social and political issues to be resolved. It would also allow time for the public to become better educated if DOE chooses to become proactive.

  9. Molten salt extraction of transuranic and reactive fission products from used uranium oxide fuel

    Science.gov (United States)

    Herrmann, Steven Douglas

    2014-05-27

    Used uranium oxide fuel is detoxified by extracting transuranic and reactive fission products into molten salt. By contacting declad and crushed used uranium oxide fuel with a molten halide salt containing a minor fraction of the respective uranium trihalide, transuranic and reactive fission products partition from the fuel to the molten salt phase, while uranium oxide and non-reactive, or noble metal, fission products remain in an insoluble solid phase. The salt is then separated from the fuel via draining and distillation. By this method, the bulk of the decay heat, fission poisoning capacity, and radiotoxicity are removed from the used fuel. The remaining radioactivity from the noble metal fission products in the detoxified fuel is primarily limited to soft beta emitters. The extracted transuranic and reactive fission products are amenable to existing technologies for group uranium/transuranic product recovery and fission product immobilization in engineered waste forms.

  10. Removal of plutonium and other transuranic elements from man

    International Nuclear Information System (INIS)

    As the use of plutonium(Pu239)and the other transuranic elements in peaceful pursuits is added to their use for defence purposes, the chance of deposition within the body is increasing. Therapy for such conditions become increasingly important. Usually, Pu239 gains entry to the body by inhalation or through wounds. When the plutonium compound, which is inhaled is poorly soluble in the lung, it is difficult to evaluate treatment by assay of the urine and faeces. Likewise, when plutonium is deposited in a wound the absorption rate varies greatly depending upon solubility, physical state and other factors and the inference drawn from excretion in urine and faeces may be in considerable error since data relating excretion to body deposit is based on intravenous injection of the material. This almost never occurs in practice. Several employees who have had, for several years, depositions obtained accidentally by inhalation, varying from 1/2 to 10 times the maximum permissible limit (radiation guide) have been treated with the tri-sodium calcium salt of diethylenetriaminepentaacetic acid (DTPA) and the present paper summarizes the results of such treatment in terms of rate of excretion of Pu239 in urine and faeces with and without treatment. A number of employees who have had depositions of plutonium or its compounds in flesh have also been treated at the Hanford Atomic Products Operation by surgical excision. This has sometimes been followed by intravenous DTPA therapy to increase elimination of systemically deposited Pu239. Our policy is to excise any measurable quantity of Pu239 if this may be accomplished with little hazard to the patient. The NCRP has not set a permissible limit or guide for Pu239 deposition in a wound. Basis for a guide figure is lacking at present and needs clarification by considerable study in animals and biopsy studies, where possible, in man. The assumption that the permissible wound deposition for Pu239 should be the same as that for the

  11. Promises and Challenges of Thorium Implementation for Transuranic Transmutation - 13550

    Energy Technology Data Exchange (ETDEWEB)

    Franceschini, F.; Lahoda, E.; Wenner, M. [Westinghouse Electric Company LLC, Cranberry Township, PA (United States); Lindley, B. [University of Cambridge (United Kingdom); Fiorina, C. [Polytechnic of Milan (Italy); Phillips, C. [Energy Solutions, Richland, WA (United States)

    2013-07-01

    This paper focuses on the challenges of implementing a thorium fuel cycle for recycle and transmutation of long-lived actinide components from used nuclear fuel. A multi-stage reactor system is proposed; the first stage consists of current UO{sub 2} once-through LWRs supplying transuranic isotopes that are continuously recycled and burned in second stage reactors in either a uranium (U) or thorium (Th) carrier. The second stage reactors considered for the analysis are Reduced Moderation Pressurized Water Reactors (RMPWRs), reconfigured from current PWR core designs, and Fast Reactors (FRs) with a burner core design. While both RMPWRs and FRs can in principle be employed, each reactor and associated technology has pros and cons. FRs have unmatched flexibility and transmutation efficiency. RMPWRs have higher fuel manufacturing and reprocessing requirements, but may represent a cheaper solution and the opportunity for a shorter time to licensing and deployment. All options require substantial developments in manufacturing, due to the high radiation field, and reprocessing, due to the very high actinide recovery ratio to elicit the claimed radiotoxicity reduction. Th reduces the number of transmutation reactors, and is required to enable a viable RMPWR design, but presents additional challenges on manufacturing and reprocessing. The tradeoff between the various options does not make the choice obvious. Moreover, without an overarching supporting policy in place, the costly and challenging technologies required inherently discourage industrialization of any transmutation scheme, regardless of the adoption of U or Th. (authors)

  12. Degradation of transuranic-contaminated wastes under geological isolation conditions

    International Nuclear Information System (INIS)

    Results of extensive experimental studies on the degradation of existing defense transuranic-contaminated (TRU) wastes are presented. Environmental conditions for waste degradation are representative of deep geological isolation of TRU wastes in a bedded-salt repository, as anticipated for the proposed Waste Isolation Pilot Plant in southeastern New Mexico. TRU-contaminated waste matrices investigated include cellulosics, plastics, rubbers, mixed organic composite, bitumen, a developmental concrete-TRU ash matrix, mild steel, and inorganic process sludges. Degradation mechanisms studied were alpha radiolysis, microbial action, thermal decomposition and dewatering, and chemical corrosion. Experimental variables are waste composition, alpha-contamination level, temperature, pressure, time, water or brine content, aerobic or anaerobic conditions, etc. Results of waste degradation are presented in terms of gas generation rates, gas compositions, container corrosion rates, effectiveness of anti-corrosion coatings, microbial formation and degradation of chelating agents. Based on experimental results, the relative quantities of gas generated by individual mechanisms acting on the organic matrix wastes can be ranked as follows: (1) microbial action, (2) thermal decomposition (at 400C and higher), (3) alpha radiolysis, and (4) corrosion. Corrosion of metallic waste canisters and realistic bedded-salt repository conditions was determined not to have a significant effect on potential waste retrievability. The technical data provided in these studies are used in assessments to determine whether existing forms of TRU wastes are acceptable for safe geological isolation. (author)

  13. Approach for systematic evaluation of transuranic waste management alternatives

    International Nuclear Information System (INIS)

    This paper describes an approach for systematic evaluation of management alternatives that are being considered for the treatment, storage, and disposal of transuranic waste (TRUW) at U.S. Department of Energy sites. The approach, which is currently under development, would apply WASTE-MGMT, a database application model developed at Argonne National Laboratory, to estimate projected environmental releases and would evaluate impact measures such as health risk and costs associated with each of the waste management alternatives. The customized application would combine site-specific TRUW inventory and characterization data with treatment and transportation parameters to estimate the quantities and characteristics of the wastes to be treated, emissions of hazardous substances from the treatment facilities, and the quantities and characteristics of the wastes to be shipped between sites. These data would then be used to estimate for several TRUW management scenarios the costs and health risks of constructing and operating the required treatment facilities and of transporting TRUW for treatment and final disposal. Treatment, storage, and disposal of TRUW at DOE sites is composed of many variables and options at each stage. The approach described in this paper would provide for efficient consideration of all of these facets when evaluating potentially feasible TRUW management alternatives. By expanding existing databases, this model could eventually be adapted to accommodate the introduction of new treatment technologies, updated TRUW characterization data, and/or revised waste acceptance criteria

  14. Assessment of LANL transuranic mixed waste management documentation

    International Nuclear Information System (INIS)

    The objective of this report is to present findings from the evaluation of the Los Alamos National Laboratory (LANL) TRU Mixed Waste Acceptance Criteria to determine its compliance with applicable DOE requirements. The driving requirements for s TRU Mixed Waste Acceptance Criteria are essentially those contained in the ''TRU Waste Acceptance Criteria for the Waste Isolation Pilot Plant'' or WIPP WAC (DOE Report WIPP-DOE-069), 40 CFR 261-270, and DOE Order 5820.2A (Radioactive Waste Management), specifically Chapter II which is entitled ''Management of Transuranic Waste''. The primary purpose of the LANL WAC is the establishment of those criteria that must be met by generators of TRU mixed waste before such waste can be accepted by the Waste Management Group. An annotated outline of a genetic TRU mixed waste acceptance criteria document was prepared from those requirements contained in the WIPP WAC, 40 CFR 261-270, and 5820.2A, and is based solely upon those requirements

  15. Transuranics Transmutation Using Neutrons Spectrum from Spallation Reactions

    Directory of Open Access Journals (Sweden)

    Maurício Gilberti

    2015-01-01

    Full Text Available The aim is to analyse the neutron spectrum influence in a hybrid system ADS-fission inducing transuranics (TRUs transmutation. A simple model consisting of an Accelerator-Driven Subcritical (ADS system containing spallation target, moderator or coolant, and spheres of actinides, “fuel,” at different locations in the system was modelled. The simulation was performed using the MCNPX 2.6.0 particles transport code evaluating capture (n,γ and fission (n,f reactions, as well as the burnup of actinides. The goal is to examine the behaviour and influences of the hard neutron spectrum from spallation reactions in the transmutation, without the contribution or interference of multiplier subcritical medium, and compare the results with those obtained from the neutron fission spectrum. The results show that the transmutation efficiency is independent of the spallation target material used, and the neutrons spectrum from spallation does not contribute to increased rates of actinides transmutation even in the vicinity of the target.

  16. Non-Destructive Assay of Curium Contaminated Transuranic Waste Drums

    Energy Technology Data Exchange (ETDEWEB)

    Foster, L.A.

    1998-11-01

    At the Plutonium Facility at Los Alamos National Laboratory, a series of non-destructive assays were performed on five transuranic waste (TRU) drums containing non-plutonium scrap metal that was potentially contaminated with weapons grade plutonium and trace quantities of curium. Typically, waste drums containing metal matrices are assayed for plutonium content using passive neutron coincidence counting techniques. The presence of trace quantities of Cm-244 prevents this type of analysis because of the strong coincidence signal created by spontaneous fission of Cm-244. To discriminate between the plutonium and curium materials present, an active neutron measurement technique was used. A Cf shuffler designed for measurement of uranium bearing materials was calibrated for plutonium in the active mode. The waste drums were then assayed for plutonium content in the shuffler using the active-mode calibration. The curium contamination levels were estimated from the difference between the active-mode measurement in the shuffler and a passive assay in a neutron coincidence counter. Far field gamma-ray measurements were made to identify additional radioactive contaminants and to corroborate the plutonium measurement results obtained from the active-mode assay. This report describes in detail the measurement process used for characterization of these waste drums. The measurement results and the estimated uncertainty will be presented.

  17. Transuranic radioactive (TRU) waste management in the USA

    International Nuclear Information System (INIS)

    In the United States of America (USA), the US Department of Energy (DOE) is responsible for the safe management and disposal of all transuranic radioactive (TRU) waste. Based on the promising characteristics of the 225-million-year-old stable sequence of evaporitic rocks (mainly rock salt) at the Waste Isolation Pilot Plant (WIPP) site, an underground test facility was developed in the early 1980s at a depth of approximately 655 meters in the candidate host salt formation. In 1994, after more than 20 years of characterizing and evaluating the WIPP site, the DOE concluded that available data and long-term performance assessments (PAs) strongly indicated the WIPP site exhibits very suitable natural characteristics for hosting a deep geologic disposal facility (repository) for TRU waste. In April 1994, the DOE Carlsbad Area Office (CAO) presented a new strategy and an accelerated schedule targeting June 1998 for the opening of a TRU waste repository at the WIPP site. The main objectives of this strategy are to: resolve regulatory compliance and technical issues; characterize the waste; address transportation and safety issues; and involve stakeholders (interested parties) in the regulatory compliance process

  18. Sources, Speciation and Mobility of Plutonium and Other Transuranics in the Groundwater at the Savannah River Site (Sept. 2003-Sept. 2006)

    Energy Technology Data Exchange (ETDEWEB)

    Buesseler, K.O.; Kaplan, D.; Peterson, S.; Dai, M.

    2006-11-07

    The intent of this research effort is to: i) provide the basis for accurate modeling and prediction of actinide transport; ii) allow for remediation strategies to be planned that might use in-situ manipulations of geochemical variables to enhance (for extraction) or retard (for immobilization) Pu mobility in the groundwater zone; iii) identify specific Pu sources and the extent of far field, or long-term migration of transuranics in groundwater; iv) reduce costly uncertainty in performance and risk assessment calculations. This new knowledge is essential to ensure continued public and worker safety at the DOE sites and the efficient management of cleanup and containment strategies.

  19. Sources, Speciation and Mobility of Plutonium and Other Transuranics in the Groundwater at the Savannah River Site (Sept. 2003-Sept. 2006)

    Energy Technology Data Exchange (ETDEWEB)

    Buesseler, K.O.; Kaplan, D.; Peterson, S.; Dai, M.

    2006-11-07

    The intent of this research effort is to: (1) provide the basis for accurate modeling and prediction of actinide transport; (2) allow for remediation strategies to be planned that might use in-situ manipulations of geochemical variables to enhance (for extraction) or retard (for immobilization) Pu mobility in the groundwater zone; (3) identify specific Pu sources and the extent of far field, or long-term migration of transuranics in groundwater; (4) reduce costly uncertainty in performance and risk assessment calculations. This new knowledge is essential to ensure continued public and worker safety at the DOE sites and the efficient management of cleanup and containment strategies.

  20. Inspection and test planning

    International Nuclear Information System (INIS)

    Purpose of Quality Plan - arrangement of all necessary tests or inspections as far as possible filted to certain components or systems. Subject of Quality Plan - precise determination of tests or inspections and - according to the actual safety significance - the certificates to be done. Disposition of Quality Plan - accommodation of tests to the actual state of fabrication. Application of Quality Plan - to any component or system that is regarded. Supervision of Employment - by authorized personnel of manufacturer, customer or authority providing exact employment of quality plan. Overservance of Instructions - certificates given by authorized personnel. (orig./RW)

  1. Studies of Heavy-Ion Reactions and Transuranic Nuclei

    Energy Technology Data Exchange (ETDEWEB)

    Schroeder, Wolf

    2016-07-28

    Studies of heavy-ion reactions and transuranic nuclei performed by the University of Rochester Nuclear Science Research Group have been successful in furthering experimental systematics and theoretical understanding of the behavior of nuclear systems excited to their limits of stability. The theoretical results explain specifically the “boiling” and “vaporization” of atomic nuclei but are more generally applicable to isolated, quantal many-particle systems which, under thermal or mechanical stresses, all disintegrate by evaporation, via surface cluster emission, or via fission-like processes Accompanying experimental investigations by the group have demonstrated several new types of dynamical instability of nuclei: In central, “head-on” collisions, target nuclei exhibit limited ability to stop energetic projectile nuclei and to dissipate the imparted linear momentum. Substantial matter overlap (“neck”) between projectile and target nuclei, which is observed at elevated collision energies, can be stretched considerably and break at several places simultaneously. These results provide new testing grounds for microscopic theory of the cohesion of nuclear matter. This property has remained elusive, even though the elementary nucleon-nucleon forces are well known since some time Technical R&D has resulted in a detailed characterization of a novel plastic material, which can now be used in the design of sensitive diagnostic systems for various types of radio-activity. Innovative application o powerful laser systems has produced intense, controllable sources of exotic particle radioactivity for nuclear investigations Several students have received their Ph.D. degree in experimental nuclear science for their work on basic nuclear research or R&D projects.

  2. Studies of Heavy-Ion Reactions and Transuranic Nuclei

    Energy Technology Data Exchange (ETDEWEB)

    Schroeder, W. Udo [Univ. of Rochester, NY (United States). Dept. of Chemistry. Dept. of Physics

    2016-07-28

    Studies of heavy-ion reactions and transuranic nuclei performed by the University of Rochester Nuclear Science Research Group have been successful in furthering experimental systematics and theoretical understanding of the behavior of nuclear systems excited to their limits of stability. The theoretical results explain specifically the “boiling” and “vaporization” of atomic nuclei but are more generally applicable to isolated, quantal many-particle systems which, under thermal or mechanical stresses, all disintegrate by evaporation, via surface cluster emission, or via fission-like processes. Accompanying experimental investigations by the group have demonstrated several new types of dynamical instability of nuclei: In central, “head-on” collisions, target nuclei exhibit limited ability to stop energetic projectile nuclei and to dissipate the imparted linear momentum. Substantial matter overlap (“neck”) between projectile and target nuclei, which is observed at elevated collision energies, can be stretched considerably and break at several places simultaneously. These results provide new testing grounds for microscopic theory of the cohesion of nuclear matter. This property has remained elusive, even though the elementary nucleon-nucleon forces are well known since some time. Technical R&D has resulted in a detailed characterization of a novel plastic material, which can now be used in the design of sensitive diagnostic systems for various types of radio-activity. Innovative application of powerful laser systems has produced intense, controllable sources of exotic particle radioactivity for nuclear investigations. Several students have received their Ph.D. degree in experimental nuclear science for their work on basic nuclear research or R&D projects.

  3. Certification for Information Brokers.

    Science.gov (United States)

    Sawyer, Deborah C.

    1995-01-01

    The future of the information broker business depends on certification. Some obstacles are lack of commonality, control, a professional title, and time. Core competencies (ethics, professional conduct, and client care) and specialties could determine certification criteria, and a grace period for phasing in established brokers could be initiated.…

  4. Review of the WIPP draft application to show compliance with EPA transuranic waste disposal standards

    Energy Technology Data Exchange (ETDEWEB)

    Neill, R.H.; Chaturvedi, L.; Clemo, T.M. [and others

    1996-03-01

    The purpose of the New Mexico Environmental Evaluation Group (EEG) is to conduct an independent technical evaluation of the Waste Isolation Pilot Plant (WIPP) Project to ensure the protection of the public health and safety and the environment. The WIPP Project, located in southeastern New Mexico, is being constructed as a repository for the disposal of transuranic (TRU) radioactive wastes generated by the national defense programs. The EEG was established in 1978 with funds provided by the U.S. Department of Energy (DOE) to the State of New Mexico. Public Law 100-456, the National Defense Authorization Act, Fiscal Year 1989, Section 1433, assigned EEG to the New Mexico Institute of Mining and Technology and continued the original contract DE-AC04-79AL10752 through DOE contract DE-AC04-89AL58309. The National Defense Authorization Act for Fiscal Year 1994, Public Law 103-160, continues the authorization. EEG performs independent technical analyses of the suitability of the proposed site; the design of the repository, its planned operation, and its long-term integrity; suitability and safety of the transportation systems; suitability of the Waste Acceptance Criteria and the generator sites` compliance with them; and related subjects. These analyses include assessments of reports issued by the DOE and its contractors, other federal agencies and organizations, as they relate to the potential health, safety and environmental impacts from WIPP. Another important function of EEG is the independent environmental monitoring of background radioactivity in air, water, and soil, both on-site and off-site.

  5. Safety analysis report for packaging (onsite) transuranic performance demonstration program sample packaging

    International Nuclear Information System (INIS)

    The Transuranic Performance Demonstration Program (TPDP) sample packaging is used to transport highway route controlled quantities of weapons grade (WG) plutonium samples from the Plutonium Finishing Plant (PFP) to the Waste Receiving and Processing (WRAP) facility and back. The purpose of these shipments is to test the nondestructive assay equipment in the WRAP facility as part of the Nondestructive Waste Assay PDP. The PDP is part of the U. S. Department of Energy (DOE) National TRU Program managed by the U. S. Department of Energy, Carlsbad Area Office, Carlsbad, New Mexico. Details of this program are found in CAO-94-1045, Performance Demonstration Program Plan for Nondestructive Assay for the TRU Waste Characterization Program (CAO 1994); INEL-96/0129, Design of Benign Matrix Drums for the Non-Destructive Assay Performance Demonstration Program for the National TRU Program (INEL 1996a); and INEL-96/0245, Design of Phase 1 Radioactive Working Reference Materials for the Nondestructive Assay Performance Demonstration Program for the National TRU Program (INEL 1996b). Other program documentation is maintained by the national TRU program and each DOE site participating in the program. This safety analysis report for packaging (SARP) provides the analyses and evaluations necessary to demonstrate that the TRU PDP sample packaging meets the onsite transportation safety requirements of WHC-CM-2-14, Hazardous Material Packaging and Shipping, for an onsite Transportation Hazard Indicator (THI) 2 packaging. This SARP, however, does not include evaluation of any operations within the PFP or WRAP facilities, including handling, maintenance, storage, or operating requirements, except as they apply directly to transportation between the gate of PFP and the gate of the WRAP facility. All other activities are subject to the requirements of the facility safety analysis reports (FSAR) of the PFP or WRAP facility and requirements of the PDP

  6. Transuranic (Tru) waste volume reduction operations at a plutonium facility

    Energy Technology Data Exchange (ETDEWEB)

    Cournoyer, Michael E [Los Alamos National Laboratory; Nixon, Archie E [Los Alamos National Laboratory; Dodge, Robert L [Los Alamos National Laboratory; Fife, Keith W [Los Alamos National Laboratory; Sandoval, Arnold M [Los Alamos National Laboratory; Garcia, Vincent E [Los Alamos National Laboratory

    2010-01-01

    Programmatic operations at the Los Alamos National Laboratory Plutonium Facility (TA 55) involve working with various amounts of plutonium and other highly toxic, alpha-emitting materials. The spread of radiological contamination on surfaces, airborne contamination, and excursions of contaminants into the operator's breathing zone are prevented through use of a variety of gloveboxes (the glovebox, coupled with an adequate negative pressure gradient, provides primary confinement). Size-reduction operations on glovebox equipment are a common activity when a process has been discontinued and the room is being modified to support a new customer. The Actin ide Processing Group at TA-55 uses one-meter-long glass columns to process plutonium. Disposal of used columns is a challenge, since they must be size-reduced to get them out of the glovebox. The task is a high-risk operation because the glass shards that are generated can puncture the bag-out bags, leather protectors, glovebox gloves, and the worker's skin when completing the task. One of the Lessons Learned from these operations is that Laboratory management should critically evaluate each hazard and provide more effective measures to prevent personnel injury. A bag made of puncture-resistant material was one of these enhanced controls. We have investigated the effectiveness of these bags and have found that they safely and effectively permit glass objects to be reduced to small pieces with a plastic or rubber mallet; the waste can then be easily poured into a container for removal from the glove box as non-compactable transuranic (TRU) waste. This size-reduction operation reduces solid TRU waste generation by almost 2% times. Replacing one-time-use bag-out bags with multiple-use glass crushing bags also contributes to reducing generated waste. In addition, significant costs from contamination, cleanup, and preparation of incident documentation are avoided. This effort contributes to the Los Alamos

  7. Transuranic (TRU) waste volume reduction operations at a plutonium facility

    International Nuclear Information System (INIS)

    Programmatic operations at the Los Alamos National Laboratory Plutonium Facility (TA-55) involve working with various amounts of plutonium and other highly toxic, alpha-emitting materials. The spread of radiological contamination on surfaces, airborne contamination, and excursions of contaminants into the operator's breathing zone are prevented through use of a variety of gloveboxes (the glovebox, coupled with an adequate negative pressure gradient, provides primary confinement). Size-reduction operations on glovebox equipment are a common activity when a process has been discontinued and the room is being modified to support a new customer. The Actinide Processing Group at TA-55 uses one-meter or longer glass columns to process plutonium. Disposal of used columns is a challenge, since they must be size-reduced to get them out of the glovebox. The task is a high-risk operation because the glass shards that are generated can puncture the bag-out bags, leather protectors, glovebox gloves, and the worker's skin when completing the task. One of the Lessons Learned from these operations is that Laboratory management should critically evaluate each hazard and provide more effective measures to prevent personnel injury. A bag made of puncture-resistant material was one of these enhanced controls. We have investigated the effectiveness of these bags and have found that they safely and effectively permit glass objects to be reduced to small pieces with a plastic or rubber mallet; the waste can then be easily poured into a container for removal from the glovebox as non-compactable transuranic (TRU) waste. This size-reduction operation reduces solid TRU waste volume generation by almost 2½ times. Replacing one-time-use bag-out bags with multiple-use glass crushing bags also contributes to reducing generated waste. In addition, significant costs from contamination, cleanup, and preparation of incident documentation are avoided. This effort contributes to the Los Alamos

  8. Behavior of a high-temperature gas reactor with transuranic fuels

    International Nuclear Information System (INIS)

    In this work, we modeled a high-temperature gas reactor, HTGR, of prismatic block type using the SCALE 6.0 code to analyze the use of transuranic fuel in these reactors. To represent the concept, the Japanese HTTR reactor was chosen. The fuels considered used transuranic elements from UREX+ reprocessing of burned PWR fuel spiked with depleted U or Th. The calculations, performed for typical temperatures of HTR reactors, showed that, in mixtures with the same percentage of fissile material, the initial effective multiplication factor, Keff , is higher in the mixtures containing Th than that with U. Comparisons between the two types of fuel were performed using fuel pairs with the same initial Keff. During burn-up, the two mixtures show a slow and practically equal decrease in Keff. For the same level of burnup, mixtures containing Th show greater effectiveness in burning transuranics and total plutonium when compared to corresponding mixtures with depleted U. (author)

  9. Current status of the multi-isotopic transuranic-waste-assay system

    International Nuclear Information System (INIS)

    We have designed, constructed, tested, and are scheduled to field a 208-l barrel-sized working version of our multi-isotopic transuranic assay system. This system uses both passive neutron multiplicity and pulsed active measurements to identify and quantify spontaneous neutron emitters and fissile TRU isotopes. Using the system we can separately quantify up to seven individual transuranic isotopes under favorable conditions with the intrinsic sensitivity to screen or assay barrels at or below the 10 nCi/g transuranic level. Our measured 3 sigma sensitivity for 239Pu is about 0.5 mg. A large range of waste matrix materials can be accommodated by the system, as well as extremes in both gamma-ray and neutron backgrounds

  10. Fusion option to dispose of spent nuclear fuel and transuranic elements

    Energy Technology Data Exchange (ETDEWEB)

    Gohar, Y.

    2000-02-10

    The fusion option is examined to solve the disposition problems of the spent nuclear fuel and the transuranic elements. The analysis of this report shows that the top rated solution, the elimination of the transuranic elements and the long-lived fission products, can be achieved in a fusion reactor. A 167 MW of fusion power from a D-T plasma for sixty years with an availability factor of 0.75 can transmute all the transuranic elements and the long-lived fission products of the 70,000 tons of the US inventory of spent nuclear fuel generated up to the year 2015. The operating time can be reduced to thirty years with use of 334 MW of fusion power, a system study is needed to define the optimum time. In addition, the fusion solution eliminates the need for a geological repository site, which is a major advantage. Meanwhile, such utilization of the fusion power will provide an excellent opportunity to develop fusion energy for the future. Fusion blankets with a liquid carrier for the transuranic elements can achieve a transmutation rate for the transuranic elements up to 80 kg/MW.y of fusion power with k{sub eff} of 0.98. In addition, the liquid blankets have several advantages relative to the other blanket options. The energy from this transmutation is utilized to produce revenue for the system. Molten salt (Flibe) and lithium-lead eutectic are identified as the most promising liquids for this application, both materials are under development for future fusion blanket concepts. The Flibe molten salt with transuranic elements was developed and used successfully as nuclear fuel for the molten salt breeder reactor in the 1960's.

  11. Converse Barrier Certificate Theorem

    DEFF Research Database (Denmark)

    Wisniewski, Rafael; Sloth, Christoffer

    2013-01-01

    This paper presents a converse barrier certificate theorem for a generic dynamical system.We show that a barrier certificate exists for any safe dynamical system defined on a compact manifold. Other authors have developed a related result, by assuming that the dynamical system has no singular...... points in the considered subset of the state space. In this paper, we redefine the standard notion of safety to comply with generic dynamical systems with multiple singularities. Afterwards, we prove the converse barrier certificate theorem and illustrate the differences between ours and previous work by...

  12. Employment certificates on HRT

    CERN Multimedia

    HR Department

    2008-01-01

    As part of the ongoing drive to simplify and streamline administrative procedures and processes, the IT and HR Departments have made employment certificates available on a self-service basis on the HRT application, in the main menu under "My self services". All members of the personnel can thus obtain a certificate of employment or association, in French or in English, for the present or past contractual period. The HR Department’s Records Office remains responsible for issuing any special certificates that might be required. IT-AIS (Administrative Information Services) HR-SPS (Services, Procedures & Social) Records Office – Tel. 73700

  13. Composition containing transuranic elements for use in the homeopathic treatment of aids

    Energy Technology Data Exchange (ETDEWEB)

    Lustig, D.

    1996-04-18

    A homeopathic remedy consisting of a composition containing one or more transuranic elements, particularly plutonium, for preventing and treating acquired immunodeficiency syndrome (AIDS) in humans, as well as seropositivity for human immunodeficiency virus (HIV). Said composition is characterized in that it uses any chemical or isotopic form of one or more transuranic elements (neptunium, plutonium, americium, curium, berkelium, californium or einsteinium), particularly plutonium, said form being diluted and dynamized according to conventional homeopathic methods, particularly the so-called Hahnemann and Korsakov methods, and provided preferably but not exclusively in the form of lactose and/or saccharose globules or granules impregnated with the active principle of said composition. (author).

  14. Composition containing transuranic elements for use in the homeopathic treatment of aids

    International Nuclear Information System (INIS)

    A homeopathic remedy consisting of a composition containing one or more transuranic elements, particularly plutonium, for preventing and treating acquired immunodeficiency syndrome (AIDS) in humans, as well as seropositivity for human immunodeficiency virus (HIV). Said composition is characterized in that it uses any chemical or isotopic form of one or more transuranic elements (neptunium, plutonium, americium, curium, berkelium, californium or einsteinium), particularly plutonium, said form being diluted and dynamized according to conventional homeopathic methods, particularly the so-called Hahnemann and Korsakov methods, and provided preferably but not exclusively in the form of lactose and/or saccharose globules or granules impregnated with the active principle of said composition. (author)

  15. Application of service examinations to transuranic waste container integrity at the Hanford Site

    International Nuclear Information System (INIS)

    Transuranic waste containers in retrievable storage trenches at the Hanford Site and their storage environment are described. The containers are of various types, predominantly steel 0.21-m3 (55-gal) drums and boxes of many different sizes and materials. The storage environment is direct soil burial and aboveground storage under plastic tarps with earth on top of the tarps. Available data from several transuranic waste storage sites are summarized and degradation rates are projected for containers in storage at the Hanford Site

  16. Waste Isolation Pilot Plant transuranic wastes experimental characterization program: executive summary

    Energy Technology Data Exchange (ETDEWEB)

    Molecke, M.A.

    1978-11-01

    A general overview of the Waste Isolation Pilot Plant transuranic wastes experimental characterization program is presented. Objectives and outstanding concerns of this program are discussed. Characteristics of transuranic wastes are also described. Concerns for the terminal isolation of such wastes in a deep bedded salt facility are divided into two phases, those during the short-term operational phase of the facility, and those potentially occurring in the long-term, after decommissioning of the repository. An inclusive summary covering individual studies, their importance to the Waste Isolation Pilot Plant, investigators, general milestones, and comments are presented.

  17. Application of service examinations to transuranic waste container integrity at the Hanford Site. Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    Duncan, D.R.; Burbank, D.A. Jr.; Anderson, B.C.; Demiter, J.A.

    1993-09-01

    Transuranic waste containers in retrievable storage trenches at the Hanford Site and their storage environment are described. The containers are of various types, predominantly steel 0.21-m{sup 3} (55-gal) drums and boxes of many different sizes and materials. The storage environment is direct soil burial and aboveground storage under plastic tarps with earth on top of the tarps. Available data from several transuranic waste storage sites are summarized and degradation rates are projected for containers in storage at the Hanford Site.

  18. Digital signature and certification authorities

    OpenAIRE

    Prouza, Marek

    2013-01-01

    This bachelor thesis deal with Public Key Infrastructure issue, certificates and certification authorities. At the beginning there is included chapter about cryptography for better understanding including historical evolution of ciphers and analysis of three important ciphers. In the next chapter are discussed possibilities and principles of certification authorities, certificates and x509 standard. Following chapter discuss practical use of certificates in business, MS Office aplications and...

  19. Indirect Air Carrier Certification

    Data.gov (United States)

    Department of Homeland Security — Required information is entered in order to obtain an IAC certification and do business as an IAC. Information is verified through site inspections and inspections...

  20. Wind power certificate marketing

    International Nuclear Information System (INIS)

    Wind Power Certificate marketing is a green power development program in Canada. The Pembina Institute partnered with Vision Quest Windelectric in October 2003 to sell Wind Power Certificates to individuals and businesses. Individuals who buy Wind Power Certificates directly support the development of wind energy in Canada and support one of Pembina's main areas of work, the development of sustainable energy. This presentation outlined both the successes and challenges of marketing the certificates. Wind Power Certificates represent the benefits that wind power generation provides, such as zero emissions of greenhouse gases and regional air pollutants; minimal impacts on the biosphere; and, offsetting life-cycle impacts of other energy sources such as fossil fuels. They also represent quality assurance on new wind power commissioned after April 2001. In the price structure of Pembina's Wind Power Certificate, a premium of 2.7 cents per kWh is charged above the regular electricity price. The premium is lowered slightly for purchases of 200 MWh or more. Pembina also began a secondary campaign in July 2004 to have 20,000 computers powered by wind across Canada. This PC campaign offers the general public an option to support wind power development in a way that is easy to understand. In the PC campaign, a consumer is asked to pay $16 per 3 years for a laptop computer or $32 per 3 years for an average desktop computer. Vision Quest has received a Market Incentive Program grant through Natural Resources Canada to help market Pembina's wind power programs. Although the programs are too new to provide important statistical information, some small successes have been reported to date including 1950 MWh of Wind Power Certificates that have been purchased, representing a reduction of about 1730 tonnes of carbon dioxide. One of the challenges facing the Wind Power Certificate program is that some companies feel they already pay too much for electricity and the premium cost of

  1. DB2 10.1 fundamentals certification study guide

    CERN Document Server

    Sanders, Roger E

    2014-01-01

    Beginning with an explanation of the certification process and working through fundamental exam objectives, this guide gives test-takers all they need to know to pass IBM's DB2 10.1 Fundamentals certification exam (Exam 610). All the subjects covered on the exam are included: planning, security, data concurrency, working with databases and database objects, working with data using SQL and XQuery, working with DB2 tables, views, and indexes-and more. The book concludes with an

  2. Results of HWVP transuranic process waste treatment laboratory and pilot-scale filtration tests using specially ground zeolite

    International Nuclear Information System (INIS)

    Process waste streams from the Hanford Waste Vitrification Plant (HWVP) may require treatment for cesium, strontium, and transuranic (TRU) element removal in order to meet criteria for incorporation in grout. The approach planned for cesium and strontium removal is ion exchange using a zeolite exchanger followed by filtration. Filtration using a pneumatic hydropulse filter is planned to remove TRU elements which are associated with process solids and to also remove zeolite bearing the cesium and strontium. The solids removed during filtration are recycled to the melter feed system to be incorporated into the HWVP glass product. Fluor Daniel, Inc., the architect-engineering firm for HWVP, recommended a Pneumatic Hydropulse (PHP) filter manufactured by Mott Metallurgical Corporation for use in the HWVP. The primary waste streams considered for application of zeolite contact and filtration are melter off-gas condensate from the submerged bed scrubber (SBS), and equipment decontamination solutions from the Decontamination Waste Treatment Tank (DWTT). Other waste streams could be treated depending on TRU element and radionuclide content. Laboratory and pilot-scale filtration tests were conducted to provide a preliminary assessment of the adequacy of the recommended filter for application to HWVP waste treatment

  3. Results of HWVP transuranic process waste treatment laboratory and pilot-scale filtration tests using specially ground zeolite

    Energy Technology Data Exchange (ETDEWEB)

    Eakin, D.E.

    1996-03-01

    Process waste streams from the Hanford Waste Vitrification Plant (HWVP) may require treatment for cesium, strontium, and transuranic (TRU) element removal in order to meet criteria for incorporation in grout. The approach planned for cesium and strontium removal is ion exchange using a zeolite exchanger followed by filtration. Filtration using a pneumatic hydropulse filter is planned to remove TRU elements which are associated with process solids and to also remove zeolite bearing the cesium and strontium. The solids removed during filtration are recycled to the melter feed system to be incorporated into the HWVP glass product. Fluor Daniel, Inc., the architect-engineering firm for HWVP, recommended a Pneumatic Hydropulse (PHP) filter manufactured by Mott Metallurgical Corporation for use in the HWVP. The primary waste streams considered for application of zeolite contact and filtration are melter off-gas condensate from the submerged bed scrubber (SBS), and equipment decontamination solutions from the Decontamination Waste Treatment Tank (DWTT). Other waste streams could be treated depending on TRU element and radionuclide content. Laboratory and pilot-scale filtration tests were conducted to provide a preliminary assessment of the adequacy of the recommended filter for application to HWVP waste treatment.

  4. Nondestructive Testing Qualification and Certification of Personnel

    International Nuclear Information System (INIS)

    Establishment of nondestructive testing qualification and certification of personnel system is very important for level up of this skill and result. The result of this efficiency is depend on a person's capability who has a sense of responsibility of this part. Now Korea Standards Committee is preparing for this system. But, that is not a detailed practice level. So in this report, We introduce ISO/DIS 9712 international standard to members and, translate it for collect the opinions of hereafter's plan.

  5. Using Downhole Probes to Locate and Characterize Buried Transuranic and Mixed Low Level Waste

    Energy Technology Data Exchange (ETDEWEB)

    Steinman, Donald K; Bramblett, Richard L; Hertzog, Russel C

    2012-06-25

    Borehole logging probes were developed and tested to locate and quantify transuranic elements in subsurface disposal areas and in contaminated sites at USDOE Weapons Complex sites. A new method of measuring very high levels of chlroine in the subsurface was developed using pulsed neutron technology from oilfield applications. The probes were demonstrated at the Hanford site in wells containing plutonium and other contaminants.

  6. Process Description for the Retrieval of Earth Covered Transuranic (TRU) Waste Containers at the Hanford Site

    Energy Technology Data Exchange (ETDEWEB)

    DEROSA, D.C.

    2000-01-13

    This document describes process and operational options for retrieval of the contact-handled suspect transuranic waste drums currently stored below grade in earth-covered trenches at the Hanford Site. Retrieval processes and options discussed include excavation, container retrieval, venting, non-destructive assay, criticality avoidance, incidental waste handling, site preparation, equipment, and shipping.

  7. Transuranics contribution off Palomares coast: tracing history and routes to the marine environment

    International Nuclear Information System (INIS)

    Following the Palomares accident, 1966, a land monitoring program has been running. The study of the possible transfer of the residual transuranics contamination on land to the marine environment began in 1986. This paper presents the use of artificial and natural radionuclides as valuable tools for the evaluation of the possible pathways by which the transfer to the Mediterranean sea could occur. (Author)

  8. ENVIRONMENTAL MANAGEMENT SYSTEMS CERTIFICATION

    Directory of Open Access Journals (Sweden)

    Aniko Miler-Virc

    2012-12-01

    Full Text Available ISO 14001 prescribes the requirements for a system, not environmental performance itself. Similarly, certification is of the management system itself, not environmental performance. An audit is not conducted to ascertain whether your flue gas emissions are less than X part per million nitrous oxide or that your wastewater effluent contains less that Y milligrams of bacteria per litre. Consequently, the procces of auditing the system for compliance to the standard entails checking to see that all of the necessary components of a functioning system are present and working properly.           A company can have a complete and fully functional EMS as prescribed by ISO 14001 without being certified. As certification can add to the time and expense of EMS development, it is important for you to establish, in advance, whether certification is of net benefit to you. Although most companies that develop an EMS do in fact certify, there are cases where certification does not add immediate value. Certification is not always beneficial to small and medium sized companies. Certification is not always necessary for companies with one or two large clients with environmental demands who are satisfied that you have a functional EMS (second-party declaration. Whatever decision you make, it is important to remember that just as a driver′s licence does not automatically make you a good driver, ISO 14001 certification does not automatically make your company environmentally benign or ensure that you will continually improve environmental performance. The system is only as good as the people who operate it.

  9. Methodology for forecasting in the Swedish–Norwegian market for el-certificates

    International Nuclear Information System (INIS)

    In this paper we describe a novel methodology for forecasting in the Swedish–Norwegian el-certificate market, which is a variant of a tradable green certificate scheme. For the forecasting, the el-certificate market is integrated in the electricity-market model EMPS, which has weekly to hourly time-step length, whereas the planning horizon can be several years. Strategies for the certificate inventory are calculated by stochastic dynamic programming, whereas penalty-rates for non-compliance during the annual settlement of certificates are determined endogenously. In the paper the methodology is described, and we show the performance of the model under different cases that can occur in the el-certificate market. The general results correspond to theoretical findings in previous studies for tradable green certificate markets, in particular that price-scenarios spread out in such a way that the unconditional expected value of certificates is relatively stable throughout the planning period. In addition the presented methodologies allows to assess the actual dynamics of the certificate price due to climatic uncertainty. Finally, special cases are indentified where the certificate price becomes excessively high respectively zero, due the design-specific dynamics of the penalty rate. - Highlights: • A method for forecasting in the Swedish–Norwegian el-certificate market is proposed. • The developed model integrates the el-certificate and the power market. • Banking of certificates and the endogenously calculated penalty rate are included. • The certificate value is calculated using Stochastic-Dynamic-Programming. • Price dynamics due to climatic weather uncertainties are assessed and illustrated

  10. Waste Generator Instructions: Key to Successful Implementation of the US DOE's 435.1 for Transuranic Waste Packaging Instructions (LA-UR-12-24155) - 13218

    Energy Technology Data Exchange (ETDEWEB)

    French, David M. [LANL EES-12, Carlsbad, NM, Los Alamos National Laboratory, P.O. Box 1663, Los Alamos, NM 87545 (United States); Hayes, Timothy A. [LANL EES-12, Carlsbad, NM, Los Alamos National Laboratory, P.O. Box 1663, Los Alamos, NM 87545 (United States); Pope, Howard L. [Aspen Resources Ltd., Inc., P.O. Box 3038, Boulder, CO 80307 (United States); Enriquez, Alejandro E. [LANL NCO-4, Los Alamos National Laboratory, P.O. Box 1663, Los Alamos, NM 87545 (United States); Carson, Peter H. [LANL NPI-7, Los Alamos National Laboratory, P.O. Box 1663, Los Alamos, NM 87545 (United States)

    2013-07-01

    In times of continuing fiscal constraints, a management and operation tool that is straightforward to implement, works as advertised, and virtually ensures compliant waste packaging should be carefully considered and employed wherever practicable. In the near future, the Department of Energy (DOE) will issue the first major update to DOE Order 435.1, Radioactive Waste Management. This update will contain a requirement for sites that do not have a Waste Isolation Pilot Plant (WIPP) waste certification program to use two newly developed technical standards: Contact-Handled Defense Transuranic Waste Packaging Instructions and Remote-Handled Defense Transuranic Waste Packaging Instructions. The technical standards are being developed from the DOE O 435.1 Notice, Contact-Handled and Remote-Handled Transuranic Waste Packaging, approved August 2011. The packaging instructions will provide detailed information and instruction for packaging almost every conceivable type of transuranic (TRU) waste for disposal at WIPP. While providing specificity, the packaging instructions leave to each site's own discretion the actual mechanics of how those Instructions will be functionally implemented at the floor level. While the Technical Standards are designed to provide precise information for compliant packaging, the density of the information in the packaging instructions necessitates a type of Rosetta Stone that translates the requirements into concise, clear, easy to use and operationally practical recipes that are waste stream and facility specific for use by both first line management and hands-on operations personnel. The Waste Generator Instructions provide the operator with step-by-step instructions that will integrate the sites' various operational requirements (e.g., health and safety limits, radiological limits or dose limits) and result in a WIPP certifiable waste and package that can be transported to and emplaced at WIPP. These little known but widely

  11. ANALYSIS OF AVAILABLE HYDROGEN DATA & ACCUMULATION OF HYDROGEN IN UNVENTED TRANSURANIC (TRU) DRUMS

    Energy Technology Data Exchange (ETDEWEB)

    DAYLEY, L

    2004-06-24

    This document provides a response to the second action required in the approval for the Justification for Continued Operations (JCO) Assay and Shipment of Transuranic (TRU) Waste Containers in 218-W-4C. The Waste Management Project continues to make progress toward shipping certified TRU waste to the Waste Isolation Pilot Plant (WIPP). As the existing inventory of TRU waste in the Central Waste Complex (CWC) storage buildings is shipped, and the uncovered inventory is removed from the trenches and prepared for shipment from the Hanford Site, the covered inventory of suspect TRU wastes must be retrieved and prepared for processing for shipment to WIPP. Accumulation of hydrogen in unvented TRU waste containers is a concern due to the possibility of explosive mixtures of hydrogen and oxygen. The frequency and consequence of these gas mixtures resulting in an explosion must be addressed. The purpose of this study is to recommend an approach and schedule for venting TRU waste containers in the low-level burial ground (LLBG) trenches in conjunction with TRU Retrieval Project activities. This study provides a detailed analysis of the expected probability of hydrogen gas accumulation in significant quantities in unvented drums. Hydrogen gas accumulation in TRU drums is presented and evaluated in the following three categories: Hydrogen concentrations less than 5 vol%; Hydrogen between 5-15 vol%; and Hydrogen concentrations above 15 vol%. This analysis is based on complex-wide experience with TRU waste drums, available experimental data, and evaluations of storage conditions. Data reviewed in this report includes experience from the Idaho National Environmental Engineering Laboratories (INEEL), Savannah River Site (SRS), Los Alamos National Laboratories (LANL), Oak Ridge National Laboratories, (ORNL), Rocky Flats sites, Matrix Depletion Program and the National Transportation and Packaging Program. Based on this analysis, as well as an assessment of the probability and

  12. Rehabilitation Counselor Certification: Moving Forward

    Science.gov (United States)

    Saunders, Jodi L.; Barros-Bailey, Mary; Chapman, Cindy; Nunez, Patricia

    2009-01-01

    This article provides a brief history of the Commission on Rehabilitation Counselor Certification and presents recent changes and strategic goals for moving forward. Challenges and opportunities for the profession in relation to certification are also discussed. (Contains 3 tables.)

  13. Soy production and certification

    DEFF Research Database (Denmark)

    Tomei, Julia; Semino, Stella Maris; Paul, Helena;

    2010-01-01

    With the rising emphasis on biofuels as a potential solution to climate change, this paper asks whether certification schemes, developed to promote sustainable feedstock production, are able to deliver genuine sustainability benefits. The Round Table on Responsible Soy (RTRS) is a certification...... scheme that aims to promote responsible soy production through the development of principles and criteria. However, can and does this initiative address the negative impacts associated with the intensive production of soy? Taking the example of soy biodiesel produced in Argentina, this paper asks whether...... the social and environmental impacts of soybean production can be mitigated by the RTRS. It concludes that at present certification schemes are unlikely to be able to address either the institutional challenges associated with their implementation or the detrimental impacts of the additional demand generated...

  14. Certification et equivalence

    Science.gov (United States)

    Colardyn, Danielle

    1992-11-01

    The new economic and social equilibrium which is gradually coming about in Europe has significant consequences in terms of mobility, recognition of qualifications and certification. Specifically in the educational arena, questions are raised as to the social and vocational value of certificates, and the recognition of vocational skills. These skills are part of the wealth of the particular countries in the Community, and of each of the individuals who are now confronted by the enlarged economic and social space, in its varying forms. In this European context, what is examined here is more particularly the French situation, from the point of view of the evolution of the notion of certification and recognition of skills, and of policies both of qualification, and of initial and continuing training of the work force.

  15. Transuranic Contamination in Sediment and Groundwater at the U.S. DOE Hanford Site

    Energy Technology Data Exchange (ETDEWEB)

    Cantrell, Kirk J.

    2009-08-20

    A review of transuranic radionuclide contamination in sediments and groundwater at the DOE’s Hanford Site was conducted. The review focused primarily on plutonium-239/240 and americium-241; however, other transuranic nuclides were discussed as well, including neptunium-237, plutonium-238, and plutonium-241. The scope of the review included liquid process wastes intentionally disposed to constructed waste disposal facilities such as trenches and cribs, burial grounds, and unplanned releases to the ground surface. The review did not include liquid wastes disposed to tanks or solid wastes disposed to burial grounds. It is estimated that over 11,800 Ci of plutonium-239, 28,700 Ci of americium-241, and 55 Ci of neptunium-237 have been disposed as liquid waste to the near surface environment at the Hanford Site. Despite the very large quantities of transuranic contaminants disposed to the vadose zone at Hanford, only minuscule amounts have entered the groundwater. Currently, no wells onsite exceed the DOE derived concentration guide for plutonium-239/240 (30 pCi/L) or any other transuranic contaminant in filtered samples. The DOE derived concentration guide was exceeded by a small fraction in unfiltered samples from one well (299-E28-23) in recent years (35.4 and 40.4 pCi/L in FY 2006). The primary reason that disposal of these large quantities of transuranic radionuclides directly to the vadose zone at the Hanford Site has not resulted in widespread groundwater contamination is that under the typical oxidizing and neutral to slightly alkaline pH conditions of the Hanford vadose zone, transuranic radionuclides (plutonium and americium in particular) have a very low solubility and high affinity for surface adsorption to mineral surfaces common within the Hanford vadose zone. Other important factors are the fact that the vadose zone is typically very thick (hundreds of feet) and the net infiltration rate is very low due to the desert climate. In some cases where

  16. TRUPACT-1 implementation plan

    Energy Technology Data Exchange (ETDEWEB)

    Hurley, J.D.; Tappen, J.J. (Westinghouse Electric Corp., Albuquerque, NM (United States). Joint Integration Office); Christensen, D.S. (USDOE Joint Integration Office, Albuquerque, NM (United States)) (eds.)

    1985-09-01

    TRUPACT-1, the TRansUranic PACkage Transporter is a packaging designed to transport defense contact handled transuranic (CH-TRU) waste from generating and interim TRU waste storage facilities to the Waste Isolation Pilot Plant (WIPP). Prior to fabrication and procurement of a full fleet, an initial design (TRUPACT-1) will be introduced to the defense TRU waste complex through use in an operational prototype fleet which will consist of Units 1, 2, and 3. In an effort to provide a relatively smooth introduction of the TRUPACT-1, the TRUPACT Technical Team (TTT) has developed the following implementation plan. The plan provides detailed information on user handling opportunities, schedules, equipment, responsibilities, reporting and data collection activities to be performed. The intent of this document is to provide users of the TRUPACT-1 with a guidance document, complete with references, that will allow the smooth introduction of this new transportation system by providing the information necessary for collecting operational, performance and cost data. These data will be used in modeling and full fleet design and procurement activities. In addition, these data will help fine tune procedures in the inspection and maintenance document and the operational document. Additional objectives of this plan are to aid in the establishment of site operational, inspection and maintenance procedures as well as training of site operators and briefing state and local officials.

  17. Board Certification in Counseling Psychology

    Science.gov (United States)

    Crowley, Susan L.; Lichtenberg, James W.; Pollard, Jeffrey W.

    2012-01-01

    Although specialty board certification by the American Board of Professional Psychology (ABPP) has been a valued standard for decades, the vast majority of counseling psychologists do not pursue board certification in the specialty. The present article provides a brief history of board certification in general and some historical information about…

  18. Study of the association between exposure to transuranic radionuclides and cancer death

    Science.gov (United States)

    Fallahian, Naz Afarin

    An exploratory epidemiological study has been conducted on 319 deceased nuclear workers, who had recorded intakes and histories of employment for at least one year during the time period from 1943 to 1995, at different facilities including the United States Department of Energy (DOE) sites, and thorium and uranium mining and milling plants. These workers voluntarily agreed to donate their organs or whole body to the United States Transuranium and Uranium Registries (USTUR) for scientific research purposes. The majority of this population was involved in documented radiological incidents during their careers. Many were exposed to transuranic radionuclides primarily via inhalation or puncture wounds. The purpose of this study was to find the level of dose that was received by the USTUR registrants following accidents and subsequent to mitigating actions, and to investigate whether or not there is any association between exposure to these transuranic radionuclides and cancer deaths. The external and internal dose assessments were performed using occupational radiation exposure histories and postmortem concentrations of transuranic radionuclides in critical organs, respectively. Statistical data analyses were performed to identify whether or not the USTUR registrants can be categorized as a 'low-dose' population and to investigate the potential correlation between exposure to transuranic radionuclides and causes of death within this population due to cancers of the lungs and liver as well as cancers of all sites, while controlling for the effects of other confounders. Based on the statistical tests performed, the USTUR registrants can be categorized as a low-dose population in terms of their occupational external exposures. However, when considering their total effective dose equivalents from both external penetrating radiation and internal exposure to transuranic radionuclides, they can not be categorized as a low-dose population with a 95% confidence level (alpha = 0

  19. Performance assessment in support of the 1996 compliance certification application for the Waste Isolation Pilot Plant: A decision analysis perspective

    Energy Technology Data Exchange (ETDEWEB)

    Helton, J.C. [Arizona State Univ., Tempe, AZ (United States). Dept. of Mathematics; Anderson, D.R.; Jow, H.N.; Marietta, M.G. [Sandia National Labs., Albuquerque, NM (United States); Basabilvazo, G. [Dept. of Energy, Carlsbad, NM (United States)

    1998-08-01

    The Waste Isolation Pilot Plant (WIPP) is under development by the US Department of Energy (DOE) for the geologic disposal of transuranic waste. The primary regulatory requirements (i.e., 40 CFR 191 and 40 CFR 194) placed on the WIPP by the US Environmental Protection Agency (EPA) involve a complementary cumulative distribution function (CCDF) for normalized radionuclide releases to the accessible environment. The interpretation and use of this CCDF from a decision analysis perspective is discussed and illustrated with results from the 1996 performance assessment for the WIPP, which was carried out to support a compliance certification application by the DOE to the EPA for the WIPP.

  20. TRUPACT-2 design, testing and certification

    International Nuclear Information System (INIS)

    A large volume of contact-handled transuranic (CH TRU) nuclear waste has been generated and has accumulated at ten Department of Energy (DOE) facilities. Approximately 168,000 cubic meters of this waste has been targeted for shipment to the Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico. Shipment of all of this waste is expected to require more than 15,000 shipments, totalling approximately 38 million kilometers of travel. The TRUPACT-II is a reusable package for shipment of CH TRU waste; it is designed in accordance with US Nuclear Regulatory Commission (NRC) requirements for Type B packages found in 10 CFR 71. There are two separate levels of containment to permit shipment of plutonium in excess of 740 GBq per package. The packaging is a right circular cylinder in shape, with a domed top and a flat bottom; external dimensions are 240 centimeters in diameter and 309 centimeters high. The capacity of each TRUPACT-II is 3182 kilograms of waste that can be loaded into fourteen 210-1 drums; or two 1.9 cubic meters standard waste boxes (SWBs). Three TRUPACT-II packages are transported on a custom designed semitrailer which is pulled by a conventional tractor for highway transport of CH TRU waste between DOE sites and to the WIPP near Carlsbad, New Mexico. The Safety Analysis Report (SAR) for the TRUPACT-II Package was initially submitted to the NRC in March 1989. Four revisions were issued during the period from May through August 1989. NRC certification of the package was received on August 30, 1989. 5 refs., 4 figs., 1 tab

  1. Repackaging of High Fissile TRU Waste at the Transuranic Waste Processing Center - 13240

    International Nuclear Information System (INIS)

    Twenty-six drums of high fissile transuranic (TRU) waste from Oak Ridge National Laboratory (ORNL) operations were declared waste in the mid-1980's and placed in storage with the legacy TRU waste inventory for future treatment and disposal at the Waste Isolation Pilot Plant (WIPP). Repackaging and treatment of the waste at the TRU Waste Packaging Center (TWPC) will require the installation of additional equipment and capabilities to address the hazards for handling and repackaging the waste compared to typical Contact Handled (CH) TRU waste that is processed at the TWPC, including potential hydrogen accumulation in legacy 6M/2R packaging configurations, potential presence of reactive plutonium hydrides, and significant low energy gamma radiation dose rates. All of the waste is anticipated to be repackaged at the TWPC and certified for disposal at WIPP. The waste is currently packaged in multiple layers of containers which presents additional challenges for repackaging activities due to the potential for the accumulation of hydrogen gas in the container headspace in quantities than could exceed the Lower Flammability Limit (LFL). The outer container for each waste package is a stainless steel 0.21 m3 (55-gal) drum which contains either a 0.04 m3 or 0.06 m3 (10-gal or 15-gal) 6M drum. The inner 2R container in each 6M drum is ∼12 cm (5 in) outside diameter x 30-36 cm (12-14 in) long and is considered to be a > 4 liter sealed container relative to TRU waste packaging criteria. Inside the 2R containers are multiple configurations of food pack cans, pipe nipples, and welded capsules. The waste contains significant quantities of high burn-up plutonium oxides and metals with a heavy weight percentage of higher atomic mass isotopes and the subsequent in-growth of significant quantities of americium. Significant low energy gamma radiation is expected to be present due to the americium in-growth. Radiation dose rates on inner containers are estimated to be 1-3 mSv/hr (100

  2. Repackaging of High Fissile TRU Waste at the Transuranic Waste Processing Center - 13240

    Energy Technology Data Exchange (ETDEWEB)

    Oakley, Brian; Heacker, Fred [WAI, TRU Waste Processing Center, 100 WIPP Road Lenoir City, TN 37771 (United States); McMillan, Bill [DOE, Oak Ridge Operations, Bldg. 2714, Oak Ridge, TN 37830 (United States)

    2013-07-01

    Twenty-six drums of high fissile transuranic (TRU) waste from Oak Ridge National Laboratory (ORNL) operations were declared waste in the mid-1980's and placed in storage with the legacy TRU waste inventory for future treatment and disposal at the Waste Isolation Pilot Plant (WIPP). Repackaging and treatment of the waste at the TRU Waste Packaging Center (TWPC) will require the installation of additional equipment and capabilities to address the hazards for handling and repackaging the waste compared to typical Contact Handled (CH) TRU waste that is processed at the TWPC, including potential hydrogen accumulation in legacy 6M/2R packaging configurations, potential presence of reactive plutonium hydrides, and significant low energy gamma radiation dose rates. All of the waste is anticipated to be repackaged at the TWPC and certified for disposal at WIPP. The waste is currently packaged in multiple layers of containers which presents additional challenges for repackaging activities due to the potential for the accumulation of hydrogen gas in the container headspace in quantities than could exceed the Lower Flammability Limit (LFL). The outer container for each waste package is a stainless steel 0.21 m{sup 3} (55-gal) drum which contains either a 0.04 m{sup 3} or 0.06 m{sup 3} (10-gal or 15-gal) 6M drum. The inner 2R container in each 6M drum is ∼12 cm (5 in) outside diameter x 30-36 cm (12-14 in) long and is considered to be a > 4 liter sealed container relative to TRU waste packaging criteria. Inside the 2R containers are multiple configurations of food pack cans, pipe nipples, and welded capsules. The waste contains significant quantities of high burn-up plutonium oxides and metals with a heavy weight percentage of higher atomic mass isotopes and the subsequent in-growth of significant quantities of americium. Significant low energy gamma radiation is expected to be present due to the americium in-growth. Radiation dose rates on inner containers are estimated

  3. The Views of Pre-Service Teachers Who Take Special Teaching Course within the Context of Pedagogical Formation Certificate Program about Micro-Teaching Method and a Physics Lesson Plan

    Science.gov (United States)

    Gurbuz, Fatih

    2015-01-01

    The purpose of this study is to determine the views of the pre-service teachers who received training on pedagogical formation certificate program about micro-teaching method. The study was carried out with a case study method. Semi-structured interviews were used in the study as a data collection tool to gather pre-service teachers' views about…

  4. Pharmacist specialty certification.

    Science.gov (United States)

    Durfee, Sharon M

    2012-03-01

    Nutrition support is a pharmacy specialty in which pharmacists work with prescribers, conduct order review, and either perform or oversee compounding of these complex parenteral nutrition formulations. Pharmacists should be certified in this specialty, and the options for certification are outlined in this article. PMID:22275326

  5. Program Implementation Plan

    International Nuclear Information System (INIS)

    The Program Implementation Plan (PIP) describes the US Department of Energy's (DOE's) current approaches for managing the permanent disposal of defense high-level waste (HLW), transuranic (TRU) waste, and low-level waste (LLW) from atomic energy defense activities. It documents the implementation of the HLW and TRU waste policies as stated in the Defense Waste Management Plan (DWMP) (DOE/DP-0015), dated June 1983, and also addresses the management of LLW. The narrative reflects both accomplishments and changes in the scope of activities. All cost tables and milestone schedules are current as of January 1987. The goals of the program, to provide safe processing and utilization, storage, and disposal of DOE radioactive waste and byproducts to support defense nuclear materials production activities, and to implement cost-effective improvements in all of its ongoing and planned activities, have not changed

  6. Synthesis of neutron-rich transuranic nuclei in fissile spallation targets

    CERN Document Server

    Mishustin, Igor; Pshenichnov, Igor; Greiner, Walter

    2014-01-01

    A possibility of synthesizing neutron-reach super-heavy elements in spallation targets of Accelerator Driven Systems (ADS) is considered. A dedicated software called Nuclide Composition Dynamics (NuCoD) was developed to model the evolution of isotope composition in the targets during a long-time irradiation by intense proton and deuteron beams. Simulation results show that transuranic elements up to Bk-249 can be produced in multiple neutron capture reactions in macroscopic quantities. However, the neutron flux achievable in a spallation target is still insufficient to overcome the so-called fermium gap. Further optimization of the target design, in particular, by including moderating material and covering it by a reflector will turn ADS into an alternative source of transuranic elements in addition to nuclear fission reactors.

  7. Evaluation of alternative treatments for spent fuel rod consolidation wastes and other miscellaneous commercial transuranic wastes

    International Nuclear Information System (INIS)

    Eight alternative treatments (and four subalternatives) are considered for both existing commercial transuranic wastes and future wastes from spent fuel consolidation. Waste treatment is assumed to occur at a hypothetical central treatment facility (a Monitored Retrieval Storage facility was used as a reference). Disposal in a geologic repository is also assumed. The cost, process characteristics, and waste form characteristics are evaluated for each waste treatment alternative. The evaluation indicates that selection of a high-volume-reduction alternative can save almost $1 billion in life-cycle costs for the management of transuranic and high-activity wastes from 70,000 MTU of spent fuel compared to the reference MRS process. The supercompaction, arc pyrolysis and melting, and maximum volume reduction alternatives are recommended for further consideration; the latter two are recommended for further testing and demonstration

  8. Synthesis of neutron-rich transuranic nuclei in fissile spallation targets

    Energy Technology Data Exchange (ETDEWEB)

    Mishustin, Igor, E-mail: mishustin@fias.uni-frankfurt.de [Frankfurt Institute for Advanced Studies, J.-W. Goethe University, 60438 Frankfurt am Main (Germany); “Kurchatov Institute”, National Research Center, 123182 Moscow (Russian Federation); Malyshkin, Yury, E-mail: malyshkin@fias.uni-frankfurt.de [Frankfurt Institute for Advanced Studies, J.-W. Goethe University, 60438 Frankfurt am Main (Germany); Institute for Nuclear Research, Russian Academy of Sciences, 117312 Moscow (Russian Federation); Pshenichnov, Igor, E-mail: pshenich@fias.uni-frankfurt.de [Frankfurt Institute for Advanced Studies, J.-W. Goethe University, 60438 Frankfurt am Main (Germany); Institute for Nuclear Research, Russian Academy of Sciences, 117312 Moscow (Russian Federation); Greiner, Walter [Frankfurt Institute for Advanced Studies, J.-W. Goethe University, 60438 Frankfurt am Main (Germany)

    2015-04-15

    A possibility of synthesizing neutron-rich superheavy elements in spallation targets of Accelerator Driven Systems (ADS) is considered. A dedicated software called Nuclide Composition Dynamics (NuCoD) was developed to model the evolution of isotope composition in the targets during a long-time irradiation by intense proton and deuteron beams. Simulation results show that transuranic elements up to {sup 249}Bk can be produced in multiple neutron capture reactions in macroscopic quantities. However, the neutron flux achievable in a spallation target is still insufficient to overcome the so-called fermium gap. Further optimization of the target design, in particular, by including moderating material and covering it by a reflector could turn ADS into an alternative source of transuranic elements in addition to nuclear fission reactors.

  9. Evaluation of alternative treatments for spent fuel rod consolidation wastes and other miscellaneous commercial transuranic wastes

    Energy Technology Data Exchange (ETDEWEB)

    Ross, W.A.; Schneider, K.J.; Oma, K.H.; Smith, R.I.; Bunnell, L.R.

    1986-05-01

    Eight alternative treatments (and four subalternatives) are considered for both existing commercial transuranic wastes and future wastes from spent fuel consolidation. Waste treatment is assumed to occur at a hypothetical central treatment facility (a Monitored Retrieval Storage facility was used as a reference). Disposal in a geologic repository is also assumed. The cost, process characteristics, and waste form characteristics are evaluated for each waste treatment alternative. The evaluation indicates that selection of a high-volume-reduction alternative can save almost $1 billion in life-cycle costs for the management of transuranic and high-activity wastes from 70,000 MTU of spent fuel compared to the reference MRS process. The supercompaction, arc pyrolysis and melting, and maximum volume reduction alternatives are recommended for further consideration; the latter two are recommended for further testing and demonstration.

  10. Environmental aspects of the transuranics. A selected, annotated bibliography. Volume 9

    International Nuclear Information System (INIS)

    This ninth published bibliography of 589 references is compiled from the Nevada Applied Ecology Information Center's Data Base on the Environmental Aspects of the Transuranics. The data base was built to provide information support to the Nevada Applied Ecology Group (NAEG) of DOE's Nevada Operations Office. The general scope covers environmental aspects of uranium and the transuranic elements, with emphasis on plutonium. This annotated bibliography highlights literature on plutonium 238 and 239 and americium 241 in the critical organs of man and animals. Studies on the migration of plutonium and the transplutonics through the environment are also emphasized. Supporting information on ecology of the Nevada Test Site and reviews and summarizing literature on other radionuclides have been included at the request of the NAEG. The references are arranged by subject category with leading authors appearing alphabetically within each category. Indexes are provided for author(s), geographic location, keywords, taxonomic name, title, and publication description

  11. Radiological, physical, and chemical characterization of transuranic wastes stored at the Idaho National Engineering Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Apel, M.L.; Becker, G.K.; Ragan, Z.K.; Frasure, J.; Raivo, B.D.; Gale, L.G.; Pace, D.P.

    1994-03-01

    This document provides radiological, physical and chemical characterization data for transuranic radioactive wastes and transuranic radioactive and hazardous (i.e., mixed) wastes stored at the Idaho National Engineering Laboratory and considered for treatment under the Private Sector Participation Initiative Program (PSPI). Waste characterization data are provided in the form of INEL Waste Profile Sheets. These documents provide, for each content code, information on waste identification, waste description, waste storage configuration, physical/chemical waste composition, radionuclide and associated alpha activity waste characterization data, and hazardous constituents present in the waste. Information is provided for 139 waste streams which represent an estimated total volume of 39,380{sup 3} corresponding to a total mass of approximately 19,000,000 kg. In addition, considerable information concerning alpha, beta, gamma, and neutron source term data specific to Rocky Flats Plant generated waste forms stored at the INEL are provided to assist in facility design specification.

  12. Environmental aspects of the transuranics: a selected, annotated bibliography. [Pu-238, Pu-239

    Energy Technology Data Exchange (ETDEWEB)

    Ensminger, J.T.; Martin, F.M.; Fore, C.S. (comps.)

    1977-03-01

    This eighth published bibliography of 427 references is compiled from the Nevada Applied Ecology Information Center's Data Base on the Environmental Aspects of the Transuranics. The data base was built to provide information support to the Nevada Applied Ecology Group (NAEG) of ERDA's Nevada Operations Office. The general scope covers environmental aspects of uranium and the transuranic elements, with emphasis on plutonium. This bibliography highlights literature on plutonium 238 and 239 and americium in the critical organs of man and animals. Supporting information on ecology of the Nevada Test Site and reviews and summarizing literature on other radionuclides have been included at the request of the NAEG. The references are arranged by subject category with leading authors appearing alphabetically in each category. Indexes are provided for author(s), geographic location, keyword(s), taxon, title, and publication description.

  13. Certification of solar products - The Florida experience

    Energy Technology Data Exchange (ETDEWEB)

    POST,HAROLD N.; ROLAND,JAMES D.; VENTRE,GERARD G.; HUGGINS,JAMES C.

    2000-02-02

    Florida legislation enacted in 1976 directed the Florida Solar Energy Center (FSEC) to develop standards for solar energy systems manufactured or sold in the state, establish criteria for testing the performance of solar energy systems, and provide a means to display compliance with approved performance tests for these systems. This mandate has been effectively implemented for both solar domestic water heating and solar pool heating systems. With growing interest and markets for photovoltaic systems, plans are presently being developed to expand the scope of the mandate to include photovoltaic technology. This paper discusses four complementary facets of a photovoltaic (PV) system certification program. They include PV module performance characterization and rating; PV system design review and approval; examination and authorization of photovoltaic system installers; and inspection and acceptance testing of PV system installation. The suggested photovoltaic system process builds on lessons learned from over 20 years of testing, certifying and labeling of solar thermal collectors, and the certification of solar thermal systems.

  14. Certification of solar products - The Florida experience

    International Nuclear Information System (INIS)

    Florida legislation enacted in 1976 directed the Florida Solar Energy Center (FSEC) to develop standards for solar energy systems manufactured or sold in the state, establish criteria for testing the performance of solar energy systems, and provide a means to display compliance with approved performance tests for these systems. This mandate has been effectively implemented for both solar domestic water heating and solar pool heating systems. With growing interest and markets for photovoltaic systems, plans are presently being developed to expand the scope of the mandate to include photovoltaic technology. This paper discusses four complementary facets of a photovoltaic (PV) system certification program. They include PV module performance characterization and rating; PV system design review and approval; examination and authorization of photovoltaic system installers; and inspection and acceptance testing of PV system installation. The suggested photovoltaic system process builds on lessons learned from over 20 years of testing, certifying and labeling of solar thermal collectors, and the certification of solar thermal systems

  15. A passive-active neutron device for assaying remote-handled transuranic waste

    International Nuclear Information System (INIS)

    A combined passive-active neutron assay device was constructed for assaying remote-handled transuranic waste. A study of matrix and source position effects in active assays showed that a knowledge of the source position alone is not sufficient to correct for position-related errors in highly moderating or absorbing matrices. An alternate function for the active assay of solid fuel pellets was derived, although the efficacy of this approach remains to be established

  16. U.S. experience with acid digestion of combustible transuranic waste

    International Nuclear Information System (INIS)

    Contaminated transuranic waste from a plutonium finishing plant has been processed in a waste treatment demonstration plant, the Radioactive Acid Digestion Test Unit (RADTU) located at Hanford, Washington, U.S.A. Waste treatment experience, including process and equipment performance, the behavior of plutonium in the system, and chemical and nuclear safety are all discussed. The complementary relationship of this research and development to that at the ALONA pilot plant in Mol, Belgium is noted

  17. Remote Handled Transuranic Sludge Retrieval Transfer And Storage System At Hanford

    Energy Technology Data Exchange (ETDEWEB)

    Raymond, Rick E. [CH2M HILL Plateau Remediation Company, Richland, WA (United States); Frederickson, James R. [AREVA, Avignon (France); Criddle, James [AREVA, Avignon (France); Hamilton, Dennis [CH2M HILL Plateau Remediation Company, Richland, WA (United States); Johnson, Mike W. [CH2M HILL Plateau Remediation Company, Richland, WA (United States)

    2012-10-18

    This paper describes the systems developed for processing and interim storage of the sludge managed as remote-handled transuranic (RH-TRU). An experienced, integrated CH2M HILL/AFS team was formed to design and build systems to retrieve, interim store, and treat for disposal the K West Basin sludge, namely the Sludge Treatment Project (STP). A system has been designed and is being constructed for retrieval and interim storage, namely the Engineered Container Retrieval, Transfer and Storage System (ECRTS).

  18. Deposition, translocation and effects of transuranic particles inhaled by experimental animals

    International Nuclear Information System (INIS)

    Inhalation exposure constitutes the most likely route of entrance for transuranics into the body. Cancer is the most likely consequence of exposure, but several thousand workers have been exposed during the last 30 yrs without, so far, evidence of exposure-related effects. Several soluble and insoluble transuranic compounds have been studied in rodents and dogs, either alone or combined with exposure to other materials (e.g., PuO/sub 2/--UO/sub 2/ fuel and Na). These studies have provided a wide variety of spatial and temporal dose distribution patterns in the lung. The distribution and total initial deposition in the respiratory tract is a function of the physical characteristics of the inhaled aerosols (size distribution, shape, hygroscopicity) and of the morphology and physiology of the animal. Translocation rates, organ and tissue distribution and excretion in urine and feces, are a function of the physicochemical characteristics of the deposited material (solubility, specific activity, chemical compound, etc.). Differences in rate of translocation of the solubilized material, primarily to the liver and bone, determines the radiation dose to the various tissues involved. Insoluble particles of plutonium dioxide are transferred to the thoracic lymph nodes, which may be functionally destroyed as a consequence. Radiation pneumonitis and pulmonary fibrosis are the main causes of death in animals with cumulative radiation doses to the lung of a few thousand rads. The most significant long-term effect of inhaled transuranic compounds in animals is the development of lung and bone tumors. The main type of lung tumor in both dog and rat is the bronchioloalveolar carcinoma (adenocarcinoma). However, tumor type is a function of radiation dose and dose-distribution at high doses. Bone ranks next to lung as the tissue developing the most tumors following inhalation of transuranics

  19. Fusion solution to dispose of spent nuclear fuel, transuranic elements, and highly enriched uranium

    Energy Technology Data Exchange (ETDEWEB)

    Gohar, Yousry E-mail: gohar@anl.gov

    2001-11-01

    The disposal of the nuclear spent fuel, the transuranic elements, and the highly enriched uranium represents a major problem under investigation by the international scientific community to identify the most promising solutions. The investigation of this paper focused on achieving the top rated solution for the problem, the elimination goal, which requires complete elimination for the transuranic elements or the highly enriched uranium, and the long-lived fission products. To achieve this goal, fusion blankets with liquid carrier, molten salts or liquid metal eutectics, for the transuranic elements and the uranium isotopes are utilized. The generated energy from the fusion blankets is used to provide revenue for the system. The long-lived fission products are fabricated into fission product targets for transmutation utilizing the neutron leakage from the fusion blankets. This paper investigated the fusion blanket designs for small fusion devices and the system requirements for such application. The results show that 334 MW of fusion power from D-T plasma for 30 years with an availability factor of 0.75 can dispose of the 70,000 tons of the U.S. inventory of spent nuclear fuel generated up to the year 2015. In addition, this fusion solution eliminates the need for a geological repository site, which is a major advantage. Meanwhile, such utilization of the fusion power will provide an excellent opportunity to develop fusion energy for the future.

  20. Systematic evaluation of options to avoid generation of noncertifiable transuranic (TRU) waste at Los Alamos National Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Boak, J.M.; Kosiewicz, S.T.; Triay, I.; Gruetzmacher, K.; Montoya, A.

    1998-03-01

    At present, >35% of the volume of newly generated transuranic (TRU) waste at Los Alamos National Laboratory is not certifiable for transport to the Waste Isolation Pilot Plant (WIPP). Noncertifiable waste would constitute 900--1,000 m{sup 3} of the 2,600 m{sup 3} of waste projected during the period of the Environmental Management (EM) Accelerated Cleanup: Focus on 2006 plan (DOE, 1997). Volume expansion of this waste to meet thermal limits would increase the shipped volume to {approximately}5,400 m{sup 3}. This paper presents the results of efforts to define which TRU waste streams are noncertifiable at Los Alamos, and to prioritize site-specific options to reduce the volume of certifiable waste over the period of the EM Accelerated Cleanup Plan. A team of Los Alamos TRU waste generators and waste managers reviewed historic generation rates and thermal loads and current practices to estimate the projected volume and thermal load of TRU waste streams for Fiscal Years 1999--2006. These data defined four major problem TRU waste streams. Estimates were also made of the volume expansion that would be required to meet the permissible wattages for all waste. The four waste streams defined were: (1) {sup 238}Pu-contaminated combustible waste from production of Radioactive Thermoelectric Generators (RTGs) with {sup 238}Pu activity which exceeds allowable shipping limits by 10--100X. (2) {sup 241}Am-contaminated cement waste from plutonium recovery processes (nitric and hydrochloric acid recovery) are estimated to exceed thermal limits by {approximately}3X. (3) {sup 239}Pu-contaminated combustible waste, mainly organic waste materials contaminated with {sup 239}Pu and {sup 241}Am, is estimated to exceed thermal load requirements by a factor of {approximately}2X. (4) Oversized metal waste objects, (especially gloveboxes), cannot be shipped as is to WIPP because they will not fit in a standard waste box or drum.

  1. "Comprehensive" energy certificate

    OpenAIRE

    Kolenac, Marko

    2013-01-01

    The thesis discusses calculated and measured energy certificates of a building, which were calculated and measured for the building of the Faculty of Civil Engineering and Geodesy in Ljubljana - the FGG building. The necessary calculations of the energy provided for functioning of the building were performed in accordance with the methodology specified in the applicable legal basis. The thesis provides measures for improving the thermal envelope of the building and presents an example of moni...

  2. Understanding Certificate Revocation

    OpenAIRE

    Hagström, Åsa

    2006-01-01

    Correct certificate revocation practices are essential to each public-key infrastructure. While there exist a number of protocols to achieve revocation in PKI systems, there has been very little work on the theory behind it: Which different types of revocation can be identified? What is the intended effect of a specific revocation type to the knowledge base of each entity? As a first step towards a methodology for the development of reliable models, we present a graph-based formalism for spec...

  3. A Proposal for Improving Administrative Preparation and Certification Programs.

    Science.gov (United States)

    Kritsonis, William A.

    Administration is the process of working with and through others to efficiently accomplish organizational goals by planning, organizing, leading, and controlling. The basic skills required by an effective administrator are technical, human, and conceptual. A strong school administrator preparation and certification program resembles the classical…

  4. 29 CFR 1956.52 - Completed developmental steps and certification.

    Science.gov (United States)

    2010-07-01

    ... Substances Act; and the State's independent Workplace Violence Prevention law, were approved by the Assistant Secretary on August 16, 2006. (b) In accordance with 29 CFR 1956.51(b), New York has promulgated regulations... PLANS New York § 1956.52 Completed developmental steps and certification. (a) In accordance with 29...

  5. 49 CFR 37.139 - Plan contents.

    Science.gov (United States)

    2010-10-01

    ..., certification by the Metropolitan Planning Organization (MPO) that it has reviewed the plan and that the plan is... Administration joint planning regulation (49 CFR part 613 and 23 CFR part 450). In a service area which is... of service provided by other agencies or organizations, which may in whole or in part be used to...

  6. Analysis of a Building Energy Efficiency Certification System in Korea

    OpenAIRE

    Duk Joon Park; Ki Hyung Yu; Yong Sang Yoon; Kee Han Kim; Sun Sook Kim

    2015-01-01

    The Korean government has established a national plan for the promotion of zero energy buildings to respond to climate change and energy crises. To achieve this plan, several energy efficiency policies for new and existing buildings have been developed. The Building Energy Efficiency Certification System (BEECS) aims to promote the spread of high energy-efficient buildings by evaluating and certifying building energy performance. This study discussed Korean building energy efficiency policies...

  7. Verifying generator waste certification: NTS waste characterization QA requirements

    International Nuclear Information System (INIS)

    Waste management activities managed by the US Department of Energy (DOE) at the Nevada Test Site (NTS) include the disposal of low-level wastes (LLW) and mixed waste (MW), waste which is both radioactive and hazardous. A majority of the packaged LLW is received from offsite DOE generators. Interim status for receipt of MW at the NTS Area 5 Radioactive Waste Management Site (RWMS) was received from the state of Nevada in 1987. The RWMS Mixed Waste Management Facility (MWMF) is expected to be operational in 1988 for approved DOE MW generators. The Nevada Test Site Defense Waste Acceptance Criteria and Certification Requirements (NVO-185, Revision 5) delineates waste acceptance criteria for waste disposal at the NTS. Regulation of the hazardous component of mixed waste requires the implementation of US Environmental Protection Agency (EPA) requirements pursuant to the Resource Conservation and Recovery Act (RCRA). Waste generators must implement a waste certification program to provide assurance that the disposal site waste acceptance criteria are met. The DOE/Nevada Operations Office (NV) developed guidance for generator waste certification program plans. Periodic technical audits are conducted by DOE/NV to assess performance of the waste certification programs. The audit scope is patterned from the waste certification program plan guidance as it integrates and provides a common format for the applicable criteria. The criteria focus on items and activities critical to processing, characterizing, packaging, certifying, and shipping waste

  8. Efficient Certificate Management in VANET

    OpenAIRE

    Samara, Ghassan

    2012-01-01

    Vehicular Ad hoc Networks is one of the most challenging research area in the field of Mobile Ad Hoc Networks, in this research We propose a flexible, simple, and scalable design for VANET certificates, and new methods for efficient certificate management, which will Reduce channel overhead by eliminating the use of CRL, and make Better certificate Revocation Management. Also it will increase the security of the network and helps in identifying the adversary vehicle.

  9. Sampling and analysis plan for ORNL filter press cake waste from the Liquid and Gaseous Waste Operations Department

    International Nuclear Information System (INIS)

    This document defines the sampling and analytical procedures needed for the initial characterization of the filter press cake waste from the Process Waste Treatment Plant (PWTP) at the Oak Ridge National Laboratory (ORNL). It is anticipated that revisions to this document will occur as operating experience and sample results suggest appropriate changes be made. Application of this document will be controlled through the ORNL Waste Management and Remedial Action Division. The sampling strategy is designed to ensure that the samples collected present an accurate representation of the waste process stream. Using process knowledge and preliminary radiological activity screens, the filter press cake waste is known to contain radionuclides. Chemical characterization under the premise of this sampling and analysis plan will provide information regarding possible treatments and ultimately, disposal of filter press cake waste at an offsite location. The sampling strategy and analyses requested are based on the K-25 waste acceptance criteria and the Nevada Test Site Defense Waste Acceptance Criteria, Certification, and Transfer Requirements [2, NVO-325, Rev. 1]. The sampling strategy will demonstrate that for the filter press cake waste there is (1) an absence of RCRA and PCBs wastes, (2) an absence of transuranic (TRU) wastes, and (3) a quantifiable amount of radionuclide activity

  10. Performance assessment requirements for the identification and tracking of transuranic waste intended for disposal at the Waste Isolation Pilot Plant

    Energy Technology Data Exchange (ETDEWEB)

    Snider, C.A. [Department of Energy, Carlsbad, NM (United States); Weston, W.W. [Westinghouse Electric Corp., Carlsbad, NM (United States)

    1997-11-01

    To demonstrate compliance with environmental radiation protection standards for management and disposal of transuranic (TRU) radioactive wastes, a performance assessment (PA) of the Waste Isolation Pilot Plant (WIPP) was made of waste-waste and waste-repository interactions and impacts on disposal system performance. An estimate of waste components and accumulated quantities was derived from a roll-up of the generator/storage sites` TRU waste inventories. Waste components of significance, and some of negligible effect, were fixed input parameters in the model. The results identified several waste components that require identification and tracking of quantities to ensure that repository limits are not exceeded. The rationale used to establish waste component limits based on input estimates is discussed. The distinction between repository limits and waste container limits is explained. Controls used to ensure that no limits are exceeded are identified. For waste components with no explicit repository based limits, other applicable limits are contained in the WIPP Waste Acceptance Criteria (WAC). The 10 radionuclides targeted for identification and tracking on either a waste container or a waste stream basis include Am-241, Pu-238, Pu-239, Pu-240, Pu-242, U-233, U-234, U-238, Sr-90, and Cs-137. The accumulative activities of these radionuclides are to be inventoried at the time of emplacement in the WIPP. Changes in inventory curie content as a function of radionuclide decay and ingrowth over time will be calculated and tracked. Due to the large margin of compliance demonstrated by PA with the 10,000 year release limits specified, the quality assurance objective for radioassay of the 10 radionuclides need to be no more restrictive than those already identified for addressing the requirements imposed by transportation and WIPP disposal operations in Section 9 of the TRU Waste Characterization Quality Assurance Program Plan. 6 refs.

  11. Entrained Solids, Strontium-Transuranic Precipitation, and Crossflow Filtration of AN102 Small C

    Energy Technology Data Exchange (ETDEWEB)

    Nash, C.A.

    2000-09-27

    This work is the first active crossflow filter testing of the new strontium-permanganate process for Envelope C at the Savannah River Technology Center. Extreme filtration difficulties with the ferric hydroxide precipitation led to investigations of other chemistries with simulants. The current process includes the isotopic dilution by precipitation from inactive strontium nitrate addition. A permanganate strike to replace ferric reagents was found to provide practical filterability and good lanthanide or transuranic decontamination. That work had been supported with simulant and active beaker testing.

  12. Strontium-Transuranic Precipitation and Crossflow Filtration of 241-AN-102 Large C

    Energy Technology Data Exchange (ETDEWEB)

    Nash, C.A.

    2001-05-21

    This work provides an important confirmation of the new strontium/permanganate precipitation process to achieve both acceptable filterability and decontamination for Envelope C (Tanks 241-AN-102 and 241-AN-107) wastes to be treated by the Hanford River Protection Project. As a bench-scale demonstration, a series of seven precipitation batches and crossflow filtration campaigns were performed to remove strontium-90 and transuranics from 16.5 liters of Tank 241-AN-102 ''Large C'' supernatant liquid containing entrained solids.

  13. The use of EDTA and DTPA for accelerating the removal of deposited transuranic elements from humans

    CERN Document Server

    Spoor, N L

    1977-01-01

    EDTA and DTPA have been prominent among the chelating agents used to increase the rate of excretion of certain deposited heavy metals from the human body. Since 1959, DTPA, administered either by intravenous injection or by aerosol inhalation, has been widely used to treat workers contaminated by plutonium or a higher actinide. In this report, an attempt is made to assess the toxicities of EDTA and DTPA and to evaluate the effectiveness and safety of DTPA as a drug for removing deposited transuranic elements.

  14. Limits for the burial of the Department of Energy transuranic wastes

    International Nuclear Information System (INIS)

    Potential limits for the shallow earth burial of transuranic elements were examined by simplified models of the individual pathways to man. Pathways examined included transport to surface steams, transport to ground water, intrusion, and people living on the burial ground area after the wastes have surfaced. Limits are derived for each pathway and operational limits are suggested based upon a dose to the organ receiving the maximum dose rate of 0.5 rem/y after 70 years of exposure for the maximum exposed individual

  15. Limits for the burial of the Department of Energy transuranic wastes

    Energy Technology Data Exchange (ETDEWEB)

    Healy, J.W.; Rodgers, J.C.

    1979-01-15

    Potential limits for the shallow earth burial of transuranic elements were examined by simplified models of the individual pathways to man. Pathways examined included transport to surface steams, transport to ground water, intrusion, and people living on the burial ground area after the wastes have surfaced. Limits are derived for each pathway and operational limits are suggested based upon a dose to the organ receiving the maximum dose rate of 0.5 rem/y after 70 years of exposure for the maximum exposed individual.

  16. Understanding the Subsurface Reactive Transport of Transuranic Contaminants at DOE Sites

    Energy Technology Data Exchange (ETDEWEB)

    Barnett, Mark O. [Auburn University; Albrecht-Schmitt, Thomas E. [University of Notre Dame; Saiers, James E. [Yale University; Shuh, David K. [Lawrence Berkeley National Laboratory

    2013-12-20

    Our primary hypothesis is that actinides can interact with surfaces in fundamentally different ways than other metals, metalloids, and oxyanions and that this fundamental difference requires new approaches to studying and modeling transuranic sorption to minerals and geomedia. This project supports a key mission of the SBR program to develop sufficient scientific understanding such that DOE sites will be able to incorporate coupled physical, chemical, and biological processes into decision making for environmental management and long-term stewardship, while also supporting DOE’s commitment to education, training, and collaboration with DOE user facilities.

  17. Draft Title 40 CFR 191 compliance certification application for the Waste Isolation Pilot Plant. Volume 1

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-03-31

    The Waste Isolation Pilot Plant (WIPP) is a research and development facility for the demonstration of the permanent isolation of transuranic radioactive wastes in a geologic formation. The facility was constructed in southeastern New Mexico in a manner intended to meet criteria established by the scientific and regulatory community for the safe, long-term disposal of transuranic wastes. The US Department of Energy (DOE) is preparing an application to demonstrate compliance with the requirements outlined in Title 40, Part 191 of the Code of Federal Regulations (CFR) for the permanent disposal of transuranic wastes. As mandated by the Waste Isolation Pilot Plant (WIPP) Land Withdrawal Act of 1992, the US Environmental Protection Agency (EPA) must evaluate this compliance application and provide a determination regarding compliance with the requirements within one year of receiving a complete application. Because the WIPP is a very complex program, the DOE has planned to submit the application as a draft in two parts. This strategy will allow for the DOE and the EPA to begin technical discussions on critical WIPP issues before the one-year compliance determination period begins. This report is the first of these two draft submittals.

  18. Draft Title 40 CFR 191 compliance certification application for the Waste Isolation Pilot Plant. Volume 1

    International Nuclear Information System (INIS)

    The Waste Isolation Pilot Plant (WIPP) is a research and development facility for the demonstration of the permanent isolation of transuranic radioactive wastes in a geologic formation. The facility was constructed in southeastern New Mexico in a manner intended to meet criteria established by the scientific and regulatory community for the safe, long-term disposal of transuranic wastes. The US Department of Energy (DOE) is preparing an application to demonstrate compliance with the requirements outlined in Title 40, Part 191 of the Code of Federal Regulations (CFR) for the permanent disposal of transuranic wastes. As mandated by the Waste Isolation Pilot Plant (WIPP) Land Withdrawal Act of 1992, the US Environmental Protection Agency (EPA) must evaluate this compliance application and provide a determination regarding compliance with the requirements within one year of receiving a complete application. Because the WIPP is a very complex program, the DOE has planned to submit the application as a draft in two parts. This strategy will allow for the DOE and the EPA to begin technical discussions on critical WIPP issues before the one-year compliance determination period begins. This report is the first of these two draft submittals

  19. Radioactive wastes. Storage time significantly reducing. Long-living transuranic elements are transmuted under neutron irradiation; Radioaktive Abfaelle. Lagerzeiten deutlich verkuerzen. Langlebige Transurane wandeln sich unter Neutronen-Beschuss um

    Energy Technology Data Exchange (ETDEWEB)

    Podlech, Holger [Frankfurt Univ., Frankfurt am Main (Germany). Inst. fuer Angewandte Physik

    2011-07-01

    Worldwide no licensed final repository for radioactive waste exists but continuously new radioactive waste amounts are produced. Transmutation of transuranic elements using neutron irradiation might be a solution into isotopes with short half-life. Since transuranic elements are only a very small percentage of the whole radioactive waste, chemical separation processes are necessary to isolate these elements. The design of the transmutation facility MYRRHA is described. A proton accelerator delivers the proton beam into a subcritical reactor - the developing neutrons transmute the radioactive waste by fission and neutron capture into short-living isotopes. The institute for applied physics in Frankfurt has developed the 17-MeV-injector for MYRRHA.

  20. Statistical sampling plan for the TRU waste assay facility

    International Nuclear Information System (INIS)

    Due to limited space, there is a need to dispose appropriately of the Oak Ridge National Laboratory transuranic waste which is presently stored below ground in 55-gal (208-l) drums within weather-resistant structures. Waste containing less than 100 nCi/g transuranics can be removed from the present storage and be buried, while waste containing greater than 100 nCi/g transuranics must continue to be retrievably stored. To make the necessary measurements needed to determine the drums that can be buried, a transuranic Neutron Interrogation Assay System (NIAS) has been developed at Los Alamos National Laboratory and can make the needed measurements much faster than previous techniques which involved γ-ray spectroscopy. The previous techniques are reliable but time consuming. Therefore, a validation study has been planned to determine the ability of the NIAS to make adequate measurements. The validation of the NIAS will be based on a paired comparison of a sample of measurements made by the previous techniques and the NIAS. The purpose of this report is to describe the proposed sampling plan and the statistical analyses needed to validate the NIAS. 5 references, 4 figures, 5 tables

  1. 42 CFR 424.16 - Timing of certification for individual admitted to a hospital before entitlement to Medicare...

    Science.gov (United States)

    2010-10-01

    ... a hospital before entitlement to Medicare benefits. 424.16 Section 424.16 Public Health CENTERS FOR MEDICARE & MEDICAID SERVICES, DEPARTMENT OF HEALTH AND HUMAN SERVICES (CONTINUED) MEDICARE PROGRAM CONDITIONS FOR MEDICARE PAYMENT Certification and Plan Requirements § 424.16 Timing of certification...

  2. In situ vitrification of transuranic wastes: An updated systems evaluation and applications assessment

    International Nuclear Information System (INIS)

    In situ vitrification (ISV) is a process whereby joule heating immobilizes contaminated soil in place into a durable glass and crystalline waste form. Numerous technological advances made during the past three years in the design, fabrication, and testing of the ISV process are discussed. Performance analysis of ISV focuses on process equipment, element retention (in the vitrified soil during processing), melt geometry, depth monitors, and electrodes. The types of soil and waste processed by ISV are evaluated as process parameters. Economic data provide the production costs of the large-scale unit for radioactive and hazardous chemical wastes (wet and dry). The processing of transuranic-contaminated soils are discussed with respect to occupational and public safety. Alternative applications and operating sequences for various waste sites are identified. The technological data base warrants conducting a large-scale radioactive test at a contaminated soil site at Hanford to provide a representative waste form that can be evaluated to determine its suitability for in-place stabilization of transuranic-contaminated soils

  3. Study of the land to sea transport of transuranic elements. Application to the Palomares Accident (Almeria 1966)

    International Nuclear Information System (INIS)

    The work presents a study on the land to sea transport of transuranic elements applied to a precise scenery at southern coast of Spain: the Palomares ecosystem, where in 1966 an accidental release of transuranics occurred (an USAF b-52 carrying four thermonuclear bombs). The study has been focused on the depositional history recorded in sediments from different sea depths. The experimental basis has been the measurement of Pu, Am, radiocaesium, and natural radionuclides in marine sediments from the referred zone, that involved the setting up of high sensitivity alpha and gamma spectrometry systems; the chronology of sediment was established by applying the CRS model to unsupported Pb-210 profiles. (author)

  4. Upgrade and Certification of the Los Alamos National Laboratory SHENC 2011 - 12270

    International Nuclear Information System (INIS)

    Nondestructive assay measurements of Transuranic (TRU) waste at Los Alamos National Laboratory (LANL) required the addition of a standard waste box (SWB) assay system. A Super High Efficiency Neutron Counter (SHENC) located at Hanford was identified to be relocated to LANL. After careful evaluation of waste streams at LANL, it was determined that the current configuration of the SHENC was not sufficient to quantify certain waste streams. At LANL, there is still a large amount of waste that needs to be retrieved and repackaged within SWB's to meet agreements with the State of New Mexico. Prior to relocating the SHENC, the only assay systems available were High Efficiency Neutron Counters having only a 55-gallon drum capacity. Further analyses indicated that the SHENC system should be capable of quantitative gamma measurements that are to be linked, and combined, with the neutron measurements. The SHENC system was therefore augmented with a new high-resolution gamma spectroscopy system using BE5030 detectors and upgraded gamma electronics. The neutron side of the system was also upgraded with an advanced shift register (JSR-15), an improved Programmable Logic Controller and NDA-2000 software. This report will include calibration of both the neutron and gamma modalities of the SHENC system and how the modality results are combined to produce a single assay result. Preliminary performance results will be discussed based on both mock and real waste measurements. Discussions will also include a complete description of the adjustable parameters as well as the calibration plan, techniques and validations including calibration confirmation based on the Waste Isolation Pilot Plant Waste Acceptance Criteria (WIPP-WAC). The SHENC was successfully upgraded to efficiently measure the complex waste streams at Los Alamos National Laboratory. A new PLC was successfully added to the system for Add-A-Source control. A new shift register was added to the SHENC (JSR-15) which provides

  5. ACCELERATING HANFORD TRANSURANC (TRU) WASTE CERTIFICATION and SHIPMENT FROM 2 PER YEAR TO 12 PER MONTH

    International Nuclear Information System (INIS)

    storage building to provide sufficient space for the required temperature residence time; installing filter and sample ports in the drums using a pneumatic dart method; improving gas analysis time using cryofocusing technology and using both onsite and offsite labs for redundancy of analysis capability. The need for real-time radiography was reduced by implementing avisual examination technique as the waste was being packaged. Key to implementing the visual examination technique was the use of a ''portable procedure'' that can be used anywhere on the Hanford Site. This approach has been used successfully for packaging newly generated waste from various decontamination and decommissioning projects. Using a glovebox for repackaging drums has also been a rate-limiting step in accelerating the characterization of TRU waste at Hanford. The impacts of this requirement, however, have been minimized in two ways: first, by venting certain heat-sealed bags, and second, by implementing hydrogen and methane testing of headspace gas for high gram drums with multiple layers of confinement. The details of these specific efforts are included in a separate paper. Payload assembly and loading efficiencies of the TRUPACT-II, and certification and shipment efficiencies were instrumental to Hanford's successfully accelerating shipments. Loading time of TRUPACT II's for a shipment (three TRUPACTS per shipment) went from four days to two days. Future acceleration plans include certification of a box radioassay unit to assay TRU standard waste boxes (SWB) for shipment to WIPP and adding additional payload building/loadout stations to increase the shipping capabilities

  6. Renewable Energy Certificate Program

    Energy Technology Data Exchange (ETDEWEB)

    Gwendolyn S. Andersen

    2012-07-17

    This project was primarily to develop and implement a curriculum which will train undergraduate and graduate students at the University seeking a degree as well as training for enrollees in a special certification program to prepare individuals to be employed in a broad range of occupations in the field of renewable energy and energy conservation. Curriculum development was by teams of Saint Francis University Faculty in the Business Administration and Science Departments and industry experts. Students seeking undergraduate and graduate degrees are able to enroll in courses offered within these departments which will combine theory and hands-on training in the various elements of wind power development. For example, the business department curriculum areas include economic modeling, finance, contracting, etc. The science areas include meteorology, energy conversion and projection, species identification, habitat protection, field data collection and analysis, etc.

  7. 10 CFR 76.91 - Emergency planning.

    Science.gov (United States)

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false Emergency planning. 76.91 Section 76.91 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) CERTIFICATION OF GASEOUS DIFFUSION PLANTS Safety § 76.91 Emergency planning... Emergency Planning and Community Right-to-Know Act of 1986, Title III, Public Law 99-499, or other State...

  8. 47 CFR 54.508 - Technology plans.

    Science.gov (United States)

    2010-10-01

    ... that the Department of Education adopts future technology plan requirements that require one or more of... covered by the future Department of Education technology plan requirements. (c) Timing of certification... 47 Telecommunication 3 2010-10-01 2010-10-01 false Technology plans. 54.508 Section...

  9. Sampling and Analysis of Rare Gas Isotopes for In Situ Delineation of Buried Transuranic and Tritium Waste

    Energy Technology Data Exchange (ETDEWEB)

    Dresel, P. Evan; Olsen, Khris B.; Hayes, James C.; McIntyre, Justin I.; Waichler, Scott R.

    2006-02-26

    This paper describes soil-gas sampling for the rare gases helium and xenon that can be used to define the locations of tritium and transuranic waste. Soil-gas sampling is a minimally invasive technique, in that direct penetration of the waste is not required and no hazardous material is brought to the surface.

  10. Framework for Certification of Fish Propagation, Protection and Monitoring Facilities. Final Report.

    Energy Technology Data Exchange (ETDEWEB)

    Carlson, Thomas J.; Costello, Ronald J.

    1997-06-01

    A conceptual framework for certification of fish production and monitoring facilities including software templates to expedite implementation of the framework are presented. The framework is based on well established and widely utilized project management techniques. The implementation templates are overlays for Microsoft Professional Office software products: Excel, Word, and Project. Use of the software templates requires Microsoft Professional Office. The certification framework integrates two classical project management processes with a third process for facility certification. These processes are: (1) organization and definition of the project, (2) acquisition and organization of project documentation, and (3) facility certification. The certification process consists of systematic review of the production processes and the characteristics of the produced product. The criteria for certification review are the plans and specifications for the products and production processes that guided development of the facility. The facility is certified when the production processes are operating as designed and the product produced meets specifications. Within this framework, certification is a performance based process, not dissimilar from that practiced in many professions and required for many process, or a product meets professional/industry standards of performance. In the case of fish production facilities, the certifying authority may be diffuse, consisting of many entities acting through a process such as NEPA. A cornerstone of certification is accountability, over the long term, for the operation and products of a facility. This is particularly important for fish production facilities where the overall goal of the facility may require decades to accomplish.

  11. Board Certification: The Global Perspective.

    Science.gov (United States)

    Day, Susan H

    2016-09-01

    This article reviews globalization of quality standards in medicine, with emphasis on accreditation and certification. In conjunction with the 100th anniversary of the American Board of Ophthalmology, the author explores globalization movements, standards of quality, expectations of others seeking certification, the American Board of Medical Specialties (ABMS) International, interrelationships with the ABMS, and considerations both pragmatic and philosophical in addressing globalization of standards. PMID:27550006

  12. Analysis of a Building Energy Efficiency Certification System in Korea

    Directory of Open Access Journals (Sweden)

    Duk Joon Park

    2015-12-01

    Full Text Available The Korean government has established a national plan for the promotion of zero energy buildings to respond to climate change and energy crises. To achieve this plan, several energy efficiency policies for new and existing buildings have been developed. The Building Energy Efficiency Certification System (BEECS aims to promote the spread of high energy-efficient buildings by evaluating and certifying building energy performance. This study discussed Korean building energy efficiency policies and analyzed especially the influence of the BEECS on the actual energy consumption of a residential building and calculated energy performance of non-residential buildings. The BEECS was evaluated to have influence on gas and district heating consumption in residential buildings. For non-residential buildings, a decreasing trend was shown in calculated primary energy consumption in the years since the BEECS has been enacted. Appropriate improvements of the certification system were also discussed by analyzing relationship between building characteristics and their energy consumptions.

  13. Evaluation of alternatives for high-level and transuranic radioactive- waste disposal standards

    International Nuclear Information System (INIS)

    The remand of the US Environmental Protection Agency's long-term performance standards for radioactive-waste disposal provides an opportunity to suggest modifications that would make the regulation more defensible and remove inconsistencies yet retain the basic structure of the original rule. Proposed modifications are in three specific areas: release and dose limits, probabilistic containment requirements, and transuranic-waste disposal criteria. Examination of the modifications includes discussion of the alternatives, demonstration of methods of development and implementation, comparison of the characteristics, attributes, and deficiencies of possible options within each area, and analysis of the implications for performance assessments. An additional consideration is the impact on the entire regulation when developing or modifying the individual components of the radiological standards

  14. Removing transuranic waste from water: The TRU/Clear process system

    International Nuclear Information System (INIS)

    A major advance toward solving some of the most intractable problems of environmental cleanup is the TRU/Clear Process System invented by a team of researchers at the Los Alamos National Laboratory (LANL). This process was developed to extract and remove the final trace amounts of the radioactive elements called transuranic (TRU) elements from wastewater streams produced by nuclear facilities. The system, which is completely compatible with existing wastewater treatment technologies, is potentially capable of removing other toxic heavy metals, such as arsenic, mercury, and cadmium, as well as hazardous organic contaminants from wastewater. Future users of the LANL system might include electronics manufacturers and chemical production plants as well as the nuclear industry. The process defines a new chemistry and chemical technology for wastewater treatment that makes a near-zero discharge of pollutants feasible in the near future, while reducing overall waste management costs

  15. Identification of the fast and thermal neutron characteristics of transuranic waste drums

    Energy Technology Data Exchange (ETDEWEB)

    Storm, B.H. Jr.; Bramblett, R.L. [Lockheed Martin Specialty Components, Largo, FL (United States); Hensley, C. [Oak Ridge National Lab., TN (United States)

    1997-11-01

    Fissile and spontaneously fissioning material in transuranic waste drums can be most sensitively assayed using an active and passive neutron assay system such as the Active Passive Neutron Examination and Assay. Both the active and the passive assays are distorted by the presence of the waste matrix and containerization. For accurate assaying, this distortion must be characterized and accounted for. An External Matrix Probe technique has been developed that accomplishes this task. Correlations between in-drum neutron flux measurements and monitors in the Active Passive Neutron Examination and Assay chamber with various matrix materials provide a non-invasive means of predicting the thermal neutron flux in waste drums. Similarly, measures of the transmission of fast neutrons emitted from sources in the drum. Results obtained using the Lockheed Martin Specialty Components Active Passive Neutron Examination and Assay system are discussed. 12 figs., 1 tab.

  16. Maria Goeppert Mayer's Theoretical Work on Rare-Earth and Transuranic Elements

    CERN Document Server

    Wang, Frank Y

    2008-01-01

    After the discovery of element 93 neptunium by Edwin McMillan and Philip H. Abelson in 1941, Maria Goeppert Mayer applied the Thomas-Fermi model to calculate the electronic configuration of heavy elements and predicted the occurrence of a second rare-earth series in the vicinity of elements 91 or 92 extending to the transuranic elements. Mayer was motivated by Enrico Fermi, who was at the time contemplating military uses of nuclear energy. Historical development of nuclear science research leading to Mayer's publication is outlined. Mayer's method is introduced with the aid of a computer, which enables students to visualize her description of eigenfunctions, particularly the sudden change of spatial distribution and eigenenergy at the beginning of the rare-earth series. The impact of Mayer's work on the periodic table is discussed.

  17. Layer thickness evaluation for transuranic transmutation in a fusion–fission system

    International Nuclear Information System (INIS)

    Highlights: • Layer thickness for transmutation in a fusion–fission system was evaluated. • The calculations were performed using MONTEBURNS code. • The results indicate the best thickness and volume ratio to induce transmutation. - Abstract: Layer thickness for transuranic transmutation in a fusion–fission system was evaluated using two different ways. In the first one, transmutation layer thicknesses were designed maintaining the fuel rod radius constant; in the second part, while the transmutation layer thickness increases, the fuel rod radius decreases maintaining ks (source-multiplication factor) ≈0.95. Spent fuel reprocessed by UREX+ method and then spiked with thorium and uranium composes the transmutation layer. The calculations were performed using MONTEBURNS code (MCNP5 and ORIGEN 2.1). The results indicate the best thickness and the volume ratio between the coolant and the fuel composition to induce transmutation

  18. Process Knowledge Summary Report for Materials and Fuels Complex Contact-Handled Transuranic Debris Waste

    Energy Technology Data Exchange (ETDEWEB)

    R. P. Grant; P. J. Crane; S. Butler; M. A. Henry

    2010-02-01

    This Process Knowledge Summary Report summarizes the information collected to satisfy the transportation and waste acceptance requirements for the transfer of transuranic (TRU) waste between the Materials and Fuels Complex (MFC) and the Advanced Mixed Waste Treatment Project (AMWTP). The information collected includes documentation that addresses the requirements for AMWTP and the applicable portion of their Resource Conservation and Recovery Act permits for receipt and treatment of TRU debris waste in AMWTP. This report has been prepared for contact-handled TRU debris waste generated by the Idaho National Laboratory at MFC. The TRU debris waste will be shipped to AMWTP for purposes of supercompaction. This Process Knowledge Summary Report includes information regarding, but not limited to, the generation process, the physical form, radiological characteristics, and chemical contaminants of the TRU debris waste, prohibited items, and packaging configuration. This report, along with the referenced supporting documents, will create a defensible and auditable record for waste originating from MFC.

  19. The utilization of freeze-cast scaffolds for burning transuranic elements in SMRS

    Energy Technology Data Exchange (ETDEWEB)

    Fernandes, Ana C.A.A.; Maiorino, Jose R., E-mail: ana.fernandes@ufabc.edu.br, E-mail: joserubens.maiorino@ufabc.edu.br [Universidade Federal do ABC (UFABC), Santo Andre, SP (Brazil). Centro de Engenharia, Modelagem e Ciencias Sociais Aplicadas; Lang, Amanda L., E-mail: amandaleelang@gmail.com [Department of Engineering Physics, University of Wisconsin Madison, Madison, WI (United States)

    2015-07-01

    This work aimed at investigating the viability of burning transuranic elements in SMRs, using the IRIS model as a basis, including freeze-cast sc olds in the fuel pins. The IRIS reactor is an integral design reactor, having all of its primary components inside the pressure vessel, assuring unique characteristics regarding economy, safety and non-proliferation. Freeze-cast scaffolds are strong solid structures, built in a process of freezing powder material. When applied to the fuel pins, they allow a precise placement of different materials. Am-241 is a representative of the transuranic elements with high cross section values in the thermal spectrum, presenting itself as a great candidate for this application. Two models were compared: the Am model, having two types of fuel - the americium alloy and UO{sub 2} -, and a reference model, with the freeze-cast structures but only uranium as a fuel. Through the utilization of the package MCNP5, it was possible to obtain and analyze: (I) k{sub eff} values, (II) axial and radial flux proles, (III) maximum fuel temperature and (IV) power peaking factors. It was possible to observe that the k{sub eff} values, even though higher than 1, are considered small in both models when compared to PWRs in beginning of life, compromising the fuel life, and showing a tendency of neutron absorption by the ceramic scaffolds. The values were even lower for the Am model, confirming the suspicion that americium would be a great neutron absorber due to the resonances observed in the cross section. However, shutdown margin was achieved in both models, both in hot and cold conditions. The flux profiles showed consistency, showing a visible flattening in the radial flux profile for the Am model. The power peaking factors are close to those of a typical PWR, and fuel maximum temperature also showed satisfying numbers. (author)

  20. Certification of training

    Science.gov (United States)

    Gibson, Richard S.

    1994-01-01

    Training has been around as an informal process for countless years. Most higher order animals require some level of training in hunting, social skills, or other survival related skills to continue their existence beyond early infancy. Much of the training is accomplished through imitation, trial and error, and good luck. In some ways the essentials of training in aviation have not deviated from this original formula a great deal. One of the major changes in aviation and other technical areas is that more complex response chains based on a broader base of knowledge are now required. 'To certify' means many things according to the American Heritage dictionary of the English Language. These meanings range from 'to guarantee as meeting a standard' to 'to declare legally insane'. For this discussion, we will use the definition 'an action taken by some authoritative body that essentially guarantees that the instruction meets some defined standard'. In order to make this certification, the responsible body subjects the educational process, training, training device, or simulator to some type of examination to determine its adequacy or validity.

  1. Ecotourism certification and its progress in China

    Institute of Scientific and Technical Information of China (English)

    2007-01-01

    Since the middle 1990s, ecotourism certification has been given more and more attention to around the world.As a developing country with abundant ecotourism products, it is necessaryfor China to adopt certification to ensure sustainable development of ecotourism. But there are few products certificated until now in China. After reviewing the trend of ecotourism certification in the world and summarizing its theory and method, this paper analyzes the progress and prospect of ecotourism certification in China, and concludes that certification in China is necessary and promising.

  2. IN-SITU ASSAY OF TRANSURANIC RADIONUCLIDES IN THE VADOSE ZONE USING HIGH-RESOLUTION SPECTRAL GAMMA LOGGING - A HANFORD CASE STUDY

    Energy Technology Data Exchange (ETDEWEB)

    ROHAY VJ; HENWOOD P; MCCAIN R

    2009-11-30

    High-resolution spectral gamma logging in steel-cased boreholes is used to detect and quantify transuranic radionuclides in the subsurface. Pu-239, Pu-241, Am-241, and Np-237 are identified based on characteristic decay gammas. Typical minimum detectable levels are on the order of 20 to 40 nCi/g. In intervals of high transuranic concentrations, gamma rays from other sources may complicate analysis and interpretation. Gamma rays detected in the borehole may originate from three sources: decay of the parent transuranic radionuclide or a daughter; alpha interactions; and interactions with neutrons resulting from either spontaneous fission or alpha particle interactions.

  3. Unvented Drum Handling Plan

    International Nuclear Information System (INIS)

    This drum-handling plan proposes a method to deal with unvented transuranic drums encountered during retrieval of drums. Finding unvented drums during retrieval activities was expected, as identified in the Transuranic (TRU) Phase I Retrieval Plan (HNF-4781). However, significant numbers of unvented drums were not expected until excavation of buried drums began. This plan represents accelerated planning for management of unvented drums. A plan is proposed that manages unvented drums differently based on three categories. The first category of drums is any that visually appear to be pressurized. These will be vented immediately, using either the Hanford Fire Department Hazardous Materials (Haz. Mat.) team, if such are encountered before the facilities' capabilities are established, or using internal capabilities, once established. To date, no drums have been retrieved that showed signs of pressurization. The second category consists of drums that contain a minimal amount of Pu isotopes. This minimal amount is typically less than 1 gram of Pu, but may be waste-stream dependent. Drums in this category are assayed to determine if they are low-level waste (LLW). LLW drums are typically disposed of without venting. Any unvented drums that assay as TRU will be staged for a future venting campaign, using appropriate safety precautions in their handling. The third category of drums is those for which records show larger amounts of Pu isotopes (typically greater than or equal to 1 gram of Pu). These are assumed to be TRU and are not assayed at this point, but are staged for a future venting campaign. Any of these drums that do not have a visible venting device will be staged awaiting venting, and will be managed under appropriate controls, including covering the drums to protect from direct solar exposure, minimizing of container movement, and placement of a barrier to restrict vehicle access. There are a number of equipment options available to perform the venting. The

  4. "The Buffett Plan for Reducing the Trade Deficit"

    OpenAIRE

    Papadimitriou, Dimitri B.; Hannsgen, Greg; Zezza, Gennaro

    2008-01-01

    This paper considers a plan proposed by Warren Buffett, in which importers would be required to obtain certificates proportional to the amount of non-oil goods (and possibly also services) they brought into the country. These certificates would be granted to firms that exported goods. Exporting firms could then sell certificates to importing firms on an organized market. In this paper, starting from a relatively neutral projection of all major variables for the U.S. economy, we estimate that ...

  5. AutoCAD 2014 review for certification official certification preparation

    CERN Document Server

    ASCENT center for technical knowledge

    2014-01-01

    The AutoCAD® 2014 Review for Certification book is intended for users of AutoCAD® preparing to complete the AutoCAD 2014 Certified Professional exam. This book contains a collection of relevant instructional topics, practice exercises, and review questions from the Autodesk Official Training Guides (AOTG) from ASCENT - Center for Technical Knowledge pertaining specifically to the Certified Professional exam topics and objectives. This book is intended for experienced users of AutoCAD in preparation for certification. New users of AutoCAD should refer to the AOTG training guides from ASCENT, such as AutoCAD/AutoCAD LT 2014 Fundamentals, for more comprehensive instruction.

  6. Demographic implications of the New United States certificates.

    Science.gov (United States)

    Lunde, A S; Grove, R D

    1966-06-01

    To assist in developing uniform reporting of vital events among the fifty states, Puerto Rico, and the Virgin Islands, the United States government prepares standard certificates of birth, fetal death, death, marriage, and divorce. These model forms are revised, with the assistance of the states, approximately every ten years. Revisions are now being prepared by the National Center for Health Statistics which will become effective beginning January 1, 1968. Important new source material for demography will be introduced.Most changes will appear in the Standard Certificate of Live Birth and in the Standard Certificate of Fetal Death. An item on education of father and mother will provide detailed national data on education and fertility. The date of the last live birth to the mother and the date of the last fetal death will provide information on previous pregnancy outcome and on child-spacing. The recording of state file numbers for mates born alive and dead in the same delivery will make it easier to match live birth and fetal death certificates for the preparation of detailed tabulations on multiple births. Several new items related to maternal and child health have also been added. No significent changes were planned for the Standard Certificate of Death.The Standard Certificate of Marriage will include as new items the education of the bride and groom, the date on which the last marriage, if any, ended, and specification of the officiant as a religious or civil official. The Standard Certificate of Divorce or Annulment will obtain information on the education of husband and wife, the approximate date on which the couple separated, the mode of dissolution of the previous marriage, and the total number of living children. It is anticipated that most of the new items will be included in the certificates of all the states. The National Center for Health Statistics will provide detailed tabulations related to these items, beginning with data year 1968.Demographers

  7. Performance Assessment in Support of the 1996 Compliance Certification Application for the Waste Isolation Pilot Plant

    Energy Technology Data Exchange (ETDEWEB)

    Anderson, D.R.; Basabilvazo, G.; Helton, J.C.; Jow, H.-N.; Marietta, M.G.

    1998-10-14

    The conceptual and computational structure of a performance assessment (PA) for the Waste Isolation Pilot Plant (WIPP) is described. Important parts of thk structure are @ maintenance of a separation between stochastic (i.e., aleatory) and subjective (i.e., epistemic) uncertain, with stochastic uncefinty arising from the many possible disruptions that could occur over the 10,000 Y regulatory period fiat applies to the WIPP and subjective uncertainty arising from `the imprecision with which many of the quantities rquired in tie `hdysis are known, (ii) use of Latin hypercttbe sampling to incorporate the effects of subjective uncefirtty, (iii) use of Monte Carlo (i.e., random) sampling to incorporate the effects of stochastic uncetinty, and OV) efficient use of tie necessarily limited number of mechanistic calculations that can be performed to SUPPOII the analysis. The WIPP is under development by the U.S. Department of Ener~ (DOE) for the geologic (i.e., deep underground) disposal of transuranic (TRU) waste, with the indicated PA supporting a ~Compliance Certification Application (CCA) by the DOE to the U.S. Environmental Protection Agency (EPA) in October 1996 for tie necessary certifications for the WIPP to begin operation. If certified, the WIPP will be the first operational faciliv in tie United States for the geologic disposal of ra&oactive waste.

  8. 7 CFR 205.404 - Granting certification.

    Science.gov (United States)

    2010-01-01

    ... Agriculture Regulations of the Department of Agriculture (Continued) AGRICULTURAL MARKETING SERVICE (Standards, Inspections, Marketing Practices), DEPARTMENT OF AGRICULTURE (CONTINUED) ORGANIC FOODS PRODUCTION ACT PROVISIONS NATIONAL ORGANIC PROGRAM Certification § 205.404 Granting certification. (a) Within a...

  9. The pursuit of Leadership in Energy and Environmental Design (LEED) certification for campus housing at public universities

    Science.gov (United States)

    Konvalinka, April Hicks

    This dissertation identifies the reasons why institutions of higher education pursue Leadership in Energy and Environmental Design (LEED) certification for new construction of campus housing. The research was guided by three questions: 1. Why did the institution choose to pursue LEED certification for campus housing? 2. What considerations should be made in the design, development, and planning process of a LEED residence hall? 3. What significant impact has the LEED residence hall made on campus? The outcomes of this study will provide insight to university and housing administrators who are considering pursuit of LEED certification for new residence hall development. The primary sources of data are chief housing officers or their designees at public four-year colleges and universities with new campus housing awarded LEED certification. Qualitative research techniques were used to conduct interviews by LEED certification level: Platinum, Silver, Gold, and Certified. Data collection ended when data saturation of each question in each certification level was achieved. This dissertation offers reasons why universities pursue LEED certification: state requirement, institutional commitment, institutional standard, environmental stewardship, departmental decision, and student interest. Additionally, considerations and lessons learned from the pursuit of LEED certification have been identified and can serve as a guide to housing administrators who aim to achieve any LEED level certification.

  10. Quality certificates for homeopathic matrices

    Directory of Open Access Journals (Sweden)

    Amarilys de Toledo Cesar

    2011-09-01

    Full Text Available Background: To produce homeopathic medicines, pharmacies need raw materials (mother tinctures and diluted-agitated solutions, named “matrices”, provided by insumes suppliers. The “matrices” are ultra high dilutions and can not be tested against Analysis Reports. Aims: to propose alternatives to the matrices Analysis Report; to contribute to the quality of homeopathic medicines and treatment. Method: search of information present in the documentation provided from 2 national and 3 European suppliers in order to develop criteria. Discussion: the needed concepts for compliance with the orders throughout their production process were presented. The control of information involved in the process allows to trace the production of matrices, providing an indication of the quality with which they were obtained. Each supplier gives different approach to issuing a document, calling it Certificate of Conformity Protocol Preparation, Manufacturing Certificate or Quality Certificate. Summarizing, it is a supplier's declaration, which involves the quality control of raw materials, packaging materials and of the process used, but not a report that enables customers to repeat the analysis. A model was proposed for a Certificate of Quality, with the minimum information needed to indicate to the pharmacies that there is a control of the process. This certificate shall contain statements about the process. Conclusion: Quality Certificate seems to be the best document to ensure the pharmacy that the matrix obtained presents characteristics compatible with the preparation of a quality homeopathic medicine.

  11. Cycling of transuranic radionuclides in the Columbia River, its estuary and the northeast Pacific Ocean. Progress report, January-December 1982

    International Nuclear Information System (INIS)

    This report summarizes progress from 1 January 1982 through 31 December 1982 in research on the behavior of transuranic and other radionuclides in the Columbia River downstream from the Hanford Reservation and in the northeast Pacific Ocean

  12. Certificate Transparency in Theory and Practice

    OpenAIRE

    Gustafsson, Josef

    2016-01-01

    Certificate Transparency provides auditability to the widely used X.509 Public Key Infrastructure (PKIX) authentication in Transport Layer Security (TLS) protocol. Transparency logs issue signed promises of inclusions to be used together with certificates for authentication of TLS servers. Google Chrome enforces the use of Certificate Transparency for validation of Extended Validation (EV) certificates. This thesis proposes a methodology for asserting correct operation and presents a survey o...

  13. IMPROVEMENTS IN CONTAINER MANAGEMENT OF TRANSURANIC (TRU) AND LOW LEVEL RADIOACTIVE WASTE STORED AT THE CENTRAL WASTE COMPLEX (CWC) AT HANFORD

    Energy Technology Data Exchange (ETDEWEB)

    UYTIOCO EM

    2007-11-14

    The Central Waste Complex (CWC) is the interim storage facility for Resource Conservation & Recovery Act (RCRA) mixed waste, transuranic waste, transuranic mixed waste, low-level and low-level mixed radioactive waste at the Department of Energy's (DOE'S) Hanford Site. The majority of the waste stored at the facility is retrieved from the low-level burial grounds in the 200 West Area at the Site, with minor quantities of newly generated waste from on-site and off-site waste generators. The CWC comprises 18 storage buildings that house 13,000 containers. Each waste container within the facility is scanned into its location by building, module, tier and position and the information is stored in a site-wide database. As waste is retrieved from the burial grounds, a preliminary non-destructive assay is performed to determine if the waste is transuranic (TRU) or low-level waste (LLW) and subsequently shipped to the CWC. In general, the TRU and LLW waste containers are stored in separate locations within the CWC, but the final disposition of each waste container is not known upon receipt. The final disposition of each waste container is determined by the appropriate program as process knowledge is applied and characterization data becomes available. Waste containers are stored within the CWC based on their physical chemical and radiological hazards. Further segregation within each building is done by container size (55-gallon, 85-gallon, Standard Waste Box) and waste stream. Due to this waste storage scheme, assembling waste containers for shipment out of the CWC has been time consuming and labor intensive. Qualitatively, the ratio of containers moved to containers in the outgoing shipment has been excessively high, which correlates to additional worker exposure, shipment delays, and operational inefficiencies. These inefficiencies impacted the LLW Program's ability to meet commitments established by the Tri-Party Agreement, an agreement between the State

  14. Certification of ICTs in Elections

    DEFF Research Database (Denmark)

    Schürmann, Carsten; Barrat, Jordi; Bolo, Eden;

    2015-01-01

    Information and communication technologies play a critical role in the administration and organization of modern elections. Any breakdown of an election technology, security breach or programming error can incur tremendous cost for the electoral management body (EMB)—and may undermine voters’ trust...... voting or tabulation systems. The key elements of quality control are certification and evaluation. Certification refers to the confirmation proof of compliance with a given standard. Evaluation is the most labour intensive part of the quality control process during which the requirements, designs...

  15. Open source systems security certification

    CERN Document Server

    Damiani, Ernesto; El Ioini, Nabil

    2009-01-01

    Open Source Advances in Computer Applications book series provides timely technological and business information for: Enabling Open Source Systems (OSS) to become an integral part of systems and devices produced by technology companies; Inserting OSS in the critical path of complex network development and embedded products, including methodologies and tools for domain-specific OSS testing (lab code available), plus certification of security, dependability and safety properties for complex systems; Ensuring integrated systems, including OSS, meet performance and security requirements as well as achieving the necessary certifications, according to the overall strategy of OSS usage on the part of the adopter

  16. 28 CFR 26.23 - Certification process.

    Science.gov (United States)

    2010-07-01

    ... 28 Judicial Administration 1 2010-07-01 2010-07-01 false Certification process. 26.23 Section 26.23 Judicial Administration DEPARTMENT OF JUSTICE DEATH SENTENCES PROCEDURES Certification Process for State Capital Counsel Systems § 26.23 Certification process. (a) An appropriate state official...

  17. 14 CFR 147.3 - Certificate required.

    Science.gov (United States)

    2010-01-01

    ... 14 Aeronautics and Space 3 2010-01-01 2010-01-01 false Certificate required. 147.3 Section 147.3 Aeronautics and Space FEDERAL AVIATION ADMINISTRATION, DEPARTMENT OF TRANSPORTATION (CONTINUED) SCHOOLS AND OTHER CERTIFICATED AGENCIES AVIATION MAINTENANCE TECHNICIAN SCHOOLS General § 147.3 Certificate...

  18. 40 CFR 86.1848-01 - Certification.

    Science.gov (United States)

    2010-07-01

    ... Complete Otto-Cycle Heavy-Duty Vehicles § 86.1848-01 Certification. (a)(1) If, after a review of the... new motor vehicle covered by the certificate will meet the requirements of the Act and of this part... trucks and incomplete heavy-duty vehicles, a certificate covers only those new motor vehicles which,...

  19. 26 CFR 1.43-3 - Certification

    Science.gov (United States)

    2010-04-01

    ... § 1.43-3 Certification (a) Petroleum engineer's certification of a project—(1) In general. A petroleum... requirements of section 43(c)(2)(A). A petroleum engineer's certification must be submitted for each project. The petroleum engineer certifying a project must be duly registered or certified in any State....

  20. 14 CFR 21.275 - Experimental certificates.

    Science.gov (United States)

    2010-01-01

    ... 14 Aeronautics and Space 1 2010-01-01 2010-01-01 false Experimental certificates. 21.275 Section 21.275 Aeronautics and Space FEDERAL AVIATION ADMINISTRATION, DEPARTMENT OF TRANSPORTATION AIRCRAFT... certificates. (a) The manufacturer shall, before issuing an experimental certificate, obtain from...

  1. T-Rex system for operation in TRU, LLW, and hazardous zones. Transuranic storage area-retrieval enclosure program

    Energy Technology Data Exchange (ETDEWEB)

    Kline, H.M. [EG and G Idaho, Inc., Idaho Falls, ID (United States); Andreychek, T.P.; Beeson, B.K. [Martin Marietta Corp., Baltimore, MD (United States). Aero and Naval Systems

    1993-04-01

    There are a large number of sites around the world containing TRU (transuranic) waste, low level waste (LLW), and hazardous areas that require teleoperated, heavy lift manipulators with long reach and high precision to handle the materials stored there. Teleoperation of the equipment is required to reduce the risk to operating personnel to as-low-as-reasonably-achievable (ALARA) levels. The Transuranic Storage Area Remote Excavator system (T-Rex) is designed to fill this requirement at low cost through the integration of a production front shovel excavator with a control system, local and remote operator control stations, a closed-circuit television system (CCTV), multiple end effectors and a quick-change system. This paper describes the conversion of an off-the-shelf excavator with a hydraulic control system, the integration of an onboard remote control system, vision system, and the design of a remote control station.

  2. Relationship of microbial processes to the fate and behavior of transuranic elements in soils, plants, and animals

    International Nuclear Information System (INIS)

    This review considers the influence of soil physicochemical and microbial processes on the long-term solubility, form, and bioavailability of plutonium and other transuranic elements important in the nuclear fuel cycle. Emphasis is placed on delineation of the relationships between soil chemical and microbial processes and the role of soil microorganisms in effecting solubilization, transformation and plant/animal uptake of elements considered largely insoluble in soils strictly on the basis of their inorganic chemical characteristics

  3. Effects of acquiring FSC forest management certification for Japanese enterprises using SmartWood Audits

    Institute of Scientific and Technical Information of China (English)

    Katsuaki SUGIURA; Takuyuki YOSHIOKA; Kouki INOUE

    2012-01-01

    We explore the organizational,environmental,and economic effects of sustainable forest management (FM) certification by SmartWood (SW),one of the certification bodies accredited by the Forest Stewardship Council (FSC) to carry out certification in Japan.We closely investigated three enterprises:the Yusuhara Forest Owners' Cooperative,Yamanashi Prefectural Forest,and Ryujin-mura Forest Owners' Cooperative.Interviews with representatives of these entities provided crucial empirical information regarding the influence of certification on environmental assessment,rare-species protection,landscape-management planning,management objectives,and forest supervision.Attainment of FM status improved environmental awareness and engendered positive changes in assessing and managing forests and other natural resources but simultaneously imposed heavier economic costs.

  4. AN EXPERIMENTAL PROJECT TO DETERMINE MORE EFFECTIVE VOCATIONAL TEACHER CERTIFICATION PROCEDURES IN MICHIGAN BY COMPETENCY EXAMINATIONS. FINAL REPORT OF PHASE I.

    Science.gov (United States)

    KAZANAS, H.D.; KIEFT, L.D.

    THE PURPOSE OF THIS PROJECT WAS TO DETERMINE MORE EFFECTIVE VOCATIONAL TEACHER CERTIFICATION PROCEDURES IN MICHIGAN WITH PARTICULAR EMPHASIS ON THE DEVELOPMENT OF COMPETENCY EXAMINATIONS FOR USE IN CERTIFICATION OF TRADE AND INDUSTRIAL TEACHERS. STATE PLANS FROM 31 STATES WERE REVIEWED. QUESTIONNAIRES TO STATE DIRECTORS COLLECTED INFORMATION AND…

  5. Trusted Certificates in Quantum Cryptography

    OpenAIRE

    Perkins, William

    2006-01-01

    This paper analyzes the performance of Kak's three stage quantum cryptographic protocol based on public key cryptography against a man-in-the-middle attack. A method for protecting against such an attack is presented using certificates distributed by a trusted third party.

  6. Teacher Certification/Preparation Guidelines.

    Science.gov (United States)

    Kotter, Rita

    1990-01-01

    Presents guidelines for general and theater specialist K-12 teacher certification developed by the American Alliance for Theatre Education and the Speech Communication Association. Advocates that all teachers have preparation in arts and communication and that theater and communication specialists continue to be trained. (SR)

  7. W-026, transuranic waste restricted waste management (TRU RWM) glovebox operational test report

    International Nuclear Information System (INIS)

    The TRU Waste/Restricted Waste Management (LLW/PWNP) Glovebox 401 is designed to accept and process waste from the Transuranic Process Glovebox 302. Waste is transferred to the glovebox via the Drath and Schraeder Bagless Transfer Port (DO-07401) on a transfer stand. The stand is removed with a hoist and the operator inspects the waste (with the aid of the Sampling and Treatment Director) to determine a course of action for each item. The waste is separated into compliant and non compliant. One Trip Port DO-07402A is designated as ''Compliant''and One Trip Port DO-07402B is designated as ''Non Compliant''. As the processing (inspection, bar coding, sampling and treatment) of the transferred items takes place, residue is placed in the appropriate One Trip port. The status of the waste items is tracked by the Data Management System (DMS) via the Plant Control System (PCS) barcode interface. As an item is moved for sampling or storage or it's state altered by treatment, the Operator will track an items location using a portable barcode reader and entry any required data on the DMS console. The Operational Test Procedure (OTP) will perform evolutions (described here) using the Plant Operating Procedures (POP) in order to verify that they are sufficient and accurate for controlled glovebox operation

  8. Consideration of nuclear criticality when disposing of transuranic waste at the Waste Isolation Pilot Plant

    Energy Technology Data Exchange (ETDEWEB)

    RECHARD,ROBERT P.; SANCHEZ,LAWRENCE C.; STOCKMAN,CHRISTINE T.; TRELLUE,HOLLY R.

    2000-04-01

    Based on general arguments presented in this report, nuclear criticality was eliminated from performance assessment calculations for the Waste Isolation Pilot Plant (WIPP), a repository for waste contaminated with transuranic (TRU) radioisotopes, located in southeastern New Mexico. At the WIPP, the probability of criticality within the repository is low because mechanisms to concentrate the fissile radioisotopes dispersed throughout the waste are absent. In addition, following an inadvertent human intrusion into the repository (an event that must be considered because of safety regulations), the probability of nuclear criticality away from the repository is low because (1) the amount of fissile mass transported over 10,000 yr is predicted to be small, (2) often there are insufficient spaces in the advective pore space (e.g., macroscopic fractures) to provide sufficient thickness for precipitation of fissile material, and (3) there is no credible mechanism to counteract the natural tendency of the material to disperse during transport and instead concentrate fissile material in a small enough volume for it to form a critical concentration. Furthermore, before a criticality would have the potential to affect human health after closure of the repository--assuming that a criticality could occur--it would have to either (1) degrade the ability of the disposal system to contain nuclear waste or (2) produce significantly more radioisotopes than originally present. Neither of these situations can occur at the WIPP; thus, the consequences of a criticality are also low.

  9. Development and characterization of basalt-glass ceramics for the immobilization of transuranic wastes

    International Nuclear Information System (INIS)

    Basalt-based waste forms were developed for the immobilization of transuranic (TRU) contaminated wastes. The specific waste studied is a 3:1 blend of process sludge and incinerator ash. Various amounts of TRU blended waste were melted with Pomona basalt powder. The vitreous products were subjected to a variety of heat treatment conditions to form glass ceramics. The total crystallinity of the glass ceramic, ranging from 20 to 45 wt %, was moderately dependent on composition and heat treatment conditions. Three parent glasses and four glass ceramics with varied composition and heat treatment were produced for detailed phase characterization and leaching. Both parent glasses and glass ceramics were mainly composed of a continuous, glassy matrix phase. This glass matrix entered into solution during leaching in both types of materials. The Fe-Ti rich dispersed glass phase was not significantly degraded by leaching. The glass ceramics, however, exhibited four to ten times less elemental releases during leaching than the parent glasses. The glass ceramic matrix probably contains higher Fe and Na and lower Ca and Mg relative to the parent glass matrix. The crystallization of augite in the glass ceramics is believed to contribute to the improved leach rates. Leach rates of the basalt glass ceramic are compared to those of other TRU nuclear waste forms containing 239Pu

  10. Transuranic-contaminated solid waste Treatment Development Facility. Final safety analysis report

    International Nuclear Information System (INIS)

    The Final Safety Analysis Report (FSAR) for the Transuranic-Contaminated Solid-Waste Treatment Facility has been prepared in compliance with the Department of Energy (DOE) Manual Chapter 0531, Safety of Nonreactor Nuclear Facilities. The Treatment Development Facility (TDF) at the Los Alamos Scientific Laboratory is a research and development facility dedicated to the study of radioactive-waste-management processes. This analysis addresses site assessment, facility design and construction, and the design and operating characteristics of the first study process, controlled air incineration and aqueous scrub off-gas treatment with respect to both normal and accident conditions. The credible accidents having potentially serious consequences relative to the operation of the facility and the first process have been analyzed and the consequences of each postulated credible accident are presented. Descriptions of the control systems, engineered safeguards, and administrative and operational features designed to prevent or mitigate the consequences of such accidents are presented. The essential features of the operating and emergency procedures, environmental protection and monitoring programs, as well as the health and safety, quality assurance, and employee training programs are described

  11. Application of Fully Ceramic Microencapsulated Fuel for Transuranic Waste Recycling in PWRs

    Energy Technology Data Exchange (ETDEWEB)

    Gentry, Cole A [ORNL; Maldonado, G Ivan [ORNL; Terrani, Kurt A [ORNL; Gehin, Jess C [ORNL; Godfrey, Andrew T [ORNL

    2012-01-01

    Presented is an investigation of the utilization of Tristructural-Isotropic (TRISO) particle-based fuel designs for the recycling of transuranic (TRU) wastes in typical Westinghouse four-loop pressurized water reactors (PWRs). Though numerous studies have evaluated the recycling of TRU in light water reactors (LWRs), this work differentiates itself by employing TRU-loaded TRISO particles embedded within a SiC matrix and formed into pellets that can be loaded into standard 17 x 17 fuel element cladding. This approach provides the capability of TRU recycling and, by virtue of the TRISO particle design, will allow for greater burnup (i.e., removal of the need for UO2 mixing) and improved fuel reliability. In this study, a variety of assembly layouts and core loading patterns were analyzed to demonstrate the feasibility of TRU-loaded TRISO fuel. The assembly and core design herein reported are a work in progress, so they still require some fine-tuning to further flatten power peaks; however, the progress achieved thus far strongly supports the conclusion that with further rod/assembly/core loading and placement optimization, TRU-loaded TRISO fuel and core designs that are capable of balancing TRU production and destruction can be designed within the standard constraints for thermal and reactivity performance in PWRs.

  12. Source and long-term behavior of transuranic aerosols in the WIPP environment.

    Science.gov (United States)

    Thakur, P; Lemons, B G

    2016-10-01

    Source and long-term behavior transuranic aerosols ((239+240)Pu, (238)Pu, and (241)Am) in the ambient air samples collected at and near the Waste Isolation Pilot Plant (WIPP) deep geologic repository site were investigated using historical data from an independent monitoring program conducted by the Carlsbad Environmental Monitoring and Research Center and an oversight monitoring program conducted by the management and operating contractor for WIPP at and near the facility. An analysis of historical data indicates frequent detections of (239+240)Pu and (241)Am, whereas (238)Pu is detected infrequently. Peaks in (239+240)Pu and (241)Am concentrations in ambient air generally occur from March to June timeframe, which is when strong and gusty winds in the area frequently give rise to blowing dust. Long-term measurements of plutonium isotopes (1985-2015) in the WIPP environment suggest that the resuspension of previously contaminated soils is likely the primary source of plutonium in the ambient air samples from WIPP and its vicinity. There is no evidence that WIPP is a source of environmental contamination that can be considered significant by any health-based standard. PMID:27394421

  13. Transuranic and Low-Level Boxed Waste Form Nondestructive Assay Technology Overview and Assessment

    International Nuclear Information System (INIS)

    The Mixed Waste Focus Area (MWFA) identified the need to perform an assessment of the functionality and performance of existing nondestructive assay (NDA) techniques relative to the low-level and transuranic waste inventory packaged in large-volume box-type containers. The primary objectives of this assessment were to: (1) determine the capability of existing boxed waste form NDA technology to comply with applicable waste radiological characterization requirements, (2) determine deficiencies associated with existing boxed waste assay technology implementation strategies, and (3) recommend a path forward for future technology development activities, if required. Based on this assessment, it is recommended that a boxed waste NDA development and demonstration project that expands the existing boxed waste NDA capability to accommodate the indicated deficiency set be implemented. To ensure that technology will be commercially available in a timely fashion, it is recommended this development and demonstration project be directed to the private sector. It is further recommended that the box NDA technology be of an innovative design incorporating sufficient NDA modalities, e.g., passive neutron, gamma, etc., to address the majority of the boxed waste inventory. The overall design should be modular such that subsets of the overall NDA system can be combined in optimal configurations tailored to differing waste types

  14. Tissue-equivalent torso phantom for calibration of transuranic-nuclide counting facilities

    International Nuclear Information System (INIS)

    Several tissue-equivalent human-torso phantoms have been constructed for the calibration of counting systems used for in-vivo measurement of transuranic radionuclides. The phantoms contain a simulated human rib cage (in some cases, real bone) and removable model organs, and they include tissue-equivalent chest plates that can be placed over the torso to simulate people with a wide range of statures. The organs included are the lungs, liver, and tracheobronchial lymph nodes. Polyurethane with varying concentrations of added calcium was used to simulate the linear photon-attenuation properties of various human tissues, including lean muscle, adipose-muscle mixtures, cartilage, and bone. Foamed polyurethane was used to simulate lung tissue. Organs have been loaded with highly pure 238Pu, 239Pu, 241Am, and other radionuclides of interest. The validity of the phantom as a calibration standard has been checked in separate intercomparison studies using human subjects whose lungs contained a plutonium simulant. The resulting phantom calibration factors generally compared to within +-20% of the average calibration factors obtained for the human subjects

  15. Consideration of nuclear criticality when disposing of transuranic waste at the Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    Based on general arguments presented in this report, nuclear criticality was eliminated from performance assessment calculations for the Waste Isolation Pilot Plant (WIPP), a repository for waste contaminated with transuranic (TRU) radioisotopes, located in southeastern New Mexico. At the WIPP, the probability of criticality within the repository is low because mechanisms to concentrate the fissile radioisotopes dispersed throughout the waste are absent. In addition, following an inadvertent human intrusion into the repository (an event that must be considered because of safety regulations), the probability of nuclear criticality away from the repository is low because (1) the amount of fissile mass transported over 10,000 yr is predicted to be small, (2) often there are insufficient spaces in the advective pore space (e.g., macroscopic fractures) to provide sufficient thickness for precipitation of fissile material, and (3) there is no credible mechanism to counteract the natural tendency of the material to disperse during transport and instead concentrate fissile material in a small enough volume for it to form a critical concentration. Furthermore, before a criticality would have the potential to affect human health after closure of the repository--assuming that a criticality could occur--it would have to either (1) degrade the ability of the disposal system to contain nuclear waste or (2) produce significantly more radioisotopes than originally present. Neither of these situations can occur at the WIPP; thus, the consequences of a criticality are also low

  16. Magnetically assisted chemical separation (MACS) process: Preparation and optimization of particles for removal of transuranic elements

    International Nuclear Information System (INIS)

    The Magnetically Assisted Chemical Separation (MACS) process combines the selectivity afforded by solvent extractants with magnetic separation by using specially coated magnetic particles to provide a more efficient chemical separation of transuranic (TRU) elements, other radionuclides, and heavy metals from waste streams. Development of the MACS process uses chemical and physical techniques to elucidate the properties of particle coatings and the extent of radiolytic and chemical damage to the particles, and to optimize the stages of loading, extraction, and particle regeneration. This report describes the development of a separation process for TRU elements from various high-level waste streams. Polymer-coated ferromagnetic particles with an adsorbed layer of octyl(phenyl)-N,N-diisobutylcarbamoylmethylphosphine oxide (CMPO) diluted with tributyl phosphate (TBP) were evaluated for use in the separation and recovery of americium and plutonium from nuclear waste solutions. Due to their chemical nature, these extractants selectively complex americium and plutonium contaminants onto the particles, which can then be recovered from the solution by using a magnet. The partition coefficients were larger than those expected based on liquid[liquid extractions, and the extraction proceeded with rapid kinetics. Extractants were stripped from the particles with alcohols and 400-fold volume reductions were achieved. Particles were more sensitive to acid hydrolysis than to radiolysis. Overall, the optimization of a suitable NMCS particle for TRU separation was achieved under simulant conditions, and a MACS unit is currently being designed for an in-lab demonstration

  17. Project B-589, 300 Area transuranic waste interim storage project engineering study

    International Nuclear Information System (INIS)

    The purpose of the study was to look at various alternatives of taking newly generated, remote-handled transuranic waste (caisson waste) in the 300 Area, performing necessary transloading operations and preparing the waste for storage. The prepared waste would then be retrieved when the Waste Isolation Pilot Plant becomes operational and transshipped to the repository in New Mexico with a minimum of inspection and packaging. The scope of this study consisted of evaluating options for the transloading of the TRU wastes for shipment to a 200 Area storage site. Preconceptual design information furnished as part of the engineering study is listed below: produce a design for a clean, sealed waste canister; hot cell loadout system for the waste; in-cell loading or handling equipment; determine transshipment cask options; determine assay system requirements (optional); design or specify transport equipment required; provide a SARP cost estimate; determine operator training requirements; determine waste compaction equipment needs if desirable; develop a cost estimate and approximate schedule for a workable system option; and update the results presented in WHC Document TC-2025

  18. W-026, transuranic waste restricted waste management (TRU RWM) glovebox operational test report

    Energy Technology Data Exchange (ETDEWEB)

    Leist, K.J.

    1998-02-18

    The TRU Waste/Restricted Waste Management (LLW/PWNP) Glovebox 401 is designed to accept and process waste from the Transuranic Process Glovebox 302. Waste is transferred to the glovebox via the Drath and Schraeder Bagless Transfer Port (DO-07401) on a transfer stand. The stand is removed with a hoist and the operator inspects the waste (with the aid of the Sampling and Treatment Director) to determine a course of action for each item. The waste is separated into compliant and non compliant. One Trip Port DO-07402A is designated as ``Compliant``and One Trip Port DO-07402B is designated as ``Non Compliant``. As the processing (inspection, bar coding, sampling and treatment) of the transferred items takes place, residue is placed in the appropriate One Trip port. The status of the waste items is tracked by the Data Management System (DMS) via the Plant Control System (PCS) barcode interface. As an item is moved for sampling or storage or it`s state altered by treatment, the Operator will track an items location using a portable barcode reader and entry any required data on the DMS console. The Operational Test Procedure (OTP) will perform evolutions (described here) using the Plant Operating Procedures (POP) in order to verify that they are sufficient and accurate for controlled glovebox operation.

  19. Results from simulated remote-handled transuranic waste experiments at the Waste Isolation Pilot Plant (WIPP)

    International Nuclear Information System (INIS)

    Multi-year, simulated remote-handled transuranic waste (RH TRU, nonradioactive) experiments are being conducted underground in the Waste Isolation Pilot-Plant (WIPP) facility. These experiments involve the near-reference (thermal and geometrical) testing of eight full size RH TRU test containers emplaced into horizontal, unlined rock salt boreholes. Half of the test emplacements are partially filled with bentonite/silica-sand backfill material. All test containers were electrically heated at about 115 W/each for three years, then raised to about 300 W/each for the remaining time. Each test borehole was instrumented with a selection of remote-reading thermocouples, pressure gages, borehole vertical-closure gages, and vertical and horizontal borehole-diameter closure gages. Each test emplacements was also periodically opened for visual inspections of brine intrusions and any interactions with waste package materials, materials sampling, manual closure measurements, and observations of borehole changes. Effects of heat on borehole closure rates and near-field materials (metals, backfill, rock salt, and intruding brine) interactions were closely monitored as a function of time. This paper summarizes results for the first five years of in situ test operation with supporting instrumentation and laboratory data and interpretations. Some details of RH TRU waste package materials, designs, and assorted underground test observations are also discussed. Based on the results, the tested RH TRU waste packages, materials, and emplacement geometry in unlined salt boreholes appear to be quite adequate for initial WIPP repository-phase operations

  20. In-line Kevlar filters for microfiltration of transuranic-containing liquid streams.

    Science.gov (United States)

    Gonzales, G J; Beddingfield, D H; Lieberman, J L; Curtis, J M; Ficklin, A C

    1992-06-01

    The Department of Energy Rocky Flats Plant has numerous ongoing efforts to minimize the generation of residue and waste and to improve safety and health. Spent polypropylene liquid filters held for plutonium recovery, known as "residue," or as transuranic mixed waste contribute to storage capacity problems and create radiation safety and health considerations. An in-line process-liquid filter made of Kevlar polymer fiber has been evaluated for its potential to: (1) minimize filter residue, (2) recover economically viable quantities of plutonium, (3) minimize liquid storage tank and process-stream radioactivity, and (4) reduce potential personnel radiation exposure associated with these sources. Kevlar filters were rated to less than or equal to 1 mu nominal filtration and are capable of reducing undissolved plutonium particles to more than 10 times below the economic discard limit, however produced high back-pressures and are not yet acid resistant. Kevlar filters performed independent of loaded particles serving as a sieve. Polypropylene filters removed molybdenum particles at efficiencies equal to Kevlar filters only after loading molybdenum during recirculation events. Kevlars' high-efficiency microfiltration of process-liquid streams for the removal of actinides has the potential to reduce personnel radiation exposure by a factor of 6 or greater, while simultaneously achieving a reduction in the generation of filter residue and waste by a factor of 7. Insoluble plutonium may be recoverable from Kevlar filters by incineration.

  1. Transuranic-contaminated solid waste Treatment Development Facility. Final safety analysis report

    Energy Technology Data Exchange (ETDEWEB)

    Warner, C.L. (comp.)

    1979-07-01

    The Final Safety Analysis Report (FSAR) for the Transuranic-Contaminated Solid-Waste Treatment Facility has been prepared in compliance with the Department of Energy (DOE) Manual Chapter 0531, Safety of Nonreactor Nuclear Facilities. The Treatment Development Facility (TDF) at the Los Alamos Scientific Laboratory is a research and development facility dedicated to the study of radioactive-waste-management processes. This analysis addresses site assessment, facility design and construction, and the design and operating characteristics of the first study process, controlled air incineration and aqueous scrub off-gas treatment with respect to both normal and accident conditions. The credible accidents having potentially serious consequences relative to the operation of the facility and the first process have been analyzed and the consequences of each postulated credible accident are presented. Descriptions of the control systems, engineered safeguards, and administrative and operational features designed to prevent or mitigate the consequences of such accidents are presented. The essential features of the operating and emergency procedures, environmental protection and monitoring programs, as well as the health and safety, quality assurance, and employee training programs are described.

  2. Magnetically assisted chemical separation (MACS) process: Preparation and optimization of particles for removal of transuranic elements

    Energy Technology Data Exchange (ETDEWEB)

    Nunez, L.; Kaminski, M.; Bradley, C.; Buchholz, B.A.; Aase, S.B.; Tuazon, H.E.; Vandegrift, G.F. [Argonne National Lab., IL (United States); Landsberger, S. [Univ. of Illinois, Urbana, IL (United States)

    1995-05-01

    The Magnetically Assisted Chemical Separation (MACS) process combines the selectivity afforded by solvent extractants with magnetic separation by using specially coated magnetic particles to provide a more efficient chemical separation of transuranic (TRU) elements, other radionuclides, and heavy metals from waste streams. Development of the MACS process uses chemical and physical techniques to elucidate the properties of particle coatings and the extent of radiolytic and chemical damage to the particles, and to optimize the stages of loading, extraction, and particle regeneration. This report describes the development of a separation process for TRU elements from various high-level waste streams. Polymer-coated ferromagnetic particles with an adsorbed layer of octyl(phenyl)-N,N-diisobutylcarbamoylmethylphosphine oxide (CMPO) diluted with tributyl phosphate (TBP) were evaluated for use in the separation and recovery of americium and plutonium from nuclear waste solutions. Due to their chemical nature, these extractants selectively complex americium and plutonium contaminants onto the particles, which can then be recovered from the solution by using a magnet. The partition coefficients were larger than those expected based on liquid[liquid extractions, and the extraction proceeded with rapid kinetics. Extractants were stripped from the particles with alcohols and 400-fold volume reductions were achieved. Particles were more sensitive to acid hydrolysis than to radiolysis. Overall, the optimization of a suitable NMCS particle for TRU separation was achieved under simulant conditions, and a MACS unit is currently being designed for an in-lab demonstration.

  3. Transuranic decontamination of nitric acid solutions by the TRUEX solvent extraction process: preliminary development studies

    International Nuclear Information System (INIS)

    This report summarizes the work that has been performed to date at Argonne National Laboratory on the development of the TRUEX process, a solvent extraction process employing a bifunctional organophosphorous reagent in a PUREX process solvent (tributyl phosphate-normal paraffinic hydrocarbons). The purpose of this extraction process is to separate and concentrate transuranic (TRU) elements from nuclear waste. Assessments were made of the use of two TRUEX solvents: one incorporating the well-studied dihexyl-N,N-diethylcarbamoylmethylphosphonate (DHDECMP) and a second incorporating an extractant with superior properties for a 1M HNO3 acid feed, octyl(phenyl)-N,N-diisobutylcarbamoylmethylphosphine oxide (O/sub phi/D[IB]CMPO). In this report, conceptual flowsheets for the removal of soluble TRUs from high-level nuclear wastes using these two TRUEX proces solvents are presented, and flowsheet features are discussed in detail. The conceptual flowsheet for TRU-element removal from a PUREX waste by the O/sub phi/D[IB]CMPO-TRUEX process solvent was tested in a bench-scale countercurrent experiment, and results of that experiment are presented and discussed. The conclusion of this study is that the TRUEX process is able to separate TRUs from high-level wastes so that the major portion of the solid waste (approx. 99%) can be classified as non-TRU. Areas where more experimentation is needed are listed at the end of the report. 45 references, 17 figures, 56 tables

  4. Transuranics Laboratory, achievements and performance; Laboratorio de Transuranicos, logros y fundamento

    Energy Technology Data Exchange (ETDEWEB)

    Gasco, C.; Anton, M. P.

    2004-07-01

    The Marine and Aquatic Radioecology Group (MARG) was established in 1985 with the main scope of analysing the consequences of the Palomares accident in the adjacent Mediterranean ecosystem. From then on and up to now , this Group has extended its investigations to other European marine environments, such as the Spanish Mediterranean margin, the Artic and the Atlantic. The main research of long-lived radionuclides (plutonium, americium and Cs-137) determining the orography influence, riverine inputs and their geo-chemical associations. This group is currently accomplishing new challenges on the radioecology field such as the development of techniques for transuranics speciation to determine their geo-chemical association to the main sediment compounds. Natural and anthropogenic radionuclides distribution on salt-marsh areas affected by dry-wet periods is being studied as well as the possibilities of fusing crossed techniques for dating recent sediments (pollen, anthropogenic, ''210 Pb, etc). The Laboratory performance description, the procedures used, calculations, challenges and gaps are described in this report. (Author) 22 refs.

  5. Hot Cell Liners Category of Transuranic Waste Stored Below Ground within Area G

    Energy Technology Data Exchange (ETDEWEB)

    Jones, Robert Wesley [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Hargis, Kenneth Marshall [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2014-09-01

    A large wildfire called the Las Conchas Fire burned large areas near Los Alamos National Laboratory (LANL) in 2011 and heightened public concern and news media attention over transuranic (TRU) waste stored at LANL’s Technical Area 54 (TA-54) Area G waste management facility. The removal of TRU waste from Area G had been placed at a lower priority in budget decisions for environmental cleanup at LANL because TRU waste removal is not included in the March 2005 Compliance Order on Consent (Reference 1) that is the primary regulatory driver for environmental cleanup at LANL. The Consent Order is an agreement between LANL and the New Mexico Environment Department (NMED) that contains specific requirements and schedules for cleaning up historical contamination at the LANL site. After the Las Conchas Fire, discussions were held by the U.S. Department of Energy (DOE) with the NMED on accelerating TRU waste removal from LANL and disposing it at the Waste Isolation Pilot Plant (WIPP). This report summarizes available information on the origin, configuration, and composition of the waste containers within the Hot Cell Liners category; their physical and radiological characteristics; the results of the radioassays; and the justification to reclassify the five containers as LLW rather than TRU waste.

  6. Radiolytic generation of chloro-organic compounds in transuranic and low-level radioactive waste

    International Nuclear Information System (INIS)

    The radiolytic degradation of chloro-plastics is being investigated to evaluate the formation of chlorinated volatile organic compounds in radioactive waste. These chlorinated VOCs, when their subsequent migration in the geosphere is considered, are potential sources of ground-water contamination. This contamination is an important consideration for transuranic waste repositories being proposed for the Waste Isolation Pilot Plant project and the several additional low-level radioactive waste sites being considered throughout the United States. The production of chlorinated volatile organic compounds due to the interaction of ionizing radiation with chloro-plastic materials has been well-established in both this work and past studies. This occurs as a result of gamma, beta, and alpha particle interactions with the plastic material. The assemblage of organic compounds generated depends on the type of plastic material, the type of ionizing radiation, the gaseous environment present and the irradiation temperature. In the authors' experiments, gas generation data were obtained by mounting representative plastics near (3 mm) an alpha particle source (Am-241 foil). This assembly was placed in an irradiation vessel which contained air, nitrogen, or a hydrogen/carbon dioxide mixture, at near-atmospheric pressures, to simulate the range of atmospheres likely to be encountered in the subsurface. The gas phase in the vessels are periodically sampled for net gas production. The gas phase concentrations are monitored over time to determine trends and calculate the radiolytic yield for the various gaseous products

  7. Transuranic solid waste management research programs. Progress report, January--June 1975

    International Nuclear Information System (INIS)

    Tests continued to evaluate less costly fiber drums as alternate storage containers for low-level wastes. Tests completed to date indicated that the factory-applied fire retardants were not satisfactory; however, investigations of more promising coatings have been undertaken. The fiber drums were more satisfactory in other aspects. Expanded laboratory and field radiolysis experiments were performed. These were accompanied by investigations of H2 diffusion through common waste packaging materials and through Los Alamos soil. Radiolysis studies were also initiated on wastes typical of Mound Laboratory. All results to date show that while H2 is being slowly generated, the quantities are not excessive and should diffuse rapidly away. Construction of the TDF facility began and was 14 percent complete at the end of this reporting period. The incinerator was received, installed and checked out, and is operational. Additional specifications were developed and equipment procurement continued. Progress is reported on development of a system for evaluating radioactively contaminated solid waste burial sites. Source term data are summarized for some Los Alamos areas along with waste composition and configuration considerations. Physical and biotic transport pathways are discussed and development of modeling methods for projecting the environmental fate of transuranic materials is detailed

  8. 78 FR 5861 - National Plan of Integrated Airport Systems: Clarification of Wildlife Hazard Management...

    Science.gov (United States)

    2013-01-28

    ... Federal Aviation Administration National Plan of Integrated Airport Systems: Clarification of Wildlife Hazard Management Requirements for Non-Certificated Federally Obligated Airports AGENCY: Federal Aviation... responsibility of federally obligated National Plan of Integrated Airport System/General Aviation...

  9. Gates Fund Creates Plan for College Completion

    Science.gov (United States)

    Gose, Ben

    2008-01-01

    The Bill & Melinda Gates Foundation plans to spend several hundred million dollars over the next five years to double the number of low-income young people who complete a college degree or certificate program by age 26. Foundation officials described the ambitious plan to an exclusive group of education leaders, citing 2025 as a target goal. If…

  10. 14 CFR 93.323 - Flight plans.

    Science.gov (United States)

    2010-01-01

    ... 14 Aeronautics and Space 2 2010-01-01 2010-01-01 false Flight plans. 93.323 Section 93.323... AND GENERAL OPERATING RULES SPECIAL AIR TRAFFIC RULES Special Flight Rules in the Vicinity of Grand Canyon National Park, AZ § 93.323 Flight plans. Each certificate holder conducting a commercial...

  11. Certification and licensing of clinical medical physicists in AFOMP countries

    International Nuclear Information System (INIS)

    Full text: In many countries the education and training of medical physicists has changed over the last few decades 'om being rather ad hoc to becoming structured with residency programs becoming quite common. These are often followed by formal certification by independent bodies, and medical physics professional organizations MPPOs) affirming the quality of certified physicists and recognizing their competence and ability to practice independently. Policies on the training and education of medical physicists have been developed by the International organization for Medical Physics (IOMP) and by the Asia Oceania Federation of Organizations for Medical Physics AFOMP). Currently nine countries in Asia-Oceania operate systems for the certification of clinical medical physicists and four others are planning or implementing such systems. The existing systems, which are described in his paper, generally conform to the policies. Licensing of medical physicists, which is primarily the responsibility of government bodies, is almost unknown in that region. (author)

  12. Review of a site developer's geo-scientific data and site-characterisation information to support repository certification

    International Nuclear Information System (INIS)

    The Waste Isolation Pilot Plant (WIPP) in New Mexico is a first-of-a-kind deep geologic facility for the disposal of transuranic (TRU) radioactive waste from weapons production in the United States. In 1993, Congress authorised the Environmental Protection Agency (EPA) to develop and implement WIPP-site-specific compliance criteria based on the general safety and environmental standards in EPA's high-level and transuranic radioactive waste regulations [1]. EPA published its site-specific regulations [2] in 1996 and certified WIPP to open in 1998. This regulatory framework set the stage for balancing diverse input data, provided a structure for document development, provided a mechanism for interaction between EPA and the Department of Energy (DOE), and provided a guide to support our review of WIPP's safety assessment. EPA's involvement continues during WIPP's operational phase. Confidence in repository site geo-scientific data enhances the regulator's ability to make a credible and defensible certification (licensing) decision and to communicate the basis for the decision to the public. Lack of confidence in the data can lead to lack of credibility about site suitability. Clear regulations and specific quality standards can enhance the quality of site-characterisation documentation and assist the regulator in its approval process of the site. In EPA's regulations, documentation is required on numerous issues, and EPA supplemented this with guidance. High-quality documentation is essential, especially for EPA. In the certification process for WIPP, the documentation in the record and our written interpretation of the record was what was used in legal proceedings that followed EPA's certification of WIPP. EPA and DOE had frequent and generally open communication. During formal regulatory proceedings, all communication had to be documented. Some decisions were made at the staff level, but major decisions were typically addressed and resolved through correspondence

  13. TRU waste inventory collection and work-off plans for the centralization of TRU waste characterization at INL - on your mark - get set - 9410

    Energy Technology Data Exchange (ETDEWEB)

    Mctaggert, Jerri Lynne [Los Alamos National Laboratory; Lott, Sheila [Los Alamos National Laboratory; Gadbury, Casey [CBFO

    2009-01-01

    The U.S. Department of Energy (DOE) amended the Record of Decision (ROD) for the Waste Management Program: Treatment and Storage ofTransuranic Waste to centralize transuranic (TRU) waste characterization/certification from fourteen TRU waste sites. This centralization will allow for treatment, characterization and certification ofTRU waste from the fourteen sites, thirteen of which are sites with small quantities ofTRU waste, at the Idaho National Laboratory (INL) prior to shipping the waste to the Waste Isolation Pilot Plant (WIPP) for disposal. Centralization ofthis TRU waste will avoid the cost ofbuilding treatment, characterization, certification, and shipping capabilities at each ofthe small quantity sites that currently do not have existing facilities. Advanced Mixed Waste Treatment Project (AMWTP) and Idaho Nuclear Technology and Engineering Center (INTEC) will provide centralized shipping facilities, to WIPP, for all ofthe small quantity sites. Hanford, the one large quantity site identified in the ROD, has a large number ofwaste in containers that are overpacked into larger containers which are inefficient for shipment to and disposal at WIPP. The AMWTP at the INL will reduce the volume ofmuch of the CH waste and make it much more efficient to ship and dispose of at WIPP. In addition, the INTEC has a certified remote handled (RH) TRU waste characterization/certification program at INL to disposition TRU waste from the sites identified in the ROD.

  14. Disposal of transuranic solid waste using Atomics International's molten salt combustion process. II

    International Nuclear Information System (INIS)

    The Atomics International Molten Salt Combustion Process reduces the weight and volume of combustible transuranic waste by utilizing a molten salt medium to combust organic materials, to trap particulates and fissile material, and to react chemically with any acidic gases produced during combustion. The ''ash'' is retained by the molten salt. To control the amount of noncombustible substances in the melt, a portion of the molten salt is periodically drained from the combustor. There are two options following the combustion step: the salt-ash mixture can be cast into a metal canister for direct storage, which is preferred, or the salt-ash mixture can be processed to separate ash for disposal, to recover the salt for recycle and to recover fissile materials. Either option results in the rapid, complete, and nonpolluting destruction of the combustible waste. Bench-scale (0.2 kg/hr) combustion tests with plutonium-contaminated waste showed that >99.9 percent of the plutonium is retained in the melt during combustion. A similar test with uranium indicated that uranium and plutonium behave identically during combustion. Bench-scale plutonium recovery tests have shown that approx. 98 percent of the plutonium can be recovered from the ash-melt mixture with a single acid leach. Pilot plant combustion tests were conducted with uncontaminated shredded waste consisting of paper, Kimwipes, cardboard, rubber, polyvinyl chloride, and polyethylene at feed rates up to 70 kg/hr. Hydrogen chloride (3 at approx. 7900C to 0.6 g/m3 at 10200C before the venturi scrubber, and 0.01 to 0.04 g/m3, respectively, after the scrubber. Downstream of the HEPA filters, no particulates could be detected

  15. Position for determining gas-phase volatile organic compound concentrations in transuranic waste containers. Revision 2

    Energy Technology Data Exchange (ETDEWEB)

    Connolly, M.J.; Liekhus, K.J. [Lockheed Martin Idaho Technologies Co., Idaho Falls, ID (United States). Idaho National Engineering and Environmental Lab.; Djordjevic, S.M.; Loehr, C.A.; Spangler, L.R. [Benchmark Environmental Corp. (United States)

    1998-06-01

    In the conditional no-migration determination (NMD) for the test phase of the Waste Isolation Pilot Plant (WIPP), the US Environmental Protection Agency (EPA) imposed certain conditions on the US Department of Energy (DOE) regarding gas phase volatile organic compound (VOC) concentrations in the void space of transuranic (TRU) waste containers. Specifically, the EPA required the DOE to ensure that each waste container has no layer of confinement that contains flammable mixtures of gases or mixtures of gases that could become flammable when mixed with air. The EPA also required that sampling of the headspace of waste containers outside inner layers of confinement be representative of the entire void space of the container. The EPA stated that all layers of confinement in a container would have to be sampled until DOE can demonstrate to the EPA that sampling of all layers is either unnecessary or can be safely reduced. A test program was conducted at the Idaho National Engineering and Environmental Laboratory (INEEL) to demonstrate that the gas phase VOC concentration in the void space of each layer of confinement in vented drums can be estimated from measured drum headspace using a theoretical transport model and that sampling of each layer of confinement is unnecessary. This report summarizes the studies performed in the INEEL test program and extends them for the purpose of developing a methodology for determining gas phase VOC concentrations in both vented and unvented TRU waste containers. The methodology specifies conditions under which waste drum headspace gases can be said to be representative of drum gases as a whole and describes a method for predicting drum concentrations in situations where the headspace concentration is not representative. The methodology addresses the approach for determining the drum VOC gas content for two purposes: operational period drum handling and operational period no-migration calculations.

  16. Comparative analysis of thorium and uranium fuel for transuranic recycle in a sodium cooled Fast Reactor

    International Nuclear Information System (INIS)

    Highlights: • Thorium as support fertile material for TRU transmutation in Fast Reactors. • Comparative analysis of Th and U based breakeven and burner Fast Reactors. • Thorium fosters significant advantages in terms of safety parameters. • Inherent safety is investigated through quasi-static reactivity and energy balances. • Th use in low-CR Fast Reactors does not reduce fuel decay heat and neutron sources. - Abstract: The present paper compares the reactor physics and transmutation performance of sodium-cooled Fast Reactors (FRs) for TRansUranic (TRU) burning with thorium (Th) or uranium (U) as fertile materials. The 1000 MWt Toshiba-Westinghouse Advanced Recycling Reactor (ARR) conceptual core has been used as benchmark for the comparison. Both burner and breakeven configurations sustained or started with a TRU supply, and assuming full actinide homogeneous recycle strategy, have been developed. State-of-the-art core physics tools have been employed to establish fuel inventory and reactor physics performances for equilibrium and transition cycles. Results show that Th fosters large improvements in the reactivity coefficients associated with coolant expansion and voiding, which enhances safety margins and, for a burner design, can be traded for maximizing the TRU burning rate. A trade-off of Th compared to U is the significantly larger fuel inventory required to achieve a breakeven design, which entails additional blankets at the detriment of core compactness as well as fuel manufacturing and separation requirements. The gamma field generated by the progeny of U-232 in the U bred from Th challenges fuel handling and manufacturing, but in case of full recycle, the high contents of Am and Cm in the transmutation fuel impose remote fuel operations regardless of the presence of U-232

  17. Development of Modern Performance Assessment Tools and Capabilities for Underground Disposal of Transuranic Waste at WIPP

    Science.gov (United States)

    Zeitler, T.; Kirchner, T. B.; Hammond, G. E.; Park, H.

    2014-12-01

    The Waste Isolation Pilot Plant (WIPP) has been developed by the U.S. Department of Energy (DOE) for the geologic (deep underground) disposal of transuranic (TRU) waste. Containment of TRU waste at the WIPP is regulated by the U.S. Environmental Protection Agency (EPA). The DOE demonstrates compliance with the containment requirements by means of performance assessment (PA) calculations. WIPP PA calculations estimate the probability and consequence of potential radionuclide releases from the repository to the accessible environment for a regulatory period of 10,000 years after facility closure. The long-term performance of the repository is assessed using a suite of sophisticated computational codes. In a broad modernization effort, the DOE has overseen the transfer of these codes to modern hardware and software platforms. Additionally, there is a current effort to establish new performance assessment capabilities through the further development of the PFLOTRAN software, a state-of-the-art massively parallel subsurface flow and reactive transport code. Improvements to the current computational environment will result in greater detail in the final models due to the parallelization afforded by the modern code. Parallelization will allow for relatively faster calculations, as well as a move from a two-dimensional calculation grid to a three-dimensional grid. The result of the modernization effort will be a state-of-the-art subsurface flow and transport capability that will serve WIPP PA into the future. Sandia National Laboratories is a multi-program laboratory managed and operated by Sandia Corporation, a wholly owned subsidiary of Lockheed Martin Corporation, for the U.S. Department of Energy's National Nuclear Security Administration under contract DE-AC04-94AL85000. This research is funded by WIPP programs administered by the Office of Environmental Management (EM) of the U.S Department of Energy.

  18. Risk evaluations of transuranic waste at the Idaho National Engineering Laboratory

    International Nuclear Information System (INIS)

    Approximately 75% of the defense low-level transuranic (TRU) waste stored in the United States and 25% of the buried TRU waste is located at the Idaho National Engineering Laboratory (INEL). Studies have been performed to identify and evaluate technical alternatives for the long-term management of this waste. (The alternatives range from leaving the waste in place as is to reviewing, processing, and shipping it to an offsite geological repository.) Among the evalations that have been performed were preliminary risk evaluations. The dose commitment and risk of hypothetical, near-term, accidental or uncontrolled releases of radionuclides have been evaluated for each alternative. The following potential causes of radionuclide release have been studied: process and handling accidents, shipping accidents, natural events (e.g., earthquakes), man-caused events (e.g., airplane crashes), and future intrusion by individuals or small populations after loss of societal control over the waste. The hypothetical releases have been evaluated, in terms of dose commitment and (if pertinent) probability and risk, for all operational steps making up each concept. The dominant scanerios in terms of near-term risk are (1) lava flow up through or over the waste, leading to airbone releases; (2) an explosion or a criticality accident in the waste-processing facility; and (3) a tornado strike or a fire during waste retrieval. The dominant long-term releases are (1) volcanic action; and (2) intrusion of people on the waste site.Although substantial dose commitments to individual members of the public were calculated for the lava flow and intrusion scenarios, no prompt health effects would be expected from the exposures. The effects would be in the form of a slightly increased likelihood of latent cancer induction

  19. Position for determining gas phase volatile organic compound concentrations in transuranic waste containers. Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    Connolly, M.J.; Liekhus, K.J. [Lockheed Idaho Technologies Co., Idaho Falls, ID (United States); Djordjevic, S.M.; Loehr, C.A.; Spangler, L.R. [Benchmark Environmental Corp., Albuquerque, NM (United States)

    1995-08-01

    In the conditional no-migration determination (NMD) for the test phase of the Waste Isolation Pilot Plant (WIPP), the US Environmental Protection Agency (EPA) imposed certain conditions on the US Department of Energy (DOE) regarding gas phase volatile organic compound (VOC) concentrations in the void space of transuranic (TRU) waste containers. Specifically, the EPA required the DOE to ensure that each waste container has no layer of confinement that contains flammable mixtures of gases or mixtures of gases that could become flammable when mixed with air. The EPA also required that sampling of the headspace of waste containers outside inner layers of confinement be representative of the entire void space of the container. The EPA stated that all layers of confinement in a container would have to be sampled until DOE can demonstrate to the EPA that sampling of all layers is either unnecessary or can be safely reduced. A test program was conducted at the Idaho National Engineering Laboratory (INEL) to demonstrate that the gas phase VOC concentration in the void space of each layer of confinement in vented drums can be estimated from measured drum headspace using a theoretical transport model and that sampling of each layer of confinement is unnecessary. This report summarizes the studies performed in the INEL test program and extends them for the purpose of developing a methodology for determining gas phase VOC concentrations in both vented and unvented TRU waste containers. The methodology specifies conditions under which waste drum headspace gases can be said to be representative of drum gases as a whole and describes a method for predicting drum concentrations in situations where the headspace concentration is not representative. The methodology addresses the approach for determining the drum VOC gas content for two purposes: operational period drum handling and operational period no-migration calculations.

  20. Axially homogeneous thorium fuel designs for transuranic burning in reduced-moderation BWRs

    International Nuclear Information System (INIS)

    Reduced-moderation Boiling Water Reactors (RBWRs) can allow sustained burning of transuranics (TRU), such that full actinide recycle can be achieved. However, the void coefficient (VC) tends to become positive with reduced moderation and high TRU loading, which can severely limit the design feasibility and performance. This motivates use of thorium (Th) as an alternative feed to uranium (U), as this tends to result in a more negative VC. Using coupled neutronic-thermal-hydraulic core calculations, Th-fuelled RBWRs are shown to be capable of achieving high discharge burn-ups, while incinerating an external supply of TRU. This gives them some flexibility to incinerate TRU with different isotope vectors. Spatial separation of Th-TRU and Th-U3 into regions of the order of a few thermal neutron diffusion lengths greatly improves neutronic performance. This can be accomplished radially or axially, but radial separation results in significantly easier fuel fabrication. A companion paper considers axially heterogeneous fuel designs, which are not found to deliver improved performance. A radially heterogeneous RBWR core design, can achieve 135 kg/GWthyr waste incineration rate, and at least 70–80 GWd/t discharge burn-up, depending on the TRU cooling time, and whether a single pass through a conventional PWR is used as an initial step before full recycle in an RBWR. Alternatively, a micro-heterogeneous assembly design with Th-Pu and Th-U3-MA pins can reduce fuel fabrication costs, although this limits the TRU incineration rate to ∼100 kg/GWthyr. ∼200 cm and ∼120 cm core heights are considered, with the former being generally preferred due to the possibility to match both the rating and pressure vessel size of an ABWR. (author)

  1. Axially heterogeneous thorium fuel designs for transuranic burning in reduced-moderation BWRs

    International Nuclear Information System (INIS)

    Reduced-moderation Boiling Water Reactors (RBWRs) can allow sustained burning of transuranics (TRU), such that full actinide recycle can be achieved. However, the void coefficient (VC) tends to become positive with reduced moderation and high TRU loading, which can severely limit the design feasibility and performance. This motivates use of thorium (Th) as an alternative feed to uranium (U), as this tends to result in a more negative VC, leading to much improved neutronic performance. While axially homogeneous fuel design is preferable for ease of fuel fabrication, it is valuable to evaluate axially heterogeneous fuel designs to see if improved neutronic performance can be realised, which could lead to a reduction in fuel reprocessing and fabrication throughput. Multi-recycled Th-TRU fuel contains Th, U, Pu and MAs, leading to a wide range of possible fuel designs. Axially heterogeneous designs are considered using 3D pincell calculations using the Monte Carlo code Serpent. Radially heterogeneous assembly designs are considered in a companion paper. Spatial separation of Th-TRU and Th-U3 into regions of the order of a few thermal neutron diffusion lengths greatly improves neutronic performance. This can be accomplished radially or axially, but radial separation results in significantly easier fuel fabrication. Axial seed-blanket heterogeneity improves neutron economy at the expense of high power peaking, such that the radially heterogeneous assembly design is preferred. Separation of Th-TRU and Th-U3 into larger regions is not effective, due to increased power density in the Th-TRU region with voiding and with burn-up, leading to a more positive VC. It is therefore concluded that there is no motivation to pursue axially heterogeneous Th-TRU RBWR burner designs. (author)

  2. In Brief: Science teaching certificate

    Science.gov (United States)

    Showstack, Randy

    2008-11-01

    More than 200 educators will receive fellowships over the next 5 years to participate in NASA's Endeavor Science Teaching Certificate Project, the agency announced on 14 November. Through workshops, online and on-site graduate courses, and NASA educational materials, the project will expose educators to NASA science and engineering and support them in translating the information for use in classrooms. ``Through the program, educators will learn to deliver cutting-edge science into the classroom, promoting science, technology, engineering, and mathematics education,'' according to Joyce Winterton, assistant administrator for education at NASA Headquarters, in Washington, D. C. Project fellows will earn a certificate from Teachers College Innovations at Teachers College, Columbia University, New York, and graduate credit from other institutional partners. For more information, visit http://education.nasa.gov/home/index.html.

  3. ISO 9001 certification forecasting models

    OpenAIRE

    Sampaio, Paulo; Saraiva, Pedro; Rodrigues, António Guimarães

    2011-01-01

    Purpose – ISO 9001 certification is nowadays considered to be one of the most effective tools that can be adopted for guiding the management of Quality Systems. The stunning growth observed by these standards all over the world confirms a strong polarization of enterprises’ interest in this practice. Owing to the wide incidence of this phenomenon, a deep investigation of ISO 9001 diffusion over time is of mandatory importance. The research here reported covers the development of s...

  4. Upward Mobility among Secondary Education Students: The Decision to Obtain a Better Certificate

    Science.gov (United States)

    Schuchart, Claudia

    2013-01-01

    This article applies the theory of planned behaviour (Ajzen 1988, 1991) to analyse the decision of students to attain a more advanced certificate than the one dictated by their school track. The analyses were based on a longitudinal survey of 1,010 Hauptschule students in Germany in years 8 and 10. Consistent with the theory, the results showed…

  5. 40 CFR 80.163 - Detergent certification options.

    Science.gov (United States)

    2010-07-01

    ... to approved State programs). (d) CARB-Based Certification. A valid certification under section 2257 of Title 13, California Code of Regulations (CARB certification) may be the basis for a certification... at the LAC specified in the CARB certification only in gasoline that meets the requirements...

  6. 46 CFR 189.60-40 - Duration of Convention certificates.

    Science.gov (United States)

    2010-10-01

    ... 46 Shipping 7 2010-10-01 2010-10-01 false Duration of Convention certificates. 189.60-40 Section... VESSELS INSPECTION AND CERTIFICATION Certificates Under International Convention for Safety of Life at Sea, 1974 § 189.60-40 Duration of Convention certificates. (a) The following certificates are valid for...

  7. 46 CFR 91.60-40 - Duration of Convention certificates.

    Science.gov (United States)

    2010-10-01

    ... 46 Shipping 4 2010-10-01 2010-10-01 false Duration of Convention certificates. 91.60-40 Section 91... VESSELS INSPECTION AND CERTIFICATION Certificates Under International Convention for Safety of Life at Sea, 1974 § 91.60-40 Duration of Convention certificates. (a) The following certificates are valid for...

  8. 46 CFR 71.75-15 - Posting of Convention certificates.

    Science.gov (United States)

    2010-10-01

    ... 46 Shipping 3 2010-10-01 2010-10-01 false Posting of Convention certificates. 71.75-15 Section 71... AND CERTIFICATION Certificates Under the International Convention for Safety of Life at Sea, 1960 § 71.75-15 Posting of Convention certificates. (a) The certificates described in this subpart,...

  9. Certification-Based Process Analysis

    Science.gov (United States)

    Knight, Russell L.

    2013-01-01

    Space mission architects are often challenged with knowing which investment in technology infusion will have the highest return. Certification-based analysis (CBA) gives architects and technologists a means to communicate the risks and advantages of infusing technologies at various points in a process. Various alternatives can be compared, and requirements based on supporting streamlining or automation can be derived and levied on candidate technologies. CBA is a technique for analyzing a process and identifying potential areas of improvement. The process and analysis products are used to communicate between technologists and architects. Process means any of the standard representations of a production flow; in this case, any individual steps leading to products, which feed into other steps, until the final product is produced at the end. This sort of process is common for space mission operations, where a set of goals is reduced eventually to a fully vetted command sequence to be sent to the spacecraft. Fully vetting a product is synonymous with certification. For some types of products, this is referred to as verification and validation, and for others it is referred to as checking. Fundamentally, certification is the step in the process where one insures that a product works as intended, and contains no flaws.

  10. Special Analysis of Transuranic Waste in Trench T04C at the Area 5 Radioactive Waste Management Site, Nevada Test Site, Nye County, Nevada, Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    Greg Shott, Vefa Yucel, Lloyd Desotell

    2008-05-01

    performance assessment (PA), composite analysis (CA), closure plan, monitoring plan, waste acceptance criteria, and a PA/CA maintenance plan. The DOE issued a DAS for the Area 5 RWMS in 2000. The Area 5 RWMS DAS was, in part, based on review of a CA as required under DOE M 435.1-1, Chapter IV, Section P.(3). A CA is a radiological assessment required for DOE waste disposed before 26 September 1988 and includes the radiological dose from all sources of radioactive material interacting with all radioactive waste disposed at the Area 5 RWMS. The approved Area 5 RWMS CA, which includes the inventory of TRU waste in T04C, indicates that the Area 5 RWMS waste inventory and all interacting sources of radioactive material can meet the 0.3 mSv dose constraint. The composite analysis maximum annual dose for a future resident at the Area 5 RWMS was estimated to be 0.01 mSv at 1,000 years. Therefore, the inadvertent disposal of TRU in T04C is protective of the public and the environment, and compliant with all the applicable requirements in DOE M 435.1-1 and the DAS. The U.S. Environmental Protection Agency promulgated 40 CFR 191 to establish standards for the planned disposal of spent nuclear fuel, high level, and transuranic wastes in geologic repositories. Although not required, the National Nuclear Security Administration Nevada Site Office requested a supplemental analysis to evaluate the likelihood that the inadvertent disposal of TRU waste in T04C meets the requirements of 40 CFR 191. The SA evaluates the likelihood of meeting the 40 CFR 191 containment requirements (CRs), assurance requirements, individual protection requirements (IPRs), and groundwater protection standards. The results of the SA indicate that there is a reasonable expectation of meeting all the requirements of 40 CFR 191. The conclusion of the SA is that the Area 5 RWMS with the TRU waste buried in T04C is in compliance with all requirements in DOE M 435.1-1 and the DAS. Compliance with the DAS is demonstrated

  11. Special Analysis of Transuranic Waste in Trench T04C at the Area 5 Radioactive Waste Management Site, Nevada Test Site, Nye County, Nevada, Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    Greg Shott, Vefa Yucel, Lloyd Desotell

    2008-05-01

    performance assessment (PA), composite analysis (CA), closure plan, monitoring plan, waste acceptance criteria, and a PA/CA maintenance plan. The DOE issued a DAS for the Area 5 RWMS in 2000. The Area 5 RWMS DAS was, in part, based on review of a CA as required under DOE M 435.1-1, Chapter IV, Section P.(3). A CA is a radiological assessment required for DOE waste disposed before 26 September 1988 and includes the radiological dose from all sources of radioactive material interacting with all radioactive waste disposed at the Area 5 RWMS. The approved Area 5 RWMS CA, which includes the inventory of TRU waste in T04C, indicates that the Area 5 RWMS waste inventory and all interacting sources of radioactive material can meet the 0.3 mSv dose constraint. The composite analysis maximum annual dose for a future resident at the Area 5 RWMS was estimated to be 0.01 mSv at 1,000 years. Therefore, the inadvertent disposal of TRU in T04C is protective of the public and the environment, and compliant with all the applicable requirements in DOE M 435.1-1 and the DAS. The U.S. Environmental Protection Agency promulgated 40 CFR 191 to establish standards for the planned disposal of spent nuclear fuel, high level, and transuranic wastes in geologic repositories. Although not required, the National Nuclear Security Administration Nevada Site Office requested a supplemental analysis to evaluate the likelihood that the inadvertent disposal of TRU waste in T04C meets the requirements of 40 CFR 191. The SA evaluates the likelihood of meeting the 40 CFR 191 containment requirements (CRs), assurance requirements, individual protection requirements (IPRs), and groundwater protection standards. The results of the SA indicate that there is a reasonable expectation of meeting all the requirements of 40 CFR 191. The conclusion of the SA is that the Area 5 RWMS with the TRU waste buried in T04C is in compliance with all requirements in DOE M 435.1-1 and the DAS. Compliance with the DAS is demonstrated

  12. Special Analysis of Transuranic Waste in Trench T04C at the Area 5 Radioactive Waste Management Site, Nevada Test Site, Nye County, Nevada, Revision 1

    International Nuclear Information System (INIS)

    performance assessment (PA), composite analysis (CA), closure plan, monitoring plan, waste acceptance criteria, and a PA/CA maintenance plan. The DOE issued a DAS for the Area 5 RWMS in 2000. The Area 5 RWMS DAS was, in part, based on review of a CA as required under DOE M 435.1-1, Chapter IV, Section P.(3). A CA is a radiological assessment required for DOE waste disposed before 26 September 1988 and includes the radiological dose from all sources of radioactive material interacting with all radioactive waste disposed at the Area 5 RWMS. The approved Area 5 RWMS CA, which includes the inventory of TRU waste in T04C, indicates that the Area 5 RWMS waste inventory and all interacting sources of radioactive material can meet the 0.3 mSv dose constraint. The composite analysis maximum annual dose for a future resident at the Area 5 RWMS was estimated to be 0.01 mSv at 1,000 years. Therefore, the inadvertent disposal of TRU in T04C is protective of the public and the environment, and compliant with all the applicable requirements in DOE M 435.1-1 and the DAS. The U.S. Environmental Protection Agency promulgated 40 CFR 191 to establish standards for the planned disposal of spent nuclear fuel, high level, and transuranic wastes in geologic repositories. Although not required, the National Nuclear Security Administration Nevada Site Office requested a supplemental analysis to evaluate the likelihood that the inadvertent disposal of TRU waste in T04C meets the requirements of 40 CFR 191. The SA evaluates the likelihood of meeting the 40 CFR 191 containment requirements (CRs), assurance requirements, individual protection requirements (IPRs), and groundwater protection standards. The results of the SA indicate that there is a reasonable expectation of meeting all the requirements of 40 CFR 191. The conclusion of the SA is that the Area 5 RWMS with the TRU waste buried in T04C is in compliance with all requirements in DOE M 435.1-1 and the DAS. Compliance with the DAS is demonstrated

  13. PKI Interoperability Based on Online Certificate Validation

    Directory of Open Access Journals (Sweden)

    Dinu Smadu

    2011-03-01

    Full Text Available One of the most important problems related to Public Key Infrastructures is the validation of the digital certificates. Certificate validation services can be based on offline and/or online schemes. Offline schemes have the major disadvantage that they cannot always give an up-to-date response. On the other side, the most used protocol for online validation, the Online Certificate Status Protocol [1], also has its drawbacks. It can only state if a certificate has been revoked or not. RFC 5055 [2] defines a more complex protocol, the Server-based Certificate Validation Protocol (SCVP, capable of building and validating the certification path. To implement a basic functionality of this new protocol, we will start from an existing project, the CADDISK and we will try to implement an OpenSSL module.

  14. Making calculated energy certificate for choosen building

    OpenAIRE

    Hafner, Rok

    2015-01-01

    The graduation thesis addresses four given energy efficiency certificates for the preschool in Škofja Loka, calculated according to the valid legislation and work methodology. The building in question was built in the seventies of last century and had it's efficiency improved in 2014. The state of the building before improvements has both measured and calculated efficiency certificates made using the KI Energija 2014 program, while the two energy efficiency certificates for the...

  15. Teacher Certification Among Athletic Training Students

    OpenAIRE

    Curtis, Neil

    1995-01-01

    Researchers have reported that athletic training students who earn teacher certification enhance their job marketability. The purpose of this study was to determine the number of athletic training students who pursue teacher certification. A survey was mailed to the directors of the 78 NATA undergraduate programs in 1992. Data from the returned surveys showed that 177 of the 703 expected graduates in 1992 and 148 of the 640 graduates in 1991 pursued teacher certification. The most common teac...

  16. ISO 9001 certification : customer’s perspective

    OpenAIRE

    Matias, Diana; Sampaio, Paulo; Braga, A.C.

    2011-01-01

    Based on our own experience and on the literature review carried out the ISO 9001 research studies have mostly addressed certification issues from the companies point of view, namely companies certification motivations and benefits, benefits evolution over time, barriers to the quality management system implementation, evolution and diffusion of worldwide ISO 9001 certification, the impact on organizational and financial performance and the relation between ISO 9001 and Total Quality Manageme...

  17. On certificates and lookahead in dynamic graph problems

    Energy Technology Data Exchange (ETDEWEB)

    Khanna, S.; Motwani, R. [Stanford Univ., Stanford, CA (United States); Wilson, R.H. [Sandia National Labs., Albuquerque, NM (United States)

    1995-05-05

    Recent work in dynamic graph algorithms has led to efficient algorithms for dynamic undirected graph problems such as connectivity. However, no efficient algorithms are known for the dynamic versions of fundamental directed graph problems like strong connectivity and transitive closure, as well as some undirected graph problems such as maximum matchings and cuts. We provide some explanation for this lack of success by presenting quadratic lower bounds on the certificate complexity of the seemingly difficult problems, in contrast to the known linear certificate complexity for the problems which have efficient dynamic algorithms. A direct outcome of our lower bounds is the demonstration that a generic technique for designing efficient dynamic graph algorithms, viz., sparsification, will not apply to the difficult problems. More generally, it is our belief that the boundary between tractable and intractable dynamic graph problems can be demarcated in terms of certificate complexity. In many applications of dynamic (di)graph problems, a certain form of lookahead is available. Specifically, we consider the problems of assembly planning in robotics and the maintenance of relations in databases. These give rise to dynamic strong connectivity and dynamic transitive closure problems, respectively. We explain why it is reasonable, and indeed natural and desirable, to assume that lookahead is available in these two applications. Exploiting lookahead to circumvent their inherent complexity, we obtain efficient fully-dynamic algorithms for strong connectivity and transitive closure.

  18. CCNA Certification All-In-One For Dummies

    CERN Document Server

    Angelescu, Silviu

    2010-01-01

    A complete preparation guide for the entry-level networking CCNA certification. If you're planning to advance your career by taking the all-important Cisco Certified Network Associate (CCNA), this is the study guide you need! Seven minibooks cover all the concepts and topics on which you'll be tested, covering the latest version of the exam. Each part of the exam is covered thoroughly in its own section, so you can readily find the information you want to study. Plenty of review questions help you prepare, and the companion CD-ROM includes the highly rated Dummies Test Engine so you can test y

  19. Investigating weaknesses in Android certificate security

    Science.gov (United States)

    Krych, Daniel E.; Lange-Maney, Stephen; McDaniel, Patrick; Glodek, William

    2015-05-01

    Android's application market relies on secure certificate generation to establish trust between applications and their users; yet, cryptography is often not a priority for application developers and many fail to take the necessary security precautions. Indeed, there is cause for concern: several recent high-profile studies have observed a pervasive lack of entropy on Web-systems leading to the factorization of private keys.1 Sufficient entropy, or randomness, is essential to generate secure key pairs and combat predictable key generation. In this paper, we analyze the security of Android certificates. We investigate the entropy present in 550,000 Android application certificates using the Quasilinear GCD finding algorithm.1 Our results show that while the lack of entropy does not appear to be as ubiquitous in the mobile markets as on Web-systems, there is substantial reuse of certificates only one third of the certificates in our dataset were unique. In other words, we find that organizations frequently reuse certificates for different applications. While such a practice is acceptable under Google's specifications for a single developer, we find that in some cases the same certificates are used for a myriad of developers, potentially compromising Android's intended trust relationships. Further, we observed duplicate certificates being used by both malicious and non-malicious applications. The top 3 repeated certificates present in our dataset accounted for a total of 11,438 separate APKs. Of these applications, 451, or roughly 4%, were identified as malicious by antivirus services.

  20. Analysis of the green certificate market

    International Nuclear Information System (INIS)

    This report studies the advantages and disadvantages of a separate financial market for the environmental advantages in the production of electricity from renewable energy sources. This market solution is evaluated against other financial systems used to promote the production of green electricity. By starting from a general equilibrium model for the green certificate market, the report discusses how the adaptation in the certificate market is influenced by changes in the market conditions. The certificate market is combined with a quota market for carbon dioxide, with and without international trade with electricity and certificate and market power in the production of electricity from renewable energy sources

  1. 8 CFR 1103.4 - Certifications.

    Science.gov (United States)

    2010-01-01

    ... agricultural worker and legalization cases—(1) General. The Commissioner or the Commissioner's delegate may.... (b) Certification of denials of special agricultural worker and legalization applications....

  2. A Title 40 Code of Federal Regulations Part 191 Evaluation of Buried Transuranic Waste at the Nevada Test Site

    International Nuclear Information System (INIS)

    In 1986, 21 m3 of transuranic (TRU) waste was inadvertently buried in a shallow land burial trench at the Area 5 Radioactive Waste Management Site on the Nevada Test Site (NTS). The U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office is considered five options for management of the buried TRU waste. One option is to leave the waste in-place if the disposal can meet the requirements of Title 40 Code of Federal Regulations (CFR) Part 191, 'Environmental Radiation Protection Standard for Management and Disposal of Spent Nuclear Fuel, High-Level, and Transuranic Radioactive Wastes'. This paper describes analyses that assess the likelihood that TRU waste in shallow land burial can meet the 40 CFR 191 standards for a geologic repository. The simulated probability of the cumulative release exceeding 1 and 10 times the 40 CFR 191.13 containment requirements is estimated to be 0.009 and less than 0.0001, respectively. The cumulative release is most sensitive to the number of groundwater withdrawal wells drilled through the disposal trench. The mean total effective dose equivalent for a member of the public is estimated to reach a maximum of 0.014 milli-Sievert (mSv) at 10,000 years, or approximately 10 percent of the 0.15 mSv 40 CFR 191.15 individual protection requirement. The dose is predominantly from inhalation of short-lived Rn-222 progeny in air produced by low-level waste disposed in the same trench. The transuranic radionuclide released in greatest amounts, Pu-239, contributes only 0.4 percent of the dose. The member of public dose is most sensitive to the U-234 inventory and the radon emanation coefficient. Reasonable assurance of compliance with the Subpart C groundwater protection standard is provided by site characterization data and hydrologic processes modeling which support a conclusion of no groundwater pathway within 10,000 years. Limited quantities of transuranic waste in a shallow land burial trench at the NTS can meet

  3. 77 FR 73334 - Adding International Energy Efficiency (IEE) Certificate to List of Certificates a Recognized...

    Science.gov (United States)

    2012-12-10

    ... SECURITY Coast Guard 46 CFR Part 8 RIN 1625-AB90 Adding International Energy Efficiency (IEE) Certificate... to add the International Energy Efficiency (IEE) Certificate to the list of certificates that a... the Protocol of 1978, has been amended to address energy efficiency for ships, and these...

  4. 7 CFR 205.400 - General requirements for certification.

    Science.gov (United States)

    2010-01-01

    ... MARKETING SERVICE (Standards, Inspections, Marketing Practices), DEPARTMENT OF AGRICULTURE (CONTINUED) ORGANIC FOODS PRODUCTION ACT PROVISIONS NATIONAL ORGANIC PROGRAM Certification § 205.400 General requirements for certification. A person seeking to receive or maintain organic certification under...

  5. China Initiates Voluntary Certification of Public Security Products

    Institute of Scientific and Technical Information of China (English)

    2004-01-01

    @@ Reporters learned from the Certification and Accreditation Administration of China(CNCA)that burglar-proof door became the first batch of voluntary certification product in public security products.China has formally initiated voluntary certification of public security products.

  6. 14 CFR 121.693 - Load manifest: All certificate holders.

    Science.gov (United States)

    2010-01-01

    ... 14 Aeronautics and Space 3 2010-01-01 2010-01-01 false Load manifest: All certificate holders. 121... manifest: All certificate holders. The load manifest must contain the following information concerning the... certificate holder....

  7. Study on plutonium distribution in Palomares ecosystem after an accidental aerosol release of transuranic radionuclides

    International Nuclear Information System (INIS)

    A discharge of plutonium and transuranic elements accidentally ocurred near Palomares (Almeria, Spain) in 1966. After decontamining operations, about 10 g of finely dispersed plutonium remained on the soil and was spreaded on the sorroundings and into Mediterranean sea. An analytical study including a 34 sampling sites of marine sediments, chemical clean-up, analytical methods for isolating plutonium from interfering radionuclides in the alfa-spectra was carried out. The detection limit level reached for the 239 u+240Pu was 10 mBq/Kg one of the lowest cited in the Spanish analytical literature until now. These results were attained following a careful electroplating Pu deposition method developed by our laboratory as result of the high signal/noise rates measured and a 20 KeV resolution. Several analytical assurance quality procedures specially developed for the Palomares ecological system were applied to the results, at the CIEMAT laboratories using reference standard certified samples. The values were unbiased and with no differences statistically significants between them. Interlaboratory comparisons were carried out. After 20 years of plutonium traces environmental transport their concentration were from two at three times the leves of radionuclides in the fallout of the zone studied. The plutonium concentration range in surface sediments was 0.3-5.0 Bq/Kg. The highest values corresponding in the coastal sediments and the lowest in the deep sea. Plutonium concentrations are highly correlated with the sediments structure, grain size composition and distance from the mouth of Almanzora river. The most important contribution at the transport from the land into sea could be the freshet occured at 1973. For this reason the plutonium ecologycal path has been from Palomares sorroundings into the sea. Sites in the Mediterranean sea not affected by plutonium apportation from Almanzora river showed Pu levels approximately the same as the mean value for the whole

  8. CNCA and MOFCOM Released Green Market Certification Rules

    Institute of Scientific and Technical Information of China (English)

    2004-01-01

    @@ Learned from the Certification and Accreditation Administration of the People's Republic of China (CNCA) on 9th June, the Green Market Certification Rules formulated by the Certification and Accreditation Administration of the People's Republic of China and the Ministry of Commerce (MOFCOM) will be formally implemented from the date of June 30. The Rules has defined specific requirements for the certification institutions and certification personnel engaged in the certification of Green Market.

  9. A NEW FOOD CHAIN APPROACH: UNI EN ISO 22005:2008 VOLUNTARY CERTIFICATION

    Directory of Open Access Journals (Sweden)

    E. Guidi

    2011-01-01

    Full Text Available This work summarize an experience of auditing according to new UNI EN ISO 22005:2008. This new food chain certification scheme, arisen from two different European schemes of internal and external traceability certification, requires companies to build up their own check plans considering all components in food chain processing. This new approach, also derived from the European legislation, wants to verify if traceability system is under control and to verify if corrective actions to warrant hygienic production standards are built up.

  10. Harmonisation of wind turbine certification in Europe JOULE project EWTC

    Energy Technology Data Exchange (ETDEWEB)

    Nath, C. [Germanischer Lloyd, Hamburg (Germany); Eriksson, C. [Det Norske Veritas, Hellerup (Denmark); Hulle, F. van [Frans van Hulle, Petten (Netherlands); Skamris, C. [Risoe National Lab., Roskilde (Denmark); Stam, W. [CIWI Holland, Arnheim (Netherlands); Vionis, P. [CRES, Attki (Greece)

    1999-03-01

    Wind turbine certification requirements are currently fairly divers within Europe. Therefore the leading European certification bodies initiated a JOULE project to harmonise the certification procedure on the basis of the current set of IEC/EN 61400 series standards. The paper presents a review of the state of the art of wind turbine certification in European countries and an outline of the sturcture of the project. The main steps of the project are (a) the collection of differences in certification practices by round robin certification of three wind turbine types; (b) assessment of the different certification results and (c) the development of a harmonised certification procedure. (au) EU-JOULE-3. 19 refs.

  11. Development of an Engineered Product Storage Concept for the UREX+1 Combined Transuranic/Lanthanide Product Streams

    International Nuclear Information System (INIS)

    The U.S. Department of Energy is developing next generation processing methods to recycle uranium and transuranic (TRU) isotopes from spent nuclear fuel. The objective of the 3-year project described in this report was to develop near-term options for storing TRU oxides isolated through the uranium extraction (UREX+) process. More specifically, a Zircaloy matrix cermet was developed as a storage form for transuranics with the understanding that the cermet also has the ability to serve as a inert matrix fuel form for TRU burning after intermediate storage. The goals of this research projects were: (1) to develop the processing steps required to transform the effluent TRU nitrate solutions and the spent Xircaloy cladding into a zireonium matrix cermet storage form; and (2) to evaluate the impact of phenomena that govern durability of the storage form, material processing, and TRU utilization in fast reactor fuel. This report represents a compilation of the results generated under this program. The information is presented as a brief technical narrative in the following sections with appended papers, presentations and academic theses to provide a detailed review of the project's accomplishments

  12. Evaluation of a self-guided transport vehicle for remote transportation of transuranic and other hazardous waste

    Energy Technology Data Exchange (ETDEWEB)

    Rice, P.M.; Moody, S.J.; Peterson, R. [and others

    1997-04-01

    Between 1952 and 1970, over two million cubic ft of transuranic mixed waste was buried in shallow pits and trenches in the Subsurface Disposal Area at the Idaho National Engineering Laboratory`s Radioactive Waste Management Complex. Commingled with this two million cubic ft of waste is up to 10 million cubic ft of fill soil. The pits and trenches were constructed similarly to municipal landfills with both stacked and random dump waste forms such as barrels and boxes. The main contaminants are micron-sized particles of plutonium and americium oxides, chlorides, and hydroxides. Retrieval, treatment, and disposal is one of the options being considered for the waste. This report describes the results of a field demonstration conducted to evaluate a technology for transporting exhumed transuranic wastes at the Idaho National Engineering and Environmental Laboratory (INEEL) and at other hazardous or radioactive waste sites through the U.S. Department of Energy complex. The full-scale demonstration, conducted at the INEEL Robotics Center in the summer of 1995, evaluated equipment performance and techniques for remote transport of exhumed buried waste. The technology consisted of a Self-Guided Transport Vehicle designed to remotely convey retrieved waste from the retrieval digface and transport it to a receiving/processing area with minimal human intervention. Data were gathered and analyzed to evaluate performance parameters such as precision and accuracy of navigation and transportation rates.

  13. Evaluation of a self-guided transport vehicle for remote transportation of transuranic and other hazardous waste

    International Nuclear Information System (INIS)

    Between 1952 and 1970, over two million cubic ft of transuranic mixed waste was buried in shallow pits and trenches in the Subsurface Disposal Area at the Idaho National Engineering Laboratory's Radioactive Waste Management Complex. Commingled with this two million cubic ft of waste is up to 10 million cubic ft of fill soil. The pits and trenches were constructed similarly to municipal landfills with both stacked and random dump waste forms such as barrels and boxes. The main contaminants are micron-sized particles of plutonium and americium oxides, chlorides, and hydroxides. Retrieval, treatment, and disposal is one of the options being considered for the waste. This report describes the results of a field demonstration conducted to evaluate a technology for transporting exhumed transuranic wastes at the Idaho National Engineering and Environmental Laboratory (INEEL) and at other hazardous or radioactive waste sites through the U.S. Department of Energy complex. The full-scale demonstration, conducted at the INEEL Robotics Center in the summer of 1995, evaluated equipment performance and techniques for remote transport of exhumed buried waste. The technology consisted of a Self-Guided Transport Vehicle designed to remotely convey retrieved waste from the retrieval digface and transport it to a receiving/processing area with minimal human intervention. Data were gathered and analyzed to evaluate performance parameters such as precision and accuracy of navigation and transportation rates

  14. New certification process starts. Pt. 2. Application of Building Information Modeling (BIM) for the certification according to DGNB; Zertifizierungsprozess auf ''neuen Beinen''. T. 2. Anwendung von Building Informationen (BIM) zur Zertifizierung nach DGNB

    Energy Technology Data Exchange (ETDEWEB)

    Essig, Bernd [SCHOLZE Consulting GmbH, Leinfelden-Echterdingen (Germany). Geschaeftsbereich Ingenieur-Beratungsleistungen in Facility-, Informations-, Qualitaets-, Nachhaltigkeitsmanagement und Energieberatung; Ernst, Tatjana [SCHOLZE Consulting GmbH, Leinfelden-Echterdingen (Germany)

    2013-04-01

    The overall life cycle plays a significant role in the certification by German Sustainable Building Council (Stuttgart, Federal Republic of Germany). In order that certification becomes much more than only a documentation, comprehensive data are requested already in an early phase of planning. Early investigations of alternatives may have a significant influence on the life cycle of a building. But, from where do the auditors achieve these amounts of data without overcharging the partners involved in the planning process with questions. The Building Information Modelling contributes to the development of the future enhancement of process quality by an innovative information management.

  15. 78 FR 28079 - Certificates of Compliance

    Science.gov (United States)

    2013-05-13

    .... 1110.3 would maintain these provisions, with minor grammatical changes, and would add 13 new... may be posted without change, including any personal identifiers, contact information, or other... on ``certificates of compliance,'' also referred to as ``certificates,'' on November 18, 2008 (73...

  16. 29 CFR 570.121 - Age certificates.

    Science.gov (United States)

    2010-07-01

    ... Provisions of the Fair Labor Standards Act of 1938, as Amended Oppressive Child Labor § 570.121 Age... person is above the oppressive child labor age.” An age certificate is a statement of a minor's age... 29 Labor 3 2010-07-01 2010-07-01 false Age certificates. 570.121 Section 570.121 Labor...

  17. 7 CFR 1570.1100 - Drawback certification.

    Science.gov (United States)

    2010-01-01

    ... OF AGRICULTURE EXPORT BONUS PROGRAMS SOAP and COAP Drawback Certification § 1570.1100 Drawback certification. An offer submitted by an exporter to FAS for an export bonus under the SOAP or the COAP must...: “None of the eligible commodity (sunflowerseed oil and/or cottonseed oil) has been or will be used...

  18. 7 CFR 54.24 - Appeal certificates.

    Science.gov (United States)

    2010-01-01

    ... certificate and stating the class, grade, other quality, or compliance of the products as shown by the appeal... AGRICULTURAL MARKETING ACT OF 1946 AND THE EGG PRODUCTS INSPECTION ACT (CONTINUED) MEATS, PREPARED MEATS, AND MEAT PRODUCTS (GRADING, CERTIFICATION, AND STANDARDS) Regulations Appeal Service § 54.24...

  19. 14 CFR 13.19 - Certificate action.

    Science.gov (United States)

    2010-01-01

    ... 14 Aeronautics and Space 1 2010-01-01 2010-01-01 false Certificate action. 13.19 Section 13.19... INVESTIGATIVE AND ENFORCEMENT PROCEDURES Legal Enforcement Actions § 13.19 Certificate action. (a) Under section... charges or other reasons upon which the Administrator bases the proposed action and, except in...

  20. 27 CFR 26.260 - Certificate.

    Science.gov (United States)

    2010-04-01

    ... 27 Alcohol, Tobacco Products and Firearms 1 2010-04-01 2010-04-01 false Certificate. 26.260 Section 26.260 Alcohol, Tobacco Products and Firearms ALCOHOL AND TOBACCO TAX AND TRADE BUREAU, DEPARTMENT... Port of Entry From the Virgin Islands § 26.260 Certificate. Persons (except tourists) bringing...

  1. Is Halal Certification Process “Green”?

    Directory of Open Access Journals (Sweden)

    Mohd Rizal Razalli

    2012-09-01

    Full Text Available These days, the environmental perspective on operations is becoming more common. In fact, any effort in improving efficiency in the organization is closely related to sustainability of our environment. The Environmental Management System (EMS certification such as ISO 14001 has been accepted as the world standard. In addition to these ISO standards, there are other certifications such as Halal certification. There is no research that investigates the relationship between Halal Certification process and its effect on our environment. Hence, our main research question is that is Halal Certification process can be considered as environmental friendly? In this paper, we argue that Halal Certification also contributes towards green initiatives. We used EDC-UUM as our case study. EDC-UUM is actively seeking the Halal certification from Malaysian authority agency or JAKIM. In this study, we assessed the perception of the EDC-UUM staff on the issue of going green. The findings and implications are discussed in the paper. Keywords: halal certification, hotel operations, sustainability, green

  2. 14 CFR 63.13 - Temporary certificate.

    Science.gov (United States)

    2010-01-01

    ... 14 Aeronautics and Space 2 2010-01-01 2010-01-01 false Temporary certificate. 63.13 Section 63.13 Aeronautics and Space FEDERAL AVIATION ADMINISTRATION, DEPARTMENT OF TRANSPORTATION (CONTINUED) AIRMEN... his application and supplementary documents and the issue of the certificate for which he applied....

  3. 14 CFR 65.13 - Temporary certificate.

    Science.gov (United States)

    2010-01-01

    ... 14 Aeronautics and Space 2 2010-01-01 2010-01-01 false Temporary certificate. 65.13 Section 65.13 Aeronautics and Space FEDERAL AVIATION ADMINISTRATION, DEPARTMENT OF TRANSPORTATION (CONTINUED) AIRMEN... review of his application and supplementary documents and the issue of the certificate and ratings...

  4. Trust Based Certificate Revocation for Secure Routing

    DEFF Research Database (Denmark)

    xmw970, xmw970

    2016-01-01

    Many trust establishment solutions in mobile ad hoc networks (MANETs) rely on public key certificates. Therefore, they should be accompanied by an efficient mechanism for certificate revocation and validation. In order to reduce the hazards from nodes and to enhance the security of network we...

  5. Brief Introduction to Compulsory Product Certification System

    Institute of Scientific and Technical Information of China (English)

    2004-01-01

    @@ What is Compulsory Product Certification System? Compulsory Product Certification System is a kind of product qualifying assessment system which implements under laws and regulations by states in order to protect life security of human, animals and plants as well as environmental protection and national security.

  6. 5 CFR 430.404 - Certification criteria.

    Science.gov (United States)

    2010-01-01

    ... MANAGEMENT Performance Appraisal Certification for Pay Purposes § 430.404 Certification criteria. (a) To be... that the performance expectations for senior employees meet the requirements of 5 CFR part 430... against program performance measures, as well as other relevant considerations; and (iii) Pay...

  7. 5 CFR 430.403 - System certification.

    Science.gov (United States)

    2010-01-01

    ....403 Administrative Personnel OFFICE OF PERSONNEL MANAGEMENT CIVIL SERVICE REGULATIONS PERFORMANCE MANAGEMENT Performance Appraisal Certification for Pay Purposes § 430.403 System certification. (a) The performance appraisal system(s) covering senior employees must be certified by OPM, with OMB concurrence,...

  8. 5 CFR 1330.403 - System certification.

    Science.gov (United States)

    2010-01-01

    ... PERSONNEL MANAGEMENT HUMAN RESOURCES MANAGEMENT Performance Appraisal Certification for Pay Purposes § 1330.403 System certification. (a) The performance appraisal system(s) covering senior employees must be... performance appraisal system(s) that meet the criteria. New appraisal systems established under 5 CFR part...

  9. 15 CFR 996.22 - Certification.

    Science.gov (United States)

    2010-01-01

    ... products; and conveys no automatic, direct or indirect NOAA endorsement of any product or service. (c... NOAA HYDROGRAPHIC PRODUCTS AND SERVICES Certification of a Hydrographic Product and Decertification. § 996.22 Certification. (a) A hydrographic product that has passed the compliance tests...

  10. Waste receiving and processing facility module 1 data management system software project management plan

    International Nuclear Information System (INIS)

    This document provides the software development plan for the Waste Receiving and Processing (WRAP) Module 1 Data Management System (DMS). The DMS is one of the plant computer systems for the new WRAP 1 facility (Project W-026). The DMS will collect, store, and report data required to certify the low level waste (LLW) and transuranic (TRU) waste items processed at WRAP 1 as acceptable for shipment, storage, or disposal

  11. Preliminary identification of interfaces for certification and transfer of TRU waste to WIPP

    International Nuclear Information System (INIS)

    This study complements the national program to certify that newly generated and stored, unclassified defense transuranic (TRU) wastes meet the Waste Isolation Pilot Plant (WIPP) Waste Acceptance Criteria. The objectives of this study were to identify (1) the existing organizational structure at each of the major waste-generating and shipping sites and (2) the necessary interfaces between the waste shippers and WIPP. The interface investigations considered existing waste management organizations at the shipping sites and the proposed WIPP organization. An effort was made to identify the potential waste-certifying authorities and the lines of communication within these organizations. The long-range goal of this effort is to develop practicable interfaces between waste shippers and WIPP to enable the continued generation, interim storage, and eventual shipment of certified TRU wastes to WIPP. Some specific needs identified in this study include: organizational responsibility for certification procedures and quality assurance (QA) program; simple QA procedures; and specification and standardization of reporting forms and procedures, waste containers, and container labeling, color coding, and code location

  12. Department of Transportation -- Exemption for using the Transuranic Package Transporter-I (TRUPACT-I) at the Idaho National Engineering Laboratory (Code of Federal Regulations, Title 49, Part 107, Subpart B -- Exemptions, 107-103 Application for Exemption)

    International Nuclear Information System (INIS)

    Exemption from specific regulations is being sought for the Transuranic Package Transporter Model I (TRUPACT-I) container. The design has successfully undergone extensive testing of a quarter-scale model and a full-scale prototype of the container. Results from the analysis and testing are in the TRUPACT-1 Safely Analysis Report for Packaging (SARP), GA-Al8695/SAND 87-7104 (TTC0735), April 1987 (see Attachment 1). The container was never certified or used because of questions raised during the certification process. Two features of the container design failed to satisfy the regulations for Type B packaging. First, the design utilizes a venting system to control internal and external pressures; this venting system is not allowed by the Code of Federal Regulations, Title 10, Parts 71(h) and 71.51(b) [10 CFR 71.(h) and 71.51(b)]. Second, the maximum quantity fissile material proposed to be hauled in TRUPACT-I exceeded the limits in 10 CFR 71.63(b) for a single-containment container. To correct these design deficiencies, the vents would be plugged during transport, and the maximum quantity of fissile material would be limited to the allowables for a single-containment container. An engineering analysis showed that the container could safely transport radioactive material within the boundaries of the Idaho National Engineering Laboratory (INEL) with the vent system plugged (see Attachment 2). However, some of the requirements for determining pressure on a container need to be changed (i.e., exempted) to reflect conditions unique to the INEL. The following are the requirements needing to be changed for INEL conditions, variances being sought, and justifications for the variances

  13. Maintenance of Certification for Radiation Oncology

    International Nuclear Information System (INIS)

    Maintenance of Certification (MOC) recognizes that in addition to medical knowledge, several essential elements involved in delivering quality care must be developed and maintained throughout one's career. The MOC process is designed to facilitate and document professional development of American Board of Radiology (ABR) diplomates in the essential elements of quality care in Radiation Oncology and Radiologic Physics. ABR MOC has been developed in accord with guidelines of the American Board of Medical Specialties. All Radiation Oncology certificates issued since 1995 are 10-year, time-limited certificates; diplomates with time-limited certificates who wish to maintain specialty certification must complete specific requirements of the American Board of Radiology MOC program. Diplomates with lifelong certificates are not required to participate but are strongly encouraged to do so. Maintenance of Certification is based on documentation of participation in the four components of MOC: (1) professional standing, (2) lifelong learning and self-assessment, (3) cognitive expertise, and (4) performance in practice. Through these components, MOC addresses six competencies-medical knowledge, patient care, interpersonal and communication skills, professionalism, practice-based learning and improvement, and systems-based practice. Details of requirements for components 1, 2, and 3 of MOC are outlined along with aspects of the fourth component currently under development

  14. 14 CFR 63.15 - Duration of certificates.

    Science.gov (United States)

    2010-01-01

    ... 14 Aeronautics and Space 2 2010-01-01 2010-01-01 false Duration of certificates. 63.15 Section 63...) AIRMEN CERTIFICATION: FLIGHT CREWMEMBERS OTHER THAN PILOTS General § 63.15 Duration of certificates. (a... month in which the certificate was issued or renewed. However, the holder may exercise the privileges...

  15. 77 FR 37385 - Export Trade Certificate of Review

    Science.gov (United States)

    2012-06-21

    ... International Trade Administration Export Trade Certificate of Review ACTION: Notice of Application for an Export Trade Certificate of Review Colombia Poultry Export Quota, Inc. (COLOM-PEQ). SUMMARY: The Office... received an application for an Export Trade Certificate of Review (``Certificate''). This notice...

  16. 29 CFR 570.12 - Revoked certificates of age.

    Science.gov (United States)

    2010-07-01

    ... 29 Labor 3 2010-07-01 2010-07-01 false Revoked certificates of age. 570.12 Section 570.12 Labor... REGULATIONS, ORDERS AND STATEMENTS OF INTERPRETATION Certificates of Age § 570.12 Revoked certificates of age. A certificate which has been revoked as proof of age under the Act shall be of no force and...

  17. 15 CFR 325.10 - Modifying or revoking a certificate.

    Science.gov (United States)

    2010-01-01

    ... 15 Commerce and Foreign Trade 2 2010-01-01 2010-01-01 false Modifying or revoking a certificate... CERTIFICATES OF REVIEW § 325.10 Modifying or revoking a certificate. (a) Action subject to modification or revocation. The Secretary shall revoke a certificate, in whole or in part, or modify it, as the Secretary...

  18. 40 CFR 90.106 - Certificate of conformity.

    Science.gov (United States)

    2010-07-01

    ... 40 Protection of Environment 20 2010-07-01 2010-07-01 false Certificate of conformity. 90.106... Standards and Certification Provisions § 90.106 Certificate of conformity. (a)(1) Except as provided in § 90... certificate of conformity covering such engines; however, engines manufactured during an annual...

  19. 40 CFR 91.106 - Certificate of conformity.

    Science.gov (United States)

    2010-07-01

    ... 40 Protection of Environment 20 2010-07-01 2010-07-01 false Certificate of conformity. 91.106... Provisions § 91.106 Certificate of conformity. (a) Every manufacturer of a new marine SI engine produced... obtain a certificate of conformity covering each engine family. The certificate of conformity must...

  20. 40 CFR 89.105 - Certificate of conformity.

    Science.gov (United States)

    2010-07-01

    ... 40 Protection of Environment 20 2010-07-01 2010-07-01 false Certificate of conformity. 89.105... and Certification Provisions § 89.105 Certificate of conformity. Every manufacturer of a new nonroad compression-ignition engine must obtain a certificate of conformity covering the engine family, as...

  1. National Board Certification: It's Time for Preschool Teachers!

    Science.gov (United States)

    Gillentine, Jonathan

    2010-01-01

    National Board Certification is a voluntary process by which teachers of students ages 3 through 18 demonstrate accomplished teaching. This article describes the process and certification requirements for one certificate--the Early Childhood/Generalist (ECG), for teachers of children ages 3 through 8. The National Board Certification process was…

  2. Certification of a weld produced by friction stir welding

    Energy Technology Data Exchange (ETDEWEB)

    Obaditch, Chris; Grant, Glenn J

    2013-10-01

    Methods, devices, and systems for providing certification of friction stir welds are disclosed. A sensor is used to collect information related to a friction stir weld. Data from the sensor is compared to threshold values provided by an extrinsic standard setting organizations using a certification engine. The certification engine subsequently produces a report on the certification status of the weld.

  3. 46 CFR 107.409 - Safety Construction Certificate.

    Science.gov (United States)

    2010-10-01

    ... 46 Shipping 4 2010-10-01 2010-10-01 false Safety Construction Certificate. 107.409 Section 107.409... § 107.409 Safety Construction Certificate. (a) Application for a Safety Construction Certificate is made... international voyages a Safety Construction Certificate if the unit meets the requirements in Regulation 12...

  4. 46 CFR 176.310 - Certification Expiration Date Stickers.

    Science.gov (United States)

    2010-10-01

    ... 46 Shipping 7 2010-10-01 2010-10-01 false Certification Expiration Date Stickers. 176.310 Section... Letters § 176.310 Certification Expiration Date Stickers. (a) A Certification Expiration Date Sticker... operated without a valid Certification Expiration Date Sticker affixed to the vessel on a place that is:...

  5. Certification Programs for Criminalists - Historical Development.

    Science.gov (United States)

    Bernett, P D

    2008-01-01

    Certification is the process by which individual practitioners of a profession are deemed competent, by a peer review process, to practice that profession. Criminalistics is a rather young profession, and until the recent publicity occasioned by a myriad of television dramas and documentaries, a rather obscure one. There has been little oversight of the profession and little call for such oversight until the 1970s. The calls for oversight primarily came from those outside the profession and with only a peripheral interest in the profession. In response, the profession itself began to consider the development of a process of self-review and to establish certification criteria (a) by which the competence of practitioners could be assessed in a way that would be acceptable to practitioners; (b) equitable to the diverse jobs requirements of various practitioners; useful for external evaluation by users of professional services; and, above all, (c) be a realistic method to evaluate the ability of the practitioner to engage in the professional practice of forensic science. Professional certification of criminalists was first suggested at a meeting of the California Association of Criminalists (CAC) in 1975. This initial proposal was taken to the broader national criminalistics community through the efforts of the Criminalistics Certification Study Committee (CCSC) beginning in 1976. Subjected in 1978 to a national referendum of practitioners, CCSC's proposal was rejected. Undaunted by national rejection, in 1986 the CAC renewed efforts to develop a certification process for its members, which resulted in the offering of the first certification examination in 1989. Since the initial certification examination by the CAC, certification of criminalists has evolved through the activities of the American Board of Criminalistics (ABC). Efforts have been continuously made to refine the process to more closely reflect the demands of the profession. The evolution has been slow

  6. High-dimensional entanglement certification.

    Science.gov (United States)

    Huang, Zixin; Maccone, Lorenzo; Karim, Akib; Macchiavello, Chiara; Chapman, Robert J; Peruzzo, Alberto

    2016-06-17

    Quantum entanglement is the ability of joint quantum systems to possess global properties (correlation among systems) even when subsystems have no definite individual property. Whilst the 2-dimensional (qubit) case is well-understood, currently, tools to characterise entanglement in high dimensions are limited. We experimentally demonstrate a new procedure for entanglement certification that is suitable for large systems, based entirely on information-theoretics. It scales more efficiently than Bell's inequality and entanglement witness. The method we developed works for arbitrarily large system dimension d and employs only two local measurements of complementary properties. This procedure can also certify whether the system is maximally entangled. We illustrate the protocol for families of bipartite states of qudits with dimension up to 32 composed of polarisation-entangled photon pairs.

  7. Conceptual design of retrieval systems for emplaced transuranic waste containers in a salt bed depository. Final report

    International Nuclear Information System (INIS)

    The US Department of Energy and the Nuclear Regulatory Commission have jurisdiction over the nuclear waste management program. Design studies were previously made of proposed repository site configurations for the receiving, processing, and storage of nuclear wastes. However, these studies did not provide operational designs that were suitable for highly reliable TRU retrieval in the deep geologic salt environment for the required 60-year period. The purpose of this report is to develop a conceptual design of a baseline retrieval system for emplaced transuranic waste containers in a salt bed depository. The conceptual design is to serve as a working model for the analysis of the performance available from the current state-of-the-art equipment and systems. Suggested regulations would be based upon the results of the performance analyses

  8. Sequential separation of transuranic elements and fission products from uranium metal ingots in electrolytic reduction process of spent PWR fuels

    International Nuclear Information System (INIS)

    A sequential separation procedure has been developed for the determination of transuranic elements and fission products in uranium metal ingot samples from an electrolytic reduction process for a metallization of uranium dioxide to uranium metal in a medium of LiCl-Li2O molten salt at 650 deg C. Pu, Np and U were separated using anion-exchange and tri-n-butylphosphate (TBP) extraction chromatography. Cs, Sr, Ba, Ce, Pr, Nd, Sm, Eu, Gd, Zr and Mo were separated in several groups from Am and Cm using TBP and di(2-ethylhexyl)phosphoric acid (HDEHP) extraction chromatography. Effect of Fe, Ni, Cr and Mg, which were corrosion products formed through the process, on the separation of the analytes was investigated in detail. The validity of the separation procedure was evaluated by measuring the recovery of the stable metals and 239Pu, 237Np, 241Am and 244Cm added to a synthetic uranium metal ingot dissolved solution. (author)

  9. Accident analysis for transuranic waste management alternatives in the U.S. Department of Energy waste management program

    International Nuclear Information System (INIS)

    Preliminary accident analyses and radiological source term evaluations have been conducted for transuranic waste (TRUW) as part of the US Department of Energy (DOE) effort to manage storage, treatment, and disposal of radioactive wastes at its various sites. The approach to assessing radiological releases from facility accidents was developed in support of the Office of Environmental Management Programmatic Environmental Impact Statement (EM PEIS). The methodology developed in this work is in accordance with the latest DOE guidelines, which consider the spectrum of possible accident scenarios in the implementation of various actions evaluated in an EIS. The radiological releases from potential risk-dominant accidents in storage and treatment facilities considered in the EM PEIS TRUW alternatives are described in this paper. The results show that significant releases can be predicted for only the most severe and extremely improbable accidents sequences

  10. Hybrid systems for transuranic waste transmutation in nuclear power reactors: state of the art and future prospects

    International Nuclear Information System (INIS)

    The features of subcritical hybrid systems (HSs) are discussed in the context of burning up transuranic wastes from the U-Pu nuclear fuel cycle. The advantages of HSs over conventional atomic reactors are considered, and fuel cycle closure alternatives using HSs and fast neutron reactors are comparatively evaluated. The advantages and disadvantages of two HS types with neutron sources (NSs) of widely different natures -- nuclear spallation in a heavy target by protons and nuclear fusion in magnetically confined plasma -- are discussed in detail. The strengths and weaknesses of HSs are examined, and demand for them for closing the U-Pu nuclear fuel cycle is assessed. (instruments and methods of investigation)

  11. Underground storage tank 511-D1U1 closure plan

    Energy Technology Data Exchange (ETDEWEB)

    Mancieri, S.; Giuntoli, N.

    1993-09-01

    This document contains the closure plan for diesel fuel underground storage tank 511-D1U1 and appendices containing supplemental information such as staff training certification and task summaries. Precision tank test data, a site health and safety plan, and material safety data sheets are also included.

  12. Licensing and Certification District Offices, California

    Data.gov (United States)

    U.S. Department of Health & Human Services — This data contains a list of California Licensing and Certification District Offices. The California Department of Public Health, Center for Health Care Quality,...

  13. Green certificates, a tool for market development

    International Nuclear Information System (INIS)

    To achieve a place for renewable energy the Government of the Netherlands has followed a market oriented approach. In view of the rapidly emerging liberalized energy market the government followed an approach with both support to producers and a demand-driven approach. With a fully liberalized market for green electricity with free consumer choice and the tradable certificate for renewable energy a market has been developed. In view of the slow domestic growth in production a new support mechanism was introduced called the environmental quality of power production (MEP) for renewable electricity in the Netherlands in 2003. This paper evaluates the market development over the last years with the green certificate system and the rapid growing market of green electricity. In 2004 the green certificate is EU-wide replaced by the Certificate of Origin. (author)

  14. 40 CFR 86.1848-10 - Certification.

    Science.gov (United States)

    2010-07-01

    ... Provisions for Control of Air Pollution From New and In-Use Light-Duty Vehicles, Light-Duty Trucks, and... incomplete light-duty trucks and incomplete heavy-duty vehicles, a certificate covers only those new...

  15. FY 2001 Hanford Waste Management Strategic Plan

    International Nuclear Information System (INIS)

    We are pleased to present the 2001 Hanford Waste Management Program Strategic Plan. This plan supports the newly developed U. S. Department of Energy Site outcomes strategy. The 2001 Plan reflects current and projected needs for Waste Management Program services in support of Hanford Site cleanup, and updates the objectives and actions using new waste stream oriented logic for the strategic goals: (1) waste treatment/processing, storage, and disposal; (2) interfaces; and (3) program excellence. Overall direction for the Program is provided by the Waste Management Division, Office of the Assistant Manager for Environmental Restoration and Waste Management, U. S. Department of Energy, Richland Operations Office. Fluor Hanford, Inc. is the operating contractor for the program. This Plan documents proactive strategies for planning and budgeting, with a major focus on helping meet regulatory commitments in a timely and efficient manner and concurrently assisting us in completing programs cheaper, better and quicker. Newly developed waste stream oriented logic was incorporated to clarify Site outcomes. External drivers, technology inputs, treatment/processing, storage and disposal strategies, and stream specific strategies are included for the six major waste types addressed in this Plan (low-level waste, mixed low-level waste, contact-handled transuranic waste, remote-handled transuranic waste, liquid waste, and cesium/strontium capsules). The key elements of the strategy are identification and quantification of the needs for waste management services, assessment of capabilities, and development of cost-effective actions to meet the needs and to continuously improve performance. Accomplishment of specific actions as set forth in the Plan depends on continued availability of the required resources and funding. The primary objectives of Plan are: (1) enhance the Waste Management Program to improve flexibility, become more holistic especially by implementing new

  16. Home Energy Professional Certifications (Fact Sheet)

    Energy Technology Data Exchange (ETDEWEB)

    2012-11-01

    As the weatherization and home energy upgrade industries expand and gain recognition, the need for a qualified workforce becomes more apparent. The certification component of the Guidelines project was designed to create meaningful and lasting careers for weatherization workers. Intended for experienced home energy professionals, the four new certifications focus on the most common jobs in the industry: energy auditor, retrofit installer technician, crew leader, and quality control inspector.

  17. Use of death certificates for mesothelioma surveillance.

    OpenAIRE

    L K Davis; Martin, T R; Kligler, B

    1992-01-01

    Data from the Massachusetts Cancer Registry and death certificates were linked for mesothelioma cases reported to the registry from 1982 through 1987 to determine the extent to which the cause of death information that is given on the death certificate is useful in identifying mesothelioma cases for disease surveillance. Only 12 percent of all persons reported with mesothelioma who had died were detected using underlying cause of death codes for cancers of the peritoneum and pleura, which are...

  18. Fissionable material handlers certification training program

    International Nuclear Information System (INIS)

    A formal program for certification of fissionable material handlers is presented that cultivates safe working practices. This certification complies with the training requirements of the Department of Energy Directive 0530 (ERDA Manual Chapter 0530), Nuclear Criticality Safety. The program consists of a series of classroom lectures, on-the-job training, and examinations in criticality safety, radiation protection, industrial safety, emergency procedures, and the employee's specific work operations. The program for recertification is also discussed

  19. PEM public key certificate cache server

    Science.gov (United States)

    Cheung, T.

    1993-12-01

    Privacy Enhanced Mail (PEM) provides privacy enhancement services to users of Internet electronic mail. Confidentiality, authentication, message integrity, and non-repudiation of origin are provided by applying cryptographic measures to messages transferred between end systems by the Message Transfer System. PEM supports both symmetric and asymmetric key distribution. However, the prevalent implementation uses a public key certificate-based strategy, modeled after the X.509 directory authentication framework. This scheme provides an infrastructure compatible with X.509. According to RFC 1422, public key certificates can be stored in directory servers, transmitted via non-secure message exchanges, or distributed via other means. Directory services provide a specialized distributed database for OSI applications. The directory contains information about objects and then provides structured mechanisms for accessing that information. Since directory services are not widely available now, a good approach is to manage certificates in a centralized certificate server. This document describes the detailed design of a centralized certificate cache serve. This server manages a cache of certificates and a cache of Certificate Revocation Lists (CRL's) for PEM applications. PEMapplications contact the server to obtain/store certificates and CRL's. The server software is programmed in C and ELROS. To use this server, ISODE has to be configured and installed properly. The ISODE library 'libisode.a' has to be linked together with this library because ELROS uses the transport layer functions provided by 'libisode.a.' The X.500 DAP library that is included with the ELROS distribution has to be linked in also, since the server uses the DAP library functions to communicate with directory servers.

  20. Radiation worker certification at Pantex Plant

    International Nuclear Information System (INIS)

    The Pantex Plant Radiation Worker Certification program is designed to educate users of radiation emitting equipment in the basic areas of radiation safety. Formal classroom instruction is supplemented with on-the-job training. Certification is granted upon the completion of written and oral proficiency examinations. In addition, the program has provisions for training and designating maintenance and repair personnel to work only on specific equipment

  1. IAHSS certification rollout: helping officers succeed.

    Science.gov (United States)

    Tarvin-Peek, Kit

    2016-01-01

    After determining that security staff should obtain IAHSS certification on every level to help reduce the risk for mishandling of incidents and enhance the health system's reputation for being a "best practice" organization, security managers, working with Human Resources, developed a special training program designed to maximize the chances of an individual officer and supervisor attaining such certification. In this article, the author reviews this training program. PMID:26978951

  2. Financial benefits of an ISO 9001 certification

    OpenAIRE

    Ari Hróbjartsson 1983

    2012-01-01

    Several companies in Iceland have received ISO 9001 certification in recent years. It has been researched qualitatively whether there is a financial benefit from getting ISO 9001 certification in Iceland but it has never been researched quantitatively. In this research all ISO 9001 certified companies that were operating in a competitive market in Iceland were compared to similar companies in an effort to find out if there was a financial benefit from becoming ISO 9001 certified. The result o...

  3. Package certification and validation of certificates from an industry perspective

    International Nuclear Information System (INIS)

    This paper considers the many aspects of the package certification and validation process, from an Industry perspective, to identify ways to further enhance the efficiency of the regulatory function. The challenge is to achieve these enhancements without a conflict of interest or the perception of a conflict of interest whilst ensuring that the regulator remains clearly independent. The Competent Authorities (CAs), responsible for regulating the transport of radioactive materials around the world, have developed procedures for the overview of the package design and shipment approval process that includes Pre-Transport license application activities; package testing programmes; license application guidance and technical reviews of the applications. There is an impressive degree of competence, experience, and knowledge among the Competent Authorities in the provision of the regulatory function. There is a great deal of constructive interaction between team members, the different CAs and the CAs with Industry; considering the quantity of work. In providing its radioactive material transport regulatory programme over recent years, the CA has demonstrated a commendable openness and a strong desire to be transparent with regard to the vital regulatory activities. The manner in which the CAs support Industry is a demonstration of the commitment to an excellent safety culture in its transport regulations. (author)

  4. The waste isolation pilot plant. Permanent isolation of defense transuranic waste in deep geologic salt. A national solution and international model

    Energy Technology Data Exchange (ETDEWEB)

    Franco, Jose; Van Luik, Abraham [US Department of Energy, Carlsbad, NM (United States). Carlsbad Field Office

    2015-07-01

    The Waste Isolation Pilot Plant is located about 42 kilometers from the city of Carlsbad, New Mexico. It is an operating deep geologic repository in bedded salt 657 meters below the surface of the Chihuahuan desert. Since its opening in March of 1999, it has received about 12,000 shipments totaling about 91,000 cubic meters of defense related transuranic (TRU) wastes. Twenty-two sites have been cleaned up of their defense-legacy TRU waste. The WIPP's shipping program has an untarnished safety record and its trucks and trailers have safely traveled the equivalent of about 60 round-trips to the Moon. WIPP received, and deserved, a variety of safety accolades over its nearly 15 year working life. In February of 2014, however, two incidents resulted in a major operational suspension and reevaluation of its safety systems, processes and equipment. The first incident was an underground mining truck fire, followed nine days later by an airborne radiation release incident. Accident Investigation Board (AIB) reports on both incidents point to failures of plans, procedures and persons. The AIB recommendations for recovery from both these incidents are numerous and are being carefully implemented. One major recommendation is to no longer have different maintenance and safety requirements for nuclear handling equipment and mining equipment. Maintenance and cleanliness of mining equipment was cited as a contributing cause to the underground fire, and the idea that there can be lesser rigor in taking care of mining equipment, when it is being operated in the same underground space as the waste handling equipment, is not tenable. At some point in the future, the changes made in response to these two incidents will be seen as a valuable lesson learned on behalf of future repository programs. WIPP will once again be seen as a ''pilot'' in the nautical sense, in terms of 'showing the way' - the way to a national and international radioactive waste

  5. The waste isolation pilot plant. Permanent isolation of defense transuranic waste in deep geologic salt. A national solution and international model

    International Nuclear Information System (INIS)

    The Waste Isolation Pilot Plant is located about 42 kilometers from the city of Carlsbad, New Mexico. It is an operating deep geologic repository in bedded salt 657 meters below the surface of the Chihuahuan desert. Since its opening in March of 1999, it has received about 12,000 shipments totaling about 91,000 cubic meters of defense related transuranic (TRU) wastes. Twenty-two sites have been cleaned up of their defense-legacy TRU waste. The WIPP's shipping program has an untarnished safety record and its trucks and trailers have safely traveled the equivalent of about 60 round-trips to the Moon. WIPP received, and deserved, a variety of safety accolades over its nearly 15 year working life. In February of 2014, however, two incidents resulted in a major operational suspension and reevaluation of its safety systems, processes and equipment. The first incident was an underground mining truck fire, followed nine days later by an airborne radiation release incident. Accident Investigation Board (AIB) reports on both incidents point to failures of plans, procedures and persons. The AIB recommendations for recovery from both these incidents are numerous and are being carefully implemented. One major recommendation is to no longer have different maintenance and safety requirements for nuclear handling equipment and mining equipment. Maintenance and cleanliness of mining equipment was cited as a contributing cause to the underground fire, and the idea that there can be lesser rigor in taking care of mining equipment, when it is being operated in the same underground space as the waste handling equipment, is not tenable. At some point in the future, the changes made in response to these two incidents will be seen as a valuable lesson learned on behalf of future repository programs. WIPP will once again be seen as a ''pilot'' in the nautical sense, in terms of 'showing the way' - the way to a national and international radioactive waste

  6. WRAP module 1 treatment plan

    International Nuclear Information System (INIS)

    This document provides the methodology to treat waste in the Waste Receiving and Processing Module 1 facility to meet the Resource Conservation and Recovery Act (RCRA) land disposal restrictions or the Waste Isolation and Pilot Plant waste acceptance criteria. This includes Low-Level Mixed Waste, Transuranic Waste, and Transuranic Mixed Waste

  7. Waste Isolation Pilot Plant Strategic Plan

    International Nuclear Information System (INIS)

    The purpose of the Waste Isolation Pilot Plant (WIPP) Strategic Plan is to provide decision makers, project participants, and the public with a high-level overview of the objectives, issues, and strategiesthat impact a decision on the suitability of WIPP as a permanent, safe disposal facility for transuranic (TRU) waste that has resulted from defense activities. This document is a component of an integrated planning process and is a key management tool that is coordinated and consistent with the Secretary's Disposal Decision Plan and the Environmental Restoration and Waste Management (EM) Five-Year Plan. This documentsupports other US Department of Energy (DOE) planning efforts, including the TRU Waste Program. The WIPP Strategic Plan addresses the WIPP Program Test Phase, Disposal Decision, Disposal Phase, and Decommissioning Phase (decontamination and decommissioning). It describes the actions and activities that the DOE will conduct to ensure that WIPP will comply with applicable, relevant, and appropriate requirements of the US Environmental Protection Agency (EPA), State of New Mexico, and other applicable federal and state regulations. It also includes the key assumptions under which the strategy was developed. A comprehensive discussion of the multitude of activities involved in the WIPP Program cannot be adequately presented in this document. The specific details of these activities are presented in other, more detailed WIPP planningdocuments

  8. Software Quality Certification: identifying the real obstacles

    Directory of Open Access Journals (Sweden)

    Megan Baker

    1996-05-01

    Full Text Available A case study of software certification reveals the real difficulty of certifying quality beyond superficial assessment - readers are invited to form their own conclusions. AS 3563 Software Quality Management System is the Australian version of ISO 9001, developed specifically for the software industry. For many Australian software houses, gaining certification with AS 3563 is a priority since certification has become a prerequisite to doing business with government departments and major corporations. However, the process of achieving registration with this standard is a lengthy and resource intensive process, and may have little impact on actual software quality. This case study recounts the experience of the consulting arm of one of Australia's accounting firms in its quest for certification. By using a number of specific management strategies this company was able to successfully implement AS 3563 in less than half the time usually taken to achieve certification - a feat for which its management should be congratulated. However, because the focus of the project was on gaining certification, few internal benefits have been realised despite the successful implementation of the standard.

  9. Test plan for a live drum survey using the gamma-neutron sensor

    Energy Technology Data Exchange (ETDEWEB)

    Gehrke, R.J.; Roybal, L.G.; Thompson, D.N.

    1995-07-01

    This plan describes performance tests to be made with the Gamma/Neutron Sensor (GNS), which that was designed and built for infield assay at an excavation site. The performance tests will be performed in Building WMF-628 in the Transuranic Storage Area of the Radioactive Waste Management Complex at the Idaho National Engineering Laboratory on stored 55-gal drums of transuranic waste from the Rocky Flats Plant. The GNS is mounted on a wooden pallet that will allow horizontal and vertical scans of the stacked drums. Scanning speed and GNS sensitivity for gamma and neutron radiation fields will be estimated. Effects of temperature, electronic, and acoustic noise will be evaluated. Two- and three-dimensional plots of radiation field as a function of position will be developed from the data.

  10. Waste Isolation Pilot Plant (WIPP) five-year Site Specific Plan

    International Nuclear Information System (INIS)

    The Waste Isolation Pilot Plant (WIPP), located 26 miles east of Carlsbad, New Mexico, is a research and development facility vested with the vital mission of demonstrating the safe disposal of radioactive transuranic (TRU) wastes resulting from our nation's defense activities and programs. It is the only facility in the United States specifically designed and constructed for the long-term storage of transuranic wastes. Since the inception of the WIPP project, work has continued to prepare the facility to receive TRU waste. A multitude of studies have been and continue to be conducted to demonstrate the safety of the WIPP facility in accordance with federal and state laws, state agreements, DOE Orders, etc. This Site Specific Plan outlines the implementation of activities at the WIPP project. 12 figs

  11. Agreement between death-certificate and autopsy diagnoses among atomic-bomb survivors

    International Nuclear Information System (INIS)

    Using the Atomic Bomb Casualty Commission/Radiation Effects Research Foundation series of over 5000 autopsies, we examined death-certificate accuracy for several disease categories and assessed the effect of potential modifying factors on this accuracy. For 12 cause-of-death categories, the overall percent agreement between death-certificate and autopsy diagnoses was only 52.5%. Although neoplasms had the highest detection rate (on the death certificate) in the study, still almost 25% of cancers diagnosed at autopsy were missed on the death certificate. Only for neoplasms and external causes of death were confirmation and detection rates above 70%. Confirmation rates were between 50% and 70% for infectious and parasitic diseases and heart and other vascular diseases. Detection rates reached a similar level for infectious and parasitic, cerebrovascular, and digestive diseases. Specificity rates were above 90% for all but the cerebrovascular disease category. Overall agreement decreased with increasing age of the decedents and was lower for deaths occurring outside of hospital vs those occurring in a hospital. There was some suggestion that agreement rates were higher for more-recent deaths but no indication that radiation dose, sex, city of residence, or inclusion in a biennial clinical-examination program influenced agreement. Because the inaccuracy of death-certificate diagnoses can have major implications for many aspects of health research and planning, it is important to be aware that death-certificate accuracy is low and can vary widely depending on the patient's age at death and the place of death. (J.P.N.)

  12. 21 CFR 80.35 - Color additive mixtures; certification and exemption from certification.

    Science.gov (United States)

    2010-04-01

    ... 21 Food and Drugs 1 2010-04-01 2010-04-01 false Color additive mixtures; certification and exemption from certification. 80.35 Section 80.35 Food and Drugs FOOD AND DRUG ADMINISTRATION, DEPARTMENT OF... number assigned by the Food and Drug Administration to the certified straight color components, but...

  13. Tradable white certificate schemes : what can we learn from tradable green certificate schemes?

    NARCIS (Netherlands)

    Oikonomou, Vlasis; Mundaca, Luis

    2008-01-01

    In this paper, we analyze the experiences gained from tradable green certificate (TGC) schemes and extract some policy lessons that can lead to a successful design of a market-based approach for energy efficiency improvement, alias tradable white certificate schemes. We use tradable green certificat

  14. 76 FR 22785 - Direct Certification and Certification of Homeless, Migrant and Runaway Children for Free School...

    Science.gov (United States)

    2011-04-25

    ... amended to conform with changes made in the November 13, 2007, interim regulation (72 FR 63785) that... provision was added in the interim rulemaking dated November 13, 2007, (72 FR 63793), we did not address how... Certification and Certification of Homeless, Migrant and Runaway Children for Free School Meals AGENCY: Food...

  15. 77 FR 60096 - Adding International Energy Efficiency (IEE) Certificate to List of Certificates a Recognized...

    Science.gov (United States)

    2012-10-02

    ... SECURITY Coast Guard 46 CFR Part 8 RIN 1625-AB90 Adding International Energy Efficiency (IEE) Certificate... Alternatives regulations to add the International Energy Efficiency (IEE) Certificate to the list of..., as modified by the Protocol of 1978, has been amended to address energy efficiency for ships,...

  16. Enacting Third-Party Certification: A Case Study of Science and Politics in Organic Shrimp Certification

    Science.gov (United States)

    Konefal, Jason; Hatanaka, Maki

    2011-01-01

    As third-party certification has become a prominent governance mechanism, conflicting understandings of it have emerged. Proponents advance third-party certification as a technical and objective governance mechanism, while critics argue that politics and relations of power characterize it. We reject this dichotomization both in terms of how TPC is…

  17. Interim Hanford Waste Management Plan

    International Nuclear Information System (INIS)

    The September 1985 Interim Hanford Waste Management Plan (HWMP) is the third revision of this document. In the future, the HWMP will be updated on an annual basis or as major changes in disposal planning at Hanford Site require. The most significant changes in the program since the last release of this document in December 1984 include: (1) Based on studies done in support of the Hanford Defense Waste Environmental Impact Statement (HDW-EIS), the size of the protective barriers covering contaminated soil sites, solid waste burial sites, and single-shell tanks has been increased to provide a barrier that extends 30 m beyond the waste zone. (2) As a result of extensive laboratory development and plant testing, removal of transuranic (TRU) elements from PUREX cladding removal waste (CRW) has been initiated in PUREX. (3) The level of capital support in years beyond those for which specific budget projections have been prepared (i.e., fiscal year 1992 and later) has been increased to maintain Hanford Site capability to support potential future missions, such as the extension of N Reactor/PUREX operations. The costs for disposal of Hanford Site defense wastes are identified in four major areas in the HWMP: waste storage and surveillance, technology development, disposal operations, and capital expenditures

  18. Spatial planning

    OpenAIRE

    Dimitrov, Nikola; Koteski, Cane

    2016-01-01

    The professional book ,, Space planning "processed chapters on: space, concept and definition of space, space as a system, spatial economics, economic essence of space, space planning, social determinants of spatial planning, spatial planning as a process, factors development and elements in spatial planning, methodology, components and content of spatial planning stages and types of preparation of spatial planning, spatial planning and industrialization, industrialization, urbanization and s...

  19. Integrated tradable green certificate markets: Functioning and compatibility

    Energy Technology Data Exchange (ETDEWEB)

    Amundsen, Eirik S.; Nese, Gjermund

    2005-07-01

    Many countries plan to increase the proportion of their electricity supply obtained from renewable sources relative to nonrenewable sources. Recently, the EU has implemented a system of tradable emission permits and many countries have introduced systems of tradable green certificates (TGCs). In this paper, we analyze how integrated TGC markets function and how they are affected by harsher CO2 emission constraints. A key result of our analytical model is that TGCs may be an imprecise instrument for regulating the generation of green electricity. Furthermore, our analysis shows that the combination of TGCs with a system of tradable emission permits may yield outcomes contrary to the intended purpose. The results are valid under both autarky and international trade. (Author)

  20. Personal Practical Knowledge and Identity in Lesson Planning Conferences on a Pre-Service TESOL Course

    Science.gov (United States)

    Morton, Tom; Gray, John

    2010-01-01

    This article reports a study of the discourse of shared lesson planning sessions in the early stages of a pre-service TESOL certificate course. The study focuses on "lesson planning conferences" (LPCs), in which a teacher educator and a group of student teachers worked on one student teacher's lesson plan. It describes the discursive practices…

  1. Interim status of closure/post-closure plan for 183-H solar evaporation basins

    International Nuclear Information System (INIS)

    This report describes a plan for decommissioning several solar evaporation basins on the Hanford reservation. The document describes procedures for sampling during decommissioning and a plan for certification of the resulting completed landfill. Additional plans deal with the training, security of the site, and post-closure monitoring

  2. ISO and software quality assurance - licensing and certification of software professionals

    Energy Technology Data Exchange (ETDEWEB)

    Hare, J.; Rodin, L.

    1997-11-01

    This report contains viewgraphs on licensing and certifing of software professionals. Discussed in this report are: certification programs; licensing programs; why became certified; certification as a condition of empolyment; certification requirements; and examination structures.

  3. 78 FR 64141 - 30-Day Notice of Proposed Information Collection: Certificate of Housing Counseling...

    Science.gov (United States)

    2013-10-25

    ... Collection: Certificate of Housing Counseling: Homeownership and Certificate of Housing Counseling: Home... Counseling: Homeownership and Certificate of Housing Counseling: Home Retention. OMB Approval Number: 2502... Information and Proposed Use: Counseling certificates will provide proof to lenders and other...

  4. Council on Certification Professional Practice Analysis.

    Science.gov (United States)

    Zaglaniczny, K L

    1993-06-01

    The CCNA has completed a PPA and will begin implementing its recommendations with the December 1993 certification examination. The results of the PPA provide content validation for the CCNA certification examination. The certification examination is reflective of the knowledge and skill required for entry-level practice. Assessment of this knowledge is accomplished through the use of questions that are based on the areas represented in the content outline. Analysis of the PPA has resulted in changes in the examination content outline and percentages of questions in each area to reflect current entry-level nurse anesthesia practice. The new outline is based on the major domains of knowledge required for nurse anesthesia practice. These changes are justified by the consistency in the responses of the practitioners surveyed. There was overall agreement as to the knowledge and skills related to patient conditions, procedures, agents, techniques, and equipment that an entry-level CRNA must have to practice. Members of the CCNA and Examination Committee will use the revised outline to develop questions for the certification examination. The questions will be focused on the areas identified as requiring high levels of expertise and those that appeared higher in frequency. The PPA survey will be used as a basis for subsequent content validation studies. It will be revised to reflect new knowledge, technology, and techniques related to nurse anesthesia practice. The CCNA has demonstrated its commitment to the certification process through completion of the PPA and implementation of changes in the structure of the examination. PMID:8291387

  5. Obtaining your annual internal taxation certificate

    CERN Multimedia

    2006-01-01

    (cf. Article R IV 2.04 of the Staff Regulations) Your annual internal taxation certificate will state the taxable amount of your CERN remuneration, payments and other financial benefits and the amount of tax levied by the Organization during the previous financial year. In France, your tax return must be accompanied by this certificate. Current Members of the Personnel (including Members of the Personnel participating in a pre-retirement programme): - You will receive an e-mail containing a link to your printable annual certificate, which will be stored together with your pay and leave statements (e-Payslips). - You can also access your annual certificate via https://hrt.cern.ch (open 'My Payslips' at the bottom of the main menu.) - If you experience any technical difficulties in accessing your annual certificate (e.g. invalid AIS login or password), please contact CERN's AIS support team at ais.support@cern.ch. Former Members of the Personnel:- If you remember your AIS login and password, you can acc...

  6. Council on Certification Professional Practice Analysis.

    Science.gov (United States)

    Zaglaniczny, K L

    1993-06-01

    The CCNA has completed a PPA and will begin implementing its recommendations with the December 1993 certification examination. The results of the PPA provide content validation for the CCNA certification examination. The certification examination is reflective of the knowledge and skill required for entry-level practice. Assessment of this knowledge is accomplished through the use of questions that are based on the areas represented in the content outline. Analysis of the PPA has resulted in changes in the examination content outline and percentages of questions in each area to reflect current entry-level nurse anesthesia practice. The new outline is based on the major domains of knowledge required for nurse anesthesia practice. These changes are justified by the consistency in the responses of the practitioners surveyed. There was overall agreement as to the knowledge and skills related to patient conditions, procedures, agents, techniques, and equipment that an entry-level CRNA must have to practice. Members of the CCNA and Examination Committee will use the revised outline to develop questions for the certification examination. The questions will be focused on the areas identified as requiring high levels of expertise and those that appeared higher in frequency. The PPA survey will be used as a basis for subsequent content validation studies. It will be revised to reflect new knowledge, technology, and techniques related to nurse anesthesia practice. The CCNA has demonstrated its commitment to the certification process through completion of the PPA and implementation of changes in the structure of the examination.

  7. Waste certification: Who really is on first?

    Energy Technology Data Exchange (ETDEWEB)

    Smith, M.A. [Oak Ridge National Lab., TN (United States)

    1989-11-01

    Waste certification is the process of stating whether or not a given waste package meets the acceptance criteria of whatever facility is receiving the package. Establishing a program for certification of low-level waste requires coordination of a variety of requirements and limitations, including regulations, physical characteristics of the waste and of the type of radiation emitted by radionuclides in the waste, uncertainty in measurements, quality assurance, and personnel exposures. The goal of such a program must be to provide an acceptable degree of assurance that the waste generating facility will be able to convince the waste receiving facility that individual waste packages do meet the applicable waste acceptance criteria. The preceding paragraph raises many questions: what is an acceptable degree of assurance? What does one have to do to convince a receiving facility? How can the measurement uncertainty be taken into account? This paper attempts to address several of those questions in the context of the development being done in the solid low-level waste (SLLW) certification program at the Oak Ridge National Laboratory (ORNL). First, a brief history of the SLLW certification program at ORNL is presented. The remaining discussions are devoted to considering the problems and pitfalls of implementing a waste certification program, concentrating on such areas as the responsibilities of various organizations and individuals, waste characterization techniques, handling levels of uncertainty, and development of waste acceptance criteria.

  8. Universally composable anonymous Hash certification model

    Institute of Scientific and Technical Information of China (English)

    ZHANG Fan; MA JianFeng; SangJae MOON

    2007-01-01

    Ideal function is the fundamental component in the universally composable security model. However, the certification ideal function defined in the universally composable security model realizes the identity authentication by binding identity to messages and the signature, which fails to characterize the special security requirements of anonymous authentication with other kind of certificate. Therefore,inspired by the work of Marten, an anonymous hash certification ideal function and a more universal certificate CA model are proposed in this paper. We define the security requirements and security notions for this model in the framework of universal composable security and prove in the plain model (not in the random-oracle model) that these security notions can be achieved using combinations of a secure digital signature scheme, a symmetrical encryption mechanism, a family of pseudorandom functions, and a family of one-way collision-free hash functions. Considering the limitation of wireless environment and computation ability of wireless devices, this anonymous Hash certification ideal function is realized by using symmetry primitives.

  9. Waste Management Program management plan. Revision 1

    International Nuclear Information System (INIS)

    As the prime contractor to the Department of Energy Idaho Operations Office (DOE-ID), Lockheed Martin Idaho Technologies Company (LMITCO) provides comprehensive waste management services to all contractors at the Idaho National Engineering and Environmental Laboratory (INEEL) through the Waste Management (WM) Program. This Program Management Plan (PMP) provides an overview of the Waste Management Program objectives, organization and management practices, and scope of work. This document will be reviewed at least annually and updated as needed to address revisions to the Waste Management's objectives, organization and management practices, and scope of work. Waste Management Program is managed by LMITCO Waste Operations Directorate. The Waste Management Program manages transuranic, low-level, mixed low-level, hazardous, special-case, and industrial wastes generated at or transported to the INEEL

  10. C-tank transfers: Transuranic sludge removal from the C-1, C-2, and W-23 waste storage tanks at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    Two fluidic pulse jet mixing systems were used to successfully mobilize remote-handled transuranic sludge for retrieval from three 50,000-gal horizontal waste storage tanks at Oak Ridge National Laboratory (ORNL). The results of this operation indicate that the pulse jet system should be considered for mixing and bulk retrieval of sludges in other vertical and horizontal waste tanks at ORNL and at other U.S. Department of Energy sites

  11. C-tank transfers: Transuranic sludge removal from the C-1, C-2, and W-23 waste storage tanks at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    Energy Technology Data Exchange (ETDEWEB)

    Dahl, T.L.; Lay, A.C.; Taylor, S.A.; Moore, J.W.

    1999-05-01

    Two fluidic pulse jet mixing systems were used to successfully mobilize remote-handled transuranic sludge for retrieval from three 50,000-gal horizontal waste storage tanks at Oak Ridge National Laboratory (ORNL). The results of this operation indicate that the pulse jet system should be considered for mixing and bulk retrieval of sludges in other vertical and horizontal waste tanks at ORNL and at other U.S. Department of Energy sites.

  12. Transuranic material recovery in the Integral Fast Reactor fuel cycle demonstration

    International Nuclear Information System (INIS)

    The Integral Fast Reactor is an innovative liquid metal reactor concept that is being developed by Argonne National Laboratory. It takes advantage of the properties of metallic fuel and liquid metal cooling to offer significant improvements in reactor safety, operation, fuel cycle economics, environmental protection, and safeguards. The plans for demonstrating the IFR fuel cycle, including its waste processing options, by processing irradiated fuel from the Experimental Breeder Reactor-II fuel in its associated Fuel Cycle Facility have been developed for the first refining series. This series has been designed to provide the data needed for the further development of the IFR program. An important piece of the data needed is the recovery of TRU material during the reprocessing and waste operations

  13. The transition of the national certification examination from paper and pencil to computer adaptive testing.

    Science.gov (United States)

    Zaglaniczny, K L

    1996-02-01

    The Council on Certification of Nurse Anesthetists (CCNA) has been exploring computerized adaptive testing (CAT) for the national certification examination (NCE) over the past several years. CCNA representatives have consulted with experts in testing and with individuals from professional associations who use CAT for certification or licensure testing. This article will provide an overview of CAT and discuss how the CCNA plans to implement CAT for the NCE beginning April 8, 1996. A future article that explains the theoretical concepts of CAT will be published in the April 1996 AANA Journal. It is important to note that the NCE will not be a new test, the current content outline and item bank will remain the same. It is only the method of test administration that is changed--from paper and pencil to CAT. Each candidate will answer questions and take a test that is individualized to his or her ability or competence level and meets the specifications of the test outline. All candidates must achieve the same passing score. The implementation of CAT for the NCE will be advantageous for the candidates and provide a more efficient competency assessment. The last paper and pencil examination was administered on December 9, 1995. The transition is a significant event in nurse anesthesia history, just as nurse anesthesia was the first advanced practice nursing specialty to implement the certification credential, the CCNA will be the first to introduce CAT. PMID:8928607

  14. The transition of the national certification examination from paper and pencil to computer adaptive testing.

    Science.gov (United States)

    Zaglaniczny, K L

    1996-02-01

    The Council on Certification of Nurse Anesthetists (CCNA) has been exploring computerized adaptive testing (CAT) for the national certification examination (NCE) over the past several years. CCNA representatives have consulted with experts in testing and with individuals from professional associations who use CAT for certification or licensure testing. This article will provide an overview of CAT and discuss how the CCNA plans to implement CAT for the NCE beginning April 8, 1996. A future article that explains the theoretical concepts of CAT will be published in the April 1996 AANA Journal. It is important to note that the NCE will not be a new test, the current content outline and item bank will remain the same. It is only the method of test administration that is changed--from paper and pencil to CAT. Each candidate will answer questions and take a test that is individualized to his or her ability or competence level and meets the specifications of the test outline. All candidates must achieve the same passing score. The implementation of CAT for the NCE will be advantageous for the candidates and provide a more efficient competency assessment. The last paper and pencil examination was administered on December 9, 1995. The transition is a significant event in nurse anesthesia history, just as nurse anesthesia was the first advanced practice nursing specialty to implement the certification credential, the CCNA will be the first to introduce CAT.

  15. Effect of Burnable Absorbers on Inert Matrix Fuel Performance and Transuranic Burnup in a Low Power Density Light-Water Reactor

    Directory of Open Access Journals (Sweden)

    Geoff Recktenwald

    2013-04-01

    Full Text Available Zirconium dioxide has received particular attention as a fuel matrix because of its ability to form a solid solution with transuranic elements, natural radiation stability and desirable mechanical properties. However, zirconium dioxide has a lower coefficient of thermal conductivity than uranium dioxide and this presents an obstacle to the deployment of these fuels in commercial reactors. Here we show that axial doping of a zirconium dioxide based fuel with erbium reduces power peaking and fuel temperature. Full core simulations of a modified AP1000 core were done using MCNPX 2.7.0. The inert matrix fuel contained 15 w/o transuranics at its beginning of life and constituted 28% of the assemblies in the core. Axial doping reduced power peaking at startup by more than ~23% in the axial direction and reduced the peak to average power within the core from 1.80 to 1.44. The core was able to remain critical between refueling while running at a simulated 2000 MWth on an 18 month refueling cycle. The results show that the reactor would maintain negative core average reactivity and void coefficients during operation. This type of fuel cycle would reduce the overall production of transuranics in a pressurized water reactor by 86%.

  16. 7 CFR 205.405 - Denial of certification.

    Science.gov (United States)

    2010-01-01

    ... Agriculture Regulations of the Department of Agriculture (Continued) AGRICULTURAL MARKETING SERVICE (Standards, Inspections, Marketing Practices), DEPARTMENT OF AGRICULTURE (CONTINUED) ORGANIC FOODS PRODUCTION ACT PROVISIONS NATIONAL ORGANIC PROGRAM Certification § 205.405 Denial of certification. (a) When the...

  17. 7 CFR 205.406 - Continuation of certification.

    Science.gov (United States)

    2010-01-01

    ... Agriculture Regulations of the Department of Agriculture (Continued) AGRICULTURAL MARKETING SERVICE (Standards, Inspections, Marketing Practices), DEPARTMENT OF AGRICULTURE (CONTINUED) ORGANIC FOODS PRODUCTION ACT PROVISIONS NATIONAL ORGANIC PROGRAM Certification § 205.406 Continuation of certification. (a) To...

  18. 7 CFR 205.401 - Application for certification.

    Science.gov (United States)

    2010-01-01

    ... Agriculture Regulations of the Department of Agriculture (Continued) AGRICULTURAL MARKETING SERVICE (Standards, Inspections, Marketing Practices), DEPARTMENT OF AGRICULTURE (CONTINUED) ORGANIC FOODS PRODUCTION ACT PROVISIONS NATIONAL ORGANIC PROGRAM Certification § 205.401 Application for certification. A person...

  19. 75 FR 44760 - Export Trade Certificate of Review

    Science.gov (United States)

    2010-07-29

    ... Trade Certificate of Review to Saintilien Enterprise Inc., doing business as Saintilien Global Services... ] Export Trade Certificate of Review to Saintilien Enterprise Inc., doing business as Saintilien Global... state and federal programs; foreign trade and business protocol; consulting; market research...

  20. 30 CFR 905.955 - Certification of blasters.

    Science.gov (United States)

    2010-07-01

    ... PROGRAMS FOR THE CONDUCT OF SURFACE MINING OPERATIONS WITHIN EACH STATE CALIFORNIA § 905.955 Certification... Indian Lands, shall apply to the training, examinatioin and certification of blasters for surface...

  1. 77 FR 21969 - Export Trade Certificate of Review

    Science.gov (United States)

    2012-04-12

    ... International Trade Administration Export Trade Certificate of Review ACTION: Notice of Application for an... Company Affairs (``ETCA'') unit, Office of Competition and Economic Analysis, International Trade Administration, Department of Commerce, has received an application for an Export Trade Certificate of...

  2. 21 CFR 1314.40 - Self-certification.

    Science.gov (United States)

    2010-04-01

    ... CHEMICAL PRODUCTS Sales by Regulated Sellers § 1314.40 Self-certification. (a) A regulated seller must.... The expiration date of the self-certification for all regulated sellers in any group will be the...

  3. Suggestions for the"Integration in Multiple Certificates"Curriculum System Construction

    Institute of Scientific and Technical Information of China (English)

    赵平

    2014-01-01

    Business English professional"Integration in Multiple Certificates"refers to these two kinds of certificates-a diploma and vocational certificates. Business English curriculum design unified vocational qualification certificate with professional training objectives. Basis on the meeting of requirements of certificates for graduation, making professional training contents, curriculum, teaching methods together with vocational training and the requirements of professional qualification certificates.

  4. Distributed certification application via a trusted dealer

    Institute of Scientific and Technical Information of China (English)

    刘端阳; 潘雪增; 平玲娣

    2003-01-01

    Distributed certification via threshold cryptography is much more secure than other ways to protect certification authority (CA) 's private key, and can tolerate some intrusions. As the original system such as ITTC, etc., is unsafe, inefficient and impracitcal in actual network environment, this paper brings up a new distributed certification scheme, which although it generates key shares concentratively, it updates key shares distributedly, and so, avoids single-point failure like ITTC. It not only enhances robustness with Feldman verification and SSL protocol, but can also change the threshold (t,k) flexibly and robustly, and so, is much more practical. In this work, the authors implement the prototype system of the new scheme and test and analyze its performance.

  5. Distributed certification application via a trusted dealer

    Institute of Scientific and Technical Information of China (English)

    刘端阳; 潘雪增; 平玲娣

    2003-01-01

    Distributed certification via threshold cryptography is much more secure than other ways to protect certification authority (CA) 's private key, and can tolerate some intrusions. As the original system such as ITTC, etc. , is unsafe, inefficient and impracitcal in actual network environment, this paper brings up a new distributed certification scheme, which although it generates key shares concentratively, it updates key shares distributedly, and so, avoids single-point failure like ITYC. It not only enhances robustness with Feldman verification and SSL protocol, but can also change the threshold ( t, k ) flexibly and robustly, and so, is muc hmore practical. In this work, the authors implement the prototype system of the new scheme and test and analyze its performance.

  6. Facility certification program for coal miners pneumoconiosis

    International Nuclear Information System (INIS)

    Public Law 91-173, often referred to as the Black Lung Law, called for a chest radiograph of all active coal miners at stated intervals. The National Institute for Occupational Safety and Health was responsible for carrying out the provisions of the law. Among other requirements was a provision for certification of radiological facilities where radiological examinations would be provide. A test object to be radiographed by each such facility was designed and sent to those facilities applying for certification. To date, 284 facilities have applied for certification of which 215 have been approved. A record has been kept of the number of times any approved facility submitted radiographs before approval. A complete listing of the types of equipment used, personnel qualifications and other pertinent data will be reported

  7. BECSI: Bandwidth Efficient Certificate Status Information Distribution Mechanism for VANETs

    OpenAIRE

    Carlos Gañán; Muñoz, Jose L.; Oscar Esparza; Jonathan Loo; Jorge Mata-Díaz; Juanjo Alins

    2013-01-01

    Certificate revocation is a challenging task, especiallyin mobile network environments such as vehicular ad Hoc networks (VANETs).According to the IEEE 1609.2 security standard for VANETs, public keyinfrastructure (PKI) will provide this functionality by means of certificate revocation lists (CRLs).When a certificate authority (CA)needs to revoke a certificate, itglobally distributes CRLs.Transmitting these lists pose a problem as they require high update frequencies and a lot of bandwidth. I...

  8. Introduction of China's Compulsory Product Certification System (Ⅰ)

    Institute of Scientific and Technical Information of China (English)

    2004-01-01

    @@ Why does China establish a new Compulso-ry Product Certification System? For a long time, our compulsory product certification system has had problems such as lack of a unified management department, repeated assessments,repeated charging and no separation between certification activities and behaviors of law enforcement.The most obvious problem is that two certification management systems exist respectively for domestic products and imported products.

  9. Performance of Transuranic-Loaded Fully Ceramic Micro-Encapsulated Fuel in LWRs Final Report, Including Void Reactivity Evaluation

    Energy Technology Data Exchange (ETDEWEB)

    Michael A. Pope; R. Sonat Sen; Brian Boer; Abderrafi M. Ougouag; Gilles Youinou

    2011-09-01

    The current focus of the Deep Burn Project is on once-through burning of transuranics (TRU) in light-water reactors (LWRs). The fuel form is called Fully-Ceramic Micro-encapsulated (FCM) fuel, a concept that borrows the tri-isotropic (TRISO) fuel particle design from high-temperature reactor technology. In the Deep Burn LWR (DB-LWR) concept, these fuel particles are pressed into compacts using SiC matrix material and loaded into fuel pins for use in conventional LWRs. The TRU loading comes from the spent fuel of a conventional LWR after 5 years of cooling. Unit cell and assembly calculations have been performed using the DRAGON-4 code to assess the physics attributes of TRU-only FCM fuel in an LWR lattice. Depletion calculations assuming an infinite lattice condition were performed with calculations of various reactivity coefficients performed at each step. Unit cells and assemblies containing typical UO2 and mixed oxide (MOX) fuel were analyzed in the same way to provide a baseline against which to compare the TRU-only FCM fuel. Then, assembly calculations were performed evaluating the performance of heterogeneous arrangements of TRU-only FCM fuel pins along with UO2 pins.

  10. Tritium Packages and 17th RH Canister Categories of Transuranic Waste Stored Below Ground within Area G

    Energy Technology Data Exchange (ETDEWEB)

    Hargis, Kenneth Marshall [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2015-03-01

    A large wildfire called the Las Conchas Fire burned large areas near Los Alamos National Laboratory (LANL) in 2011 and heightened public concern and news media attention over transuranic (TRU) waste stored at LANL’s Technical Area 54 (TA-54) Area G waste management facility. The removal of TRU waste from Area G had been placed at a lower priority in budget decisions for environmental cleanup at LANL because TRU waste removal is not included in the March 2005 Compliance Order on Consent (Reference 1) that is the primary regulatory driver for environmental cleanup at LANL. The Consent Order is a settlement agreement between LANL and the New Mexico Environment Department (NMED) that contains specific requirements and schedules for cleaning up historical contamination at the LANL site. After the Las Conchas Fire, discussions were held by the U.S. Department of Energy (DOE) with the NMED on accelerating TRU waste removal from LANL and disposing it at the Waste Isolation Pilot Plant (WIPP). This report summarizes available information on the origin, configuration, and composition of the waste containers within the Tritium Packages and 17th RH Canister categories; their physical and radiological characteristics; the results of the radioassays; and potential issues in retrieval and processing of the waste containers.

  11. Removal of strontium and transuranics from Hanford waste via hydrothermal processing -- FY 1994/95 test results

    International Nuclear Information System (INIS)

    Under the Tank Waste Remediation System (TWRS) Pretreatment Technology Development Project, Pacific Northwest Laboratory (PNL) is evaluating and developing organic destruction technologies that may be incorporated into the Initial Pretreatment Module (IPM) to treat Hanford tank waste. Organic (and ferrocyanide) destruction removes the compounds responsible for waste safety issues, and conditions the supernatant for low-level waste disposal by removing compounds that may be responsible for promoting strontium and transuranic (TRU) components solubility. Destruction or defunctionalization of complexing organics in tank wastes eliminates organic species that can reduce the efficiency of radionuclide (E.g., 90Sr) separation processes, such as ion exchange, solvent extraction, and precipitation. The technologies being evaluated and tested for organic destruction are low-temperature hydrothermal processing (HTP) and wet air oxidation (WAO). Four activities are described: Batch HTP/WAO testing with Actual Tank Waste (Section 3.0), Batch HTP Testing with Simulant (Section 4.0), Batch WAO testing with Simulant (Section 5.0), and Continuous Bench-scale WAO Testing with Simulant (Section 6.0). For each of these activities, the objectives, test approach, results, status, and direction of future investigations are discussed. The background and history of the HTP/WAO technology is summarized below. Conclusions and Recommendations are provided in Section 2.0. A continuous HTP off-gas safety evaluation conducted in FY 1994 is included as Appendix A

  12. Improved Hydrogen Gas Getters for TRU Waste Transuranic and Mixed Waste Focus Area - Phase 2 Final Report

    Energy Technology Data Exchange (ETDEWEB)

    Stone, Mark Lee

    2002-04-01

    Alpha radiolysis of hydrogenous waste and packaging materials generates hydrogen gas in radioactive storage containers. For that reason, the Nuclear Regulatory Commission (NRC) limits the flammable gas (hydrogen) concentration in the Transuranic Package Transporter-II (TRUPACT-II) containers to 5 vol% of hydrogen in air, which is the lower explosion limit. Consequently, a method is needed to prevent the build up of hydrogen to 5 vol% during the storage and transport of the TRUPACT-II containers (up to 60 days). One promising option is the use of hydrogen getters. These materials scavenge hydrogen from the gas phase and irreversibly bind it in the solid phase. One proven getter is a material called 1,4-bis (phenylethynyl) benzene, or DEB. It has the needed binding rate and capacity, but some of the chemical species that might be present in the containers could interfere with its ability to remove hydrogen. This project is focused upon developing a protective polymeric membrane coating for the DEB getter material, which comes in the form of small, irregularly shaped particles. This report summarizes the experimental results of the second phase of the development of the materials.

  13. An Investigation of the Use of Fully Ceramic Microencapsulated Fuel for Transuranic Waste Recycling in Pressurized Water Reactors

    Energy Technology Data Exchange (ETDEWEB)

    Gentry, Cole A [ORNL; Godfrey, Andrew T [ORNL; Terrani, Kurt A [ORNL; Gehin, Jess C [ORNL; Powers, Jeffrey J [ORNL; Maldonado, G Ivan [ORNL

    2014-01-01

    An investigation of the utilization of TRistructural- ISOtropic (TRISO)-coated fuel particles for the burning of plutonium/neptunium (Pu/Np) isotopes in typical Westinghouse four-loop pressurized water reactors is presented. Though numerous studies have evaluated the burning of transuranic isotopes in light water reactors (LWRs), this work differentiates itself by employing Pu/Np-loaded TRISO particles embedded within a silicon carbide (SiC) matrix and formed into pellets, constituting the fully ceramic microencapsulated (FCM) fuel concept that can be loaded into standard LWR fuel element cladding. This approach provides the capability of Pu/Np burning and, by virtue of the multibarrier TRISO particle design and SiC matrix properties, will allow for greater burnup of Pu/Np material, plus improved fuel reliability and thermal performance. In this study, a variety of heterogeneous assembly layouts, which utilize a mix of FCM rods and typical UO2 rods, and core loading patterns were analyzed to demonstrate the neutronic feasibility of Pu/Np-loaded TRISO fuel. The assembly and core designs herein reported are not fully optimized and require fine-tuning to flatten power peaks; however, the progress achieved thus far strongly supports the conclusion that with further rod/assembly/core loading and placement optimization, Pu/Np-loaded TRISO fuel and core designs that are capable of balancing Pu/Np production and destruction can be designed within the standard constraints for thermal and reactivity performance in pressurized water reactors.

  14. An overview of the waste handling and packaging plant, a major processing facility for remote-handled transuranic waste

    International Nuclear Information System (INIS)

    The Waste Handling and Packaging Plant (WHPP) is a FY 1991 line item project proposed for construction at the Oak Ridge National Laboratory (ORNL). The purpose of the facility is to receive, package, certify and ship remote-handled (RH) and special case (SC) transuranic (TRU) waste to the Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico. The scope of the facility includes the mobilization of liquids and sludges from the Melton Valley Storage Tanks, transport of these liquids and sludges to the WHPP, solidification to a certifiable waste form, and final packaging and shipment to WIPP. Various solid hot cell wastes will be received at the WHPP from storage at ORNL and from other Department of Energy (DOE) sites. The solid wastes will be removed from the storage or shipping container, examined, processed as required, certified and packaged for shipment to WIPP. All packages coming from the processing cell will be in 55 gallon drums, and the facility will have the capability to load these directly into a shielded drum shipping cask, or to load these into the RH TRU canister for remote welding and shipment to WIPP using the RH TRU canister cask. 4 figs

  15. Compositional Safety Analysis using Barrier Certificates

    DEFF Research Database (Denmark)

    Sloth, Christoffer; Pappas, George J.; Wisniewski, Rafael

    2012-01-01

    This paper proposes a compositional method for verifying the safety of a dynamical system, given as an interconnection of subsystems. The safety verification is conducted by the use of the barrier certificate method; hence, the contribution of this paper is to show how to obtain compositional...... conditions for safety verification. We show how to formulate the verification problem, as a composition of coupled subproblems, each given for one subsystem. Furthermore, we show how to find the compositional barrier certificates via linear and sum of squares programming problems. The proposed method makes...

  16. Consensus recommendations on rater training and certification.

    Science.gov (United States)

    West, Mark D; Daniel, David G; Opler, Mark; Wise-Rankovic, Alexandria; Kalali, Amir

    2014-01-01

    There is currently no accepted standard for the clinical research industry to follow when selecting and training raters to administer rating scales in clinical neuroscience trials. This article offers guidelines, based on expert recommendations of the CNS Summit Rater Training and Certification Committee, for selecting, training, and evaluating raters. The article also defines terminology and offers recommendations for considering raters with prior training and certification. These guidelines are intended for investigators, pharmaceutical companies, contract research organizations, and other entities involved in clinical neuroscience trials.

  17. Certification of qualification of radioprotection supervisors

    International Nuclear Information System (INIS)

    In the scope of the process adopted by CNEN to certification of radiation protection supervisors, are discussed important items, such as: definition of new areas of expertise, training programs, communication between the CNEN and stakeholders knowledge exams, standardization, desirable profile and responsibilities related to the performance of supervisors, considering its importance in safety and radiological protection of occupationally exposed individuals and the public. Taking into account the needs and particularities of each area, are presented the perspectives of the procedure for certification of qualification, and suggested improvements to be introduced

  18. Who Owns Renewable Energy Certificates?

    Energy Technology Data Exchange (ETDEWEB)

    Holt, Edward; Wiser, Ryan; Bolinger, Mark

    2006-06-01

    Renewable energy certificates (RECs) are tradable instruments that convey the attributes of a renewable energy generator and the right to make certain claims about energy purchases. RECs first appeared in US markets in the late 1990s and are particularly important in states that accept or require them as evidence of compliance with renewables portfolio standards (RPS). The emergence of RECs as a tradable commodity has made utilities, generators, and regulators increasingly aware of the need to specify who owns the RECs in energy transactions. In voluntary transactions, most agree that the question of REC ownership can and should be negotiated privately between the buyer and the seller, and should be clearly established by contract. Claims about purchasing or using renewable energy should only be made if REC ownership can be documented. In many other cases, however, renewable energy transactions are either mandated or encouraged through state or federal policy. Because of the recent appearance of RECs, legislation and regulation mandating the purchase of renewable energy has sometimes been silent on the disposition of the RECs associated with that generation. Furthermore, some renewable energy contracts pre-date the existence of RECs, and therefore do not address REC ownership. In both of these instances, the issue of REC ownership must often be answered by legislative or regulatory authorities. The resulting uncertainty in REC ownership has hindered the development of robust REC markets and has, in some cases, led to contention between buyers and sellers of renewable generation. This article, which is based on a longer Berkeley Lab report, reviews federal and state efforts to clarify the ownership of RECs from Qualifying Facilities (QFs) that sell their generation under the Public Utility Regulatory Policies Act (PURPA) of 1978. The full report also addresses state efforts to clarify REC ownership in two other situations, customer-owned generation that benefits

  19. The Role of Logging Business Owners in Forest Certification

    OpenAIRE

    Barrett, Scott Michael; Munsell, John F; Gagnon, Jennifer L.

    2013-01-01

    Many forest products companies and landowners participate in forest certification programs. Forest certification programs set standards for sustainable forest management and verify that they are being met. Participants in certification programs commit to meeting sustainable forest management standards and are periodically audited by a third party to verify compliance.

  20. 25 CFR 152.7 - Application for certificate of competency.

    Science.gov (United States)

    2010-04-01

    ... 25 Indians 1 2010-04-01 2010-04-01 false Application for certificate of competency. 152.7 Section... IN FEE, CERTIFICATES OF COMPETENCY, REMOVAL OF RESTRICTIONS, AND SALE OF CERTAIN INDIAN LANDS Issuing Patents in Fee, Certificates of Competency Or Orders Removing Restrictions § 152.7 Application...

  1. 25 CFR 152.8 - Issuance of certificate of competency.

    Science.gov (United States)

    2010-04-01

    ... 25 Indians 1 2010-04-01 2010-04-01 false Issuance of certificate of competency. 152.8 Section 152... FEE, CERTIFICATES OF COMPETENCY, REMOVAL OF RESTRICTIONS, AND SALE OF CERTAIN INDIAN LANDS Issuing Patents in Fee, Certificates of Competency Or Orders Removing Restrictions § 152.8 Issuance of...

  2. 78 FR 31517 - Export Trade Certificate of Review

    Science.gov (United States)

    2013-05-24

    ... International Trade Administration Export Trade Certificate of Review ACTION: Notice of Issuance of an amended Export Trade Certificate of Review to California Almond Export Association, LLC (``CAEA'') (Application 99-5A002). SUMMARY: The U.S. Department of Commerce issued an amended Export Trade Certificate...

  3. 78 FR 5778 - Export Trade Certificate of Review

    Science.gov (United States)

    2013-01-28

    ... America Inc. (``AIAA'') original Certificate was issued on September 8, 1992 (57 FR 41920, September 14... International Trade Administration Export Trade Certificate of Review ACTION: Notice of Application (92-11A01) to amend the Export Trade Certificate of Review Issued to Aerospace Industries Association of...

  4. 76 FR 10885 - Export Trade Certificate of Review

    Science.gov (United States)

    2011-02-28

    ... International Trade Administration Export Trade Certificate of Review ACTION: Notice of Application ( 11-00001) for an Export Trade Certificate of Review for the Latin American ] Multichannel Advertising Council..., U.S. Department of Commerce, received an application for an Export Trade Certificate of...

  5. 22 CFR 61.4 - Certification procedures-Exports.

    Science.gov (United States)

    2010-04-01

    ... 22 Foreign Relations 1 2010-04-01 2010-04-01 false Certification procedures-Exports. 61.4 Section... AUDIO-VISUAL MATERIALS § 61.4 Certification procedures—Exports. (a) Applicants seeking certification of... accompany each export shipment of the certified material....

  6. 9 CFR 590.402 - Egg products inspection certificates.

    Science.gov (United States)

    2010-01-01

    ... 9 Animals and Animal Products 2 2010-01-01 2010-01-01 false Egg products inspection certificates... AGRICULTURE EGG PRODUCTS INSPECTION INSPECTION OF EGGS AND EGG PRODUCTS (EGG PRODUCTS INSPECTION ACT) Certificates § 590.402 Egg products inspection certificates. (a) Upon request of the applicant or the...

  7. 46 CFR 308.550 - Certificate, Form MA-320.

    Science.gov (United States)

    2010-10-01

    ... 46 Shipping 8 2010-10-01 2010-10-01 false Certificate, Form MA-320. 308.550 Section 308.550... Risk Cargo Insurance Iv-General § 308.550 Certificate, Form MA-320. Wherever any provision of this... execute a certificate on Form MA-320-A for an individual, on Form MA-320-B for a partnership, or on...

  8. PMAA`s Silver/Gold National Certification Program - update

    Energy Technology Data Exchange (ETDEWEB)

    Boltz, R. [Vincent R. Boltz, Inc., Lebanon, PA (United States)

    1996-07-01

    The Petroleum Marketers Association of America`s (PMAA) Silver/Gold National Certification Program is discussed. The oil heat technician certification is a process whose time has come. The information age has put us in an era of improved technology as well as improved equipment. The advantages of the oil heat certification program for oil heat dealers, technicians, and customers are listed.

  9. 19 CFR 10.234 - Certificate of Origin.

    Science.gov (United States)

    2010-04-01

    ... Origin must be prepared by the exporter in the CBTPA beneficiary country. Where the CBTPA beneficiary... 19 Customs Duties 1 2010-04-01 2010-04-01 false Certificate of Origin. 10.234 Section 10.234... Certificate of Origin. A Certificate of Origin as specified in § 10.236 must be employed to certify that...

  10. 7 CFR 966.113 - Registered handler certification.

    Science.gov (United States)

    2010-01-01

    ..., grading, sizing and packing of tomatoes grown in the production area. (b) Application for certification... informed by written notice from the committee. If certification is denied, such denial shall be made by the committee in writing, stating the reasons for denial. (d) A registered handler's certification shall...

  11. 27 CFR 13.41 - Authority to revoke certificates.

    Science.gov (United States)

    2010-04-01

    ... 27 Alcohol, Tobacco Products and Firearms 1 2010-04-01 2010-04-01 false Authority to revoke....41 Authority to revoke certificates. Certificates of label approval, certificates of exemption from... revoked by the appropriate TTB officer upon a finding that the label or bottle at issue is not...

  12. 20 CFR 656.32 - Revocation of approved labor certifications.

    Science.gov (United States)

    2010-04-01

    ... Officer in consultation with the Chief, Division of Foreign Labor Certification may take steps to revoke... Intent to Revoke an approved labor certification which contains a detailed statement of the grounds for... relevant evidence presented in deciding whether to revoke the labor certification. (2) If rebuttal...

  13. 78 FR 36747 - Export Trade Certificate of Review

    Science.gov (United States)

    2013-06-19

    ... Certificate was issued on March 19, 1990 (55 FR 11041, March 26, 1990). A summary of the current application... International Trade Administration Export Trade Certificate of Review ACTION: Notice of Application to amend the Export Trade Certificate of Review Issued to Outdoor Power Equipment Institute, Inc., Application no....

  14. 76 FR 39846 - Export Trade Certificate of Review

    Science.gov (United States)

    2011-07-07

    ...'') original Certificate was issued on May 13, 2010 (75 FR 29514, May 26, 2010). A summary of the current... International Trade Administration Export Trade Certificate of Review ACTION: Notice of application (10-1A001) to Amend the export trade certificate of review issued to alaska longline cod commission,...

  15. 76 FR 63608 - Export Trade Certificate of Review

    Science.gov (United States)

    2011-10-13

    .... (``AIAA'') original Certificate was issued on September 8, 1992 (57 FR 41920, September 14, 1992). A... International Trade Administration Export Trade Certificate of Review ACTION: Notice of Application (92-10A01) to amend the Export Trade Certificate of Review Issued to Aerospace Industries Association of...

  16. 77 FR 28853 - Export Trade Certificate of Review

    Science.gov (United States)

    2012-05-16

    ... Cod Commission's (``ALCC'') original Certificate was issued on May 13, 2010 (75 FR 29514, May 26, 2010... International Trade Administration Export Trade Certificate of Review ACTION: Notice of issuance of an Export....S. Department of Commerce issued an amended Export Trade Certificate of Review Alaska Longline...

  17. 78 FR 62585 - Export Trade Certificate of Review

    Science.gov (United States)

    2013-10-22

    .... original Certificate was issued on March 19, 1990 (55 FR 11041, March 26, 1990). A summary of the current... International Trade Administration Export Trade Certificate of Review ACTION: Notice of Application to amend the Export Trade Certificate of Review Issued to Outdoor Power Equipment Institute, Inc. (Application No....

  18. 29 CFR 825.312 - Fitness-for-duty certification.

    Science.gov (United States)

    2010-07-01

    ... 29 Labor 3 2010-07-01 2010-07-01 false Fitness-for-duty certification. 825.312 Section 825.312... § 825.312 Fitness-for-duty certification. (a) As a condition of restoring an employee whose FMLA leave... provider to provide the information directly to the employer) in the fitness-for-duty certification...

  19. 47 CFR 2.962 - Requirements for Telecommunication Certification Bodies.

    Science.gov (United States)

    2010-10-01

    ... 47 Telecommunication 1 2010-10-01 2010-10-01 false Requirements for Telecommunication Certification Bodies. 2.962 Section 2.962 Telecommunication FEDERAL COMMUNICATIONS COMMISSION GENERAL FREQUENCY... Telecommunication Certification Bodies (tcbs) § 2.962 Requirements for Telecommunication Certification Bodies....

  20. 45 CFR 170.450 - EHR module testing and certification.

    Science.gov (United States)

    2010-10-01

    ... (as defined in 45 CFR 170.102), and one or more of the constituent EHR Modules is/are demonstrably... 45 Public Welfare 1 2010-10-01 2010-10-01 false EHR module testing and certification. 170.450... CERTIFICATION PROGRAMS FOR HEALTH INFORMATION TECHNOLOGY Temporary Certification Program for HIT § 170.450...

  1. 22 CFR 92.34 - Fastening certificate to instrument.

    Science.gov (United States)

    2010-04-01

    ... 22 Foreign Relations 1 2010-04-01 2010-04-01 false Fastening certificate to instrument. 92.34... SERVICES Specific Notarial Acts § 92.34 Fastening certificate to instrument. The proper place for the certificate of acknowledgment is after the signature of the parties to the instrument. If the instrument is...

  2. 33 CFR 138.90 - Individual and Fleet Certificates.

    Science.gov (United States)

    2010-07-01

    ... 33 Navigation and Navigable Waters 2 2010-07-01 2010-07-01 false Individual and Fleet Certificates... for Water Pollution (Vessels) § 138.90 Individual and Fleet Certificates. (a) The Director, NPFC... provided and appropriate fees have been paid, except where a Fleet Certificate is issued under this...

  3. 29 CFR 102.115 - Certification of papers and documents.

    Science.gov (United States)

    2010-07-01

    ... 29 Labor 2 2010-07-01 2010-07-01 false Certification of papers and documents. 102.115 Section 102... Certification and Signature of Documents § 102.115 Certification of papers and documents. The executive... Board in his place and stead shall certify copies of all papers and documents which are a part of any...

  4. 46 CFR 154.1803 - Expiration of Certificates of Compliance.

    Science.gov (United States)

    2010-10-01

    ... 46 Shipping 5 2010-10-01 2010-10-01 false Expiration of Certificates of Compliance. 154.1803 Section 154.1803 Shipping COAST GUARD, DEPARTMENT OF HOMELAND SECURITY (CONTINUED) CERTAIN BULK DANGEROUS... Expiration of Certificates of Compliance. (a) A Certificate of Compliance expires after a period not...

  5. 10 CFR 76.66 - Expiration and termination of certificates.

    Science.gov (United States)

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false Expiration and termination of certificates. 76.66 Section... Certification § 76.66 Expiration and termination of certificates. (a) Except as provided in § 76.55, each... submit a renewal application under § 76.36, the Corporation shall, on or before the expiration...

  6. 14 CFR 121.437 - Pilot qualification: Certificates required.

    Science.gov (United States)

    2010-01-01

    ... 14 Aeronautics and Space 3 2010-01-01 2010-01-01 false Pilot qualification: Certificates required... Pilot qualification: Certificates required. (a) No pilot may act as pilot in command of an aircraft (or... pilots) unless he holds an airline transport pilot certificate and an appropriate type rating for...

  7. 20 CFR 655.1309 - Labor certification determinations.

    Science.gov (United States)

    2010-04-01

    ... the association) must pay in a timely manner a non-refundable fee upon issuance of the certification... certification is granted will be considered timely. Non-payment of fees by the date that is 30 days after the... course of processing the temporary labor certification application, an audit, or otherwise. The number...

  8. 10 CFR 76.45 - Application for amendment of certificate.

    Science.gov (United States)

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false Application for amendment of certificate. 76.45 Section 76.45 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) CERTIFICATION OF GASEOUS DIFFUSION PLANTS Application § 76.45 Application for amendment of certificate. (a) Contents of an amendment application....

  9. Planning Lessons

    Institute of Scientific and Technical Information of China (English)

    Linda Jensen

    2007-01-01

    @@ Jensen's "Lesson Planning"article serves aS a guide fOr novice teachers who need to create formalized lesson plans.The article covers why,when,and how teachers plan lessons,as well aS basic lesson plan principles and a lesson plan template.

  10. Salt Repository Project transportation program plan

    International Nuclear Information System (INIS)

    The Salt Repository Project (SRP) has the responsibility to develop a comprehensive transportation program plan (TrPP) that treats the transportation of workers, supplies, and high-level radioactive waste to the site and the transportation of salt, low-level, and transuranic wastes from the site. The TrPP has developed a systematic approach to transportation which is directed towards satisfying statutes, regulations, and directives and is guided by a hierarchy of specific functional requirements, strategies, plans, and reports. The TrPP identifies and develops the planning process for transportation-related studies and provides guidance to staff in performing and documenting these activities. The TrPP also includes an explanation of the responsibilities of the organizational elements involved in these transportation studies. Several of the report chapters relate to identifying routes for transporting nuclear waste to the site. These include a chapter on identifying an access corridor for a new rail route leading to the site, identifying and evaluating emergency-response preparedness capabilities along candidate routes in the state, and identifying alternative routes from the state border, ports, or in-state reactors to the site. The TrPP also includes plans for identifying salt disposal routes and a discussion of repository/transportation interface requirements. 89 refs., 6 figs

  11. Monitoring Sustainability Certification of Bioenergy: Impacts of sustainability certification on bioenergy markets and trade

    NARCIS (Netherlands)

    Goh, C.S.; Junginger, H.M.; et al,; Goovaerts, L.

    2013-01-01

    At present numerous biomass and biofuel sustainability certification schemes are being developed or implemented by a variety of private and public organisations. Schemes are applicable to different feedstock production sectors (forests, agricultural crops), different bioenergy products (wood chips,

  12. 14 CFR 61.94 - Student pilot seeking a sport pilot certificate or a recreational pilot certificate: Operations...

    Science.gov (United States)

    2010-01-01

    ... 14 Aeronautics and Space 2 2010-01-01 2010-01-01 false Student pilot seeking a sport pilot... Student pilot seeking a sport pilot certificate or a recreational pilot certificate: Operations at... operational control tower in other airspace. (a) A student pilot seeking a sport pilot certificate or...

  13. 42 CFR 493.1775 - Standard: Inspection of laboratories issued a certificate of waiver or a certificate for provider...

    Science.gov (United States)

    2010-10-01

    ... 42 Public Health 5 2010-10-01 2010-10-01 false Standard: Inspection of laboratories issued a... (CONTINUED) STANDARDS AND CERTIFICATION LABORATORY REQUIREMENTS Inspection § 493.1775 Standard: Inspection of laboratories issued a certificate of waiver or a certificate for provider-performed microscopy procedures....

  14. Language Planning: Corpus Planning.

    Science.gov (United States)

    Baldauf, Richard B., Jr.

    1989-01-01

    Focuses on the historical and sociolinguistic studies that illuminate corpus planning processes. These processes are broken down and discussed under two categories: those related to the establishment of norms, referred to as codification, and those related to the extension of the linguistic functions of language, referred to as elaboration. (60…

  15. Directory of certificates of compliance for radioactive materials packages. Certificates of compliance

    International Nuclear Information System (INIS)

    This volume contains all Certificates of Compliance for radioactive material packages effective September 14, 1979. Purpose of this directory is to make available a convenient source of information on packagings which have been approved by the US Nuclear Regulatory Commission. To assist in identifying packaging, an index by Model Number and corresponding Certificate of Compliance number is included at the back of each volume of the directory

  16. Does Eco-certification Stem Tropical Deforestation? Forest Stewardship Council Certification in Mexico

    OpenAIRE

    Blackman, Allen; Goff, Leonard; Planter, Marisol Rivera

    2015-01-01

    Since its creation more than two decades ago as a voluntary market-based approach to improving forest management, forest certification has proliferated rapidly in developing countries. Yet we know little about whether and under what conditions it affects deforestation. We use rich forest management unit-level panel data—including information on deforestation, certification, regulatory permitting, and geophysical and socioeconomic land characteristics—along with matched fixed effects models to...

  17. Directory of certificates of compliance for radioactive materials packages. Certificates of compliance

    Energy Technology Data Exchange (ETDEWEB)

    None

    1979-10-01

    This volume contains all Certificates of Compliance for radioactive material packages effective September 14, 1979. Purpose of this directory is to make available a convenient source of information on packagings which have been approved by the US Nuclear Regulatory Commission. To assist in identifying packaging, an index by Model Number and corresponding Certificate of Compliance number is included at the back of each volume of the directory.

  18. 21 CFR 1010.2 - Certification.

    Science.gov (United States)

    2010-04-01

    ... 21 Food and Drugs 8 2010-04-01 2010-04-01 false Certification. 1010.2 Section 1010.2 Food and Drugs FOOD AND DRUG ADMINISTRATION, DEPARTMENT OF HEALTH AND HUMAN SERVICES (CONTINUED) RADIOLOGICAL HEALTH PERFORMANCE STANDARDS FOR ELECTRONIC PRODUCTS: GENERAL General Provisions § 1010.2...

  19. 40 CFR 82.161 - Technician certification.

    Science.gov (United States)

    2010-07-01

    ... individuals a wallet-sized card to be used as proof of certification, upon successful completion of the test. Programs must issue an identification card to technicians that receive a score of 70 percent or higher on... mail-in format, must issue a permanent identification card to technicians that receive a score of...

  20. 14 CFR 121.378 - Certificate requirements.

    Science.gov (United States)

    2010-01-01

    ... 14 Aeronautics and Space 3 2010-01-01 2010-01-01 false Certificate requirements. 121.378 Section 121.378 Aeronautics and Space FEDERAL AVIATION ADMINISTRATION, DEPARTMENT OF TRANSPORTATION (CONTINUED... REQUIREMENTS: DOMESTIC, FLAG, AND SUPPLEMENTAL OPERATIONS Maintenance, Preventive Maintenance, and...